80 FR 27193 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
NUCLEAR REGULATORY COMMISSION Federal Register Volume 80, Issue 91 (May 12, 2015)
Federal Register Volume 80, Issue 91 (May 12, 2015)
| Page Range | 27193-27204 | |
| FR Document | 2015-11225 |
[Federal Register Volume 80, Number 91 (Tuesday, May 12, 2015)] [Notices] [Pages 27193-27204] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2015-11225] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2015-0117] Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations AGENCY: Nuclear Regulatory Commission. ACTION: Biweekly notice. ----------------------------------------------------------------------- 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 April 16, 2015, to April 29, 2015. The last biweekly notice was published on April 28, 2015. DATES: Comments must be filed by June 11, 2015. A request for a hearing must be filed by July 13, 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-2015-0117. 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-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: Lynn M. Ronewicz, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1927, email: [email protected]. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC-2015-0117 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-2015-0117. 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-2015-0117, 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 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 [[Page 27194]] submissions to remove such information before making the comment submissions available to the public or entering the comment submissions 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 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 that 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 [[Page 27195]] 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 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 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. Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50- 529, and STN 50-530, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Maricopa County, Arizona Date of amendment request: February 27, 2015. A publicly-available version is [[Page 27196]] in ADAMS under Accession No. ML15065A031. Description of amendment request: The amendments would revise Technical Specification (TS) 1.3, ``Completion Times''; TS 3.7.5, ``Auxiliary Feedwater (AFW) System''; TS 3.8.1, ``AC [Alternating Current] Sources--Operating''; and TS 3.8.9, ``Distribution Systems-- Operating,'' to remove the second completion times. The change would also revise Example 1.3-3 in TS 1.3, ``Completion Times,'' by adding a discussion of administrative controls to combinations of Conditions to ensure that the Completion Times for those conditions are not inappropriately extended. The proposed changes are consistent with the NRC-approved Technical Specification Task Force (TSTF) Traveler TSTF-439-A, Revision 2, ``Eliminate Second Completion Times Limiting Time From Discovery of Failure to Meet an LCO [Limiting Condition of Operation],'' dated June 20, 2005 (ADAMS Accession No. ML051860296). 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 change proposed by incorporating TSTF-439-A, Revision 2, eliminates certain Completion Times from the Technical Specifications. Completion Times are not an initiator of any accident previously evaluated. As a result, the probability of an accident previously evaluated is not affected. The consequences of an accident during the revised Completion Times are no different than the consequences of the same accident during the existing Completion Times. As a result, the consequences of an accident previously evaluated are not affected by this change. The proposed change does not alter or prevent the ability of structures, systems, or components from performing their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed change to modify certain Completion Times does not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of an accident previously evaluated. Further, the proposed change does not increase the types or amounts of radioactive effluent that may be released offsite, nor significantly increase the cumulative occupational/public radiation exposures. The proposed change is consistent with the safety analysis assumptions and resultant consequences. 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 changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The proposed changes do not alter any assumptions made in the safety analyses. 3. Does the proposed amendment involve a significant reduction in the margin of safety? Response: No. The proposed change to delete the second [Completion Time] and the related example of the second Completion Time does not alter the manner in which safety limits, limiting safety systems settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by this change. The proposed change will not result in plant operation in a configuration outside of the design basis. Therefore, the proposed amendment does not involve a significant reduction in the margin of safety. The NRC staff has reviewed the licensee's analysis and, based on that review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the request for amendments involves no significant hazards consideration. Attorney for licensee: Michael G. Green, Senior Regulatory Counsel, Pinnacle West Capital Corporation, P.O. Box 52034, Mail Station 8695, Phoenix, AZ 85072-2034. NRC Branch Chief: Michael T. Markley. Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire Nuclear Station, Units 1 and 2, Mecklenburg County, North Carolina Date of amendment request: March 23, 2015. A publicly-available version is in ADAMS under Accession No. ML15097A010. Description of amendment request: The amendments would modify the definition of RATED THERMAL POWER and delete a footnote that allowed for staggered implementation of the previously approved Measurement Uncertainty Recapture Power Uprate. 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. This LAR [license amendment request] proposes administrative non-technical changes only. These proposed changes do not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, or configurations of the facility. The proposed changes do not alter or prevent the ability of structures, systems[,] and components (SSCs) to perform their intended function to mitigate the consequences of an initiating event witin the assumed acceptance limits. Given the above discussion, it is concluded the proposed amendment does not significantly increase 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 LAR proposes administrative non-technical changes only. The proposed changes will not alter the design requirements of any SSC or its function during accident conditions. No new or different accidents result from the changes proposed. The changes do not involve a physical alteration of the plant or any changes in methods governing normal plant operation. The changes do not alter assumptions made in the safety analysis. Given the above discussion, it is concluded the proposed 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. This LAR proposes administrative non-technical changes only. The proposed changes do not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by these changes. The proposed changes will not result in plant operation in a configuration outside the design basis. The proposed changes do not adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition. Given the above discussion, it is concluded [that] the proposed amendment 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: Lara S. Nichols, Associate General Counsel, Duke Energy Corporation, 526 South Church Street--EC07H, Charlotte, NC 28202. [[Page 27197]] NRC Branch Chief: Robert J. Pascarelli. Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power Station (CPS), Unit 1, DeWitt County, Illinois Date of amendment request: November 17, 2014, as supplemented by letter dated April 21, 2015. Publicly-available versions are in ADAMS under Accession Nos. ML14321A882 and ML15111A258, respectively. Description of amendment request: The amendment would revise technical specification (TS) 5.5.2, ``Primary Coolant Sources Outside Containment,'' to change the integrated leak testing frequency for systems subject to TS 5.5.2. The proposed amendment was initially published in the Federal Register Biweekly Notice on February 17, 2015 (80 FR 8361). 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 change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change to the CPS, Unit 1, TS 5.5.2, ``Primary Coolant Sources Outside Containment'' program, does not involve a physical change to the plant or a change in the manner in which the plant is operated or controlled. The proposed amendment affects only the interval at which integrated system leak tests are performed, not the effectiveness of the integrated leak test requirements for the identified systems. The proposed change effectively results in the performance of the integrated system leak tests at the same frequency that these tests are currently being performed. Incorporation of an allowance to extend the 24-month interval by 25% does not significantly degrade the reliability that results from performing the surveillance at its specified frequency. Implementation of the proposed change will continue to provide adequate assurance that during design basis accidents, the containment and its components would limit leakage rates to less than the values assumed in the plant safety analyses. Test intervals are not considered as initiators of any accident previously evaluated. As a result, the probability of any accident previously evaluated is not significantly increased by the proposed amendment. TS 5.5.2 continues to require the performance of periodic integrated system leak tests. As stated in TS 5.5.2, the required plan provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. Therefore, accident analysis assumptions will still be verified. The proposed change does not impact the purpose of this plan. As a result, the consequences of any accident previously evaluated are not significantly increased. Therefore, the probability and consequences of an accident previously evaluated will not be increased by this proposed change. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The testing requirements, to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident, exist to ensure the plant's ability to mitigate the consequences of an accident and do not involve any accident precursors or initiators. The proposed amendment affects only the interval at which integrated system leak tests are performed; they do not alter the design or physical configuration of the plant. The proposed change does not involve a physical change to the plant (i.e., no new or different type of equipment will be installed) or a change to the manner in which the plant is currently operated or controlled. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed change does not alter the manner in which safety limits, limiting safety system setpoints, or limiting conditions for operation are determined. The specific requirements and conditions of the primary coolant sources outside containment program, as proposed, will continue to ensure that the leakage from the identified systems outside containment is minimized. The proposed amendment provides operating flexibility without significantly affecting plant operation. Therefore, the proposed change 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: Tamra Domeyer, Associate General Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, Warrenville, IL 60555. NRC Branch Chief: Travis L. Tate. Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Calvert County, Maryland Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point Nuclear Station, Unit 2, Oswego County, New York Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear Power Plant, Wayne County, New York Date of amendment request: July 10, 2014. A publicly-available version is in ADAMS under Accession No. ML14191A255. Description of amendment request: The amendments would revise and add several Technical Specification surveillance requirements (SRs) to address concerns discussed in Generic Letter 2008-01, ``Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.'' These changes are consistent with Technical Specification Task Force Traveler 523, Revision 2, ``Generic Letter 2008-01, Managing Gas Accumulation.'' 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 change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change revises or adds SRs that require verification that the Emergency Core Cooling System (ECCS), Residual Heat Removal (RHR) System, Shutdown Cooling (SDC) System, the Containment Spray (CS) System, and the Reactor Core Isolation Cooling (RCIC) System, as appropriate, are not rendered inoperable due to accumulated gas and to provide allowances which permit performance of the revised verification. Gas accumulation in the subject systems is not an initiator of any accident previously evaluated. As a result, the probability of any accident previously evaluated is not significantly increased. The proposed SRs ensure that the subject systems continue to be capable to perform their assumed safety function and are not rendered inoperable due to gas accumulation. Thus, the consequences of any accident previously evaluated are not significantly increased. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. [[Page 27198]] The proposed change revises or adds SRs that require verification that the ECCS, RHR, SDC, CS, and RCIC systems, as appropriate, are not rendered inoperable due to accumulated gas and to provide allowances which permit performance of the revised verification. The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. In addition, the proposed change does not impose any new or different requirements that could initiate an accident. The proposed change does not alter assumptions made in the safety analysis and is consistent with the safety analysis assumptions. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed change revises or adds SRs that require verification that the ECCS, RHR, SDC, CS, and RCIC systems, as appropriate, are not rendered inoperable due to accumulated gas and to provide allowances which permit performance of the revised verification. The proposed change adds new requirements to manage gas accumulation in order to ensure the subject systems are capable of performing their assumed safety functions. The proposed SRs are more comprehensive than the current SRs and will ensure that the assumptions of the safety analysis are protected. The proposed change does not adversely affect any current plant safety margins or the reliability of the equipment assumed in the safety analysis. Therefore, there are no changes being made to any safety analysis assumptions, safety limits or limiting safety system settings that would adversely affect plant safety as a result of the proposed change. Therefore, the proposed change 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: J. Bradley Fewell, Exelon Generation, 200 Exelon Way, Kennett Square, PA 19348. NRC Acting Branch Chief: Michael I. Dudek. FirstEnergy Nuclear Operating Company, et al., Docket Nos. 50-334 and 50-412, Beaver Valley Power Station, Units 1 and 2, Beaver County, Pennsylvania Date of amendment request: April 1, 2015. A publicly-available version is in ADAMS under Accession No. ML15092A569. Description of amendment request: The amendment would change the Beaver Valley Power Station, Units 1 and 2 (BVPS-1 and BVPS-2), technical specifications. Specifically, the proposed license amendment would revise various sections associated with steam generators and would include changes that are consistent with the guidance provided in Technical Specification Task Force (TSTF) Traveler 510, Revision 2, ``Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection'' (ADAMS Accession No. ML110610350). 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, along with NRC edits in square brackets: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed changes to Technical Specification 5.5.5.2.f.3 replaces the date and outage when all Alloy 800 sleeves shall be removed from service with a limitation on the individual sleeve service life from the date of installation. The allowed maximum service life previously approved for Alloy 800 sleeves remains unchanged. Since the maximum service life of the Alloy 800 sleeves is unchanged, the probability of a failure due to degradation does not increase. Implementation of the proposed changes to TS 5.5.5.2.f.3 have no significant effect on either the configuration of the plant or the manner in which is it operated. The consequences of a hypothetical failure of the leak-limiting Alloy 800 sleeve/tube assembly are bound by the current steam generator tube rupture (SGTR) analysis described in the BVPS-2 Updated Final Safety Analysis Report (UFSAR) because the total number of plugged SG tubes (including equivalency associated with installed sleeves) is required to be consistent with accident analysis assumptions. A main steam line break or feedwater line break would not cause a SGTR since the sleeves are analyzed for a maximum accident differential pressure greater than that predicted in the BVPS-2 accident analysis. The sleeve/tube assembly leakage during plant operation would be minimal and is well within the allowable Technical Specification leakage limits and accident analysis assumptions, neither of which would be changed to compensate for the repair method. The proposed changes to TSs 3.4.20, 5.5.5, and 5.6.6 are consistent with TSTF-510, editorial corrections, and clarifications. Changes that are consistent with TSTF-510 and other editorial corrections and clarifications do not change the physical plant or how it is operated; therefore they cannot affect the probability or consequence of a previously-evaluated accident. A proposed change modifies the frequency of verification of SG [steam generator] tube integrity and SG tube sample selection. The proposed SG tube inspection frequency and sample selection criteria will continue to ensure that the SG tubes are inspected such that the probability of a SGTR is not increased. The consequences of a SGTR are bounded by the conservative assumptions in the design basis accident analysis. The proposed changes will not cause the consequences of a SGTR to exceed those assumptions. Therefore, it is concluded that these changes do 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. Proposed changes to Technical Specification 5.5.5.2.f.3 replaces the date and outage when all Alloy 800 sleeves shall be removed from service with a limitation on the individual sleeve service life from the date of installation. The allowed maximum service life previously approved for Alloy 800 sleeves remains unchanged. Implementation of these proposed changes have no significant effect on either the configuration of the plant or the manner in which it is operated. The leak-limiting Alloy-800 sleeves are designed using the applicable ASME Code as guidance and meet the objectives of the original SG tubing. As a result, the functions of the SG will not be significantly affected by the installation of the proposed sleeve. Therefore, the only credible failure mode for the sleeve or tube is to rupture, which has already been evaluated. No new failure modes, malfunctions, or accident initiators have been created. The continued integrity of the installed sleeve/tube assembly is periodically verified as required by the Technical Specifications and a sleeved tube will be plugged on detection of a flaw in the sleeve or in the pressure boundary portion of the original tube wall in the sleeve-to-tube joint. The proposed changes to TSs 3.4.20, 5.5.5, and 5.6.6 are changes consistent with TSTF-510, editorial corrections, and clarification. These changes do not affect the operation of the SGs or the ability of the SGs to perform their design or safety functions; therefore they do not create new failure modes, malfunctions, or accident initiators. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The SG tubes in pressurized water reactors are an integral part of the reactor coolant pressure boundary and, as such, are relied upon to maintain the primary system's pressure and inventory. As part of the reactor coolant pressure boundary, the SG tubes are unique in that they are also relied upon as a heat transfer surface between the primary and secondary systems such that residual heat can be removed from the primary system. In addition, the SG tubes also isolate [[Page 27199]] the radioactive fission products in the primary coolant from the secondary system. In summary, the safety function of a SG is maintained by ensuring the integrity of its tubes. Proposed changes to Technical Specification 5.5.5.2.f.3 replaces the date and outage when all Alloy 800 sleeves shall be removed from service with a limitation on the individual sleeve service life from the date of installation. The allowed maximum service life previously approved for Alloy 800 sleeves remains unchanged. The sleeve and portions of the installed sleeve/tube assembly that represent the reactor coolant pressure boundary will be monitored and a sleeved tube will be plugged on detection of a flaw in the sleeve or in the pressure boundary portion of the original tube wall in the leak-limiting sleeve/tube assembly. Design criteria and design verification testing ensures that the margin of safety is not significantly different from the original SG tubes. The proposed changes to TSs 3.4.20, 5.5.5, and 5.6.6 are changes consistent with TSTF-510, editorial corrections, and clarifications. The proposed changes will continue to require monitoring of the physical condition of the SG tubes such that there will not be a reduction in the margin of safety compared to the current requirements. Therefore, the proposed changes do 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: David W. Jenkins, FirstEnergy Nuclear Operating Company, FirstEnergy Corporation, 76 South Main Street, Akron, OH 44308. NRC Branch Chief: Douglas A. Broaddus. Florida Power & Light Company (FPL), Docket Nos. 50-250 and 50-251, Turkey Point Nuclear Generating Units 3 and 4, Miami-Dade County, Florida Date of amendment request: April 9, 2014, as supplemented by letters dated February 20, 2015, and April 3, 2015. Publicly available versions are in ADAMS under Accession Nos. ML14105A042, ML15069A153, and ML15113A311, respectively. Description of amendment request: The NRC staff has previously made a proposed determination that the amendment request dated April 9, 2014, involves no significant hazards consideration (79 FR 42551; July 22, 2014). Subsequently, by letter dated April 3, 2015, the licensee provided additional information that expanded the scope of the amendment request as originally noticed. Accordingly, this notice supersedes the previous notice in its entirety. The amendment would revise the Technical Specifications (TSs) by relocating specific surveillance frequency requirements to a licensee- controlled program with implementation of Nuclear Energy Institute (NEI) 04-10 (Revision 1), ``Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies'' (ADAMS Accession No. ML071360456). The licensee stated that the NEI 04-10 methodology provides reasonable acceptance guidelines and methods for evaluating the risk increase of proposed changes to surveillance frequencies, consistent with Regulatory Guide 1.177, ``An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications'' (ADAMS Accession No. ML003740176). The licensee stated that the changes are consistent with NRC-approved Technical Specification Task Force (TSTF) Standard Technical Specifications change TSTF-425, Revision 3, ``Relocate Surveillance Frequencies to Licensee Control--RITSTF [Risk-Informed TSTF] Initiative 5b,'' Revision 3 (ADAMS Accession No. ML090850642). The Federal Register notice published on July 6, 2009 (74 FR 31996), announced the availability of TSTF-425, Revision 3. In the supplement dated April 3, 2015, the licensee requested additional surveillance frequencies be relocated to the licensee-controlled program, editorial changes, administrative deviations from TSTF-425, and other changes resulting from differences between the Turkey Point Units 3 and 4 TSs and the TSs on which TSTF-425 is based. 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. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change relocates the specified frequencies for periodic surveillance requirements to licensee control under a new Surveillance Frequency Control Program. Surveillance frequencies are not an initiator to any accident previously evaluated. As a result, the probability of any accident previously evaluated is not significantly increased. The systems and components required by the Technical Specifications for which the surveillance frequencies are relocated are still required to be operable, meet the acceptance criteria for the surveillance requirements, and be capable of performing any mitigation function assumed in the accident analysis. As a result, the consequences of any accident previously evaluated are not significantly increased. Therefore, the proposed change does not involve a significant increase in the probability or consequences of any accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed changes relocate the surveillance frequencies for Surveillance Requirements that have a set periodicity from the TS to a licensee controlled Surveillance Frequency Control Program. This change does not alter any existing surveillance frequencies. Within the constraints of the Program, the licensee will be able to change the periodicity of these surveillance requirements. Relocating the surveillance frequencies does not impact the ability of structures, systems or components (SSCs) from performing there [sic] design functions, and thus, does not create the possibility of a new or different kind of accident from any previously evaluated. No new or different accidents result from utilizing the proposed change. The changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. In addition, the changes do not impose any new or different requirements. The changes do not alter assumptions made in the safety analysis assumptions and current plant operating practice. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in the margin of safety? Response: No. The design, operation, testing methods, and acceptance criteria for systems, structures, and components (SSCs), specified in applicable codes and standards (or alternatives approved for use by the NRC) will continue to be met as described in the plant licensing basis (including the final safety analysis report and bases to TS), since these are not affected by changes to the surveillance frequencies. Similarly, there is no impact to safety analysis acceptance criteria as described in the plant licensing basis. To evaluate a change in the relocated surveillance frequency, FPL will perform a probabilistic risk evaluation using the guidance contained in NRC-approved NEI 04-10, Revision 1, in accordance with the TS Surveillance Frequency Control Program. NEI 04-10, Revision 1, methodology provides reasonable acceptance guidelines and methods for evaluating the risk increase of proposed changes to surveillance frequencies consistent with Regulatory Guide (RG) 1.177, ``An Approach for Plant-Specific, Risk-Informed Decision-Making: Technical Specifications.'' [[Page 27200]] Therefore, the proposed changes do not involve a significant reduction in a margin of safety. The NRC staff 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: William S. Blair, Managing Attorney-- Nuclear, Florida Power & Light Company, 700 Universe Blvd., MS LAW/JB, Juno Beach, FL 33408-0420. NRC Branch Chief: Shana R. Helton. NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold Energy Center, Linn County, Iowa Date of amendment request: January 26, 2015. A publicly-available version is in ADAMS under Accession No. ML15029A600. Description of amendment request: The proposed amendment would revise Technical Specifications (TS) Section 3.8.3, ``Diesel Fuel Oil, Lube Oil, and Starting Air,'' by relocating the current stored diesel fuel oil and lube oil numerical volume requirements from the TS to the TS bases so that it may be modified under licensee control. The proposed amendment would also revise TS conditions to state ``a greater than 6-day and less 7-day'' supply of stored diesel fuel oil and lube oil inventory, in place of the numerical volume requirements, to be available for each diesel generator. The requirement to maintain a 7- day supply of diesel fuel oil and lube oil is not changed and is consistent with the assumptions in the accident analyses. The changes are consistent with NRC-approved Technical Specification Task Force (TSTF) Change Traveler TSTF-501, Revision 1, ``Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee 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. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change relocates the volume of diesel fuel oil and lube oil required to support 7-day operation of an onsite diesel generator; and the volume equivalent to a 6-day supply, to licensee control. The specific volume of fuel oil equivalent to a 7-day and 6-day supply is calculated using the NRC-approved methodology described in Regulatory Guide 1.137, Revision 1, ``Fuel-Oil Systems for Standby Diesel Generators,'' and ANSI N195-1976, ``Fuel Oil Systems for Standby Diesel-Generators.'' The specific volume of lube oil equivalent to a 7-day and 6-day supply is based on the diesel generator manufacturer's consumption values for the run time of the diesel generator. Because the requirement to maintain a 7-day supply of diesel fuel oil and lube oil is not changed and is consistent with the assumptions in the accident analyses, and the actions taken when the volume of fuel oil and lube oil is less than a 6-day supply have not changed, neither the probability nor the consequences of any accident previously evaluated will be affected. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The change does not alter assumptions made in the safety analysis but ensures that the diesel generator operates as assumed in the accident analysis. The proposed change is consistent with the safety analysis assumptions. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed change relocates the volume of diesel fuel oil and lube oil required to support 7-day operation of an onsite diesel generator, and the volume equivalent to a 6-day supply, to licensee control. As the bases for the existing limits on diesel fuel oil and lube oil are not changed, no change is made to the accident analysis assumptions and no margin of safety is reduced as part of this change. Therefore, the proposed change 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. James Petro, P. O. Box 14000 Juno Beach, FL 33408-0420. NRC Branch Chief: David L. Pelton. South Carolina Electric and Gas Company, Docket Nos.: 52-027 and 52- 028, Virgil C. Summer Nuclear Station Units 2 and 3, Fairfield County, South Carolina Date of amendment request: December 19, 2014, as supplemented by letter dated February 25, 2015. Publicly-available versions are in ADAMS under Accession Nos. ML14353A126 and ML15056A429, respectively. Description of amendment request: The amendment request proposes changes to the Class 1E direct current and Uninterruptible Power Supply System, replacing four Spare Termination Boxes with a single Spare Battery Termination Box. Because this proposed change requires a departure from Tier 1 information in the Westinghouse Advanced Passive 1000 Design Control Document (DCD), the licensee also requested an exemption from the requirements of the Generic DCD Tier 1 in accordance with 10 CFR 52.63(b)(1). 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 changes do not affect the operation of any systems or equipment that initiate an analyzed accident or alter any structures, systems, and components (SSC) accident initiator or initiating sequence of events. The IDS design change involves replacing the four Spare Termination Boxes with a single Spare Battery Termination Box, and minor raceway and cable routing changes. The proposed changes maintain the method used to manually connect the Spare Battery Bank and Spare Battery Bank Charger to supply loads of one of the four 24 Hour Battery Switchboards or one of the two 72 Hour Battery Switchboards at a time while maintaining the independence of the IDS divisions. Therefore, the probabilities of the accidents evaluated in the UFSAR [Updated Final Safety Analysis Report] are not affected. The proposed changes do not have an adverse impact on the ability of the IDS equipment to perform its design functions. The design of the IDS equipment continues to meet the same regulatory acceptance criteria, electrical codes, and standards as required by the UFSAR. Therefore, the proposed changes do not affect the prevention and mitigation of other abnormal events, e.g., accidents, anticipated operational occurrences, earthquakes, floods and turbine missiles, or their safety or design analyses. In addition, the proposed changes do not have an adverse effect on any safety- [[Page 27201]] related SSC or function used to mitigate an accident; therefore, the consequences of the accidents evaluated in the UFSAR are not affected. Therefore, the proposed changes do 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 changes do not change the design functions of IDS or any of the systems or equipment in the plant. The IDS design change involves replacing the four Spare Termination Boxes with a single Spare Battery Termination Box, and minor raceway and cable routing changes, and the electrical equipment continues to perform its design functions because the same electrical codes and standards as stated in the UFSAR continue to be met. The proposed changes maintain the method used to manually connect the Spare Battery Bank and Spare Battery Bank Charger to supply loads of one of the four 24 Hour Battery Switchboards or one of the two 72 Hour Battery Switchboards at a time while maintaining the independence of the IDS divisions. These proposed changes do not adversely affect any IDS or SSC design functions or methods of operation in a manner that results in a new failure mode, malfunction, or sequence of events that affect safety-related or non-safety-related equipment. Therefore, this activity does not allow for a new fission product release path, result in a new fission product barrier failure mode, or create a new sequence of events that result in significant fuel cladding failures. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed changes maintain existing safety margins. The proposed changes do not result in changes to the IDS design requirements or design functions. The proposed changes maintain existing safety margin through continued application of the existing requirements of the UFSAR. Therefore, the proposed changes satisfy the same design functions in accordance with the same codes and standards as stated in the UFSAR. These proposed changes do not affect any design code, function, design analysis, safety analysis input or result, or design/safety margin. Because no safety analysis or design basis acceptance limit/ criterion is challenged or exceeded by these proposed changes, no margin of safety is reduced. 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: Ms. Kathryn M. Sutton, Morgan, Lewis & Bockius LLC, 1111 Pennsylvania Avenue NW., Washington, DC 20004-2514. NRC Branch Chief: Lawrence J. Burkhart. 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. Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270 and 50-287, Oconee Nuclear Station, Units 1, 2 and 3, Oconee County, South Carolina Date of amendment request: April 26, 2013, as supplemented by letter dated February 12, 2015. Brief description of amendments: The amendments revised the Oconee Nuclear Station (ONS) Technical Specifications (TSs) surveillance requirement to verify that acceptable steady-state limits on the electrical frequency are achieved by the two Keowee Hydro Units, which are the emergency power sources for the ONS. Date of Issuance: April 23, 2015. Effective date: As of the date of issuance and shall be implemented within 30 days from the date of issuance. Amendment Nos.: 390, 392, and 391. A publicly-available version is in ADAMS under Accession No. ML15093A349. Documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Renewed Facility Operating License Nos. DPR-38, DPR-47, and DPR-55: Amendments revised the Renewed Facility Operating Licenses and TSs. Date of initial notice in Federal Register: July 9, 2013, 78 FR 41121. The supplemental letter dated February 12, 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 amendments is contained in a Safety Evaluation dated April 23, 2015. No significant hazards consideration comments received: No. Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear Plant, Van Buren County, Michigan Date of application for amendment: June 25, 2013, as supplemented by letters dated August 7, 2013; and February 13, July 16, and December 9, 2014. Brief description of amendment: The amendment revises the Palisades Nuclear Plant Site Emergency Plan Figure 5-2, ``Plant Staffing and Augmentation Requirements'' to increase augmentation response times for certain emergency response organization positions. Date of issuance: April 22, 2015. Effective date: As of the date of issuance and shall be implemented within 60 days. Amendment No.: 255. A publicly-available version is in ADAMS under Accession No. ML15055A106; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. [[Page 27202]] Renewed Facility Operating License No. DPR-20: Amendment revised the Renewed Facility Operating License. Date of initial notice in Federal Register: March 18, 2014 (79 FR 15148). The supplement letters dated August 7, 2013, and February 13 and July 16, 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 issued a revised no significant hazards consideration determination that was published in the Federal Register on January 6, 2015 (80 FR 523), to consider the aspects of the revised tasks associated with radiation protection technicians provided in the supplemental letter dated December 9, 2014. The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated April 22, 2015. No significant hazards consideration comments received: No. Entergy Operations, Inc., Docket No. 50-368, Arkansas Nuclear One, Unit 2, Pope County, Arkansas Date of application for amendment: February 6, 2015, as supplemented by letter dated February 24, 2015. Brief description of amendment: The amendment revised a Note to Technical Specification (TS) Surveillance Requirement (SR) 4.1.3.1.2 to exclude Control Element Assembly (CEA) 18 from being exercised per the SR for the remainder of Cycle 24 due to a degrading upper gripper coil. The amendment allows the licensee to delay exercising the CEA until after repairs can be made during the upcoming fall 2015 outage. Date of issuance: April 29, 2015. Effective date: As of the date of issuance and shall be implemented immediately. Amendment No.: 302. A publicly-available version is in ADAMS under Accession No. ML15096A381; 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 TSs/license. Date of initial notice in Federal Register: March 3, 2015 (80 FR 11475). The supplemental letter dated February 24, 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 and final no significant hazards consideration determination are contained in a Safety Evaluation dated April 29, 2015. No significant hazards consideration comments received: No. Entergy Operations, Inc., Docket No. 50-313, Arkansas Nuclear One, Unit 1, Pope County, Arkansas Date of amendment request: November 21, 2014, as supplemented by letters dated February 6, March 10, March 25, and April 7, 2015. Brief description of amendment: The amendment revised Technical