ML18022A823

Forwards Summary of 910703 Enforcement Conference Re Failure of Reactor Trip Breaker a to Automatically Open on Demand.List of Attendees Encl

ML18022A823
Person / Time
Site:	Harris
Issue date:	07/11/1991
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Eury L CAROLINA POWER & LIGHT CO.
References
NUDOCS 9108280152
Download: ML18022A823 (24)

Text

Docket No. 50-400 License No. NPF-63 Carolina Power and Light Company ATTN:

Mr. Lynn W. Eury Executive Vice President Power Supply P. 0.

Box 1551

Raleigh, NC 27602 Gentlemen:

SUBJECT:

ENFORCEMENT CONFERENCE

SUMMARY

- HARRIS This refers to the Enforcement Conference held at our request on July 3, 1991.

This meeting concerned activities authorized for your Harris facility.

The issues discussed at this conference related to failure of reactor trip breaker "A" to automatically open on demand.

A list of attendees, a summary, and a

copy of your handout are enclosed.

We are continuing our review of these issues to determine the appropriate enforcement action.

In accordance with Section 2.790 of the NRC's "Rules of Practice,"

Part 2, Title 10, Code of Federal Regulations, a

copy of this letter and its enclosures will be placed in the NRC Public Document Room.

Should you have any questions concerning this matter, please contact use.

Sincerely,

Enclosures:

1.

List of Attendees 2.

Handout Luis A. Reyes, Director Division of Reactor Projects cc w/encls:

R. B. Richey, Vice President Harris Nuclear Project Box 165 New Hill, NC 27562 (cc w/encls cont'd - See page 2) p] pgZBOi SZ +

ppppg Pgg ADOCN, 05~ p~~

P

Carolina Power and Light'ompany JUL 11 1991 (cc w/encls cont'd)

C. S. Hinnant General Manager Harris Nuclear Plant Box 165 New Hill, NC 27562 C. S. Olexik, Jr.,

Manager Regulatory Compliance Harris Nuclear Project P. 0.

Box 165 New Hill, NC 27562 Mr. H. Ray Starling Manager - Legal Department P. 0.

Box 1551

Raleigh, NC 27602 Dayne H. Brown, Director Division of Radiation Protection N.

C. Department of Environment, Health 5 Natural Resources P. 0.

Box 27687

Raleigh, NC 27611-7687 c w/encls:

ocument Control Desk H. Christensen, RII B. Mozafari, NRR NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 1,

Box 315B New Hill, NC 27562 RII: DRP RII: DRPj MG1Ãsmah:tj HChr stensen 07/)[/91 07/ f)/91 RII:D P DVerrelli 07/ ~gg1 RII:E G e i

07/q/

1

ENCLOSURE 1

LIST OF ATTENDEES Carolina Power and Li ht Com an R. A. Watson, Senior Vice President, Nuclear Generation R.

B. Richey, Vice President, Harris Nuclear Project C. S. Hinnant, General Manager, Harris Plant L. I. Loflin, Manager, Nuclear Assessment Department S.

D. Floyd, Manager, Nuclear Licensing Department D. T. Halker, Electrical Supervisor, Harris W. T. Cooper, Senior Engineer, Technical Support M. R.

Hamby, Project Engineer, Regulatory Compliance Nuclear Re ulator Commission S.

D. Ebneter, Regional Administrator, Region II, (RII)

J.

L. Milhoan, Deputy Regional Administrator, RII L. A. Reyes, Director, Division of Reactor Projects, (DRP), RII J.

R. Johnson, Deputy Director, Division of Reactor Safety, (DRS), RII D.

M. Verrelli, Branch Chief, DRP, RII E.

G. Adensam, Director, Project Directorate II-l, Office of Nuclear Reactor Regulation (NRR)

H. 0. Christensen, Section Chief, DRP, Section 1A, RII F. Jape, Section Chief, (DRS), RII B. Uryc, Jr., Senior Enforcement Specialist, Enforcement Investigation Coordination Staff, (EICS), RII J.

E. Tedrow, Senior Resident Inspector,

Harris, DRP, RII B. L. Mozafari, Licensing Project Manager, NRR M. C. Shannon, Resident Inspector,

Harris, DRP, RII M.

