CPSES-200200080, Annual Report of Changes in Peak Cladding Temperature
| ML020310379 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/08/2002 |
| From: | Terry C, Walker R TXU Electric |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 10010, CPSES-200200080, TXX-02007 | |
| Download: ML020310379 (3) | |
Text
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TXU TXU Electric Comanche Peak Steam Electric Station P.O. Box 1002 Glen Rose,TX 76043 Tel: 254 897 8920 Fax:254 897 6652 Iterryl@txu.com C. Lance Terry Senior Vice President & Principal Nuclear Officer Ref: 10CFR50.46 CPSES-200200080 Log # TXX-02007 File#
10010 January 8, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 ANNUAL REPORT OF CHANGES IN PEAK CLADDING TEMPERATURE Gentlemen:
In accordance with the requirements of 1 OCFR50.46(a)(3)(ii), TXU Electric submits the attached changes or errors discovered in the Emergency Core Cooling System (ECCS) evaluation model used to calculate peak cladding temperature (PCT) and the estimated effect of these changes or errors on the limiting ECCS analysis. As in the previous year, the analyses for Unit 1 were performed with a Steam Generator Tube Plugging allowance of 10% and those for Unit 2 with an allowance of 5%.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Comanche Peak Diablo Canyon South Texas Project Callaway Wolf Creek If"R
TXU TXX-02007 Page 2 of 2 This communication contains no new licensing basis commitments regarding CPSES Units 1 and 2.
Sincerely, C. L. Terry By:
a,1ý RogeYD. Walker Regulatory Affairs Manager JDS/js Attachment c -
E. W. Merschoff, Region IV C. E. Johnson, Region IV D. H. Jaffe, NRR Resident Inspectors, CPSES
Attachment to TXX-02007 Page 1 of 1 CPSES Units 1 and 2 Peak Clad Temperatures Analysis/Evaluation CPSES Unit 1 PCT (°F)
[Large Break]
Small Break LOCA PCT* (°F) 1884 1859 CPSES Unit 2 PCT (°F) 1912 1835
- An error pertaining to clad rupture at negative pressures was corrected in the Small Break LOCA hot rod response code TOODEE2 (UAPR94). The correction to the TOODEE2 code was conservatively estimated to be 11 °F. Units 1 and 2 were re-analyzed for the Small Break LOCA and the revised PCT obtained with the corrected version of the Small Break LOCA TOODEE2 code is herein reported.