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Ref:- 10CFR50.73(a)(2)(1) w wAm

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W3BS-01-0219-A4.05QA

August 5,;1991

l - U.S.- Nuclear Regulatory Commission -' ATTENTION: Document Control Desk i

Washington, D.C. 20555 -|

Subject: Waterford 3 SESDocket No. 50-382

-License No. NPF-38-Reporting of Licensee Event Report[-

|

:Gentiemen:

Attached is Licensee Event Report Number LER-91-015-00 for.Waterford Steamu. Electric Station' Unit 3'. This Licensee Event Report is submitted pursuantto 10CFR50.73(a)(2)(1).

| Very truly-'yours,|=

|-

D.F. PackerGeneral Manager - Plant Operations

DFP/DDW/rkAttachment--

cc: ' Messrs. R.D.-Martin.E G.L. FlorreichL J.T. Wheelock - INP0 Records Centerl' E . L . - Bl ake

|l D.L. Wigginton|- N.S. Reynolds -

.

NRC Resident Inspectors Office

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' U S NUC L E A R Rt Gui A f DR V COMM44 TON

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LICENSEE EVENT REPORT (LER) imesan-.

f hCittTY NAMG 1H POC E E I NUM9E R 12l f ad d-

Waterford Steam Electric Station Unit 3 o i s t o 1 o 1 o 1318 | 2 I l0FIO I 4' ' ' ' ' ' ' ' Failure to Stroke BD-103B When Restoring to Service

due to a lack of Procedural ComplianceEVCNT DATE 691 L t R NUM5t h 161 REPOnf DAf t I?! OTHE R f AcalTIE S INVOLVED 85>

480 NTH DA, YEAR Vt4R ' E j.$[g ',* ' " j*,Q Mostw Dav vtam '40 u t v % Auts DW a t T Nvvfit a 5-[

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LICENSEt CONT ACY FOP. THis LED sitii

%4Mt T E .t * <N a N A*B E p

D.W. Vinci, Operations Superintendent5 !O I 4 41614 1-l31 11114

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At 0800 hours on July 16, 1991, Waterford Steam Electric Station Unit 3 wasoperating at 100% power. Work had commenced to adjust the packing on SteamGenerator Blowdown Containment Isolation Valve BD-103B. Limiting Condition

for Operation 3.6.3 was in effect since the valve was inoperaole, requir'ngthe inoperable valve to be returned to operable status or the affectedpenetration isolated within 4 hours. Technical Specification (TS) 3.6.3requires that each affected valve be stroked and timed prior to returning thevalve to service. BD-103B was not tested prior to placing the valve inservice and TS 3.6.3 requirements were not satisfied until 2146 on July 16,1991 when the Operations Procedure 903-032 retest was completed.

The root cause of this event was a lack of procedural compliance. Upongranting permission for maintenance workers to adjust packing on BD-103B, theshift supervisor failed to enter BD-103B in the equipment out of service logand enter TS 3.6.3 to properly track the TS requirements for returning BD-103Bto operable status. Since BD-103B was later tested satisfactorily, the valve

would have performed its required function; therefore, this event did notthreaten the health or cafety of the public or plant personnel.

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Nme. . m.+9 53 :

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UCENSEE EVENT REPOAT (LER) |N,'c'%^M!,%'M80d!"c,"'53*i',/%*f";V ,*d".'A"'S$ '-

TEXT CONTINUATlON iJ"M8 ';fMNd $$'.* 1"c'O,'l# ',"/ *',5n'

F APE RWO RED 3 i TON R J 43 O ICOF MANAGE uttaf AND SUDGET,W ASHINGTON, DC NbO3

F ActL4TY NAmt un DOCKET huMBER(21 tta NUMalm (St Pact (3)Water ford Steam

,,A, . ,Eoa 1% mmElectric Station Unit 3 " " " " " "

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At 0800 hours on July 16, 1991, Waterford Steam Electric Station Unit 3 was

operating at 1001 power. Work had comaienced to adjust the packing on SteamGenerator (SG) (EIIS Identifier - SG) Blowdown System (EIIS Identifier - WI)

Containment Isolation Valve (EIIS Identifier - ISV) BD-103B. Limiting

Condition for Operation (LCO) of Technical Specification (TS) 3.6.3 was inL| effect since the valve was inoperable, requiring the inoperable-valve to bet

| returned to operable status or the affected penetration isolated within 4'

hours. TS 3.6.3 requires that each affected valve be stroked and timed prior

to returning the valve to service. BD-103B was not tested prior to placing

the valve in service and TS 3.6.3 requirements were not satisfied until 2146

on July 16, 1991 when the Operating Procedure (OP) 903 032 retest was:

completed.