M. Glasman, Project Engineer, DRP, RII D. J. Roberts, Project Engineer/Intern, DRP, RII N. L. Salgado, Reactor Engineer/Intern, DRS, RII

ENCLOSURf 2 HARM NUCXEAR PLANT NF RCKME WFEREN' RELATED T REACTOR TRIP ON U7W3 19 5

INTRODUCTION APPARENT VIOLATIONS R..B. RICHEY V.

P.

HARRIS NUCLEAR PROJECT NATURE OF FAILURE SAFETY SIGNIFICANCE ROOT CAUSE C. S. HINNANT GENERAL MANAGER HARMS PLANT CORRECTIVE ACTIONS SVIVIMARY R. B. RICHEY

FAILURE TO MAINTAIN TWO OPERABLE AUTOMATIC REACTOR TRIP CHANNELS P

ITI N'PPARENT VIOLATIONADMITTED.FROM MAY18 TO JUNE 3, ONE CHA&tNELWAS INOPERABLE DUE TO FAILEDUNDERVOLTAGEOUTPUT CARD IN THE SOLID STATE PROTECTION SYSTEM.

HARRIS POSITION ON APPARENT VIOLATIONS FAILURETO PROPERLY IMPLEMENTPLANT PROCEDURES P

ITI N:

APPARENT VIOLATIONADMITTED,SUBJECT TO FOLLOWING CLARIFICATION:

THE PROCEDURE STEPS FOR POST MAINTENANCE TESTING WERE FOLLOWED, BUT TIIE SCOPE OF POST MAINTENANCE TESTING SELECTED WAS INADEQUATE. THE PRACTICE FOR CONTROL OF JUMPERS WAS NOT ADDRESSED BY CURRENT PROCEDURE.

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UNDERVOLTAGE TRIP COIL I

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SAFETY SIGMFICANCK I

ONE TB'AIN OF AUTOMATICREACTOR PROTECTION ALWAYSAVAILABLE I

MA2'AJAL REACTOR TRIP (2

SWITCHES)

ALWAYS AVAILABLE OPERATOR TRAININGON ATWS EVENT EMPHASIZES VERIFICATIONOF ALLRODS FULLYINSERTED AS TILE FIRST ACTIONFOLLOWINGA REACTOR TRIP.

IF NOT, OPERATOR PERFORMS HIS II%MEDIATE ACTION OF ACTUATINGA MAI%JALTRIP PATH-1 GUIDANCE ON REACTOR TRIP SIGNAL

MANUALLYINSERT CONTROL RODS DISPATCH OPERATCR TO LOCALLY TRIP REACTOR TRIP BREAKERS VERIFY lURBINE TRIPPED REACTOR TRIP OR SAFETY INJECTION VERIFY ALL AFW PUMPS RUNNING INIllATE MONITORING OF CRIllCAL SAFElY FUNCllON STATUS TREES INillATE EMERGENCY BORAIION OF RCS INlllATE MONITORING OF

~ EAL NETWORK AT ENlRY POINT X FOLDOUT A APPUES MANUALLYlRIP REACTOR FRP S.1 REACTOR 1RIPPED NO REACTOR TRIPPED MANUALLYTRIP OR RUN BACK TURBINE NO lURBINE TRIPPED

BACI< R D

MARCH 1985 IEN S5-1S ISSUED O CAUTIONEDABOUT SHORT CIRCUIT PROBLEM RECOMMENDED PMT JULY 1985 WESTINGHOUSE TECIINICALBULLETINISSUED 0 DID NOT REQUIRE REPLACEMENT IF PMT ADEQUATE O RECOMMENDED PURCHASING NEW CARDS, WHEN AVAILABLE JUNE 1986 ORDER FOR MODIFIEDBO&U)PLACED AUGUST 1987 MODIFIEDBOARD RECEIVED SEPTEMBER 1987 UV DRIVER CARD DRAWINGREVISED BY WESTINGHOUSE DRAWINGREVISED TO SHOW FUSE LINK O NO FIELD CHANGE NOTICE ISSUED NOVEMBER 19SS MAINTENANCEFEEDBACK REPORT WRITTEN O QUESTIONED WHETHER FUSED CARD SHOULD BE INSTALLED O EVALUATEDAS NOT REQUIRED PROVIDED PMT

MAY16, 1991 MAY18, 1991 e "A"TRAINSSPS LOGIC TESTED SATISFACTORILY FOR NORMIALPERIODIC SURVEILLANCE REACTOR TRIP BREAKER "A"FAILEDTO CLOSE MAY18, 1991 e REACTOR TRIP "A"BREAKERREPAIRED AI'6)

