BSEP 03-0107, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models

Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models

ML031980462
Person / Time
Site:	Brunswick
Issue date:	07/09/2003
From:	O'Neil E Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 03-0107
Download: ML031980462 (3)

Text

C40 Progress Energy JUL 0 9'2003 10 CFR 50.46(a)(3)(ii)

SERIAL: BSEP 03-0107 TS.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 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 Ladies and Gentlemen:

In accordance with 10 CFR 50.46(a)(3)(ii), Progress Energy Carolinas, Inc. is providing an annual report summarizing the effects of changes and errors in accepted loss-of-coolant accident (LOCA) Emergency Core Cooling System (ECCS) evaluation models applicable to the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. 10 CFR 50.46(a)(3)(ii) specifies reporting requirements based on the sum of the absolute value of the changes and errors in calculated peak cladding temperature (PCT), including a requirement that, at least annually, the estimated effect of changes or errors on the limiting ECCS analysis be reported.

A summary of the effects of the currently reported LOCA analysis changes and errors for the GE13 and GE14 fuel types is enclosed. This summary includes changes and errors in the LOCA analysis for BSEP for the period ending May 6, 2003. The previous annual report, covering the period ending May 15, 2002, was submitted by letter dated July 10, 2002 (i.e., Serial: BSEP 02-0123, ADAMS Accession Number ML022040695).

Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor -

Licensing/Regulatory Programs, at (910) 457-2073.

Sincerely, Edward T. ONeil Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461

Document Control Desk BSEP 03-0107 / Page 2 LU/lu

Enclosure:

Update to Report of Loss-of-Coolant Accident (LOCA) Emergency Core Cooling System (ECCS) Evaluation Model Analysis Changes and Errors 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 ATI7N: NRC Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ArTIN: 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 27626-0510

if BSEP 03-0107 Enclosure Page 1 of 1 Update to Report of Loss-of-Coolant Accident (LOCA)

Emergency Core Cooling System (ECCS)

Evaluation Model Analysis Changes and Errors Change Notice or Period Change or Error GE BWR Estimated BSEP Licensing PCT Impact Cumulative BSEP Is BSEP Licensing PCT or Error Document Covered Description Estimated and Estimated PCT Licensing PCT Change Change Greater than 50°F?

Notice Date Licensing PCT Impact GE13 GE14 GE13 GE14 Incremental Cumulative 10 CFR 50.46 June 2002 through SAFER Core Spray -95°F to +600 P +50F +5OF 5Op 5Op No No Notice 5/02 Injection Elevation for LBLOCA, 2002-01 Error SBLOCA UlcU2 c1722°F UI<U2 <1562°F up to +30°P .

10 CFR 50.46 June 2002 through SAFER Bulk Water -5°P to +20°F +10 0° +10 0° 15°F 15°F No. No Notice 5/02 Level Error Impact on 2002-02 PCT UI < U2 <1732°F UI < U2 <1572°F ,/

10 CPR 50.46 August through GESTR Input File Negligible Op 0OpF 15F 15OF No No Notice 2002 8/26/02 Interpolation Error 2002-03 Impact on PCT U I <U2 c1732°F U I <U2 <1572°F 10 CFR 50.46 August through SAFER04 Computer Negligible 0Op 0°F 15F 15°F No No Notice 2002 8/26/02 Platform Change Impact 2002-04 onPCT UI cU2 <1732°F Ul <U2c1572°F 10 CPR 50.46 August through WEVOL SI Volume Negligible 0Op 0°F 150 F 15°F No No Notice 2002 8/26102 En-or Impact on PCT 2002-05 UI c U2 d732°F U1 < U2 <1572°F

/

10 CPR 50.46 May 2003 through SAFER Level/Volume Generically 0°F -50 F 15°F 20°F No No Notice 5/06/03 Table Error Impact on not reported 0

2003-01 PC U Ic U2<1732F Ul <U2 <1567°.

10 CPR 50.46 May 2003 through SAFER initial Separator Generically 0Op 0°F 15°F 20°F ' No No Notice 5/06/03 Pressure Drop Error not reported 2003-03 Impact on PCT UI < U2 c1732°F UI < U2 c1567°PF