80_FR_20091 80 FR 20020 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations

80 FR 20020 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 80, Issue 71 (April 14, 2015)

Page Range20020-20031
FR Document2015-08579

Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular biweekly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued from March 19, 2015 to April 1, 2015. The last biweekly notice was published on March 31, 2015.

Federal Register, Volume 80 Issue 71 (Tuesday, April 14, 2015)
[Federal Register Volume 80, Number 71 (Tuesday, April 14, 2015)]
[Notices]
[Pages 20020-20031]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2015-08579]


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NUCLEAR REGULATORY COMMISSION

[NRC-2015-0088]


Biweekly Notice; Applications and Amendments to Facility 
Operating Licenses and Combined Licenses Involving No Significant 
Hazards Considerations

AGENCY: Nuclear Regulatory Commission.

ACTION: Biweekly notice.

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SUMMARY: Pursuant to Section 189a. (2) of the Atomic Energy Act of 
1954, as amended (the Act), the U.S. Nuclear Regulatory Commission 
(NRC) is publishing this regular biweekly notice. The Act requires the 
Commission to publish notice of any amendments issued, or proposed to 
be issued and grants the Commission the authority to issue and make 
immediately effective any amendment to an operating license or combined 
license, as applicable, upon a determination by the Commission that 
such amendment involves no significant hazards consideration, 
notwithstanding the pendency before the Commission of a request for a 
hearing from any person.
    This biweekly notice includes all notices of amendments issued, or 
proposed to be issued from March 19, 2015 to April 1, 2015. The last 
biweekly notice was published on March 31, 2015.

DATES: Comments must be filed by May 14, 2015. A request for a hearing 
must be filed by June 15, 2015.

ADDRESSES: You may submit comments by any of the following methods 
(unless this document describes a different method for submitting 
comments on a specific subject):
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0088. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected].
     Mail comments to: Cindy Bladey, Office of Administration, 
Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Angela Baxter, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 
20555-0001; telephone: 301-415-2976, email: [email protected].

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2015-0088 when contacting the NRC 
about the availability of information for this action. You may obtain 
publicly-available information related to this action by any of the 
following methods:
     Federal rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0088.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to [email protected]. The 
ADAMS accession number for each document referenced (if it is available 
in ADAMS) is provided the first time that it is mentioned in the 
SUPPLEMENTARY INFORMATION section.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

B. Submitting Comments

    Please include Docket ID NRC-2015-0088, facility name, unit 
number(s), application date, and subject in your comment submission.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS.

II. Notice of Consideration of Issuance of Amendments to Facility 
Operating Licenses and Combined Licenses and Proposed No Significant 
Hazards Consideration Determination

    The Commission has made a proposed determination that the following 
amendment requests involve no significant hazards consideration. Under 
the Commission's regulations in Sec.  50.92 of Title 10 of the Code of 
Federal Regulations (10 CFR), this means that operation of the facility 
in accordance with the proposed amendment would not (1) involve a 
significant increase in the probability or consequences of an accident 
previously evaluated, or (2) create the possibility of a new or 
different kind of accident from any accident previously evaluated; or 
(3) involve a significant reduction in a margin of safety. The basis 
for this proposed determination for each amendment request is shown 
below.
    The Commission is seeking public comments on this proposed 
determination. Any comments received within 30 days after the date of 
publication of this notice will be considered in making any final 
determination.
    Normally, the Commission will not issue the amendment until the 
expiration of 60 days after the date of publication of this notice. The 
Commission may issue the license

[[Page 20021]]

amendment before expiration of the 60-day period provided that its 
final determination is that the amendment involves no significant 
hazards consideration. In addition, the Commission may issue the 
amendment prior to the expiration of the 30-day comment period should 
circumstances change during the 30-day comment period such that failure 
to act in a timely way would result, for example in derating or 
shutdown of the facility. Should the Commission take action prior to 
the expiration of either the comment period or the notice period, it 
will publish in the Federal Register a notice of issuance. Should the 
Commission make a final No Significant Hazards Consideration 
Determination, any hearing will take place after issuance. The 
Commission expects that the need to take this action will occur very 
infrequently.

A. Opportunity to Request a Hearing and Petition for Leave to Intervene

    Within 60 days after the date of publication of this notice, any 
person(s) whose interest may be affected by this action may file a 
request for a hearing and a petition to intervene with respect to 
issuance of the amendment to the subject facility operating license or 
combined license. Requests for a hearing and a petition for leave to 
intervene shall be filed in accordance with the Commission's ``Agency 
Rules of Practice and Procedure'' in 10 CFR part 2. Interested 
person(s) should consult a current copy of 10 CFR 2.309, which is 
available at the NRC's PDR, located at One White Flint North, Room O1-
F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. The 
NRC's regulations are accessible electronically from the NRC Library on 
the NRC's Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is 
filed by the above date, the Commission or a presiding officer 
designated by the Commission or by the Chief Administrative Judge of 
the Atomic Safety and Licensing Board Panel, will rule on the request 
and/or petition; and the Secretary or the Chief Administrative Judge of 
the Atomic Safety and Licensing Board will issue a notice of a hearing 
or an appropriate order.
    As required by 10 CFR 2.309, a petition for leave to intervene 
shall set forth with particularity the interest of the petitioner in 
the proceeding, and how that interest may be affected by the results of 
the proceeding. The petition should specifically explain the reasons 
why intervention should be permitted with particular reference to the 
following general requirements: (1) The name, address, and telephone 
number of the requestor or petitioner; (2) the nature of the 
requestor's/petitioner's right under the Act to be made a party to the 
proceeding; (3) the nature and extent of the requestor's/petitioner's 
property, financial, or other interest in the proceeding; and (4) the 
possible effect of any decision or order which may be entered in the 
proceeding on the requestor's/petitioner's interest. The petition must 
also identify the specific contentions which the requestor/petitioner 
seeks to have litigated at the proceeding.
    Each contention must consist of a specific statement of the issue 
of law or fact to be raised or controverted. In addition, the 
requestor/petitioner shall provide a brief explanation of the bases for 
the contention and a concise statement of the alleged facts or expert 
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing. 
The requestor/petitioner must also provide references to those specific 
sources and documents of which the petitioner is aware and on which the 
requestor/petitioner intends to rely to establish those facts or expert 
opinion. The petition must include sufficient information to show that 
a genuine dispute exists with the applicant on a material issue of law 
or fact. Contentions shall be limited to matters within the scope of 
the amendment under consideration. The contention must be one which, if 
proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements with respect to at 
least one contention will not be permitted to participate as a party.
    Those permitted to intervene become parties to the proceeding, 
subject to any limitations in the order granting leave to intervene, 
and have the opportunity to participate fully in the conduct of the 
hearing.
    If a hearing is requested, the Commission will make a final 
determination on the issue of no significant hazards consideration. The 
final determination will serve to decide when the hearing is held. If 
the final determination is that the amendment request involves no 
significant hazards consideration, the Commission may issue the 
amendment and make it immediately effective, notwithstanding the 
request for a hearing. Any hearing held would take place after issuance 
of the amendment. If the final determination is that the amendment 
request involves a significant hazards consideration, then any hearing 
held would take place before the issuance of any amendment unless the 
Commission finds an imminent danger to the health or safety of the 
public, in which case it will issue an appropriate order or rule under 
10 CFR part 2.

B. Electronic Submissions (E-Filing)

    All documents filed in NRC adjudicatory proceedings, including a 
request for hearing, a petition for leave to intervene, any motion or 
other document filed in the proceeding prior to the submission of a 
request for hearing or petition to intervene, and documents filed by 
interested governmental entities participating under 10 CFR 2.315(c), 
must be filed in accordance with the NRC's E-Filing rule (72 FR 49139; 
August 28, 2007). The E-Filing process requires participants to submit 
and serve all adjudicatory documents over the internet, or in some 
cases to mail copies on electronic storage media. Participants may not 
submit paper copies of their filings unless they seek an exemption in 
accordance with the procedures described below.
    To comply with the procedural requirements of E-Filing, at least 
ten 10 days prior to the filing deadline, the participant should 
contact the Office of the Secretary by email at [email protected], 
or by telephone at 301-415-1677, to request (1) a digital 
identification (ID) certificate, which allows the participant (or its 
counsel or representative) to digitally sign documents and access the 
E-Submittal server for any proceeding in which it is participating; and 
(2) advise the Secretary that the participant will be submitting a 
request or petition for hearing (even in instances in which the 
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the 
Secretary will establish an electronic docket for the hearing in this 
proceeding if the Secretary has not already established an electronic 
docket.
    Information about applying for a digital ID certificate is 
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/getting-started.html. System requirements for accessing 
the E-Submittal server are detailed in the NRC's ``Guidance for 
Electronic Submission,'' which is available on the agency's public Web 
site at http://www.nrc.gov/site-help/e-submittals.html. Participants 
may attempt to use other software not listed on the Web site, but 
should note that the NRC's E-Filing system does not support

[[Page 20022]]

unlisted software, and the NRC Meta System Help Desk will not be able 
to offer assistance in using unlisted software.
    If a participant is electronically submitting a document to the NRC 
in accordance with the E-Filing rule, the participant must file the 
document using the NRC's online, Web-based submission form. In order to 
serve documents through the Electronic Information Exchange System, 
users will be required to install a Web browser plug-in from the NRC's 
Web site. Further information on the Web-based submission form, 
including the installation of the Web browser plug-in, is available on 
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
    Once a participant has obtained a digital ID certificate and a 
docket has been created, the participant can then submit a request for 
hearing or petition for leave to intervene. Submissions should be in 
Portable Document Format (PDF) in accordance with NRC guidance 
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the 
documents are submitted through the NRC's E-Filing system. To be 
timely, an electronic filing must be submitted to the E-Filing system 
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of 
a transmission, the E-Filing system time-stamps the document and sends 
the submitter an email notice confirming receipt of the document. The 
E-Filing system also distributes an email notice that provides access 
to the document to the NRC's Office of the General Counsel and any 
others who have advised the Office of the Secretary that they wish to 
participate in the proceeding, so that the filer need not serve the 
documents on those participants separately. Therefore, applicants and 
other participants (or their counsel or representative) must apply for 
and receive a digital ID certificate before a hearing request/petition 
to intervene is filed so that they can obtain access to the document 
via the E-Filing system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System 
Help Desk through the ``Contact Us'' link located on the NRC's public 
Web site at http://www.nrc.gov/site-help/e-submittals.html, by email to 
[email protected], or by a toll-free call at 1-866-672-7640. The 
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., 
Eastern Time, Monday through Friday, excluding government holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, Sixteenth 
Floor, One White Flint North, 11555 Rockville Pike, Rockville, 
Maryland, 20852, Attention: Rulemaking and Adjudications Staff. 
Participants filing a document in this manner are responsible for 
serving the document on all other participants. Filing is considered 
complete by first-class mail as of the time of deposit in the mail, or 
by courier, express mail, or expedited delivery service upon depositing 
the document with the provider of the service. A presiding officer, 
having granted an exemption request from using E-Filing, may require a 
participant or party to use E-Filing if the presiding officer 
subsequently determines that the reason for granting the exemption from 
use of E-Filing no longer exists.
    Documents submitted in adjudicatory proceedings will appear in the 
NRC's electronic hearing docket which is available to the public at 
http://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the 
Commission, or the presiding officer. Participants are requested not to 
include personal privacy information, such as social security numbers, 
home addresses, or home phone numbers in their filings, unless an NRC 
regulation or other law requires submission of such information. 
However, a request to intervene will require including information on 
local residence in order to demonstrate a proximity assertion of 
interest in the proceeding. With respect to copyrighted works, except 
for limited excerpts that serve the purpose of the adjudicatory filings 
and would constitute a Fair Use application, participants are requested 
not to include copyrighted materials in their submission.
    Petitions for leave to intervene must be filed no later than 60 
days from the date of publication of this notice. Requests for hearing, 
petitions for leave to intervene, and motions for leave to file new or 
amended contentions that are filed after the 60-day deadline will not 
be entertained absent a determination by the presiding officer that the 
filing demonstrates good cause by satisfying the three factors in 10 
CFR 2.309(c)(1)(i)-(iii).
    For further details with respect to these license amendment 
applications, see the application for amendment which is available for 
public inspection in ADAMS and at the NRC's PDR. For additional 
direction on accessing information related to this document, see the 
``Obtaining Information and Submitting Comments'' section of this 
document.
Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick 
Generating Station, Units 1 and 2, Montgomery County, Pennsylvania
    Date of amendment request: February 2, 2015. A publicly-available 
version is in ADAMS under Accession No. ML15036A486.
    Description of amendment request: The proposed amendment would 
modify several Technical Specification Limiting Conditions for 
Operation (LCOs) and Surveillance Requirements (SRs) to allow secondary 
containment access openings to be opened intermittently under 
administrative control.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Do the proposed changes involve a significant increase in the 
probability or consequences of an accident previously evaluated?
    Response: No. The proposed changes allow temporary conditions 
during which the secondary containment LCO and SRs are not met. The 
secondary containment is not an initiator of any accident previously 
evaluated. As a result, the probability of any accident previously 
evaluated is not increased. The consequences of an accident 
previously evaluated while utilizing the proposed changes are no 
different than the consequences of an accident while utilizing the 
existing 4-hour allowed outage time for an inoperable reactor 
enclosure secondary containment. As a result, the consequences of an 
accident previously evaluated are not significantly increased.
    Therefore, the proposed changes do not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Do the proposed changes create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No. The proposed changes do not alter the protection 
system design, create

[[Page 20023]]

new failure modes, or change any modes of operation. The proposed 
changes do not involve a physical alteration of the plant, and no 
new or different kind of equipment will be installed. Consequently, 
there are no new initiators that could result in a new or different 
kind of accident.
    Therefore, the proposed changes do not create the possibility of 
a new or different kind of accident from any accident previously 
evaluated.
    3. Do the proposed changes involve a significant reduction in a 
margin of safety?
    Response: No. The proposed changes allow temporary conditions 
during which the secondary containment LCO and SRs are not met. 
Temporary conditions in which the secondary containment vacuum is 
below the required limit are acceptable provided the conditions do 
not affect the ability of the Standby Gas Treatment System to 
establish the required secondary containment vacuum. This condition 
is incorporated in the proposed changes by requiring the condition 
to be momentary or under administrative control such that the 
conditions equivalent to the design condition can be quickly 
restored should secondary containment vacuum be required. Therefore, 
the safety function of the secondary containment is not affected. 
The allowance for both an inner and outer secondary containment 
access door to be open simultaneously for entry and exit does not 
affect the safety function of the secondary containment as the doors 
are promptly closed after entry or exit, thereby restoring the 
secondary containment boundary.
    Therefore, the proposed changes do not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: J. Bradley Fewell, Esquire, Vice President 
and Deputy General Counsel, Exelon Generation Company, LLC, 4300 
Winfield Road, Warrenville, IL 60555.
    NRC Branch Chief: Doulas A. Broaddus.
Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-
277 and 50-278, Peach Bottom Atomic Power Station (PBAPS), Units 2 and 
3, York and Lancaster Counties, Pennsylvania
    Date of amendment request: February 23, 2015. A publicly-available 
version is in ADAMS under Accession No. ML15055A506.
    Description of amendment request: The proposed amendment would 
modify a Technical Specification Limiting Condition for Operation (LCO) 
and certain Surveillance Requirements (SRs) to allow secondary 
containment access openings to be opened intermittently under 
administrative control.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Do the proposed changes involve a significant increase in the 
probability or consequences of an accident previously evaluated?
    Response: No. The proposed changes allow temporary conditions 
during which the secondary containment LCO and certain SRs are not 
met. The secondary containment is not an initiator of any accident 
previously evaluated. As a result, the probability of any accident 
previously evaluated is not increased. The consequences of an 
accident previously evaluated while utilizing the proposed changes 
are no different than the consequences of an accident while 
utilizing the existing 4-hour Completion Time for an inoperable 
secondary containment. As a result, the consequences of an accident 
previously evaluated are not significantly increased.
    Therefore, the proposed changes do not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Do the proposed changes create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No. The proposed changes do not alter the protection 
system design, create new failure modes, or change any modes of 
operation. The proposed changes do not involve a physical alteration 
of the plant; and no new or different kind of equipment will be 
installed. Consequently, there are no new initiators that could 
result in a new or different kind of accident.
    Therefore, the proposed changes do not create the possibility of 
a new or different kind of accident from any accident previously 
evaluated.
    3. Do the proposed changes involve a significant reduction in a 
margin of safety?
    Response: No. The proposed changes allow temporary conditions 
during which the secondary containment LCO and certain SRs are not 
met. Temporary conditions in which the secondary containment is open 
is acceptable provided the conditions do not affect the ability of 
the Standby Gas Treatment System to create a lower pressure in the 
secondary containment than in the outside environment if required. 
This condition is incorporated in the proposed changes by requiring 
the condition to be under administrative control such that the 
conditions equivalent to the design condition can be quickly 
restored should secondary containment vacuum be required. Therefore, 
the safety function of the secondary containment is not affected. 
The allowance for both an inner and outer secondary containment door 
to be open simultaneously for entry and exit does not affect the 
safety function of the secondary containment as the doors are 
promptly closed after entry or exit, thereby restoring the secondary 
containment boundary. The ability to open secondary containment 
access openings under administrative control, even if it means the 
secondary containment boundary is temporarily not intact, is 
acceptable due to the low probability of an event that requires 
secondary containment during the short time in which the secondary 
containment is open and the presence of administrative controls to 
rapidly close the opening.
    Therefore, the proposed changes do not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: J. Bradley Fewell, Esquire, Vice President 
and Deputy General Counsel, Exelon Generation Company, LLC, 4300 
Winfield Road, Warrenville, IL 60555.
    NRC Branch Chief: Douglas A. Broaddus.
    Northern States Power Company--Minnesota, Docket Nos. 50-282 and 
50-306, Prairie Island Nuclear Generating Plant, Units 1 and 2, Goodhue 
County, Minnesota
    Date of amendment request: December 11, 2014. A publicly-available 
version is in ADAMS under Accession No. ML14349A749.
    Brief description of amendment request: The proposed amendments 
would revise the technical specification (TS) 3.3.3, ``EM [Event 
Monitoring] Instrumentation,'' to add the Steam Generator Water Level--
Narrow Range Instruments to Table 3.3.3-1. In addition, the amendments 
would revise Appendix B, ``Additional Condition,'' of the Renewed 
Operating License for each unit regarding implementation of License 
Amendment Nos. 206 (Unit 1) and 193 (Unit 2) for Alternative Source 
Term (AST), and removes two AST Additional Conditions for each unit 
that have been fulfilled.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee provided 
its analysis of the issue of no significant hazards consideration, 
which is presented below:

    1. Do the proposed amendments involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The license amendment requests propose to add Steam Generator 
Water Level (narrow range) Instrumentation to Technical

[[Page 20024]]

