80_FR_55833 80 FR 55654 - Instrumentation and Controls

80 FR 55654 - Instrumentation and Controls

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 80, Issue 179 (September 16, 2015)

Page Range55654-55656
FR Document2015-23185

The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comments on proposed changes to the ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' (NUREG-0800) for changes to 33 individual sections of Chapter 7, ``Instrumentation and Controls,'' as listed in the table in Section IV of this notice entitled, Availability of Documents.

Federal Register, Volume 80 Issue 179 (Wednesday, September 16, 2015) 
[Federal Register Volume 80, Number 179 (Wednesday, September 16, 2015)]
[Notices]
[Pages 55654-55656]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2015-23185]


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NUCLEAR REGULATORY COMMISSION

[NRC-2015-0211]


Instrumentation and Controls

AGENCY: Nuclear Regulatory Commission.

ACTION: Standard review plan-draft section revision; request for 
comment.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting 
public comments on proposed changes to the ``Standard Review Plan for 
the Review of Safety Analysis Reports for Nuclear Power Plants: LWR 
Edition,'' (NUREG-0800) for changes to 33 individual sections of 
Chapter 7, ``Instrumentation and Controls,'' as listed in the table in 
Section IV of this notice entitled, Availability of Documents.

DATES: Comments must be filed no later than November 16, 2015. Comments 
received after this date will be considered, if it is practical to do 
so, but the Commission is able to ensure consideration only for 
comments received on or before this date.

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-2015-0211. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     Mail comments to: Cindy Bladey, Office of Administration, 
Mail Stop: OWFN-12-H8, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
    For additional direction on accessing information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Michael S. Jones, Office of New 
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-0189, email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2015-0211 when contacting the NRC 
about the availability of information regarding this document. You may 
obtain publicly-available information related to this action by the 
following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0211.
     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 available in 
ADAMS) is provided the first time that a document is referenced. In 
addition, for the convenience of the reader, instructions about 
accessing materials referenced in this document are provided in the 
``Availability of Documents'' 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-2015-0211 in the subject line of your 
comment submission, in order to ensure that the NRC is able to make 
your comment submission available to the public in this docket.
    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 posts all comment submissions at http://www.regulations.gov as well as entering 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 submissions into ADAMS.

II. Further Information

    The NRC seeks public comment on the proposed draft revisions of 
Standard Review Plan (SRP) sections of Chapter 7 listed above. These 
sections have been developed to assist the NRC staff review the design 
of instrumentation and controls and auxiliary systems under parts 50 
and 52 of Title 10 of the Code of Federal Regulations (10 CFR). The 
revisions to these SRP sections reflect no changes in staff position; 
rather they clarify the original intent of these SRP sections using 
plain language throughout in accordance with the NRC's Plain Writing 
Action Plan. Additionally, these revisions reflect operating 
experience, lessons learned, updates to NRC guidance, and address the 
applicability of regulatory treatment of non-safety systems, where 
appropriate.

[[Page 55655]]

    Following the NRC staff's evaluation of public comments, the NRC 
intends to finalize the proposed revisions of the subject SRP Sections 
in ADAMS and post them on the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/. The SRP is 
guidance for the NRC staff. The SRP is not a substitute for the NRC 
regulations, and compliance with the SRP is not required.

