ML092380101

Request for Additional Information Relief Request No. RV-06

ML092380101
Person / Time
Site:	Cooper
Issue date:	08/26/2009
From:	Lyon C Plant Licensing Branch IV
To:	Minahan S Nebraska Public Power District (NPPD)
Lyon, C F, NRR/DLPM, 415-2296
References
TAC ME1521
Download: ML092380101 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 26, 2009 Mr. Stewart B. Minahan Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321

SUBJECT:

COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST NO. RV-06 (TAC NO. ME1521)

Dear Mr. Minahan:

By application dated June 18, 2009, to the U.S. Nuclear Regulatory Commission (NRC)

(Agencywide Documents Access and Management System Accession No. ML091760099),

Nebraska Public Power District submitted Relief Request No. RV-06, in accordance with Title 10 of the Code of Federal Regulations, Section 50.55a. RV-06 requests to use alternative testing consistent with NUREG 1482, Revision 1, for certain check valves, solenoid operated valves, and air operated valves within the Control Rod Drive system, instead of the testing required by the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants.

The NRC staff has reviewed the information provided in your application and determined that additional information is required in order to complete its review. The enclosed questions were provided to Mr. D. Van Der Kamp of your staff on August 26, 2009. Please provide a response to the questions by October 1, 2009.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for NRC staff review and contribute toward the NRC's goal of efficient and effective use of NRC staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.

Sincerely, Carl F. Lyon, 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

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NO. RV-06 COOPER NUCLEAR STATION DOCKET NO. 50-298 The U.S. Nuclear Regulatory Commission staff has reviewed the information provided by Nebraska Public Power District (the licensee) for Cooper Nuclear Station (CNS) in its letter dated June 18, 2009, and determined that additional information is necessary to complete the review of Relief Request No. RV-06. Please provide a response that addresses the following questions.

1) Request RV-06 has two separate discussions on eight valves. Neither discussion identifies which Code requirement is applicable. Please clarify by providing a discussion of how each Code requirement applies to the situation, the alternative, and the reason for the request for each component listed.

2) CNS Updated Safety Analysis Report details that Control Rod Drive (CRD) scram outlet check valve, CRD-CV-114CV, also has a close function that prevents pressure from the Scram Discharge Volume header from operating the control rod drive mechanism.

Please explain how CRD-CV-114CV close function is tested and its frequency and/or explain why CRD-CV-114CV close function is not tested.

Enclosure

... ML092380101 *memo dated OFFICE NRRlLPL4/PM NRRlLPL4/LA DCI/CPTB/BC NRR/LPL4/BC NRR/LPL4/PM JBurkhardt BClayton NAME FLyon for JMcHale* MMarkley FLyon DATE 8/26/09 8/26/09 8/24/09 8/26/09 8/26/09