Specification Event Monitoring Instrumentation; revise license 
Additional Conditions to exclude Steam Generator Water Level (narrow 
range) Instrument implementation requirements from Alternative 
Source Term license amendment implementation; and remove Alternative 
Source Term amendment implementation Additional Conditions which 
have been fulfilled.
    The Steam Generator Water Level (narrow range) Instrumentation 
is not an accident initiator and therefore addition of this 
instrumentation to the Technical Specifications does not increase 
the probability of an accident. Addition of this instrumentation to 
the Technical Specifications will bring it under the controls and 
testing requirements of the Technical Specifications. The proposed 
change will not increase the consequences of previously-evaluated 
accidents because the inclusion of these instruments in the 
technical specification improves their reliability to perform during 
a postulated accident. Therefore, the proposed Technical 
Specification changes do not involve a significant increase in the 
probability or consequences of an accident previously evaluated.
    The Alternative Source Term license amendment was previously 
analyzed and approved for implementation. The proposed Additional 
Condition revision to exclude Steam Generator Water Level (narrow 
range) Instrumentation implementation requirements from Alternative 
Source Term license amendment implementation clarifies 
implementation requirements and allows completion of implementation 
activities. Since the Alternative Source Term amendment was 
previously approved, this change does not increase the probability 
or consequences of a previously evaluated accident.
    Removal of license Additional Conditions which have been 
fulfilled is an administrative change and thus this change does not 
increase the probability or consequences of a previously evaluated 
accident.
    Therefore, the proposed changes do not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Do the proposed amendments create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The license amendment requests propose to add Steam Generator 
Water Level (narrow range) Instrumentation to Technical 
Specification Event Monitoring Instrumentation; revise license 
Additional Conditions to exclude Steam Generator Water Level (narrow 
range) Instrument implementation requirements from Alternative 
Source Term license amendment implementation; and remove Alternative 
Source Term amendment implementation Additional Conditions which 
have been fulfilled.
    The proposed Technical Specification changes and Additional 
Condition changes and the resulting instrument upgrades do not 
create new failure modes or mechanisms and do not change plant 
conditions from which some new material interaction may create a new 
or different type of accident. Thus, the Technical Specification and 
license Additional Condition changes do not create new failure modes 
or mechanisms, nor do they generate new accident precursors.
    Therefore, the proposed changes do not create the possibility of 
a new or different kind of accident from any previously evaluated.
    The proposed removal of fulfilled Additional Conditions is an 
administrative change and thus does not create the possibility of a 
new or different kind of accident.
    3. Do the proposed amendments involve a significant reduction in 
a margin of safety?
    Response: No.
    The license amendment requests propose to add Steam Generator 
Water Level (narrow range) Instrumentation to Technical 
Specification Event Monitoring Instrumentation; revise license 
Additional Conditions to exclude Steam Generator Water Level (narrow 
range) Instrument implementation requirements from Alternative 
Source Term license amendment implementation; and remove Alternative 
Source Term amendment implementation Additional Conditions which 
have been fulfilled.
    Addition of this instrumentation to the Technical Specifications 
will bring it under the controls and testing requirements of the 
Technical Specifications. The proposed change will not increase the 
consequences of previously evaluated accidents because instrument 
upgrade and the inclusion of these instruments in the Technical 
Specifications improve their reliability to perform during a 
postulated accident.
    Therefore, the proposed changes do not involve a significant 
reduction in a margin of safety.
    The Alternative Source Term license amendment was previously 
analyzed and approved for implementation. The proposed Additional 
Condition revision to exclude Steam Generator Water Level (narrow 
range) Instrumentation implementation requirements from Alternative 
Source Term license amendment implementation clarifies 
implementation requirements and allows completion of implementation 
activities. Since the Alternative Source Term [amendment] was 
previously approved, the changes proposed in this license amendment 
do not involve a significant reduction in a margin of safety.
    The proposed removal of fulfilled Additional Conditions is 
administrative in nature and thus does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment requests involve no significant hazards consideration.
    Attorney for licensee: Peter M. Glass, Assistant General Counsel, 
Xcel Energy Services, Inc., 414 Nicollet Mall, Minneapolis, MN 55401.
    NRC Branch Chief: David L. Pelton.
PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station, 
Unit 1, Salem County, New Jersey
PSEG Nuclear LLC, Docket Nos. 50-272 and 50-311, Salem Nuclear 
Generating Station, Unit Nos. 1 and 2, Salem County, New Jersey
    Date of amendment request: December 9, 2014. A publicly-available 
version is in ADAMS under Accession No. ML14343A926.
    Description of amendment request: The proposed amendments would 
revise the Public Service Electric and Gas Nuclear LLC (PSEG) 
Environmental Protection Plans (Non-Radiological), Appendix B to the 
renewed facility operating license (FOL) numbers DPR-70 and DPR-75 for 
Salem Nuclear Generating Station, Units 1 and 2, and the renewed FOL 
number NPF-57 for Hope Creek Generating Station. The proposed changes 
will simplify the Aquatic Monitoring section of Appendix B, modify the 
criteria for reporting Unusual or Important Environmental Events, and 
will clarify that PSEG Nuclear must adhere to the currently applicable 
Biological Opinion.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below, with NRC staff edits in square 
brackets:

    1. Do the proposed changes involve a significant increase in the 
probability or consequences of an accident previously evaluated?
    Response: No.
    The [Environmental Protection Plan] EPP provides for protection 
of non-radiological environmental values during operation of the 
nuclear facility.
    The proposed changes do not have any impact on structures, 
systems and components (SSCs) of the plant, and no effect on plant 
operations. The proposed changes do not impact any accident 
initiators, or analyzed events, or assumed mitigation of accident or 
transient events. The proposed changes do not result in the addition 
or removal of any equipment.
    Therefore, these proposed changes do not represent a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Do the proposed changes create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The proposed changes are administrative in nature and do not 
involve a modification to the physical configuration of the plant

[[Page 20025]]

(i.e., no new equipment will be installed) or change in the methods 
governing normal plant operation. The proposed changes will not 
impose any new or different requirements or introduce a new accident 
initiator, accident precursor, or malfunction mechanism.
    Therefore, the proposed changes do not create the possibility of 
a new or different kind of accident from any accident previously 
evaluated.
    3. Do the proposed changes involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed changes are administrative in nature.
    There is no change to any design basis, licensing basis or 
safety limit, and no change to any parameters; consequently no 
safety margins are affected.
    Therefore, the proposed changes do not involve a significant 
reduction in a margin of safety.

    Based upon the above, PSEG concludes that the proposed change 
presents no significant hazards consideration under the standards set 
forth in 10 CFR 50.92(c), and, accordingly, a finding of ``no 
significant hazards consideration'' is justified.
    The NRC staff has reviewed the licensee's analysis and, based on 
this review, and with the changes noted above in square brackets, it 
appears that the three standards of 10 CFR 50.92(c) are satisfied. 
Therefore, the NRC staff proposes to determine that the amendment 
request involves no significant hazards consideration.
    Attorney for licensee: Jeffrie J. Keenan, PSEG Nuclear LLC--N21, 
P.O. Box 236, Hancocks Bridge, NJ 08038.
    NRC Branch Chief: Douglas A. Broaddus.
South Carolina Electric & Gas Company, Docket Nos.: 52-027 and 52-028, 
Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3, Fairfield 
County, South Carolina
    Date of amendment request: September 25, 2014; as supplemented by 
letter dated March 13, 2015. Publicly-available versions are in ADAMS 
under Accession Nos. ML14268A388 and ML15072A306, respectively.
    Description of amendment request: The proposed change would amend 
Combined License Nos. NPF-93 and NPF-94 for the VCSNS Units 2 and 3 by 
allowing changes to adjust the concrete wall thickness tolerances of 
four Nuclear Island walls found in Tier 1. In addition, the changes 
include an update to Tier 2 Subsection 3.8.3.6.1 to address the 
exceeded American Concrete Institute (ACI) 117 tolerance for the four 
affected walls.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    As indicated in the Updated Final Safety Analysis Report 
Subsection 3.8.3.1, the containment internal structures and 
associated modules support the reactor coolant system components and 
related piping systems and equipment. The increase in tolerance 
associated with the concrete thickness of four of these containment 
internal structure walls do not involve any accident initiating 
components or events, thus leaving the probabilities of an accident 
unaltered. The increased tolerance does not adversely affect any 
safety-related structures or equipment nor does the increased 
tolerance reduce the effectiveness of a radioactive material 
barrier. Thus, the proposed changes would not affect any safety-
related accident mitigating function served by the containment 
internal structures.
    Therefore, the proposed amendment does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed tolerance increases do not change the performance 
of the affected containment internal structures. As demonstrated by 
the continued conformance to the applicable codes and standards 
governing the design of the structures, the walls with an increased 
concrete thickness tolerance continue to withstand the same effects 
as previously evaluated. There is no change to the design function 
of the affected modules and walls, and no new failure mechanisms are 
identified as the same types of accidents are presented to the walls 
before and after the change.
    Therefore, the proposed amendment does not create the 
possibility of a new or different kind of accident.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed change to increase the concrete thickness tolerance 
does not alter any design function, design analysis, or safety 
analysis input or result, and sufficient margin exists to justify a 
departure from the standards identified in the underlying Tier 2 
information with respect to the four affected walls. As such, 
because the system continues to respond to design basis accidents in 
the same manner as before without any changes to the expected 
response of the structure, no safety analysis or design basis 
acceptance limit/criterion is challenged or exceeded by the proposed 
changes. Accordingly, no safety margin is reduced by the increase of 
the wall concrete thickness tolerance.
    Therefore, the proposed amendment does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Ms. Kathryn M. Sutton, Morgan, Lewis & 
Bockius LLC, 1111 Pennsylvania Avenue NW., Washington, DC 20004-2514.
    NRC Branch Chief: Lawrence Burkhart.
Southern Nuclear Operating Company, Inc. Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant Units 3 and 4, Burke County, Georgia
    Date of amendment request: March 6, 2015. A publicly-available 
version is in ADAMS under Accession No. ML15065A362.
    Description of amendment request: The proposed amendment and 
exemption identify portions of the licensing basis that would more 
appropriately be classified as Tier 2, specifically the Tier 2* 
information on Fire Area Figures 9A-1, 9A-2, 9A-3, 9A-4, 9A-5, and 9A-
201 in the Vogtle Electric Generating Plant Units 3 and 4 Updated Final 
Safety Analysis Report. With the reclassification, prior U.S. Nuclear 
Regulatory Commission approval would continue to be required for any 
safety significant changes to the Fire Area Figures because any 
revisions to that information would follow the Tier 2 change process 
provided in 10 CFR part 52, Appendix D, Section VIII.B.5.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed amendment would reclassify Fire Area Figures Tier 
2* information. The proposed amendment does not modify the design, 
construction, or operation of any plant structures, systems, or 
components (SSCs), nor does it change any procedures or method of 
control for any SSCs. Because the proposed amendment does not change 
the design, construction, or operation of any SSCs, it does not 
adversely affect any design function as described in the Updated 
Final Safety Analysis Report.
    Therefore, the proposed amendment does not affect the 
probability of an accident

[[Page 20026]]

previously evaluated. Similarly, because the proposed amendment does 
not alter the design or operation of the nuclear plant or any plant 
SSCs, the proposed amendment does not represent a change to the 
radiological effects of an accident, and therefore, does not involve 
an increase in the consequences of an accident previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed amendment would reclassify Fire Area Figures Tier 
2* information. The proposed amendment is not a modification, 
addition to, or removal of any plant SSCs. Furthermore, the proposed 
amendment is not a change to procedures or method of control of the 
nuclear plant or any plant SSCs. The only impact of this activity is 
the reclassification of information in the Updated Final Safety 
Analysis Report. Because the proposed amendment only reclassifies 
information and does not change the design, construction, or 
operation of the nuclear plant or any plant operations, the 
amendment does not create the possibility of a new or different kind 
of accident from any accident previously evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed amendment would reclassify Fire Area Figures Tier 
2* information. The proposed amendment is not a modification, 
addition to, or removal of any plant SSCs. Furthermore, the proposed 
amendment is not a change to procedures or method of control of the 
nuclear plant or any plant SSCs. The only impact of this activity is 
the reclassification of information in the Updated Final Safety 
Analysis Report.
    Therefore, the proposed amendment does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Mr. M. Stanford Blanton, Balch & Bingham 
LLP, 1710 Sixth Avenue North Birmingham, AL 35203-2015.
    NRC Branch Chief: Lawrence Burkhart.
ZionSolutions LLC, Docket Nos. 50-295 and 50-304, Zion Nuclear Power 
Station (Zion), Units 1 and 2, Lake County, Illinois
    Date of amendment request: December 19, 2014, as supplemented on 
February 26, 2015. Publicly available versions are in ADAMS under 
Accession Nos. ML15005A336 and ML15061A230, respectively.
    Description of amendment request: The proposed amendment would add 
License Condition 2.C (17) that approves the License Termination Plan 
(LTP) and establishes the criteria for determining when changes to the 
LTP require prior the U.S. Nuclear Regulatory Commission (NRC) 
approval.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    (1) Does the change involve a significant increase in the 
probability or consequences of an accident previously evaluated?
    The only remaining accident after fuel transfer is completed in 
January 2015 is the Radwaste handling accident. Calculations were 
performed to determine the dose at the Exclusion Area Boundary that 
would result from dropping a High Integrity Container in the former 
Interim Radwaste Storage Facility (IRSF) such that its entire 
contents of radioactive, dewatered resin escape. A fraction of the 
escaped resin is non mechanistically assumed to be released as 
airborne radioactivity and pass from the IRSF directly to the 
environment, resulting in off-site dose consequences. The solid-to-
aerosol release fraction is assumed to be the worst case non-
mechanistic, mechanically initiated release fraction. The whole body 
and inhalation dose at the closest point on the Exclusion Area 
Boundary from the IRSF are then calculated.
    The results of the radiological dose consequences for an 
accident involving the failure of a High Integrity Container show 
that the projected doses are insignificant in comparison to the 10 
CFR 100 guidelines, and are less than the EPA [Environmental 
Protection Agency] PAGs [protective action guidelines]. The 
projected dose at the Low Population Zone would be less than at the 
Exclusion Area Boundary and, since this accident involves an 
instantaneous release, it is also within the 10 CFR 100 guidelines.
    The proposed change does not affect the boundaries used to 
evaluate compliance with liquid or gaseous effluent limits, and has 
no impact on plant operations. The proposed changes do not have an 
adverse impact on the remaining decommissioning activities or any 
decommissioning related postulated accident consequences.
    The proposed changes related to the approval of the LTP do not 
affect operating procedures or administrative controls that have the 
function of preventing or mitigating the remaining decommissioning 
design basis accident.
    Therefore, the proposed changes do not involve a significant 
increase in the probability or consequences of any accident 
previously evaluated.
    (2) Does the change create the possibility of a new or different 
kind of accident from any accident previously evaluated?
    The accident analysis for the facility related to 
decommissioning activities is described in the DSAR [defueled safety 
analysis report]. The requested license amendment is consistent with 
the plant activities described in the DSAR and PSDAR [post-shutdown 
decommissioning activities report]. Thus, the proposed changes do 
not affect the remaining plant systems, structures, or components in 
a way not previously evaluated.
    There are sections of the LTP that refer to the decommissioning 
activities still remaining (e.g.; removal of large components, 
structure removal, etc.). However, these activities are performed in 
accordance with approved work packages/steps and undergo a 10 CFR 
50.59 screening prior to initiation. The proposed amendment merely 
makes mention of these processes and does not bring about physical 
changes to the facility.
    Therefore, the facility conditions for which the remaining 
postulated accident has been evaluated is still valid and no new 
accident scenarios, failure mechanisms, or single failures are 
introduced by this amendment. The system operating procedures are 
not affected. Therefore, the proposed changes will not create the 
possibility of a new or different kind of accident from any accident 
previously evaluated.
    (3) Does the change involve a significant reduction in a margin 
of safety?
    The LTP is a plan for demonstrating compliance with the 
radiological criteria for license termination as provided in 10 CFR 
20.1402 (Reference 5). The margin of safety defined in the 
statements of consideration for the final rule on the Radiological 
Criteria for License Termination is described as the margin between 
the 100 mrem/yr public dose limit established in 10 CFR 20.1301 for 
licensed operation and the 25 mrem/yr dose limit to the average 
member of the critical group at a site considered acceptable for 
unrestricted use (one of the criteria of 10 CFR 20.1402). This 
margin of safety accounts for the potential effect of multiple 
sources of radiation exposure to the critical group. Since the 
License Termination Plan is designed to comply with the radiological 
criteria for license termination for unrestricted use, the LTP 
supports this margin of safety.
    In addition, the LTP provides the methodologies and criteria 
that will be used to perform remediation activities of residual 
radioactivity to demonstrate compliance with the ALARA [as low as 
reasonably achievable] criterion of 10 CFR 20.1402.
    Additionally, the LTP is designed with recognition that (a) the 
methods in MARSSIM (Multi-Agency Radiation Survey and Site 
Investigation Manual) (Reference 6) and (b) the building surface 
contamination levels are not directly applicable to use with complex 
nonstructural components. Therefore, the LTP states that 
nonstructural components remaining in buildings (e.g., pumps, heat 
exchangers, etc.) will be evaluated against the criteria of 
Regulatory Guide 1.86 (Reference 7) to determine if the components 
can be released for unrestricted use. The LTP also states that 
materials, surveyed and evaluated as a part of normal 
decommissioning activities and prior to implementation of the final 
radiation surveys, will be surveyed for release using current site 
procedures to demonstrate compliance with the ``no detectable'' 
criteria. Such materials that do not pass these criteria will be 
controlled as contaminated.

[[Page 20027]]

    Also, as previously discussed, the bounding accident for 
decommissioning is the resin container accident. Since the bounding 
decommissioning accident results in more airborne radioactivity than 
can be released from other decommissioning events, the margin of 
safety associated with the consequences of decommissioning accidents 
is not reduced by this activity.
    Thus, the proposed change does not involve a significant 
reduction in the margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Russ Workman, Deputy General Counsel, 
EnergySolutions, 423 West 300 South, Suite 200, Salt Lake City, UT 
84101.
    NRC Branch Chief: Bruce Watson.