CYCLED JUNE 3, 1991 REACTOR TRIP REACTOR TRIP BREAKER "A"FAILEDTO OPEN AUTOMATICALLY JUNE 4, 1991 UNDERVOLTAGEDRIVER CARD REPLACED PLANT RESTARTED JUNE 6, 1991 0 REACTOR TRIP/CLOSE SWITCH DECLARED INOPERABLE JUNE 8, 1991 PLANT SHUTDOWN AI'6) REACTOR TRIP/CLOSE SWITCH TESTED JUNE 9, 1991 e PLANT RESTARTED

MISSED OPPORTUNITIES OEF REVIEW PLANT REVIEW PMT EVALUATION RTB A'UTOMATIC TRIP DISABLED NO CARD REPLACEMENT REQUIRED NO CARD REPLACEMENT REQUIRED PMT TO CYCLE BREAKER WAS SELECI'ED AS ADEQUATE PLANTEVALUATION DEI'ERMINEDEITHER CARDWAS ADEQUATE IF ROUTINE PMT IS PERFORMED PLANT EVALUATION DEI'ERMINEDEITHER ARD WAS ADEQUATE IF ROUTINE PMT IS PERFORMED WORK PERFORMED ONLYON RTB CLOSING CIRCUII'ESTINGHOUSE ECHNICALBULLEIIN RECOMMENDED REPLACEMENT OF UV DRIVERCARD MAINTENANCEFEEDBACK REPORT SUBMHTEDTO RECOMMEND NEW FUSED CARD BE INSTALLED IEN 85-13 RECOMMENDS PMT 1985 OCT 1986 1988 1991 PRE-LICENSE POST-LICENSE

ISSUES O

OPERATING EXPERIENCE FEEDBACK O

PROCEDURAL COMPLIANCE/WORKCONIROL O

WORK SCHEDULE POST

PKRATI EXPERIENCE FKEDBA K USE OF ORIGINALCARD WITHPOST MAINTENANCETESTING WAS EVALUATEDAS ACCEPTABLE NEW IMPROVED" CARD WAS ORDERED Al'6) STOCKED AS ULTIMATEREPLACEMENT PROCESS WORKED BUT FOLLOWUP ACTIONS COULD HAVEBEEN STRONGER

PROCEDURAL COMPLIANCE WORK CONTR L O

RTB WAS INITIALLYEXAMINEDUSING A SEPAL TE TEST POWER SUPPLY 0

TROUBLESHOOTING TO CONFIRM SOURCE OF CLOSING CIRCUIT PROBLEM RESULTED IN CONNECTING TIM BREAKER TO THE CONTROL CIRCUIT USING A JUMPER CONNECTION TEMPORARY

BYPASS, JUMPER, AND WIRE REMOVAL CONTROL (AP-024) DOES NOT APPLY TO LIFTED LEADS

'OR TROUBLESHOOTING ON TECH. SPEC. EQUIPMENT THAT HAS BEEN DECLARED INOPERABLE AS LONG AS THE TECHNICIANREMAINS IN THE WORK AREA TO MAINTAINCONTROL OF THE LIFl'EDLEAD

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PLANT PRACTICg ALLOWED USAGE OF JUMPERS IN THE SAME MANNER AS LIFTED LEADS DURING TROUBLESHOOTING ALTHOUGHNOT SPECIFICALLY PERMITTED IN AP-024 NCI I N PROCEDURE DID NOT FULLYADDRESS PRACTICE OF JUMPER USE DURING TROUBLESHOOTING

W RK CHEDULE MAINTENANCECRAZI'SMEN AND SUPERVISOR HAD NOT EXCEEDED THE TECH. SPEC. LIMITSFOR TIME WORKED/HOURS OFF PRIOR TO PERFORMING THIS JOB NO MANAGEMENTOR UNUSUALPRESSURE WAS APPLIED TO COMPLETE THIS JOB CONCLUSION THIS WAS A ROUTINE BUT IMPORTANTREPAIR JOB COMPLETED BY QUALIH<EDMAINTENANCE PERSONNEL

P TMAI TE A CETE TIN POST MAINTENANCETESTING IS CONTROLLED BY HARRIS PLANT PROCEDURE PLP-400 0

SCOPE OF THE PROGIU84 - TO SPECIFY'ND PERFORM APPROPRIATE TESTING BASED ON THE EXTENT OF MAINTENANCETO VERIFY:

- EQUIPMENT OR CIRCUIT ~iCTION CAN BE PERFOMriED

- MAINTENANCEWAS PROPERLY PERFORMED

- DEFICIENCY WAS CORRECTED CONTROL OF PMT

- MAINTENANCEPLANNER A SUPERVISOR SPECIFIES REQUIRED PMT

- OPERATIONS SPECIHES TECH. SPEC.

