05000298/LER-1981-015, Forwards LER 81-015/03L-0.Detailed Event Analysis Also Submitted

Forwards LER 81-015/03L-0.Detailed Event Analysis Also Submitted

ML20009F044
Person / Time
Site:	Cooper
Issue date:	06/30/1981
From:	Lessor L NEBRASKA PUBLIC POWER DISTRICT
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20009F045	List: 05000298/LER-1981-015, Forwards LER 81-015/03L-0.Detailed Event Analysis Also Submitted 05000298/LER-1981-015-03, /03L-0:on 810531,twelve Penetrations Were Found Leaking Excessively.Ten Caused by Normal Wear & Two by Improper Limitorque Operation.Valve Repairs Performed
References
CNSS810372, NUDOCS 8107280628
Download: ML20009F044 (4)

LER-1981-015, Forwards LER 81-015/03L-0.Detailed Event Analysis Also Submitted

Event date:
Report date:
2981981015R00 - NRC Website

text

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COOPER NUCLEAR STATION Nebraska Public Power District

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CNSS810372 June 30, 1981 e

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}.I Mr. K. V. Seyfrit, Director Q

U.S. Nuclear Regulatory Commission J

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Office of Inspection and Enforcement h

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Region IV

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611 Ryan Plaza Drive b

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Suite 1000 Arlington, Texas 76011

Dear Sir:

This report is submitted in accordance with Section 6.7.2.B.2 of the Technical Specifications for Cooper Nuclear Station and discusses a reportable occurrence that was determined during leak rate testing A licensee event report form is also enclosed.

Report No.:

50-298-81-15 Report Date:

June 30, 1981 Occurrence Date: May 31,1981 Facili ty:

Cooper Nuclear Station Brownville, Nebraska 68321 During the Spring 1981 Refueling Outage all primary containment double "0" ring seals, testable expansion bellows, electrical penetrations, and testable isolation valves were tested in accordance with Technical Specifications Section 4.7.A.2.f and Tables 3.7.2 through 3.7.4.

This report describes a conditica which may have resulted in the limiting condition for operation established in Section 3.7.A.2 of the Technical Specifications not being met.

There were a total of 47 Type "B" pene-trations and 46 Type "C" penetrations tested. There were 12 Type "C" penetrations that were found to be leaking above established limits which necessitated repair and retest.

Leak rate limits for each penetration are arbitrary limits established from the preoperational local leak rate test results. No electrical penetrations, double "0" ring seals, or testable bellows were leaking excessively.

Listed below is a summary of each primary containment penetration which was repaired due to a high leakage rate.

X-39B

$N ACAD "B" Loop Supply to the Drywell. ACAD-1311 MV (inboard isolation y

valve) and ACAD-1312 MV (outboard isolation valve).

Ii 0107280628 810630 PDR ADOCK 05000298 S

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