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Category:Annual Operating Report
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[Table view]
Category:Letter
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[Table view] |
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 May 4,2005 Ms. Donna M. Skay Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
Subject:
10CFR50.46 30 Day and Annual ECCS Report R.E. Ginna Nuclear Power Plant Docket No. 50-244
References:
(a) Westinghouse LetterRGE-05-22,
Subject:
10CFR50.46 Annual Notification and Reporting for 2004, dated April 6, 2005.
(b) Letter from Mary G. Korsnick (Ginna LLC) to Donna M. Skay (NRC),
"License Amendment Request Regarding Revised Loss of Coolant Accident (LOCA) Analyses - Changes to Accumulator, Refueling Water Storage (RWST), and Administrative Control Technical Specifications", dated April 29, 2005.
Dear Ms. Skay:
In accordance with the requirements in 10CFR50.46 paragraph (a)(3)(ii), this 30 day and annual Emergency Core Cooling System (ECCS) report is hereby submitted by R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC).
Westinghouse, the provider of loss of coolant accident (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). A summary of the cumulative PCT changes can be found in Attachment 1 to this letter.
The large-break LOCA PCT has not changed since the last annual report. The large-break LOCA PCT remains at 20870 F.
The small-break LOCA PCT has not changed since the last annual report. The small-break LOCA PCT remains at 1381'F. Because the cumulative sum of the absolute magnitudes of the effects on the small-break LOCA PCT remain greater than 50'F, the changes conservatively qualify as being significant as defined in 10CFR50.46(a)(3)(i). Consequently, the cumulative changes are being reported in this 30 day report. I
(\DDI 100 (3t5
The small-break LOCA PCT value determined in the analysis of record, when combined with all PCT margin allocations, remains over 8000 F below the 10CFR50.46 acceptance criteria of 2200 0 F. As such, no reanalysis is currently planned to address the specific issues raised in . Ginna LLC has previously submitted (Reference (b)) new large-break LOCA and small-break LOCA analyses in support of the planned power uprate of the facility.
If you should have any questions regarding this submittal, please contact George Wrobel at (585) 771-3535.
Very truly yours Mary Korsnick
Attachment:
LOCA PCT Summary, 2005 Update xc: Ms. Donna M. Skay (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
ATTACHMENT 1 LOCA PCT
SUMMARY
2005 UPDATE
ATTACHMENT 1 LOCA PCT
SUMMARY
Large-Break LOCA R.E. Ginna Nuclear Power Plant Evaluation Model: UPI SECY Fuel: OFA FQ=2.45 FAI i = 1.75 SGTP = 15%
A. Analysis of Record (3/03) (effective 6/03) PCT = 2087TF B. 2004 10CFR50.46 Model Assessments
- 1. None APCT = 00 F C. Other Margin Allocations
- 1. None APCT = 00F Licensing Basis PCT = 2087°F
ATTACHMENT 1 LOCA PCT
SUMMARY
Small-Break LOCA R.E. Ginna Nuclear Power Plant Evaluation Model: NOTRUMP Fuel: OFA FQ = 2.50 FA I= 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 = -150 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
- 1. 2002 IOCFR50.46 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. 2004 10CFR50.46 Model Assessments
- 1. None - APCT = 0°F L. Ginna Evaluations
- 1. Annular Axial Pellets (1997 evaluation, SEV-1 108) APCT = 10°F M. Other Margin Allocations
- 1. None APCT = 0°F Licensing Basis PCT = 13 81°F
