ML20086R862
| ML20086R862 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/19/1991 |
| From: | Vaughn G CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-86-10, GL-88-12, NLS-91-327, TAC-M79416, TAC-M79417, NUDOCS 9201020273 | |
| Download: ML20086R862 (4) | |
Text
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4 Carolins li ter & Light Company c o Don isst e smose N C #7W Sf RI Al : fJl S 91327 DEC 191991 10 CrR 50.90 1 SC 87 i Sl104 0 E VAUGHN vite cres.oent Nuclear ser ices Departrnent v
United States Nuclear Regulatory Commission ATTENTION: Document Controf Desk Washington, DC 20555 BRUNSWlCK STLAM LLLCTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS.50-32b & 50 324/LICLNSL NOS DPR.716 DPR 02 SUPPLCMINT TO REQUEST FOR LICENSE AMENDMLNT FIRE PRO ~lECTION 1r.CitNICM SPI CITICAllONS AND llCU6l CONDITION (NRC TAC NOS. M79410 AND M79417)
Gentlemen:
The purpose of this letter is to supploment the significant hazards analysis provided in CP&L's January 4,1991 lirerdi amendment application for the Brunswick Steam llectnc Plant, Units 1 and 2.
By letter dated January 4,1991 (NLS 90 237), Carchna Power & light Cornpany requested a revision to the Operating licenses and Technical Specifications for the brunswick Steam flectric Plant, Units 1 and 2. The proposed changes would replace the current hcense condition regarding fire protection with a standard hconse conditinn and delete the associated Technical Specifications in accordance with NRC Generic letters 8010 and 8012. This application was supplemented by letter dated June 24,1991 (NL S 91085) to provide the specific wording for thn replacement Operating License pages and to add a new Technical Specification requirement (proposed Technical Specification 6.5.3.8.m).
In accordance with 10 CFR 50.91(a), Enclosure 1 details the basis for the Company's determination that the new Technicrl Specification 6.5.3 8.m requirement does not involve a significant hatards consideration.
Please refer any questions reg irding this submittal to Mr. W. R. Murray at (919) 540 4061.
Yours very truly,
,G.
y-G. E, Vaughn WRM/wrm ('p-s2.wpf)
Enclosures:
1.
10 CFR 50.92 Evaluation
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Mr. R. L. Prevatte G. E. Vaughn, having been first duly 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.
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ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50 325 & 50 324 OPERATING LICENSE NOS DPR 71 & DPR 02 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT FIRE PROTECTION TECHNICAL SPECIFICATIONS AND LICENSE CONDITION (NRC TAC NOS, M79410 AND M79417) 1_0 CFR 50 92 EVALUATION l
The Commission has provided standards in 10 CFR 50.32(c) for determining whether a significant harards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards consideration _if operation of the f acility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
Pursuant to 10 CFR 50.91(a)(1), Carolina Power & Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards consideration. The bases for this determination are as follows:
PLgnggd Chinae Noc 5:
Add 's new requirement to Technical Specification 6.5.3.8 for the Plant Nuclear Safety Committee (PNSC) to review changes to the Fire Protection Program and implementing procedures and submit any changes approved by the PNSC to the Nuclear Assessment Department for review.
' Snig:
The change does not involve a significant hazards consideration for the following reasons:
1.
The proposed change requires the additional review by the PNSC and the NAD of future changes to the Fire Protection Program and implementing procedures. The change is a new Technical Specification requirement that is consistent with the renuirements of NRC Generic
' Letters 8610 and 8812. The proposed change is an administrative control that does not physically alter the facility in any manner and, as such, does not affect the medes by which any safety-related system performs its intended safew function. As such, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. As stated in item 1 above, the proposed change requires the additional review by the PNSC and the NAD of future changes to the Fire Protection Program and implementing procedures. As such; the proposed change does not involve physical alterations of the plant c,nfiguration or changes in setpoints or operating parameters. The proposed change adds a new requirement to Tarbnical Specification 6.5.3.8 which is administrative in nature.
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The proposed change does not involve a significant reduction in the margin of safety. Ihr proposed change requires the additional review by the PNSC and the NAD of future changes to the Fire Protection Program and implementing procedures. Future changes to the Fire Protection Program and the associated implernenung procedures will be subject to controlled review in accordance with both the requirements of Section G of the Technical Specifications and in accordance the existing teovirements of 10 CFR 60.59. Therefore.
the proposed change does not involve a significant reduction in the margin of safety.
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