ML20045A449

LER 93-009-00:on 930506,inlet & Outlet skid-mounted Isolation Valves to Radiation Monitor Found Shut.Caused by Procedure Noncompliance by I&C Personnel.Personnel Will Review & Edit Radiation procedures.W/930604 Ltr

ML20045A449
Person / Time
Site:	Millstone
Issue date:	06/04/1993
From:	Binkowski M, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-009, LER-93-9, MP-93-446, NUDOCS 9306100282
Download: ML20045A449 (4)

Text

, l NORTHEAST UTILITIES ' oeaerai of'>ce se'oen street. Seriin connect > cut l I NsNNa$s"s'ch sUtIE1e e compa P.O. BOX 270

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Y[80as't u StIeEser $o c.nay

' tJortheast Nxtear Ene<gy Company HARTFORD. CONNECTICUT 061'*-0270 (2031665-5000 June 4, 1993 MP-93-446 Re: 10CFR50.73(a)(2)(i)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Reference:

Facility Operating License No. DPR-65 Docket No. 50-336 Licensee Event Report 93-009-00 Gentlemen:

This letter forwards Licensee Event Report 93-009-00 required to be submitted within thirty (30) days pursuant to 10CFR50.73(a)(2)(i)(B). reporting any operation or condition prohibited by the plant's technical specifications.

Very truly yours.

NORTHEAST NUCLEAR ENERGY COMPANY x - ML-

/ Stephen E. Scace Vice President - Millstone Station SES/MWB:dir

Attachment:

LER 93-009-00 cc: T. T. Martin, Region 1 Administrator P. D. Swetland, Senior Resident inspector, Millstone Unit Nos.1, 2 and 3 G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 0900O i

ON A / #67/ '/50%(o 9306100282 930604 /)nY \

PDR ADOCK 05000336

.S . (pg

NRC Form 366 US NUCLE AR REGULATORY 00MM.SS$ON APPROVED DVB NO 315C-0104 (6-69i 5 EXP<RE S 4/30'92 Estimated buroen per response to compey wrtn tms intoernation cobacpon rewest 50 0 nrs. F ora are comments regarding baroen estimate to tne Records LICENSEE EVENT REPORT (LER) and Reports Manage-em e a,cn m-53M. U S Nuc 4e a' Regulatory Comm:ssion. Wasmngton DO 23555. and to tne Pape wom RewcDon Pro;oct (3150-0104! . Cfhte et Managemem ano Buoget. WasNngton. DO 205C3 FACUTV NAME (1) DOCH E T NUMBER MJ 'AS Millstone Nuclear Power Station Unit ol sl oj ol ol3 l3 ls 1 lod 0l 3 TG Lit i4)

Radiation Mon: tor 6035 Inlet and Outlet I.,olauon Valves Found Shut EVENT DATE f 5i (ER NUvmER q i AEpOqT DA-; ,71 CTrER F ActLitEs NvoLvEO f a t MONTF DAY YEAR YEAR MONTH cay YEAR F ACUT Y NAMES of si of ol al I I

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OPERATN3 TH:S REPORT IS BENG SJBM:TTED PUR$vANT TO THE REOJiREMENTS OF 10 CFA l sCheck one or more of tne follow!n;1f111 20 402(ot 20 402ic) 50 73(a)(2)Ov) 73 71(b) ,

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UOENSEE CONTACT FOR THIS LER 112)

NAMg TELEDHONE NUMBER AM. A C ODi Ahchael W. Binkowski. Mechamcal Engineer. Ext. 684S 2l0l3 4l4l7l-l1l7]9l1 COMRE~E ONE UNE FOR E ACH COMDONENT F ALURE DESCR9ED N THIS REPORT M3)

CAV$E SYSTEU COMPONENT g CAUSE SYSTEM COMPONENT I II I I I I I II I I I I I II I I I I I II I I I I SJPPLEMENT A. AEPDAT ExDECTED M4 -. MON'H DAY YEAR SUBM'SSiON VE S Ut yes compte'e EXPEC'ED SU3M S S!CN D ATE) NO l l l ABSTR ACT (L.md to MQQ sp, aces ig , 3Dycom39ety theen gin;pegate typewrgten hqeg) p 6)

On May 6.1993, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, uith the plant operating in Mode 1 at 100 percent power, the inlet and outlet skid mounted isolation vahes to radiauon monitor RM-6038 for the Reactor Building Component Cochng Water (RBCCW) system were found shut. The closed vahes uere discosered by a Plant Equipment Operator miesugaung the cause of no flow through two sample flow indicators for the radiation monitor. Immediate operator acuan was to open the inlet and outlet isolation salves and notify the Control Room. Chemistry was then requested to sample the Reactor Building Component Cooling Water (RBCCW) for possible radioactne contammauon. None was found.

