BSEP 08-0121, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors

ML082760470
Person / Time
Site:	Brunswick
Issue date:	09/24/2008
From:	Leich P Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 08-0121, TAC MD4063, TAC MD4064
Download: ML082760470 (5)

Text

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

SER 2 42008

.SERIAL: BSEP 08-0121 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 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors

References:

1. Letter from Randy C. Ivey (CP&L) to U.S. Nuclear Regulatory Commission, "Annual Report of Emergency Core Cooling Systems Evaluation Model Changes and Errors," dated September 11, 2007, ADAMS Accession Number ML072620146

2. Letter from the U.S. Nuclear Regulatory Commission to Benjamin Waldrep (CP&L), "Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendments to Support Transition to AREVA Fuel and Methodologies (TAC Nos. MD4063 and MD4064)," dated March 27, 2008, ADAMS Accession Number ML080870478 Ladies and Gentlemen:

The purpose of this letter is to submit the annual 10 CFR 50.46 reporting information for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The enclosed reports fulfill the annual reporting requirements of the emergency core cooling system (ECCS) evaluation model changes and errors for BSEP, Units 1 and 2, for the period from August 16, 2007, through August 15, 2008.

By letter dated September 11, 2007, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., reported an estimated fuel peak cladding temperature (PCT) of < 1567°F for Global Nuclear Fuel (GNF) fuel being used in BSEP, Units 1 and 2. For the current reporting period, there is no change in the PCT for the GNF fuel.

By letter dated March 27, 2008, the NRC approved license amendments supporting the transition to AREVA NP fuel and core design methodologies. Beginning with Cycle 17, Brunswick Unit 1 is operating with a mixed core design comprised of~co-resident GNF and AREVA fuel. BSEP Unit 2 has not yet begun operation with AREVA fuel. For the-current reporting period, there is no change in the reported PCT of < 1900'F for AREVA fuel.

Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant PO Box 10429 Southport, NC 28461

Document Control Desk BSEP 08-0121 / Page 2 The results of the loss-of-coolant accident (LOCA) analyses of record for both GNF and AREVA fuel are within all of the acceptance criteria set forth in 10 CFR 50.46.

No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Gene Atkinson, Supervisor - Licensing/Regulatory Programs, at (910) 457-2056.

Sincerely, Philip A. Leich Manager - Support Services Brunswick Steam Electric Plant WRM/wrm

Enclosures:

1. Brunswick Units 1 and 2 10 CFR 50.46 Report (GNF Fuel)

2. Brunswick Units 1 and 2 10 CFR 50.46 Report (AREVA Fuel)

Document Control Desk BSEP 08-0121 / Page 3 cc (with enclosures):

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. Joseph D. Austin, 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 27626-05 10

BSEP 08-0121 Enclosure 1 Page 1 of 1 Brunswick Units 1 and 2 10 CFR 50.46 Report (GNF Fuel)

PLANT: Brunswick Steam Electric Plant, Units 1 and 2 ECCS EVALUATION MODEL: SAFER/GESTR LOCA REPORT REVISION DATE: August 15, 2008 CURRENT OPERATING CYCLES: B1C17 and B2C18 ANALYSIS OF RECORD Evaluation Model: NEDE-24011 -P-A- 15, "General Electric Standard Application for Reactor Fuel," September 2005, and the U.S. Supplement NEDE-2401 1-P-A- 15-US, September 2005.

Fuel: GE14 Estimated PCT: < 15670 F GNF SAFER/GESTR-LOCA Analysis Evaluation Model Reporting Period: August 16, 2007 to August 15, 2008 Estimated Incremental Absolute Change in Cumulative Change Description PCT in PCT 10 CFR 50.46 Report dated September 11, 2007 +100F +20°F Notices for Current Report Period (August 16, 2007 -

August 15, 2008):

• None 0°F 0°F Estimated Change in PCT (As of August 15, 2008) +100F +20°F Estimated PCT Impact Reporting Period Ending August 15, 2008*

Cumulative Incremental Licensing Basis Change Estimated PCT Fuel Type PCT in PCT Estimated PCT < 22000 F GE14 < 1557 0 F +100 F < 1567 0 F Yes

• LOCA Results presented for Unit 2, which bounds Unit 1

BSEP 08-0121 Enclosure 2 Page 1 of 1 Brunswick Units 1 and 2 10 CFR 50.46 Report (AREVA Fuel)

PLANT: Brunswick Steam Electric Plant, Units 1 and 2 ECCS EVALUATION MODEL: EXEM BWR-2000 Evaluation Model REPORT REVISION DATE: August 15, 2008 CURRENT OPERATING CYCLES: BIC17 ANALYSIS OF RECORD Evaluation Model: EMF-2361(P)(A), Revision 0, EXEM BWR-2000 ECCS Evaluation Model, May 2001.

Fuel: ATRIUM- 10 Estimated PCT: < 1900°F AREVA EXEM BWR-2000 LOCA Analysis Evaluation Model Reporting Period: August 16, 2007 to August 15, 2008 Estimated Incremental Absolute Change in Cumulative Change Description PCT in PCT 10 CFR 50.46 Report dated September 11, 2007 N/A N/A Notices for Current Report Period (August 16, 2007 -

August 15, 2008):

e AREVA 2007 Annual Notice (March 24, 2008) 0°F 0°F Estimated Change in PCT (As of August 15, 2008) 0°F 0°F Estimated PCT Impact Reporting Period Ending August 15, 2008*

Cumulative Incremental Licensing Basis Change Estimated PCT Fuel Type PCT in PCT Estimated PCT _<2200OF ATRIUM-10 <1900°F 0°F <1900°F Yes

• LOCA Results presented for Unit 2, which bounds Unit 1