III. Backfitting and Issue Finality

    Issuance of these draft SRP sections, if finalized, would not 
constitute backfitting as defined in 10 CFR 50.109 (the Backfit Rule) 
or otherwise be inconsistent with the issue finality provisions in 10 
CFR part 52. The NRC's position is based upon the following 
considerations:
    1. The draft SRP positions, if finalized, would not constitute 
backfitting, inasmuch as the SRP is internal guidance to NRC staff.
    The SRP provides internal guidance to the NRC staff on how to 
review an application for NRC regulatory approval in the form of 
licensing. Changes in internal staff guidance are not matters for which 
either nuclear power plant applicants or licensees are protected under 
either the Backfit Rule or the issue finality provisions of 10 CFR part 
52.
    2. The NRC staff has no intention to impose the SRP positions on 
existing licensees either now or in the future.
    The NRC staff does not intend to impose or apply the positions 
described in the draft SRP to existing licenses and regulatory 
approvals. Hence, the issuance of a final SRP--even if considered 
guidance within the purview of the issue finality provisions in 10 CFR 
part 52--would not need to be evaluated as if it were a backfit or as 
being inconsistent with issue finality provisions. If, in the future, 
the NRC staff seeks to impose a position in the SRP on holders of 
already issued licenses in a manner that does not provide issue 
finality as described in the applicable issue finality provision, then 
the staff must make the showing as set forth in the Backfit Rule or 
address the criteria for avoiding issue finality as described in the 
applicable issue finality provision.
    3. Backfitting and issue finality do not--with limited exceptions 
not applicable here--protect current or future applicants.
    Applicants and potential applicants are not, with certain 
exceptions, protected by either the Backfit Rule or any issue finality 
provisions under 10 CFR part 52. Neither the Backfit Rule nor the issue 
finality provisions under 10 CFR part 52--with certain exclusions--were 
intended to apply to every NRC action that substantially changes the 
expectations of current and future applicants. The exceptions to the 
general principle are applicable whenever an applicant references a 10 
CFR part 52 license (e.g., an early site permit) and/or NRC regulatory 
approval (e.g., a design certification rule) with specified issue 
finality provisions. The NRC staff does not, at this time, intend to 
impose the positions represented in the draft SRP in a manner that is 
inconsistent with any issue finality provisions. If, in the future, the 
staff seeks to impose a position in the draft SRP in a manner that does 
not provide issue finality as described in the applicable issue 
finality provision, then the staff must address the criteria for 
avoiding issue finality as described in the applicable issue finality 
provision.

IV. Availability of Documents

    The documents identified in Table 1 below are available to 
interested persons through one or more of the following methods, as 
indicated.

                                          Table 1--Standard Review Plan (SRP) Chapter 7 Sections Being Revised
--------------------------------------------------------------------------------------------------------------------------------------------------------
                                                                                                                                Redline ADAMS Accession
            SRP Section                  Current revision ADAMS Accession No.        Proposed revision ADAMS Accession No.                No.
--------------------------------------------------------------------------------------------------------------------------------------------------------
SRP 7.0, ``Instrumentation and       Revision 6, ML100740146....................  Revision 7, ML15159B042...................  ML14303A149
 Controls--Overview of Review
 Process''.
SRP 7.1, ``Instrumentation and       Revision 5, ML070550076....................  Revision 6, ML15159B068...................  ML14303A153
 Controls--Introduction''.
Table 7-1, ``Table 7-1 Regulatory    Revision 5, ML070460342....................  Revision 6, ML15159B203...................  ML14303A447
 Requirements, Acceptance Criteria,
 and Guidelines for Instrumentation
 and Control Systems Important to
 Safety''.
SRP 7.2, ``Reactor Trip System''...  Revision 5, ML070550083....................  Revision 6, ML15159B086...................  ML14303A403
SRP 7.3, ``Engineered Safety         Revision 5, ML070560004....................  Revision 6, ML15159B099...................  ML14303A408
 Features Systems''.
SRP 7.4, ``Safe Shutdown Systems''.  Revision 5, ML070550085....................  Revision 6, ML15159B122...................  ML14303A411
SRP 7.5, ``Information Systems       Revision 5, ML070550086....................  Revision 6, ML15159B138...................  ML14303A413
 Important to Safety''.
SRP 7.6, ``Interlock Systems         Revision 5, ML070460348....................  Revision 6, ML15159B156...................  ML14303A416
 Important to Safety''.
SRP 7.7, ``Control Systems''.......  Revision 5, ML070670042....................  Revision 6, ML15159B161...................  ML14303A428
SRP 7.8, ``Diverse Instrumentation   Revision 5, ML070650035....................  Revision 6, ML15159B171...................  ML14303A432
 and Control Systems''.
SRP 7.9, ``Data Communication        Revision 5, ML070650036....................  Revision 6, ML15159B177...................  ML14303A435
 Systems''.
App. 7.0-A, ``Review Process for     Revision 5, ML070660258....................  Revision 6, ML15159A199...................  ML14302A297
 Digital Instrumentation and
 Control Systems''.
App. 7.1-A, ``Acceptance Criteria    Revision 5, ML070660170....................  Revision 6, ML15159A207...................  ML14302A299
 and Guidelines for Instrumentation
 and Controls Systems Important to
 Safety''.
App. 7.1-B, ``Guidance for           Revision 5, ML070550087....................  Revision 6, ML15159A226...................  ML14302A300
 Evaluation of Conformance to IEEE
 Std 279''.
App. 7.1-C, ``Guidance for           Revision 5, ML070550088....................  Revision 6, ML15159A337...................  ML14302A303
 Evaluation of Conformance to IEEE
 Std 603''.
App. 7.1-D, ``Guidance for           Initial Issuance, ML070660327..............  Revision 1, ML15159A491...................  ML14302A309
 Evaluation of the Application of
 IEEE Std 7-4.3.2''.
BTP 7-1, ``Guidance on Isolation of  Revision 5, ML070460345....................  Revision 6, ML15159A540...................  ML14302A385
 Low-Pressure Systems from the High-
 Pressure Reactor Coolant System''.
BTP 7-2, ``Guidance on Requirements  Revision 5, ML070550090....................  Revision 6, ML15159A592...................  ML14302A459
 of Motor-Operated Valves in the
 Emergency Core Cooling System
 Accumulator Lines''.
BTP 7-3, ``Guidance on Protection    Revision 5, ML070550091....................  Revision 6, ML15159A638...................  ML14303A079
 System Trip Point Changes for
 Operation with Reactor Coolant
 Pumps Out of Service''.

