IR 05000322/1987009

Mgt Meeting Insp Rept 50-322/87-09 on 870404 to Discuss 870318 Loss of Offsite Power Event

ML20215K562
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	05/05/1987
From:	Anderson C, Paulitz F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20215K524	List: IR 05000322/1987009 ML20215K521
References
50-322-87-09-MM, 50-322-87-9-MM, NUDOCS 8705110251
Download: ML20215K562 (15)

Text

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /87-09 Docket N License No. NPF-19 Licensee: Long Island Lighting Company P.O. Box 618, North Country Road Wading River, New York 11792 Facility Name: Shoreham Nuclear Power Station Meeting At: NRC, Region I King of Prussia, Pennsylvania Meeting Conducted: On April 4, 1987 Reporting Inspector: b L C ,a itz, Reactor Engineer

dat rI Approved by: b [5 J' 1 C. J. Ahderson, Chief, Plant Systems Section date Meeting Summary: Management Meeting at Region I office on April 4, 1987 to l discuss the Loss of Offsite Power Event of March 18, 1987. The licensee ! discussed the event including the cause and correction action to prevent i future occurrences.

l l ! ! ! l l l I 0705110251 070506 PDR ADOCK 05000322 O PDR

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Details l l 1.0 Participants  ; l 1.1 Long Island Lighting Company (LILCO) J. Leonard, J Vice President, Nuclear Operation S. Skorupski . Assistant Vice President, Nuclear Operation W. Steiger, J Plant Manager E. Youngling Manager, Nuclear Engineering Department L. Britt Director, Licensing & Regulatory Affairs R. Purcell Manager, Outage / Modification 1.2 United States Nuclear Regulatory Commission W. Johnston Acting Director, Division of Roactor Safety (DRS) ' L. Bettenhausen Acting Deputy Director, DRS J. Durr Chief, Engineering Branch (EB), DRS R. Lo Project Manager, Nuclear Reactor Regulation C. Anderson Chief, Plant System Section (PSS), EB, DRS J. Wiggins Chief, Project Section 18, Division of Reactor Projects P. Eselgroth Chief, Test Program Section, Operations Branch, DRS - Observer: T. J. Pappas, Esquire Kirkpatrick, Lockhart, Hill, Christopher & Phillips 2.0 Purpose This meeting was held at the request of NRC Region I to allow the licensee the opportunity to present their understanding of the event and corrective actions to prevent future occurrence .0 Presentation and Discussion The Acting Director of the Division of Reactor Safety, opened the meeting by stating that the reason for the meeting was a concern that Losses of Offsite Power had been occurring more frequently at Nuclear Power Facilitie The NRC wanted to be assured that the licensee understood the root cause of the event and to determine that the licensee's management was involved ! to assure that adequate correction action would be taken to prevent future occurrence The Vice President of Nuclear Operations welcomed the opportunity to present their understanding of the event and their corrective actions.

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V The licensee's staff made a slide presentation of the following: ,

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Plant Condition Prior to Event  ;

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Event Chronology

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Operator Response

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Incident Investigation

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Immediate Cause of Event

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Root Causes

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Corrective Actions

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Summary The licensee's slides presented at the meeting are attached to this repor ! The licensee also presented the installation status of the new emergency diesel generator .0 Concluding Statements The NRC staff thanked the licensee for their presentation. The staff i stated that the licensee understood the root cause of the event. The i licensee's corrective actions appeared appropriate.

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! l ! ELANT COND1Il01 ER10R_IO EVENT ! 0 OCS REFUEL MODE TO REPLACE 'N' SOURCES 21 FT. OF WATER AB0VE REACTOR FLANGEj 1.E., CAVITY FULL 0 ELECTRICAL LINE UP PRIOR TO EVENT NORMAL EXCEPT FOR Bus 103 OUT OF SERVICE FOR MAINTENAtlCE & MODIFICATIONS , l 0 ACTIVITIES lti PROGRESS r

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Bus 103 MODIFICATIONS TO INSTALL SPARE SWITCHGEAR CUBICLE FOR COLT [tlGINE 4KV SUPPLY ,

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BREAKER MAINTENANCE ON CONDENSATE PUMP BREAKER COMPLETE AtlD CONDEriSATE PUMP WAS BEltlG TESTED i RQIE: PLANT MODIFICATIONS MADE TO TIE-IN THE COLT DIESELS l AT THE 1ST REFUELING OUTAGE WHICH IMPACT UPON STAT 10ft ! OPERAT10tl ARE OtlLY DONE IN THE SnuTDOWtl CONDITION.

