05000260/LER-1980-038-03, /03L-0:on 800911,during Refueling Outage W/Unit in Cold Shutdown,Hpci Check Valve 2-73-609 Failed Local Leak Rate Test.Caused by Buildup of Residual Matl on Body,Causing Disc of Hcpi Valve to Be Cocked Open.Matl Removed

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/03L-0:on 800911,during Refueling Outage W/Unit in Cold Shutdown,Hpci Check Valve 2-73-609 Failed Local Leak Rate Test.Caused by Buildup of Residual Matl on Body,Causing Disc of Hcpi Valve to Be Cocked Open.Matl Removed
ML18025B116
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 10/07/1980
From:
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18025B114 List:
References
LER-80-038-03L-02, LER-80-38-3L-2, NUDOCS 8010140371
Download: ML18025B116 (3)


LER-1980-038, /03L-0:on 800911,during Refueling Outage W/Unit in Cold Shutdown,Hpci Check Valve 2-73-609 Failed Local Leak Rate Test.Caused by Buildup of Residual Matl on Body,Causing Disc of Hcpi Valve to Be Cocked Open.Matl Removed
Event date:
Report date:
2601980038R03 - NRC Website

text

aPI 400 LICENSEE EVENT REPORT

,CONTROL OLOCK:

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60 61 DOCKFT NUhlBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PRO8ABLE CONSEQUENCES QIO LWith the unit in a cold shutdown condition during a scheduled refueling outage, HPCI check valve 2-73-609 failed the local leak-rate test.

Valve 73-24 was s

~operable.

There was no danger to the health or safety of the public, nor 80 08 Lany significant resulting chain of events.:

Refer to Tech Spec 4.7.A.2.g and h.

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VALVE CODE CODE SUBCODE COMPONENTCODE SVBCODE SUBCOOE

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~G>4 MQ" 33 34 35 36 31 4p 41 42 43 44 41 CAUSE DESCRIPTION ANDCORRECTIVE ACTIONS Q27 Maintenance inspection revealed that disc of HPCI check valve 2-73-609 was held open by a build-up of residual material on the body which caused disc to be cocked.

Material was removed and line flushed.

Previ.ous failure history of valve indicates no recurrence control required.

Hancock; 2 inch Mdl SWE, 600 lb.

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11 12 13 PERSONNEL INJURIES 45 NA LOCATION OF RELEASE Q38 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 Q3I Local leak-rate test 45 80 80 8

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Tennessee Valley Authority Browns Ferry Nuclear Plant LER SUPPLEMENTAL INFORMATION Form BF-17 BF 15.2 1/10/79 BFRO 260 / 8038 Technical Specification Involved 4.7.A.2.G

& H Reported Under Technical Specification

6. 7.2.b 4

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Identification and Descri tion'of Occurrence:

With the unit in cold shutdown during a scheduled refueling outage, HPCX check valve 2-73-609 failed the local leak rate test.

Conditions Prior to Occurrence:

Unit 1 75% steady state power 1

Unit 2 refueling "outage Unit 3 96% steady state power.

Action specified in the Technical Specification Surveillance Requirements met due to ino erable e ui ment.

Describe.

Valve 2-'73-24 was operable A

arent Cause of Occurrence:

There was a build-up of residual material on the valve body under the disc causing the valve t'o remain open.

Anal sis of Occurrence:

There was no danger to the health or safety of the public, no release of activity, no damage to plant or equipment, and no significant resulting chain of events.

Corrective Action

The valve w'as cleaned-and the line flushed.

Failure Data:

N A

  • Retention:

+Revision:

eriod - Lifetime; Responsibility - Administrative Supervisor