[[Page 55656]]

 
BTP 7-4, ``Guidance on Design        Revision 5, ML070550093....................  Revision 6, ML15159A672...................  ML14303A088
 Criteria for Auxiliary Feedwater
 Systems''.
BTP 7-5, ``Guidance on Spurious      Revision 5, ML070550094....................  Revision 6, ML15159A681...................  ML14303A109
 Withdrawals of Single Control Rods
 in Pressurized Water Reactors''.
BTP 7-6, ``Guidance on Design of     Revision 5, ML070550095....................  Revision 6, ML15209A319...................  ML15209A455
 Instrumentation and Controls
 Provided to Accomplish Changeover
 from Injection to Recirculation
 Mode''.
BTP 7-8, ``Guidance for Application  Revision 5, ML070550096....................  Revision 6, ML15159A699...................  ML14303A143
 of Regulatory Guide 1.22''.
BTP 7-9, ``Guidance on Requirements  Revision 5, ML070550084....................  Revision 6, ML15209A459...................  ML15209A571
 for Reactor Protection System
 Anticipatory Trips''.
BTP 7-10, ``Guidance on Application  Revision 5, ML070550082....................  Revision 6, ML15159A726...................  ML14302A397
 of Regulatory Guide 1.97''.
BTP 7-11, ``Guidance on Application  Revision 5, ML070550080....................  Revision 6, ML15159A769...................  ML14302A401
 and Qualification of Isolation
 Devices''.
BTP 7-12, ``Guidance on              Revision 5, ML070550078....................  Revision 6, ML15159A799...................  ML14302A404
 Establishing and Maintaining
 Instrument Setpoints''.
BTP 7-13, ``Guidance on Cross-       Revision 5, ML070550077....................  Revision 6, ML15159A809...................  ML14302A410
 Calibration of Protection System
 Resistance Temperature Detectors''.
BTP 7-14, ``Guidance on Software     Revision 5, ML070670183....................  Revision 6, ML15159A946...................  ML14302A467
 Reviews for Digital Computer-Based
 Instrumentation and Control
 Systems''.
BTP 7-17, ``Guidance on Self-Test    Revision 5, ML070550075....................  Revision 6, ML15159A959...................  ML14302A477
 and Surveillance Test Provisions''.
BTP 7-18, ``Guidance on the Use of   Revision 5, ML070550073....................  Revision 6, ML15159A982...................  ML14302A488
 Programmable Logic Controllers in
 Digital Computer-Based
 Instrumentation and Control
 Systems''.
BTP 7-19, ``Guidance for Evaluation  Revision 6, ML110550791....................  Revision 7, ML15159A996...................  ML14302A495
 of Diversity and Defense-in-Depth
 in Digital Computer-Based
 Instrumentation and Control
 Systems''.
BTP 7-21, ``Guidance on Digital      Revision 5, ML070550070....................  Revision 6, ML15159B011...................  ML14303A112
 Computer Real-Time Performance''.
--------------------------------------------------------------------------------------------------------------------------------------------------------

