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| | number = ML12067A078 | | | number = ML12067A078 |
| | issue date = 03/13/2012 | | | issue date = 03/13/2012 |
| | title = North Anna Power Station, Unit Nos. 1 and 2 - Correction to Issuance of Amendments Regarding Addition of Analytical Methodology to Core Operating Limits Report for Best Estimate Large Break Loss-of-Coolant Accident | | | title = Correction to Issuance of Amendments Regarding Addition of Analytical Methodology to Core Operating Limits Report for Best Estimate Large Break Loss-of-Coolant Accident |
| | author name = Sreenivas V | | | author name = Sreenivas V |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
Revision as of 18:41, 8 February 2019
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MONTHYEARML1029804472010-10-21021 October 2010 Proposed License Amendment Request (LAR) Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA) Project stage: Request ML1031406372010-11-10010 November 2010 Acceptance Review of Addition of Analytical Methodology to COLR Best-Estimate Large Break LOCA-TAC ME4933 and ME4934 Project stage: Acceptance Review ML11166A2532011-06-21021 June 2011 Request for Additional Information, Addition of Analytical Methodology to the Technical Specifications Project stage: RAI ML1117413232011-06-23023 June 2011 Supplemental Information to Support Proposed License Amendment Request for Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA) Project stage: Supplement ML11241A0452011-08-22022 August 2011 Response to Request for Additional Information Proposed License Amendment Request (LAR) Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA) Project stage: Response to RAI ML12054A1682012-02-29029 February 2012 Issuance of Amendments 267 & 248 Regarding Addition of Analytical Methodology to Core Operating Limits Report for Best Estimate Large Break Loss-of-Coolant Accident (TAC Nos. ME4933 and ME4934) Project stage: Approval ML12068A0512012-03-0707 March 2012 Administrative Correction to License Amendment Nos. 267/248 Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA) Project stage: Other ML12067A0782012-03-13013 March 2012 Correction to Issuance of Amendments Regarding Addition of Analytical Methodology to Core Operating Limits Report for Best Estimate Large Break Loss-of-Coolant Accident Project stage: Approval 2011-06-23
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Category:Letter
MONTHYEARIR 05000338/20244202024-09-23023 September 2024 Security Baseline Inspection Report 05000338/2024420 and 05000339/2024420, Cover Letter IR 05000338/20244022024-09-17017 September 2024 Security Baseline Inspection Report 05000338/2024402 and 05000339/2024402 ML24215A2622024-08-28028 August 2024 Transmittal Letter for Subsequent Renewed License IR 05000338/20240052024-08-27027 August 2024 Updated Inspection Plan for North Anna Power Station, Units 1 and 2 (Report 05000338/2024005 and 05000339/2024005) 05000339/LER-2024-001, Loss of Generator Field for 2J Eog During 2-PT-82.282024-08-20020 August 2024 Loss of Generator Field for 2J Eog During 2-PT-82.28 ML24234A0742024-08-15015 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-23-63, NEI 03-08 Needed Guidance: PWR Thermal Shield Flexure Inspection Requirements ML24221A1902024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Pamunkey Indian Tribe ML24163A3002024-08-0808 August 2024 Request for Relief Request N1-I5-NDE-007 Inservice Inspection Alternative ML24206A0062024-08-0808 August 2024 Notice of Availability of the Final Environmental Impact Statement for the North Anna Nuclear Power Station Unit Numbers 1 and 2 Subsequent License Renewal (Docket Numbers: 50-338 and 50-339) ML24221A1832024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Chickahominy Indian Tribe-Eastern Division ML24221A1852024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Tribe of Indians ML24221A1942024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-United Keetoowah Band of Cherokee Indians in Oklahoma ML24221A1912024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Rappahannock Tribe, Inc ML24221A1882024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Monacan Indian Nation