ML20237B588

Summary of 871201 Operating Reactors Events Meeting 87-42 to Brief Senior Managers from Nrr,Res,Aeod & Regional Ofcs on Events That Occurred Since 871124 Meeting.List of Attendees & Viewgraphs Encl

ML20237B588
Person / Time
Site:	Millstone, Perry, Haddam Neck, Farley, 05000000
Issue date:	12/04/1987
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-87-042, OREM-87-42, NUDOCS 8712160368
Download: ML20237B588 (17)

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MEMORANDUM FOR:

Charles E. Rossi, Director Director of Operational Events Assessment z.

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FROM:

Wayne Lanning, Chief Events Assessment Branch b

Division of Operational Events Assessment v:

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SUBJECT:

THE OPERATING REACTORS EVENTS MEETING

[;,j December 1, 1987 - MEETING 87-42 e.;

[.7-On December 1,1987 an Operating Reactors Events meeting (87-42) was held to L

brief senior managers from NRR, RES, AE00 and Regional Offices on events which f

occurred since our last meeting on November 24, 1987. The list of attendees is j

included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2.

The Enclosure 3 provides a summary of reactor scrams and a comparison of-this week's statistics with industry averages.

Two significant events were identified for input to NRC's performance indicator program.

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Events Assessm nt ranch Division of Oper onal Events Assessment

Enclosures:

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MEMORANDUM FOR:

Charles E. Rossi, Director Director of Operational Events Assessment 9

FROM:

Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING December 1, 1987 _ MEETING 87_42 On December 1,1987 an Operating Reactors Events meeting (87 42) was held to brief senior managers from NRR, RES, AE00 and Regional Offices on events which occurred since our last meeting on November 24, 1987. The list of attendees is j

included as Enclnsure 1.

i The events discussed and the significant elements of these events are presented in Enclosure 2.

The Enclosure 3 provides a sumary of reactor scrams and a comparison of this week's statistics with industry averages. Two significant events were identified for input to NRC's performance indicator program.

Wayne Lanning, Chief l

Events Assessment Branch i

Division of Operational Events Assessment i

Enclosures:

As stated l

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See Next Page DISTRIBUTION Central File' EAB Reading File Circulating Copy EAB Staff MLReardon, EAB D0udinot, EAB LKilgore, SECY, PDR OFC

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LIST OF ATTENDEES WJ s.a j :l.},

OPERATING REACTORS EVENTS BRIEFING (87-42) 9.!

bij December 1,1987 e

'M NAME ORGANIZATION NAME ORGANIZATION R. Lobel NRR/D0EA L. Zerr NRR/DOEA M.L. Reardon NRR/D0EA C. McCracken NRR/ECEB O-W. Jensen NRR/00EA P. Baranowsky NRR/DOEA i

W, G. Requa NRR/PD 2-1 V. Potapovs NRR/DRIS

'4h M. Virgilio NRR/DRPSP E. Weiss AE0D W

V. Benaroya' AE0D/DSP B. Boger NRR/ADR 1 i

73 R.W. Cooper, II DEDR0 M.R. Johnson DEDR0 yk P. Gill NRR/SELB K. Black AE00/ SSP q

,T F. Rosa NRR/SELB W. Minners RES/DRPS

~~6 F. Miraglia NRR/ADP G. Lainas NRR/ADR II I

Q A.S. Masciantozio NRR/EMEB J. Guillen NRR/00EA j

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OPERATING REACTORS EVENTS BRIEFING 87-42 TUESDAY DECEMBER 1, 1987, 11 A,M,

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35 THE' AGENDA INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION'27174, si

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PERRY W I MSIVs FAILED TO REMAIN CLOSED

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~3 MILLSTONE 3 i.7; 1

LOOSE PARTS c.,

GENERIC ISSUE INTEGRITY OF SILICONE RUBBER-INSULATED CABLES

<J HADDAM NECK 9 / $

INADEQUATE MAINTENANCE i

PROCEDURE i

i FARLEY 2 3 d LOSS OF COOLANT AT SHUTDOWN

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y-t MILLSTONE UNIT 3 LOOSE PARTJ PROBLEM REACTOR COOLANT PUMP PARTS FOUND ON LOWER CORE SUPPORT PLATE.

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SIGNIFICANCE LOOSE PARTS MIGHT LEAD TO FUEL ELEMENT DAMAGE OR REACTOR COOLANT PUMP

DAMAGE, i

DISCUSSION l

0 ON NOVEMBER 17, 1987 AN UNUSUAL SHADOW WAS SEEN IN THE LOWER CORE l

FLOW HOLE FOR POSITION C05 DURING FUEL MOVEMENT.