    The NRC may post materials related to these documents, including 
public comments, on the Federal rulemaking Web site at http://www.regulations.gov under Docket ID NRC-2015-0211. The Federal 
rulemaking Web site allows you to receive alerts when changes or 
additions occur in a docket folder. To subscribe: (1) Navigate to the 
docket folder (NRC-2015-0211); (2) click the ``Sign up for Email 
Alerts'' link; and (3) enter your email address and select how 
frequently you would like to receive emails (daily, weekly, or 
monthly).

    Dated at Rockville, Maryland, this 3rd day of September, 2015.

    For the Nuclear Regulatory Commission.
Kimyata Morgan Butler,
Acting Chief, New Reactor Rulemaking and Guidance Branch, Division of 
Advanced Reactors and Rulemaking, Office of New Reactors.
[FR Doc. 2015-23185 Filed 9-15-15; 8:45 am]
 BILLING CODE 7590-01-P

55654 Federal Register / Vol. 80, No. 179 / Wednesday, September 16, 2015 / Notices ATTACHMENT 1—GENERAL TARGET SCHEDULE FOR PROCESSING AND RESOLVING REQUESTS FOR ACCESS TO SENSITIVE UNCLASSIFIED NON-SAFEGUARDS INFORMATION IN THIS PROCEEDING—Continued Day Event/Activity A + 28 ............... Deadline for submission of contentions whose development depends upon access to SUNSI. However, if more than 25 days remain between the petitioner’s receipt of (or access to) the information and the deadline for filing all other contentions (as established in the notice of hearing or opportunity for hearing), the petitioner may file its SUNSI contentions by that later deadline. A + 53 ............... (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI. A + 60 ............... (Answer receipt +7) Petitioner/Intervenor reply to answers. >A + 60 ............. Decision on contention admission. [FR Doc. 2015–23184 Filed 9–15–15; 8:45 am] see ‘‘Obtaining Information and B. Submitting Comments BILLING CODE 7590–01–P Submitting Comments’’ in the Please include Docket ID NRC–2015– SUPPLEMENTARY INFORMATION section of 0211 in the subject line of your this document. comment submission, in order to ensure NUCLEAR REGULATORY that the NRC is able to make your FOR FURTHER INFORMATION CONTACT: COMMISSION comment submission available to the Michael S. Jones, Office of New [NRC–2015–0211] Reactors, U.S. Nuclear Regulatory public in this docket. Commission, Washington, DC 20555– The NRC cautions you not to include Instrumentation and Controls 0001; telephone: 301–415–0189, email: identifying or contact information that Michael.Jones2@nrc.gov. you do not want to be publicly AGENCY: Nuclear Regulatory disclosed in your comment submission. Commission. SUPPLEMENTARY INFORMATION: The NRC posts all comment ACTION: Standard review plan-draft submissions at http:// section revision; request for comment. I. Obtaining Information and Submitting Comments www.regulations.gov as well as entering SUMMARY: The U.S. Nuclear Regulatory the comment submissions into ADAMS. A. Obtaining Information The NRC does not routinely edit Commission (NRC) is soliciting public comments on proposed changes to the comment submissions to remove Please refer to Docket ID NRC–2015– identifying or contact information. ‘‘Standard Review Plan for the Review 0211 when contacting the NRC about If you are requesting or aggregating of Safety Analysis Reports for Nuclear the availability of information regarding comments from other persons for Power Plants: LWR Edition,’’ (NUREG– this document. You may obtain submission to the NRC, then you should 0800) for changes to 33 individual publicly-available information related to inform those persons not to include sections of Chapter 7, ‘‘Instrumentation this action by the following methods: identifying or contact information that and Controls,’’ as listed in the table in • Federal Rulemaking Web site: Go to they do not want to be publicly Section IV of this notice entitled, disclosed in their comment submission. http://www.regulations.gov and search Availability of Documents. Your request should state that the NRC for Docket ID NRC–2015–0211. DATES: Comments must be filed no later does not routinely edit comment than November 16, 2015. Comments • NRC’s Agencywide Documents submissions to remove such information received after this date will be Access and Management System before making the comment considered, if it is practical to do so, but (ADAMS): You may obtain publicly- submissions available to the public or the Commission is able to ensure available documents online in the entering the comment submissions into consideration only for comments ADAMS Public Documents collection at ADAMS. received on or before this date. http://www.nrc.gov/reading-rm/ adams.html. To begin the search, select II. Further Information ADDRESSES: You may submit comments ‘‘ADAMS Public Documents’’ and then The NRC seeks public comment on by any of the following methods (unless select ‘‘Begin Web-based ADAMS the proposed draft revisions of Standard this document describes a different Search.’’ For problems with ADAMS, Review Plan (SRP) sections of Chapter method for submitting comments on a please contact the NRC’s Public 7 listed above. These sections have been specific subject): • Federal Rulemaking Web site: Go to Document Room (PDR) reference staff at developed to assist the NRC staff review http://www.regulations.gov and search 1–800–397–4209, 301–415–4737, or by the design of instrumentation and for Docket ID NRC–2015–0211. Address email to pdr.resource@nrc.gov. The controls and auxiliary systems under questions about NRC dockets to Carol ADAMS accession number for each parts 50 and 52 of Title 10 of the Code Gallagher; telephone: 301–415–3463; document referenced (if it available in of Federal Regulations (10 CFR). The email: Carol.Gallagher@nrc.gov. For ADAMS) is provided the first time that revisions to these SRP sections reflect technical questions, contact the a document is referenced. In addition, no changes in staff position; rather they individual listed in the FOR FURTHER for the convenience of the reader, clarify the original intent of these SRP INFORMATION CONTACT section of this instructions about accessing materials sections using plain language asabaliauskas on DSK7TPTVN1PROD with NOTICES document. referenced in this document are throughout in accordance with the • Mail comments to: Cindy Bladey, provided in the ‘‘Availability of NRC’s Plain Writing Action Plan. Office of Administration, Mail Stop: Documents’’ section. Additionally, these revisions reflect OWFN–12–H8, U.S. Nuclear Regulatory • NRC’s PDR: You may examine and operating experience, lessons learned, Commission, Washington, DC 20555– purchase copies of public documents at updates to NRC guidance, and address 0001. the NRC’s PDR, Room O1–F21, One the applicability of regulatory treatment For additional direction on accessing White Flint North, 11555 Rockville of non-safety systems, where information and submitting comments, Pike, Rockville, Maryland 20852. appropriate. VerDate Sep<11>2014 18:18 Sep 15, 2015 Jkt 235001 PO 00000 Frm 00067 Fmt 4703 Sfmt 4703 E:\FR\FM\16SEN1.SGM 16SEN1