Specification (TS) 3.4.3, ``RCS [Reactor Coolant System] Pressure and Temperature (P/T) Limits''; TS 3.4.9, ``Pressurizer''; TS 3.4.10, ``Pressurizer Safety Valves''; and TS 3.4.11, ``Low Temperature Overpressure Protection (LTOP) System,'' to update the RCS P/T limits to 54 effective full power years (EFPY). The current P/T limits are applicable up to 31 EFPY. Date of issuance: April 24, 2015. Effective date: As of the date of issuance and shall be implemented within 30 days from the date of issuance. Amendment No.: 254. A publicly-available version is in ADAMS under Accession No. ML15096A324; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Renewed Facility Operating License No. DPR-51: Amendment revised the TSs/license. Date of initial notice in Federal Register: January 6, 2015 (80 FR 524). The supplemental letters dated February 6, March 10, March 25, and April 7, 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 April 24, 2015. No significant hazards consideration comments received: No. Entergy Operations, Inc., System Energy Resources, Inc., South Mississippi Electric Power Association, and Entergy Mississippi, Inc., Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1, Claiborne County, Mississippi Date of application for amendment: November 8, 2013, as supplemented by letters dated September 29, 2014; November 13 and 19, 2014; and January 20 and 27, 2015. Brief description of amendment: The amendment revised the Technical Specifications (TSs) to risk-inform requirements regarding selected required action end states by adopting Technical Specification Task Force (TSTF) Traveler 423, Revision 1, ``Technical Specifications End States, NEDC-32988-A,'' with some deviations as approved by the NRC staff. This TS improvement is part of the consolidated line item improvement process. In addition, it approves a change to the facility operating license for the Grand Gulf Nuclear Station, Unit 1. The change adds a new license condition for maintaining commitments required for the approval of this TSTF into the Updated Final Safety Analysis Report. Date of issuance: April 23, 2015. Effective date: As of the date of issuance and shall be implemented 60 days from the date of issuance. Amendment No: 201. A publicly-available version is in ADAMS under Accession No. ML15007A183; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Operating License No. NPF-29: The amendment revised the Facility Operating License and TSs. Date of initial notice in Federal Register: March 4, 2014 (79 FR 12245). The supplemental letters dated September 29, November 13, and November 19, 2014; and January 20 and January 27, 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 April 23, 2015. No significant hazards consideration comments received: No. NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit 1, Rockingham County, New Hampshire Date of amendment request: July 10, 2014, as supplemented by letter dated July 22, 2014. [[Page 27203]] Description of amendment request: The amendment revised the Seabrook Station, Unit 1, Cyber Security Plan (CSP) Milestone 8 full implementation date as set forth in the Cyber Security Plan Implementation Schedule. Date of issuance: April 22, 2015. Effective date: As of its date of issuance, and shall be implemented within 60 days. Amendment No.: 146. A publicly-available version is in ADAMS under Accession No. ML15058A706; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Operating License No. NPF-86: The amendment revised the Facility Operating License. Date of initial notice in Federal Register: October 7, 2014 (79 FR 60519). The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated April 22, 2015. No significant hazards consideration comments received: No. NextEra Energy Seabrook, LLC, Docket No. 50-443, Seabrook Station, Unit 1, Rockingham County, New Hampshire Date of amendment request: July 24, 2014, as supplemented by letters dated December 11, 2014, and January 9, 2015. Description of amendment request: The amendment revised the Seabrook Technical Specifications (TS). The amendment increased the voltage limit for a full load rejection test of the emergency diesel generator specified in Surveillance Requirements 4.8.1.1.2.f.3 of TS 3.8.1.1, ``A.C. Sources--Operating.'' The amendment also revised the TS definition of the terms ``Operable--Operability.'' Date of issuance: April 24, 2015. Effective date: As of its date of issuance, and shall be implemented within 60 days. Amendment No.: 147. A publicly-available version is in ADAMS under Accession No. ML15082A233; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Operating License No. NPF-86: The amendment revised the facility operating license and TSs. Date of initial notice in Federal Register: September 30, 2014 (79 FR 58821). The supplemental letters dated December 11, 2014, and January 9, 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 April 24, 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, Units 2 and 3, Fairfield County, South Carolina Date of amendment request: May 20, 2014, and supplemented by the letters dated June 3, November 6, and November 20, 2014. Brief description of amendment: The license amendment revised the facilities' combined operating licenses (COLs) to make changes to COL Appendix C and corresponding plant-specific Tier 1 information to correct editorial errors and/or consistency errors (e.g., inconsistencies between Updated Final Safety Analysis Report (UFSAR) (Tier 2) and Tier 1 information, and inconsistencies between information from different locations within Tier 1). Date of issuance: March 10, 2015. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment No.: 23. A publicly-available version is in ADAMS under Accession No. ML14345B023; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. Facility Combined Licenses Nos. NPF-93 and NPF-94: Amendment revised the facilities' COLs. Date of initial notice in Federal Register: September 2, 2014 (79 FR 52059). The supplemental letters dated June 3, November 6, and November 20, 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 10, 2015. No significant hazards consideration comments received: No. Southern Nuclear Operating Company, Inc. Docket Nos. 52-025 and 52-026, Vogtle Electric Generating Plant (VEGP) Units 3 and 4, Burke County, Georgia Date of amendment request: November 20, 2014. Brief description of amendment: The amendment is to Combined Operating License Nos. NPF-91 and NPF-92 for the VEGP Units 3 and 4. The amendment revises the VEGP Updated Final Safety Analysis Report (UFSAR) to clarify a human factors engineering operational sequence analysis related to the AP1000 Automatic Depressurization System and will delete document WCAP-15847, ``AP1000 Quality Assurance Procedures Supporting NRC Review of AP1000 DCD Sections 18.2 and 18.8,'' that is incorporated by reference into the UFSAR. Both of the amendments constitute changes to information identified as Tier 2* information as defined in 10 CFR, part 52, appendix D, section II.F. Date of issuance: April 21, 2015. Effective date: As of the date of issuance and shall be implemented within 30 days of issuance. Amendment No.: 33. A publicly-available version is in ADAMS under Accession No. ML15023A563; documents related to this amendment are listed in the Safety Evaluation enclosed with the amendment. Facility Combined Licenses No. NPF-91 and NPF-92: Amendment revised the Facility Combined Operating Licenses. Date of initial notice in Federal Register: January 20, 2015 (80 FR 2752). The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated April 21, 2015. No significant hazards consideration comments received: No. Virginia Electric and Power Company, Docket Nos. 50-280 and 50-281, Surry Power Station, Units 1 and 2, Surry County, Virginia Date of amendment request: April 11, 2014, as supplemented by letter dated March 4, 2015. Description of amendment request: The amendments revise Technical Specification (TS) 4.2, ``Augmented Inspections,'' and TS 4.15, ``Augmented Inservice Inspection Program for High Energy Lines Outside of Containment,'' by relocating them to the SPS Technical Requirements Manual (TRM), with the exception of the reactor coolant pump flywheel inspection. In addition, TS 6.4.U, ``Augmented Inspections and Examinations,'' is added to TS 6.4, ``Unit Operating Procedures and Programs.'' Date of issuance: April 28, 2015. Effective date: As of the date of issuance and shall be implemented within 60 days from the date of issuance. Amendment Nos.: 284 and 284. A publicly-available version is in ADAMS under Accession No. ML15099A679; documents related to these amendments are listed in the Safety Evaluation enclosed with the amendments. [[Page 27204]] Renewed Facility Operating License Nos. DPR-32 and DPR-37: Amendments revised the Renewed Facility Operating Licenses and Technical Specifications. Date of initial notice in Federal Register: July 22, 2014 (79 FR 42553). The supplemental letter dated March 4, 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 amendments is contained in a Safety Evaluation dated April 28, 2015. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, this 1st day of May, 2015. For the Nuclear Regulatory Commission. George A. Wilson, Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2015-11225 Filed 5-11-15; 8:45 am] BILLING CODE 7590-01-P
![Federal Register / Vol. 80, No. 91 / Tuesday, May 12, 2015 / Notices 27193
ML13273A493). The NRC staff held NUCLEAR REGULATORY Reactor Regulation, U.S. Nuclear
public meetings on June 5, 2013 COMMISSION Regulatory Commission, Washington,
(ADAMS Accession No. ML13197A216), DC 20555–0001; telephone: 301–415–
[NRC–2015–0117]
and January 30, 2014 (ADAMS 1927, email: Lynn.Ronewicz@nrc.gov.
Accession No. ML14064A550). Public Applications and Amendments to SUPPLEMENTARY INFORMATION:
comments were accepted and are Facility Operating Licenses and I. Obtaining Information and
available at the Federal rulemaking Web Combined Licenses Involving No Submitting Comments
site (www.regulations.gov) under Docket Significant Hazards Considerations
ID NRC–2013–0254. The public A. Obtaining Information
AGENCY: Nuclear Regulatory
comments that were received on the Please refer to Docket ID NRC–2015–
Commission.
draft conceptual agencywide policy 0117 when contacting the NRC about
statement varied greatly. The NRC staff’s ACTION: Biweekly notice.
the availability of information for this
overall assessment was that the SUMMARY: Pursuant to Section 189a. (2) action. You may obtain publicly-
comments indicated a need to revise the of the Atomic Energy Act of 1954, as available information related to this
staff’s approach. The NRC staff is now amended (the Act), the U.S. Nuclear action by any of the following methods:
seeking public comments on a revised Regulatory Commission (NRC) is • Federal Rulemaking Web site: Go to
policy statement approach as described publishing this regular biweekly notice. http://www.regulations.gov and search
in Section III of the draft NRC Staff The Act requires the Commission to for Docket ID NRC–2015–0117.
White Paper. publish notice of any amendments • NRC’s Agencywide Documents
issued, or proposed to be issued and Access and Management System
III. Opportunity for Public Comment (ADAMS): You may obtain publicly-
grants the Commission the authority to
issue and make immediately effective available documents online in the
The NRC staff notes that the draft ADAMS Public Documents collection at
NRC Staff White Paper represents work any amendment to an operating license
or combined license, as applicable, http://www.nrc.gov/reading-rm/
in progress; the information may be adams.html. To begin the search, select
modified before the NRC staff provides upon a determination by the
Commission that such amendment ‘‘ADAMS Public Documents’’ and then
its recommendation to the Commission select ‘‘Begin Web-based ADAMS
involves no significant hazards
for a decision, as a result of internal Search.’’ For problems with ADAMS,
consideration, notwithstanding the
NRC review and/or consideration of please contact the NRC’s Public
pendency before the Commission of a
public comments received. The NRC Document Room (PDR) reference staff at
request for a hearing from any person.
staff will review and consider all timely This biweekly notice includes all 1–800–397–4209, 301–415–4737, or by
comments received on the draft NRC notices of amendments issued, or email to pdr.resource@nrc.gov. The
Staff White Paper, but the staff does not proposed to be issued, from April 16, ADAMS accession number for each
intend to provide detailed comment 2015, to April 29, 2015. The last document referenced (if it is available in
responses for all comments received. biweekly notice was published on April ADAMS) is provided the first time that
Should the Commission proceed with 28, 2015. it is mentioned in the SUPPLEMENTARY
these initiatives, the public will be INFORMATION section.
DATES: Comments must be filed by June
afforded opportunity to provide formal • NRC’s PDR: You may examine and
11, 2015. A request for a hearing must
comment to the NRC through the purchase copies of public documents at
be filed by July 13, 2015.
rulemaking or policy statement the NRC’s PDR, Room O1–F21, One
ADDRESSES: You may submit comments White Flint North, 11555 Rockville
development process. by any of the following methods (unless Pike, Rockville, Maryland 20852.