REQUIRED TESTING

- FOLLOWINGWORK, OPERATIONS AND CRA'FT REVIEWWORKPERFORMED ANDMAI&lCIIANGES AS NECESSARY TO LISTED PMT's CONCLUSION PROCEDURE PROCESS WAS FOLLOWED BUT THE AMOUNTOF PMT DETERMINEDTO BE NECESSARY WAS INADEQUATE

R T

RUE

. INADEQUATEPOST-MAINTENANCETESTING PERFORlVIED FOLLOWINGREPAIR OF "A" REACTOR TRIP BREAKER SPRING LATCH COIL AND REACTOR TRIP SWITCH

C RRECTIVE ACTI N O

HAIKU)&Ajar' PRO CEDURKS O

MANAGEMENTEMPHASIS

REPLACED U1%3ERVOLTAGE DRIVER CARD WITH FUSEB CARD ORDERED ADDITIONALFUSED CARDS AND PLACED NON-FUSED CAIU)S ON HOLD TESTED REACTOR TRIP SWITCH DURING SHU'INTOWN Al.'6) OBTAINEDSATISFACTORY RESULTS FABRICATEANUMBILICALCORD TO SUPPLY 125 VDC FOR RTB MAINTENANCEAND TROUBLESHOOTING (WITHOUTCONNECTING TO SSPS OUTPUT). A TEMPORARY 48 VDC SUPPLY WILLBE USED TO SIMULATEA SSPS SIGNAL POR FUTURE RTB WORK.

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UPDATE PROCEDURE ON TEMPO&LRYBYPASS, JUMPER AND WIRE REMOVALCONTROL (AP-024) TO INCLUDE PLANT PRACTICE OF JUMPER USE DURING TROUBLESHOOTING DEVELOP ADDITIONALTROUBLESHOOTING GUIDANCE FOR IQCI USION IN APPROPRIATE PROCEDURES

MANA EMENT KMPHA I OPERATIONS MANAGERMUST APPROVE AI'lV'AIVER OF SSPS LOGIC TEST AS PMT FOR RTB WORK 0

PLANTGENERALMANAGERWILLMEETWITHMAINTENANCE AND MODIFICATIONSUPERVISORY PERSONNEL TO CONVEY IMPORTANCE OF EXTENSIVE POST-MAINTENANCEAND POST-MODIFICATIONTESTING PLANTGENERALMANAGE'RWILLISSUE WRITTENGUIDANCE TO MAINTENANCEAI'6) MODIFICATION WORK FORCE TO ENSURE PROPER SENSITIVITY TO IMPORTANCE OF EXTENSIVE POST-MAINTENANCEAl'6) POST-MODIFICATION TESTING

ARY HARRIS FAILEDTO MAINTAINTWO OPERABLE AUTO REACTOR TRIP CHAI%NELS AS REQUIRED BY TECHNICALSPECIFICATIONS O

HAjRRIS PERSONNE~L WORK ON TROUBLESHOOTING AND REPAIR OF THE RTB WAS PERFOMCED IN ACCORDANCE WITHNORMALPRACTICES BUT THE SPECIFICS OF AP-024 WERE NOT SATISFIED O

OPERATIONS AND MAINTENANCEPERSONNEL SPECIFIED INADEQUATEPOST-MAINTENANCE TESTING REQUIREMENTS FOLLOWINGTHE WORK ON THE "A"REACTOR TRIP BREAKER AND CONTROL BOARD TRIP/CLOSE SWITCH O

HARRIS HAS TAKENPROMPT AND EXTENSIVE CORRECTIVE ACTIONS O

IIARIGS IS EVALUATINGOTHER LONGER TERM ACTIONS TO IMPROVE PLANT PROGIUAIS