III. Notice of Issuance of Amendments to Facility Operating Licenses 
and Combined Licenses

    During the period since publication of the last biweekly notice, 
the Commission has issued the following amendments. The Commission has 
determined for each of these amendments that the application complies 
with the standards and requirements of the Atomic Energy Act of 1954, 
as amended (the Act), and the Commission's rules and regulations. The 
Commission has made appropriate findings as required by the Act and the 
Commission's rules and regulations in 10 CFR Chapter I, which are set 
forth in the license amendment.
    A notice of consideration of issuance of amendment to facility 
operating license or combined license, as applicable, proposed no 
significant hazards consideration determination, and opportunity for a 
hearing in connection with these actions, was published in the Federal 
Register as indicated.
    Unless otherwise indicated, the Commission has determined that 
these amendments satisfy the criteria for categorical exclusion in 
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), 
no environmental impact statement or environmental assessment need be 
prepared for these amendments. If the Commission has prepared an 
environmental assessment under the special circumstances provision in 
10 CFR 51.22(b) and has made a determination based on that assessment, 
it is so indicated.
    For further details with respect to the action see (1) the 
applications for amendment, (2) the amendment, and (3) the Commission's 
related letter, Safety Evaluation and/or Environmental Assessment as 
indicated. All of these items can be accessed as described in the 
``Obtaining Information and Submitting Comments'' section of this 
document.
Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-
529, and STN 50-530, Palo Verde Nuclear Generating Station, Unit Nos. 
1, 2, and 3, Maricopa County, Arizona
    Date of application for amendment: November 20, 2013, as 
supplemented by letters dated November 20, 2013, and January 16 and 
December 19, 2014.
    Brief description of amendment: The amendment modified Technical 
Specification (TS) Surveillance Requirement (SR) 3.1.4.1 utilizing 
Westinghouse Electric Company LLC's topical report WCAP-16011-NP-A, 
Revision 0, ``Startup Test Activity Reduction [STAR] Program,'' 
February 2005. The changes are consistent with NRC-approved Technical 
Specification Task Force (TSTF) Standard Technical Specification Change 
Traveler TSTF-486, Revision 2. The use of WCAP-16011-NP-A is justified 
by the licensee in WCAP-17787-NP, Revision 0, ``Palo Verde Nuclear 
Generating Station STAR Program Implementation Report,'' August 2013.
    The amendments also modify SR 3.1.4.2 not to require the moderator 
temperature coefficient (MTC) determination if the result of the MTC 
determination required in TS 3.1.4.1 is within a certain tolerance of 
the corresponding design value. This change is based on the methods 
described in Combustion Engineering Owners Group Report CE NPSD-911-A 
and Amendment 1-A, ``Analysis of Moderator Temperature Coefficients in 
Support of a Change in the Technical Specifications End-of-Cycle 
Negative MTC Limits,'' September 2000.
    Date of issuance: March 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: Unit 1-195; Unit 2-195; Unit 3-195. A publicly-
available version is in ADAMS under Accession No. ML15070A124; 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. NPF-41, NPF-51, and NPF-74: 
The amendment revised the Operating Licenses and Technical 
Specifications.
    Date of initial notice in Federal Register: February 27, 2014 (79 
FR 11146). The supplemental letters dated January 16 and December 19, 
2014, provided additional information that clarified the application, 
did not expand the scope of the application as originally noticed, and 
did not change the staff's original proposed no significant hazards 
consideration determination as published in the Federal Register.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated March 30, 2015.
    No significant hazards consideration comments received: No.
Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba 
Nuclear Station, Units 1 and 2, York County, South Carolina, Duke 
Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire Nuclear 
Station, Units 1 and 2, Mecklenburg County, North Carolina
    Date of application for amendments: November 14, 2013, as 
supplemented by letters dated June 27, and November 10, 2014.
    Brief description of amendments: The amendments approve the use of 
DPC-3001-NE-P, Revision 1, ``Multidimensional Reactor Transients and 
Safety Analysis Physics Parameters Methodology.''
    Date of issuance: March 25, 2015.
    Effective date: This license amendment is effective as of its date 
of issuance and shall be implemented within 30 days of issuance.
    Amendment Nos.: 274, 270, 277, and 257. A publicly-available 
version of the application is in ADAMS under Accession No. ML15027A366; 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. NPF-35, NPF-52, NPF-9, and 
NPF-17: Amendments revised the licenses.
    Date of initial notice in Federal Register: February 27, 2014 (79 
FR 11147). The supplemental letters dated June 27, and November 10, 
2014, provided additional information that clarified the application, 
did not expand the scope of the application as originally noticed, and 
did not change the staff's original proposed no significant hazards 
consideration determination as published in the Federal Register.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated March 25, 2015.
    No significant hazards consideration comments received: No.

[[Page 20028]]

Duke Energy Florida, Inc., et al., Docket No. 50-302, Crystal River 
Unit 3 Nuclear Generating Plant, Citrus County, Florida
    Date of amendment request: September 26, 2013, as supplemented by 
letters dated March 28, May 23, and October 6, 2014.
    Brief description of amendment: The amendment revised the 
facility's emergency plan and emergency action level scheme to reflect 
the low likelihood of any credible accident at the facility in its 
permanently shutdown and defueled condition that could result in 
radiological releases requiring offsite protective measures.
    Date of issuance: March 31, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment No.: 246. A publicly-available version is in ADAMS under 
Accession No. ML15027A209; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Operating License No. DPR-72: Amendment revised the 
emergency plan and the emergency action levels.
    Date of initial notice in Federal Register: January 7, 2014 (79 FR 
857). The supplemental letters dated March 28, May 23, and October 6, 
2014, provided additional information that clarified the application, 
did not expand the scope of the application as originally noticed, and 
did not change the staff's original proposed no significant hazards 
consideration determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 31, 2015.
    No significant hazards consideration comments received: No.
Energy Northwest, Docket No. 50-397, Columbia Generating Station, 
Benton County, Washington
    Date of application for amendment: March 24, 2014, as supplemented 
by letters dated May 8, August 28, November 6, and December 15, 2014.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) Table 3.3.1.1-1, ``Reactor Protection System 
Instrumentation,'' Functions 7.a and 7.b to update Scram Discharge 
Volume instrumentation nomenclature, add a surveillance requirement 
(SR), which was previously omitted, and add footnotes to an SR 
consistent with TS Task Force (TSTF) change traveler TSTF-493, Revision 
4, ``Clarify Application of Setpoint Methodology for LSSS [Limiting 
Safety System Settings] Functions,'' Option A. The notice of 
availability of the models for plant-specific adoption of TSTF-493, 
Revision 4, was announced in the Federal Register on May 11, 2010 (75 
FR 26294).
    Date of issuance: March 27, 2015.
    Effective date: As of its date of issuance and shall be implemented 
prior to restarting from refueling outage R-22, scheduled for spring 
2015.
    Amendment No.: 232. A publicly-available version is in ADAMS under 
Accession No. ML15063A010; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-21: The amendment 
revised the Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: July 22, 2014 (79 FR 
42544). The supplemental letters dated August 28, November 6, and 
December 15, 2014, provided additional information that clarified the 
application, did not expand the scope of the application as originally 
noticed, and did not change the staff's original proposed no 
significant hazards consideration determination as published in the 
Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 27, 2015.
    No significant hazards consideration comments received: No.
Energy Northwest, Docket No. 50-397, Columbia Generating Station, 
Benton County, Washington
    Date of application for amendment: June 25, 2014.
    Brief description of amendment: The amendment revised the Columbia 
Generating Station Cyber Security Plan (CSP) Milestone 8 full 
implementation date as set forth in the CSP Implementation Schedule.
    Date of issuance: March 27, 2015.
    Effective date: As of its date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment No.: 231. A publicly-available version is in ADAMS under 
Accession No. ML15042A464; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-21: The amendment 
revised the Facility Operating License.
    Date of initial notice in  Federal Register: October 7, 2014 (79 FR 
60518).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 27, 2015.
    No significant hazards consideration comments received: No.
Entergy Operations, Inc., Docket No. 50-368, Arkansas Nuclear One, Unit 
No. 2 (ANO-2), Pope County, Arkansas
    Date of application for amendment: March 26, 2013, as supplemented 
by letters dated December 12, 2013, and May 12, August 19, October 22, 
and December 5, 2014.
    Brief description of amendment: The amendment revised the ANO-2 
Technical Specification (TS) requirements for end states associated 
with the implementation of the NRC-approved Topical Report NPSD-1186, 
Revision 0, ``Technical Justification for the Risk Informed 
Modification to Selected Required Action End States for CEOG 
[Combustion Engineering Owners Group] Member PWRs [Pressurized-Water 
Reactors],'' as well as Required Actions revised by a specific Note in 
TS Task Force (TSTF) change traveler TSTF-422, Revision 2, ``Change in 
Technical Specifications End States (CE NPSD-1186).'' The Notice of 
Availability for TSTF-422, Revision 2, was announced in the Federal 
Register on April 7, 2011 (76 FR 19510).
    Date of issuance: March 31, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: 301. A publicly-available version is in ADAMS under 
Accession No. ML15068A319; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-6: Amendment revised the 
Technical Specifications/license.
    Date of initial notice in Federal Register: July 23, 2013 (78 FR 
44172). The supplemental letters dated December 12, 2013, and May 12, 
August 19, October 22, and December 5, 2014, provided additional 
information that clarified the application, did not expand the scope of 
the application as originally noticed, and did not change the staff's 
original proposed no significant hazards consideration determination as 
published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 31, 2015.
    No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad 
Cities Nuclear Power Station, Units 1 and 2, Rock Island County, 
Illinois
    Date of application for amendments: June 10, 2013, as supplemented 
by

[[Page 20029]]

letters dated October 24, 2013, March 5, 2014, and February 4, 2015.
    Brief description of amendments: The amendment revises the 
technical specifications (TSs), Surveillance Requirements 3.8.4.2 and 
3.8.4.5 to add new acceptance criteria for total battery connection 
resistance.
    Date of issuance: March 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment Nos.: 256 and 251. A publicly-available version is in 
ADAMS under Accession No. ML15056A772. Documents related to these 
amendments are listed in the Safety Evaluation enclosed with the 
amendments.
    Renewed Facility Operating License Nos. DPR-29 and DPR-30: The 
amendments revised the TSs and License.
    Date of initial notice in Federal Register: September 3, 2013 (78 
FR 54283). The October 24, 2013, March 5, 2014, and February 4, 2015, 
supplements contained clarifying information and did not change the NRC 
staff's initial proposed finding of no significant hazards 
consideration.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated March 30, 2015.
    No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-219, Oyster Creek Nuclear 
Generating Station (OCNGS), Ocean County, New Jersey
    Date of application for amendment: December 19, 2013, as 
supplemented by letters dated January 31, 2014, and November 3, 2014.
    Brief description of amendment: The amendment revised Renewed 
Facility Operating License No. DPR-16 for OCNGS. Specifically, the 
changes implement the use of an alternative measure that required prior 
NRC review and approval pursuant to Title 10 of the Code of Federal 
Regulations (10 CFR), Section 73.55(r), related to controlling vital 
area access for certain portions of the Reactor Building at OCNGS.
    Date of Issuance: March 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment No.: 285. A publicly-available version is in ADAMS under 
Accession No. ML14329A625; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-16: The amendment 
revised the license and technical specifications.
    Date of initial notice in Federal Register: May 6, 2014 (79 FR 
25901). The supplemental letter dated November 3, 2014, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of this amendment is contained 
in a Safety Evaluation dated March 30, 2015.
    No significant hazards consideration comments received: No.
FirstEnergy Nuclear Operating Company, Docket No. 50-440, Perry Nuclear 
Power Plant, Unit No. 1, Lake County, Ohio
    Date of application for amendment: October 8, 2014, as supplemented 
by a letter dated February 12, 2015.
    Brief description of amendment: The amendment revised the technical 
specifications (TSs) safety limit minimum critical power ratio value 
for single recirculation-loop-operation to support the use of GNF-2 
fuel during the next operating cycle.
    Date of issuance: March 27, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days.
    Amendment No.: 165. A publicly-available version is in ADAMS under 
Accession No. ML15075A091; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Operating License No. NPF-58: This amendment revised the 
TSs and License.
    Date of initial notice in Federal Register: February 13, 2015 (80 
FR 5819). The February 12, 2015, supplement contained clarifying 
information and did not change the NRC staff's initial proposed finding 
of no significant hazards consideration.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 27, 2015.
    No significant hazards consideration comments received: No.
Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, Donald 
C. Cook Nuclear Plant, Units 1 and 2, Berrien County, Michigan
    Date of amendment requests: March 7, 2014, as supplemented by 
letters dated September 30, 2014, December 16, 2014, January 15, 2015, 
and February 20, 2015.
    Brief description of amendments: The amendments revised the Donald 
C. Cook Nuclear Plant, Units 1 and 2, Technical Specification 5.5.14, 
``Containment Leakage Rate Testing Program,'' by adopting Nuclear 
Energy Institute (NEI) 94-01, Revision 3-A, ``Industry Guideline for 
Implementing Performance-Based Option of 10 CFR part 50, Appendix J'' 
(ADAMS Accession No. ML12221A202), and Section 4.1, ``Limitations and 
Conditions for NEI TR 94-01, Revision 2'' of the NRC Safety Evaluation 
Report in NEI 94-01, Revision 2-A, dated October 2008 (ADAMS Accession 
No. ML100620847), as the implementing document for the performance-
based Option B of 10 CFR part 50, Appendix J.
    Date of issuance: March 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: 326 for Unit 1 and 309 for Unit 2. A publicly-
available version is in ADAMS under Accession No. ML15072A264; 
documents related to this amendment are listed in the Safety Evaluation 
enclosed with the amendment.
    Renewed Facility Operating License Nos. DPR-58 and DPR-74: 
Amendments revise the Renewed Facility Operating Licenses and Technical 
Specifications.
    Date of initial notice in Federal Register: May 27, 2014 (79 FR 
30188). The supplemental letters dated September 30, 2014, December 16, 
2014, January 15, 2015, and February 20, 2015, provided additional 
information that clarified the application, did not expand the scope of 
the application as originally noticed, and did not change the staff's 
original proposed no significant hazards consideration determination as 
published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 30, 2015.
    No significant hazards consideration comments received: No.
NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit 
No. 1, Rockingham County, New Hampshire
    Date of amendment request: September 24, 2014, as supplemented by 
letter dated December 11, 2014.
    Description of amendment request: The amendment changes the 
Technical Specifications (TSs) and the Facility Operating License. The 
change deletes the Functional Unit ``Cold Leg Injection, P-15'' from TS 
3.3.2, ``Engineered Safety Features Actuation System Instrumentation,'' 
and changes License Condition 2.K, ``Inadvertent Actuation of the 
Emergency Core Cooling System (ECCS).''
    Date of issuance: March 31, 2015.

[[Page 20030]]

    Effective date: As of its date of issuance, and shall be 
implemented within 30 days.
    Amendment No.: 145. A publicly-available version is in ADAMS under 
Accession No. ML15002A251; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Operating License No. NPF-86: Amendment revised the 
Facility Operating License and TSs.
    Date of initial notice in Federal Register: January 6, 2015, (80 FR 
525).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 31, 2015.
    No significant hazards consideration comments received: No.
Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station, 
Unit No. 1, Washington County, Nebraska
    Date of amendment request: November 7, 2014.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) 3.1, Table 3-3, Item 3.c concerning containment wide 
range radiation monitors to correct a typographical error introduced in 
TS Amendment No. 152.
    Date of issuance: March 27, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment No.: 281. A publicly-available version is in ADAMS under 
Accession No. ML15035A203; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-40: The amendment 
revised the license and Technical Specifications.
    Date of initial notice in Federal Register: January 20, 2015 (80 FR 
2751).
    The Commission's related evaluation of the amendment is contained 
in a safety evaluation dated March 27, 2015.
    No significant hazards consideration comments received: No.
PSEG Nuclear LLC, Docket Nos. 50-272 and 50-311, Salem Nuclear 
Generating Station, Unit Nos. 1 and 2, Salem County, New Jersey
    Date of application for amendments: March 24, 2014.
    Brief description of amendments: The amendments approved a change 
to revise Surveillance Requirements 4.2.1.3, 4.2.1.4, and 4.2.2.2.f 
associated with Power Distribution Limits Technical Specification (TS) 
3/4.2.1, ``Axial Flux Difference (AFD),'' and TS 3/4.2.2, ``Heat Flux 
Hot Channel Factor--FQ(Z).''
    Date of issuance: March 30, 2015.
    Effective date: As of the date of issuance, to be implemented 
within 60 days.
    Amendment Nos.: 307 and 289. A publicly-available version is in 
ADAMS under Accession No. ML15063A293; documents related to these 
amendments are listed in the Safety Evaluation enclosed with the 
amendments.
    Renewed Facility Operating License Nos. DPR-70 and DPR-75: The 
amendments revised the Technical Specifications and the License.
    Date of initial notice in Federal Register: June 6, 2014 (79 FR 
32770).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated March 30, 2015.
    No significant hazards consideration comments received: No.
South Carolina Electric & Gas Company, Docket Nos. 52-027 and 52-028, 
Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3, Fairfield 
County, South Carolina
    Date of amendment request: August 5, 2014, revised by letter dated 
August 28, 2014, and supplemented by letter dated November 3, 2014 
(Non-Public).
    Description of amendment: The amendment revises the design of 
connections between reinforced concrete (RC) and steel plate concrete 
composite construction (SC) included in the VCSNS Units 2 and 3 updated 
Final Safety Analysis Report and changes to the Technical Report, 
``APP-GW-GLR-602, AP1000 Shield Building Design Details for Select Wall 
and RC/SC Connections,'' (prepared by Westinghouse Electric Company and 
reviewed by the U.S. Nuclear Regulatory Commission as part of the 
design certification rule).
    Date of issuance: December 16, 2014.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment No.: 21. A publicly-available version is in ADAMS under 
Accession No. ML14339A717; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Combined Licenses No. NPF-93 and NPF-94: Amendment revised 
the Facility Combined Licenses.
    Date of initial notice in Federal Register: September 30, 2014 (79 
FR 58824). The supplemental letter dated November 3, 2014, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in the Safety Evaluation dated December 16, 2014.
    No significant hazards consideration comments received: No.
South Carolina Electric & Gas Company, Docket Nos. 52-027 and 52-028, 
Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3, Fairfield 
County, South Carolina
    Date of amendment request: June 20, 2014, and supplemented by 
letter dated August 6, 2014.
    Description of amendment: The amendment revises the Updated Final 
Safety Analysis Report in regard to Tier 2 and Tier 2* information 
related to fire area boundaries. These changes include: adding of three 
new fire zones in the middle annulus to provide fire barrier enclosures 
for the Class 1E Electrical Divisions B, C, and D containment 
penetrations; and eliminating the Class 1E Electrical Division A 
enclosure and making the Division A containment penetration assemblies 
part of the existing middle annulus fire zone.
    Date of issuance: December 30, 2014.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment No.: 22. A publicly-available version is in ADAMS under 
Accession No. ML14328A233; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Combined Licenses No. NPF-93 and NPF-94: Amendment revised 
the Facility Combined Licenses.
    Date of initial notice in Federal Register: October 28, 2014 (79 FR 
64228).
    The Commission's related evaluation of the amendment is contained 
in the Safety Evaluation dated December 30, 2014.
    No significant hazards consideration comments received: No.
Union Electric Company, Docket No. 50-483, Callaway Plant, Unit 1, 
Callaway County, Missouri
    Date of application for amendment: December 6, 2013, as 
supplemented by letters dated September 2 and December 11, 2014, and 
February 3, 2015.
    Brief description of amendment: The amendment changed the licensing 
basis as described in the Final Safety Analysis Report (FSAR)-Standard 
Plant Section 3.6.2.1.2.4, ``ASME [American Society of Mechanical 
Engineers] Section III and Non-Nuclear Piping-Moderate-Energy,'' and 
FSAR-Standard Plant Table 3.6-2,

[[Page 20031]]

``Design Comparison to Regulatory Positions of Regulatory Guide 1.46, 
Revision 0, dated May 1973, titled `Protection Against Pipe Whip Inside 
Containment,' '' in particular regard to the high-density polyethylene 
(HDPE) piping installed in ASME Class 3 line segments of the essential 
service water system. Also, new Reference 25 is added to FSAR-Standard 
Plant Section 3.6.3 to cite the NRC-approved version of the HDPE 
requirements covered by Relief Request I3R-10 dated October 31, 2008.
    Date of issuance: March 31, 2015.
    Effective date: As of its date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment No.: 211. A publicly-available version is in ADAMS under 
Accession No. ML15064A028; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-30: The amendment 
revised the Operating License.
    Date of initial notice in Federal Register: March 18, 2014 (79 FR 
15150). The supplements dated September 2 and December 11, 2014, and 
February 3, 2015, provided additional information that clarified the 
application, did not expand the scope of the application as originally 
noticed, and did not change the staff's original proposed no 
significant hazards consideration determination as published in the 
Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 31, 2015.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 6th day of April 2015.

