ML103050273

Correction to Amendment Regarding Technical Specification Revisions Related to the Measurement Uncertainty Recapture (Mur) Power Uprate

ML103050273
Person / Time
Site:	Surry
Issue date:	11/02/2010
From:	Cotton K Plant Licensing Branch II
To:	Heacock D Virginia Electric & Power Co (VEPCO)
Cotton K
References
TAC ME3293, TAC ME3294
Download: ML103050273 (5)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 November 2, 2010 Mr. David A. Heacock President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 SURRY POWER STATION, UNIT NOS. 1 AND 2, CORRECTION TO AMENDMENTS REGARDING TECHNICAL SPECIFICATION REVISIONS RELATED TO THE MEASUREMENT UNCERTAINTY RECAPTURE (MUR) POWER UPRATE (TAC NOS.

ME3293 AND ME3294)

Dear Mr. Heacock:

The U.S. Nuclear Regulatory Commission issued the Amendment No. 269 to Renewed Facility Operating License No. DPR-32 and Amendment No. 268 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively on September 24, 2010. The amendments changed the Technical Specifications in response to your application dated January 27, 2010 1 , as supplemented by letters dated February 4 2 and April 29 3 , 2010. The amendments consisted of an approximate 1.6 percent MUR that increased the rated thermal power from 2546 megawatts thermal (MWt) to 2587 MWt. The License Condition T, Item 16, for Surry Units 1 and 2, respectively, were incorrect.

Enclosed are the corrected updated license pages for Amendment No. 269 to Renewed Facility Operating License No. DPR-32 and Amendment No. 268 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively.

1 VEPCO letter to NRC, Agency Document Access Management System (ADAMS) Accession No. MLl00320264 2 VEPCO letter to NRC, ADAMS Accession No. ML100480781 3 VEPCO letterto NRC, ADAMS Accession No. MLl01200269 D. Heacock -2 If you have any questions, please feel free to contact me at 301-415-1438.

Sincerely, Karen Cotton, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Enclosure:

As stated Docket Nos. 50-280 and 50-281 cc w/encl: Distribution via Listserv

-9(Continued)

16. For the applicable UFSAR Chapter 14 events, Surry 1 will re-analyze the transient consistent with VEPCO's NRC-approved reload design methodology in VEP-FRD-42, Rev. 2.1-A. If NRC review is deemed necessary pursuant to the requirements of 10 CFR 50.59, the accident analyses will be submitted to the NRC for review prior to operation at the uprate power level. These commitments apply to the following Surry 1 UFSAR Chapter 14 DNBR analyses that were analyzed at 2546 MWt consistent with the Statistical DNBR Evaluation Methodology in VEP-NE-2-A:

• Section 14.2.7 -Excessive Heat Removal due to Feedwater System Malfunctions (Full Power Feedwater Temperature Reduction case only);

• Section 14.2.8 -Excessive Load Increase Incident;

• Section 14.2.9 -Loss of Reactor Coolant Flow; and

• Section 14.2.10 -Loss of External Electrical Load Prior to operating above 2546 MWt (98.4% RP). This renewed license is effective as of the date of issuance and shall expire at midnight on May 25, 2032. FOR THE NUCLEAR REGULATORY COMMISSION Original signed by: Samuel J. Collins, Director Office of Nuclear Reactor Regulation

Attachment:

Appendix A, Technical Specifications Date of Issuance:

March 20, 2003 Renewed License No. DPR-32 Amendment No. 269

-9 1. (Continued)

16. For the applicable UFSAR Chapter 14 events, Surry 2 will re-analyze the transient consistent with VEPCO's NRC-approved reload design methodology in VEP-FRD-42, Rev. 2.1-A. Prior to operating above 2546 MWt (98.4% RP). If NRC review is deemed necessary pursuant to the requirements of 10 CFR 50.59, the accident analyses will be submitted to the NRC for review prior to operation at the uprate power level. These commitments apply to the following Surry 2 UFSAR Chapter 14 DNBR analyses that were analyzed at 2546 MWt consistent with the Statistical DNBR Evaluation Methodology in VEP-NE-2-A:

• Section 14.2.7 -Excessive Heat Removal due to Feedwater System Malfunctions (Full Power Feedwater Temperature Reduction case only);

• Section 14.2.8 -Excessive Load Increase Incident;

• Section 14.2.9 -Loss of Reactor Coolant Flow; and

• Section 14.2.10 -Loss of External Electrical Load This renewed license is effective as of the date of issuance and shall expire at midnight on January 29, 2033. FOR THE NUCLEAR REGULATORY COMMISSION Original signed by: Samuel J. Collins, Director Office of Nuclear Reactor Regulation

Attachment:

Appendix A, Technical Specifications Date of Issuance:

March 20, 2003 Renewed License l\lo. DPR-37 Amendment No. 268 D. Heacock -2 If you have any questions, please feel free to contact me at 301-415-1438.

Sincerely, IRA! Karen Cotton, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Enclosure:

As stated Docket Nos. 50-280 and 50-281 cc w/encl: Distribution via Listserv DISTRIBUTION:

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