ML20237G379

Summary of Operating Reactors Events Meeting 87-23 on 870721.List of Attendees,Viewgraphs & Summary of Reactor Scrams & Significant Events Encl

ML20237G379
Person / Time
Site:	Calvert Cliffs, Mcguire, Palisades, Brunswick, North Anna, 05000000
Issue date:	08/11/1987
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-87-023, OREM-87-23, NUDOCS 8708140049
Download: ML20237G379 (15)

Text

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AUG 11- 1987

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HEMORANDUM FOR:- Charles E. Rossi,' Director-

' Division of.0perational Events Assessment'

- FROM: Wayne Lanning, Chief .

Events Assessment Branch.

Division of Operational Events Assessment .

J

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING l July 21, 1987 - MEETING 87-23 l

On July 21,1987 an Operating Reactors Events meeting (87-23) was held to brief senior managers.from NRR, RES, AEOD and Regional Offices on events which occurred'since our last meeting on July 14,1987. The list of attendees 4

is included as Enclosure 1.

' Tha tevents" discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 provides a summary of reactor scrams and "significant events" that will be input to NRC's performance indicator program.

4 i Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment o

Enclosures:

As stated cc:

- See Next Page DISTRIBUTION

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. cc: T. Murley T. Wambach J. Sniezek M. Virgilio R. Starostecki L. Engle J. Taylor L. Rubenstein E. Jordan S. McNeil E. Beckjord F. Capra W. Russell, Reg. . D. Hood J. Nelson Grace, Reg. II B.J. Youngblood B. Davis, Reg. III E. Sylvester R. D. Martin, Reg. IV E. Adensam J. B. Martin, Reg. V F. fliraglia W. Kane, Reg. I E. Merschoff L. Reyes, Reg. II R. Hernan C. Norelius, Reg. III H. Bailey E. Johnson, Reg. IV D. Kirsch, Reg. V S. Varga D. Crutchfield B. Boger G. Lainas G. Holahan F. Schroeder L. Shao J. Partlow B. Grines F. Congel H. Miller E. Weiss S. Black T. hbrtin, EDO F. fliraglia E. Merschoff R. Hernan l H. Bailey l

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (87-23)

JULY 21, 1987 NAME ORGANIZATION NAME ORGANIZATION Thomas Starostecki NRR John Thompson NRR/EAB J. Partlow NRR Faust Rosa NRR/SELB Brian Grimes NRR/DRIS Gerald Klinger NRR/ILRB Gary Holahan NRR/DRSP Frank Cherry RES/DE Larry Shao NRR/DESI Jerry Mazetis RES/RPSIB Frank Miraglia NRR/ADP Peter VanDoorn SRI / CATAWBA Ernie Rossi NRR/00EA K.N. Jabbour NRR/DRPI/II Carl Berlinger NRR/DOEA Gus Lainas NRR/0RP S. Varga NRR/DRP Paul Norian RES/APSIB W. Troskoski EDO Peter Prescott VIB/NRR Stu Rubin AEOD/DOA Darl Hood NRR/PD2-3 John Harmon NRR/DLPQ Jack Donohew OSP Danielle Oudinot NRR/EAB

ENCLOSURE 2 r '~ .

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OPERATING REACTORS EVENTS BRIEFING 87-23 TlESDAY JllLY 71 - 1987, 11 A.M,.

T E AGEFDA INFORMATION MAY ALSO BE OBTATN01 FY DIALING EX1ENSION 27174, PALISADES 1 - LONG DUPATION LOSS OF 0FFSITE PNEP NORTil ANNA 1 - STEAM GENERATOR TUBE LEAK CALVERT CLIFFS 1- UNCONTROLLED BOPATION MCGUIPf2 - RTB FAILURE OJPDATE)

BRUNSWICK 1- SAFETY ELIEF VALVE FAILUPE NOTE: THEPE WILL NOT E AN OPERATING E\9'T BRIEFING ON MEDAY ' JULY 2.7,1987.

WE TUESDAY BRIEFING WILL BE ELD AS llSUAL,

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PAL!SADFS 1 - LONG DURATION LOSS OF 0FF-SITE POWER

.!ULY 14, 1987 PROBLEM FAILURE OF START-UP TRANSFORMER PRECIPIT/TED A MANUAL REACTOR SCRAM AND LENGTilY LOSS OF 0FF-SITE POPER CAUSE OFF - SITE POWER WAS LOST DUE TO FAILED TRANSF0PMER SIGNIFICANCE AC' POWER REQUIRED FOR OPERATION OF MOST SAFE SHUTDOWN EQUIPMENT.

LOSS OF 0FF-SITE POWER LEAVES PLANT DEPENDENT ON EDGs, DISCUSSION JULY 14, 1987, PLANT AT 91% POWER START-UP TRANSFORMER BUSHINGS FAILED CAUSING LENGTHY LOSS OF 0FF-SITE POWER ADEQUACY OF 0FF-SITE POWER AT PALISADES SHOULD BE EVALUATED RESTORATION OF 0FF-SITE POWER REQUIRES DISCONNECTION OF MAIN GENERATOR TIME REQUIRED IS 5 TO 9 HOURS - THIS EVENT TOOK 7,5 HRS.

