ML100610513

Closeout of Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems

ML100610513
Person / Time
Site:	Cooper
Issue date:	03/17/2010
From:	Lyon C Plant Licensing Branch IV
To:	Minahan S Nebraska Public Power District (NPPD)
Thadani, M C, NRR/DORL/LPL4, 415-1476
References
GL-08-001, TAC MD7815, TAC ME0848
Download: ML100610513 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 17, 2010 Mr. Stewart B. Minahan Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321

SUBJECT:

COOPER NUCLEAR STATION - CLOSEOUT OF GENERIC LETTER 2008-01 "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NO. ME0848)

Dear Mr. Minahan:

On January 11,2008, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2008-01, "lVIanaging Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072910759). The stated purpose of GL 2008-01 was (a) to request addressees to submit information to demonstrate that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance; and (b) to collect the requested information to determine if additional regulatory action is required.

GL 2008-01 requested that licensees provide the following information within 9 months of the date of the GL:

(a) A description of the results of evaluations that were performed pursuant to requested actions specified in the GL. This description should provide sufficient information to demonstrate that you are or will be in compliance with the quality assurance criteria in Sections III, V, XI, XVI, and XVII of Appendix B to Part 50 of Title 10 of the Code of Federal Regulations and the licensing basis and operating license as those requirements apply to the subject systems; (b) A description of all corrective actions, including plant, programmatic, procedure, and licensing basis modifications that you determined were necessary to assure compliance with these regulations; and (c) A statement regarding which corrective actions were completed, the schedule for completing the remaining corrective actions, and the basis for that schedule.

By letters dated October 10,2008, May 7,2009, December 17, 2009, and February 2,2010, (ADAMS Accession Nos. ML082890161, ML091340024, ML093580022, and ML100470199, respectively), Nebraska Public Power District, the licensee for Cooper Nuclear Station, provided information in response to the GL 2008-01. The NRC staff has reviewed the submitted information and has concluded that the licensee has acceptably demonstrated that, "the subject

S. Minahan -2 systems are in compliance with the current licensing and design bases and applicable regulatory requirements; and that suitable design, operation, and testing measures are in place for maintaining this compliance" as stated in GL 2008-01. Consequently, the licensee's GL 2008-01 response is considered closed and no further information or action is requested of the licensee. Notwithstanding the above, the NRC's Region IV staff may decide to perform and may contact the licensee to schedule an inspection using Temporary Instruction (TI) 2515/177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (NRC Generic Letter 2008-01)" (ADAMS Accession No. ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to selectively verify that the licensee has implemented or is in the process of acceptably implementing the commitments, modifications, and programmatically controlled actions described in the licensee's response to GL 2008-01 and the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.

If you have any questions, please contact me at (301) 415-2296 or Mohan Thadani at (301) 415-1476.

Sincerely,

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Carl F. Lyon, Project Manager .

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0(/ VI" Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298 cc: Distribution via Listserv

ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to selectively verify that the licensee has implemented or is in the process of acceptably implementing the commitments, modifications, and programmatically controlled actions described in the licensee's response to GL 2008-01 and the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.

If you have any questions, please contact me at (301) 415-2296 or Mohan Thadani at (301) 415-1476.

Sincerely, Ira/Mohan C. Thadani/for Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298 cc: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrPMCooper Resource LPLIV r/f RidsNrrLAJBurkhardt Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDorlLpl4 Resource RidsRgn4MailCenter Resource RidsNrrDssSrxb Resource ADAMS Accession No. ML100610513 *memo dated OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/DSS/SRXB NRR/LPL4/BC NRR/LPL4/PM NAME FLyon (MThadani for) JBurkhardt GCranston MMarkley FLyon (MThadani for)

DATE 3/11/10 3/10/10 2/22/10 3/17/10 3/17/10