ML12068A051

Administrative Correction to License Amendment Nos. 267/248 Addition of Analytical Methodology to COLR Best-Estimate Large Break Loss of Coolant Accident (BE-LBLOCA)

ML12068A051
Person / Time
Site:	North Anna
Issue date:	03/07/2012
From:	Huber T Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
12-146
Download: ML12068A051 (4)

Text

Dominion Resonrces Services, Inc.

lnnsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 March 7, 2012 U.S. Nuclear Regulatory Commission Serial No.12-146 Attention: Document Control Desk NLOS/ETS RO Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STAllON UNITS 1 AND 2 ADMINISTRATIVE CORRECTION TO LICENSE AMENDMENT NOS. 267/248 ADDITION OF ANALYTICAL METHODOLOGY TO COLR BEST-ESTIMATE LARGE BREAK LOSS OF COOLANT ACCIDENT (BE-LBLOCA)

By applications dated July 19, 2010 and October 21, 2010, Dominion requested amendments to the Technical Specifications (TSs) for the North Anna Power Station (NAPS), Units 1 and 2. The NRC approved the proposed amendment in a letter dated February 29, 2012. Dominion has reviewed the SERs and the approved TS pages and identified an inadvertent typographical error on TS page 5.6-3, which was submitted as part of the original application in Attachment 3, "Proposed Technical Specifications Pages (Typed)."

Specifically Item 7 of the Core Operating Limits Report list of approved methodologies is a Dominion methodology and not a Westinghouse methodology. Therefore, the report number for item 7 should be "VEP-NE-1-A," not "WCAP-NE-1-A." Attachment 2, "Proposed Technical Specifications Pages (Mark-Up)," of the original applications correctly identified the methodology as VEP-NE-1-A. Dominion requests the NRC re-issue the TS page with the reference as noted in the mark-up.

If you have any questions or require additional information, please contact Mr. Thomas Shaub at (804) 273-2763.

Sincerely,

1. ~

T. R. Huber Director, Nuclear Licensing and Operations Support Dominion Resources Services, Inc.

for Virginia Electric and Power Company Attachment TS Page 5.6-3

Serial No.12-146 Docket No. 50-338/339 Page 20f2 cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. J. E. Reasor, Jr.

Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.

Suite 300 Glen Allen, Virginia 23060 State Health Commissioner Virginia Department of Health James Madison Building - 7th Floor 109 Governor Street Suite 730 Richmond, Virginia 23219 NRC Senior Resident Inspector North Anna Power Station Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G 9A 11555 Rockville Pike Rockville, Maryland 20852 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G 9A 11555 Rockville Pike Rockville, Maryland 20852

Serial No.12-146 Docket No. 50-338/339 Attachment TS Page 5.6-3 Virginia Electric and Power Company (Dominion)

North Anna Units 1 and 2

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

b. 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:

1. VEP-FRD-42-A. "Reload Nuclear Design Methodology."

2. 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.

3. WCAP-10054-P-A. "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code."

4. WCAP-I0079-P-A. "NOTRUMP. A Nodal Transient Small Break and I General Network Code."

5. WCAP-126l0. "VANTAGE+ FUEL ASSEMBLY-REFERENCE CORE REPORT."

6. VEP-NE-2-A. "Statistical DNBR Evaluation Methodology."

7. VEP-NE-l-A. "VEPCO Relaxed Power Distribution Control Methodology and Associated FQ Surveillance Technical Specifications."

8. WCAP-8745-P-A, "Design Bases for Thermal Overpower Delta-T and Thermal Overtemperature Delta-T Trip Function."

9. WCAP-14483-A. "Generic Methodology for Expanded Core Operating Limits Report."

10. BAW-l0227P-A. "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel."

11. BAW-10199P-A. "The BWU Critical Heat Flux Correlations."

12. BAW-10170P-A. "Statistical Core Design for Mixing Vane Cores."

(continued)

North Anna Units 1 and 2 5.6-3 Amendments