ML20207E475

Forwards Amend 88 to License DPR-61 & Safety Evaluation. Amend Would Establish Plant Configuration Which Assures That Adequate Cooling Will Be Maintained During Sump Recirculation,Satisfying Single Failure Requirement

ML20207E475
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/24/1986
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:	Opeka J CONNECTICUT YANKEE ATOMIC POWER CO.
Shared Package
ML20207E479	List: ML20207E475 ML20207E504 ML20207E514
References
NUDOCS 8701020188
Download: ML20207E475 (2)

Text

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o- , December 24, 1986 Docket No. 50-213 DISTRIBUTION N OGC-Bethesda NRC PDR ELJordan Mr. John F. Opeka, Senior Vice President Local PDR BGrimes Nuclear Engineering and Operations ISAP Reading JPartlow Connecticut Yankee Atomic Power Company NSIC ACRS (10)

P.O. Box 270 RDiggs TBarnhart(4)

Hartford, Connecticut 06141-0270 FMiraglia LJHarmon FAkstulewicz WRegan

Dear Mr. Opeka:

FAnderson WJones.

OELD CMiles, OPA

SUBJECT:

REVISION TO TECHNICAL SPECIFICATION - MBoyle AWang REPOSITIONING FLOW CONTROL VALVE - RH-FCV-796 IN THE RESIDUAL HEAT REMOVAL SYSTEM Re: Haddam Neck Plant The Commission has issued the enclosed Amendment No. 88 to Facility

. Operating License No. DPR-61 for the Haddam Neck Plant. This amendment is in response to your application dated December 17, 1986, as supple-mented December 19, 1986.

The amendment would establish a plant configuration which assures that adequate cooling will be maintained during sump recirculation while satis-fying single failure requirements. That configuration involves reposi-tioning and locking flow control valve RH-FCV-796 in the Residual Heat Removal (RHR) system in the partially open position and initiating, under prescribed conditions, charging system flow to assure proper flow distribution and pump operability in the event the specific break at issue were to occur.

The staff has reviewed the circumstances associated with your request and has concluded that this change is needed to avoid the requirement to derate or shutdown. Therefore, in accordance with 10 CFR 50.91(a)(5), justification for the issuance of an emergency technical specification existed.

A Notice of Consideration of Issuance of Amendment to License will be included in the Comission's biweekly Federal Register notices. A copy of our related Safety Evaluation is enclosed.

. Sincerely, I

(original signed by) 8701020188 861224 PDR ADOCK 05000213 Christopher I. Grimes, Director P PDR Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Enclosures:

, 1. Amendment No. 88 to License No. DPR-61

2. Safety Evaluation *See previous concurrence sheet DPLB-EB* DPLB:AD*

cc w/ enclosures: LMarsh DCrutchfield l See next page 12/23/86 12/23/86

DPL-B

ISAP* DPL-B:ISAP* DPL-8:ISAP* OGg thesda DPLB-PSB*

i FAkstulewicz:dj PAnderson CGrimes 6 4 CThomas 12/23/86 12/23/86 12/23/86 y/ 86 12/23/86

- p Docket No. 50-213 DISTRIBUTION Docket File OGC-Bethesda NRC PDR ELJordan Mr. John F. Opeka, Senior Vice President Local PDR BGrimes Nuclear Engineering and Operations ISAP Reading JPartlow Connecticut Yankee Atomic Power Company NSIC ACRS (10)

P.O. Box 270 RDiggs TBarnhart (4)

Hartford, Connecticut 06141-0270 FMiraglia LJHannon FAkstulewicz WRegan

Dear Mr. Opeka:

PAnderson WJones OELD CMiles, OPA

SUBJECT:

REVISION TO TECHNICAL SPECIFICATION - MBoyle AWang REPOSITIONING FLOW CONTROL VALVE - RH-FCV-796 IN THE RESIDUAL HEAT REMOVAL SYSTEM Re: Haddam Neck Plant The Commission has issued the enclosed Amendment No. 88 to Facility Operating License No. DPR-61 for the Haddam Neck Plant. This amendment is in response to your application dated December 17, 1986, as sunple-mented December 19, 1986.

The amedment would establish a plant configuration which assures that adequate cooling will be maintained during sump recirculation while satis-fying single failure requirements. That configuration involves reposi-tioning and locking flow control valve RH-FCV-796 in the Residual Heat Removal (RHR) system in the partially open position and initiating, under prescribed conditions, charging system flow to assure proper flow distribution and pump operability in the event the specific break at issue were to occur.

The staff has reviewed the circumrtances associated with your request and has concluded that this change is needed to avoid the requirement to derate or shutdown. Therefore, in accordance with 10 CFR 50.91(a)(5), justification for the issuance of an emergency technical specification existed.

A Notice of Consideration of Issuance of Amendment to License will be included in the Commission's biweekly Federal Register notices. A copy of our related Safety Evaluation is enclosed.

Sincerely, Christopher I. Grimes, Director Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Enclosures:

1. Amendment No. 88 to License No. DPR-61

2. Safety Evaluation DPLB-EB DP cc w/ enclosures: LMarsh DC ield See next pace~ 12 />3/86 ;2/2$/86 dk (2C iC07 DPL-B:ISA h DPL-B:IS

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