    For the Nuclear Regulatory Commission.
A. Louise Lund,
Acting Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2015-08579 Filed 4-13-15; 8:45 am]
 BILLING CODE 7590-01-P



                                                    20020                          Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices

                                                    categorical exclusion in accordance                     DATES:  Comments must be filed by May                 White Flint North, 11555 Rockville
                                                    with 10 CFR 51.22. Therefore, pursuant                  14, 2015. A request for a hearing must                Pike, Rockville, Maryland 20852.
                                                    to 10 CFR 51.22(b), no environmental                    be filed by June 15, 2015.
                                                                                                                                                                  B. Submitting Comments
                                                    impact statement or environmental                       ADDRESSES: You may submit comments
                                                    assessment need be prepared for these                   by any of the following methods (unless                 Please include Docket ID NRC–2015–
                                                    amendments.                                             this document describes a different                   0088, facility name, unit number(s),
                                                                                                                                                                  application date, and subject in your
                                                    IV. Conclusion                                          method for submitting comments on a
                                                                                                                                                                  comment submission.
                                                                                                            specific subject):
                                                       Using the reasons set forth in the                                                                           The NRC cautions you not to include
                                                                                                              • Federal Rulemaking Web site: Go to                identifying or contact information that
                                                    combined safety evaluation, the staff                   http://www.regulations.gov and search
                                                    granted the exemption and issued the                                                                          you do not want to be publicly
                                                                                                            for Docket ID NRC–2015–0088. Address                  disclosed in your comment submission.
                                                    amendment that the licensee requested                   questions about NRC dockets to Carol
                                                    on July 29, 2014, as supplemented by                                                                          The NRC will post all comment
                                                                                                            Gallagher; telephone: 301–415–3463;                   submissions at http://
                                                    letter dated November 5, 2014. The                      email: Carol.Gallagher@nrc.gov.
                                                    exemption and amendment were issued                                                                           www.regulations.gov as well as enter the
                                                                                                              • Mail comments to: Cindy Bladey,                   comment submissions into ADAMS.
                                                    on February 13, 2015 as part of a                       Office of Administration, Mail Stop:
                                                    combined package to the licensee                                                                              The NRC does not routinely edit
                                                                                                            OWFN–12–H08, U.S. Nuclear                             comment submissions to remove
                                                    (ADAMS Accession No. ML14350B012).                      Regulatory Commission, Washington,                    identifying or contact information.
                                                      Dated at Rockville, Maryland, this 7th day            DC 20555–0001.                                          If you are requesting or aggregating
                                                    of April 2015.                                            For additional direction on obtaining               comments from other persons for
                                                      For the Nuclear Regulatory Commission.                information and submitting comments,                  submission to the NRC, then you should
                                                    Chandu P. Patel,                                        see ‘‘Obtaining Information and                       inform those persons not to include
                                                    Acting Chief, Licensing Branch 4, Division              Submitting Comments’’ in the                          identifying or contact information that
                                                    of New Reactor Licensing, Office of New                 SUPPLEMENTARY INFORMATION section of                  they do not want to be publicly
                                                    Reactors.                                               this document.                                        disclosed in their comment submission.
                                                    [FR Doc. 2015–08566 Filed 4–13–15; 8:45 am]             FOR FURTHER INFORMATION CONTACT:                      Your request should state that the NRC
                                                    BILLING CODE 7590–01–P                                  Angela Baxter, Office of Nuclear Reactor              does not routinely edit comment
                                                                                                            Regulation, U.S. Nuclear Regulatory                   submissions to remove such information
                                                                                                            Commission, Washington DC 20555–                      before making the comment
                                                    NUCLEAR REGULATORY                                      0001; telephone: 301–415–2976, email:                 submissions available to the public or
                                                    COMMISSION                                              Angela.Baxter@nrc.gov.                                entering the comment into ADAMS.
                                                                                                            SUPPLEMENTARY INFORMATION:                            II. Notice of Consideration of Issuance
                                                    [NRC–2015–0088]                                                                                               of Amendments to Facility Operating
                                                                                                            I. Obtaining Information and
                                                                                                            Submitting Comments                                   Licenses and Combined Licenses and
                                                    Biweekly Notice; Applications and
                                                                                                                                                                  Proposed No Significant Hazards
                                                    Amendments to Facility Operating                        A. Obtaining Information                              Consideration Determination
                                                    Licenses and Combined Licenses
                                                    Involving No Significant Hazards                           Please refer to Docket ID NRC–2015–                   The Commission has made a
                                                    Considerations                                          0088 when contacting the NRC about                    proposed determination that the
                                                                                                            the availability of information for this              following amendment requests involve
                                                    AGENCY:  Nuclear Regulatory                             action. You may obtain publicly-                      no significant hazards consideration.
                                                    Commission.                                             available information related to this                 Under the Commission’s regulations in
                                                    ACTION: Biweekly notice.                                action by any of the following methods:               § 50.92 of Title 10 of the Code of Federal
                                                                                                               • Federal rulemaking Web site: Go to               Regulations (10 CFR), this means that
                                                    SUMMARY:   Pursuant to Section 189a. (2)                http://www.regulations.gov and search                 operation of the facility in accordance
                                                    of the Atomic Energy Act of 1954, as                    for Docket ID NRC–2015–0088.                          with the proposed amendment would
                                                    amended (the Act), the U.S. Nuclear                        • NRC’s Agencywide Documents                       not (1) involve a significant increase in
                                                    Regulatory Commission (NRC) is                          Access and Management System                          the probability or consequences of an
                                                    publishing this regular biweekly notice.                (ADAMS): You may obtain publicly-                     accident previously evaluated, or (2)
                                                    The Act requires the Commission to                      available documents online in the                     create the possibility of a new or
                                                    publish notice of any amendments                        ADAMS Public Documents collection at                  different kind of accident from any
                                                    issued, or proposed to be issued and                    http://www.nrc.gov/reading-rm/                        accident previously evaluated; or (3)
                                                    grants the Commission the authority to                  adams.html. To begin the search, select               involve a significant reduction in a
                                                    issue and make immediately effective                    ‘‘ADAMS Public Documents’’ and then                   margin of safety. The basis for this
                                                    any amendment to an operating license                   select ‘‘Begin Web-based ADAMS                        proposed determination for each
                                                    or combined license, as applicable,                     Search.’’ For problems with ADAMS,                    amendment request is shown below.
                                                    upon a determination by the                             please contact the NRC’s Public                          The Commission is seeking public
                                                    Commission that such amendment                          Document Room (PDR) reference staff at                comments on this proposed
                                                    involves no significant hazards                         1–800–397–4209, 301–415–4737, or by                   determination. Any comments received
                                                    consideration, notwithstanding the                      email to pdr.resource@nrc.gov. The                    within 30 days after the date of
asabaliauskas on DSK5VPTVN1PROD with NOTICES




                                                    pendency before the Commission of a                     ADAMS accession number for each                       publication of this notice will be
                                                    request for a hearing from any person.                  document referenced (if it is available in            considered in making any final
                                                       This biweekly notice includes all                    ADAMS) is provided the first time that                determination.
                                                    notices of amendments issued, or                        it is mentioned in the SUPPLEMENTARY                     Normally, the Commission will not
                                                    proposed to be issued from March 19,                    INFORMATION section.                                  issue the amendment until the
                                                    2015 to April 1, 2015. The last biweekly                   • NRC’s PDR: You may examine and                   expiration of 60 days after the date of
                                                    notice was published on March 31,                       purchase copies of public documents at                publication of this notice. The
                                                    2015.                                                   the NRC’s PDR, Room O1–F21, One                       Commission may issue the license


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                                                                                   Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices                                           20021

                                                    amendment before expiration of the 60-                  with particular reference to the                      consideration, then any hearing held
                                                    day period provided that its final                      following general requirements: (1) The               would take place before the issuance of
                                                    determination is that the amendment                     name, address, and telephone number of                any amendment unless the Commission
                                                    involves no significant hazards                         the requestor or petitioner; (2) the                  finds an imminent danger to the health
                                                    consideration. In addition, the                         nature of the requestor’s/petitioner’s                or safety of the public, in which case it
                                                    Commission may issue the amendment                      right under the Act to be made a party                will issue an appropriate order or rule
                                                    prior to the expiration of the 30-day                   to the proceeding; (3) the nature and                 under 10 CFR part 2.
                                                    comment period should circumstances                     extent of the requestor’s/petitioner’s
                                                                                                                                                                  B. Electronic Submissions (E-Filing)
                                                    change during the 30-day comment                        property, financial, or other interest in
                                                    period such that failure to act in a                    the proceeding; and (4) the possible                     All documents filed in NRC
                                                    timely way would result, for example in                 effect of any decision or order which                 adjudicatory proceedings, including a
                                                    derating or shutdown of the facility.                   may be entered in the proceeding on the               request for hearing, a petition for leave
                                                    Should the Commission take action                       requestor’s/petitioner’s interest. The                to intervene, any motion or other
                                                    prior to the expiration of either the                   petition must also identify the specific              document filed in the proceeding prior
                                                    comment period or the notice period, it                 contentions which the requestor/                      to the submission of a request for
                                                    will publish in the Federal Register a                  petitioner seeks to have litigated at the             hearing or petition to intervene, and
                                                    notice of issuance. Should the                          proceeding.                                           documents filed by interested
                                                    Commission make a final No Significant                     Each contention must consist of a                  governmental entities participating
                                                    Hazards Consideration Determination,                    specific statement of the issue of law or             under 10 CFR 2.315(c), must be filed in
                                                    any hearing will take place after                       fact to be raised or controverted. In                 accordance with the NRC’s E-Filing rule
                                                    issuance. The Commission expects that                   addition, the requestor/petitioner shall              (72 FR 49139; August 28, 2007). The E-
                                                    the need to take this action will occur                 provide a brief explanation of the bases              Filing process requires participants to
                                                    very infrequently.                                      for the contention and a concise                      submit and serve all adjudicatory
                                                                                                            statement of the alleged facts or expert              documents over the internet, or in some
                                                    A. Opportunity to Request a Hearing                     opinion which support the contention                  cases to mail copies on electronic
                                                    and Petition for Leave to Intervene                     and on which the requestor/petitioner                 storage media. Participants may not
                                                       Within 60 days after the date of                     intends to rely in proving the contention             submit paper copies of their filings
                                                    publication of this notice, any person(s)               at the hearing. The requestor/petitioner              unless they seek an exemption in
                                                    whose interest may be affected by this                  must also provide references to those                 accordance with the procedures
                                                    action may file a request for a hearing                 specific sources and documents of                     described below.
                                                    and a petition to intervene with respect                which the petitioner is aware and on                     To comply with the procedural
                                                    to issuance of the amendment to the                     which the requestor/petitioner intends                requirements of E-Filing, at least ten 10
                                                    subject facility operating license or                   to rely to establish those facts or expert            days prior to the filing deadline, the
                                                    combined license. Requests for a                        opinion. The petition must include                    participant should contact the Office of
                                                    hearing and a petition for leave to                     sufficient information to show that a                 the Secretary by email at
                                                    intervene shall be filed in accordance                  genuine dispute exists with the                       hearing.docket@nrc.gov, or by telephone
                                                    with the Commission’s ‘‘Agency Rules                    applicant on a material issue of law or               at 301–415–1677, to request (1) a digital
                                                    of Practice and Procedure’’ in 10 CFR                   fact. Contentions shall be limited to                 identification (ID) certificate, which
                                                    part 2. Interested person(s) should                     matters within the scope of the                       allows the participant (or its counsel or
                                                    consult a current copy of 10 CFR 2.309,                 amendment under consideration. The                    representative) to digitally sign
                                                    which is available at the NRC’s PDR,                    contention must be one which, if                      documents and access the E-Submittal
                                                    located at One White Flint North, Room                  proven, would entitle the requestor/                  server for any proceeding in which it is
                                                    O1–F21, 11555 Rockville Pike (first                     petitioner to relief. A requestor/                    participating; and (2) advise the
                                                    floor), Rockville, Maryland 20852. The                  petitioner who fails to satisfy these                 Secretary that the participant will be
                                                    NRC’s regulations are accessible                        requirements with respect to at least one             submitting a request or petition for
                                                    electronically from the NRC Library on                  contention will not be permitted to                   hearing (even in instances in which the
                                                    the NRC’s Web site at http://                           participate as a party.                               participant, or its counsel or
                                                    www.nrc.gov/reading-rm/doc-                                Those permitted to intervene become                representative, already holds an NRC-
                                                    collections/cfr/. If a request for a hearing            parties to the proceeding, subject to any             issued digital ID certificate). Based upon
                                                    or petition for leave to intervene is filed             limitations in the order granting leave to            this information, the Secretary will
                                                    by the above date, the Commission or a                  intervene, and have the opportunity to                establish an electronic docket for the
                                                    presiding officer designated by the                     participate fully in the conduct of the               hearing in this proceeding if the
                                                    Commission or by the Chief                              hearing.                                              Secretary has not already established an
                                                    Administrative Judge of the Atomic                         If a hearing is requested, the                     electronic docket.
                                                    Safety and Licensing Board Panel, will                  Commission will make a final                             Information about applying for a
                                                    rule on the request and/or petition; and                determination on the issue of no                      digital ID certificate is available on the
                                                    the Secretary or the Chief                              significant hazards consideration. The                NRC’s public Web site at http://
                                                    Administrative Judge of the Atomic                      final determination will serve to decide              www.nrc.gov/site-help/e-submittals/
                                                    Safety and Licensing Board will issue a                 when the hearing is held. If the final                getting-started.html. System
                                                    notice of a hearing or an appropriate                   determination is that the amendment                   requirements for accessing the E-
                                                    order.                                                  request involves no significant hazards               Submittal server are detailed in the
asabaliauskas on DSK5VPTVN1PROD with NOTICES




                                                       As required by 10 CFR 2.309, a                       consideration, the Commission may                     NRC’s ‘‘Guidance for Electronic
                                                    petition for leave to intervene shall set               issue the amendment and make it                       Submission,’’ which is available on the
                                                    forth with particularity the interest of                immediately effective, notwithstanding                agency’s public Web site at http://
                                                    the petitioner in the proceeding, and                   the request for a hearing. Any hearing                www.nrc.gov/site-help/e-
                                                    how that interest may be affected by the                held would take place after issuance of               submittals.html. Participants may
                                                    results of the proceeding. The petition                 the amendment. If the final                           attempt to use other software not listed
                                                    should specifically explain the reasons                 determination is that the amendment                   on the Web site, but should note that the
                                                    why intervention should be permitted                    request involves a significant hazards                NRC’s E-Filing system does not support


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                                                    20022                          Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices

