ML13227A337

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Dresden Nuclear Power Station, Units 2 & 3 - Clarification Re Inservice Testing of High Pressure Coolant Injection Valves 2(3)-2301-32-SO
ML13227A337
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 08/14/2013
From: Simpson P R
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-13-208
Download: ML13227A337 (2)


Text

biD/NUU u;t,ee RS-13-208 August 14, 2013 10 CFR 50.55a ATTN:Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249

Subject:

Clarification Regarding the Inservice Testing of Dresden Nuclear Power Station High Pressure Coolant Injection (HPCI) Valves 2(3)-2301-32-SO (TAC No.ME9872)

References:

1.Letter from P. R. Simpson (Exelon Generation Company, LLC (EGC)) to U. S. NRC, "Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval," dated October 30, 2012 2.Letter from P. R. Simpson (EGC) to U. S. NRC, "Response to Request for Additional Information Related to Request for NRC Approval of Relief Requests for Fifth Inservice Testing Interval (TAC Nos. ME9871 and ME9872)," dated April 1, 2013 In Reference 1, EGC requested approval of relief requests associated with the upcoming fifth inservice testing (IST) interval at Dresden Nuclear Power Station (DNPS), Units 2 and 3.

While reviewing Reference 1, the NRC found that additional information was required to support its review. The requested information was provided in Reference 2.

During a telephone conversation between NRC and EGC personnel on July 31, 2013, NRC personnel requested that EGC provide an additional clarification related to the testing of DNPS, Units 2 and 3 HPCI valves 2(3)-2301-32-SO.

1 RS-13-208 10 CFR 50.55a August 14, 2013 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249

Subject:

Clarification Regarding the Inservice Testing of Dresden Nuclear Power Station High Pressure Coolant Injection (HPCI) Valves 2(3)-2301-32-S0 (TAC No. ME9872)

References:

1. Letter from P. R. Simpson (Exelon Generation
Company, LLC (EGC>> to U. S. NRC, "Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval,"

dated October 30,2012 2. Letter from P. R. Simpson (EGC) to U. S. NRC, "Response to Request for Additional I nformation Related to Request for NRC Approval of Relief Requests for Fifth Inservice Testing Interval (TAC Nos. ME9871 and ME9872),"

dated April 1, 2013 In Reference 1, EGC requested approval of relief requests associated with the upcoming fifth inservice testing (1ST) interval at Dresden Nuclear Power Station (DNPS), Units 2 and 3. While reviewing Reference 1, the NRC found that additional information was required to support its review. The requested information was provided in Reference

2. During a telephone conversation between NRC and EGC personnel on July 31,2013, NRC personnel requested that EGC provide an additional clarification related to the testing of DNPS, Units 2 and 3 HPCI valves 2(3)-2301-32-S0.

August 14, 2013 U. S. Nuclear Regulatory Commission Page 2Specifically, in EGC's response to NRC Request RAI-RV-23H-3 provided in Reference 2, EGC stated that 2(3)-2301-32-SO valve internals were not repaired or replaced during the fourth ten-year inservice testing interval. The intent of this response was to convey the fact that the entire valve assembly is replaced at a six-year frequency in lieu of valve disassembly and inspection and or repair of valve internals. Moreover, the valve assemblies were last replaced on March 11, 2013, and on December 8, 2007, for DNPS Units 2 and 3, respectively.

Respectfully, Exelon Generation Company, LLC August 14,2013 U. S. Nuclear Regulatory Commission Page 2 Specifically, in EGC's response to NRC Request RAI-RV-23H-3 provided in Reference 2, EGC stated that 2(3)-2301-32-S0 valve internals were not repaired or replaced during the fourth year inservice testing interval.

The intent of this response was to convey the fact that the entire valve assembly is replaced at a six-year frequency in lieu of valve disassembly and inspection and or repair of valve internals.

Moreover, the valve assemblies were last replaced on March 11, 2013, and on December 8, 2007, for DNPS Units 2 and 3, respectively.

Respectfully, Patrick R. Simpson Manager -Licensing Exelon Generation

Company, LLC