, EXAMPLES:

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 - CORE BORitlG ELECTRICAL pet 1ETRAT10tlS Ill MAlti C0tnROL ROOM FLOOR AND RELAY ROOM 8 SWITCHGEAR WALLS I
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IflSTALLING FALSE FLOOR FOR CONDUlT RutlS lti CORRIDOR

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 - INSTALLING C0flDUlT, CONTROL PANELS Ill RELAY ROOM AtlD MAlti CONTROL ROOM   .
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MODIFICATIONS TO EMERGEricY SWITCHGEAR BUSES

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EVENT CHRONOLOGY o 'A' CONDENSATE PUMP IS BUMPED (IlME 0146) o NSST TRIPS ON PRIMARY DIFFERENTIAL PROTECTION (I!ME 0146) o RSST TRIPS ON PRIMARY DIFFERENTIAL PROTECTION (TIME 0146) o. REACTOR SCRAM (IIME 0146) o EDG 101 S 102 Auro START AND SUPPLY THEIR BUSSES o EDG 103 OUT OF SERV!CE FOR MAINTENANCE O ALL PLANT SYSTEMS RESPOND AS DESIGNED ,

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OPERATOR RESPONSE O OPERATORS PERFORM EMERGENCY SHUTDOWN PROCEDURE O OPERATORS PERFORM LOSS OF 0FFSITE POWER EMERGENCY PROCEDURE O WATCH ENGINEER DIRECTS A FIELD INSPECTION OF INPLANT EQUIPM 0 VERIFICATION OF lHTEGRITY AND AVAILABILITY OF 0FFSITE DISTRIBUTION POWER SYSTEM IS CONFIRMED WITH THE SYSTEM O 0 ."A" CONDENSATE PUMP MOTOR WAS PUT IN PULL-IO-LOCK AND THE CB RACKED OUT 0 RSST PatMARY PROTECTION RELAYS WERE RESET AT 0200 0 RSST WAS RE-ENERGlZED AT 0202 0 BUSSES 11, 12, 1B RE-ENERGlZED FROM THE RSST BY 0204 > 0 UNUSUAL EVENT DF.CLARATION; UE-7, LOSS OF 0FFSITE POWER

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0 NOTIFICATIONS MADE TO PLANT MANAGEMENT AND GOVERNMENT OFFIC 0 UE-7 TERMINATED (TIME - 0500)

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INCIDENT INVESTIGATION O INCIDENT INVESTIGATION STARTED AT 0530 BY MANAGEMENT PERSONNEL IN RESPONSE TO WATCH ENGINEER'S CALLOUT

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0 NSST & RSST CIRCUlT AND RELAY CHECKS WERE CONDUCTED BY 0800 0 INVEST.lGATION IDENTIFIED TRANSFORMER DIFF. CIRCulT SECONDARY SIDE CI'S WERE SHORTED (IlME - 0930) 0 THE SHORTED CI'S WERE PART OF THE STATION MODIFICATION FOR BUS 103 THEREFORE:

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REVIEW OF STATION DESIGN OuTeuT PACKAGE (PROGRAM WAS FOLLOWED SATISFACTORILY)

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REVIEW OF STATION MODIFICATION PROCEDURE (PROCEDURE WAS FOLLOWED SATISFACTORILY) . e

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JBSEDIATE CAUSE OF EVENT

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0 SHORTitlG OF EuS 103 CT CIRCUlTRY (PUT UP SLIDE) ; l

