ML20092N824

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Application to Amend License DPR-62,changing Tech Specs to Incorporate Revised Min Critical Power Ratio Values & Revised MAPLHGR Values for New BP8DRB299 Fuel Type.Fee Encl
ML20092N824
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 06/26/1984
From: Cutter A
CAROLINA POWER & LIGHT CO.
To: Vassallo D
Office of Nuclear Reactor Regulation
Shared Package
ML20092N825 List:
References
NLS-84-274, NUDOCS 8407050097
Download: ML20092N824 (2)


Text

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Cp&L Carolina Power & Light Company SERIAL:

NLS-84-274 JUN 2 61984 Director of Nuclear Reactor Regulation

~ Attention:

Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division o'f Licensing United States _ Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 i

DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR REVISION TO TECHNICAL SPECIFICATIONS s

FUEL CYCLE NO. 6 - RELOAD LICENSING Dea'r Mr. Vassallo:

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SUMMARY

In accordance with the Code of Federal Regulations, Title 10, Part 50.90 and Part 2.101, Carolina Power & Light Company (CP&L) hereby requests revisions to the Technical Specifications (TS) for Brunswick Steam Electric Plant Unit No. 2.

These revisions are necessary to complete the fifth refueling of Brunswick-2 and begin Cycle 6 operation.

DISCUSSION Enclosed are proposed changes to the TS that incorporate revised minimum I-critical power ratio (MCPR) values, revised maximum' average planar linear heat generation rate (MAPLHGR) values for the new BP8DRB299 fuel type, and l

inclusion of a footnote to TS 3.3.6.2, End-of-Cycle Recirculation Pump Trip

-(EOC-RPT) System Instrumentation to reflect the manual bypassing of the l

EOC-RPT system during Cycle 6 operation.

In addition, TS 5.3.1 is being revised to reflect that reload fuel has a maximum enrichment of 2.99 weight 7

percent U-235.-

Forty (40) copies of General Electric Report No. 23Al?65, Rev. 0,." Supplemental Reload Licensing Submittal for Brunswick Steam Electric Plant Unit 2, Reload 5" are attached to this letter. The enclosed Reload

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Licensing Submittal _ incorporates the results of analysis supporting the use of l

full-are admission without' Recirculation Pump Trip (EOC-RPT). The Brunswick-2 refueling outage is presently scheduled to.end on September 25, 1984.

SIGNIFICANT HAZARDS ANALYSIS-Carolina Power & Light Company has_ reviewed this request and determined that I

these proposed revisions to the Brunswick-2 Technical Specifications involve i

no significant hazards consideration because the' proposed changes do 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 fron'any accident previously evaluated, or l-(3) involve a significant reductionLin a' margin of safety. The Commission has

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8407050097 840626 PDR ADOCK 05000324

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Mr.

D.' B. Van =llo 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 consideration is a change resulting from a nuclear reactor core reloading, if no fuel assemblies significantly different from those found previously acceptable to the NRC for a previous core at the facility are involved. The enclosed changes revise the Brunswick-2 Technical Specifications to reflect the results of the reload analysis and do not involve fuel assemblies significantly different from those previously reviewed by the NRC. Therefore, CP&L believes the proposed changes fall within the Commission's example (iii) of an action not likely to involve a significant hazards consideration.

ADMINISTRATIVE INF0PMATION Enclosed are proposed Technical Specification pages for Brunswick-2 with the changes indicated by vertical lines in the right-hand margins. We have reviewed this request in accordance with the provisions of 10 CFR 170.12 and are enclosing an application fee of $150.

Should you have any questions concerning this submittal, please contact Mr. S. R. Zimmerman at (919) 836-6242.

Your ery t ly, q

A. B. Cutter - Vice President Nuclear Engineering & Licensing WRM/mf (263WRM)

Enclosures cc:

Mr. D. O. Myers (NRC-BSEP)

Mr. J. P. O'Reilly (NRC-RII)

Mr. M. Grotenhuis (NRC)

Mr. Dayne H. Brown Radiation Protection Branch Division of Facility Services Department of Human Resources A. B. Cutter, 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

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Notary'The~al) 6 My commission expires: OCT 041986 hEUn' 1/ssggggggnO