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Text
Maria Korsnick 1503 Lake Road Vice President Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maria.korsnick~constellation.com
.%Constellation Energy R.E. Ginna Nuclear Power Plant July 6, 2004 Mr. Robert L. Clark Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
Subject:
10CFR50.46 Annual ECCS Report R.E. Ginna Nuclear Power Plant Docket No. 50-244
Reference:
(a) WestinghouseLetterRGE-04-19,
Subject:
JOCFR50.46AznnualNotification andReportingfor 2003, dated March 17, 2004.
Dear Mr. Clark:
In accordance with the requirements in 10CFR50.46 paragraph (a)(3)(ii), this annual ECCS report is hereby submitted.
Westinghouse, the provider of LOCA analysis services for the R.E. Ginna Nuclear Power Plant, has provided an update to the peak cladding temperature (PCT) margin in Reference (a).
The large-break LOCA PCT has not changed since the last report. The large-break LOCA PCT remains at 20870 F. The small-break LOCA PCT has increased from 1346 0 F to 1381'F. This increase has been determined to be bounding and accounts for changes to address inconsistencies in two-phase flow models in the Westinghouse NOTRUMP code. A summary of PCT changes can be found in Attachment 1 to this letter.
If you should have any questions regarding this submittal, please contact Thomas Harding at (585) 771-3384.
Very truly yours, Mary G. Korsnick
Attachment:
LOCA PCT Summary, June 2004 Update jot' cMOL(
xc: Mr. Robert Clark (Mail Stop 0-8-C2)
Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector Mr. James M. Petro Jr., Esquire Counsel Constellation Energy 750 East Pratt Street, 5th Floor Baltimore, MD 21202
ATTACHMENT 1 LOCA PCT
SUMMARY
JULY 2004 UPDATE
ATTACHMENT 1 LOCA PCT
SUMMARY
Large-Break LOCA R.E. Ginna Nuclear Power Plant Evaluation Model: UPI SECY Fuel: OFA FQ = 2.45 FAt}, = 1.75 SGTP = 15%
A. Analysis of Record (3/03) (effective 6/03) PCT= 20871F B. 2004 10CFR50.46 Model Assessments
- 1. None APCT= 00 F C. Other Margin Allocations
- 1. None APCT = 00 F Licensing Basis PCT = 2087'F Revision Date: 7/2004
ATTACHMENT I LOCA PCT
SUMMARY
Small-Break LOCA R.E. Ginna Nuclear Power Plant Evaluation Model: NOTRUMP Fuel: OFA FQ = 2 .50 FMt = 1.75 SGTP = 15%
A. Analysis of Record (6/95) (effective 6/96) APCT = 1308'F B. 1995 10CFR50.46 Model Assessments
- 1. NOTRUMP Specific Enthalpy Error APCT = 20'F
- 2. SALIBRARY Double Precision Errors APCT = -15'F C. 1996 10CFR50.46 Model Assignments
- 1. SBLOCA Fuel Rod Initialization Error APCT = I 0F D. 1997 10CFR50.46 Model Assessment
- 1. None APCT = 00 F E. 1998 10CFR50.46 Model Assessments
- 1. None APCT = 00 F F. 1999 10CFR50.46 Model Assessments
- 1. None APCT = 00 F G. 2000 10CFR50.46 Model Assessments
- 1. NOTRUMP - Mixture Level Tracking /
Region Depletion Errors APCT= 13°F H. 2001 10CFR50.46 Model Assessments
- 1. None APCT = 0°F I. 2002 10CFR50.46 Model Assessments
- 1. None APCT= 0°F J. 2003 10CFR50.46 Model Assessments
- 1. NOTRUMP - Bubble Rise /
Drift Flux Model Inconsistencies APCT = 35°F K. Ginna Evaluations
- 1. Annular Axial Pellets (1997 evaluation, SEV-1108) APCT = 10°F L. Other Margin Allocations
- 1. None APCT = 0°F Licensing Basis PCT = 1381°F Revision Date: 7/2004
