ML20042B220

Operating Reactor Power Operated Relief Valve & ECCS Repts.

ML20042B220
Person / Time
Site:	FitzPatrick
Issue date:	02/19/1982
From:	Overbeck G FRANKLIN INSTITUTE
To:	Chow E NRC
Shared Package
ML20042B219	List: ML20042B220
References
CON-NRC-03-81-130, CON-NRC-3-81-130, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.17, TASK-TM NUDOCS 8203250107
Download: ML20042B220 (4)

Text

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REQUEST FOR ADDITIONAL INFORMATION OPERATING REACTOR PORV AND ECCS REPORTS TMl ACTION PLAN REQUIREMENTS POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT NRC DOCKET NO. 50-333 FRC PROJECT C5506 FRC ASSIGNMENT 7 N RC CONTRACT NO. NRC-03-81-130 FRC TASK 187 Prepared by Franklin Research Center Author: G. J. Overbeck The Parkway at Twentieth Street Philadelphia, PA 19103 FRC Group L eader: G. J. Overbeck Prepared for Nuclear Regulatory Commission Washington, D.C. 20555 Lead NRC Engineer: E. Chow February 19, 1982 )

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INTRODUCTION This Request for Additional Information (RFI) is the result of an e.aluation or the information contained in the Power Authority of the State of New York (PASNY) letter dated January 8, 1981 (1] to the Nuclear Regulatory Commission (NRC) in response to NUREG-0737, Item II.K.3.17, " Report on Outages of Emergency Core-Cooling Systems Licensee Report and Proposed Technical Specification Changes" (2). The referenced documents represent the only Licensee submittal received and available for review at Franklin Research Center (FRC). Preliminary evaluation revealed that additional information is needed before a final evaluation can be accomplished.

BACKGROUND In NUREG-0737, Item II.K.3.17, the NRC requested u.at each licensee submit a report detailing dates, lengths, and causes of outages fo'r all emergency core cooling (ECC) systems for the 5 years of plant operation through 1980.

The purpose of the request was to obtain a quantitative history of the unavail-ability of the ECC systems to help the NRC determine if the need exists for cumulative outage requirements in technical specifications.

To clarify the issue, the report was to contain the following details on outages that occurred during the 5 years of plant operation through 1980: (1) dates and duration; (2) causes, including test and preventive maintenance; (3)

ECC systems or components involved; and (4) corrective actions taken. In adoition, each licensee was to propose changes to improve the availability of ECC system equipment, if necessary.

PASNY responded to this request in a letter to the NRC dated January 8, 1981 (1].

CONCERN An ECC system unavailability or outage is one of two kinds, either unplanned or planned. Any unplanned or forced unavailability is reportable as

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e' a licensee event report (LER). A report is not required for planned outages or unavailability for periodic maintenance and testing. The technical specifications permit several components of the ECC systems to have substantial outaae times. In addition, there are no cumulative outage limitations for ECC systens. Thus, the unavailability of an ECC system train for extended periods is not precluded.

For an evaluation of the responses to NUREG-0737, Item II.K.3.17, to be meaningful and to produce significant conclusions, the responses must be complete and accurate. They must include, for the 5 years of plant operation through 1980, not only the outage dates, durations, and causes, ECC system equipment involved, and corrective actions taken, but also outages of the diesel generators and identification of the ECC system train affected by the outages. The response should be based on a review of reportable occurrences, preventive maintenance, and surveillance testing. This information will be used to determine the cumulative outage time of each ECC system train per reactor year and the need for cumulative outage limitations in the technical specifications.

Reference 1 lists only outages associated with LERs and does not appear to include preventive maintenance or surveillance testing outages. Further, PASNY has provided outage duration information for only approximately 50% of the outages listed. The PASNY response does not provide sufficient information to satisfy the objective of NUREG-0737, Item II.K.3.17.

REQUEST In order for the staff to continue its review of PASNY's response to NUREG-0737, Item II.K.3.17, the following additional information is required:

o A complete summary of each ECC and diesel generator system outage for the past 5 years through 1980. For each outage, include the date, duration or estimate of duration, cause, ECC or diesel generator system, train, and component involved, and the corrective action taken. Ensure that outages for surveillance testing and planned, unplanned, or preventive maintenance are included.

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REFERENCES

1. J. P. Bayne (PASNY) i T. A. Ippolito (NRC)

Subject:

Post-TMI Requirements (

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2. NUREG-0737  ;

1 " Clarifications of TMI Action Plan Requirements"

NRC, November 1980 1

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