ML023610177
| ML023610177 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 12/17/2002 |
| From: | Cooper D Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML023610177 (5) | |
Text
NMC Committed to Nuclear Excellence 5 Palisades Nuclear Plant Operated by Nuclear Management Company, LLC December 17, 2002 10 CFR 50.46 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 PALISADES NUCLEAR PLANT DOCKET 50-255 LICENSE DPR-20 ANNUAL REPORT OF CHANGES IN ECCS MODELS PER 10 CFR 50.46 Nuclear Management Company, LLC, is submitting the annual report of changes in 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 Westinghouse Electric Company, LLC, small break loss-of-coolant accident (SBLOCA) ECCS evaluation summary and the Framatome Advanced Nuclear Power, Inc., SEM/PWR-98 large break loss-of-coolant accident (LBLOCA) evaluation summary. This report covers the period from December 27, 2001 through December 17, 2002.
SUMMARY
OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.
Vouglls:E. Cooper Site Vice-President, Palisades CC Regional Administrator, USNRC, Region III Project Manager, USNRC, NRR NRC Resident Inspector - Palisades Attachment 27780 Blue Star Memorial Highway 0 Covert, MI 49043 Telephone: 616.764.2000
ATTACHMENT NUCLEAR MANAGEMENT COMPANY, LLC PALISADES NUCLEAR PLANT DOCKET 50-255 December 17, 2002 ANNUAL REPORT OF CHANGES IN ECCS MODELS PER 10 CFR 50.46 3 Pages Follow
10 CFR 50.46 REPORT OF CHANGES AND ERRORS IN SMALL BREAK LOSS-OF COOLANT ACCIDENT (SBLOCA) EMERGENCY CORE COOLING (ECCS)
EVALUATION MODEL Westinghouse Electric Company, LLC, (formerly Asea Brown Boveri-Combustion Engineering Nuclear Power) performed the SBLOCA analysis for fuel cycle 14 for the Palisades Nuclear Plant. This analysis also applies to fuel cycle 15 and 16 operations.
The peak cladding temperature (PCT) of 20630F and was reported in Reference 1.
Westinghouse Electric Company, LLC, has reported no errors since the Reference 1 report.
The resulting PCT, as applicable for the current fuel cycle 16, is 2063°F.
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10 CFR 50.46 REPORT OF CHANGES AND ERRORS IN LARGE BREAK LOSS-OF-COOLANT ACCIDENT (LBLOCA) ECCS EVALUATION MODEL Framatome Advanced Nuclear Power, Inc., (FRA-ANP; formerly Siemens Power Corporation) evaluates the LBLOCA for the Palisades Nuclear Plant with the SEM/PWR-98 methodology. The PCT of 1934°F for fuel cycle 16 was reported in Reference 1. FRA-ANP has reported the following 2 errors since the Reference 1 report.
RFPAC V&V Findings from CDUP (FRA-ANP Condition Report 8674)
FRA-ANP (formerly Siemens Power Corporation) committed, in response to the Nuclear Regulatory Commission 1997 inspection at Siemens Power Corporation, to perform additional validation and verification (V&V) and to update or create user's manuals, theory manuals, and programmer's manuals for FRA-ANP's primary codes. One of the primary codes was the RFPAC code. The RFPAC code performs the refill and reflood calculations for the LBLOCA event in the SEM/PWR-98 evaluation model. A number of minor errors were identified and corrected as a result of the additional V&V activities.
The estimate of the PCT impact of the error corrections is +281F for the LBLOCA analysis for the Palisades Nuclear Plant.
Error in TOODEE2 Clad Thermal Expansion Calculation (FRA-ANP Condition Report 9156)
TOODEE2 uses a correlation for determining clad thermal expansion with three ranges; Alpha phase, Beta phase, and a transition region between the Alpha and Beta phases.
The formulation for the Beta phase was programmed with an incorrect constant coefficient of 2.9E-6 instead of 3.2E-6. This introduces a discontinuity between the transition region and the Beta region and causes all clad thermal expansion calculations at temperatures above 17730F to be under predicted. The PCT impact of this error correction is estimated to be -1 OF for the LBLOCA analysis for the Palisades Nuclear Plant.
The sum of these errors is +27°F, which results in the LBLOCA PCT for the current fuel cycle 16 being 1961°F.
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Reference:
- 1. Letter, Laurie A. Lahti (Nuclear Management Company) to Document Control Desk (NRC), "Annual Report of Changes in ECCS Models per 10 CFR 50.46," dated December 27, 2001.
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