ML19242B107

LER 79-018/03L-0 on 790630:one motor-operated Butterfly Valve Found Inoperable by Remote Manual Control.Cause Is Unknown.Cause & Corrective Action to Be Reported in Future Suppl

ML19242B107
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/30/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19242B098	List: ML19242B097 ML19242B107
References
LER-79-018-03L, LER-79-18-3L, NUDOCS 7908070518
Download: ML19242B107 (1)

Text

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION 17-77)

LICENSEE EVENT REPORT CCNTROL SLOCK: l 1

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CURCE Ib h 0 l5 l0 l0 l0 l2 l6 17 @l0 OOJ ET NUMS E q 68 69 6 l3 l0 l7 l9 @ ol 7REPCRT EV ENT DATE 74 75 l 3l DATE 017 l o @ 80 60 61 EVENT DESCRIPT1CN AND PROBA8LE CCNSEQUENCES h a  : lWith the reactor operating at approximately 1.4%, plant operations personnel observed l oi3 l a dual position indication for HV-4153 (tie between circulating water cystem and ser- l 0 4 lvice water system). Subsequent investigation revealed the valve was closed, but not l fo s l fully seated, and was not operable from its associated hand switch. Because of Final l ISafety Analysis Report references in basis of LCO 4.2.4, this is reportable sider de-c is o 7 l graded mode operation per Technical Specification AC 7.5.2(b)2. No accompanying occur-l g,3 l rence or probable consequences. No affect on public health or safety. l 30 7 3 3 SYSTEM CAUSE CAL *S E COMP. VA LV E COCE CCCE SU8CCCE COMPCNENT CODE SUSCCCE SUBCCCE o 9 8

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,_ SEQUENTI AL OCCURRENCd REPCRT REVISloN EVENT YEAR REPCRT No. COCE TYPE NO.

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REPORT DATE: July 30, 1979 REPORTABLE OCCURRENCE 79-18 ISSUE O OCCURRENCE DATE: June 30, 1979 Page 1 of 2 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLATTEVILLE, COLORADO 80651 REPODT No. 50-267/ 79-18/03-L-0 Preliminary IDENTIFICATION OF OC CURRENCE :

On June 30, 1979, with the reactor operating at approximately 1.4%, HV-4153, one of two motor operated butterfly valves which provide a tie between the cir-culating water system and the service water system, was found inoperable by remote manual control. Because the basis of LCO 4.2.4, Service Water Pumps, references operability of this valve by remote manual action as outlined in Final Safety Analysis Report Section 10.3, this constitutes operation under a degraded mode of LCO 4.2.4, and is reportable per Technical Specification AC 7.5.2(b) 2.

EVENT DESCRIPTION:

On June 30, 1979, while operating at approximately 1.4% thermal power, plant operations personnel observed dual position indication for HV-4153, where ZI-4153 on I-06 was indicating both open and closed. Further investigation re-vealed that the valve was closed, but was not fully seated. Subsequent attempts to operate the valve from its associated hand switch were unsuccessful. Al-though this valve would not operate from the motor drive due to the amount of torqua required, it could be operated locally with the handjack.

The basis of Technical Specification LCO 4.2.4, Service Water Pu=ps, states that the availability of the service water system ensures the capability of supplying a.ssential components with cooling water, as described in Final Safety Analysis Report Sections 1.4, 10.3, and 14.4. Section 10.3.9 of the Final Safe ty Analysis Report, Cooldown with Safe Shutdown List Eculement Iters Fol-lowing " Safe Shutdcwn Earthquake" or Maximum Tornado", references the fact that makeup pump discharge is connected by remote manual action (via this valve as operated from the hand switch) to the service water pu=p suction pit. With this valve inoperable from the switch, the tie between the two systems is still available by manual operation of the valve; thus req 11rements for cooling water to essential components could still be met.

CAUSE DESCRIPTION:

The reason for the inability to operate this valve from t. e associaggd, hand swit ch is presently unknavn. Attempts to cycle the valve _ S,d(hate Jhad it would partially open by operation of the hand switch.

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REPORTABLE OCCURRENCE 79-18 ISSUE O Page 2 of 2 CAUSE DES CRIPTION (continued):

As further information becomes available, a supplemental report will be sub-mit te d.

COPRECTIVE

_ ACTION :

No corrective action has as yet been initiated. Upon determination of the cause of occurrence and completion of required corrective action, a future supplement to this report will be issued.

Prepared by: L M . ;.- LJ$.kA-t.<

Cathy C.vCollard Technical Services Technician Reviewed by: bVv /

M,.,

J. W. Gahm Tecnnical S Oicas J pervisor Reviewed by: // [

FratiX/i' /Mrth'ib Operations Manager b

Approved by: AL/_ 7/Jw d m Don Warembourg Manager, Nuclear Produ[ction 519 244