LR-N10-0066, Supplement to License Amendment Request S09-04, Revision to Technical Specification 6.8.4.i, Steam Generator (SG) Program, for One-Time (Interim) Alternate Repair Criteria (H*)
| ML100680482 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/25/2010 |
| From: | Fricker C Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LAR S09-04, LR-N10-0066 | |
| Download: ML100680482 (2) | |
Text
PSEG P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear LLC FEB 24010 10 CFR 50.90 LR-N 10-0066 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Salem Generating Station - Unit 1 Facility Operating License No. DPR-70 NRC Docket No. 50-272
Subject:
Supplement to License Amendment Request S09-04, Revision to Technical Specification 6.8.4.i, "Steam Generator (SG) Program," for One-Time (Interim) Alternate Repair Criteria (H*)
References:
(1) Letter from PSEG to NRC, "License Amendment Request, Revision to Technical Specification 6.8.4.i, "Steam Generator (SG) Program," for One-Time (Interim) Alternate Repair Criteria (H*)," dated October 8, 2009 In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request for the facility operating license listed above. The request would modify the Salem Unit 1 Technical Specification (TS) 6.8.4.i, "Steam Generator (SG) Program," by adding a one-time alternate repair criteria that excludes portions of the tube below the top of the steam generator tubesheet from periodic steam generator tube inspections. In addition, the amendment request would revise TS 6.9.1.10, "Steam Generator Tube Inspection Report," to provide reporting requirements specific to the alternate repair criteria. The proposed change was supported by Westinghouse Electric Company LLC, WCAP-17071-P, "H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F)."
Subsequent to submittal of Reference 1, PSEG discovered a typographical error in one TS mark-up page. Specifically, on Salem Unit 1 TS page 6-24b, TS 6.9.1.10.h (Steam Generator Tube Inspection Report), the word "preceding" was misspelled as "proceeding." From the context of the report requirement the information requested necessarily refers to the cycle occurring before (i.e.,
"preceding") the required inspection report. The corrected wording for TS 6.9.1.10.h is provided below:
The primary to secondary leakage rate observed in each SG (if it is not practical to assign the leakage to an individual SG, the entire primary to secondary leakage should be conservatively assumed to be from one SG) during the cycle preceding the inspection which is the subject of the report, PSEG has reviewed the information supporting a finding of no significant hazards consideration that was provided to the NRC in Reference 1. The additional information provided in this letter does not affect the conclusion that the proposed license amendment does not involve a significant hazards consideration. No regulatory commitments are contained in this submittal.
Ao R
Document Control Desk 2
LR-NI 0-0066 If you have any questions or require additional information, please do not hesitate to contact Mr.
Jeff Keenan at (856) 339-5429.
1 declare under penalty of perjury that the foregoing is true and correct.
Executed on c*/z-5/O (Date)
Sincere aYr.
F V~t Site Vice President - Salem S. Collins, Regional Administrator - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector - Salem Unit I and Unit 2 P. Mulligan, Manager IV, NJBNE Commitment Coordinator - Salem PSEG Commitment Coordinator - Corporate