At 0800 hours on July 16, 1991, the Shif t Supervisor (SS) gave mechanical' maintenance personnel permission to commence Work Authorization (WA) 01080546

to adjust the packing on BD-103B. Work commenced, however, SD-103B was not,

entered in t'.ic equipment out of service (EOS) log as required by Operating-Procedure (DP) 100-010, Equipment Out of Service Administrative Procedure.-OP-100 010 p.ovir'es guidance for the documentation of the removal from and

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| restoration to service of Quality / Safety related equipment. -OP-100-010

| specifically states that whenever packing is adjusted on ASME Section XIvalves, a Quality / Safety-related EOS Checklist should be completed beforeemoval when possible or as soon as possible thereafter. The SS did not

ensure that the valve was entered in the EOS. In addition, TS 3.6.3 was not

entered. When the WA was returned to the control room after packing

adjustments had been made, the SS assumed that the retest had been completed

and did not discuss the WA 01081546 retest requirements with the Control RoomSupervisor.

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UCENSEE EVENT REPORT (LER) |Sg,^'!,%"d8R.E!"o"'#Rit/%c?'%V ,*o'.",'"O-

TEXT CONTINUATlON P."T To",';16,'",?ni 'Y"f'." n's','h L".' "Mf'-.

' Oft #2 ? Tat!,",<*=">?'?" ?&tM?'c?OF MANAGEMENT 4.ND tuDGET WASHINGTON. DC 20t@3.

F ACellTY NAMt H) DOCK 41 NUM8tm 01 Ltm stuM89R 461 PAGE (35Waterford Steam

y,, ...,,u ..cElectric Station Unit 3 "*"" " " *

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During the 4 hours after the valve packing was tightened, the valve was cycledfor an unrelated test of a blowdown system modification. OP 903 032,Quarterly IST Valve Tests Surveillance Procedure, however, requires a timed

stroke test of the BD-103B to determine operability. Since the SS thoughtthat the retest had been completed and since there was no EOS log entry to

.

track the retest requirement, the 4 hour time limit was exceeded,r

Midway during the next shift, the SS aaked the Shift Technical Advisor (STA)

if BD-1038 should have been entered in the EOS log. -The STA had assumed that

the valve had been entered in the EOS log and, when questioned, the STArealized that th- 4 hour time limit had been exceeded. OP 903-032 was

satisfactorily completed and a late entry in the control room logs was madedeclaring BD-103B inoperable. BD-103B was declared operable at 2146 on July16, 1991.

The root cause of this event is an inappropriate action by the SS in that BD-

103B was not entered in the EOS log when the valve was out of service. TheEOS log is used to document out of service quality / safety-related equipment

| and associated TSs and LCOs. If this valve would have been entered in the EOS| log, the shift would have been more able to track time constraints associated

with placing the valve out of service. The SS has been debriefed per the

Improving Human Performance Program.

Since BD-103B was later tested satisfactorily, the valve would have performedits required function; therefore, this event did not threaten the health or

safety of the public or plant personnel.

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N3C f orm 3ASA 164M

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* LICENSEE EVENT REPORT (LER) 'S '",*i',%',f"8 EJ',"0"'A@',,T .#""!' ,*0 "WJ'S' '.

TEXT CONTINUATION C J"',*'',';i"M AO%%i"E',* 1','CH'**'MP ;"| 0 ."f!* ^"-

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*l Rt GUL ATOR Y COSAWE$ TON, W ASHINGTON DC 20b66 AND TO1HE P APf R 40HK RE DUCTION PRO,lE CT 0160 010e OF F ICE

- _ Of M ANAGEME DiT AND DVOGE t, W A&HINGTON. DC 20WJ

ts.CILITY hAMg og DOcktt NUMean u' tia NUMelm(4) Pact (31Waterford Steam s a g;',a 6 37y,gs A.

.iElectric Station. Unit 3li

0 |5 |0 | 0 | 0 | 318|2 91 1- 0|1 | 5 01 0 01 4 or 0|4 |

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text in a w .mai.nw *nein asu e> pn

SIMIIAR EVENTS

! LERs 88-021, 89 021 and 91-012 reported failures to perform requiredsurvoillances with an Emergency Diesel Generator out of service within thespecified time limits. Corrective action for LER 89 021 included enhancementsto the EOS log, requiring additional tracking information regarding LCO actionstatements. i

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PLANT CONTACT

D.W. Vinci, Operations Superintendent, 504 464-3134

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NHC Form Je6A {&89)

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