ML20054G536
| ML20054G536 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/15/1982 |
| From: | Overbeck G, Vosbury F FRANKLIN INSTITUTE |
| To: | Chow E NRC |
| Shared Package | |
| ML20054G537 | List: |
| References | |
| CON-NRC-03-80-130, CON-NRC-3-80-130, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.17, TASK-TM RAI-C5506-274, NUDOCS 8206210671 | |
| Download: ML20054G536 (5) | |
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REQUEST FOR ADDITIONAL INFORMATION ECCS REPORTS (F-47) i TMI ACTION PLAN REQUIREMENTS ALABAMA POWER COMPANY J. M. FARLEY NUCLEAR PLANT UNIT 1 NRC DOCKET NO. 50-348 FRC PROJECT C5506 FRC ASSIGNMENT 7 N RC CONTR ACT NO. NRC-03-81 130 FRC TASK 274 J
Prepared by Franklin Research Center Author: F. Vosbury 20th and Race Street Philadelphia, PA 19103 FRC Group Leader: G. Overbeck Prepared far Nuclear Regulatory Commission Lead NRC Engineer: E. Chow Washington, D.C. 20555 June 15, 1982 l
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This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor
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ar.y agenty thereof, or any of their employees, makes any warranty, ex-pressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any informat on, apparatus,'
product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.
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A Division of The Franklin Institute The Bengmin Frank.hn Partwey, PNLa.. Pa. 19103 (215)448 1000
RAI-C5506-274 INTRODUCTION This Request for Additional Information (RA1) is the result of an evalua-tion of the information contained in the Alabama Power Company's (APC) letter dated January 14, 1981 [1] to the Nuclear Regulatory Commission (NRC),in response to NUREG-0737 [2), Item II.K.3.17, " Report on Outages of Emergency Core-Cooling Systems Licensee Report and Proposed Technical Specification Changes." The evaluation revealed an item of concern.
Additional information relating to this concern is needed before a final evaluatica can be made.
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' RAI-C5506-274 Item II.K.3.17 Report on Outages of Emergency Cote Cooling Systems Licensee Report and Proposed Technical Specification Changes BACKGROUND In NUREG-0737, Item II.K.3.17, the NRC requested that
' licensee submit a
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report detailing dates, lengths, and causes of outages for all emergency core cooling (ECC) systems for the last 5 years of operation.
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 a cont'inuous 5-year period of recent operation:
(1) dates and durations; (2) causes, including test and maintenance; (3) ECC systems or components involved; and (4) corrective actions taken.
In addition, a licensee was to propose changes to improve the availability of ECC system equipment, if necessary.
CONCERd Evaluation of calculated small-break transie~nts, with the assumptions of proper operator actions and the worst single failure in the ECC systems, has shown that some small breaks will result in partial uncovering of the core.
However, 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, for a continuous 5-year period of I
recent operation, 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. Ou'tages for surveillance testing and for planned, unplanned, and 4 - h.' Franklin Research Center w orm ne w su,
RAI-C5506-274 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 neeo for cumulative outage limitations in the technical specifications.
APC's response [1] does not list diesel generator system outages or curveillance testing ontages that render ECCS trains unavailable during testing. The APC response does not provide sufficient information to satisfy the objective of NUREG-0737, Item II.K.3.17.
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REQUEST In order for the staff to continue its review of APC's response to NUREG-0737, Item II.K.3.17, additional information is required.
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A complete summary of each component outage in the diesel generator -
systems from December 1, 1977 through 1980.
For each outage, include the date, duration, and cause; the diesel generator train and component involved; and corrective action taken.
Include outages for surveillance testing and planned, unplanned, or preventive maintanance.
2.
A complete summary of each outage for surveillance testing from December 1, 1977 through 1980.
For each outage, include the date, duration, and cause; the component and train involved; and the corrective action taken.
Where actual data are not avsilable, estimates of the outage time due to testing should be substituted.
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RAI-C5506-274 REFERENCES 1.
F.-L. Clayton_(APC)
Letter to S. A. Varga and A. Schwencer (NRC)
Subject:
Response to NUREG-0737 January 14, 1981 2.
" Clarification of.TMI Action Plan Requirements" NRC November 1980 r
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