ML20247G785
| ML20247G785 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/29/1989 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19302D801 | List: |
| References | |
| NLS-89-072, NLS-89-72, NUDOCS 8904040317 | |
| Download: ML20247G785 (3) | |
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{{#Wiki_filter:_ _ - - _ _ _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ e aec P.O. Box 1551
- Raleigh. N.C. 27802 MAR 2 91989 A. B CUTTF.R Vice President SERIAL: NLS-89-072 Nuclear Services Department.
10CFR50.46 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 6 50-324/ LICENSE NOS. DPR-71 & DPR-62 SAFER /GESTR-LOCA ANALYSIS Gentlemen: Carolina Power & Light Company (CP&L) hereby submits a request for use of the SAFER /GESTR-LOCA application methodology for analysis of postulated loss of coolant accidents for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. This methodology was accepted for referencing by the NRC in a letter entitled " Acceptance for Referencing of Licensing Topical Report NEDE-23785, Revision 1, Volume III (P), 'The GESTR-LOCA and SAFER Models fer the Evaluation of the Loss-of-Coolant Accident'" on June 1,1984. contains an evaluation entitled " Brunswick Steam Electric Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-I Coolant Accident Analysis," prepared by CE Nuclear Energy. This evaluation was prepared to revise the BSEP LOCA licensing basis and update the demonstration of conformance to the criteria prot.ided in 10CFR50.46, as modified by SECY-83-472, " Emergency Core Coolant System Analysis Methods." The report includes proprietary General Electric (GE) information which should be withheld from publi; disclosure. provides the GE affidavit attesting to this fact. No changes to the bases of the Technical Specifications are required as a result of this change in n.ethodology based on the information and proposed bases changes provided in the February 20, 1989 submittal concerning the Elimination of Cycle Specific Parametere. This change in methodology is required to support use of the Maximum Extended Operating Domain (MEOD) modifications described in our March 29, 1989 submittal. In addition, the SAFER /GESTR-LOCA methodology is being used to support the upcoming Reload 8 for BSEP-2, Cycle 9 operation. Therefore, the Company requests that this methodology be approved for use at BSEP prior to issuance of the MEOD changes, but after issuance of the Elimination of Cycle Specific Parameters changes, gganseBESQg4 i i P I l L
1i h Document Control Desk l NLS-89-072 / Page 2 Please refer any questions regarding this submittal to Mr. Stephen D. Floyd at (919) 546-6901. Yours very truly, u-{4 A. B. Cutter BAB/bab (\\cor\\saferg)
Enclosures:
1. " Brunswick Steam Electric Plant Units 1 and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis" 2. Affidavit cc: Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. G. Tourigny
f -: N. l ENCLOSURE 1 l. BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 SAFER /GESTR-LOCA ANALYSIS BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 l SAFER /GESTR-LOCA LOSS OF COOLANT ACCIDENT ANALYSIS l _ _ _ _ _ -}}