Persons interested in monitoring this this document describes a different
activity can do so by searching for method for submitting comments on a B. Submitting Comments
Docket ID NRC–2013–0254 on the specific subject): Please include Docket ID NRC–2015–
Federal Rulemaking Web site at • Federal Rulemaking Web site: Go to 0117, facility name, unit number(s),
https://www.regulations.gov. The http://www.regulations.gov and search application date, and subject in your
Federal Rulemaking Web site allows for Docket ID NRC–2015–0117. Address comment submission.
you to receive alerts when changes or questions about NRC dockets to Carol The NRC cautions you not to include
additions occur in a docket folder. To Gallagher; telephone: 301–415–3463; identifying or contact information that
subscribe: (1) Navigate to the docket email: Carol.Gallagher@nrc.gov. For you do not want to be publicly
folder (NRC–2013–0254); (2) click the technical questions, contact the disclosed in your comment submission.
‘‘Email Alert’’ link; and (3) enter your individual listed in the FOR FURTHER The NRC posts all comment
INFORMATION CONTACT section of this submissions at http://
email address and select how frequently
document. www.regulations.gov as well as entering
you would like to receive emails (daily,
• Mail comments to: Cindy Bladey, the comment submissions into ADAMS.
weekly, or monthly). Office of Administration, Mail Stop: The NRC does not routinely edit
Dated at Rockville, Maryland, this 5th day OWFN–12–H08, U.S. Nuclear comment submissions to remove
of May, 2015. Regulatory Commission, Washington, identifying or contact information.
For the Nuclear Regulatory Commission. DC 20555–0001. If you are requesting or aggregating
For additional direction on obtaining
mstockstill on DSK4VPTVN1PROD with NOTICES
Lawrence E. Kokajko, comments from other persons for
information and submitting comments, submission to the NRC, then you should
Director, Division of Policy and Rulemaking,
Office of Nuclear Reactor Regulation.
see ‘‘Obtaining Information and inform those persons not to include
Submitting Comments’’ in the identifying or contact information that
[FR Doc. 2015–11454 Filed 5–11–15; 8:45 am]
SUPPLEMENTARY INFORMATION section of they do not want to be publicly
BILLING CODE 7590–01–P
this document. disclosed in their comment submission.
FOR FURTHER INFORMATION CONTACT: Your request should state that the NRC
Lynn M. Ronewicz, Office of Nuclear does not routinely edit comment
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![27196 Federal Register / Vol. 80, No. 91 / Tuesday, May 12, 2015 / Notices
in ADAMS under Accession No. Therefore, the proposed amendment does 1. Does the proposed amendment involve
ML15065A031. not involve a significant increase in the a significant increase in the probability or
Description of amendment request: probability or consequences of an accident consequences of an accident previously
The amendments would revise previously evaluated. evaluated?
2. Does the proposed amendment create Response: No.
Technical Specification (TS) 1.3, This LAR [license amendment request]
the possibility of a new or different kind of
‘‘Completion Times’’; TS 3.7.5, accident from any accident previously proposes administrative non-technical
‘‘Auxiliary Feedwater (AFW) System’’; evaluated? changes only. These proposed changes do not
TS 3.8.1, ‘‘AC [Alternating Current] Response: No. adversely affect accident initiators or
Sources—Operating’’; and TS 3.8.9, The proposed changes do not involve a precursors nor alter the design assumptions,
‘‘Distribution Systems—Operating,’’ to physical alteration of the plant (i.e., no new conditions, or configurations of the facility.
remove the second completion times. or different type of equipment will be The proposed changes do not alter or prevent
installed) or a change in the methods the ability of structures, systems[,] and
The change would also revise Example components (SSCs) to perform their intended
1.3–3 in TS 1.3, ‘‘Completion Times,’’ governing normal plant operation. The
proposed changes do not alter any function to mitigate the consequences of an
by adding a discussion of administrative initiating event witin the assumed
assumptions made in the safety analyses.
controls to combinations of Conditions 3. Does the proposed amendment involve acceptance limits.
to ensure that the Completion Times for a significant reduction in the margin of Given the above discussion, it is concluded
those conditions are not inappropriately safety? the proposed amendment does not
extended. Response: No. significantly increase the probability or
The proposed changes are consistent The proposed change to delete the second consequences of an accident previously
with the NRC-approved Technical [Completion Time] and the related example evaluated.
of the second Completion Time does not alter 2. Does the proposed amendment create
Specification Task Force (TSTF) the possibility of a new or different kind of
Traveler TSTF–439–A, Revision 2, the manner in which safety limits, limiting
safety systems settings or limiting conditions accident from any accident previously
‘‘Eliminate Second Completion Times evaluated?
for operation are determined. The safety
Limiting Time From Discovery of Response: No.
analysis acceptance criteria are not affected
Failure to Meet an LCO [Limiting by this change. The proposed change will not The LAR proposes administrative non-
Condition of Operation],’’ dated June 20, result in plant operation in a configuration technical changes only. The proposed
2005 (ADAMS Accession No. changes will not alter the design
outside of the design basis.
ML051860296). requirements of any SSC or its function
Therefore, the proposed amendment does
Basis for proposed no significant during accident conditions. No new or
not involve a significant reduction in the
different accidents result from the changes
hazards consideration determination: margin of safety.
proposed. The changes do not involve a
As required by 10 CFR 50.91(a), the The NRC staff has reviewed the physical alteration of the plant or any
licensee has provided its analysis of the licensee’s analysis and, based on that changes in methods governing normal plant
issue of no significant hazards review, it appears that the three operation. The changes do not alter
consideration, which is presented standards of 10 CFR 50.92(c) are assumptions made in the safety analysis.
below: Given the above discussion, it is concluded
satisfied. Therefore, the NRC staff the proposed amendment does not create the
1. Does the proposed amendment involve proposes to determine that the request possibility of a new or different kind of
a significant increase in the probability or for amendments involves no significant accident from any accident previously
consequences of an accident previously hazards consideration. evaluated.
evaluated? 3. Does the proposed amendment involve
Response: No.
Attorney for licensee: Michael G.
Green, Senior Regulatory Counsel, a significant reduction in a margin of safety?
The change proposed by incorporating Response: No.
TSTF–439–A, Revision 2, eliminates certain Pinnacle West Capital Corporation, P.O.
This LAR proposes administrative non-
Completion Times from the Technical Box 52034, Mail Station 8695, Phoenix, technical changes only. The proposed
Specifications. Completion Times are not an AZ 85072–2034. changes do not alter the manner in which
initiator of any accident previously NRC Branch Chief: Michael T. safety limits, limiting safety system settings
evaluated. As a result, the probability of an Markley. or limiting conditions for operation are
accident previously evaluated is not affected. determined. The safety analysis acceptance
The consequences of an accident during the Duke Energy Carolinas, LLC, Docket criteria are not affected by these changes. The
revised Completion Times are no different Nos. 50–369 and 50–370, McGuire proposed changes will not result in plant
than the consequences of the same accident Nuclear Station, Units 1 and 2, operation in a configuration outside the
during the existing Completion Times. As a Mecklenburg County, North Carolina design basis. The proposed changes do not
result, the consequences of an accident adversely affect systems that respond to
previously evaluated are not affected by this Date of amendment request: March safely shutdown the plant and to maintain
change. The proposed change does not alter 23, 2015. A publicly-available version is the plant in a safe shutdown condition.
or prevent the ability of structures, systems, in ADAMS under Accession No. Given the above discussion, it is concluded
or components from performing their ML15097A010. [that] the proposed amendment does not
intended function to mitigate the involve a significant reduction in the margin
Description of amendment request:
consequences of an initiating event within of safety.
the assumed acceptance limits. The amendments would modify the
The proposed change to modify certain definition of RATED THERMAL The NRC staff has reviewed the
Completion Times does not affect the source POWER and delete a footnote that licensee’s analysis and, based on this
term, containment isolation, or radiological allowed for staggered implementation of review, it appears that the three
release assumptions used in evaluating the the previously approved Measurement standards of 10 CFR 50.92(c) are
radiological consequences of an accident
mstockstill on DSK4VPTVN1PROD with NOTICES
Uncertainty Recapture Power Uprate. satisfied. Therefore, the NRC staff
previously evaluated. Further, the proposed Basis for proposed no significant proposes to determine that the
change does not increase the types or
hazards consideration determination: amendment request involves no
amounts of radioactive effluent that may be
released offsite, nor significantly increase the As required by 10 CFR 50.91(a), the significant hazards consideration.
cumulative occupational/public radiation licensee has provided its analysis of the Attorney for licensee: Lara S. Nichols,
exposures. The proposed change is consistent issue of no significant hazards Associate General Counsel, Duke Energy
with the safety analysis assumptions and consideration, which is presented Corporation, 526 South Church Street—
resultant consequences. below: EC07H, Charlotte, NC 28202.
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![27198 Federal Register / Vol. 80, No. 91 / Tuesday, May 12, 2015 / Notices
The proposed change revises or adds SRs Beaver Valley Power Station, Units 1 verification of SG [steam generator] tube
that require verification that the ECCS, RHR, and 2 (BVPS–1 and BVPS–2), technical integrity and SG tube sample selection. The
SDC, CS, and RCIC systems, as appropriate, specifications. Specifically, the proposed SG tube inspection frequency and
are not rendered inoperable due to sample selection criteria will continue to
accumulated gas and to provide allowances
proposed license amendment would
ensure that the SG tubes are inspected such
which permit performance of the revised revise various sections associated with that the probability of a SGTR is not
verification. The proposed change does not steam generators and would include increased. The consequences of a SGTR are
involve a physical alteration of the plant (i.e., changes that are consistent with the bounded by the conservative assumptions in
no new or different type of equipment will guidance provided in Technical the design basis accident analysis. The
be installed) or a change in the methods Specification Task Force (TSTF) proposed changes will not cause the
governing normal plant operation. In Traveler 510, Revision 2, ‘‘Revision to consequences of a SGTR to exceed those
addition, the proposed change does not assumptions.
