BSEP 10-0107, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

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

ML102670051
Person / Time
Site:	Brunswick
Issue date:	09/13/2010
From:	Mentel P Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 10-0107
Download: ML102670051 (3)

Text

4Progress Energy 10 CFR 50.46(a)(3)(ii)

SEP 1 3,2010 SERIAL: BSEP 10-0107 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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.

BSEP, Units 1 and 2 employ a mixed core design containing co-resident AREVA and Global Nuclear Fuel (GNF) fuel. Because the GNF fuel is now a non-limiting fuel type, model changes and errors are not being reported for the GNF fuel.

The enclosed report covers the period from August 17, 2009, through August 27, 2010.

The reported estimated licensing basis peak cladding temperature (PCT) remains within the acceptance criteria set forth in 10 CFR 50.46 (i.e., < 2200'F).

No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Ms. Annette Pope, Supervisor - Licensing/Regulatory Programs, at (910) 457-2184.

Sincerely, Phyllis N. Mentel Manager - Support Services Brunswick Steam Electric Plant Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461

Document Control Desk BSEP 10-0107 / Page 2 WRM/wrm

Enclosure:

Brunswick Units 1 and 2 10 CFR 50.46 Report cc (with enclosure):

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission ATTN: Mr. Philip B. O'Bryan, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mrs. Farideh E. Saba (Mail Stop OWFN 8G9A) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

BSEP 10-0107 Enclosure Page 1 of 1 Brunswick Units 1 and 2 10 CFR 50.46 Report Plant: Brunswick Steam Electric Plant, Units 1 and 2 Report Revision Date: August 27, 2010 Current Operating Cycles: Unit 1 - Cycle 18, Unit 2 - Cycle 19 Evaluation Model: EMF-2361(P)(A), Revision 0, EXEM BWR-2000 ECCS Evaluation Model, May 2001.

Fuel: ATRIUMTM- 10 Net Absolute PCT Effect PCT Effect A. Cumulative 10 CFR 50.46 Changes and Error -70 F +70 F Corrections - Previously Reported (Resulting in an effective licensing basis PCT of 1900'F)

B. 10 CFR 50.46 Changes and Error Corrections - This Reporting Period

1. LOCA re-analysis establishing a new licensing ---

basis PCT of 1904°F (

Reference:

AREVA Report ANP-2624(P), Revision 2)

2. RELAX code array index issues (

Reference:

00 F 0°F AREVA Engineering Information Record 51-9133678-000)

3. HUXY code numerical view factor evaluation +10 1F +10 F

(

Reference:

AREVA Engineering Information Record 51-9143783-000)

C. Absolute Sum of 10 CFR 50.46 Changes and Error --- +10 F Corrections (based on new licensing basis PCT of 1904 0 F)

D. Evaluated Effective Licensing Basis PCT including Changes and Error Corrections Licensing Cumulative Basis Incremental Estimated Estimated PCT Fuel Type PCT Change in PCT PCT < 2200°F A10 1904°F +10 F 1905OF Yes