NLS2012082, Response to Nuclear Regulatory Commission Third Request for Additional Information Relief Requests RV-07 Revision 0 and RV-01 Revision 1

Response to Nuclear Regulatory Commission Third Request for Additional Information Relief Requests RV-07 Revision 0 and RV-01 Revision 1

ML12233A160
Person / Time
Site:	Cooper
Issue date:	08/14/2012
From:	O'Grady B J Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2012082, TAC ME7021
Download: ML12233A160 (4)

Text

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 what frequency 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 alternative inspection intervals going to be submitted, since there is very little data for HPCI-SOV-SSV64?

And if deficiencies are found 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.