View source for L-89-010, Revision to the Generic Letter 89-10, Safety-related Motor-operated Valve, Scope

{{Adams
| number = ML13037A090
| issue date = 01/31/2013
| title = Revision to the Generic Letter 89-10, Safety-related Motor-operated Valve, Scope
| author name = Shea J
| author affiliation = Tennessee Valley Authority
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000259, 05000260, 05000296
| license number = DPR-033, DPR-052, DPR-068
| contact person = 
| case reference number = GL-89-010
| document type = Letter type:L
| page count = 4
}}

=Text=
{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 January 31, 2013 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 the Generic Letter 89-10, Safety-related Motor-operated Valve, Scope

==Reference:==
: 1. 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
: 2. Letter from TVA 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 In a letter dated January 6, 1997 (Reference 1), the Tennessee Valley Authority (TVA) submitted a letter that provided a reevaluation of the safety functions of certain motor-operated valves (MOVs) that were removed from or not included in the Browns Ferry Nuclear Plant (BFN) Generic Letter (GL) 89-10 program for BFN, Units 2 and 3. Based on the reevaluation performed by TVA, certain MOVs were added to the GL 89-10 program.
However, other MOVs that were normally in their safety position were not added to the GL 89-10 program for BFN, Units 2 and 3. For these MOVs, a commitment was made to revise plant procedures to require that the affected system, or train for the MOVs that were not added to the GL 89-10 program be declared inoperable when the MOVs were taken out of their normal safety position for testing.
TVA submitted a letter dated May 5, 2004 (Reference 2) that provided an updated response to GL 89-10 for BFN, Unit 1. Based on this updated response to GL 89-10 program, BFN, Unit 1, included the same scope of the GL 89-10 program as the BFN, Units 2 and 3, GL 89-10 program.
Printedon recycledpaper

U.S. Nuclear Regulatory Commission Page 2 January 31, 2013 As part of extent of condition reviews associated with the failure of valve 1-FCV-74-66, discovered on October 23, 2010, the scope of the GL 89-10 program for BFN has been reevaluated. The purpose of this letter is to revise the scope of the GL 89-10 program for BFN to include the additional valves identified during this reevaluation. The Enclosure provides a list of MOVs that have been added to the GL 89-10 program for BFN.
The Enclosure provides a summary of commitments contained in this letter and a projected schedule for their completion. Should you have any questions concerning this submittal, please contact J. E. Emens, Jr., Nuclear Site Licensing Manager, at (256) 729-2636.
Respecffu y, J.   .hea V icresident, Nuclear Licensing

==Enclosure:==

List of Valves Added to Generic Letter 89-10 Program cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

ENCLOSURE Browns Ferry Nuclear Plant Units 1, 2, and 3 List of Valves Added to Generic Letter 89-10 Program Commitment Summary The Tennessee Valley Authority has added the following motor-operated valves (MOVs) to the Generic Letter (GL) 89-10 program. These MOVs will be in full compliance with GL 89-10 program requirements by the end of the Browns Ferry Nuclear Plant, Unit 2, Spring 2013 refueling outage.
UNID                                      Description 1-FCV-71-17      Unit 1 Reactor Core Isolation Cooling Torus Supply Valve 1-FCV-71-18      Unit 1 Reactor Core Isolation Cooling Torus Supply Valve 1-FCV-71-19      Unit 1 Reactor Core Isolation Cooling Suction Valve from Condensate Storage Tank 1-FCV-74-01      Unit 1 Residual Heat Removal Shutdown Cooling Valves (Torus) 1-FCV-74-12      Unit 1 Residual Heat Removal Shutdown Cooling Valves (Torus) 1-FCV-74-24      Unit 1 Residual Heat Removal Shutdown Cooling Valves (Torus) 1-FCV-74-35      Unit 1 Residual Heat Removal Shutdown Cooling Valves (Torus) 1-FCV-74-02      Unit 1 Residual Heat Removal Shutdown Cooling Valves (Reactor) 1-FCV-74-13      Unit 1 Residual Heat Removal Shutdown Cooling Valves (Reactor) 1-FCV-74-25      Unit 1 Residual Heat Removal Shutdown Cooling Valves (Reactor) 1-FCV-74-36      Unit 1 Residual Heat Removal Shutdown Cooling Valves (Reactor) 1-FCV-74-52      Unit 1 Residual Heat Removal Loop I Low Pressure Coolant Injection Valve 1-FCV-74-66      Unit 1 Residual Heat Removal Loop II Low Pressure Coolant Injection Valve 2-FCV-71-17      Unit 2 Reactor Core Isolation Cooling Torus Supply Valve 2-FCV-71-18      Unit 2 Reactor Core Isolation Cooling Torus Supply Valve 2-FCV-71-19      Unit 2 Reactor Core Isolation Cooling Suction Valve from Condensate Storage Tank 2-FCV-74-01      Unit 2 Residual Heat Removal Shutdown Cooling Valves (Torus) 2-FCV-74-12      Unit 2 Residual Heat Removal Shutdown Cooling Valves (Torus) 2-FCV-74-24      Unit 2 Residual Heat Removal Shutdown Cooling Valves (Torus) 2-FCV-74-35      Unit 2 Residual Heat Removal Shutdown Cooling Valves (Torus) 2-FCV-74-02      Unit 2 Residual Heat Removal Shutdown Cooling Valves (Reactor) 2-FCV-74-13      Unit 2 Residual Heat Removal Shutdown Cooling Valves (Reactor) 2-FCV-74-25      Unit 2 Residual Heat Removal Shutdown Cooling Valves (Reactor) 2-FCV-74-36      Unit 2 Residual Heat Removal Shutdown Cooling Valves (Reactor) 2-FCV-74-52      Unit 2 Residual Heat Removal Loop I Low Pressure Coolant Injection Valve 2-FCV-74-66      Unit 2 Residual Heat Removal Loop II Low Pressure Coolant Injection Valve E-1

UNID                                  Description 3-FCV-71-17 Unit 3 Reactor Core Isolation Cooling Torus Supply Valve 3-FCV-71-18 Unit 3 Reactor Core Isolation Cooling Torus Supply Valve 3-FCV-71-19 Unit 3 Reactor Core Isolation Cooling Suction Valve from Condensate Storage Tank 3-FCV-74-01 Unit 3 Residual Heat Removal Shutdown Cooling Valves (Torus) 3-FCV-74-12 Unit 3 Residual Heat Removal Shutdown Cooling Valves (Torus) 3-FCV-74-24 Unit 3 Residual Heat Removal Shutdown Cooling Valves (Torus) 3-FCV-74-35 Unit 3 Residual Heat Removal Shutdown Cooling Valves (Torus) 3-FCV-74-02 Unit 3 Residual Heat Removal Shutdown Cooling Valves (Reactor) 3-FCV-74-13 Unit 3 Residual Heat Removal Shutdown Cooling Valves (Reactor) 3-FCV-74-25 Unit 3 Residual Heat Removal Shutdown Cooling Valves (Reactor) 3-FCV-74-36 Unit 3 Residual Heat Removal Shutdown Cooling Valves (Reactor) 3-FCV-74-52 Unit 3 Residual Heat Removal Loop I Low Pressure Coolant Injection Valve 3-FCV-74-66 Unit 3 Residual Heat Removal Loop II Low Pressure Coolant Injection Valve E-2}}