ML20010A017

Technical Evaluation of Response to Position 5 of Item II.E.4.2 of NUREG-0737,Containment Isolation Setpoint for Oyster Creek Nuclear Power Plant. Setpoint Requirements Have Been Met

ML20010A017
Person / Time
Site:	Oyster Creek
Issue date:	05/31/1981
From:	Ruvalcaba W, Wade W EG&G, INC.
To:
Shared Package
ML20010A013	List: ML20010A017
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM SRO-263, NUDOCS 8108100389
Download: ML20010A017 (2)

Text

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500 Cnergy Measurements Group SP.0-263 San Ramon Operations May };g}

TECHNICAL EVALUATION OF THE RESPONSE TO POSITION NO.5 O F iTEla If. E. 4.2 OF NUREG-0737 CONTAINMENT ISOLATION SETPOINT FOR THE OYSTER CREEK NUCLEAR POWER PLANT (D O C K ET 'N O. 50-219 ')

by W. O. Wade A::c r:ee: for fuci ca:icn

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w. R. Ruvalca a Ta;artment Managcr inis cocumen; is U:iCLASSIFIED i.

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3 l-INTRODUCT,10N AND BACKGROUND' L

. ' As : a consequence of tne incident at TM1-2, implementation nf a number of new J requirements nas been recommended for operating rcactors.

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-Tnese new requirements are described in NUREG-0660, "NRC Action Plan Devel-

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oped as a Result. of ene. TMI Accident," May 1980, and NUREG-0737, "Clari-fication of TMI ~ Action-P1an Requirements,"' Novemoer 1980.

Tne NRC staff nas also requested = licensees to sucmit information sufficient _ to permit an independent evaluation' of their response to tnese new requirements.

Inis l

report provides an evaluation of tne response to Action Plan item II.E.4.2, position 5. by the designated licensee.

- DESIGN BASIS OR REVIEW CRITERIA i

Position 5 requires that tne containment. pressure se: point tnat

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t initiates containment isolation for non-essential system _ containment vessel i

penetrations :ce at, or reduced to, "...tn'e minimum compatiole witn normal l,,

operating conditions."

TECHNICAL EVALVATION I

Response evaluation is tased upon the values provicea _ for tne

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following parameters:

l-l (1)

The maximum _ obser_ved or expected containment pressure 1

during normal operation.

l (2)

The loop error and caserved drift in tne pressure sensing instrumentation providing :ne isolation signal l

(see ncte).

(3) ine containment 1sela.icn cressure se:::o n.

!:DTE : Tne clarification cocument- (NUREG-0737) provided only

ne exoected margin for instrument error and did not specify acceptable values for instrument drift or atmospnaric cnan'ges contributing to ne total sensing loop errer.

Additional staff guicence estaclisne: a l

ilmi: of 3.0 psi for an isola:icn se: point. margin over

ne normal containment pressure to account for total l

loco error.

In accition, for suoatmospneric contain-l ments, a 3.0 psi setpoint margin.over atmospneric L

pressure is also considered acceptable.

- In consideration of tnese values, tne isolation pressure se: point is to-be as low as practical witnout increasing tne procacility of inadver-l tent activation of tne isolation signal.

j CONCLUSIONS i

Tne. letter. of February 10, 1981, submitted by Jersey Central -

Power and Lignt Company, provided sufficient information to concluce tnat tne containment isolation pressure se point for Oyster Creek Nuclear Powar Plant meets tne NUREG-0660/0737 requirements and is wi:nin tne addnional-limiting guidelines provided oy tne MC staff.

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