05000344/LER-1981-013, Forwards LER 81-013/03L-0.Detailed Event Analysis Encl

Forwards LER 81-013/03L-0.Detailed Event Analysis Encl

ML20010B214
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/03/1981
From:	Yundt C PORTLAND GENERAL ELECTRIC CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20010B215	List: 05000344/LER-1981-013, Forwards LER 81-013/03L-0.Detailed Event Analysis Encl 05000344/LER-1981-013-03, /03L-0:on 810703,during RCS Integrity Test,Rcs Leakage Exceeded Tech Spec Limit.Caused by Leaking Drain Valves on Reactor Coolant Loops Due to Failure to Torque Valves
References
CPY-544-81, NUDOCS 8108140226
Download: ML20010B214 (3)

LER-1981-013, Forwards LER 81-013/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3441981013R00 - NRC Website

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E Portland General Electric Company Trojan Nuclear Plant P.O. Box 439 Rainier, Oregon 97048 (503)S56-3713 August 3, 1981 CPY-5/4-81 9 i1*'

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5 lol Mr. R. H. Engelken, Director f

Nuclear Regulatory Commission, Region v 8

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1990 North Califc,rnia Boulevard gMD 7 Walnut Creek, California 94596 L

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Dear Sir:

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U1 In accordance with the Trojan Plant Operating License, Appendix A, uo anC Technical Specifications, Paragraph 6.9.1.7, we are submitting Licensee Event Report No. 81-13.

This report describes a situation where Reactor Coolant System identified leakage exceeded the maxin:um amount allowed by the Technical Specifications.

Sincerely, 0

C.

P'. Yundt General Manager CPY S:mae Attachments c:

LER Distribution List 5'A a

8108140226 810803 DR ADOCK 05000344 PDR-

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REPORTABLE OCCURRENCE i

1.

Report No.:

81-13 2.

a.

Report Date:

August 3,'1981 i

b.

Occurrence Date: July 3, 1981 3.

Facility: Trojan Nuclear Plant, P.O. Box 439, Rainier, Oregon 97048 4.

Identification of Occurrence:

7

' Reactor Coolant System leakage of approximately 14 gallons per' minute-4 was experienced during the performance of a Reactor Coolant System.in-tegrity test.

This is in excess of the Technical-Specifications limit of 10 gallons per minute for identified leakage. The source was leak-ing drain valves on the Reactor Coolant loops.

Condit'ons Prior to Occurrence:

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The plant was'in-Mode 3 at the time of this event. Reactor Coolant System pressure was at 2335 psig for the jerformance of the Reactor.

Coolant System integrity test.

Reector Coolant temperature was 557'F.

6.

Description of Occurrence:

A Reactor Coolant System pressure test was being conducted to verify system integrity following a plant refueling. After increasing pres-sure to-2335 psig, plant personnel noted increased temperature and pressure in the Reactor Coolant Drain Tank'(RCDT). Efforts to cool:

the tank were unsuccessful.and a Containment entry was made to inspect for leakage. This inspection t.vealed that loop drains on A, B, and C loops appeared to be leaking to the RCDT. Calculations determined the Reactor Coolant leak rate to be approximately 14 gallons per minute.

The valves were retorqued to their hot torque values and the. leakage stopped.

7.

Designation of Apparent Cause of Occurrence:

The type of valve used to isolate the loop drains must be torqued to ensure they seat properly. Plant procedures did not specify this re-

- quirement. As a result, the valves were checked shut during preopera-tional valve lineups but were not torqued.

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8.

Significance of Occurrence:

This event had no effect on plant or public safety. All leakage was contained in the Reactor Coolant Drain Tank and the Containment sump.

The Reactor-Coolant ' System integrity te.

is intended to identify and.

correct system leaks prior'to reactor startup.

In this instance the test accomplished this purpose.

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- Corrective Action:

. The valves ~were torqued to tne correct values and the leakage was.

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stopped. Changes -will be made to plant procedures, to provide in -

i structions for:praperly torquing these valves.

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