L:

o LICENSEE UNLOADED THE CORE AND FOUND A TOTAL OF 8 FOREIGN OBJECTS ON THE CORE SUPPORT PLATE.

o ONE FLAT OBJECT ABOUT THE SIZE OF A DIME (0RIGIN UNKNOWN).

o SEVEN OBJECTS WERE DETERMINED TO BE LOCKING CUPS FOR HOLD-DOWN BOLTS OF THE REACTOR COOLANT PUMP TURNING VANE DIFFUSER (MODEL 93Al WESTINGHOUSE PUMP),

THERE ARE 23 CUPS AND HOLD-DOWN BOLTS PER PUMP, o

o LICENSEE INSPECTED THE AREA BELOW THE CORE PLATE AND THE REACTOR VESSEL BOTTOM USING A SUBMERSIBLE CAMERA, N0 ADDITIONAL FOREIGN OBJECTS FOUND, o

MILLSTONE 3 IS THE ONLY PLANT WITH PEENED LOCKING CUPS, o

OLDER PLANTS HAVE WELDED LOCKING CAPS, NEWER PLANTS HAVE SELF LOCKING CAPS, o

LICENSEE IS EVALUATING POTENTIAL FOR CORE OR PUMP DAMAGE FROM ADDITIONAL LOOSE LOCKING CAPS OR BOLTS DURING NEXT CYCLE, o

RESTART FROM CURRENT REFUELING OUTAGE IS SCHEDULED FOR DECEMBER l-

1987, o

LOOSE PARTS MONITORING OPERABLE BUT HIGH SET POINT.

FOLLOWUP NRR AND REGION ARE CONTINUING TO DISCUSS ISSUE WITH LICENSEE, CONTACT:

W. JENSEN

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, f, INTEGRITY OF SILICONE RUBBER-INSULATED CABLES j

l PROBLEM j

TVA NOTIFIED NRC (9/87) 0F FAILURES OF NINE SILICONE RUBBER-INSULATED

<1 SINGLE CONDUCTOR CABLES DURING HIGH POTENTIAL TESTS AT SE000YAH i

6 NUCLEAR PLANT, y

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SIGNIFICANCE o

SILICONE RUBBER-INSULATED CABLES ARE WIDELY USED IN LOW VOLTAGE POWER AND CONTROL CIRCUITS (BOTH SAFETY RELATED AND NON-SAFETY

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RELATED).

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STAFF IS CONCERNED THAT THESE CABLES MAY FAIL TO PERFORM THEIR i, '-

INTENDED FUNCTION IN A DESIGN BASIS ACCIDENT ENVIRONMENT (LOCA, C

STEAM LINE BREAK).

a DISCUSSION o

TVA SUBMITTED 10CFR PART 21 NOTIFICATION IN SEPTEMBER 1987 f<

REGARDING SEVERAL CABLE INSULATION FAILURES AT SEQUOYAH, o

FAILURES IDENTIFIED DURING HIGH POTENTIAL DIRECT CURRENT TEST f

(240 VOLTS / MIL).

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o INSULATION FAILURES IDENTIFIED IN 3 SILICONE RUBB'ER-INSULATED L ':

SINGLE CONDUCTOR CABLES MANUFACTURED BY AMERICAN INSULATED WIRE L

(AIW).

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LABORATORY TESTING REVEALED 6 ADDITIONAL INSULATION FAILURES (3 IN AIW CABLES AND 3 IN ROCKBESTOS CABLES).

o EXAMINATION OF FAILED CABLES IDENTIFIED:

HIGHLY LOCALIZED DAMAGE i'r INSULATION DAMAGE CAUSED BY LOWER THAN EXPECTED IMPACT FORCES o

IMPACT FORCES COULD POSSIBLY OCCUR DURING:

HANDLING BY MANUFACTURER SHIPPING RECEIPT AND STORAGE BY TVA e

INSTALLATION PROCESS 3

o TVA HAS CONCLUDED THAT PERFORMANCE OF SILICONE RUBBER-INSULATED l

CABLES IS SIGNIFICANTLY DIFFERENT FROM OTHER CABLES AT TVA, ON WHICH 923 TESTS WERE RECENTLY COMPLETED WITH NO FAILURES.

