ML20206U255

Safety Evaluation Supporting Amend 187 to License DPR-64

ML20206U255
Person / Time
Site:	Indian Point
Issue date:	02/09/1999
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML100361062	List: ML20206U255
References
NUDOCS 9902120265
Download: ML20206U255 (3)

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g NUCLEAR REGULATORY COMMISSION i

A" WASHINGTON, D.C. 2066H001

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 187 TO FACILITY OPERATING LICENSE NO. DPR-64 POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286

1.0 INTRODUCTION

By letter dated April 16,1998, The Power Authority of the State of New York proposed changes to Indian Point 3 (IP3) Technical Specifications (TSs) 3.7.B.1 to modify a testing requirement fer the emergency diesel generators (EDGs). The current TSs require that whenever an EDG becomes inoperable for any reason other than preplanned preventive maintenance or testing, the remaining EDGs must be tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The proposed change will allow an evaluation for potential common-cause failures to be used as an attemative to testing. Changes to the TSs Bases are also proposed to explain this altemative to testing.

2.0 EVALUATION The licensee proposed the following changes to the TSs:

Specification 3.7.B.1 currently states in part:

" lf the inoperable diesel generator became inoperable due to any cause other than preplanned preventive maintenance or testing, the remaining diesel generators shall be tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />."

The proposed change is:

"...lf the ope:able diesel generator became inoperable due to any cause other than preplanned maintenance or testing, then within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, either a.

Determine by evaluation, that the remaining operable diesel generators are not l

inoperable due to common-cause failure.

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. b.

Verify by testing, that the remaining diesel generators are operable.

There are three EDGs at IP3 designed to provide a source of power to support a safe and orderly plant shutdown in the event of a loss-of-offsite power. Any two of the three EDGs are capable of supplying the minimum power requirements for emergency safeguard equipment that mitigate the consequences of postulated accidents.

Currently, the IP3 TSs require that whenever an EDG becomes inoperable, the remaining operable EDGs must be tested only once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The proposed change will require testing of the remaining EDGs based on common-cause failure consideration. If an evaluation, conducted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of finding an inoperable EDG, concludes that the I

remaining EDGs are not inoperable due to a common-cause failure, then testing of those l

EDGs is not required. If the evaluation conducted does identify a common-cause failure, then l

one or both of the remaining affected EDGs, as appropriate, must be declared inoperable and l-the specified required actions must be taken. If the evaluation is inconclusive regarding i

common-cause failure, then testing of the remaining EDGs (within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of finding the j

inoperable EDG) suffices to provide assurance of continued operability of those EDGs.

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Based on the above, the staff concludes that the proposed change reduces unnecessary testing of EDGs as recommended by Generic Letter 84-15 and is consistent with the improved l

Standard Technical Specification. Therefore, the staff finds the proposed change to be

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acceptable.

3.0 STATE CONSULTATION

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in accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The state official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

l The amendment changes a requirement with respect to installation or use of a facility L

component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has l'

determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (63 FR 56256). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmentalimpact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

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5.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

j Principal Contributor: O. Chopra Date: February 9, 1999 i

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