ML103570192
| ML103570192 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/23/2010 |
| From: | Cotton K Plant Licensing Branch II |
| To: | Heacock D Virginia Electric & Power Co (VEPCO) |
| Cotton K, NRR/DLPM, 301-415-1438 | |
| References | |
| TAC ME3343, TAC ME3344 | |
| Download: ML103570192 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 23, 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 SUB~IECT:
SURRY POWER STATION, UNIT NOS. 1 AND 2, CORRECTIONS TO AMENDMENTS REGARDING THE USE OF OPTIMIZED ZIRLO' FUEL ROD CLADDING (TAC NOS. ME3343 AND ME3344)
Dear Mr. Heacock:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 271 to Renewed Facility Operating License No. DPR-32 and Amendment No. 270 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively. The amendments change the Technical Specifications (TSs) in response to your application dated February 10, 2010 (Agencywide Documents and Management System (ADAMS) Accession No. ML100470738).
These amendments revise TS 5.2.1, "Fuel Assemblies," to add Optimized ZIRLO as an acceptable fuel rod cladding material. In addition, the amendments propose adding the Westinghouse topical report for Optimized ZIRLO to the analytical methods used to determine the core operating limits listed in TS 6.2.C.
The initial license pages referred to an incorrect maximum power level. Enclosed are the corrected updated license pages for Amendment No. 271 to Renewed Facility Operating License No. DPR-32 and Amendment No. 270 to Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively.
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 Docket Nos. 50-280 and 50-281
Enclosures:
License Page 3 - Surry Unit 1 License Page 3 - Surry Unit 2 cc w/encls: Distribution via Listserv
-3
- 3. This renewed license shall be deemed to contaIn an~ Is subject to the condItions speclfted in the following Commission regulations: 10 CFR Part 20, Section 30:34 of 10 CFR Part 30. SectIon 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50. and SectIon 70.32,of 10 CFR Part 70: and is subject to all applicable provisions of the Act and tne rLiles, regulations, and olders Of 1he Commission row or hereafter in effect and Is subject to the additional conditions specified below:
A. MaXimum power Level The licensee Is authorized to operate the facility at steady state reactor core power levels not In excess of2r::J37 megawatts (thermal).
B. Technical SDectncations The Technical S~cations conumed In Appendix A. as revised through Amendment No. 271 are hereby Incorporated In the renewed license. The licensee shall oPerate the facility In accordance with 1he r,chnical Specifications.
C. Reports T.he licensee shalf make certain reports In accordance with the requirements of the TechnIcal Specifications.
O. Becords The licensee shall keep facility operating records In 8coordance with the requirements of the Technical Specifications.
E.. Deleted by Amendment 65 F. Deleted by Amendment 71 G. Deleted by Amendment 227 H. Deleted by Amendment 221
- l. FIre prpt"ctlon The licensee shall Implement and maintain in effect the prov,lslons of the approved fire protection. program as descrfbed In the Updated Anal Safety Analysis Report' and as approved In the SER dated September 19,1979, (and Supplements dated May 29,1980, October 9.1980, December 18,1980, February 13, 1981, December 4, 1981, April 21, 1982, November 18. 1982.
January 17,1984. February 25. 19BB, and Renewed License No. DPR*32 SURRY UNIT' Amendment No. 271
-3 E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
- 3. This renewed license shall be deemed to contain and Is sUbject to the conditions specified in the fohowing Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and. 50:59 of 10 CFR Part 50. and Section 70.32 of 10 CFR Part 70; and is sUbject \\0 all applicable provisions of the Act and the rules, 'regulatlons; and orders of the Commission now or hereaner In effect; and is subject to the additional conditions specified below:
A. Maximum Power Level The licensee Is authortzeq to operate the facility at steady state reactor core power levels not in excess of 2587 megawatts (thermal).
B. Technical SpecifICations The Technical SpecificatiOns contained *in Appendix A, as revised through I
Amendment No. 270 are hereby incorporated In thIs renewed license. The I licensee shall operate the !aci\\\\ty in accordance wtth the Technlca~*Specificatlons.*
C. Reports The licensee s~all make certain reports in accordance with the requirements of the Technical Specifications.
D. Records ThQ licensee shall keep facility operating records In accordance with the requirements of the Technical Specifications.
E. Deleted by Amendment 54 F. Deleted by Amendment 59 and Amendment.65 G.. Deleted by Amendment 227 H. Deleted by Amendment 227 SURRY* UNIT 2 Renewed LIcense No.. OPR-37 Amendment No. 270 I
103570192 OFFICE DORULPL2-1/PM DORULPL2-1/LA DORULPL2-1/BC NAME KCotlon MOBrien GKulesa (RSola for)
(PBoyle for)
DATE 12/23/10 12/23/10 12/23/10