                                                    unlisted software, and the NRC Meta                     Time, Monday through Friday,                          are filed after the 60-day deadline will
                                                    System Help Desk will not be able to                    excluding government holidays.                        not be entertained absent a
                                                    offer assistance in using unlisted                         Participants who believe that they                 determination by the presiding officer
                                                    software.                                               have a good cause for not submitting                  that the filing demonstrates good cause
                                                       If a participant is electronically                   documents electronically must file an                 by satisfying the three factors in 10 CFR
                                                    submitting a document to the NRC in                     exemption request, in accordance with                 2.309(c)(1)(i)–(iii).
                                                    accordance with the E-Filing rule, the                  10 CFR 2.302(g), with their initial paper               For further details with respect to
                                                    participant must file the document                      filing requesting authorization to                    these license amendment applications,
                                                    using the NRC’s online, Web-based                       continue to submit documents in paper                 see the application for amendment
                                                    submission form. In order to serve                      format. Such filings must be submitted                which is available for public inspection
                                                    documents through the Electronic                        by: (1) First class mail addressed to the             in ADAMS and at the NRC’s PDR. For
                                                    Information Exchange System, users                      Office of the Secretary of the                        additional direction on accessing
                                                    will be required to install a Web                       Commission, U.S. Nuclear Regulatory                   information related to this document,
                                                    browser plug-in from the NRC’s Web                      Commission, Washington, DC 20555–                     see the ‘‘Obtaining Information and
                                                    site. Further information on the Web-                   0001, Attention: Rulemaking and                       Submitting Comments’’ section of this
                                                    based submission form, including the                    Adjudications Staff; or (2) courier,                  document.
                                                    installation of the Web browser plug-in,                express mail, or expedited delivery
                                                                                                                                                                  Exelon Generation Company, LLC,
                                                    is available on the NRC’s public Web                    service to the Office of the Secretary,
                                                                                                                                                                  Docket Nos. 50–352 and 50–353,
                                                    site at http://www.nrc.gov/site-help/e-                 Sixteenth Floor, One White Flint North,
                                                                                                                                                                  Limerick Generating Station, Units 1
                                                    submittals.html.                                        11555 Rockville Pike, Rockville,
                                                                                                                                                                  and 2, Montgomery County,
                                                       Once a participant has obtained a                    Maryland, 20852, Attention:
                                                                                                                                                                  Pennsylvania
                                                    digital ID certificate and a docket has                 Rulemaking and Adjudications Staff.
                                                                                                            Participants filing a document in this                   Date of amendment request: February
                                                    been created, the participant can then                                                                        2, 2015. A publicly-available version is
                                                    submit a request for hearing or petition                manner are responsible for serving the
                                                                                                            document on all other participants.                   in ADAMS under Accession No.
                                                    for leave to intervene. Submissions                                                                           ML15036A486.
                                                                                                            Filing is considered complete by first-
                                                    should be in Portable Document Format                                                                            Description of amendment request:
                                                                                                            class mail as of the time of deposit in
                                                    (PDF) in accordance with NRC guidance                                                                         The proposed amendment would
                                                                                                            the mail, or by courier, express mail, or
                                                    available on the NRC’s public Web site                                                                        modify several Technical Specification
                                                                                                            expedited delivery service upon
                                                    at http://www.nrc.gov/site-help/e-                                                                            Limiting Conditions for Operation
                                                                                                            depositing the document with the
                                                    submittals.html. A filing is considered                                                                       (LCOs) and Surveillance Requirements
                                                                                                            provider of the service. A presiding
                                                    complete at the time the documents are                                                                        (SRs) to allow secondary containment
                                                                                                            officer, having granted an exemption
                                                    submitted through the NRC’s E-Filing                                                                          access openings to be opened
                                                                                                            request from using E-Filing, may require
                                                    system. To be timely, an electronic                                                                           intermittently under administrative
                                                                                                            a participant or party to use E-Filing if
                                                    filing must be submitted to the E-Filing                the presiding officer subsequently                    control.
                                                    system no later than 11:59 p.m. Eastern                 determines that the reason for granting                  Basis for proposed no significant
                                                    Time on the due date. Upon receipt of                   the exemption from use of E-Filing no                 hazards consideration determination:
                                                    a transmission, the E-Filing system                     longer exists.                                        As required by 10 CFR 50.91(a), the
                                                    time-stamps the document and sends                         Documents submitted in adjudicatory                licensee has provided its analysis of the
                                                    the submitter an email notice                           proceedings will appear in the NRC’s                  issue of no significant hazards
                                                    confirming receipt of the document. The                 electronic hearing docket which is                    consideration, which is presented
                                                    E-Filing system also distributes an email               available to the public at http://                    below:
                                                    notice that provides access to the                      ehd1.nrc.gov/ehd/, unless excluded                      1. Do the proposed changes involve a
                                                    document to the NRC’s Office of the                     pursuant to an order of the Commission,               significant increase in the probability or
                                                    General Counsel and any others who                      or the presiding officer. Participants are            consequences of an accident previously
                                                    have advised the Office of the Secretary                requested not to include personal                     evaluated?
                                                    that they wish to participate in the                    privacy information, such as social                     Response: No. The proposed changes allow
                                                    proceeding, so that the filer need not                  security numbers, home addresses, or                  temporary conditions during which the
                                                    serve the documents on those                                                                                  secondary containment LCO and SRs are not
                                                                                                            home phone numbers in their filings,
                                                    participants separately. Therefore,                                                                           met. The secondary containment is not an
                                                                                                            unless an NRC regulation or other law                 initiator of any accident previously
                                                    applicants and other participants (or                   requires submission of such                           evaluated. As a result, the probability of any
                                                    their counsel or representative) must                   information. However, a request to                    accident previously evaluated is not
                                                    apply for and receive a digital ID                      intervene will require including                      increased. The consequences of an accident
                                                    certificate before a hearing request/                   information on local residence in order               previously evaluated while utilizing the
                                                    petition to intervene is filed so that they             to demonstrate a proximity assertion of               proposed changes are no different than the
                                                    can obtain access to the document via                   interest in the proceeding. With respect              consequences of an accident while utilizing
                                                    the E-Filing system.                                                                                          the existing 4-hour allowed outage time for
                                                                                                            to copyrighted works, except for limited
                                                                                                                                                                  an inoperable reactor enclosure secondary
                                                       A person filing electronically using                 excerpts that serve the purpose of the                containment. As a result, the consequences of
                                                    the NRC’s adjudicatory E-Filing system                  adjudicatory filings and would                        an accident previously evaluated are not
                                                    may seek assistance by contacting the                   constitute a Fair Use application,                    significantly increased.
                                                    NRC Meta System Help Desk through                       participants are requested not to include
asabaliauskas on DSK5VPTVN1PROD with NOTICES




                                                                                                                                                                    Therefore, the proposed changes do not
                                                    the ‘‘Contact Us’’ link located on the                  copyrighted materials in their                        involve a significant increase in the
                                                    NRC’s public Web site at http://                        submission.                                           probability or consequences of an accident
                                                    www.nrc.gov/site-help/e-                                   Petitions for leave to intervene must              previously evaluated.
                                                    submittals.html, by email to                            be filed no later than 60 days from the                 2. Do the proposed changes create the
                                                                                                                                                                  possibility of a new or different kind of
                                                    MSHD.Resource@nrc.gov, or by a toll-                    date of publication of this notice.                   accident from any accident previously
                                                    free call at 1–866–672–7640. The NRC                    Requests for hearing, petitions for leave             evaluated?
                                                    Meta System Help Desk is available                      to intervene, and motions for leave to                  Response: No. The proposed changes do
                                                    between 8 a.m. and 8 p.m., Eastern                      file new or amended contentions that                  not alter the protection system design, create



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                                                                                   Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices                                               20023

                                                    new failure modes, or change any modes of               access openings to be opened                          doors are promptly closed after entry or exit,
                                                    operation. The proposed changes do not                  intermittently under administrative                   thereby restoring the secondary containment
                                                    involve a physical alteration of the plant, and         control.                                              boundary. The ability to open secondary
                                                    no new or different kind of equipment will                 Basis for proposed no significant                  containment access openings under
                                                    be installed. Consequently, there are no new                                                                  administrative control, even if it means the
                                                                                                            hazards consideration determination:
                                                    initiators that could result in a new or                                                                      secondary containment boundary is
                                                    different kind of accident.                             As required by 10 CFR 50.91(a), the                   temporarily not intact, is acceptable due to
                                                       Therefore, the proposed changes do not               licensee has provided its analysis of the             the low probability of an event that requires
                                                    create the possibility of a new or different            issue of no significant hazards                       secondary containment during the short time
                                                    kind of accident from any accident                      consideration, which is presented                     in which the secondary containment is open
                                                    previously evaluated.                                   below:                                                and the presence of administrative controls
                                                       3. Do the proposed changes involve a                                                                       to rapidly close the opening.
                                                                                                               1. Do the proposed changes involve a
                                                    significant reduction in a margin of safety?                                                                    Therefore, the proposed changes do not
                                                                                                            significant increase in the probability or
                                                       Response: No. The proposed changes allow                                                                   involve a significant reduction in a margin of
                                                                                                            consequences of an accident previously
                                                    temporary conditions during which the                                                                         safety.
                                                                                                            evaluated?
                                                    secondary containment LCO and SRs are not                  Response: No. The proposed changes allow              The NRC staff has reviewed the
                                                    met. Temporary conditions in which the                  temporary conditions during which the
                                                    secondary containment vacuum is below the                                                                     licensee’s analysis and, based on this
                                                                                                            secondary containment LCO and certain SRs             review, it appears that the three
                                                    required limit are acceptable provided the              are not met. The secondary containment is
                                                    conditions do not affect the ability of the                                                                   standards of 10 CFR 50.92(c) are
                                                                                                            not an initiator of any accident previously
                                                    Standby Gas Treatment System to establish               evaluated. As a result, the probability of any        satisfied. Therefore, the NRC staff
                                                    the required secondary containment vacuum.              accident previously evaluated is not                  proposes to determine that the
                                                    This condition is incorporated in the                   increased. The consequences of an accident            amendment request involves no
                                                    proposed changes by requiring the condition             previously evaluated while utilizing the              significant hazards consideration.
                                                    to be momentary or under administrative                 proposed changes are no different than the               Attorney for licensee: J. Bradley
                                                    control such that the conditions equivalent to          consequences of an accident while utilizing           Fewell, Esquire, Vice President and
                                                    the design condition can be quickly restored            the existing 4-hour Completion Time for an
                                                    should secondary containment vacuum be
                                                                                                                                                                  Deputy General Counsel, Exelon
                                                                                                            inoperable secondary containment. As a                Generation Company, LLC, 4300
                                                    required. Therefore, the safety function of the         result, the consequences of an accident
                                                    secondary containment is not affected. The              previously evaluated are not significantly
                                                                                                                                                                  Winfield Road, Warrenville, IL 60555.
                                                    allowance for both an inner and outer                   increased.                                               NRC Branch Chief: Douglas A.
                                                    secondary containment access door to be                    Therefore, the proposed changes do not             Broaddus.
                                                    open simultaneously for entry and exit does             involve a significant increase in the                    Northern States Power Company—
                                                    not affect the safety function of the secondary         probability or consequences of an accident            Minnesota, Docket Nos. 50–282 and 50–
                                                    containment as the doors are promptly closed            previously evaluated.                                 306, Prairie Island Nuclear Generating
                                                    after entry or exit, thereby restoring the                 2. Do the proposed changes create the              Plant, Units 1 and 2, Goodhue County,
                                                    secondary containment boundary.                         possibility of a new or different kind of             Minnesota
                                                       Therefore, the proposed changes do not               accident from any accident previously
                                                    involve a significant reduction in a margin of
                                                                                                                                                                     Date of amendment request:
                                                                                                            evaluated?
                                                    safety.                                                    Response: No. The proposed changes do
                                                                                                                                                                  December 11, 2014. A publicly-available
                                                                                                            not alter the protection system design, create        version is in ADAMS under Accession
                                                       The NRC staff has reviewed the                                                                             No. ML14349A749.
                                                                                                            new failure modes, or change any modes of
                                                    licensee’s analysis and, based on this                  operation. The proposed changes do not                   Brief description of amendment
                                                    review, it appears that the three                       involve a physical alteration of the plant; and       request: The proposed amendments
                                                    standards of 10 CFR 50.92(c) are                        no new or different kind of equipment will            would revise the technical specification
                                                    satisfied. Therefore, the NRC staff                     be installed. Consequently, there are no new          (TS) 3.3.3, ‘‘EM [Event Monitoring]
                                                    proposes to determine that the                          initiators that could result in a new or              Instrumentation,’’ to add the Steam
                                                    amendment request involves no                           different kind of accident.
                                                                                                                                                                  Generator Water Level—Narrow Range
                                                    significant hazards consideration.                         Therefore, the proposed changes do not
                                                                                                            create the possibility of a new or different          Instruments to Table 3.3.3–1. In
                                                       Attorney for licensee: J. Bradley                                                                          addition, the amendments would revise
                                                                                                            kind of accident from any accident
                                                    Fewell, Esquire, Vice President and                     previously evaluated.                                 Appendix B, ‘‘Additional Condition,’’ of
                                                    Deputy General Counsel, Exelon                             3. Do the proposed changes involve a               the Renewed Operating License for each
                                                    Generation Company, LLC, 4300                           significant reduction in a margin of safety?          unit regarding implementation of
                                                    Winfield Road, Warrenville, IL 60555.                      Response: No. The proposed changes allow           License Amendment Nos. 206 (Unit 1)
                                                       NRC Branch Chief: Doulas A.                          temporary conditions during which the                 and 193 (Unit 2) for Alternative Source
                                                    Broaddus.                                               secondary containment LCO and certain SRs             Term (AST), and removes two AST
                                                                                                            are not met. Temporary conditions in which
                                                    Exelon Generation Company, LLC, and                     the secondary containment is open is                  Additional Conditions for each unit that
                                                    PSEG Nuclear LLC, Docket Nos. 50–277                    acceptable provided the conditions do not             have been fulfilled.
                                                    and 50–278, Peach Bottom Atomic                         affect the ability of the Standby Gas                    Basis for proposed no significant
                                                    Power Station (PBAPS), Units 2 and 3,                   Treatment System to create a lower pressure           hazards consideration determination:
                                                    York and Lancaster Counties,                            in the secondary containment than in the              As required by 10 CFR 50.91(a), the
                                                    Pennsylvania                                            outside environment if required. This                 licensee provided its analysis of the
                                                                                                            condition is incorporated in the proposed             issue of no significant hazards
                                                      Date of amendment request: February                   changes by requiring the condition to be              consideration, which is presented
                                                    23, 2015. A publicly-available version is               under administrative control such that the
asabaliauskas on DSK5VPTVN1PROD with NOTICES




                                                                                                            conditions equivalent to the design condition
                                                                                                                                                                  below:
                                                    in ADAMS under Accession No.
                                                    ML15055A506.                                            can be quickly restored should secondary                1. Do the proposed amendments involve a
                                                      Description of amendment request:                     containment vacuum be required. Therefore,            significant increase in the probability or
                                                                                                            the safety function of the secondary                  consequences of an accident previously
                                                    The proposed amendment would                            containment is not affected. The allowance            evaluated?
                                                    modify a Technical Specification                        for both an inner and outer secondary                   Response: No.
                                                    Limiting Condition for Operation (LCO)                  containment door to be open simultaneously              The license amendment requests propose
                                                    and certain Surveillance Requirements                   for entry and exit does not affect the safety         to add Steam Generator Water Level (narrow
                                                    (SRs) to allow secondary containment                    function of the secondary containment as the          range) Instrumentation to Technical



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                                                    20024                          Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices

                                                    Specification Event Monitoring                          create new failure modes or mechanisms and            Services, Inc., 414 Nicollet Mall,
                                                    Instrumentation; revise license Additional              do not change plant conditions from which             Minneapolis, MN 55401.
                                                    Conditions to exclude Steam Generator Water             some new material interaction may create a              NRC Branch Chief: David L. Pelton.
                                                    Level (narrow range) Instrument                         new or different type of accident. Thus, the
                                                    implementation requirements from                        Technical Specification and license                   PSEG Nuclear LLC, Docket No. 50–354,
                                                    Alternative Source Term license amendment               Additional Condition changes do not create            Hope Creek Generating Station, Unit 1,
                                                    implementation; and remove Alternative                  new failure modes or mechanisms, nor do               Salem County, New Jersey
                                                    Source Term amendment implementation                    they generate new accident precursors.
                                                    Additional Conditions which have been                      Therefore, the proposed changes do not             PSEG Nuclear LLC, Docket Nos. 50–272
                                                    fulfilled.                                              create the possibility of a new or different          and 50–311, Salem Nuclear Generating
                                                       The Steam Generator Water Level (narrow              kind of accident from any previously                  Station, Unit Nos. 1 and 2, Salem
                                                    range) Instrumentation is not an accident               evaluated.                                            County, New Jersey
                                                    initiator and therefore addition of this                   The proposed removal of fulfilled
                                                    instrumentation to the Technical                        Additional Conditions is an administrative               Date of amendment request:
                                                    Specifications does not increase the                    change and thus does not create the                   December 9, 2014. A publicly-available
                                                    probability of an accident. Addition of this            possibility of a new or different kind of             version is in ADAMS under Accession
                                                    instrumentation to the Technical                        accident.                                             No. ML14343A926.
                                                    Specifications will bring it under the controls            3. Do the proposed amendments involve a               Description of amendment request:
                                                    and testing requirements of the Technical               significant reduction in a margin of safety?          The proposed amendments would
                                                    Specifications. The proposed change will not               Response: No.                                      revise the Public Service Electric and
                                                    increase the consequences of previously-                   The license amendment requests propose             Gas Nuclear LLC (PSEG) Environmental
                                                    evaluated accidents because the inclusion of            to add Steam Generator Water Level (narrow
                                                                                                            range) Instrumentation to Technical
                                                                                                                                                                  Protection Plans (Non-Radiological),
                                                    these instruments in the technical
                                                    specification improves their reliability to             Specification Event Monitoring                        Appendix B to the renewed facility
                                                    perform during a postulated accident.                   Instrumentation; revise license Additional            operating license (FOL) numbers DPR–
                                                    Therefore, the proposed Technical                       Conditions to exclude Steam Generator Water           70 and DPR–75 for Salem Nuclear
                                                    Specification changes do not involve a                  Level (narrow range) Instrument                       Generating Station, Units 1 and 2, and
                                                    significant increase in the probability or              implementation requirements from                      the renewed FOL number NPF–57 for
                                                    consequences of an accident previously                  Alternative Source Term license amendment             Hope Creek Generating Station. The
                                                    evaluated.                                              implementation; and remove Alternative                proposed changes will simplify the
                                                       The Alternative Source Term license                  Source Term amendment implementation
                                                                                                            Additional Conditions which have been
                                                                                                                                                                  Aquatic Monitoring section of Appendix
                                                    amendment was previously analyzed and
                                                                                                            fulfilled.                                            B, modify the criteria for reporting
                                                    approved for implementation. The proposed
                                                    Additional Condition revision to exclude                   Addition of this instrumentation to the            Unusual or Important Environmental
                                                    Steam Generator Water Level (narrow range)              Technical Specifications will bring it under          Events, and will clarify that PSEG
                                                    Instrumentation implementation                          the controls and testing requirements of the          Nuclear must adhere to the currently
                                                    requirements from Alternative Source Term               Technical Specifications. The proposed                applicable Biological Opinion.
                                                    license amendment implementation clarifies              change will not increase the consequences of             Basis for proposed no significant
                                                    implementation requirements and allows                  previously evaluated accidents because                hazards consideration determination:
                                                    completion of implementation activities.                instrument upgrade and the inclusion of               As required by 10 CFR 50.91(a), the
                                                    Since the Alternative Source Term                       these instruments in the Technical
                                                                                                            Specifications improve their reliability to
                                                                                                                                                                  licensee has provided its analysis of the
                                                    amendment was previously approved, this                                                                       issue of no significant hazards
                                                    change does not increase the probability or             perform during a postulated accident.
                                                    consequences of a previously evaluated                     Therefore, the proposed changes do not             consideration, which is presented
                                                    accident.                                               involve a significant reduction in a margin of        below, with NRC staff edits in square
                                                       Removal of license Additional Conditions             safety.                                               brackets:
                                                    which have been fulfilled is an                            The Alternative Source Term license
                                                                                                                                                                    1. Do the proposed changes involve a
                                                    administrative change and thus this change              amendment was previously analyzed and
                                                                                                                                                                  significant increase in the probability or
                                                    does not increase the probability or                    approved for implementation. The proposed
                                                                                                                                                                  consequences of an accident previously
                                                    consequences of a previously evaluated                  Additional Condition revision to exclude
                                                                                                                                                                  evaluated?
                                                    accident.                                               Steam Generator Water Level (narrow range)
                                                                                                                                                                    Response: No.
                                                       Therefore, the proposed changes do not               Instrumentation implementation
                                                                                                                                                                    The [Environmental Protection Plan] EPP
                                                    involve a significant increase in the                   requirements from Alternative Source Term
                                                                                                                                                                  provides for protection of non-radiological
                                                    probability or consequences of an accident              license amendment implementation clarifies
                                                                                                                                                                  environmental values during operation of the
                                                    previously evaluated.                                   implementation requirements and allows
                                                                                                                                                                  nuclear facility.
                                                       2. Do the proposed amendments create the             completion of implementation activities.
                                                                                                                                                                    The proposed changes do not have any
                                                    possibility of a new or different kind of               Since the Alternative Source Term
                                                                                                                                                                  impact on structures, systems and
                                                    accident from any accident previously                   [amendment] was previously approved, the
                                                                                                                                                                  components (SSCs) of the plant, and no effect
                                                    evaluated?                                              changes proposed in this license amendment            on plant operations. The proposed changes
                                                       Response: No.                                        do not involve a significant reduction in a           do not impact any accident initiators, or
                                                       The license amendment requests propose               margin of safety.                                     analyzed events, or assumed mitigation of
                                                    to add Steam Generator Water Level (narrow                 The proposed removal of fulfilled                  accident or transient events. The proposed
                                                    range) Instrumentation to Technical                     Additional Conditions is administrative in            changes do not result in the addition or
                                                    Specification Event Monitoring                          nature and thus does not involve a significant        removal of any equipment.
                                                    Instrumentation; revise license Additional              reduction in a margin of safety.                        Therefore, these proposed changes do not
                                                    Conditions to exclude Steam Generator Water                The NRC staff has reviewed the                     represent a significant increase in the
                                                    Level (narrow range) Instrument                         licensee’s analysis and, based on this                probability or consequences of an accident
asabaliauskas on DSK5VPTVN1PROD with NOTICES