THESE TIMES ARE OUTSIDE THE NORMS FOR USI-A44 I

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' CAPACITY.0F THE STATION BATTERIES IS ESTIMATED'AT 5 T0 7 HOUPS RESTORATION'0F.THE DAMAGED START-UP TRANSFORMER MAY BE COMPLETED IfrONE WEEK THIS PLANT HAS HAD FOUR PREVIOUS INSTANCES OF LOSS OF 0FF-SITE POWER THIS PLANT HAS BEEN IDFNT!FIED AS "HIGH RISK" F0P STATION BLACK 0UT FOLLOWilP AIT SENT TO SITE LICEN3EE IS CONSIDERING SWITCHYAPD UPOPADES TO MINIMIZE A REPEAT'0F THIS "YPE OF EVENT CONTACT:.-R .

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9 NDPTH ANNA - 1 STEAM GENERATOR TUBE LEAK JllLYJ5,1987 PROBLEM:' STEAM GENERATOR TUEE LEAK PESl'LTED IN SCRAM, SAFELY INJECTION, AND DECLARATION OF ALEPT, CAllSE lf'KNDvt SIGNIFICANCE STEAM GENEPATOR TUBE RUPTilRE.

PADI0 ACTIVITY RELEASE OlffSIDE CONTAlfFDTT.

POSSIBILITY FOR MOPE SEVEPE ACCIDENT.

DISCUSSION "C" STFAM LINE RAD MONITOR ALAPED HIGH ORRATOR NOTED PRESSURIZED LEVEL Ato PRESSUPE DECREASING OPERAIDR MANUALLY SCPAMED PEACTOR SAFETY INJECTION DERGENCY PROCEDilRES INITIATED FOR POST SGTP C00LDOWN STEAM JET AIR EJECTOR ( SJAE) RAD MONITOR WAS OUT OF SERVICE (b0 AUTO-TRANSFER OF SJAE EXHAUST FROM STACK TO CONTAINMENT)

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TOTAL PADT0 ACTIVITY RELEASE FROM SJAE AND AUX-FEED TERRY TUPBINE 0.265 CI, (AB0lff 0.6% T.S. ALLOWABLE)

ALL STEAM GBJERATOR TUBES EDDY CUPPFNT TESTED DURING PEFLELING OUTAGE.

FOLLrHUP LICENSFE IfNESTIGATICN CONTINt!!NG PEGION !! RESPONSE TEAM UPGPADED TO ATT. .

CONTACT: SWENSON/NPR l l l )

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CALVERT CLIFFS 1 UNCONTROLLED BORATION-JULY 14, 1987 PROBLEM UNCONTROLLED B0 RATION RESULTED IN RAPID DECREASE OF REACTOR CAUSE REACTOR MAKEUP SYSTEM MODE SELEC. TOR SWITCH DESIGN DEFICIENCY HUMAN FACTORS PROBLEM SIGNIFICANCE UNNECESSARY CHALLENGE TO PLANT AND OPERATORS DISCUSSION .

. INSTRUMENT AIR TO FEEDWATER HEATER VALVES SECURED TO ALLOW o.

ON "16A" LEVEL CONTROL VALVE FEEDWATER HEATER FLOODED OUT RESULTING LEVEL AND TEMPERATURE CHANGES IN FEEDWATER HEATER CA REACTOR POWER TO INCREASE FROM 100% TO 103%

0PERATOR SWITCHED FROM MANUAL TO BORATE MODE AND INITIATED A RC INSERTION TO RAPIDLY DECREASE POWER OPERATOR TURNED SWITCH BACK TO MANUAL (0FF)

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• 6 MINUTES LATER OPERATOR DISCOVERED BORIC ACID PUMP STILL RUNN OPERATOR PROCEEDED TO MANUALLY TRIP THE REACTOR FROM 5% POWER UNSUCCESSFUL ATTEMPT TO RUN TURBINE BACK PEMAINING INVENTORY IN BORIC ACID TANK AND B0 RATION TIME SEEM TO INDICATE THAT OPERATOR USED DIRECT PATH TO CHARGING PUMP S ..

AS WELL AS PATH TO VCT.

OPERATORS WERE AWARE THAT IF SWITCH TURNED T00 FAST TO OFF POSITION, BORIC ACID PUMPS CONTINUE TO OPERATE FOLLOWUP LICENSEE:

SHORT TERM - WILL PLACE INFORMATION TAG ON SWITCH

- WILL REPRODUCE EVENT ON SIMULATOR TO TRAIN OPERATORS LONG TERM: SCHEDULED IMPROVEMENT OF SWITCH DESIGN REGION I TO FOLLOW LICENSEE'S ACTIONS l j

CONTACT: D. OUDINOT L

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i UPDATE OF MCGUIRE 2 RTB FAILURE NEGOTI ATIONS BETWEEN DUKE AND }] ON LABORATORY INVESTIGATIONS IN PROGRESS 3 REMAINING (INIT 2 BREAKERS INSPECTED 1