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CONTACT:

J. GUILLEN l

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CABLE FAILURES AT VOLTAGES BELOW THOSE ACCEPTED BY THE INDUSTRY f

TO DEMONSTRATE II'SULATION INTEGRITY DURING EQ TESTING MAY INDICATE THE INABILITY OF 'JHESE CABLES TO PERFORM THEIR INTENDED FUNCTION l

i' UNDER DBA CONDITI0hS, 1

NRC ACTIONS o

GENERIC COMMUNICATIONS BRANCH (COORDINATED WITH ELECTRICAL SYS1 EMS c:

BRANCH AND OFFICE OF SPECIAL PROJECTS) ISSUED AN INFORMATION NOTICE I

ON OCTOBER 16, 1987, BASED ON TVA NOTIFICATION.

o DRAFT GENERIC LETTER HAS BEEN PREPARED REQUESTING INFORMATION FROM i

M LICENSEES TO SCOPE THE PROBLEM AND PROVIDE A BASIS FOR FURTHER REGULATORY ACTION.

o BASED ON INFORMATION RECEIVED FROM LICENSEES AND INPUT FROM FRANKLIN RESEARCH LABORATORY-CONSULTANTS, GENERIC COMMUNICATIONS U

BRANCH AND ELECTRICAL SYSTEMS BRANCH WILL ISSUE A BULLETIN DELINEATING CORRECTIVE ACTIONS,

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L1 HADDAM NEC.K 2 INADEQUATE MAINTENANCE PROCEDURE

-i PROBLEM

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ON NOVEMBER 20, 1987, ALL-PURPOSE GEAR GREASE WAS INAPPROPRIATELY O

APPLIED TO THE MOTOR WItlDINGS OF 20 MOTOR OPERATED VALVES (t'0Vs).

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CAllSE j

INADE00 ATE MAINTENANCE PROCEDURES.

SIGNIFICANCE POSSIBLE DAMAGE TO VALVE MOTORS FOR SAFETY RELATED VALVES.

DISCUSSION o

UNIT SHUTDOWN FOR REFUELING.

i o

LJCENSEE EMPLOYEE WAS SUPERVISING CONTRACT PERSONNEL DURING MAINTENANCE ACTIVITIES.

o EMPLOYEE HAS HAD PRIOR EXPERIENCE CONDUCTING MAINTENANCE ACTIVITIES.

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PERSONNEL, IN PACKING MOV GEARS WITH GREASE, INAPPROPRIATELY PACKED ELECTRICAL WINDINGS OF MOTOR.

o FITTINGS ON BOTH MOTOR CASING AND GEAR HOUSING ARE SIMILAR IN

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APPEARANCE, o

ALLIANCE AND LIMITOROUE MOVs IMPACTED.

FOLLOWUP 0

LICEt(SEE IS REVIEWING ALL WORK CONDUCTED OR SUPERVISED BY LICENSEE's j

EMPLOYEE DURING CURRENT OUTAGE.

o ALL MOVs ON SITE WILL BE INSPECTED, o

MOV VENDORS ARE BEING CONSULTED FOR APPROPRIATE REMEDIAL ACTION.

o MAINTENANCE PROCEDURE WILL BE MODIFIED TO INCLUDE AN ILLUSTRATION,

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CONTACT:

N. FIELDS

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'i-I FARLEY 2 SPILL FROM RESIDUAL HEAT REMOVAL (RHR) SYSTFM p

PROBLEM j

2200 GAL. OF COOLANT WERE SPILLED FROM THE REACTOR COOLANT SYSTEM f.j AND THE REFUELING WATER STORAGE TANK.

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o FAILURE OF AN RHR RELIEF VALVE.

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FAILURE TO FOLLOW SURVEILLANCE PROCEDURE,

a SIGNIFICANCE JJ BREAKDOWN IN ADMINISTRATIVE CONTROL,

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DISCUSSION L"

o ON 11/27/87, UNIT CONDITIONS WERE BEING CHANGED FROM MODE 5 T0 MODE 4..THE RCS WAS AT 195 F AND 1400 PSIG WITH 3 RCPs,1 CHARGING PUMP, AND 2 RHR PUMPS RUNNING.

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RHR VALVE WAS BEING STROKE-TESTED AFTER MAINTENANCE USING THE

< :1 i OUARTERLY SURVEILLANCE PROCEDURE.

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CONTRARY TO PROCEDURE, THE.RHR PUMPS WERE RUNNING AND RHR VALVES WERE NOT PROPERLY ALIGNED.

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o WHEN A VALVE WAS STROKED, A PRESSURE SURGE RESULTED (PROBABLY-

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BECAUSE OF TRAPPED AIR) WHICH CAUSED A PUMP SUCTION RELIEF VALVE TO OPEN AND STICK OPEN.

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o THE RELIEF VALVE, WHICH IS SET AT IS 435 +15 -0 PSIG, RELIEVES TO THE PRESSURIZER RELIEF TANK (PRT),

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THE RUPTURE' DISK ON THE PRT FUNCTIONED SPILLING 2200 GAL OF o

COOLANT TO THE CONTAINMENT SUMP WHICH WAS PUMPED TO A LIQUID WASTE HOLDUP TANK.

OPERATORS ISOLATED THE RELIEF VALVE AND TERMINATED THE SPILL.