                                                    implementation requirements from                        review, it appears that the three                     previously evaluated.
                                                    Alternative Source Term license amendment               standards of 10 CFR 50.92(c) are                        2. Do the proposed changes create the
                                                    implementation; and remove Alternative                                                                        possibility of a new or different kind of
                                                    Source Term amendment implementation
                                                                                                            satisfied. Therefore, the NRC staff                   accident from any accident previously
                                                    Additional Conditions which have been                   proposes to determine that the                        evaluated?
                                                    fulfilled.                                              amendment requests involve no                           Response: No.
                                                       The proposed Technical Specification                 significant hazards consideration.                      The proposed changes are administrative
                                                    changes and Additional Condition changes                   Attorney for licensee: Peter M. Glass,             in nature and do not involve a modification
                                                    and the resulting instrument upgrades do not            Assistant General Counsel, Xcel Energy                to the physical configuration of the plant



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                                                                                   Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices                                              20025

                                                    (i.e., no new equipment will be installed) or           As required by 10 CFR 50.91(a), the                     Therefore, the proposed amendment does
                                                    change in the methods governing normal                  licensee has provided its analysis of the             not involve a significant reduction in a
                                                    plant operation. The proposed changes will              issue of no significant hazards                       margin of safety.
                                                    not impose any new or different
                                                                                                            consideration, which is presented                        The NRC staff has reviewed the
                                                    requirements or introduce a new accident
                                                    initiator, accident precursor, or malfunction           below:                                                licensee’s analysis and, based on this
                                                    mechanism.                                                 1. Does the proposed amendment involve             review, it appears that the three
                                                       Therefore, the proposed changes do not               a significant increase in the probability or          standards of 10 CFR 50.92(c) are
                                                    create the possibility of a new or different            consequences of an accident previously                satisfied. Therefore, the NRC staff
                                                    kind of accident from any accident                      evaluated?                                            proposes to determine that the
                                                    previously evaluated.                                      Response: No.                                      amendment request involves no
                                                       3. Do the proposed changes involve a                    As indicated in the Updated Final Safety           significant hazards consideration.
                                                    significant reduction in a margin of safety?            Analysis Report Subsection 3.8.3.1, the                  Attorney for licensee: Ms. Kathryn M.
                                                       Response: No.                                        containment internal structures and                   Sutton, Morgan, Lewis & Bockius LLC,
                                                       The proposed changes are administrative              associated modules support the reactor
                                                    in nature.
                                                                                                                                                                  1111 Pennsylvania Avenue NW.,
                                                                                                            coolant system components and related
                                                       There is no change to any design basis,              piping systems and equipment. The increase            Washington, DC 20004–2514.
                                                    licensing basis or safety limit, and no change          in tolerance associated with the concrete                NRC Branch Chief: Lawrence
                                                    to any parameters; consequently no safety               thickness of four of these containment                Burkhart.
                                                    margins are affected.                                   internal structure walls do not involve any           Southern Nuclear Operating Company,
                                                       Therefore, the proposed changes do not               accident initiating components or events,
                                                    involve a significant reduction in a margin of                                                                Inc. Docket Nos. 52–025 and 52–026,
                                                                                                            thus leaving the probabilities of an accident
                                                    safety.                                                 unaltered. The increased tolerance does not           Vogtle Electric Generating Plant Units 3
                                                                                                            adversely affect any safety-related structures        and 4, Burke County, Georgia
                                                       Based upon the above, PSEG
                                                                                                            or equipment nor does the increased                      Date of amendment request: March 6,
                                                    concludes that the proposed change                      tolerance reduce the effectiveness of a
                                                    presents no significant hazards                                                                               2015. A publicly-available version is in
                                                                                                            radioactive material barrier. Thus, the               ADAMS under Accession No.
                                                    consideration under the standards set                   proposed changes would not affect any
                                                    forth in 10 CFR 50.92(c), and,                          safety-related accident mitigating function
                                                                                                                                                                  ML15065A362.
                                                    accordingly, a finding of ‘‘no significant              served by the containment internal
                                                                                                                                                                     Description of amendment request:
                                                    hazards consideration’’ is justified.                   structures.                                           The proposed amendment and
                                                       The NRC staff has reviewed the                          Therefore, the proposed amendment does             exemption identify portions of the
                                                    licensee’s analysis and, based on this                  not involve a significant increase in the             licensing basis that would more
                                                    review, and with the changes noted                      probability or consequences of an accident            appropriately be classified as Tier 2,
                                                    above in square brackets, it appears that               previously evaluated.                                 specifically the Tier 2* information on
                                                                                                               2. Does the proposed amendment create              Fire Area Figures 9A–1, 9A–2, 9A–3,
                                                    the three standards of 10 CFR 50.92(c)                  the possibility of a new or different kind of
                                                    are satisfied. Therefore, the NRC staff                                                                       9A–4, 9A–5, and 9A–201 in the Vogtle
                                                                                                            accident from any accident previously                 Electric Generating Plant Units 3 and 4
                                                    proposes to determine that the                          evaluated?
                                                    amendment request involves no                                                                                 Updated Final Safety Analysis Report.
                                                                                                               Response: No.
                                                    significant hazards consideration.                         The proposed tolerance increases do not
                                                                                                                                                                  With the reclassification, prior U.S.
                                                       Attorney for licensee: Jeffrie J. Keenan,            change the performance of the affected                Nuclear Regulatory Commission
                                                    PSEG Nuclear LLC—N21, P.O. Box 236,                     containment internal structures. As                   approval would continue to be required
                                                    Hancocks Bridge, NJ 08038.                              demonstrated by the continued conformance             for any safety significant changes to the
                                                       NRC Branch Chief: Douglas A.                         to the applicable codes and standards                 Fire Area Figures because any revisions
                                                    Broaddus.                                               governing the design of the structures, the           to that information would follow the
                                                                                                            walls with an increased concrete thickness            Tier 2 change process provided in 10
                                                    South Carolina Electric & Gas Company,                  tolerance continue to withstand the same              CFR part 52, Appendix D, Section
                                                    Docket Nos.: 52–027 and 52–028, Virgil                  effects as previously evaluated. There is no          VIII.B.5.
                                                    C. Summer Nuclear Station (VCSNS)                       change to the design function of the affected            Basis for proposed no significant
                                                    Units 2 and 3, Fairfield County, South                  modules and walls, and no new failure
                                                                                                                                                                  hazards consideration determination:
                                                                                                            mechanisms are identified as the same types
                                                    Carolina                                                                                                      As required by 10 CFR 50.91(a), the
                                                                                                            of accidents are presented to the walls before
                                                       Date of amendment request:                           and after the change.                                 licensee has provided its analysis of the
                                                    September 25, 2014; as supplemented                        Therefore, the proposed amendment does             issue of no significant hazards
                                                    by letter dated March 13, 2015.                         not create the possibility of a new or different      consideration, which is presented
                                                    Publicly-available versions are in                      kind of accident.                                     below:
                                                    ADAMS under Accession Nos.                                 3. Does the proposed amendment involve                1. Does the proposed amendment involve
                                                                                                            a significant reduction in a margin of safety?        a significant increase in the probability or
                                                    ML14268A388 and ML15072A306,                               Response: No.
                                                    respectively.                                                                                                 consequences of an accident previously
                                                                                                               The proposed change to increase the                evaluated?
                                                       Description of amendment request:                    concrete thickness tolerance does not alter
                                                    The proposed change would amend                                                                                  Response: No.
                                                                                                            any design function, design analysis, or                 The proposed amendment would reclassify
                                                    Combined License Nos. NPF–93 and                        safety analysis input or result, and sufficient       Fire Area Figures Tier 2* information. The
                                                    NPF–94 for the VCSNS Units 2 and 3 by                   margin exists to justify a departure from the         proposed amendment does not modify the
                                                    allowing changes to adjust the concrete                 standards identified in the underlying Tier 2         design, construction, or operation of any
                                                    wall thickness tolerances of four                       information with respect to the four affected
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                                                                                                                                                                  plant structures, systems, or components
                                                    Nuclear Island walls found in Tier 1. In                walls. As such, because the system continues          (SSCs), nor does it change any procedures or
                                                    addition, the changes include an update                 to respond to design basis accidents in the           method of control for any SSCs. Because the
                                                                                                            same manner as before without any changes             proposed amendment does not change the
                                                    to Tier 2 Subsection 3.8.3.6.1 to address               to the expected response of the structure, no         design, construction, or operation of any
                                                    the exceeded American Concrete                          safety analysis or design basis acceptance            SSCs, it does not adversely affect any design
                                                    Institute (ACI) 117 tolerance for the four              limit/criterion is challenged or exceeded by          function as described in the Updated Final
                                                    affected walls.                                         the proposed changes. Accordingly, no safety          Safety Analysis Report.
                                                       Basis for proposed no significant                    margin is reduced by the increase of the wall            Therefore, the proposed amendment does
                                                    hazards consideration determination:                    concrete thickness tolerance.                         not affect the probability of an accident



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                                                    20026                          Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices

                                                    previously evaluated. Similarly, because the            License Condition 2.C (17) that                       activities described in the DSAR and PSDAR
                                                    proposed amendment does not alter the                   approves the License Termination Plan                 [post-shutdown decommissioning activities
                                                    design or operation of the nuclear plant or             (LTP) and establishes the criteria for                report]. Thus, the proposed changes do not
                                                    any plant SSCs, the proposed amendment                                                                        affect the remaining plant systems,
                                                    does not represent a change to the
                                                                                                            determining when changes to the LTP                   structures, or components in a way not
                                                    radiological effects of an accident, and                require prior the U.S. Nuclear                        previously evaluated.
                                                    therefore, does not involve an increase in the          Regulatory Commission (NRC) approval.                    There are sections of the LTP that refer to
                                                    consequences of an accident previously                     Basis for proposed no significant                  the decommissioning activities still
                                                    evaluated.                                              hazards consideration determination:                  remaining (e.g.; removal of large components,
                                                       2. Does the proposed amendment create                As required by 10 CFR 50.91(a), the                   structure removal, etc.). However, these
                                                    the possibility of a new or different kind of           licensee has provided its analysis of the             activities are performed in accordance with
                                                    accident from any accident previously                   issue of no significant hazards                       approved work packages/steps and undergo a
                                                    evaluated?                                                                                                    10 CFR 50.59 screening prior to initiation.
                                                       Response: No.
                                                                                                            consideration, which is presented                     The proposed amendment merely makes
                                                       The proposed amendment would reclassify              below:                                                mention of these processes and does not
                                                    Fire Area Figures Tier 2* information. The                 (1) Does the change involve a significant          bring about physical changes to the facility.
                                                    proposed amendment is not a modification,               increase in the probability or consequences              Therefore, the facility conditions for which
                                                    addition to, or removal of any plant SSCs.              of an accident previously evaluated?                  the remaining postulated accident has been
                                                    Furthermore, the proposed amendment is not                 The only remaining accident after fuel             evaluated is still valid and no new accident
                                                    a change to procedures or method of control             transfer is completed in January 2015 is the          scenarios, failure mechanisms, or single
                                                    of the nuclear plant or any plant SSCs. The             Radwaste handling accident. Calculations              failures are introduced by this amendment.
                                                    only impact of this activity is the                     were performed to determine the dose at the           The system operating procedures are not
                                                    reclassification of information in the Updated          Exclusion Area Boundary that would result             affected. Therefore, the proposed changes
                                                    Final Safety Analysis Report. Because the               from dropping a High Integrity Container in           will not create the possibility of a new or
                                                    proposed amendment only reclassifies                    the former Interim Radwaste Storage Facility          different kind of accident from any accident
                                                    information and does not change the design,             (IRSF) such that its entire contents of               previously evaluated.
                                                    construction, or operation of the nuclear               radioactive, dewatered resin escape. A                   (3) Does the change involve a significant
                                                    plant or any plant operations, the                      fraction of the escaped resin is non                  reduction in a margin of safety?
                                                    amendment does not create the possibility of            mechanistically assumed to be released as                The LTP is a plan for demonstrating
                                                    a new or different kind of accident from any            airborne radioactivity and pass from the IRSF         compliance with the radiological criteria for
                                                    accident previously evaluated.                          directly to the environment, resulting in off-        license termination as provided in 10 CFR
                                                       3. Does the proposed amendment involve                                                                     20.1402 (Reference 5). The margin of safety
                                                                                                            site dose consequences. The solid-to-aerosol
                                                    a significant reduction in a margin of safety?                                                                defined in the statements of consideration for
                                                                                                            release fraction is assumed to be the worst
                                                       Response: No.                                                                                              the final rule on the Radiological Criteria for
                                                                                                            case non-mechanistic, mechanically initiated
                                                       The proposed amendment would reclassify                                                                    License Termination is described as the
                                                                                                            release fraction. The whole body and
                                                    Fire Area Figures Tier 2* information. The                                                                    margin between the 100 mrem/yr public dose
                                                                                                            inhalation dose at the closest point on the           limit established in 10 CFR 20.1301 for
                                                    proposed amendment is not a modification,
                                                    addition to, or removal of any plant SSCs.              Exclusion Area Boundary from the IRSF are             licensed operation and the 25 mrem/yr dose
                                                    Furthermore, the proposed amendment is not              then calculated.                                      limit to the average member of the critical
                                                    a change to procedures or method of control                The results of the radiological dose               group at a site considered acceptable for
                                                    of the nuclear plant or any plant SSCs. The             consequences for an accident involving the            unrestricted use (one of the criteria of 10 CFR
                                                    only impact of this activity is the                     failure of a High Integrity Container show            20.1402). This margin of safety accounts for
                                                    reclassification of information in the Updated          that the projected doses are insignificant in         the potential effect of multiple sources of
                                                    Final Safety Analysis Report.                           comparison to the 10 CFR 100 guidelines,              radiation exposure to the critical group.
                                                       Therefore, the proposed amendment does               and are less than the EPA [Environmental              Since the License Termination Plan is
                                                    not involve a significant reduction in a                Protection Agency] PAGs [protective action            designed to comply with the radiological
                                                    margin of safety.                                       guidelines]. The projected dose at the Low            criteria for license termination for
                                                                                                            Population Zone would be less than at the             unrestricted use, the LTP supports this
                                                       The NRC staff has reviewed the                       Exclusion Area Boundary and, since this
                                                    licensee’s analysis and, based on this                                                                        margin of safety.
                                                                                                            accident involves an instantaneous release, it           In addition, the LTP provides the
                                                    review, it appears that the three                       is also within the 10 CFR 100 guidelines.             methodologies and criteria that will be used
                                                    standards of 10 CFR 50.92(c) are                           The proposed change does not affect the            to perform remediation activities of residual
                                                    satisfied. Therefore, the NRC staff                     boundaries used to evaluate compliance with           radioactivity to demonstrate compliance with
                                                    proposes to determine that the                          liquid or gaseous effluent limits, and has no         the ALARA [as low as reasonably achievable]
                                                    amendment request involves no                           impact on plant operations. The proposed              criterion of 10 CFR 20.1402.
                                                    significant hazards consideration.                      changes do not have an adverse impact on                 Additionally, the LTP is designed with
                                                       Attorney for licensee: Mr. M. Stanford               the remaining decommissioning activities or           recognition that (a) the methods in
                                                                                                            any decommissioning related postulated                MARSSIM (Multi-Agency Radiation Survey
                                                    Blanton, Balch & Bingham LLP, 1710
                                                                                                            accident consequences.                                and Site Investigation Manual) (Reference 6)
                                                    Sixth Avenue North Birmingham, AL                          The proposed changes related to the                and (b) the building surface contamination
                                                    35203–2015.                                             approval of the LTP do not affect operating           levels are not directly applicable to use with
                                                       NRC Branch Chief: Lawrence                           procedures or administrative controls that            complex nonstructural components.
                                                    Burkhart.                                               have the function of preventing or mitigating         Therefore, the LTP states that nonstructural
                                                                                                            the remaining decommissioning design basis            components remaining in buildings (e.g.,
                                                    ZionSolutions LLC, Docket Nos. 50–295                   accident.                                             pumps, heat exchangers, etc.) will be
                                                    and 50–304, Zion Nuclear Power Station                     Therefore, the proposed changes do not             evaluated against the criteria of Regulatory
                                                    (Zion), Units 1 and 2, Lake County,                     involve a significant increase in the                 Guide 1.86 (Reference 7) to determine if the
                                                    Illinois                                                probability or consequences of any accident           components can be released for unrestricted
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                                                       Date of amendment request:                           previously evaluated.                                 use. The LTP also states that materials,
                                                    December 19, 2014, as supplemented on                      (2) Does the change create the possibility         surveyed and evaluated as a part of normal
                                                                                                            of a new or different kind of accident from           decommissioning activities and prior to
                                                    February 26, 2015. Publicly available                   any accident previously evaluated?                    implementation of the final radiation
                                                    versions are in ADAMS under                                The accident analysis for the facility             surveys, will be surveyed for release using
                                                    Accession Nos. ML15005A336 and                          related to decommissioning activities is              current site procedures to demonstrate
                                                    ML15061A230, respectively.                              described in the DSAR [defueled safety                compliance with the ‘‘no detectable’’ criteria.
                                                       Description of amendment request:                    analysis report]. The requested license               Such materials that do not pass these criteria
                                                    The proposed amendment would add                        amendment is consistent with the plant                will be controlled as contaminated.



