BSEP 06-0102, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

ML062780225
Person / Time
Site:	Brunswick
Issue date:	09/28/2006
From:	Ivey R Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 06-0102
Download: ML062780225 (3)

Text

Progress Energy SEP 2 8 2006 10 CFR 50.46(a)(3)(ii)

SERIAL: BSEP 06-0102 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

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 Emergency Core Cooling System Evaluation Model Changes and Errors

Reference:

Letter from Edward T. O'Neil to the U.S. Nuclear Regulatory Commission, "Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models," dated August 31, 2005 (ML052500310)

Ladies and Gentlemen:

In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Carolina Power &

Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., is submitting the annual report of the emergency core cooling system (ECCS) evaluation model changes and errors for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The enclosed report covers the period from August 1, 2005, through August 15, 2006. The previous annual report for BSEP, Units 1 and 2, was submitted by CP&L's letter dated August 31, 2005.

No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor - Licensing/Regulatory Programs, at (910) 457-2073.

Sincerely, 4(z/Co&,

Randy . Ivey Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 4D02,

Document Control Desk BSEP 06-0102 / Page 2 WRM/wrm

Enclosure:

Summary of Loss-of-Coolant Accident (LOCA) Emergency Core Cooling System (ECCS) Evaluation Model Analysis Changes and Errors cc: U. S. Nuclear Regulatory Commission, Region II ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Eugene M. DiPaolo, 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 27626-0510

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BSEP 06-0102 Enclosure Page 1 of 1 Summary of Loss-of-Coolant Accident (LOCA) Emergency Core Cooling System (ECCS)

Evaluation Model Analysis Changes and Errors Estimated Is BSEP Licensing PCT BSEP Change Greater Than Licensing 500 F?

PCT Impact Notice GE BWR and Cumulative or Change or estimated Estimated BSEP Change or Document Period Error Licensing PCT Licensing Error Notice Date Covered Description PCT Impact (GE14) PCT Change Incremental Cumulative 10 CFR 50.46 7/28/2006 8/1/2005 Impact of Generically 00 F 00 F No No Notification through top peaked not Letter 8/15/2006 power shape reportable U1 <U2 2006-01 for small < 1567'F break LOCA analysis.