BSEP-99-0157, Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)

Submits Annual Rept Summarizing Effect of Changes & Errors in Accepted loss-of-coolant Accident ECCS Evaluation Models Applicable to Bsep,Units 1 & 2 IAW 10CFR50.46(a)(3)(ii)

ML20217A650
Person / Time
Site:	Brunswick
Issue date:	10/04/1999
From:	Jury K CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-99-0157, NUDOCS 9910120045
Download: ML20217A650 (4)

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CP&L Caroline Power & Ught Company.

P.O. Box 10429 Southport. NC 28461-0429

-00T 0 41999 10 CFR 50.46(a)(3)(ii)

SERIAL: BSEP99-0157 U. S. 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 Gentlemen:

~ In accordance .with 10 CFR 50.46(a)(3)(ii), Carolina Power & Light (CP&L) Company hereby j submits the annual report summarizing the~effect 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. I 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). The regulation requires reporting, at least annually, of the estimated effect of changes or errors on the limiting ECCS analysis. This letter

fulfills this annual reporting requirement.

This letter reports changes and errors in the LOCA analysis for BSEP for the period from N1y 1, 1998, through June 30,1999. The previous annual report of LOCA analysis changes and errors for BSEP was submitted by CP&L's .Util Will Continue to Perform Static Testing IAW Original GL 89-10|letter dated October 27,1998]] (Serial: BSEP 98-0198). In addition, by [[letter::BSEP-99-0020, Submits Info Re Estimated Effects of Errors Identified in GE Nuclear Energy Safer/Gestr LOCA Evaluation Model,Per 10CFR50.46(a)(3)(ii).Base Case LOCA Analyses for Bsep,Units 1 & 2,are Documented in Listed Documents|letter dated February 26,1999]] (Serial: BSEP 99-0020), CP&L. submitted a 30-day notification based on a cumulation of changes and errors such that the sum of the absolute magnitudes of the calculated PCT changes exceeded 50 F. No change or error relative to the LOCA analysis for BSEP has been identified since CP&L submitted the February 26,1999 l notification. General Electric (GE), the LOCA analysis vendor, has reported only one error in I

. their ECCS evaluation models since CP&L's last 10 CFR 50.46 notification. The error is not

- applicable to BSEP.

' A summary of the effects of the currently reported LOCA analysis changes and errors is enclosed. The absolute value of the currently reported errors and changes to the licensing-basis o\

PCT is 73 F for GE7 fuel and 60 F for GE13 fuel. The absolute value of the currently reported errors and changes to the upper bound PCT is 110 F for GE7 fuel and 60 F for GE13 fuel. The

,  : absolute value of these errors and changes for the GE7 fuel type bounds the GE8, GE9, and

_ GE10 fuel types.

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Document, Control Desk BSEP 99-0157 / Page 2 No regulatory commitments are being made in this subm.ittal. Please refer any questions regarding this submittal to Mr. Warren J. Dorman, Supervisor - Licensing, at (910) 457-2068.

Sincerely, e.

Keith R. Jury Manager- Regulatory Affairs Bmnswick Steam Electric Plant WRM/wrm

Enclosure:

Update To Annual Repon 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 Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-3415 U. S. Nuclear Regulatory Commission ATTN: Mr. Theodore A. Eastick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission ATTN: Mr. Allen G. Hansen (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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l l ENCLOSURE 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 Annual Report of Loss-of-Coolant Accident (LOCA)

Emergency Core Cooline System (ECCS) Evaluation Model Analysis Chances and Errors Summary of SAFER /GESTR LOCA ECCS Analysis Changes and Errors (July 1,1998, to June 30,1999)

General Electric BWR Estimated Estimated Brunswick Steam Peak Electric Plant Notice Cladding (BSEP)Iicensing is Cumulative Change or Temperature Basis PCT Cunndative BSEP PCT or Error ihmiment Period Change or Error (PCT) Impact and BSEP PCT Change Greater Notice IAe Covered Description impact Estimated PCT Change Than 50*F Willt: 994)07 1/27/99 1/96 to 150*F for input 50*F 50*F +73*F GE7' incremental - No (Received 6/30/99 parameter sensitivity +60*F GE13 Cumulative - Yes MFN 032 98 U t - 1606*F GE7 1/27/99) (10"F for Bottom Ilead Drain U2 - 1610*F GE7 pre &siv reported). UI - 1595'F GE7 U2 - 1595 F GF7

• GE7 bounds GE8, GE9, and GE10.

BSEP Licensing Basis PCT Change Summary (Through June 30,1999)

Greatest Licensing Basis PCT Reported in a LOCA Document Current Estimated Change From Reported Unit and Fuel Type Submitted to the NRC Licensing Basis PCT Licensing Basis PCT Unit 1 GE7* 1533*F 1606 F +73 F Unit 1 GE13 1535'F 1595*F +60 F Unit 2 GE7* 1537 F 1610 F +73 F Unit 2 GE13 1535 F 1595 F +60 F

• GE7 bounds GE8, GE9, and GE10.

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BSEP Upper Bound PCT Change Summary (Through June 30,1999)

Greatest Licensing Basis PCT Reported in a i

LOCA Document Current Estimated Change From Reported Unit and Fuel Type Submitted to the NRC Licensing Basis PCT Licensing Basis PCT .

i Unit 1 GE7* 1353'F 1463'F +110*F l Unit 1 GE13 1448'F 1508'F +60 F Unit 2 GE7* 1390*F 1500 F +110 F Unit 2 GE13 1448'F 1508'F +60 F

• GE7 bounds GE8, GE9, and GE10.

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