ML24221A1932024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Upper Mattaponi Tribe ML24206A0052024-08-0808 August 2024 SLR Final EIS Letter to Achp ML24221A1842024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Delaware Nation, Oklahoma ML24221A1922024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Tuscarora Nation of New York ML24221A1872024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Shawnee Tribe of Oklahoma ML24221A1862024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Eastern Band of Cherokee Indians ML24221A1812024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Catawba Indian Nation ML24208A0142024-08-0808 August 2024 Tribal Section 106 Letters-North Anna-Absentee-Shawnee Tribe of Indians of Oklahoma ML24221A1822024-08-0808 August 2024 Tribal Section 106 Letters - North Anna - Chickahominy Indian Tribe ML24221A1892024-08-0808 August 2024 Tribal Section 106 Letters-North Anna - Nansemond Indian Nation ML24241A0692024-08-0606 August 2024 ISFSI, Submittal of Cask Registration for Spent Fuel Storage IR 05000338/20240022024-08-0202 August 2024 Integrated Inspection Report 05000338/2024002 and 05000339/2024002 ML24206A0432024-07-26026 July 2024 Feis - Letter to the Applicant 05000338/LER-2024-001, Automatic Reactor Trip Due to Prni High Negative Rate2024-07-25025 July 2024 Automatic Reactor Trip Due to Prni High Negative Rate ML24206A0902024-07-24024 July 2024 Owners Activity Report ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML24165A1462024-06-0505 June 2024 Loss of Generator Field for 2J EDG During 2-PT-82.28 IR 05000338/20240102024-05-24024 May 2024 NRC Fire Protection Team Inspection (FPTI) Report 05000338/2024010 and 05000339/2024010 IR 05000338/20240012024-05-10010 May 2024 Integrated Inspection Report 05000338/2024001 and 05000339/2024001 IR 05000338/20244032024-04-30030 April 2024 – Security Baseline Inspection Report 05000338-2024403 and 05000339-2024403 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24110A1462024-04-18018 April 2024 Independent Spent Fuel Storage Installation (Sfsi) - Annual Radiological Environmental Operating Report ML24110A1502024-04-18018 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report ML24110A1392024-04-18018 April 2024 Annual Environmental Operating Report ML24087A0572024-04-16016 April 2024 Correction to Issuance of Amendment Nos. 296 and 279 ML24088A2692024-03-27027 March 2024 Core Operating Limits Report Cycle 31 Pattern Sos Revision 0 ML24086A4292024-03-25025 March 2024 Response to Request for Additional Information Associated with Alternative Request N1-I5-NDE-007 Request to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24082A2742024-03-22022 March 2024 Request for Approval of Alternative Request N1-I5-NDE-007 to Deter Additional Required Reactor Coolant Pump Casing Inspection ML24086A4682024-03-21021 March 2024 Summary of Facility Changes, Tests and Experiments ML24005A0042024-03-18018 March 2024 Issuance of Amendment Nos. 296 and 279, Regarding Revised Emergency Plan for Relocation of the Technical Support Center ML24074A3012024-03-14014 March 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000338-2024403 and 05000339-2024403) IR 05000338/20244012024-03-0808 March 2024 Security Baseline Inspection Report 05000338/2024401, 05000339/2024401 and 07200016/2024401 IR 05000338/20230062024-02-28028 February 2024 Annual Assessment Letter for North Anna Power Station, Units 1 and 2 - NRC Inspection Reports 05000338/2023006 and 05000339/2023006 2024-09-23
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 March 13, 2012 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center SOOO Dominion Boulevard Glen Allen, VA 23060-6711 NORTH ANNA POWER STATION, UNITS 1 AND 2 -CORRECTION RE: ISSUANCE OF AMENDMENTS REGARDING ADDITION OF ANALYTICAL METHODOLOGY TO CORE OPERATING LIMITS REPORT FOR BEST ESTIMATE LARGE BREAK LOSS-OF-COOLANT ACCIDENT (TAC NOS. ME4933 AND ME4934)
Dear Mr. Heacock:
By letter dated February 29, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 120S4A168), the U.S. Nuclear Regulatory Commission (NRC) has issued Amendment Nos. 267 and 248 to Renewed Facility Operating License Nos. NPF-4 and NPF-7 for the North Anna Power Station, Units 1 and 2 (NAPS 1 and 2), respectively.
