ML20042A962

Operating Reactor Power Operated Relief Valves & ECCS Repts, Request for Addl Info

ML20042A962
Person / Time
Site:	Vermont Yankee
Issue date:	02/11/1982
From:	Overbeck G FRANKLIN INSTITUTE
To:	Chow E NRC
Shared Package
ML20042A959	List: ML20042A962
References
CON-NRC-03-81-130, CON-NRC-3-81-130 NUDOCS 8203240337
Download: ML20042A962 (4)

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S REQUEST FOR ADDITIONAL INFORMATION OPERATING REACTOR PORV AND ECCS REPORTS TMl ACTION PLAN REQUIREMENTS VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION NRC OOCKET NO. 50-271 FRC PROJECT C5506 FRC ASSIGNMENT 7 NRC CONTR ACT NO. NRC-03-81 130 FRC TASK 228 Preparedby Franklin Research Center Author: G. J. Overbeck The Parkway at Twentieth Street Philadelphia, PA 19103 FRC Group Leader: 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 evaluation of the information contained in the Vermont Yankee Nuclear Power Corporation (VYNPC) letter dated December 2, 1980 [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 document represents the only Licensee submittal received and available for review at Franklin Research Center (FRC). Preliminary

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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 that each licensee submit a report detailing dates, lengths, and causes of outages for 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 unavailability of the ECC systems to help the NRC determine if cumulative outage limitations are required 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 durations, (2) causes, including test and maintenance, (3) ECC systems or components involved, and (4) corrective actions taken. In addition, each licensee was to propose changes to improve the availability. of ECC system equipment, if necessary.

VYNPC responded to this request in a letter to the NRC dated December 2, 19'80 [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 O

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a licensee event report (LER). A report is not required for planned outages or unavailability for periodic or preventive maintenance and testing.

The technical specifications permit several components of the ECC systems to have substantial outage times. In addition, there are no cumulative outage limitations for ECC systems. 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, fer 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 trains affected by the outages. Outages for surveillance testing and for planned, unplanned, and preventive maintenance should also be reported. 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 does not appear to include test and preventive maintenance outages which contribute to cumulative ECC system unavailability. VYNPC's response incluoed the cause of equipment malfut.0tions; however, insufficient detail was provided to determine whether or not the outage was discovered

- ouring testing and preventive maintenance activities. The VYNPC response does not provide sufficient information to satisfy the objective of NUREG-0737, Item II.K.3.17.

REQUEST To enable the staff to continue its review of VYNPC's response to NUREG-0737, Item II.K.3.17, additional information is required.

o A complete summary of each outage for surveillance testing and preventive maintenance for the 5 years of operation through 1980.

For each outage, include the date and duration and the ECC or diesel generator system, train, and component involved.

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Letter to Office of Nuclear Reactor Regulation

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Response to NUREG-0737 Item II.K.3.17 l

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December 2, 1980

2. NUREG-0737

" Clarification of TMI Action Plan Requirements" NRC, November 1980

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