Steam Generator Program Inspection
impose any new or different requirements Therefore, it is concluded that these
that could initiate an accident. The proposed Frequencies and Tube Sample
changes do not involve a significant increase
change does not alter assumptions made in Selection’’ (ADAMS Accession No. in the probability or consequences of an
the safety analysis and is consistent with the ML110610350). accident previously evaluated.
safety analysis assumptions. Basis for proposed no significant 2. Does the proposed amendment create
Therefore, the proposed change does not hazards consideration determination: the possibility of a new or different kind of
create the possibility of a new or different As required by 10 CFR 50.91(a), the accident from any accident previously
kind of accident from any accident licensee has provided its analysis of the evaluated?
previously evaluated. Response: No.
issue of no significant hazards
3. Does the proposed change involve a Proposed changes to Technical
significant reduction in a margin of safety? consideration, which is presented
Specification 5.5.5.2.f.3 replaces the date and
Response: No. below, along with NRC edits in square
outage when all Alloy 800 sleeves shall be
The proposed change revises or adds SRs brackets: removed from service with a limitation on
that require verification that the ECCS, RHR, 1. Does the proposed amendment involve the individual sleeve service life from the
SDC, CS, and RCIC systems, as appropriate, a significant increase in the probability or date of installation. The allowed maximum
are not rendered inoperable due to consequences of an accident previously service life previously approved for Alloy
accumulated gas and to provide allowances evaluated? 800 sleeves remains unchanged.
which permit performance of the revised Response: No. Implementation of these proposed changes
verification. The proposed change adds new The proposed changes to Technical have no significant effect on either the
requirements to manage gas accumulation in
Specification 5.5.5.2.f.3 replaces the date and configuration of the plant or the manner in
order to ensure the subject systems are
outage when all Alloy 800 sleeves shall be which it is operated. The leak-limiting Alloy-
capable of performing their assumed safety
removed from service with a limitation on 800 sleeves are designed using the applicable
functions. The proposed SRs are more
the individual sleeve service life from the ASME Code as guidance and meet the
comprehensive than the current SRs and will
date of installation. The allowed maximum objectives of the original SG tubing. As a
ensure that the assumptions of the safety
service life previously approved for Alloy result, the functions of the SG will not be
analysis are protected. The proposed change
800 sleeves remains unchanged. Since the significantly affected by the installation of
does not adversely affect any current plant
maximum service life of the Alloy 800 the proposed sleeve. Therefore, the only
safety margins or the reliability of the
equipment assumed in the safety analysis. sleeves is unchanged, the probability of a credible failure mode for the sleeve or tube
Therefore, there are no changes being made failure due to degradation does not increase. is to rupture, which has already been
to any safety analysis assumptions, safety Implementation of the proposed changes to evaluated. No new failure modes,
limits or limiting safety system settings that TS 5.5.5.2.f.3 have no significant effect on malfunctions, or accident initiators have
would adversely affect plant safety as a result either the configuration of the plant or the been created. The continued integrity of the
of the proposed change. manner in which is it operated. The installed sleeve/tube assembly is periodically
Therefore, the proposed change does not consequences of a hypothetical failure of the verified as required by the Technical
involve a significant reduction in a margin of leak-limiting Alloy 800 sleeve/tube assembly Specifications and a sleeved tube will be
safety. are bound by the current steam generator plugged on detection of a flaw in the sleeve
tube rupture (SGTR) analysis described in the or in the pressure boundary portion of the
The NRC staff has reviewed the BVPS–2 Updated Final Safety Analysis original tube wall in the sleeve-to-tube joint.
licensee’s analysis and, based on this Report (UFSAR) because the total number of The proposed changes to TSs 3.4.20, 5.5.5,
review, it appears that the three plugged SG tubes (including equivalency and 5.6.6 are changes consistent with TSTF–
standards of 10 CFR 50.92(c) are associated with installed sleeves) is required 510, editorial corrections, and clarification.
satisfied. Therefore, the NRC staff to be consistent with accident analysis These changes do not affect the operation of
proposes to determine that the assumptions. A main steam line break or the SGs or the ability of the SGs to perform
feedwater line break would not cause a SGTR their design or safety functions; therefore
amendment request involves no
since the sleeves are analyzed for a maximum they do not create new failure modes,
significant hazards consideration. accident differential pressure greater than malfunctions, or accident initiators.
Attorney for licensee: J. Bradley that predicted in the BVPS–2 accident Therefore, the proposed changes do not
Fewell, Exelon Generation, 200 Exelon analysis. The sleeve/tube assembly leakage create the possibility of a new or different
Way, Kennett Square, PA 19348. during plant operation would be minimal kind of accident from any previously
NRC Acting Branch Chief: Michael I. and is well within the allowable Technical evaluated.
Dudek. Specification leakage limits and accident 3. Does the proposed amendment involve
analysis assumptions, neither of which a significant reduction in a margin of safety?
FirstEnergy Nuclear Operating would be changed to compensate for the Response: No.
Company, et al., Docket Nos. 50–334 repair method. The SG tubes in pressurized water reactors
and 50–412, Beaver Valley Power The proposed changes to TSs 3.4.20, 5.5.5, are an integral part of the reactor coolant
Station, Units 1 and 2, Beaver County, and 5.6.6 are consistent with TSTF–510, pressure boundary and, as such, are relied
mstockstill on DSK4VPTVN1PROD with NOTICES
Pennsylvania editorial corrections, and clarifications. upon to maintain the primary system’s
Changes that are consistent with TSTF–510 pressure and inventory. As part of the reactor
Date of amendment request: April 1, and other editorial corrections and coolant pressure boundary, the SG tubes are
2015. A publicly-available version is in clarifications do not change the physical unique in that they are also relied upon as
ADAMS under Accession No. plant or how it is operated; therefore they a heat transfer surface between the primary
ML15092A569. cannot affect the probability or consequence and secondary systems such that residual
Description of amendment request: of a previously-evaluated accident. A heat can be removed from the primary
The amendment would change the proposed change modifies the frequency of system. In addition, the SG tubes also isolate
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![Federal Register / Vol. 80, No. 91 / Tuesday, May 12, 2015 / Notices 27199
the radioactive fission products in the notice supersedes the previous notice in the surveillance requirements, and be
primary coolant from the secondary system. its entirety. capable of performing any mitigation
In summary, the safety function of a SG is The amendment would revise the function assumed in the accident analysis.
maintained by ensuring the integrity of its Technical Specifications (TSs) by As a result, the consequences of any accident
tubes. previously evaluated are not significantly
Proposed changes to Technical
relocating specific surveillance
increased.
Specification 5.5.5.2.f.3 replaces the date and frequency requirements to a licensee- Therefore, the proposed change does not
outage when all Alloy 800 sleeves shall be controlled program with involve a significant increase in the
removed from service with a limitation on implementation of Nuclear Energy probability or consequences of any accident
the individual sleeve service life from the Institute (NEI) 04–10 (Revision 1), previously evaluated.
date of installation. The allowed maximum ‘‘Risk-Informed Technical Specification 2. Does the proposed change create the
service life previously approved for Alloy Initiative 5b, Risk-Informed Method for possibility of a new or different kind of
800 sleeves remains unchanged. Control of Surveillance Frequencies’’ accident from any accident previously
The sleeve and portions of the installed evaluated?
sleeve/tube assembly that represent the
(ADAMS Accession No. ML071360456).
The licensee stated that the NEI 04–10 Response: No.
reactor coolant pressure boundary will be The proposed changes relocate the
monitored and a sleeved tube will be plugged methodology provides reasonable
surveillance frequencies for Surveillance
on detection of a flaw in the sleeve or in the acceptance guidelines and methods for Requirements that have a set periodicity from
pressure boundary portion of the original evaluating the risk increase of proposed the TS to a licensee controlled Surveillance
tube wall in the leak-limiting sleeve/tube changes to surveillance frequencies, Frequency Control Program. This change
assembly. Design criteria and design consistent with Regulatory Guide 1.177, does not alter any existing surveillance
verification testing ensures that the margin of ‘‘An Approach for Plant-Specific, Risk- frequencies. Within the constraints of the
safety is not significantly different from the
Informed Decisionmaking: Technical Program, the licensee will be able to change
original SG tubes.
Specifications’’ (ADAMS Accession No. the periodicity of these surveillance
The proposed changes to TSs 3.4.20, 5.5.5,
ML003740176). The licensee stated that requirements. Relocating the surveillance
and 5.6.6 are changes consistent with TSTF–
the changes are consistent with NRC- frequencies does not impact the ability of
510, editorial corrections, and clarifications.
approved Technical Specification Task structures, systems or components (SSCs)
The proposed changes will continue to
from performing there [sic] design functions,
require monitoring of the physical condition Force (TSTF) Standard Technical and thus, does not create the possibility of a
of the SG tubes such that there will not be Specifications change TSTF–425, new or different kind of accident from any
a reduction in the margin of safety compared Revision 3, ‘‘Relocate Surveillance previously evaluated.
to the current requirements. Frequencies to Licensee Control—
Therefore, the proposed changes do not No new or different accidents result from
RITSTF [Risk-Informed TSTF] Initiative utilizing the proposed change. The changes
involve a significant reduction in the margin
of safety. 5b,’’ Revision 3 (ADAMS Accession No. do not involve a physical alteration of the
ML090850642). The Federal Register plant (i.e., no new or different type of
The NRC staff has reviewed the notice published on July 6, 2009 (74 FR equipment will be installed) or a change in
licensee’s analysis and, based on this 31996), announced the availability of the methods governing normal plant
review, it appears that the three TSTF–425, Revision 3. In the operation. In addition, the changes do not
standards of 10 CFR 50.92(c) are impose any new or different requirements.
supplement dated April 3, 2015, the
satisfied. Therefore, the NRC staff The changes do not alter assumptions made
licensee requested additional in the safety analysis assumptions and
proposes to determine that the surveillance frequencies be relocated to current plant operating practice.
amendment request involves no the licensee-controlled program, Therefore, the proposed changes do not
significant hazards consideration. editorial changes, administrative create the possibility of a new or different
Attorney for licensee: David W. deviations from TSTF–425, and other kind of accident from any accident
Jenkins, FirstEnergy Nuclear Operating changes resulting from differences previously evaluated.
Company, FirstEnergy Corporation, 76 between the Turkey Point Units 3 and 3. Does the proposed change involve a
South Main Street, Akron, OH 44308. 4 TSs and the TSs on which TSTF–425 significant reduction in the margin of safety?
NRC Branch Chief: Douglas A. Response: No.
is based.
Broaddus. Basis for proposed no significant The design, operation, testing methods,
and acceptance criteria for systems,
Florida Power & Light Company (FPL), hazards consideration determination:
structures, and components (SSCs), specified
Docket Nos. 50–250 and 50–251, Turkey As required by 10 CFR 50.91(a), the in applicable codes and standards (or
Point Nuclear Generating Units 3 and 4, licensee provided its analysis of the alternatives approved for use by the NRC)
Miami-Dade County, Florida issue of no significant hazards will continue to be met as described in the
Date of amendment request: April 9, consideration, which is presented plant licensing basis (including the final
2014, as supplemented by letters dated below: safety analysis report and bases to TS), since
1. Does the proposed change involve a these are not affected by changes to the
February 20, 2015, and April 3, 2015. surveillance frequencies. Similarly, there is
Publicly available versions are in significant increase in the probability or
consequences of an accident previously no impact to safety analysis acceptance
ADAMS under Accession Nos. criteria as described in the plant licensing
evaluated?