Federal Register / Vol. 80, No. 179 / Wednesday, September 16, 2015 / Notices 55655 Following the NRC staff’s evaluation issue finality provisions of 10 CFR part any issue finality provisions under 10 of public comments, the NRC intends to 52. CFR part 52. Neither the Backfit Rule finalize the proposed revisions of the 2. The NRC staff has no intention to nor the issue finality provisions under subject SRP Sections in ADAMS and impose the SRP positions on existing 10 CFR part 52—with certain post them on the NRC’s public Web site licensees either now or in the future. exclusions—were intended to apply to at http://www.nrc.gov/reading-rm/doc- The NRC staff does not intend to every NRC action that substantially collections/nuregs/staff/sr0800/. The impose or apply the positions described changes the expectations of current and SRP is guidance for the NRC staff. The in the draft SRP to existing licenses and future applicants. The exceptions to the SRP is not a substitute for the NRC regulatory approvals. Hence, the general principle are applicable regulations, and compliance with the issuance of a final SRP—even if whenever an applicant references a 10 SRP is not required. considered guidance within the purview CFR part 52 license (e.g., an early site of the issue finality provisions in 10 permit) and/or NRC regulatory approval III. Backfitting and Issue Finality CFR part 52—would not need to be (e.g., a design certification rule) with Issuance of these draft SRP sections, evaluated as if it were a backfit or as specified issue finality provisions. The if finalized, would not constitute being inconsistent with issue finality NRC staff does not, at this time, intend backfitting as defined in 10 CFR 50.109 provisions. If, in the future, the NRC to impose the positions represented in (the Backfit Rule) or otherwise be staff seeks to impose a position in the the draft SRP in a manner that is inconsistent with the issue finality SRP on holders of already issued inconsistent with any issue finality provisions in 10 CFR part 52. The NRC’s licenses in a manner that does not provisions. If, in the future, the staff position is based upon the following provide issue finality as described in the seeks to impose a position in the draft considerations: applicable issue finality provision, then SRP in a manner that does not provide 1. The draft SRP positions, if the staff must make the showing as set issue finality as described in the finalized, would not constitute forth in the Backfit Rule or address the backfitting, inasmuch as the SRP is applicable issue finality provision, then criteria for avoiding issue finality as internal guidance to NRC staff. the staff must address the criteria for described in the applicable issue finality The SRP provides internal guidance avoiding issue finality as described in provision. to the NRC staff on how to review an 3. Backfitting and issue finality do the applicable issue finality provision. application for NRC regulatory approval not—with limited exceptions not IV. Availability of Documents in the form of licensing. Changes in applicable here—protect current or internal staff guidance are not matters future applicants. The documents identified in Table 1 for which either nuclear power plant Applicants and potential applicants below are available to interested persons applicants or licensees are protected are not, with certain exceptions, through one or more of