ML033580606

Annual Report of Changes in Emergency Core Cooling System Models

ML033580606
Person / Time
Site:	Palisades
Issue date:	12/11/2003
From:	Domonique Malone Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML033580606 (2)

Text

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Palisades Nuclear Plant Operated by Nuclear Management Company, LLC December 11, 2003 10 CFR 50.46 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Palisades Nuclear Plant Docket 50-255 License No. DPR-20 Annual ReDort of Changes in Emergency Core Cooling System Models Nuclear Management Company, LLC, is submitting the annual report of changes in the emergency core cooling system (ECCS) models for the Palisades Nuclear Plant. The report is submitted in accordance with 10 CFR 50.46(a)(3)(ii). The report contains both the small break loss-of-coolant accident ECCS evaluation summary and the large break loss-of-coolant accident evaluation summary. This report covers the period from December 17, 2002 through December 11, 2003.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

Daniel J. Malone Site Vice President, Palisades Nuclear Plant Nuclear Management Company, LLC Enclosure (1)

CC Regional Administrator, Region l1l, USNRC Project Manager, Palisades, USNRC NRC Resident Inspector, Palisades USNRC 27780 Blue Star Memorial Highway. Covert, Michigan 49043-9530 Telephone: 269.764.2000

ENCLOSURE 1 ANNUAL REPORT OF CHANGES IN EMERGENCY CORE COOLING MODELS 1.0 CHANGES AND ERRORS IN SMALL BREAK LOSS-OF-COOLANT ACCIDENT (SBLOCA) EMERGENCY CORE COOLING (ECCS) EVALUATION MODEL Framatome Advanced Nuclear Power, Inc. (FANP) performed the SBLOCA analysis for fuel cycle 17 for Palisades Nuclear Plant. The peak cladding temperature (PCT) of 14650F was reported in Reference 1.

FANP has reported no errors since the Reference 1 report.

The resulting PCT, as applicable for the current fuel cycle 17, is 14650F.

2.0 CHANGES AND ERRORS IN LARGE BREAK LOSS-OF-COOLANT ACCIDENT (LBLOCA) ECCS EVALUATION MODEL FANP evaluates the LBLOCA for the Palisades Nuclear Plant with the SEM/PWR-98 methodology. The PCT of 1961 'F for fuel cycle 16 was reported in Reference 2. FANP has reported no errors since the Reference 2 report.

The resulting PCT, as applicable for the current fuel cycle 17, is 1961'F.

3.0 REFERENCES

1.

Letter, Douglas E. Cooper (Nuclear Management Company) to Document Control Desk (NRC), "Thirty-Day Report of Changes in Emergency Core Cooling System Models per 10 CFR 50.46," dated May 15, 2003.

2.

Letter, Douglas E. Cooper (Nuclear Management Company) to Document Control Desk (NRC), "Annual Report of Changes in ECCS Models per 10 CFR 50.46," dated December 17, 2002.

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