ML12157A541

Second Request for Additional Information Request for Relief for the Fourth 10-Year Pump and Value Inservice Testing Program

ML12157A541
Person / Time
Site:	Cooper
Issue date:	06/11/2012
From:	Lynnea Wilkins Plant Licensing Branch IV
To:	O'Grady B Nebraska Public Power District (NPPD)
References
TAC ME7021
Download: ML12157A541 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 11,2012 Mr. Brian J. O'Grady Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321

SUBJECT:

COOPER NUCLEAR STATION - SECOND REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST FOR RELIEF FOR THE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. ME7021)

Dear Mr. O'Grady:

By letter dated August 24, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11242A129), Nebraska Public Power District (NPPD, the licensee) submitted requests for relief (RV-07, Revision 0, and RV-01, Revision 1) from certain inservice testing (1ST) American Society of Mechanical Engineers Boiler and Pressure Vessel Code (Code) requirements for Cooper Nuclear Station pursuant to Section 50.55a of Title 10 of the Code of Federal Regulations. These requests are applicable to the fourth 10-year 1ST interval, which began March 1, 2006, and request relief from certain 1ST Code requirements regarding the required 2-year test interval for pressure isolation valve leakage rate testing and the frequency for disassembly and examination of the affected components. By letter dated February 13, 2012 (ADAMS Accession No. ML120270155), the U.S. Nuclear Regulatory Commission (NRC) transmitted a request for additional information (RAI). By letter dated March 12, 2012 (ADAMS Accession No. ML12079A032), you responded to the NRC's request.

The NRC staff has reviewed your submittals and determined that additional information is needed for the staff to complete its evaluation. The RAI was transmitted via e-mail to Mr. Edward McCutchen of your staff on May 18, 2012. Mr. McCutchen indicated via telephone on June 5, 2011, that the response would be provided by June 22, 2012.

B. O'Grady -2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Lynnea. wilkins@nrc.gov.

Sincerely, L ~ nnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv

SECOND REQUEST FOR ADDITIONAL INFORMATION NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 By letter dated August 24,2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11242A129), Nebraska Public Power District (NPPD, the licensee) submitted requests for relief (RV-07, Revision 0, and RV-01, Revision 1) from certain inservice testing (1ST) requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (Code), for Cooper Nuclear Station, pursuant to Section 50.55a of Title 10 of the Code of Federal Regulations. These requests are applicable to the fourth 10-year 1ST interval, which began March 1, 2006, and request relief from certain 1ST Code requirements regarding the required 2-year test interval for pressure isolation valve leakage rate testing and the frequency for disassembly and examination of the affected components. By letter dated February 13, 2012 (ADAMS Accession No. ML120270155), the U.S. Nuclear Regulatory Commission (NRC) transmitted a request for additional information (RAI). By letter dated March 12,2012 (ADAMS Accession No. ML12079A032), the licensee responded to the NRC's request.

The NRC staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review.

1. Please describe any significant differences in the operational conditions and the relative physical locations to each other for HPCI-SOV-SSV64 and HPCI-SOV-SSV87.

2. Please provide the reason for the replacement of HPCI-SOV-SSV87 in June 2005.

3. The licensee's letter dated August 24, 2011, states, in part, that, "For instance, solenoid valve, HPCI-SOV-SSV87, was replaced in June 2005, and has had an acceptable disassembly and examination completed in November 2006, March 2008, August 2009, and March 2011." Please provide the acceptance criteria and results for these four examinations of HPCI-SOV-SSV87 and describe any future acceptance criteria changes for HPCI-SOV-SSV64 and HPCI-SOV-SSV87.

4. If the disassembly and examination interval is extended to 36 months and issues/problems are discovered in HPCI-SOV-SSV64 or HPCI-SOV-SSV87, please state any planned disassembly and examination interval change. If the disassembly and examination interval is decreased, please provide the criteria used to return to a 36-month interval.

Enclosure

B. O'Grady - 2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Lynnea. wilkins@nrc.gov.

Sincerely, IRA!

Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298

Enclosure:

Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:

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