ML14105A042, ML15069A153, and Response: No. basis. To evaluate a change in the relocated
ML15113A311, respectively. The proposed change relocates the surveillance frequency, FPL will perform a
Description of amendment request: specified frequencies for periodic probabilistic risk evaluation using the
The NRC staff has previously made a surveillance requirements to licensee control guidance contained in NRC-approved NEI
proposed determination that the under a new Surveillance Frequency Control 04–10, Revision 1, in accordance with the TS
Surveillance Frequency Control Program. NEI
mstockstill on DSK4VPTVN1PROD with NOTICES
amendment request dated April 9, 2014, Program. Surveillance frequencies are not an
involves no significant hazards initiator to any accident previously 04–10, Revision 1, methodology provides
evaluated. As a result, the probability of any reasonable acceptance guidelines and
consideration (79 FR 42551; July 22,
accident previously evaluated is not methods for evaluating the risk increase of
2014). Subsequently, by letter dated significantly increased. The systems and proposed changes to surveillance frequencies
April 3, 2015, the licensee provided components required by the Technical consistent with Regulatory Guide (RG) 1.177,
additional information that expanded Specifications for which the surveillance ‘‘An Approach for Plant-Specific, Risk-
the scope of the amendment request as frequencies are relocated are still required to Informed Decision-Making: Technical
originally noticed. Accordingly, this be operable, meet the acceptance criteria for Specifications.’’
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Therefore, the proposed changes do not approved methodology described in South Carolina Electric and Gas
involve a significant reduction in a margin of Regulatory Guide 1.137, Revision 1, ‘‘Fuel- Company, Docket Nos.: 52–027 and 52–
safety. Oil Systems for Standby Diesel Generators,’’ 028, Virgil C. Summer Nuclear Station
The NRC staff reviewed the licensee’s and ANSI N195–1976, ‘‘Fuel Oil Systems for Units 2 and 3, Fairfield County, South
analysis and, based on this review, it Standby Diesel-Generators.’’ The specific Carolina
appears that the three standards of 10 volume of lube oil equivalent to a 7-day and
6-day supply is based on the diesel generator Date of amendment request:
CFR 50.92(c) are satisfied. Therefore, the December 19, 2014, as supplemented by
manufacturer’s consumption values for the
NRC staff proposes to determine that the letter dated February 25, 2015. Publicly-
run time of the diesel generator. Because the
amendment request involves no available versions are in ADAMS under
requirement to maintain a 7-day supply of
significant hazards consideration. Accession Nos. ML14353A126 and
diesel fuel oil and lube oil is not changed and
Attorney for licensee: William S. ML15056A429, respectively.
is consistent with the assumptions in the
Blair, Managing Attorney—Nuclear, accident analyses, and the actions taken Description of amendment request:
Florida Power & Light Company, 700 when the volume of fuel oil and lube oil is The amendment request proposes
Universe Blvd., MS LAW/JB, Juno less than a 6-day supply have not changed, changes to the Class 1E direct current
Beach, FL 33408–0420. neither the probability nor the consequences and Uninterruptible Power Supply
NRC Branch Chief: Shana R. Helton. of any accident previously evaluated will be System, replacing four Spare
NextEra Energy Duane Arnold, LLC, affected. Termination Boxes with a single Spare
Docket No. 50–331, Duane Arnold Therefore, the proposed changes do not Battery Termination Box. Because this
Energy Center, Linn County, Iowa involve a significant increase in the proposed change requires a departure
probability or consequences of an accident from Tier 1 information in the
Date of amendment request: January previously evaluated. Westinghouse Advanced Passive 1000
26, 2015. A publicly-available version is 2. Does the proposed change create the Design Control Document (DCD), the
in ADAMS under Accession No. possibility of a new or different kind of licensee also requested an exemption
ML15029A600. accident from any accident previously from the requirements of the Generic
Description of amendment request: evaluated? DCD Tier 1 in accordance with 10 CFR
The proposed amendment would revise Response: No. 52.63(b)(1).
Technical Specifications (TS) Section The change does not involve a physical Basis for proposed no significant
3.8.3, ‘‘Diesel Fuel Oil, Lube Oil, and alteration of the plant (i.e., no new or hazards consideration determination:
Starting Air,’’ by relocating the current different type of equipment will be installed) As required by 10 CFR 50.91(a), the
stored diesel fuel oil and lube oil or a change in the methods governing normal licensee has provided its analysis of the
numerical volume requirements from plant operation. The change does not alter issue of no significant hazards
the TS to the TS bases so that it may be assumptions made in the safety analysis but consideration, which is presented
modified under licensee control. The ensures that the diesel generator operates as
below:
proposed amendment would also revise assumed in the accident analysis. The
proposed change is consistent with the safety 1. Does the proposed amendment involve
TS conditions to state ‘‘a greater than 6- a significant increase in the probability or
day and less 7-day’’ supply of stored analysis assumptions.
Therefore, the proposed change does not consequences of an accident previously
diesel fuel oil and lube oil inventory, in evaluated?
create the possibility of a new or different
place of the numerical volume Response: No.
kind of accident from any accident The proposed changes do not affect the
requirements, to be available for each
previously evaluated. operation of any systems or equipment that
diesel generator. The requirement to 3. Does the proposed change involve a
maintain a 7-day supply of diesel fuel initiate an analyzed accident or alter any
significant reduction in a margin of safety? structures, systems, and components (SSC)
oil and lube oil is not changed and is Response: No. accident initiator or initiating sequence of
consistent with the assumptions in the The proposed change relocates the volume events. The IDS design change involves
accident analyses. The changes are of diesel fuel oil and lube oil required to replacing the four Spare Termination Boxes
consistent with NRC-approved support 7-day operation of an onsite diesel with a single Spare Battery Termination Box,
Technical Specification Task Force generator, and the volume equivalent to a 6- and minor raceway and cable routing
(TSTF) Change Traveler TSTF–501, day supply, to licensee control. As the bases changes. The proposed changes maintain the
Revision 1, ‘‘Relocate Stored Fuel Oil for the existing limits on diesel fuel oil and method used to manually connect the Spare
and Lube Oil Volume Values to Battery Bank and Spare Battery Bank Charger
lube oil are not changed, no change is made
to supply loads of one of the four 24 Hour
Licensee Control.’’ to the accident analysis assumptions and no Battery Switchboards or one of the two 72
Basis for proposed no significant margin of safety is reduced as part of this Hour Battery Switchboards at a time while
hazards consideration determination: change. maintaining the independence of the IDS
As required by 10 CFR 50.91(a), the Therefore, the proposed change does not divisions. Therefore, the probabilities of the
licensee has provided its analysis of the involve a significant reduction in a margin of accidents evaluated in the UFSAR [Updated
issue of no significant hazards safety. Final Safety Analysis Report] are not
consideration, which is presented affected.
below: The NRC staff has reviewed the The proposed changes do not have an
licensee’s analysis and, based on this adverse impact on the ability of the IDS
1. Does the proposed change involve a review, it appears that the three equipment to perform its design functions.
significant increase in the probability or standards of 10 CFR 50.92(c) are The design of the IDS equipment continues
consequences of an accident previously to meet the same regulatory acceptance
evaluated?
satisfied. Therefore, the NRC staff
criteria, electrical codes, and standards as
mstockstill on DSK4VPTVN1PROD with NOTICES
Response: No. proposes to determine that the required by the UFSAR. Therefore, the
The proposed change relocates the volume amendment request involves no proposed changes do not affect the
of diesel fuel oil and lube oil required to significant hazards consideration. prevention and mitigation of other abnormal
support 7-day operation of an onsite diesel Attorney for licensee: Mr. James Petro, events, e.g., accidents, anticipated
generator; and the volume equivalent to a 6- P. O. Box 14000 Juno Beach, FL 33408– operational occurrences, earthquakes, floods
day supply, to licensee control. The specific and turbine missiles, or their safety or design
volume of fuel oil equivalent to a 7-day and
0420. analyses. In addition, the proposed changes
6-day supply is calculated using the NRC- NRC Branch Chief: David L. Pelton. do not have an adverse effect on any safety-
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![27202 Federal Register / Vol. 80, No. 91 / Tuesday, May 12, 2015 / Notices
Renewed Facility Operating License proposed no significant hazards Entergy Operations, Inc., System Energy
No. DPR–20: Amendment revised the consideration determination as Resources, Inc., South Mississippi
Renewed Facility Operating License. published in the Federal Register. Electric Power Association, and Entergy
Date of initial notice in Federal Mississippi, Inc., Docket No. 50–416,
The Commission’s related evaluation
Register: March 18, 2014 (79 FR Grand Gulf Nuclear Station, Unit 1,
of the amendment and final no
15148). The supplement letters dated Claiborne County, Mississippi
significant hazards consideration
August 7, 2013, and February 13 and
determination are contained in a Safety Date of application for amendment:
July 16, 2014, provided additional
Evaluation dated April 29, 2015. November 8, 2013, as supplemented by
information that clarified the
letters dated September 29, 2014;
application, did not expand the scope of No significant hazards consideration
November 13 and 19, 2014; and January
the application as originally noticed, comments received: No.
20 and 27, 2015.
and did not change the staff’s original
Entergy Operations, Inc., Docket No. 50– Brief description of amendment: The
proposed no significant hazards
313, Arkansas Nuclear One, Unit 1, amendment revised the Technical
consideration determination as
Pope County, Arkansas Specifications (TSs) to risk-inform
published in the Federal Register. The
requirements regarding selected
Commission issued a revised no Date of amendment request: required action end states by adopting
significant hazards consideration November 21, 2014, as supplemented by Technical Specification Task Force
determination that was published in the letters dated February 6, March 10, (TSTF) Traveler 423, Revision 1,
Federal Register on January 6, 2015 (80
March 25, and April 7, 2015. ‘‘Technical Specifications End States,
FR 523), to consider the aspects of the
Brief description of amendment: The NEDC–32988–A,’’ with some deviations
revised tasks associated with radiation
amendment revised Technical as approved by the NRC staff. This TS
protection technicians provided in the
Specification (TS) 3.4.3, ‘‘RCS [Reactor improvement is part of the consolidated
supplemental letter dated December 9,
line item improvement process. In
2014. Coolant System] Pressure and
addition, it approves a change to the
The Commission’s related evaluation Temperature (P/T) Limits’’; TS 3.4.9,
facility operating license for the Grand
of the amendment is contained in a ‘‘Pressurizer’’; TS 3.4.10, ‘‘Pressurizer
Gulf Nuclear Station, Unit 1. The
Safety Evaluation dated April 22, 2015. Safety Valves’’; and TS 3.4.11, ‘‘Low
No significant hazards consideration change adds a new license condition for
Temperature Overpressure Protection maintaining commitments required for
comments received: No. (LTOP) System,’’ to update the RCS the approval of this TSTF into the
Entergy Operations, Inc., Docket No. 50– P/T limits to 54 effective full power Updated Final Safety Analysis Report.