The amendments change the Technical Specifications (TSs) in response to your application dated October 21, 2010, as supplemented June 23 and August 22, 2011. These amendments add a reference to TSs S.6.S.b, "Core Operating Limits Report (COLR)," to permit the use of the "Westinghouse Best Estimate Large Break Loss-of-Coolant Accident (BE-LBLOCA)
Evaluation Methodology using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)" for the analysis of LBLOCA. By letter dated March 7,2012 (ADAMS Accession No. ML 12068A051), Dominion identified an inadvertent typographical error on TS page 5.6-3 provided with their application and requested the NRC to re-issue the corrected TS page. Because of this error, the mark-up and the typed TS Page S.6-3, did not match for TS S.6.S.b. item 7. The enclosure to this letter provides a corrected Page S.6-3 for NAPS 1 and 2.
D. Heacock -2 Please contact me, if you have any questions regarding this correction letter. Sincerely, r. V. Sreenivas, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339
Enclosures:
- 1. Corrected Page 5.6-3 for NAPS, Units 1 and 2, Amendment Nos. 267 and 248. cc wi encl: Distribution via Listserv Reporting Requirements 5.6 5.6 Reporting Requirements S.6.5 CORE OPERATING LIMITS REPORT (COLR) {continued} The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: VEP-FRD-42-A, "Reload Nucl ear Des ign Methodology." Plant-specific adaptation of WCAP-16009-P-A, "Realistic large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," as approved by NRC Safety Evaluation Report dated February 29, 2012. WCAP-I0054-P-A. "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code." WCAP-I0079-P-A.
nNOTRUMP.
A Nodal Transient Small Break and General Network Code." WCAP-12610, "YANTAGE+
FUEL ASSEMBLY-REFERENCE CORE REPORT. II YEP-NE-2-A. "Statistical DNBR Evaluation Methodology," VEP-NE-I-A. "VEPCO Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications." WCAP-874S-P-A. "Design Bases for Thermal Overpower De1ta-T Thermal Overtemperature Delta-T Trip Function," WCAP-14483-A. "Gener1c Methodology for Expanded Core Operating Limits 10. BAW-I0227P-A. "Evaluation of Advanced Cladding and Structural Material (MS) in PWR Reactor Fuel." BAW-I0199P-A.
liThe BWU Critical Heat Flux Correlations." BAW-10170P-A, IIStatistical Core Design for Mixing Vane Cores. ,I (continued)
North Anna Units 1 and 2 5.6-3 Amendments 267 and 248 Corrected by letter dated March 13, 2012 D. Heacock -2 Please contact me, if you have any questions regarding this correction letter. Sincerely, IRA! Dr. V. Sreenivas, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339
Enclosures:
- 1. Corrected Page 5.6-3 for NAPS, Units 1 and 2, Amendment Nos. 267 and 248. cc wI encl: Distribution via Listserv DISTRIBUTION:
Public LPL2-1 RlF RidsNrrDssSrxb Resource RidsNrrPMNorthAnna RidsAcrsAcnw_MailCTR RidsNrrLAS Fig ueroa RidsNrrDirsltsb RidsOgcRp RidsNrrDorlDpr RidsRgn2MailCenter RidsNrrLpl2-1 Resource T. Huang. NRRlSRXB L. Ward. NRRlSNPB ADAMS Accession No ML 12067 A078 OFFICE NRRlLPL2-1/PM NRRlLPL2-1/LA NRRlLPL2-lIBC NRRlLPL2-1/PM NAME VSreenivas SFigueroa NSalgado VSreenivas DATE 03/07/12 03/12112 03/08/12 03/13/12 OFFICIAL RECORD COpy