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MONTHYEARNLS2011085, Relief Request from Certain Inservice Testing Code Requirements2011-08-24024 August 2011 Relief Request from Certain Inservice Testing Code Requirements Project stage: Request ML1127304842011-09-30030 September 2011 Acceptance Review Email, Relief Request Nos. RV-07- Pressure Isolation Valve Leaking Testing and RV-01, Revision 1 - HPCI Solenoid Operated Drain Valve Testing - Fourth 10-Year IST Program Interval Project stage: Acceptance Review ML1201304542012-01-13013 January 2012 Draft Request for Additional Information, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval Project stage: Draft RAI ML1201304512012-01-13013 January 2012 Email, Draft Request for Additional Information, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval Project stage: Draft RAI ML1202701552012-02-13013 February 2012 Request for Additional Information, Relief Request No. RV-01, Revision 1, HPCI Solenoid Operated Drain Valve Testing, Fourth 10-Year Inservice Testing Program Interval Project stage: RAI NLS2012016, Response to Nuclear Regulatory Commission Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Valve Inservice Testing Program2012-03-12012 March 2012 Response to Nuclear Regulatory Commission Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Valve Inservice Testing Program Project stage: Request ML1213905112012-05-18018 May 2012 Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval Project stage: Draft RAI ML1213905092012-05-18018 May 2012 Email, Draft Request for Additional Information, Second Round, Relief Request Nos. RV-07 and RV-01, Revision 1, Fourth 10-Year Inservice Testing Program Interval Project stage: Draft RAI ML12157A5412012-06-11011 June 2012 Second Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Value Inservice Testing Program Project stage: RAI NLS2012057, Response to Nuclear Regulatory Commission Request for Additional Information Relief Request RV-01 Revision 12012-06-22022 June 2012 Response to Nuclear Regulatory Commission Request for Additional Information Relief Request RV-01 Revision 1 Project stage: Request NLS2012082, Response to Nuclear Regulatory Commission Third Request for Additional Information Relief Requests RV-07 Revision 0 and RV-01 Revision 12012-08-14014 August 2012 Response to Nuclear Regulatory Commission Third Request for Additional Information Relief Requests RV-07 Revision 0 and RV-01 Revision 1 Project stage: Request ML12233A1762012-08-28028 August 2012 Relief Request Nos. RV-07, Revision 0, and RV-01, Revision for Fourth 10-Day Inservice Inspection Interval Regarding Weld Overlay Repair Project stage: Other 2012-03-12
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Category:Letter type:NLS
MONTHYEARNLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 NLS2024007, Emergency Plan Implementing Procedure 5.7.1, Revision 732024-01-16016 January 2024 Emergency Plan Implementing Procedure 5.7.1, Revision 73 NLS2024003, 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector2024-01-15015 January 2024 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector NLS2024004, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20232024-01-10010 January 2024 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023 NLS2023053, ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-30030 November 2023 ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023050, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023051, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-10-10010 October 2023 Response to Nuclear Regulatory Commission Request for Additional 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N Nebraska Public Power District Always there when you need us 50.55a NLS2012082 August 14, 2012 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Response to Nuclear Regulatory Commission Third Request for Additional Information Re: Relief Requests RV-07 Revision 0 and RV-01 Revision 1 (TAC No. ME7021)
Cooper Nuclear Station, Docket No. 50-298, DPR-46
References:
Letter from Brian J. O'Grady, Nebraska Public Power District, to the U.S. Nuclear Regulatory Commission, dated August 24, 2011, "10 CFR 50.55a Request Numbers RV-07, Revision 0, and RV-01, Revision 1"
Dear Sir or Madam:
The purpose of this letter is for Nebraska Public Power District (NPPD) to submit a response to a request for additional information (RAI) from the Nuclear Regulatory Commission (NRC) discussed in a telephone conversation on August 2, 2012 between NRC's Carl F. Lyon, Anthony McMurtray, and Michael Orenak and NPPD's Edward McCutchen and Thomas Robinson. The RAI requested information in support of NRC's review of Cooper Nuclear Station (CNS) relief requests RV-07 for Pressure Isolation Valve Leakage Tests, and RV-0 1 for High Pressure Coolant Injection Solenoid Valves. These relief requests are applicable to the Fourth 10-Year Interval Inservice Testing Program (Reference).
Responses to the specific RAI questions are provided in the Attachment to this letter. No regulatory commitments are made in this submittal. If you have any questions concerning this matter, please contact David Van Der Kamp, Licensing Manager, at (402) 825-2904.
mrely, Brian J. O'Grady Vice President - Nuclear and Chief Nuclear Officer
/em COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www. nppd .com
NLS2012082 Page 2 of 2
Attachment:
Response to Nuclear Regulatory Commission Third Request for Additional Information Re: Relief Requests RV-07 Revision 0 and RV-01 Revision 1 (TAC No. ME7021) cc: Regional Administrator w/ attachment USNRC - Region IV Cooper Project Manager w/ attachment USNRC - NRR Project Directorate IV-I Senior Resident Inspector w/ attachment USNRC - CNS NPG Distribution w/ attachment CNS Records w/ attachment
NLS2012082 Attachment Page 1 of 2 Attachment Response to Nuclear Regulatory Commission Third Request for Additional Information Re: Relief Requests RV-07 Revision 0 and RV-01 Revision 1 (TAC No. ME7021)
Cooper Nuclear Station (CNS), Docket No. 50-298, DPR-46 NRC Question #1 For RV-07, at whatfrequency is CNS performing the functional testing?
Response
For valves in NLS2011085, Attachment I Section 1, the Functional Test and Position Indication Test (PIT) frequencies are as follows.
Valve Functional Test PIT RHR-MOV-MO25A Quarterly 2 yrs RHR-MOV-MO25B Quarterly 2 yrs RHR-MOV-MO274A Normally De-energized Closed Refueling Outage RHR-MOV-MO274B Normally De-energized Closed Refueling Outage RHR-CV-26CV Refueling Outage Refueling Outage RHR-CV-27CV Refueling Outage Refueling Outage RHR-MOV-MO 17 Cold S/D Refueling Outage RHR-MOV-MO18 Cold S/D Refueling Outage CS-MOV-MO12A Cold S/D Refueling Outage CS-MOV-MO 12B Cold S/D Refueling Outage CS-CV- 18CV Refueling Outage Refueling Outage CS-CV- 19CV Refueling Outage Refueling Outage NRC Question #2 For R V-O1, are any alternativeinspection intervalsgoing to be submitted, since there is very little datafor HPCI-SOV-SSV64? And if deficiencies arefound in either valve, would CNS reduce both valves' intervals back to 18 months?
NLS2012082 Attachment Page 2 of 2
Response
For HPCI-SOV-SSV64 or HPCI-SOV-SSV87, following a repair for an unsatisfactory acceptance criteria step or valve replacement, CNS agreed to collect at least 2 sets of acceptable data before extending the frequency of a specific valve to a frequency beyond 18 months, but not to exceed 36 months. The span of acceptable tests shall support the new test frequency. For future testing, if an unsatisfactory acceptance criteria step is found in either valve, CNS will reduce the frequency back to 18 months for both valves for one cycle. If it can be shown that the deficiency is not from a cause that could be common to both valves, the valve without the unsatisfactory acceptance criteria can return to a 36 month frequency after the one 18 month cycle.