BSEP 02-0123, Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models from Brunswick Steam Electric Plant, Units 1 & 2
| ML022040695 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/10/2002 |
| From: | O'Neil E Carolina Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BSEP 02-0123 | |
| Download: ML022040695 (3) | |
Text
SCP&L AProgressEnergy Company 10 CFR 50.46(a)(3)(ii)
JUL 102002 SERIAL: BSEP 02-0123 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 NOS. 1 AND 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT DPR-71 AND DPR-62 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS.
EMERGENCY CORE ANNUAL REPORT OF CHANGES AND ERRORS IN COOLING SYSTEM EVALUATION MODELS Ladies and Gentlemen:
& Light (CP&L) Company is In accordance with 10 CFR 50.46(a)(3)(ii), Carolina Power and errors in accepted loss providing an annual report summarizing the effects of changes System (ECCS) evaluation models of-coolant accident (LOCA) Emergency Core Cooling Unit Nos. 1 and 2.
applicable to the Brunswick Steam Electric Plant (BSEP),
based on the sum of the absolute 10 CFR 50.46(a)(3)(ii) specifies reporting requirements temperature (PCT), including a value of the changes and errors in calculated peak cladding of changes or errors on the limiting requirement that, at least annually, the estimated effect ECCS analysis be reported.
analysis changes and errors for A summary of the effects of the currently reported LOCA includes changes and errors in the GE13 and GE14 fuel types is enclosed. This summary 15, 2002. The previous annual the LOCA analysis for BSEP for the period ending May letter dated July 11, report, covering the period ending May 24, 2001, was submitted by Number ML011990030).
2001 (i.e., Serial: BSEP 01-0083, ADAMS Accession Leonard R. Beller, Supervisor Please refer any questions regarding this submittal to Mr.
Licensing/Regulatory Programs, at (910) 457-2073.
Sincerely, Edward T. O'Neil Manager - Regulatory Affairs Brunswick Steam Electric Plant Brunswick Nuclear Planr, PO.Box 10429 Southport, NC 28461
Document Control Desk BSEP 02-0123 / Page 2 WRM/wrm Core
Enclosure:
Update to Report of Loss-of-Coolant Accident (LOCA) Emergency Errors Cooling System (ECCS) Evaluation Model Analysis Changes and cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Theodore A. Easlick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-05 10
BSEP 02-0123 Enclosure Page 1 of 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 ANNUAL REPORT OF CHANGES AND ERRORS IN EMERGENCY CORE COOLING SYSTEM EVALUATION MODELS Update to Report of Loss-of-Coolant Accident (LOCA)
Emergency Core Cooling System (ECCS) Evaluation Model Analysis Changes and Errors GE BWR Estimated BSEP Licensing Estimated PCT Impact and Cumulative BSEP Licensing Is BSEP Licensing PCT Change Licensing Estimated PCT PCT Change Greater than 50'F?
Peak Cladding Change Notice or Change or Temperature or Error Document Period Error (PCT)
Notice Date Covered Description Impact 2558 MWt 2923 MWt 2558 MWt 2923 MWt Incremental Cumulative Extended June 2001 Through New ECCS NA 0°F -31F 00 F for GE13 3°F for GEl 3 No No Power May LOCA Uprate 2002 analysisto GE13: UI <U2 GE13: UI <U2 00FforGE14 3°F forGE14 (EPU) support EPU < 1720'F < 1717'F Task conditions.
Report GE14: UI <U2 GE14: UI < U2 T0407* < 1560'F <1557°F
- GE Report GE-NE-A22-00113-27-01, Revision 0, June 2001.