ML19332C762

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Safety Evaluation Supporting Amend 73 to License DPR-66
ML19332C762
Person / Time
Site: Beaver Valley
Issue date: 10/17/1983
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19332C743 List:
References
NUDOCS 8911280519
Download: ML19332C762 (5)


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UNITED STATES

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SAFETY-EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 73 TO FACILITY OPERATING LICENSE N0. DPR-66 DUQUESNE LIGriT CUMPANT OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY

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BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-334 l

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INTRODUCTION-In_a letter dated December 16, 1982, Ducuesne Light Proposed Change-Request

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No.75 to. the Operating License of Beaver Valley Powr Station, Unit No.1.

The request proposed to reduce the number of thimbles required by the Technical Specifications _to 50% from 75% for the incere movable detector system to be l

- operabl e.

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The licensee provided documentation in letters dated January 4,1983 and 1

February 24, 1983 supporting an increase of the movable incore detector map measurement uncertainty as part of the change request.

By Amendmant No. 61 dated January 19, 1983, we provided interim approval of the proposed-Technical L

i Specification change request for the remainder of the then operating Cycle 3.

l Our intention was to complete the review of the subject report.

EVALUATION Essentially all PWR Technical Specifications contain a requirement for oper-ability of 75% of the incore detector locations for periodic mapping of the core power distribution.

On a number of occasions, for various reasons, 8911280519 831017 ADOCK 0500g4 DR iW

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s failures in operating PWRs' have approached or exceeded 25%, and relaxation of g ~

--the 75% requirement has been permitted for the duration of affected reactor cycles.. This has generally been allowed either with increased surveillance of some sort (such as increased. frequency of mapping) or, as in the case of the'-

interim approval 6f this change for Cycle 3 of Beaver Valley Unit 1, when there is substantial. margin to Technical Specification oeaking factor. limits.

We advocate maintenance of as cipse to 200% operability of the incere cetector system as is possible. We believe that : is is reouired to be able to

'icentify and evaluate possible power' distribution or reactivity anomalies wnich might-occur during the operation of power plants.

An example is the.

burnable poison rod leaching problem that occurred in St. Lucie I where the

-incere instrumentation was essent.ial in identifying and understanding the Oreblem.

The -75% operability _ requirenent was chosen to allow a reasontbie amount of f ailures of the intore. detectors, but to encourage the licensees te strive for as near to 100% as possible.

Pem.anent Technical Specification changes te reduce _the number to 50% might result in e' lack of incentive to keep the system eperating as close to 100f as possible.

This could result in an unacceptably degraded ability to detect anomalous conditions in the cgre.

Wc therefore concluoe that a pemanent change of the Beaver Valley Unit 1 l

Technical Specifications to allow operation with up to 50% of the incore detector thimbles failed is not acceptable.

In the event that the operability reevirement of 75% cannot be met during a cycle, we will consicer l;

intrim Technical Specifications for the remainder of a cycle, as has been L

d::ne before.

Consideration would be given to available resulting marcin from reduction of operating peaking factors with cycle burnu:, application of additional measurement uncertainties, and more frequent incore maccing, 1

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Environmental Consideration i

i Wo. have detemined tnat the-amendment does not authorize a change in i

L effluent types or total _ amounts nor an increase in power level and will not result in any significant. environmental impact.

Having made this detemination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of l

environmental impact and, pursuant to 10 CFR {51.5(d)(4), that an environmental impact statement or negative decla-ation and environ-

' mental impact acoraisal need not-be prepared in connection with the issuance.of.this amendment.

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~ Conclusion We-have concluded,-based on-the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the O

public will not be endangered by operation in the proposed manner, and-

-(2) such activities will be' conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical 2

to the common defense and security or to the health -and safety. of the public.

Date: October 17,1983 Principal Contributor:

M. Dunenfeld

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AMENDMENT' ROUTE SLIP

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Assist irector - concurrenc'e [0 ELD review af/is not requeste for eine the enclosed Safety Evaluation f

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Licensing. Assistant - assig[Amendmer 'Io.A and data / /d-[--8 Q 9.

Secretary - dispatch V

l Letter to:- (Plant Namel omA7 8%

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[~TMf4WS SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION INFORMATION Initial Determination: Significant Hazards Considerationconsioerations(Circle one)

Cno signiricant nauros 9[24[tg(Date)

Notice Period 6/)

Days.

Com er.t period expires l

If less than 30 days or hearing request received, Final No Significant Hazards Consideration Determination enclosed: Yes

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E Emergency or Exigency

.M/d Input for Monthly FR Notice Enclosed:h5 No

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Date Consulted withAtate:

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.Date checked w/SECY fpr public comments cr Petitions for Le to Intervene:

9/27'/fB Petitiens Filed:

Yes 40

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Comments Filed:

Yes

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Remarks :

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4--1o-11-19 12 NRC FEE DETERMINATON

' I The above application has been rev6ewed in accordance oth Section 170.22 of Part 170 and is property categorized.

The above application has been reviewed in accordance with Section 170.22 of Part 170 and is incorrectly classified.

Fee shoutd be class (es):

JUSTIFICATION FOR CLASSIFICATON OR RECL AS$1FICATON Aw ht Ys, A dvA a

(t J This application 6s a Class type of action and is exempt from fees because it is:

Fifed by a nonprofit educational institution.

Filed by a Government agency and is not for a power reactor.

For a Class 1.16. or til amendment which resu'ts from en NRC request dated for tne application and the amendment is to simplify or clarlfy Llcense or Technical Specifications. has only minor safety significance; and is being issued for the convenience of NRC (must meet all of the Criterial l I Oiner<s,a,e reason,nere,or, l

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