ML20010C955

Application for Amend Changing Emergency Tech Specs for Single Loop Operation Per 810811 Discussion.Change Would Allow Operation Up to 50% of Rated Thermal Power W/One Recirculation Loop Out of Svc

ML20010C955
Person / Time
Site:	Brunswick
Issue date:	08/12/1981
From:	Utley E CAROLINA POWER & LIGHT CO.
To:	Ippolito T Office of Nuclear Reactor Regulation
Shared Package
ML20010C956	List: ML20010C955 ML20010C958
References
NO-81-1339, NUDOCS 8108210268
Download: ML20010C955 (2)

Text

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li( **.*g FILE: NG-3514(B) Serial No.: "0-81-1339 Of fice of Nuclear Reactor Regulation ATTENTION: Mr. T. A. Ippolito, Chief Opera tirs; Reactors Branch No. 2 l'alted States Nuclear Regulatory Commission Washington, D. C. 20555 BRUNSWICK STEAM ELECTRIC PLANT UNIT NO. 2 DOCKET NO. 50-324 LICENSE NO. DPR-62

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REQUEST FOR EMERGENCY TECHNICAL SPECIFICATION CHANGE

! SINGLE LOOP OPERATION

Dear Mr. Ippolito:

4 Summary f

j The purpose of this letter la to formally request an emergency

Technical Specification change request which was discussed with the NRC Staf f on August 11, 1981. The requested changes would allow operation up to 50% of 4

rated thermal power with one recirculation loop out of service on the Brunswick Steam Llectric Plant Unit No. 2.

Formal Request i

1 Therefore, in accordance. with the Code of Federal Regulations, Title 10, Section 50.90 and Section 2.101, Carolina Power & Light Company 1 (CP&L) hereby requests revisions to the Technical Specifications for its

) Brunswick Steam Electric Plant Unit No. 2.

Attached 5au will find the revised Technical Specification pages with the changes indicated by a vertical line in the right hand column. We have determined that these changes involve a single technical issue, and we //

jNj caelose a check for $4000 for one Class III amendment in accordance with #

10CFR170.22. j Evaluation W/cde+II 2

l General Electric has previously performed a safety evaluation for/ yooo.ou operation with one recirculation loop out of service for a similar plant (refer to the letter from Larry D. Root (DAEC) to Harold Denton (NRC) dated May 2, 1980, letter LDR-80-127) and has determined that this mode of operation 8102210268 810812 --r~ -- ' - -

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is applicable to Brur.swick Unit No. 2 with appropriate Technical Specification

hanges.

In addition, on Kirch 13, 1981, CP&L requested a lice..se amendment to allow temporary single loop operation on Brunswick Unit No. 1. This submittal included justifications and analyses supporting singin loop operation. NRC concurred with this information in the Safety Evaluation for Amendment No. 35 to License No. DPR-71 (reference date - March 27, 1981).

Although the package attached to this letter 10 specific to Brunswick Unit No. 2 in certain areas, the analyses are identical to those that CP&L submitted to NRC on March 13, 1981 for Brunswick Unit No. 1.

Concurrence This Technical Specification change request and its safety justifications have been reviewed and concurred with by both the on-site safety review group (Plant Nuclear Safety Committee) and the of f-site safety review group (Corporate Nuclear Safety Unit).

Canclusion CP&L requests that NRC consider the review of this change to Technical Specifications and issuance of the license amendment on an emergency basis in order to maintain Brunswick Unit No. 2 in service. Technical justifications and analyses are provided in the attached pr.ckage which indicate that there is no significant decrease in safety margin and that it does not involve a significant increase in the probability or consequences of accidents previously considered.

Should you have any questions regarding this matter, please contact my staff.

Yours very truly,

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GW Ef E. Utley Executive Vice President Power Supply and Engineering & Construction JAM /1r ( NRC#7)

Attachments Sworn to and subscribed before me this 12th day of August, 1981.

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Notary Public My commission expires: .

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