ML11362A394
| ML11362A394 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/19/2011 |
| From: | James Shea Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML11362A394 (2) | |
Text
Tennessee Valley Authority, I 101 Market Street, Chattanooga, Tennessee 37402 December 19, 2011 10 CFR 50.9(b)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Revision to Follow-up Letter to 10 CFR 50.9, "Completeness and accuracy of information," Notification
References:
- 1.
Letter from TVA to NRC, "Follow-up Letter to 10 CFR 50.9, 'Completeness and accuracy of information,' Notification," dated October 20, 2011
- 2.
Letter from TVA to NRC, "Browns Ferry Nuclear Plant (BFN) - Units 2 and 3 -
Generic Letter (GL) 89-10, Safety-Related Motor-Operated Valve (MOV)
Testing and Surveillance, NRC Inspector Followup Item (IFI) 50-260, 296/95-19-01, Response to Request for Reevaluation Regarding Reduced Scope of MOVs," dated January 6, 1997
- 3.
Letter from WVA to NRC, "Browns Ferry Nuclear Plant (BFN) Unit 1 -
Generic Letter 89-10 and Supplements 1 to 7, Safety-Related Motor-Operated Valve (MOV) Testing and Surveillance," dated May 5, 2004 On September 21, 2011, the Tennessee Valley Authority (TVA) determined that information previously provided to the NRC in response to an inspection was inaccurate. As required by 10 CFR 50.9(b), a notification was made within two working days to the NRC Region II office via a telephone call between R. M. Krich, WVA Vice President, Nuclear Licensing and Victor McCree, NRC Region II Administrator. As requested during that telephone call, WVA provided a follow-up letter (Reference 1) to that notification on October 20, 2011.
pbh-
U.S. Nuclear Regulatory Commission Page 2 December 19, 2011 By letter dated January 6, 1997 (Reference 2), TVA responded to NRC inspector follow-up item 50-260, 296/95-19-01 regarding the reduced scope of motor-operated valves in the NRC Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance," program for Browns Ferry Nuclear Plant (BFN), Units 2 and 3. This letter stated in part that "... Closure of valves FCV-74-52 and FCV-74-66 is not required by plant procedures to operate the RHR system in the suppression pool cooling mode... "
As a result of the current root cause analysis that is being conducted to address the issues associated with the failure of valve FCV-74-66 in BFN, Unit 1, TVA discovered that this statement was inaccurate. Specifically, the revision of the Emergency Operating Instruction Program Manual, Appendix 17A, that was in place in January 1997 included a step to verify that the FCV-74-52 or FCV-74-66 valve was closed as part of performing the steps to place the Residual Heat Removal (RHR) system in the suppression pool cooling mode.
Accordingly, TVA determined that this condition was reportable to the NRC in accordance with 10 CFR 50.9(b) on September 21, 2011, and the notification was made to the NRC Region II office within two working days, on September 22, 2011. The corrective actions for this condition are being implemented as part of the corrective actions being taken as identified in the root cause analysis.
The purpose of this revision to the Reference 1 letter is to include BFN, Unit 1. The Reference 2 letter, which included the inaccurate information, was applicable to BFN, Units 2 and 3. However, the Reference 3 letter, which provided an updated response to Generic Letter 89-10 and Supplements 1 through 7 for BFN, Unit 1, stated "TVA's review and documentation of the design basis for the operation of each Unit 1 MOV within the scope of the Generic Letter 89-10 program, the valves included in the program, the methods for determining and adjusting switch settings, testing, surveillance, and maintenance are the same as with the Units 2 and 3 program." The Reference 3 letter also referenced the January 6, 1997, letter (Reference 2) from TVA to NRC.
As such, it has been determined that the inaccurate information included in the Reference 2 letter also applied to BFN, Unit 1. Accordingly, on December 19, 2011, a subsequent notification was made to the NRC Region II office via a telephone call between J. W. Shea, WVA Manager, Nuclear Licensing and Victor McCree, NRC Region II Administrator. As stated during that telephone call, TVA is providing a revision to the Reference 1 follow-up letter.
Should you have any questions, please contact Thomas Hess at (423) 751-3487.
Respec t, JcShea cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant