ML20087J723

Application for Amend to License DPR-71,changing Tech Spec Description of Reactor Core Fuel Assemblies

ML20087J723
Person / Time
Site:	Brunswick
Issue date:	01/31/1984
From:	Howe P CAROLINA POWER & LIGHT CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20087J726	List: ML20087J723 ML20087J733
References
NUDOCS 8403230049
Download: ML20087J723 (2)

Text

I Cp&L l Carolina Power & !.lght Company JAN 311984 Director of Nuclear Reactor Regulation l Attention: Mr. D. B. Vassallo, Chief l Operating Reactors Branch "o. 2 Division of Licensing

-United States Nuclear Regulatorf Conmission Washington, DC 20555 BRUNSWICK STEA!! ELECTRIC PLANT, UNIT NO. I DOCKET NOS. 50-325 LICENSE NOS. UPR-71 REQUEST FOR LICENSE AMENDMLNT REACTOR CORE-FUEL ASSEMBLIES

Dear Mr. Vassallo:

Summary In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to the Technical Specifications (TS) for the Brunswick Steam Electric Plant, Unit No. 1. The proposed TS change requests a change in the description of the fuel assemblies listed in Section 5, Design Features.

Discussion Technical Specification 5.3.1 specifies that the Unit I reload fuel assemblies shall have a fuel enrichment maximum of 2.85 weight percent of U-235. This weight percent represents early predicted reload enrichments. Due to longer cycles and the new core configuration, a higher enrichment reload fuel is required. The reload analysis for the completion of the third refueling of the Brunswick Steam Electric Plant, Unit No. 1 (BSEP-1) was submittcd to the NRC on May 2,1983 and subsequently approved on June 28, 1983. During the third refueling some higher enrichment fuel (>2.85 weight percent) was let.ded into the core and any safety concerns related to the hagher enrichments were addressed in the reload analysis. Therefore, in order to correctly reflect the enrichment level used in the reload analysis, CP&L is requesting that an enrichment level of 3 weight percent be inserted into Technical Specification 5.3.1.

$0! In addition, CP&L has rewritten section 5.3.1 to conform with the GE BWR/4 CIM' Standard Technical Specification. Reformating of section 5.3.1 for BSEP-2 O will be submitted with the relced analysis for the next refueling of U nit 2.

mn g[3 Significant Hazards Analysis e:s o0 Carolina Power & Light Company has reviewed this request and determined that fj$ the proposed revision to section 5.3.1 of the Brunswick-1 Technical Qg Specification involves no significant hazards consideration because the ec S Q.tL 411 Fayetteville Street

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4 Mr. D. B. Vassallo i p oposed change does not (1) involve an increase in the probability or consequences of an accident previously evaluated,-(2) create the pessibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a reduction in a margin of safety. The Commission has provided guidance concerning the application of its standards set forth in 10 CFR 50.92 for no significant hazards considerations by providing certain examples published in the Federal Register on April 6, 1983 (48FR14864). One of.the examples of an amendment which will likely be found to involve no significant hazards considerations: for example, a change to achieve consistency throughout the technical specifications, correcti6n of an etcor, or a change in nomenclature. The proposed revision to section 5.3.1 will eake the BSEP-1 Technical Specifications consistent with the already approved reload analysis and the GE BWR/4 Standa-d Technical Specification and is, therefore, administrative in nature.

Administrative Information Attachment 1 provider- the proposed revision to section 5.3.1 of the BSEP-1 Technical Specification (CP&L P.ef. #83TSB36). In accordance with 10 CFR 170.22, CP&L has determined that this request is administrative in nature and thus constitutes one Class II license amendment request. A check for $1,200 is enclosed in payment of the required fee.

Yours very truly, I /

Q . u;.yh P. W. Howe Vice President i

Brunswick Nuclear Project PPC/ lev (8046PPC)

Attachment P. - W. Howe, having been first duly sworn, did depot.e 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 of ficers, employees, contractors, and agents of Carolina Power & Light Company, b k1sch 'iYass '

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1 cc, Mr. D. O. Myers (WRC-BSEP) l Mr. J. P. O'Reilly (NRC-RII). j Mr. M. Grotenhuis-(NRC) 'l Mr. D. H. Brown

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