the following under either the Backfit Rule or the protected by either the Backfit Rule or methods, as indicated. TABLE 1—STANDARD REVIEW PLAN (SRP) CHAPTER 7 SECTIONS BEING REVISED Proposed revision Current revision ADAMS Redline ADAMS SRP Section ADAMS Accession No. Accession No. Accession No. SRP 7.0, ‘‘Instrumentation and Controls—Overview of Re- Revision 6, ML100740146 ...... Revision 7, ML15159B042 ..... ML14303A149 view Process’’. SRP 7.1, ‘‘Instrumentation and Controls—Introduction’’ ....... Revision 5, ML070550076 ...... Revision 6, ML15159B068 ..... ML14303A153 Table 7–1, ‘‘Table 7–1 Regulatory Requirements, Accept- Revision 5, ML070460342 ...... Revision 6, ML15159B203 ..... ML14303A447 ance Criteria, and Guidelines for Instrumentation and Control Systems Important to Safety’’. SRP 7.2, ‘‘Reactor Trip System’’ ........................................... Revision 5, ML070550083 ...... Revision 6, ML15159B086 ..... ML14303A403 SRP 7.3, ‘‘Engineered Safety Features Systems’’ ................ Revision 5, ML070560004 ...... Revision 6, ML15159B099 ..... ML14303A408 SRP 7.4, ‘‘Safe Shutdown Systems’’ ..................................... Revision 5, ML070550085 ...... Revision 6, ML15159B122 ..... ML14303A411 SRP 7.5, ‘‘Information Systems Important to Safety’’ ........... Revision 5, ML070550086 ...... Revision 6, ML15159B138 ..... ML14303A413 SRP 7.6, ‘‘Interlock Systems Important to Safety’’ ................ Revision 5, ML070460348 ...... Revision 6, ML15159B156 ..... ML14303A416 SRP 7.7, ‘‘Control Systems’’ .................................................. Revision 5, ML070670042 ...... Revision 6, ML15159B161 ..... ML14303A428 SRP 7.8, ‘‘Diverse Instrumentation and Control Systems’’ ... Revision 5, ML070650035 ...... Revision 6, ML15159B171 ..... ML14303A432 SRP 7.9, ‘‘Data Communication Systems’’ ........................... Revision 5, ML070650036 ...... Revision 6, ML15159B177 ..... ML14303A435 App. 7.0–A, ‘‘Review Process for Digital Instrumentation Revision 5, ML070660258 ...... Revision 6, ML15159A199 ..... ML14302A297 and Control Systems’’. App. 7.1–A, ‘‘Acceptance Criteria and Guidelines for Instru- Revision 5, ML070660170 ...... Revision 6, ML15159A207 ..... ML14302A299 mentation and Controls Systems Important to Safety’’. App. 7.1–B, ‘‘Guidance for Evaluation of Conformance to Revision 5, ML070550087 ...... Revision 6, ML15159A226 ..... ML14302A300 IEEE Std 279’’. App. 7.1–C, ‘‘Guidance for Evaluation of Conformance to Revision 5, ML070550088 ...... Revision 6, ML15159A337 ..... ML14302A303 IEEE Std 603’’. App. 7.1–D, ‘‘Guidance for Evaluation of the Application of Initial Issuance, ML070660327 Revision 1, ML15159A491 ..... ML14302A309 asabaliauskas on DSK7TPTVN1PROD with NOTICES IEEE Std 7–4.3.2’’. BTP 7–1, ‘‘Guidance on Isolation of Low-Pressure Systems Revision 5, ML070460345 ...... Revision 6, ML15159A540 ..... ML14302A385 from the High-Pressure Reactor Coolant System’’. BTP 7–2, ‘‘Guidance on Requirements of Motor-Operated Revision 5, ML070550090 ...... Revision 6, ML15159A592 ..... ML14302A459 Valves in the Emergency Core Cooling System Accumu- lator Lines’’. BTP 7–3, ‘‘Guidance on Protection System Trip Point Revision 5, ML070550091 ...... Revision 6, ML15159A638 ..... ML14303A079 Changes for Operation with Reactor Coolant Pumps Out of Service’’. VerDate Sep<11>2014 18:18 Sep 15, 2015 Jkt 235001 PO 00000 Frm 00068 Fmt 4703 Sfmt 4703 E:\FR\FM\16SEN1.SGM 16SEN1

