ML12067A078

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

ML12067A078
Person / Time
Site:	North Anna
Issue date:	03/13/2012
From:	V Sreenivas Plant Licensing Branch II
To:	Heacock D A Virginia Electric & Power Co (VEPCO)
Sreenivas V
References
TAC ME4933, TAC ME4934
Download: ML12067A078 (4)

Text

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