It was determined that Radiation Alomtor RM-603S had been isolated for three days without any grab samples taken and analyred, as required by plant Technical Specifications. The root cause of the event was procedure noncomphance durmp the performance of the calibrauon procedure for Radiation Monitor RM-6038 by Instrument and Control (l&C) personnel. This occurred when I&C notified Operations that RM-6038 was returned to service but mistakenly left the skid mounted valves in the closed position. The personnel involved i hare been counseled as to the importance of procedure comphance and the procedure used to calibrate RM-6035 has been enhanced to present future recurrence. In addition the Instrument and Control Departrnent is gomg to review and edit other radiauon monitoring procedures and enhance them as required to '

ensure this error will not be repeated in similar procedures. No safety related equipment was affected This esent is reportable pursuant to 10CFR50.73(a)(2)(i)(B) as a condition prohibited by the plant's Technical Specifications.  ;

Nac Form ass (649i

NAc Form 36CA

• U s NUCLEAR pgGgtATORy COMM;ss;oq APPROVED OMB NO. 3150-0104 (6-89) EXPIRES 4:30/92 Estimated burden per response to compiy w'tn tms

• m'o"nat o' co"*ct* '** 510 "r5 ***'d LICENSEE EVENT REPORT (LER) comments regaramG buroen" estimate to the Aecoros TEXT CONTINUATION ano neoons vanagenwnt ecch (p-530s. U S Nuc.ea-Aegulatory Comrmssion. Wasmng'on DC 20655 and to the Peterworu Beduction Profeet 13100-e1041. O*f ce of i

Mar.apement and Bunget_ Wasnmgton DC 20603.

F ACIUTV NAME p i DOCKET NUVBER (2) 1 Fo Nt ursp m PAGE[3r vtAa = nmac em n>m um Millstone Nuclear Pouer Stauon UN - 0l 5l 0l oj ol3 l3 l6 9l3 0l 0l 9 0l0 0l 2 OF 0l3 Tf xT O' more space is feos ea r use 40:1 t'onat NRC Form a66 A si (17;

1. Desctriion of Event On May 6,1993, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, with the plant operating m Mode 1 at 100 percent power, the inlet and oudet skid mounted isolation valves to radiation morator RM-6038 for the RBCCW system were found shut. The closed valves were discosered by an operator mvestigating the cause of no flow through two sample flow indicators for the radiation monitor. On May 3,1993, two Instrument and Controls (l&C) personnel performed a calibration procedure on radiauon morntor RM-6038. The cabbration procedure specifically states that IkC contact the Operations Department to close the isolation rahes at the beginnmg of the procedure and to open the valves at the end of the procedure. The Operations ,

Department was not nonfied to mampulate the vahes as required. Instead, one of the 1&C technicians ,

closed the isolanon valves himself and then failed to open the isolation valves at the conclusion of the  !

calibranon procedure. Upon discovery of the shut isolanon valves, the Plant Equipment Operator opened t the mlet and oudet isolation valves and nonfied the Control Room. Chemistry was then requested to sample the RBCCW for possible radioactive contammation. None was found. There were no manual or automatic saf ety actuations as a result of this event.

11. Cause of Event The root cause of the event was procedure noncomphance. Despite the calibranon procedure specifically requinng that the Operations Department close and reopen the isolation valves to RM-6036, an I&C technician closed the isolanon vahes himself and then failed to reopen the vahes upon completion of the calibration procedure. ,

III. Analpis of Es tnt This esent is reponable pursuant to 10CFR50.73(a)(2)(i)(B), any operanon or condition prohibited by Plant Techrucal Specificanons. Specifically, one RBCCW monitor must be in continuous service at all times. During penods where the radiation morntor is inoperable for greater than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. grab samples must be taken and analyzed for gross contamination. Since the monitor was out of service and no grab samples were taken as required, the unit operated outside of plant Technical Specificauons for three days.

The esent had no safety consequences. After the isolation valves were found shut, Chemistry tested both the Service Water and RBCCW for gross contammanon and none was present. No radioactive water was released to the enuronment via the RBCCW system during the three days Radiatica Monitor RM-603S was out of sernce.

IV. Correcuve Actinn Immediate correctise action was taken by the Plant Equipment Operator. He opened the isolation valves to radiation rnonitor RM-6038 for the RBCCW systern and notihed the Control Room. Chemistry was then requested to sample the RBCCW to venfy no pross contammation was present. None was present.

The 1&C mdividuals mvohed in the meident have been counseled on the importance of procedure compliance. Also, the cabbration procedure for RM-6038 has been revised to include the following:

1) Clanhcation of isolation valve restoration instructions.

2) A venficanon and sign-off of normal process flow during restoration has been added to a data sheet m the exisimp procedure.

3) A scrification and sign-off of mlet and outlet valves open after restoration has been added to the same data sheet.

In addition,1&C is going to review and edit, as appropnate, other radiation monitoring procedures. This review will include adding sign-off areas, as required, to estabbsh the required valve line-up(s) for operanon and sign-off areas to venfy flow through the designated monitor (s).

usc t o,m m (6-89)

i i

NRO Form 3fSA U.S. NUCLEAR REGULATORY COMM.SSION APPROVED OMS NO 3150-0104 (6-89) ,

EXPtRES 4/30/02

• Estemated careen per response to compiy with trns  ;

' FWaec LICENSEE EVENT REPORT (LER) c'nto'm** co'*: tim ouroen omments regare.no m@estestimaie

. 50. 0tohrs tne me:oras

, TEXT CONTINUATION ano sepons vanageme,i Branch e53D). U. S Nuclear Regu:atory Comm'sse Wasnington. DC 20556. and to

. ine Paperwork Reouction Prcsect (3150-01041 Off<ce of Management and Bsapet Wasnington DC 10503. .

F AOfLITY P.AME (1) DOCKET NUMBER (2i (F A NUM9F A (f., PAGEf3)

YEAR euern toem Millstone Nuclear Power Station L QL *'

0l5l0l0l0l3l3l6 9l3 0l0l9 0l0 0l 3 OF 0l3 rExT e mo<e soace is rewee use acemona' Nac Form 366A s} lt7)

V. Additional Information Similar LERS: 88-010,89-009 There were no f ailed components as a rewa o4 this event.

Ells Code for referenced component: - Radianon Monitor; IL-LB-N305 I

NRC Form 3th (6-89)