55656 Federal Register / Vol. 80, No. 179 / Wednesday, September 16, 2015 / Notices TABLE 1—STANDARD REVIEW PLAN (SRP) CHAPTER 7 SECTIONS BEING REVISED—Continued Proposed revision Current revision ADAMS Redline ADAMS SRP Section ADAMS Accession No. Accession No. Accession No. BTP 7–4, ‘‘Guidance on Design Criteria for Auxiliary Revision 5, ML070550093 ...... Revision 6, ML15159A672 ..... ML14303A088 Feedwater Systems’’. BTP 7–5, ‘‘Guidance on Spurious Withdrawals of Single Revision 5, ML070550094 ...... Revision 6, ML15159A681 ..... ML14303A109 Control Rods in Pressurized Water Reactors’’. BTP 7–6, ‘‘Guidance on Design of Instrumentation and Revision 5, ML070550095 ...... Revision 6, ML15209A319 ..... ML15209A455 Controls Provided to Accomplish Changeover from Injec- tion to Recirculation Mode’’. BTP 7–8, ‘‘Guidance for Application of Regulatory Guide Revision 5, ML070550096 ...... Revision 6, ML15159A699 ..... ML14303A143 1.22’’. BTP 7–9, ‘‘Guidance on Requirements for Reactor Protec- Revision 5, ML070550084 ...... Revision 6, ML15209A459 ..... ML15209A571 tion System Anticipatory Trips’’. BTP 7–10, ‘‘Guidance on Application of Regulatory Guide Revision 5, ML070550082 ...... Revision 6, ML15159A726 ..... ML14302A397 1.97’’. BTP 7–11, ‘‘Guidance on Application and Qualification of Revision 5, ML070550080 ...... Revision 6, ML15159A769 ..... ML14302A401 Isolation Devices’’. BTP 7–12, ‘‘Guidance on Establishing and Maintaining In- Revision 5, ML070550078 ...... Revision 6, ML15159A799 ..... ML14302A404 strument Setpoints’’. BTP 7–13, ‘‘Guidance on Cross-Calibration of Protection Revision 5, ML070550077 ...... Revision 6, ML15159A809 ..... ML14302A410 System Resistance Temperature Detectors’’. BTP 7–14, ‘‘Guidance on Software Reviews for Digital Revision 5, ML070670183 ...... Revision 6, ML15159A946 ..... ML14302A467 Computer-Based Instrumentation and Control Systems’’. BTP 7–17, ‘‘Guidance on Self-Test and Surveillance Test Revision 5, ML070550075 ...... Revision 6, ML15159A959 ..... ML14302A477 Provisions’’. BTP 7–18, ‘‘Guidance on the Use of Programmable Logic Revision 5, ML070550073 ...... Revision 6, ML15159A982 ..... ML14302A488 Controllers in Digital Computer-Based Instrumentation and Control Systems’’. BTP 7–19, ‘‘Guidance for Evaluation of Diversity and De- Revision 6, ML110550791 ...... Revision 7, ML15159A996 ..... ML14302A495 fense-in-Depth in Digital Computer-Based Instrumentation and Control Systems’’. BTP 7–21, ‘‘Guidance on Digital Computer Real-Time Per- Revision 5, ML070550070 ...... Revision 6, ML15159B011 ..... ML14303A112 formance’’. The NRC may post materials related NUCLEAR REGULATORY DATES: Comments must be filed by to these documents, including public COMMISSION October 16, 2015. A request for a comments, on the Federal rulemaking hearing must be filed by October 6, [Docket No. 50–440; NRC–2015–0212] Web site at http://www.regulations.gov 2015. Any potential party as defined in under Docket ID NRC–2015–0211. The Perry Nuclear Power Plant, Unit 1; § 2.4 of Title 10 of the Code of Federal Federal rulemaking Web site allows you Consideration of Approval of Transfer Regulations (10 CFR), who