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[Table view]
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[Table view] |
Text
ROi Always at Your Service Robert C. Mecredy Vice President Nuclear Operations June 20,2003 Mr. Robert L. Clark Office of Nuclear Regulatory 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 Ref. (a) Westinghouse Letter RGE-03-18,
Subject:
Transmittal of SECY Large Break LOCA Analysis Engineering Report and Associated Documentation, dated March 27, 2003 (b) Westinghouse Letter RGE-03-11,
Subject:
IOCFR50.46 Annual Notification and Report for 2002, dated March 7, 2003
Dear Mr. Clark:
In accordance with the requirements in 10CFR50.46 paragraph (aX3Xii), this annual ECCS report is hereby submitted.
Westinghouse, the provider of LOCA analysis for the R. E. Ginna Nuclear Power Plant, has provided RG&E with an update to the peak cladding temperature (PCT) margin for Ginna Station (References a and b).
The large break LOCA analysis of record has been re-analyzed (Reference a). The new large break LOCA PCT is 20877F and is summarized in Attachment I to this letter.
An equal opportunity employer AOCcA 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com 1000-&7- An EnwW~ East Company
The small break LOCA PCT has not changed since the last report (Reference b). The small break LOCA PCT remains at 1346 0 F and is summarized in Attachment 1 to this letter.
Very truly yours, Robert C.
Attachments cc: Mr. Robert Clark (Mail Stop 0-8-C2)
Project Directorate I-1 Division of Reactor Projects - /11I Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector
ATTACHMENT I LOCA PCT
SUMMARY
JUNE 2003 UPDATE
ATTACHMENT I LOCA PCT
SUMMARY
Large Break LOCA RE. Ginna Nuclear Power Plant Rochester Gas and Electric Corporation Evaluation Model: UPI SECY Fuel: OFA FQ = 2.45 FAN= 1.75 SGTP= 15%
A. Analysis of Record (3/03) (effective 6/03) PCT = 2087° F B. Other Margin Allocations I1. None APCT = 0F Licensing Basis PCT = 2087TF Re vision Date: 6/2003
ATTACHMENT I LOCA PCT
SUMMARY
Small Break LOCA R.E. Ginna Nuclear Power Plant Rochester Gas and Electric Corporation Evaluation Model: NOTRUMP Fuel: OFA FQ = 2.50 FAH= 1.75 SGTP = 15%
A. Analysis of Record (6/95) (effective 6/96) A&PCT =13080 F B. 1995 10CFR50.46 Model Assessments
- 1. Notrunp Specific Enthalpy Error
- 2. SALIBRARY Double Precision Errors APCT = -15 0 F C. 1996 10CFR50.46 Model Assignments
- 1. SBLOCA Fuel Rod Initialization Error A&PCT =100 F D. 1997 10CFR50.46 Model Assessment
- 1. None ,&PCT = 0 F E. 1998 10CFR50.46 Model Assessments
- 1. None A&PCT =O0 F. 1999 10CFR50.46 Model Assessments
- 1. None ,&PCT= 0F G. 2000 10CFR50.46 Model Assessments
- 1. NOTRUMP - Mixture Level Tracking/ Region Depletion Errors A&PCT =13 0F H. 2001 10CFR50.46 Model Assessments
- 1. None A&PCT =O0 I. 2002 10CFR50.46 Model Assessments
- 1. None ,&PCT=0 0 F J. Ginna Evaluations
- 1. Annular Axial Pellets A&PCT =100 F (1997 evaluation; SEV-1 108)
K. Other Margin Allocations
- 1. None A&PCT= 0 F Licensing Basis PCT= 1346 0 F Revision Date: 6/2003