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                                                                                   Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices                                           20027

                                                       Also, as previously discussed, the                   the Commission’s related letter, Safety               January 16 and December 19, 2014,
                                                    bounding accident for decommissioning is                Evaluation and/or Environmental                       provided additional information that
                                                    the resin container accident. Since the                 Assessment as indicated. All of these                 clarified the application, did not expand
                                                    bounding decommissioning accident results
                                                                                                            items can be accessed as described in                 the scope of the application as originally
                                                    in more airborne radioactivity than can be
                                                    released from other decommissioning events,             the ‘‘Obtaining Information and                       noticed, and did not change the staff’s
                                                    the margin of safety associated with the                Submitting Comments’’ section of this                 original proposed no significant hazards
                                                    consequences of decommissioning accidents               document.                                             consideration determination as
                                                    is not reduced by this activity.                                                                              published in the Federal Register.
                                                                                                            Arizona Public Service Company, et al.,
                                                       Thus, the proposed change does not
                                                    involve a significant reduction in the margin           Docket Nos. STN 50–528, STN 50–529,                     The Commission’s related evaluation
                                                    of safety.                                              and STN 50–530, Palo Verde Nuclear                    of the amendments is contained in a
                                                       The NRC staff has reviewed the                       Generating Station, Unit Nos. 1, 2, and               Safety Evaluation dated March 30, 2015.
                                                    licensee’s analysis and, based on this                  3, Maricopa County, Arizona                             No significant hazards consideration
                                                    review, it appears that the three                          Date of application for amendment:                 comments received: No.
                                                    standards of 10 CFR 50.92(c) are                        November 20, 2013, as supplemented by
                                                    satisfied. Therefore, the NRC staff                     letters dated November 20, 2013, and                  Duke Energy Carolinas, LLC, Docket
                                                    proposes to determine that the                          January 16 and December 19, 2014.                     Nos. 50–413 and 50–414, Catawba
                                                    amendment request involves no                              Brief description of amendment: The                Nuclear Station, Units 1 and 2, York
                                                    significant hazards consideration.                      amendment modified Technical                          County, South Carolina, Duke Energy
                                                       Attorney for licensee: Russ Workman,                 Specification (TS) Surveillance                       Carolinas, LLC, Docket Nos. 50–369 and
                                                    Deputy General Counsel,                                 Requirement (SR) 3.1.4.1 utilizing                    50–370, McGuire Nuclear Station, Units
                                                    EnergySolutions, 423 West 300 South,                    Westinghouse Electric Company LLC’s                   1 and 2, Mecklenburg County, North
                                                    Suite 200, Salt Lake City, UT 84101.                    topical report WCAP–16011–NP–A,                       Carolina
                                                       NRC Branch Chief: Bruce Watson.                      Revision 0, ‘‘Startup Test Activity
                                                                                                            Reduction [STAR] Program,’’ February                     Date of application for amendments:
                                                    III. Notice of Issuance of Amendments                                                                         November 14, 2013, as supplemented by
                                                    to Facility Operating Licenses and                      2005. The changes are consistent with
                                                                                                            NRC-approved Technical Specification                  letters dated June 27, and November 10,
                                                    Combined Licenses                                                                                             2014.
                                                                                                            Task Force (TSTF) Standard Technical
                                                       During the period since publication of               Specification Change Traveler TSTF–                      Brief description of amendments: The
                                                    the last biweekly notice, the                           486, Revision 2. The use of WCAP–                     amendments approve the use of DPC–
                                                    Commission has issued the following                     16011–NP–A is justified by the licensee               3001–NE–P, Revision 1,
                                                    amendments. The Commission has                          in WCAP–17787–NP, Revision 0, ‘‘Palo                  ‘‘Multidimensional Reactor Transients
                                                    determined for each of these                            Verde Nuclear Generating Station STAR                 and Safety Analysis Physics Parameters
                                                    amendments that the application                         Program Implementation Report,’’                      Methodology.’’
                                                    complies with the standards and                         August 2013.
                                                    requirements of the Atomic Energy Act                                                                            Date of issuance: March 25, 2015.
                                                                                                               The amendments also modify SR
                                                    of 1954, as amended (the Act), and the                  3.1.4.2 not to require the moderator                     Effective date: This license
                                                    Commission’s rules and regulations.                     temperature coefficient (MTC)                         amendment is effective as of its date of
                                                    The Commission has made appropriate                     determination if the result of the MTC                issuance and shall be implemented
                                                    findings as required by the Act and the                 determination required in TS 3.1.4.1 is               within 30 days of issuance.
                                                    Commission’s rules and regulations in                   within a certain tolerance of the                        Amendment Nos.: 274, 270, 277, and
                                                    10 CFR Chapter I, which are set forth in                corresponding design value. This                      257. A publicly-available version of the
                                                    the license amendment.                                  change is based on the methods                        application is in ADAMS under
                                                       A notice of consideration of issuance                described in Combustion Engineering                   Accession No. ML15027A366;
                                                    of amendment to facility operating                      Owners Group Report CE NPSD–911–A                     documents related to these amendments
                                                    license or combined license, as                         and Amendment 1–A, ‘‘Analysis of                      are listed in the Safety Evaluation
                                                    applicable, proposed no significant                     Moderator Temperature Coefficients in                 enclosed with the amendments.
                                                    hazards consideration determination,                    Support of a Change in the Technical
                                                    and opportunity for a hearing in                                                                                 Renewed Facility Operating License
                                                                                                            Specifications End-of-Cycle Negative
                                                    connection with these actions, was                                                                            Nos. NPF–35, NPF–52, NPF–9, and
                                                                                                            MTC Limits,’’ September 2000.
                                                    published in the Federal Register as                       Date of issuance: March 30, 2015.                  NPF–17: Amendments revised the
                                                    indicated.                                                 Effective date: As of the date of                  licenses.
                                                       Unless otherwise indicated, the                      issuance and shall be implemented                        Date of initial notice in Federal
                                                    Commission has determined that these                    within 90 days from the date of                       Register: February 27, 2014 (79 FR
                                                    amendments satisfy the criteria for                     issuance.                                             11147). The supplemental letters dated
                                                    categorical exclusion in accordance                        Amendment No.: Unit 1–195; Unit 2–                 June 27, and November 10, 2014,
                                                    with 10 CFR 51.22. Therefore, pursuant                  195; Unit 3–195. A publicly-available                 provided additional information that
                                                    to 10 CFR 51.22(b), no environmental                    version is in ADAMS under Accession                   clarified the application, did not expand
                                                    impact statement or environmental                       No. ML15070A124; documents related                    the scope of the application as originally
                                                    assessment need be prepared for these                   to these amendments are listed in the                 noticed, and did not change the staff’s
                                                    amendments. If the Commission has
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                                                                                                            Safety Evaluation enclosed with the                   original proposed no significant hazards
                                                    prepared an environmental assessment                    amendments.                                           consideration determination as
                                                    under the special circumstances                            Renewed Facility Operating License                 published in the Federal Register.
                                                    provision in 10 CFR 51.22(b) and has                    Nos. NPF–41, NPF–51, and NPF–74: The
                                                    made a determination based on that                      amendment revised the Operating                          The Commission’s related evaluation
                                                    assessment, it is so indicated.                         Licenses and Technical Specifications.                of the amendments is contained in a
                                                       For further details with respect to the                 Date of initial notice in Federal                  Safety Evaluation dated March 25, 2015.
                                                    action see (1) the applications for                     Register: February 27, 2014 (79 FR                       No significant hazards consideration
                                                    amendment, (2) the amendment, and (3)                   11146). The supplemental letters dated                comments received: No.


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                                                    20028                          Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices

                                                    Duke Energy Florida, Inc., et al., Docket               Settings] Functions,’’ Option A. The                    No significant hazards consideration
                                                    No. 50–302, Crystal River Unit 3                        notice of availability of the models for              comments received: No.
                                                    Nuclear Generating Plant, Citrus                        plant-specific adoption of TSTF–493,
                                                                                                                                                                  Entergy Operations, Inc., Docket No. 50–
                                                    County, Florida                                         Revision 4, was announced in the
                                                                                                                                                                  368, Arkansas Nuclear One, Unit No. 2
                                                       Date of amendment request:                           Federal Register on May 11, 2010 (75
                                                                                                                                                                  (ANO–2), Pope County, Arkansas
                                                    September 26, 2013, as supplemented                     FR 26294).
                                                                                                               Date of issuance: March 27, 2015.                     Date of application for amendment:
                                                    by letters dated March 28, May 23, and                                                                        March 26, 2013, as supplemented by
                                                                                                               Effective date: As of its date of
                                                    October 6, 2014.                                                                                              letters dated December 12, 2013, and
                                                                                                            issuance and shall be implemented
                                                       Brief description of amendment: The
                                                                                                            prior to restarting from refueling outage             May 12, August 19, October 22, and
                                                    amendment revised the facility’s
                                                                                                            R–22, scheduled for spring 2015.                      December 5, 2014.
                                                    emergency plan and emergency action                                                                              Brief description of amendment: The
                                                                                                               Amendment No.: 232. A publicly-
                                                    level scheme to reflect the low                                                                               amendment revised the ANO–2
                                                                                                            available version is in ADAMS under
                                                    likelihood of any credible accident at                                                                        Technical Specification (TS)
                                                                                                            Accession No. ML15063A010;
                                                    the facility in its permanently shutdown                                                                      requirements for end states associated
                                                                                                            documents related to this amendment
                                                    and defueled condition that could result                                                                      with the implementation of the NRC-
                                                                                                            are listed in the Safety Evaluation
                                                    in radiological releases requiring offsite                                                                    approved Topical Report NPSD–1186,
                                                                                                            enclosed with the amendment.
                                                    protective measures.                                       Renewed Facility Operating License                 Revision 0, ‘‘Technical Justification for
                                                       Date of issuance: March 31, 2015.                    No. NPF–21: The amendment revised                     the Risk Informed Modification to
                                                       Effective date: As of the date of                    the Facility Operating License and                    Selected Required Action End States for
                                                    issuance and shall be implemented                       Technical Specifications.                             CEOG [Combustion Engineering Owners
                                                    within 60 days of issuance.                                Date of initial notice in Federal                  Group] Member PWRs [Pressurized-
                                                       Amendment No.: 246. A publicly-                      Register: July 22, 2014 (79 FR 42544).                Water Reactors],’’ as well as Required
                                                    available version is in ADAMS under                     The supplemental letters dated August                 Actions revised by a specific Note in TS
                                                    Accession No. ML15027A209;                              28, November 6, and December 15,                      Task Force (TSTF) change traveler
                                                    documents related to this amendment                     2014, provided additional information                 TSTF–422, Revision 2, ‘‘Change in
                                                    are listed in the Safety Evaluation                     that clarified the application, did not               Technical Specifications End States (CE
                                                    enclosed with the amendment.                            expand the scope of the application as                NPSD–1186).’’ The Notice of
                                                       Facility Operating License No. DPR–                  originally noticed, and did not change                Availability for TSTF–422, Revision 2,
                                                    72: Amendment revised the emergency                     the staff’s original proposed no                      was announced in the Federal Register
                                                    plan and the emergency action levels.                   significant hazards consideration                     on April 7, 2011 (76 FR 19510).
                                                       Date of initial notice in Federal                    determination as published in the                        Date of issuance: March 31, 2015.
                                                    Register: January 7, 2014 (79 FR 857).                  Federal Register.                                        Effective date: As of the date of
                                                    The supplemental letters dated March                       The Commission’s related evaluation                issuance and shall be implemented
                                                    28, May 23, and October 6, 2014,                        of the amendment is contained in a                    within 90 days from the date of
                                                    provided additional information that                    Safety Evaluation dated March 27, 2015.               issuance.
                                                    clarified the application, did not expand                  No significant hazards consideration                  Amendment No.: 301. A publicly-
                                                    the scope of the application as originally              comments received: No.                                available version is in ADAMS under
                                                    noticed, and did not change the staff’s                                                                       Accession No. ML15068A319;
                                                    original proposed no significant hazards                Energy Northwest, Docket No. 50–397,                  documents related to this amendment
                                                    consideration determination as                          Columbia Generating Station, Benton                   are listed in the Safety Evaluation
                                                    published in the Federal Register.                      County, Washington                                    enclosed with the amendment.
                                                       The Commission’s related evaluation                     Date of application for amendment:                    Renewed Facility Operating License
                                                    of the amendment is contained in a                      June 25, 2014.                                        No. NPF–6: Amendment revised the
                                                    Safety Evaluation dated March 31, 2015.                    Brief description of amendment: The                Technical Specifications/license.
                                                       No significant hazards consideration                 amendment revised the Columbia                           Date of initial notice in Federal
                                                    comments received: No.                                  Generating Station Cyber Security Plan                Register: July 23, 2013 (78 FR 44172).
                                                    Energy Northwest, Docket No. 50–397,                    (CSP) Milestone 8 full implementation                 The supplemental letters dated
                                                    Columbia Generating Station, Benton                     date as set forth in the CSP                          December 12, 2013, and May 12, August
                                                    County, Washington                                      Implementation Schedule.                              19, October 22, and December 5, 2014,
                                                                                                               Date of issuance: March 27, 2015.                  provided additional information that
                                                       Date of application for amendment:                      Effective date: As of its date of                  clarified the application, did not expand
                                                    March 24, 2014, as supplemented by                      issuance and shall be implemented                     the scope of the application as originally
                                                    letters dated May 8, August 28,                         within 30 days from the date of                       noticed, and did not change the staff’s
                                                    November 6, and December 15, 2014.                      issuance.                                             original proposed no significant hazards
                                                       Brief description of amendment: The                     Amendment No.: 231. A publicly-                    consideration determination as
                                                    amendment revised Technical                             available version is in ADAMS under                   published in the Federal Register.
                                                    Specification (TS) Table 3.3.1.1–1,                     Accession No. ML15042A464;                               The Commission’s related evaluation
                                                    ‘‘Reactor Protection System                             documents related to this amendment                   of the amendment is contained in a
                                                    Instrumentation,’’ Functions 7.a and 7.b                are listed in the Safety Evaluation                   Safety Evaluation dated March 31, 2015.
                                                    to update Scram Discharge Volume
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                                                                                                            enclosed with the amendment.                             No significant hazards consideration
                                                    instrumentation nomenclature, add a                        Renewed Facility Operating License                 comments received: No.
                                                    surveillance requirement (SR), which                    No. NPF–21: The amendment revised
                                                    was previously omitted, and add                         the Facility Operating License.                       Exelon Generation Company, LLC,
                                                    footnotes to an SR consistent with TS                      Date of initial notice in Federal                  Docket Nos. 50–254 and 50–265, Quad
                                                    Task Force (TSTF) change traveler                       Register: October 7, 2014 (79 FR 60518).              Cities Nuclear Power Station, Units 1
                                                    TSTF–493, Revision 4, ‘‘Clarify                            The Commission’s related evaluation                and 2, Rock Island County, Illinois
                                                    Application of Setpoint Methodology                     of the amendment is contained in a                      Date of application for amendments:
                                                    for LSSS [Limiting Safety System                        Safety Evaluation dated March 27, 2015.               June 10, 2013, as supplemented by


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                                                                                   Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices                                          20029

                                                    letters dated October 24, 2013, March 5,                  Date of initial notice in Federal                   Specification 5.5.14, ‘‘Containment
                                                    2014, and February 4, 2015.                             Register: May 6, 2014 (79 FR 25901).                  Leakage Rate Testing Program,’’ by
                                                       Brief description of amendments: The                 The supplemental letter dated                         adopting Nuclear Energy Institute (NEI)
                                                    amendment revises the technical                         November 3, 2014, provided additional                 94–01, Revision 3–A, ‘‘Industry
                                                    specifications (TSs), Surveillance                      information that clarified the                        Guideline for Implementing
                                                    Requirements 3.8.4.2 and 3.8.4.5 to add                 application, did not expand the scope of              Performance-Based Option of 10 CFR
                                                    new acceptance criteria for total battery               the application as originally noticed,                part 50, Appendix J’’ (ADAMS
                                                    connection resistance.                                  and did not change the staff’s original               Accession No. ML12221A202), and
                                                       Date of issuance: March 30, 2015.                    proposed no significant hazards                       Section 4.1, ‘‘Limitations and
                                                       Effective date: As of the date of                    consideration determination as                        Conditions for NEI TR 94–01, Revision
                                                    issuance and shall be implemented                       published in the Federal Register.                    2’’ of the NRC Safety Evaluation Report
                                                    within 30 days from the date of                           The Commission’s related evaluation                 in NEI 94–01, Revision 2–A, dated
                                                    issuance.                                               of this amendment is contained in a                   October 2008 (ADAMS Accession No.
                                                       Amendment Nos.: 256 and 251. A                       Safety Evaluation dated March 30, 2015.               ML100620847), as the implementing
                                                    publicly-available version is in ADAMS                    No significant hazards consideration                document for the performance-based
                                                    under Accession No. ML15056A772.                        comments received: No.                                Option B of 10 CFR part 50, Appendix
                                                    Documents related to these amendments                                                                         J.
                                                    are listed in the Safety Evaluation                     FirstEnergy Nuclear Operating
                                                                                                                                                                     Date of issuance: March 30, 2015.
                                                    enclosed with the amendments.                           Company, Docket No. 50–440, Perry
                                                                                                                                                                     Effective date: As of the date of
                                                       Renewed Facility Operating License                   Nuclear Power Plant, Unit No. 1, Lake
                                                                                                                                                                  issuance and shall be implemented
                                                    Nos. DPR–29 and DPR–30: The                             County, Ohio
                                                                                                                                                                  within 60 days of issuance.
                                                    amendments revised the TSs and                             Date of application for amendment:                    Amendment Nos.: 326 for Unit 1 and
                                                    License.                                                October 8, 2014, as supplemented by a                 309 for Unit 2. A publicly-available
                                                       Date of initial notice in Federal                    letter dated February 12, 2015.                       version is in ADAMS under Accession
                                                    Register: September 3, 2013 (78 FR                         Brief description of amendment: The                No. ML15072A264; documents related
                                                    54283). The October 24, 2013, March 5,                  amendment revised the technical                       to this amendment are listed in the
                                                    2014, and February 4, 2015,                             specifications (TSs) safety limit                     Safety Evaluation enclosed with the
                                                    supplements contained clarifying                        minimum critical power ratio value for                amendment.
                                                    information and did not change the NRC                  single recirculation-loop-operation to                   Renewed Facility Operating License
                                                    staff’s initial proposed finding of no                  support the use of GNF–2 fuel during                  Nos. DPR–58 and DPR–74: Amendments
                                                    significant hazards consideration.                      the next operating cycle.                             revise the Renewed Facility Operating
                                                       The Commission’s related evaluation                     Date of issuance: March 27, 2015.                  Licenses and Technical Specifications.
                                                    of the amendments is contained in a                        Effective date: As of the date of                     Date of initial notice in Federal
                                                    Safety Evaluation dated March 30, 2015.                 issuance and shall be implemented                     Register: May 27, 2014 (79 FR 30188).
                                                       No significant hazards consideration                 within 30 days.                                       The supplemental letters dated
                                                    comments received: No.                                     Amendment No.: 165. A publicly-                    September 30, 2014, December 16, 2014,
                                                                                                            available version is in ADAMS under                   January 15, 2015, and February 20,
                                                    Exelon Generation Company, LLC,                         Accession No. ML15075A091;                            2015, provided additional information
                                                    Docket No. 50–219, Oyster Creek                         documents related to this amendment                   that clarified the application, did not
                                                    Nuclear Generating Station (OCNGS),                     are listed in the Safety Evaluation                   expand the scope of the application as
                                                    Ocean County, New Jersey                                enclosed with the amendment.                          originally noticed, and did not change
                                                       Date of application for amendment:                      Facility Operating License No. NPF–                the staff’s original proposed no
                                                    December 19, 2013, as supplemented by                   58: This amendment revised the TSs                    significant hazards consideration
                                                    letters dated January 31, 2014, and                     and License.                                          determination as published in the
                                                    November 3, 2014.                                          Date of initial notice in Federal                  Federal Register.
                                                       Brief description of amendment: The                  Register: February 13, 2015 (80 FR                       The Commission’s related evaluation
                                                    amendment revised Renewed Facility                      5819). The February 12, 2015,                         of the amendment is contained in a
                                                    Operating License No. DPR–16 for                        supplement contained clarifying                       Safety Evaluation dated March 30, 2015.
                                                    OCNGS. Specifically, the changes                        information and did not change the NRC                   No significant hazards consideration
                                                    implement the use of an alternative                     staff’s initial proposed finding of no                comments received: No.
                                                    measure that required prior NRC review                  significant hazards consideration.
                                                    and approval pursuant to Title 10 of the                   The Commission’s related evaluation                NextEra Energy Seabrook, LLC, Docket
                                                    Code of Federal Regulations (10 CFR),                   of the amendment is contained in a                    No. 50–443, Seabrook Station, Unit No.
                                                    Section 73.55(r), related to controlling                Safety Evaluation dated March 27, 2015.               1, Rockingham County, New Hampshire
                                                    vital area access for certain portions of                  No significant hazards consideration                  Date of amendment request:
                                                    the Reactor Building at OCNGS.                          comments received: No.                                September 24, 2014, as supplemented
                                                       Date of Issuance: March 30, 2015.                                                                          by letter dated December 11, 2014.
                                                       Effective date: As of the date of                    Indiana Michigan Power Company,                          Description of amendment request:
                                                    issuance and shall be implemented                       Docket Nos. 50–315 and 50–316, Donald                 The amendment changes the Technical
                                                    within 60 days.                                         C. Cook Nuclear Plant, Units 1 and 2,                 Specifications (TSs) and the Facility
                                                       Amendment No.: 285. A publicly-                      Berrien County, Michigan                              Operating License. The change deletes
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                                                    available version is in ADAMS under                        Date of amendment requests: March                  the Functional Unit ‘‘Cold Leg Injection,
                                                    Accession No. ML14329A625;                              7, 2014, as supplemented by letters                   P–15’’ from TS 3.3.2, ‘‘Engineered
                                                    documents related to this amendment                     dated September 30, 2014, December 16,                Safety Features Actuation System
                                                    are listed in the Safety Evaluation                     2014, January 15, 2015, and February                  Instrumentation,’’ and changes License
                                                    enclosed with the amendment.                            20, 2015.                                             Condition 2.K, ‘‘Inadvertent Actuation
                                                       Renewed Facility Operating License                      Brief description of amendments: The               of the Emergency Core Cooling System
                                                    No. DPR–16: The amendment revised                       amendments revised the Donald C. Cook                 (ECCS).’’
                                                    the license and technical specifications.               Nuclear Plant, Units 1 and 2, Technical                  Date of issuance: March 31, 2015.