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THE LICENSEE IS DISASSEMBLING THE OFFENDING VALVE FOR EXAMINATION.

FOLLOWUP

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THE REGION IS REVIEWING THE LICENSEE's ADMINISTRATIVE CONTROLS.

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CONTACT:

R. WOODRUFF

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FARLEY 2

[ik, PRELIMINARY SE00ENCE OF EVENTS 7.;s 0 SEC.

STROKED SUMP VALVE OPEN

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RCS PRESSURE 8 PZR LEVEL START.ED TO DECREASE 1.0 PRT LEVEL 8 PRESSURE STARTED TO INCREASE LO s 't J 'e :

60 SEC.

CLOSED THE SUMP VALVE s,

j PZR LEVEL CONTINUED TO DECREASE 4,E

q 60'- 120 SEC. PZR LEVEL AT OR BELOW 0%

RHR SUCTION VALVE CLOSED p:e

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STARTED TO RESTORE PZR LEVEL VIA

';g CHARGING PUMP, VCT, AND RWST

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LEVEL RESTORED L, s..

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.y REACTOR SCRAM SUMARY WEEK ENDIh5 11/29/E7

1. PLANT SPEtlFIC CATA DATE SITE UNIT POWER SIEhAL CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE SELOW TOTAL 15I 151 3'j:2' 11/23/E7 NORTH ANNA

,, 1 100 A EDUIFMENT N0 4

0 4

!!)23/57916 ROCK FOINil h 1 0A EQUlFMENT ND 0

5 5

11/25/E7 ST LUC 1E 2

50 A EDVIFMENT ND 1

0 1

11/29/E7 PERRY 17 M FERSDNNEL NO 10 2

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGEE J

SCRAMS FOR WEEK ENDING

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SCRAM CAUSE POWER NUMBER 1987 1986 1985 l

OF WEEKLY WEEKLY WEEKLY SCRAMS (5)

AVERAGE AVERAGE AVERAGE YTD (0)(4)

(B) (9) 3

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• • POWER >15%

i EQUIP. RELATED

>15%

2 4.O

'4.3 5.4 PERS. RELATED(6) >15%

1 1.3 1.8

2. 0

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OTHER(7)-

>15%

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• • Subtotal **

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3 6.5 6.5-8.0 1

• • POWER <15%

EQUIP. RELATED

<15%

1 1.2 1.4 1.0 L

PERS. RELATED

<15%

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• • Subtotal **

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• • • Total ***

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8.6 8.9 10.4 MANUAL VS AUTO SCRAMS t

TYPE t

NUMBER 1987 1986 1985 I

OF WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE YTD Y

'fd 8;

MANUAL SCRAMS 1

1.4 1.0 1.0 AUTOMATIC SCRAMS 3

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PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS

'4 FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH *,

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MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE QA ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED M

TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE g

WITH A PLANT PROCEDURE.

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RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS Ay UNRELATED TO CAU5E OF SCRAf!.

3.

1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEK'LY DATA DETEPJIINED BY TAKING TOTAL TRIPS

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j IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.

I9 4.

IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND i,

MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING Li OPERATING LICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS

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PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.0 TRIPS PER WEEK 9'

FOR ALL REACTORS.

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BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.

6.

PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL l

DEFICIENCIES, AND MANUAL STIAM GENERATOR LEVEL CONTROL PROBLEMS.

7.

• 0THER" INCLUDES AUT0tMTIC SCR AMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

1 8.

1985 INFORMATION DERIVED FROM AN ORAS' STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL _ TRIPS IN A GIVEN CATEGORY AND DIVIDING BY S2 WEEKS / YEAR.

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9.

IN 1985, THERE WERE AN ESTIfMTED TOTAL OF 541 AUTOMATIC AND MANUAL' UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). TH]S YIELDS AN AVERAGE RATE OF 5.0 TRIPS'PER REACTOR YEAR AND AN AVERAGE RATE OF 10.d TRIPS PER WEEK FOR ALL REACTORS.

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( h fLANT NAME EVENT EVENT DESCRIPT10N QTR SISNIFICMEE

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DATE

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FARLEY 2 11/22/87 2200 SAL SPILL FRDM RUPTURED PRESSURIZER RELIEF TANK 1 POTENTIAL F0E OR ACTL'AL DEE3ADATIt';

j RUPTURE DISK DUE TO OPERATOR ERROR WHILE TESTING RHR OF PRIMARY C30LANT PREE3";E F'A BOUNDARY l

PERRY 11/29/87 CNE MSIV FAILED TO CLOSE DURING TESTINS - INOPERABLE I POTENTIAL FOR OR ACTUAL DE3RADATIC1

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