368, Arkansas Nuclear One, Unit 2, years (EFPY). The current P/T limits are Date of issuance: April 23, 2015.
Pope County, Arkansas applicable up to 31 EFPY. Effective date: As of the date of
Date of application for amendment: Date of issuance: April 24, 2015. issuance and shall be implemented 60
February 6, 2015, as supplemented by days from the date of issuance.
Effective date: As of the date of
letter dated February 24, 2015. Amendment No: 201. A publicly-
issuance and shall be implemented
Brief description of amendment: The available version is in ADAMS under
within 30 days from the date of
amendment revised a Note to Technical Accession No. ML15007A183;
issuance. documents related to this amendment
Specification (TS) Surveillance
Requirement (SR) 4.1.3.1.2 to exclude Amendment No.: 254. A publicly- are listed in the Safety Evaluation
Control Element Assembly (CEA) 18 available version is in ADAMS under enclosed with the amendment.
from being exercised per the SR for the Accession No. ML15096A324; Facility Operating License No. NPF–
remainder of Cycle 24 due to a documents related to this amendment 29: The amendment revised the Facility
degrading upper gripper coil. The are listed in the Safety Evaluation Operating License and TSs.
amendment allows the licensee to delay enclosed with the amendment. Date of initial notice in Federal
exercising the CEA until after repairs Renewed Facility Operating License Register: March 4, 2014 (79 FR 12245).
can be made during the upcoming fall The supplemental letters dated
No. DPR–51: Amendment revised the
2015 outage. September 29, November 13, and
TSs/license.
Date of issuance: April 29, 2015. November 19, 2014; and January 20 and
Effective date: As of the date of Date of initial notice in Federal January 27, 2015, provided additional
issuance and shall be implemented Register: January 6, 2015 (80 FR 524). information that clarified the
immediately. The supplemental letters dated February application, did not expand the scope of
Amendment No.: 302. A publicly- 6, March 10, March 25, and April 7, the application as originally noticed,
available version is in ADAMS under 2015, provided additional information and did not change the staff’s original
Accession No. ML15096A381; that clarified the application, did not proposed no significant hazards
documents related to this amendment expand the scope of the application as consideration determination as
are listed in the Safety Evaluation originally noticed, and did not change published in the Federal Register.
enclosed with the amendment. the staff’s original proposed no The Commission’s related evaluation
Renewed Facility Operating License significant hazards consideration of the amendment is contained in a
No. NPF–6: Amendment revised the determination as published in the Safety Evaluation dated April 23, 2015.
TSs/license. Federal Register. No significant hazards consideration
mstockstill on DSK4VPTVN1PROD with NOTICES
Date of initial notice in Federal comments received: No.
Register: March 3, 2015 (80 FR 11475). The Commission’s related evaluation
The supplemental letter dated February of the amendment is contained in a NextEra Energy Seabrook, LLC, Docket
24, 2015, provided additional Safety Evaluation dated April 24, 2015. No. 50–443, Seabrook Station, Unit 1,
information that clarified the Rockingham County, New Hampshire
No significant hazards consideration
application, did not expand the scope of comments received: No. Date of amendment request: July 10,
the application as originally noticed, 2014, as supplemented by letter dated
and did not change the staff’s original July 22, 2014.
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![27204 Federal Register / Vol. 80, No. 91 / Tuesday, May 12, 2015 / Notices
Renewed Facility Operating License ADDRESSES: Please refer to Docket ID OVERSEAS PRIVATE INVESTMENT
Nos. DPR–32 and DPR–37: Amendments NRC–2015–0059 when contacting the CORPORATION
revised the Renewed Facility Operating NRC about the availability of
Licenses and Technical Specifications. information for this action. You may Sunshine Act Meeting Notice
Date of initial notice in Federal obtain publicly-available information
Register: July 22, 2014 (79 FR 42553). related to this action by any of the TIME AND DATE: 2 p.m., Wednesday, June
The supplemental letter dated March 4, 3, 2015.
following methods:
2015, provided additional information PLACE: Offices of the Corporation,
that clarified the application, did not • Federal Rulemaking Web site: Go to
Twelfth Floor Board Room, 1100 New
expand the scope of the application as http://www.regulations.gov and search
York Avenue NW., Washington, DC.
originally noticed, and did not change for Docket ID NRC–2015–0059.
STATUS: Hearing OPEN to the Public at
the staff’s original proposed no • NRC’s Agencywide Documents 2 p.m.
significant hazards consideration Access and Management System
determination as published in the MATTERS TO BE CONSIDERED:
(ADAMS): You may obtain publicly-
Federal Register. available documents online in the Purpose
The Commission’s related evaluation ADAMS Public Documents collection at
of the amendments is contained in a Public Hearing in conjunction with
http://www.nrc.gov/reading-rm/ each meeting of OPIC’s Board of
Safety Evaluation dated April 28, 2015. adams.html. To begin the search, select
No significant hazards consideration Directors, to afford an opportunity for
‘‘ADAMS Public Documents’’ and then any person to present views regarding
comments received: No. select ‘‘Begin Web-based ADAMS the activities of the Corporation.
Dated at Rockville, Maryland, this 1st day Search.’’ For problems with ADAMS,
of May, 2015. please contact the NRC’s Public Procedures
For the Nuclear Regulatory Commission. Document Room (PDR) reference staff at Individuals wishing to address the
George A. Wilson, 1–800–397–4209, 301–415–4737, or by hearing orally must provide advance
Deputy Director, Division of Operating email to pdr.resource@nrc.gov. The notice to OPIC’s Corporate Secretary no
Reactor Licensing, Office of Nuclear Reactor ADAMS accession number for each later than 5 p.m. Thursday, May 28,
Regulation. document referenced (if it is available in 2015. The notice must include the
[FR Doc. 2015–11225 Filed 5–11–15; 8:45 am] ADAMS) is provided the first time that individual’s name, title, organization,
BILLING CODE 7590–01–P it is mentioned in the SUPPLEMENTARY address, and telephone number, and a
INFORMATION section. Draft NUREG– concise summary of the subject matter
2178, ‘‘Refining and Characterizing Heat to be presented.
NUCLEAR REGULATORY Oral presentations may not exceed ten
Release Rates from Electrical Enclosures
COMMISSION (10) minutes. The time for individual
During Fire (RACHELLE–FIRE), is
[NRC–2015–0059] available in ADAMS under Accession presentations may be reduced
No. ML15111A045. proportionately, if necessary, to afford
Refining and Characterizing Heat all participants who have submitted a
Release Rates From Electrical • NRC’s PDR: You may examine and timely request an opportunity to be
Enclosures During Fire (RACHELLE– purchase copies of public documents at heard.
FIRE); Correction the NRC’s PDR, Room O1–F21, One Participants wishing to submit a
White Flint North, 11555 Rockville written statement for the record must
AGENCY: Nuclear Regulatory Pike, Rockville, Maryland 20852.
Commission. submit a copy of such statement to
FOR FURTHER INFORMATION CONTACT: OPIC’s Corporate Secretary no later than
ACTION: Draft NUREG; request for
David Stroup, Office of Nuclear 5 p.m. Thursday, May 28, 2015. Such
comment; correction. statement must be typewritten, double
Regulatory Research; telephone: 301–
SUMMARY: The U.S. Nuclear Regulatory 251–7609; email: David.Stroup@nrc.gov; spaced, and may not exceed twenty-five
Commission (NRC) is correcting a notice U.S. Nuclear Regulatory Commission, (25) pages.
that was published in the Federal Washington, DC 20555–0001. Upon receipt of the required notice,
Register (FR) on April 30, 2015, OPIC will prepare an agenda, which
announcing the issuing for public SUPPLEMENTARY INFORMATION: In the FR will be available at the hearing, that
comment of a draft NUREG, NUREG– on April 30, 2015, in FR Doc. 2015– identifies speakers, the subject on which
2178 (EPRI 3002005578), ‘‘Refining and 10126, on page 24290, in the second each participant will speak, and the
Characterizing Heat Release Rates from column, third paragraph under the time allotted for each presentation.
Electrical Enclosures During Fire heading ‘‘I. Obtaining Information and A written summary of the hearing will
(RACHELLE–FIRE), Volume 1: Peak Submitting Comments,’’ the ADAMS be compiled, and such summary will be
Heat Release Rates and Effect of Accession number ‘‘ML15056A144’’ is made available, upon written request to
Obstructed Plume.’’ This action is corrected to read ‘‘ML15111A045.’’ OPIC’s Corporate Secretary, at the cost
necessary to correct the Agencywide Dated at Rockville, Maryland, this 4 day of
of reproduction.
Documents Access and Management May, 2015. Written summaries of the projects to
(ADAMS) Accession number for be presented at the June 11, 2015 Board
For the Nuclear Regulatory Commission.
NUREG–2178. meeting will be posted on OPIC’s Web
mstockstill on DSK4VPTVN1PROD with NOTICES
Mark H. Salley, site.
DATES: This correction is effective
Chief, Fire Research Branch, Division of Risk
immediately. Submit comments by June CONTACT PERSON FOR MORE INFORMATION:
Analysis, Office of Nuclear Regulatory
15, 2015. Comments received after this Information on the hearing may be
Research.
date will be considered if it is practical obtained from Catherine F.I. Andrade at
[FR Doc. 2015–11450 Filed 5–11–15; 8:45 am]
to do so, but the Commission is able to (202) 336–8768, via facsimile at (202)
ensure consideration only for comments BILLING CODE 7590–01–P 408–0297, or via email at
received before this date. Catherine.Andrade@opic.gov.
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Document Created: 2015-12-16 07:55:46
Document Modified: 2015-12-16 07:55:46
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Biweekly notice. | |
| Dates | Comments must be filed by June 11, 2015. A request for a hearing must be filed by July 13, 2015. | |
| Contact | Lynn M. Ronewicz, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1927, email: [email protected] | |
| FR Citation | 80 FR 27193 |
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