ML20114D950

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Forwards Vols 1 & 2 to, Brunswick Steam Electric Plant Units 1 & 2 IPE, Per Generic Ltr 88-20,Suppl 1.Results of Level 1 IPE Indicate Overall Core Damage Frequency of 2.7E-5/yr
ML20114D950
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 08/31/1992
From: Starkey R
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20114D951 List:
References
GL-88-20, NLS-92-245, NUDOCS 9209100204
Download: ML20114D950 (2)


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United States Nuclear Regulatory Commission ATTENTION: Documer)t Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR 71 & DPR 62 RESPONSE TO GENERIC LETTER 88 20, SUPPLEMENT 1--SUBMITTAL OF INDIVIDUAL PLANT EXAMINATION (IPE) FOR BRUNSWICK UNITS 1 & 2 Gentlemen:

The purpose of this letter is to submit the results of the Individual Plant Examination (IPE) for Brunswick Steam Electric Plant (BSEP), Units 1 & 2, as committed in our October 31,1989 response to Supplement 1 of Generic Letter 88-20. The IPE for BSEP Units 1 and 2 was completed using a plant-specific, comprehensive probabilistic risk assessment (PRA), consistent with the approved method listed in Section 4 of Generic Letter 88-20. The PRA was performed using methods consistent with the technology in the PRA procedures guide (References 1-3 of the Enclosure) and PRAs of other utilities. The original BSEP PRA, submitted to the NRC in the spring of 1988, served as a foundation for the current PRA and the BSEP IPE.

The results of the BSEP Level 1 IPE indicate an overall Core Damage Frequency (CDF) of 2.7E-5 /

year. Approximately 66% of the overal! CDF for DSEP Units 1 and 2 is attributed to Station Blackout sequences (1.8E-5 / year); however, GDC 17 related modifications and installation of a non-class 1E diesel generator planned for BSEP Units 1 & 2, as discussed in a meeting with the .

NRC staff on February 19,1992, and docketed by NRC correspondence dated March 30,1992, will considerably reduce the risk associated with those scenarios. The Level 1 IPE also demonstrated that transient initiated sequences involving Loss of Decay Heat Removal contribute approximately 30% to the overall CDF (8.3E-6 / year). Modifications to install a hardened wetwell vent will reduce the already low core damage irequency contribution associated with these scenarios.

In accordance with Generic Letter 88-20, Unresolved Safety Issue (USI) A-45, " Shutdown Decay Heat Removal Requirements," has been resolved by the BSEP IPE The resolution of this issue is discussed in Section 3.4 of this report, in addition, USl A-17, " System Interactions in Nuclear Power Plants," has been resolved by the IPE This resolution is also provided in Section 3.4 of this report.

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Document Control Desk NLS-92 245 / Page 2 Please refer any questions regarding this submittal to Mr. M. R. Oates at (919) 546-6063.

Yours very truly, R. B. Starkey, Jr.I KAH/kah (ipesubm.th)

Enclosure R. B. Starkey, Jr., having been first duty sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Light Company, osisers

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