05000259/LER-1979-028-03, /03L-0:on 791017,flow Control Valve 73-27 Would Not Open.Caused by Dirty Contacts on Control Valve 73-27 Limitorque Operator Limit Switches.Limit Switch Contacts Cleaned

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/03L-0:on 791017,flow Control Valve 73-27 Would Not Open.Caused by Dirty Contacts on Control Valve 73-27 Limitorque Operator Limit Switches.Limit Switch Contacts Cleaned
ML19260A515
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 11/15/1979
From:
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19260A510 List:
References
LER-79-028-03L, LER-79-28-3L, NUDOCS 7911210388
Download: ML19260A515 (2)


LER-1979-028, /03L-0:on 791017,flow Control Valve 73-27 Would Not Open.Caused by Dirty Contacts on Control Valve 73-27 Limitorque Operator Limit Switches.Limit Switch Contacts Cleaned
Event date:
Report date:
2591979028R03 - NRC Website

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. ARC,s4RM 366 U. S. NUCLEAR REGULA10RY COMMISSION (7 176 Lif.,ENSEE EVENT REPORT CONTROL BLOCK:

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60 61 OOCKET NUMBER 68 69 EVENT DATE 74 7S REPORT D ATE do EVENT DESCRIPTION AND PRO 8 ABLE CONSEQUENCES h o

l During nomal operations, while performinst S1 4.5.E.1.c. FCV 73-27 would not open. re-l l 0 j a j ! sulting in HPCI system inoperability (Technical Specification 3.5.E.1). Redundant sys-oi.

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31 40 41 42 43 44 47 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS h l Dirty contacts on FCV 73-27 limitorque operator (Type 4T4G) limit switches prevented i

o l valve operation. Tite limit switch contacts were cleaned and the SI completed satis-

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factorily. The failure was random and no recurrence control is appropriate.

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Tennessee Valley Authority Fonn BF-17 Braw.ts Ferry Nuclear Plant B F 15. ':

t/10/73 LER SUPPLEMENTAL INFORMATION BFRC 259 / 7928 Technical Specification Involved 3.5.E.1(2)

Reported Under Technical Specification 6.7.2.b.2 Date af Occurrence 10/17/79 Time of Occurrence 1400, __ Unit 1

Identification and Description of Occurrence-

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FCV 73-27 (torus suction) would not open.

.P Conditions Prior to Occurrence:

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Unit 1 operating at 987. steady-state power.

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Unit 2 operating at 99%.

Unit 3 in refueling outage.

Action specified in the Technical Specification Surveillance Requirements met

!! ue to inoperable equipmcnt. Describe.

Test operability of ADS, CSS, LPCI, and RCIC to establish seven-day operability.

Mp3 rent Cause of Occurrence:

Dirty contacts on the valves limitorque operator.

A_nalysis af Occurrence:

There was no hazard to public health or safety.

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Correr.tive Action:

The contacts on the valves limitorque operator were cleaned. The system was satisfactorily tested and returned to operation.

Failure Data:

None previous.

  • Re ten ti)n :

eriod - Lifetime; Responsibility - Admini.strstive Supervioor

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  • Revision :

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