believes to receive alerts when changes or of License and Conforming access to SUNSI is necessary to respond additions occur in a docket folder. To Amendment to this notice must request document subscribe: (1) Navigate to the docket access by September 28, 2015. AGENCY: Nuclear Regulatory folder (NRC–2015–0211); (2) click the ADDRESSES: You may submit comments Commission. ‘‘Sign up for Email Alerts’’ link; and (3) by any of the following methods (unless ACTION: Application for direct transfer of this document describes a different enter your email address and select how license; opportunity to comment, method for submitting comments on a frequently you would like to receive request a hearing, and petition for leave specific subject): emails (daily, weekly, or monthly). to intervene; order. • Federal Rulemaking Web site: Go to Dated at Rockville, Maryland, this 3rd day SUMMARY: The U.S. Nuclear Regulatory http://www.regulations.gov and search of September, 2015. Commission (NRC) received and is for Docket ID NRC–2015–0212. Address For the Nuclear Regulatory Commission. questions about NRC dockets to Carol considering approval of an application Kimyata Morgan Butler, filed by FirstEnergy Nuclear Operating Gallagher; telephone: 301–415–3463; Acting Chief, New Reactor Rulemaking and Company (FENOC) on June 30, 2015. email: Carol.Gallagher@nrc.gov. For Guidance Branch, Division of Advanced The application seeks NRC approval of technical questions contact the Reactors and Rulemaking, Office of New the direct transfer of the leased interests individual listed in the FOR FURTHER Reactors. in NPF–58 for Perry Nuclear Power INFORMATION CONTACT section of this [FR Doc. 2015–23185 Filed 9–15–15; 8:45 am] Plant, Unit 1, from the current holder, document. asabaliauskas on DSK7TPTVN1PROD with NOTICES BILLING CODE 7590–01–P the Ohio Edison Company (OE), to • Email comments to: FirstEnergy Nuclear Generation, LLC Hearingdocket@nrc.gov. If you do not (FENGen). The NRC is also considering receive an automatic email reply amending the facility operating license confirming receipt, then contact us at for administrative purposes to reflect 301–415–1677. the proposed transfer. The application • Fax comments to: Secretary, U.S. contains sensitive unclassified non- Nuclear Regulatory Commission at 301– safeguards information (SUNSI). 415–1101. VerDate Sep<11>2014 18:18 Sep 15, 2015 Jkt 235001 PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 E:\FR\FM\16SEN1.SGM 16SEN1


Document Created: 2018-02-26 10:16:48
Document Modified: 2018-02-26 10:16:48
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
ActionStandard review plan-draft section revision; request for comment.
DatesComments must be filed no later than November 16, 2015. Comments received after this date will be considered, if it is practical to do so, but the Commission is able to ensure consideration only for comments received on or before this date.
ContactMichael S. Jones, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555- 0001; telephone: 301-415-0189, email: [email protected]
FR Citation80 FR 55654 
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