ML20209B416

Forwards Safety Evaluation & SALP Input Accepting Util 870128 Request for Tech Spec Changes Re Drywell Leakage Test Interval,Provided That Util Revise Tech Specs to Ref Testing During Each Refueling Outage.W/O SALP Input

ML20209B416
Person / Time
Site:	River Bend
Issue date:	04/22/1987
From:	Jocelyn Craig Office of Nuclear Reactor Regulation
To:	Calvo J Office of Nuclear Reactor Regulation
Shared Package
ML20209B420	List: ML20209B416 ML20209B429
References
TAC-64855, NUDOCS 8704280431
Download: ML20209B416 (2)

Text

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UNITED STATES g NUCLEAR REGULATORY COMMISSION

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\ / April 22, 19&7 Docket No.: 50-458 MEMORANDUM FOR: Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects FROM: John W. Craig, Acting Chief Plant Systems Branch Division of Engineering and Systems Technology

SUBJECT:

SAFETY EVALUATION OF PROPOSED TECHNICAL SPECIFICATION '

CHANGES FOR RIVER BEND STATION UNIT 1 (TAC NO. 64855)

In accordance with TAC request No. 64855, the Plant Systems Branch has completed its review of the proposed River Bend Station Unit 1 Technical Specification (TS) change for the drywell leakage test interval. The change was requested in Gulf States Utilities (GSU) letter dated January 28, 1987 The requested change is a deletion of Specification 4.6.2.2.b. Through this deletion, the licensee would be able to invoke Specification 4.0.2 in determining the test interval.

In effect, for an individual test, the licensee could then extend the interval by as much as 25% from the nominal test interval. This extension is not expected to increase the nominal test interval since the licensee must still show that the combined interval for three consecutive intervals will not exceed 3.25 times the surveillance interval.

Without the requested change, a station outage in April 1987 will result to specifically perform this test. By invoking the 25% time extension, the revised scheduled test would then more or less coincide with the next planned refueling outage in August 1987. Based on a review of the provided justifica-tion for the proposed change, PSB finds that GSU has adequately supported the requested TS change. Therefore, Plant Systems Branch (PSB) finds the proposed change, as identified in the enclosed Safety Evaluation, acceptable.

However, although the proposed TS change will eliminate the need to perform the drywell leakage test in April 1987, GSU may have a need to obtain additional relief from the revised specification sometime in the future. The staff's reouirement is to test during each refueling outage. The licensee, however, has maintained an absolute time within the TS. Therefore, it is ccnceivable that with an extended fuel cycle, the maximum allowed time interval could be exceeded. As a result, it is our recommendation that GSU consider revising 8704280431 870422 i PDR ADOCK 05000458 P PDR

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-2 this Specification sometime in the future to reference testing during each refueling outage rather than maintaining the reference to an absolute time limit.

Also provided, as Enclosure 2, is our S Oputfor his effort.

ohn W. Craig, Acting Chief Plant Systems Branch

. Division of Engineering and Systems Technology

Enclosures:

As stated cc w/ enclosures:

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