ML13099A106

Correction Letter Regarding Amendment Nos. 278 and 278 to Adopt Technical Specification Task Force (TSTF)-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection

ML13099A106
Person / Time
Site:	Surry
Issue date:	04/23/2013
From:	Cotton K Plant Licensing Branch II
To:	Heacock D Virginia Electric & Power Co (VEPCO)
Cotton K NRR/DORL/LPL2-1
References
Download: ML13099A106 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 23, 2013 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

SUBJECT:

SURRY POWER STATION, UNIT NOS. 1 AND 2, CORRECTION LETTER REGARDING AMENDMENT NOS. 278 AND 278 TO ADOPT TECHNICAL SPECIFICATION TASK FORCE (TSTF)-510, REVISION 2, REVISION TO STEAM GENERATOR PROGRAM INSPECTION FREQUENCIES AND TUBE SAMPLE SELECTION

Dear Mr. Heacock:

On January 28, 2013, the U.S. Nuclear Regulatory Commission issued Amendment Nos. 278 and 278 to Renewed Facility Operating License Nos. DPR-32 and DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively. The amendments revised the Technical Specifications (TS) in accordance with TS Task Force Traveler (TSTF) 510, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Revision 2."

In discussion with our staff on February 19, 2013, a representative of your staff identified a mistake in your license amendment request (LAR) submitted by letter dated July 31, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12222A340), as supplemented by letter dated November 6,2012 (ADAMS Accession No. ML12319A006). The mistake was the inadvertent repetition of the text "outage in an inspection period and the subsequent" in TS 6.4.Q.4.b on the proposed typed TS page TS 6.4-13 included in the LAR. The marked-up proposed TS page was correct. The repeated text was included in the revised TS page issued in Amendment Nos. 278 and 278. While the inadvertently repeated text has no operational impact and was not addressed in any part of the NRC staff safety evaluation, the NRC staff nevertheless considers this to be an error to be corrected. The NRC staff further considers the use of a letter for this type of change is allowed by the NRC's "Proposed Guidance for Correction of Technical Specification Typographical Errors," SECY-96-238, dated November 19, 1996 (the guidance in SECY-96-238 was approved in a Staff Requirements Memorandum dated December 17, 1996.)

The guidance in SECY 238 allows for use of an administrative letter to correct an error provided that: 1) the error was introduced inadvertently in a particular license amendment, and 2) the erroneous change was not addressed in the notice to the public nor reviewed by the NRC staff.

Dominion staff has identified orally and the NRC staff also independently determines that the error inadvertently occurred in the LAR and in License Amendments 278 and 278. This satisfies the first requirement. The repeated text was not included in the TSTF-510 documentation, was not identified in the notice on the amendment published in the Federal Register (77 FR 63351), and was not the subject of any specific part of the staff's safety evaluation that was issued with the license amendments. This satisfies the second requirement.

D. Heacock

- 2 The NRC staff has considered the licensee's request to correct the error on TS page TS 6.4-13 in accordance with the guidance contained in SECY 238. Based on our review, as set forth above, we have determined that the use of a letter to correct the typographical error is acceptable.

Enclosed is the corrected TS page TS 6.4-13.

Sincerely,

~ect Manager Plant licensing Branch 11-1 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281 cc w/encls: Distribution via listserve

TS 6.4-13

b.

After the first refueling outage following SO installation, inspect each SO at least every 48 effective full power months or at least every other refueling outage (whichever results in more frequent inspections). In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SOs divided by the number of SO inspection outages scheduled in each inspection period as defined in b.I, b.2, and b.3 below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated. The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SO is scheduled to be inspected in the inspection period after the determination that a new form of degradation could potentially be occurring at this location divided by the total number of times the SO is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SO inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SO inspection outage.

1. After the first refueling outage following SO installation, inspect 100% of the tubes during the next 120 effective full power months. This constitutes the first inspection period;

2. During the next 96 effective full power months, inspect 100% of the tubes.

This constitutes the second inspection period; and

3. During the remaining life of the SOs, inspect 100% of the tubes every 72 effective full power months. This constitutes the third and subsequent inspection periods.

Amendment Nos. 278 and 278

ML13099A106 RidsNrrDirsltsb (TKobetz)

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