05000259/LER-1980-015-01, /01T-1:on 800206,during Refueling,Found Two Spare Unwelded 1-inch Lines on Penetration X-49 W/Only One Manual Isolation Valve Per Line External to Containment.Caused by Installation error.X-49 Line Capped & Similar Lines Wel

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/01T-1:on 800206,during Refueling,Found Two Spare Unwelded 1-inch Lines on Penetration X-49 W/Only One Manual Isolation Valve Per Line External to Containment.Caused by Installation error.X-49 Line Capped & Similar Lines Welded
ML19323J015
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 06/09/1980
From:
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19323J010 List:
References
LER-80-015-01T, LER-80-15-1T, NUDOCS 8006170639
Download: ML19323J015 (2)


LER-1980-015, /01T-1:on 800206,during Refueling,Found Two Spare Unwelded 1-inch Lines on Penetration X-49 W/Only One Manual Isolation Valve Per Line External to Containment.Caused by Installation error.X-49 Line Capped & Similar Lines Welded
Event date:
Report date:
2591980015R01 - NRC Website

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EVENT DESCRIPTION ANC PRC0ARLE CONSEQUENCES h g l During refueling operations two spare one-inch lines were_ fnund te nanarrara I

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,;o; j The cause of the spare lines having only one manual isolation valve was installation I

Units 2 and 3 were inspected and similar lines were properly capped.

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g investigation revealed that 3 lines at penetrations X-51, X-203, and X-217 had not i

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X-49 line was capped.and the others seal I

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'Ifrowns Ferry Nucle r Plant Fcim DF-17 11F 15.2 1/10/'ia LER SUPPLEMENTAL INFORMATION BFRO 259 /__8015 Technical Specification involved Reported Under T;chnical Specification

6. 7. 2. A.3 Date of Occurrence 2/6/80 Time of Occurrence 1400 Unit 1

Identification and DescrMion _of Occurrence:

Two spare 1" lines on penetration X-49 had only 1 manual isolation valve per line external to containment. Neither was welded.

Two 1" and one 2" lines were found at penetrations X-51, X-203 and X-217 which were not seal welded, but did have double isolation valves.

The lines had not been tested per 10 CFR 50, Appendix J.

Conditions' Prior to Occurrence:

Unit 1 - scheduled refueling outage Unit 2 - 549 We Steady State Operation

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Unit 3 - 1098 We Steady State operation Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.

N/A

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Mparent Cause of Occurrence:

It is not known at this time when these lines were installed in their present configuration and for what specific purpose.

Analysis of Occurrence:

There was no loss of containment caused by the occurrence. There wa.; no danger to the health or safety of the public, no damage to plant or equipment, no resulting significant chain of events.

Corrective Action-

'Each of the identified lines at X-49, -51, -203, and -217 were seal welded inside primary containment.

Each line was air pressure tested to 65 psig which is above original, design pressure for primary containment.

Similar lines in Units 2 and 3 were inspected and found to be acceptable.

i Failure Data:

i N/A

  • Retention:

eriod - Lifetime; Responsibility - Administrative Supervisor

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  • Revision:

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