; O EaIn NSST ArtD RSST DIFF PROT. RELAY CIRCUlTS WERE I  AFFECTED BY SHORT!!1G ALL THE CIS Oft BUS 103 0 "A" C0tlDEllSATE Pul4P BUMPED
! O THE "SEllSED" CI CURREllT, IRIPPED OC NSST DIFFEREllTIAL l  PROTECT 10!! RELAY
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l 0 USSI DIFF. RELAY ACTIVATED - LOCKlilG OUT TiiE NSST 1  ! j 0 LOCKOUT OF Tite NSSI tillTI ATED A PAST IRAllSFER TO TliE RSST

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0 IllE "SEllSED" CI CURREtlT, IRIPPED OA, OB, OC RSST DIFF.

l i PROTECT 10rt RELAYS i i

! O RSST DIFF. RELAYS ACTIVATED - LOCKillG OUT TiiE RSST 0 LOSS OF 0FFSITE POWER I

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i It00T CAUSE O PROCEDURAL DEFICIEllCY

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BECAUSE lilSTRUCT10llS Ill THE STAT 10rl MODIFICAT10!l PROCEDURE WERE lilSUFFICIEllT Oil HOW TO SHORT OUT TliE CTS FOR TiiE bus WOR i t

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0 HOW

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IllTERPRETATION OF D0P INSTRUCTIONS BY THE ErlGirlEER Oil CI SliORTillG WAS lilCORRECT) SINCE, THE VEllDOR'S BUS WIRiflG DIAGRAf4 REFERENCED IN THE DOP DID NOT DESCRIBE TliE PROTECTIVE CIRCulT DESIGN IN ITS EllTIRET . NEITHER THE DOP fl0R THE STATION MOD PROCEDURE DEFillED WHICli BUS CIS SHOULD HAVE BEEN SHORTED At1D WHICH 11EED I fl0T .3E SHORTED TO PROTECT THE BUS DURING Hi POT TESTillG l PER 711E MAllVFACTURER'S RECOMMEllDATIO [tlGlflEER ASSUMPTIONS ON CI C0!lFIGURAT10tl WERE WR0!lG

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IEClittlCAL REVIEW 0F THE PROCEDURE DID fl0T DETECT THE , DEFICIEllCY i

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J1EEDIAILCOBRECIIVEXUORS

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l o REr4ovtD SHoRTific Plf4S FRot4 DIFF. CIRCUlT CI'S (Ill4E 1000) I o llSCI DIFF. RELAYS CHECKED Af1D SETPolflTS VERIFIED

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o RSSI DIFF. RELAYS CHECKED AllD SETP0lflTS VERIFIED 1 o "A" CouDEUSATE Pur4P liEGGER TESTED AflD SATISFACTORY

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o "A" CONDENSATE PUl4P SUPPLY BREAKER PRor. RELAY & CIRCulT i CHECKED AtlD SATISFACTORY l B p

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CORRECTIVE ACTI0flS TOPREVBIT l l RMIRE OC0lRTflCES__ l l l i 0 RE-EMPHAS!ZE RE0pMEMENT TO PROVIDE SPECIFIC DETAILS ON IffLDEffTATION REQUIREMEllTS IN UU" O IfFROVEIEGINCIALREVl&JOFST APROCEDUREOtECKSilEET(S..lDb>ATIONlbDIFICATIO ,

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O ASSURE TEOfllCAL REVIEWER IS If0EPEf0Ef(T OF ORIG!fMT0rt(s) O CliECKLIST FOR STAT 10H lhDIFICATION IEOiftlCAL REVIEW TO EllSURE TIMT i TliE ACTUAL IfPLEMDITAT10fl 0F THIS MODIFICAT10fl HILL f40T ADVERSELY , EFFECT TIE SAFE OR DESlof4ED OPERATION OF TliE Pl.NTT

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O DEVELOP LESS0fl PLAN NO C0flDUCT TRAIN!flG SESSION Ofl C0flFirURATION CoffiROL FOR IMillTENANCE, TEST NO MODIFICATION PERSOfiflCL Mio COULD * OlANGE PLNIT C0f4FIGURAT10N l l

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