ML090900635

Report of Changes, Tests and Experiments and Summary of Commitment Changes

ML090900635
Person / Time
Site:	Big Rock Point  File:Consumers Energy icon.png
Issue date:	03/31/2009
From:	Lahti L Entergy Nuclear Operations
To:	Document Control Desk, NRC/FSME, Office of Nuclear Material Safety and Safeguards
References
Download: ML090900635 (2)

Text

Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Tel269 764 2000 March 31,2009 10 CFR 72.48 10 CFR 50.59 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Big Rock Point Plant Docket 50-155 and 72-043 License No. DPR-6 Report of Changes, Tests and Experiments and Summaw of Commitment Changes

Dear Sir or Madam:

Entergy Nuclear Operations, Inc. (ENO) is providing the Report of Facility Changes, Tests and Experiments for the time period from April 1, 2007, through March 31, 2009, for the Big Rock Point Plant. The report is contained in . This report is being submitted in accordance with the requirements of 10 CFR 72.48 and 10 CFR 50.59. There were no commitment changes made in accordance with NEI 99-04, "Guidelines for Managing Commitment Changes," during the period.

Laurie A. Lahti Licensing Manager Palisades Nuclear Plant Enclosure CC Administrator, Region Ill, USNRC Director, Spent Fuel Storage and Transportation Office, USNRC NRC NMSS Project Manager

ENCLOSURE I

SUMMARY

OF 72.48 AND 50.59 EVALUATION BIG ROCK POINT PLANT Log No. Description of Change and Summary of 72.48 and 50.59 Evaluation Performed 063-07 The Big Rock Point (BRP) plant quality assurance (QA) program was changed from the Consumers Energy QA program to the Entergy Operations, Inc. QA program.

The Entergy Nuclear Operations QA program was previously approved by the NRC in a safety evaluation dated November 6, 1998. Under 10 CFR 72.140(d), a QA program accepted as satisfying 10 CFR 50, Appendix B, is acceptable to satisfy 10 CFR 72.140. The adoption of the Entergy Nuclear Operations QA program has no effect on the frequency of any accidents previously evaluated in the Safety Analysis Reports. The likelihood of occurrence of a malfunction of a system, structure, or component important to safety is not increased, the consequences of previously evaluated accidents are not affected, no consequences of malfunctions of important to safety components are increased, no accidents of a different type are created, the possibilities of different malfunctions are not created, no design basis limits for fission product barriers are exceeded or altered, and no methods of evaluation are affected.

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