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                                                    20030                          Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices

                                                       Effective date: As of its date of                       Date of issuance: March 30, 2015.                  consideration determination as
                                                    issuance, and shall be implemented                         Effective date: As of the date of                  published in the Federal Register.
                                                    within 30 days.                                         issuance, to be implemented within 60                   The Commission’s related evaluation
                                                       Amendment No.: 145. A publicly-                      days.                                                 of the amendment is contained in the
                                                    available version is in ADAMS under                        Amendment Nos.: 307 and 289. A                     Safety Evaluation dated December 16,
                                                    Accession No. ML15002A251;                              publicly-available version is in ADAMS                2014.
                                                    documents related to this amendment                     under Accession No. ML15063A293;                        No significant hazards consideration
                                                    are listed in the Safety Evaluation                     documents related to these amendments                 comments received: No.
                                                    enclosed with the amendment.                            are listed in the Safety Evaluation
                                                       Facility Operating License No. NPF–                                                                        South Carolina Electric & Gas Company,
                                                                                                            enclosed with the amendments.                         Docket Nos. 52–027 and 52–028, Virgil
                                                    86: Amendment revised the Facility                         Renewed Facility Operating License
                                                    Operating License and TSs.                                                                                    C. Summer Nuclear Station (VCSNS)
                                                                                                            Nos. DPR–70 and DPR–75: The                           Units 2 and 3, Fairfield County, South
                                                       Date of initial notice in Federal                    amendments revised the Technical
                                                    Register: January 6, 2015, (80 FR 525).                                                                       Carolina
                                                                                                            Specifications and the License.
                                                       The Commission’s related evaluation                                                                           Date of amendment request: June 20,
                                                                                                               Date of initial notice in Federal
                                                    of the amendment is contained in a                                                                            2014, and supplemented by letter dated
                                                    Safety Evaluation dated March 31, 2015.                 Register: June 6, 2014 (79 FR 32770).
                                                                                                               The Commission’s related evaluation                August 6, 2014.
                                                       No significant hazards consideration                                                                          Description of amendment: The
                                                    comments received: No.                                  of the amendments is contained in a
                                                                                                            Safety Evaluation dated March 30, 2015.               amendment revises the Updated Final
                                                    Omaha Public Power District, Docket                                                                           Safety Analysis Report in regard to Tier
                                                                                                               No significant hazards consideration
                                                    No. 50–285, Fort Calhoun Station, Unit                                                                        2 and Tier 2* information related to fire
                                                                                                            comments received: No.
                                                    No. 1, Washington County, Nebraska                                                                            area boundaries. These changes include:
                                                                                                            South Carolina Electric & Gas Company,                adding of three new fire zones in the
                                                       Date of amendment request:                           Docket Nos. 52–027 and 52–028, Virgil                 middle annulus to provide fire barrier
                                                    November 7, 2014.                                       C. Summer Nuclear Station (VCSNS)                     enclosures for the Class 1E Electrical
                                                       Brief description of amendment: The
                                                                                                            Units 2 and 3, Fairfield County, South                Divisions B, C, and D containment
                                                    amendment revised Technical
                                                                                                            Carolina                                              penetrations; and eliminating the Class
                                                    Specification (TS) 3.1, Table 3–3, Item
                                                    3.c concerning containment wide range                      Date of amendment request: August 5,               1E Electrical Division A enclosure and
                                                    radiation monitors to correct a                         2014, revised by letter dated August 28,              making the Division A containment
                                                    typographical error introduced in TS                    2014, and supplemented by letter dated                penetration assemblies part of the
                                                    Amendment No. 152.                                      November 3, 2014 (Non-Public).                        existing middle annulus fire zone.
                                                       Date of issuance: March 27, 2015.                                                                             Date of issuance: December 30, 2014.
                                                                                                               Description of amendment: The
                                                       Effective date: As of the date of                                                                             Effective date: As of the date of
                                                                                                            amendment revises the design of
                                                    issuance and shall be implemented                                                                             issuance and shall be implemented
                                                                                                            connections between reinforced
                                                    within 30 days from the date of                                                                               within 90 days of issuance.
                                                                                                            concrete (RC) and steel plate concrete                   Amendment No.: 22. A publicly-
                                                    issuance.                                               composite construction (SC) included in
                                                       Amendment No.: 281. A publicly-                                                                            available version is in ADAMS under
                                                                                                            the VCSNS Units 2 and 3 updated Final                 Accession No. ML14328A233;
                                                    available version is in ADAMS under                     Safety Analysis Report and changes to
                                                    Accession No. ML15035A203;                                                                                    documents related to this amendment
                                                                                                            the Technical Report, ‘‘APP–GW–GLR–                   are listed in the Safety Evaluation
                                                    documents related to this amendment                     602, AP1000 Shield Building Design
                                                    are listed in the Safety Evaluation                                                                           enclosed with the amendment.
                                                                                                            Details for Select Wall and RC/SC                        Facility Combined Licenses No. NPF–
                                                    enclosed with the amendment.                            Connections,’’ (prepared by
                                                       Renewed Facility Operating License                                                                         93 and NPF–94: Amendment revised the
                                                                                                            Westinghouse Electric Company and                     Facility Combined Licenses.
                                                    No. DPR–40: The amendment revised                       reviewed by the U.S. Nuclear Regulatory
                                                    the license and Technical                                                                                        Date of initial notice in Federal
                                                                                                            Commission as part of the design                      Register: October 28, 2014 (79 FR
                                                    Specifications.                                         certification rule).
                                                       Date of initial notice in Federal                                                                          64228).
                                                                                                               Date of issuance: December 16, 2014.                  The Commission’s related evaluation
                                                    Register: January 20, 2015 (80 FR 2751).
                                                       The Commission’s related evaluation                     Effective date: As of the date of                  of the amendment is contained in the
                                                    of the amendment is contained in a                      issuance and shall be implemented                     Safety Evaluation dated December 30,
                                                    safety evaluation dated March 27, 2015.                 within 90 days of issuance.                           2014.
                                                       No significant hazards consideration                    Amendment No.: 21. A publicly-                        No significant hazards consideration
                                                    comments received: No.                                  available version is in ADAMS under                   comments received: No.
                                                                                                            Accession No. ML14339A717;
                                                    PSEG Nuclear LLC, Docket Nos. 50–272                    documents related to this amendment                   Union Electric Company, Docket No.
                                                    and 50–311, Salem Nuclear Generating                    are listed in the Safety Evaluation                   50–483, Callaway Plant, Unit 1,
                                                    Station, Unit Nos. 1 and 2, Salem                       enclosed with the amendment.                          Callaway County, Missouri
                                                    County, New Jersey                                         Facility Combined Licenses No. NPF–                   Date of application for amendment:
                                                       Date of application for amendments:                  93 and NPF–94: Amendment revised the                  December 6, 2013, as supplemented by
                                                    March 24, 2014.                                         Facility Combined Licenses.                           letters dated September 2 and December
                                                       Brief description of amendments: The                    Date of initial notice in Federal                  11, 2014, and February 3, 2015.
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                                                    amendments approved a change to                         Register: September 30, 2014 (79 FR                      Brief description of amendment: The
                                                    revise Surveillance Requirements                        58824). The supplemental letter dated                 amendment changed the licensing basis
                                                    4.2.1.3, 4.2.1.4, and 4.2.2.2.f associated              November 3, 2014, provided additional                 as described in the Final Safety Analysis
                                                    with Power Distribution Limits                          information that clarified the                        Report (FSAR)-Standard Plant Section
                                                    Technical Specification (TS) 3/4.2.1,                   application, did not expand the scope of              3.6.2.1.2.4, ‘‘ASME [American Society
                                                    ‘‘Axial Flux Difference (AFD),’’ and TS                 the application as originally noticed,                of Mechanical Engineers] Section III and
                                                    3/4.2.2, ‘‘Heat Flux Hot Channel                        and did not change the staff’s original               Non-Nuclear Piping-Moderate-Energy,’’
                                                    Factor—FQ(Z).’’                                         proposed no significant hazards                       and FSAR-Standard Plant Table 3.6–2,


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                                                                                   Federal Register / Vol. 80, No. 71 / Tuesday, April 14, 2015 / Notices                                            20031

                                                    ‘‘Design Comparison to Regulatory                       ACTION: Exemption and combined                          • NRC’s PDR: You may examine and
                                                    Positions of Regulatory Guide 1.46,                     license amendment; issuance.                          purchase copies of public documents at
                                                    Revision 0, dated May 1973, titled                                                                            the NRC’s PDR, Room O1–F21, One
                                                    ‘Protection Against Pipe Whip Inside                    SUMMARY:    The U.S. Nuclear Regulatory               White Flint North, 11555 Rockville
                                                    Containment,’ ’’ in particular regard to                Commission (NRC) is granting an                       Pike, Rockville, Maryland 20852.
                                                    the high-density polyethylene (HDPE)                    exemption to allow a departure from the               FOR FURTHER INFORMATION CONTACT:
                                                    piping installed in ASME Class 3 line                   certification information of Tier 1 of the            Ruth Reyes, Office of New Reactors,
                                                    segments of the essential service water                 generic design control document (DCD)                 U.S. Nuclear Regulatory Commission,
                                                    system. Also, new Reference 25 is added                 and issuing License Amendment No. 23                  Washington, DC 20555–0001; telephone:
                                                    to FSAR-Standard Plant Section 3.6.3 to                 to Combined Licenses (COL), NPF–93                    301–415–3249; email: Ruth.Reyes@
                                                    cite the NRC-approved version of the                    and NPF–94. The COLs were issued to                   nrc.gov.
                                                    HDPE requirements covered by Relief                     South Carolina Electric & Gas Company
                                                                                                            (SCE&G), and South Carolina Public                    SUPPLEMENTARY INFORMATION:
                                                    Request I3R–10 dated October 31, 2008.
                                                       Date of issuance: March 31, 2015.                    Service Authority (the licensee), for                 I. Introduction
                                                       Effective date: As of its date of                    construction and operation of the Virgil
                                                                                                            C. Summer Nuclear Station (VCSNS),                       The NRC is granting an exemption
                                                    issuance and shall be implemented                                                                             from the provisions of Paragraph B of
                                                    within 60 days from the date of                         Units 2 and 3 located in Fairfield
                                                                                                            County, South Carolina.                               Section III, ‘‘Scope and Contents,’’ of
                                                    issuance.                                                                                                     appendix D, ‘‘Design Certification Rule
                                                       Amendment No.: 211. A publicly-                        The granting of the exemption allows
                                                                                                            the changes to Tier 1 information                     for the AP1000,’’ to part 52 of Title 10
                                                    available version is in ADAMS under                                                                           of the Code of Federal Regulations (10
                                                    Accession No. ML15064A028;                              requested in the amendment. Because
                                                                                                            the acceptability of the exemption was                CFR) and issuing License Amendment
                                                    documents related to this amendment                                                                           No. 23 to COLs, NPF–93 and NPF–94,
                                                    are listed in the Safety Evaluation                     determined in part by the acceptability
                                                                                                            of the amendment, the exemption and                   to the licensee. The exemption is
                                                    enclosed with the amendment.                                                                                  required by Paragraph A.4 of Section
                                                       Renewed Facility Operating License                   amendment are being issued
                                                                                                            concurrently.                                         VIII, ‘‘Processes for Changes and
                                                    No. NPF–30: The amendment revised                                                                             Departures,’’ appendix D to 10 CFR part
                                                    the Operating License.                                  ADDRESSES:   Please refer to Docket ID                52 to allow the licensee to depart from
                                                       Date of initial notice in Federal                    NRC–2008–0441 when contacting the                     Tier 1 information. With the requested
                                                    Register: March 18, 2014 (79 FR                         NRC about the availability of                         amendment, the licensee sought
                                                    15150). The supplements dated                           information regarding this document.                  changes to COL Appendix C and
                                                    September 2 and December 11, 2014,                      You may obtain publicly-available                     corresponding plant-specific Tier 1
                                                    and February 3, 2015, provided                          information related to this document                  information to correct editorial errors
                                                    additional information that clarified the               using any of the following methods:                   and/or consistency errors (e.g.,
                                                    application, did not expand the scope of                   • Federal Rulemaking Web site: Go to               inconsistencies between Updated Final
                                                    the application as originally noticed,                  http://www.regulations.gov and search                 Safety Analysis Report (UFSAR) (Tier 2)
                                                    and did not change the staff’s original                 for Docket ID NRC–2008–0441. Address                  and Tier 1 information, and
                                                    proposed no significant hazards                         questions about NRC dockets to Carol                  inconsistencies between information
                                                    consideration determination as                          Gallagher; telephone: 301–415–3463;                   from different locations within Tier 1).
                                                    published in the Federal Register.                      email: Carol.Gallagher@nrc.gov. For                      Part of the justification for granting
                                                       The Commission’s related evaluation                  technical questions, contact the                      the exemption was provided by the
                                                    of the amendment is contained in a                      individual listed in the FOR FURTHER                  review of the amendment. Because the
                                                    Safety Evaluation dated March 31, 2015.                 INFORMATION CONTACT section of this                   exemption is necessary in order to issue
                                                       No significant hazards consideration                 document.                                             the requested license amendment, the
                                                    comments received: No.                                     • NRC’s Agencywide Documents                       NRC granted the exemption and issued
                                                      Dated at Rockville, Maryland, this 6th day            Access and Management System                          the amendment concurrently, rather
                                                    of April 2015.                                          (ADAMS): You may obtain publicly-                     than in sequence. This included issuing
                                                      For the Nuclear Regulatory Commission.
                                                                                                            available documents online in the                     a combined safety evaluation containing
                                                                                                            ADAMS Public Documents collection at                  the NRC staff’s review of both the
                                                    A. Louise Lund,
                                                                                                            http://www.nrc.gov/reading-rm/                        exemption request and the license
                                                    Acting Director, Division of Operating Reactor          adams.html. To begin the search, select               amendment. The exemption met all
                                                    Licensing, Office of Nuclear Reactor
                                                    Regulation.
                                                                                                            ‘‘ADAMS Public Documents’’ and then                   applicable regulatory criteria set forth in
                                                                                                            select ‘‘Begin Web-based ADAMS                        10 CFR 50.12, 10 CFR 52.7, and
                                                    [FR Doc. 2015–08579 Filed 4–13–15; 8:45 am]
                                                                                                            Search.’’ For problems with ADAMS,                    52.63(b)(1). The license amendment was
                                                    BILLING CODE 7590–01–P
                                                                                                            please contact the NRC’s Public                       found to be acceptable as well. The
                                                                                                            Document Room (PDR) reference staff at                combined safety evaluation is available
                                                    NUCLEAR REGULATORY                                      1–800–397–4209, 301–415–4737, or by                   in ADAMS under Accession No.
                                                    COMMISSION                                              email to pdr.resource@nrc.gov. The                    ML14345B029.
                                                                                                            ADAMS accession number for each                          Identical exemption documents
                                                                                                            document referenced (if it is available in            (except for referenced unit numbers and
                                                    [Docket Nos. 52–027 and 52–028; NRC–                    ADAMS) is provided the first time that                license numbers) were issued to the
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                                                    2008–0441]
                                                                                                            a document is referenced. The request                 licensee for VCSNS Units 2 and 3 (COLs
                                                    Virgil C. Summer Nuclear Station,                       for the amendment and exemption was                   NPF–93 and NPF–94). These documents
                                                    Units 2 and 3; South Carolina Electric                  submitted by the letter dated May 20,                 can be found in ADAMS under
                                                    & Gas Company; Tier 1 Editorial and                     2014 (ADAMS Accession No.                             Accession Nos. ML14352A155 and
                                                    Consistency Changes                                     ML14140A637). The licensee                            ML14352A164, respectively. The
                                                                                                            supplemented this request by letter                   exemption is reproduced (with the
                                                    AGENCY:Nuclear Regulatory                               dated June 3, 2014 (ADAMS Accession                   exception of abbreviated titles and
                                                    Commission.                                             No. ML14155A257).                                     additional citations) in Section II of this


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Document Created: 2015-12-18 11:10:22
Document Modified: 2015-12-18 11:10:22
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionNotices
ActionBiweekly notice.
DatesComments must be filed by May 14, 2015. A request for a hearing must be filed by June 15, 2015.
ContactAngela Baxter, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001; telephone: 301-415-2976, email: [email protected]
FR Citation80 FR 20020 

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