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• IFF0PMATION NOTICE WILL BE ISSllED SHORTLY 1

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FPlt!SWICK - 1 SAFETY RELIEF VALVE FATLUPE - UPDATE JLETT 2 1987 PROBLEP,

" SAttlY RELIEF VALVE (SRV) FAILDED DURING SCRAM FPOM 1007, ANOTHER SPV FAILED DURING STARTUP TESTING,

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CAUSE

~ LURED LOCTITE RC 620 ON SOLEN 0ID PLlNGER DISCUSSION ,

' RhvISItr> TO I 8 E INF0PFATION NOTICE 84-53 HAS BEEN DRAFTED, ALL PLAffTS HAV!NG VALVES REBUILT BY TARGET POCK HAVE BEEN CONTACTED BY PEGIONS, THE THREE PLANTS HAVING HAD VALVES REBUILT IN THE LAST 18 M0hTHS PLLG Tk0

, . OTHER OPEPATING PLANTS KERE ASKED THE FOLLOWING QUESTIONS:

1. WHEN WAS MAINTENANCE LAST PERFORMED ON THE SOLEN 0ID VALVES FOR THE ADS VALVES?

?, kH0 PERFORMED THE MAlfTIENANCE AND WAS LOCTITE llSED? '

3. HAVE ADS VALVES HA\E BEEN ACTIVATED IN SITU AFTER MAINTENANCE WAS PERFORMED AFTEP THE SOLEN 0ID WAS SUPJECIED TO AN INERT ENVIRONEhT?

RESPONSE

" PLANI: #1 #2 #3

• FITIPATPICK 5/1/87 TAPGET ROCK-YES YES

• HOPE CPEEK PRIOR TO APRIL '86 TAPGET ROCK-YES NO

• HATCH 1 4/22 - 6/23/87 TARGET PDCK-YES YES

• FERMI 2 DON'T KNOW TARGET ROCK-YES NOT INERTED DURING STARTUP TESTING

• COOPER DON'T KtOI YET TARGET ROCK-YES DON'T KNOW YET

• ADS SOLENDIDS APE TESTED DURING STARTUP AFTER EACH PEFULEING AT BWR.

i FOLLOWUP

~ 10 PURSUE ISSl!ANCE OF PEVISED INF0PFATION NOTICE 84-53

• TARGET ROCK TO REVISE MAINTENANCE PROCEDUPES AND ADMINISTRATIVE CONTPOLS, J'

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-' EEA: TOR SCRAM SUErARY WEEK ENDINS 07/19/27

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I, PLANT SPECIFIC DATA LATI SITE UNIT POWER RPS CAugE t05pt!. yn y73 yn l CAi!DNS A50VE BELOW TDIAL 151 151 07/13/E7 CLINIDS 1 !3 A EDUIPr.ENT h2 ) 4 07/14/37 LIAFLO CANY0h  : 12 A EDUlff.ENT ND j 3 4 l 07/14/57 ffil5AME 1 91 P EDU!?/TRAN5 TOE. ND 3 1 4 l 07/14/!' CALVEET CLIFFS 1 100 A EEUIP..ENT "

NO  : 0 3 07!!5'E7 N: iH (NNA 100 P EQUIPf.ENT NO (

(?! M/I' ECPIN!D'; I 72 A EDUIFr>ENT NC [ g .

0?!!s/E' P.0NTICELLO 1 100 A EDulF/ ELECT. N3 4 (> 4 07!!S!!' EESDEN  ; 70 A EQUIP / ELECT. NO 2 0  ;

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.- II. COMPARISON OF WEEKL STATISTICS W8TH 2NDUSTRY AVERAGES SCRAMS FOR WEEK ENDING, 07/19/87 SCRAM CAUSE POWER NUMBER 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY

,9 SCRAMS (5) AVERAGE AVERAGE' AVERAGE f- YTD (3) (4) (B) (9)

• • POWER >15%

EQUIP. RELATED >15% 7 4.4 4.3 5.4 PERS. RELATED(6) >15% 0 1.4 1.e 2.0

'OTHER(7) >15% 0 1.0 0.4 0.6

• • Subtotal ** . -

7 6.8 6.5 8.0

• • POWER <15%

EQUIP. RELATED <15% 1 1.3 1.4 1.3

1. PERS. RELATED <15% 0 0.7 0.8 0.9 OTHER <15% 0 0.3 0.2 0.2

• • Subtotal **-

1 2.C 2.4 2.4

• • • Tetal ***

8 9.1 BI9 10.4 MANUAL VS AUTO SCRAMS t TYPE NUMBER 1987 1986 1995 OF WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 2 1.6 1.0 1. O '

AUTOMATIC ECRAMS 6 7.6 7.9 9. 4 i

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. NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F E0.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS VHICH RESULT IN R0D MOTION, AND EXCLIDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN i,CCORDANCE WITH A PLANT PROCEDURE.

E. RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED 70 ULTSTDF SCRAM.

3. 1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.

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

, MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATING LICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.8 TRIPS PER WEEK FOR ALL REACTORS.

5. BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.

6. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

7. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

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 52 UEEKS/ YEAR.

9. IN 198E, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

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