NLS2004004, Revision to Commitment Referenced to Amendment 201 Safety Evaluation

Revision to Commitment Referenced to Amendment 201 Safety Evaluation

ML040340497
Person / Time
Site:	Cooper
Issue date:	01/30/2004
From:	Edington R Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2004004, TAC MB7209
Download: ML040340497 (3)

Text

Nebraska Public Power District Always theme when you need us NLS2004004 January 30, 2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Revision to Commitment Referenced In Amendment 201 Safety Evaluation Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46

References:

1. Letter to U.S. Nuclear Regulatory Commission from M. Coyle (Nebraska Public Power District) dated December 31, 2002, "License Amendment Request to Adopt an Integrated Reactor Vessel Material Surveillance Program" (NLS2002104).

2. Letter to C. Warren (Nebraska Public Power District) from U.S. Nuclear Regulatory Commission dated October 31, 2003, "Cooper Nuclear Station -

Issuance of Amendment to Implement the Boiling Water Reactor Vessel and Internals Project Reactor Pressure Vessel Integrated Surveillance Program (TAC No. MB7209)."

The purpose of this letter is to communicate the revision of a commitment made in Reference 1.

In that letter, the Nebraska Public Power District (NPPD) committed to perform fluence recalculations for previously withdrawn capsules using Regulatory Guide (RG) 1.190 methodology by February 2004, upon Nuclear Regulatory Commission (NRC) approval of the associated License Amendment Request. This commitment was included in the Safety Evaluation to License Amendment 201 (Reference 2). The February 2004 date was predicated on NRC acceptance in 2003 of the Electric Power Research Institute RAMA computer code as meeting RG 1.190. However, RAMA is still under regulatory review. Accordingly, NPPD is revising its commitment as follows:

Fluence recalculations will be performed for previously withdrawn capsules using RG 1.190 methodology within 12 months after NRC approval of the RAMA Code.

Should you have any questions concerning this matter, please contact Mr. Paul Fleming at (402) 825-2774.

R41dall K. Edington Vice President- Nuclear and Chief Nuclear Officer COOPER NUCLEAR STATION P.O. Box 98 / Brownville. NE 68321-0098 toD(

Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com

NLS2004004 Page 2 of 2 cc: Regional Administrator USNRC - Region IV Senior Project Manager USNRC - NRR Project Directorate IV-1 Senior Resident Inspector USNRC NPG Distribution Records

I ATTACHMENT 3 LIST OF REGULATORY COMMITMENTSl Correspondence Number: NLS2004004 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the Licensing & Regulatory Affairs Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE Fluence recalculations will be performed for previously withdrawn capsules using RG 1.190 methodology within 12 N/A months after NRC approval of the RAMA Code. _

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