ML20211G936
| ML20211G936 | |
| Person / Time | |
|---|---|
| Site: | Palisades, Catawba, Saint Lucie, Byron, Pilgrim, Susquehanna, Turkey Point, River Bend, LaSalle, 05000000 |
| Issue date: | 06/06/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8606200310 | |
| Download: ML20211G936 (28) | |
Text
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i JUN 6 1986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON June 2, 1986 - MEETING 86-18 On June 2,1986, an Operating Reactor Events meeting (86-18) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on May 19, 1986. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2.
In addition, the assignment of followup review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.
Completion dates have been assigned for items in Enclosure 3.
Each assignee should review Enclosure 3 with regard to their respective responsibilities.
Note that several assignments are approaching the due date.
Please be responsive and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.
Original signed By:
Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
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JUN 6 1986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON June 2, 1986 - MEETINC 86-18 On June 2,1986, an Operating Reactor Events meeting (86-18) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on May 19, 1986. The list of i
attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2.
In addition, the assignment of followup review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.
Completion dates have been assigned for items in Enclosure 3.
Each assignee should review Enclosure 3 with regard to their respective responsibilities.
Note that several assignments are approaching the due date. Please be responsive and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.
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Gary M' Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
See Next Page i
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D. Eisenhut A. Bournia J. Taylor E. Adensam C. Heltemes P. Leech T. Murley, Reg. I J. Zwolinski J. Nelson Grace, Reg. II D. Mcdonald J. Keppler, Reg. III L. Rubenstein R. D. Martin, Reg. IV-D. Sells J. B. Martin, Reg. V A. Thadani R. Starostecki, Reg. I M. J. Campagnone S. Ebneter, Reg. I T. Wambach R. Walker, Reg. II L. Olshan C. Norelius, Reg. III K. Jabbour E. Johnson. Reg. IV B. J. Youngblood D. Kirsch, Reg. V S. Stern H. Thompson W. Butler i
F. Miraglia R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S, Showe S. Rubin
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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-18)
JUNE 2, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR S. Newberry ORAS/NRR R. Scholl ORAS/NRR J. T. Beard ORAS/NRR M. Caruso ORAS/NRR M. J. Virgilio ORAS/NRR F. Miraglia NRR/PWRB F. Schroeder NRR/PWRB D. Humenansky OCM D. Mcdonald NRR/PWRA R. W. Houston NRR/ DBL R. Baer IE/DEPER B. Sheron NRR/DSR0 T. Novak NRR/PWRA F. Rowsome NRR/DHFT T. Wambach NRR/PWRB A. Bournia NRR/ DBL K. Jabbour NRR/ PAD 4 P. Lam AE00 E. Weiss IE/DEPER L. Marsh NRR/DPLB W. Paulson NRR/PWRB l
j E. Brown AE0D M. Chiramal AE0D S. Rubin AE0D H. Bailey IE/DEPER V. Thomas IE/EGCB G. Murphy ORNL/N0AC E. Tourigny NRR/PWRB A. Thadani NRR/PWRB V. Benaroya NRR/PWRA W. Regan NRR/PWRB D. Crutchfield NRR/PWRB D. Allison IE/EAB E. Murphy ORAS/NRR B. Benedict NRR/BWL R. Hernan NRR/PPAS W. Swenson ORAS/NRR W. Haass IE/VPB G. Hubbard IE/VPB M. J. Campagnone NRR/ DBL L. Olshan NRR/PWRA S. Stern NRR/ DBL D. Vassallo NRR/ DBL-e
ENCLOSURE 2 c.
4 OPERATING REACTORS EVENTS BRIEFING 86-18 JUNE 2, 1986 LASALLE UNIT 2 FEEDWATER TRANSIENT WITHOUT REACTOR SCRAM IMPROPER USE OF HEAT SHRINKABLE TUBING ON ELECTRICAL CABLES PILGRIM SINGLE FAILURE COULD DISABLE ALL REDUNDANT RHR PUMPS TURKEY POINT UNITS 3,4 POTENTIAL SINGLE FAILURE OF DIESELS ST. LUCIE UNIT 1 STEAM GENERATOR TUBE INDICATIONS EXCEEDING PLUGGING LIMIT SUSQUEHANNA UNITS 1,2 LOSS OF ESW PUMPS PALISADES REACTOR TRIP OTHER EVENTS OF INTEREST BYRON UNIT'1 DERATING TO 75% POWER CATAWBA UNIT 2 CONTINUING FEEDWATER CONTROL PROBLEMS RIVER BEND MULTIPLE MOTOR-0PERATED VALVE ELECTRICAL QUALIFICATION PROBLEMS T
0 LASALLE UNIT 2 - FEEDWATER TRANSIENT WITHOUT REACTOR SCRAM JUNE 1, 1986 (A BOURNIA, NRR)
PROBLEM:
REACTOR VESSEL WATER LEVEL APPARENTLY FELL BELOW REACTOR SCRAM SETPOINT BUT GENERATED ONLY A HALF-SCRAM SIGNAL SIGNIFICANCE:
POTENTIAL ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)
' DISCUSSION:
PLANT NEAR FULL POWER; 1 NAIN FEEDWATER PUMP IN MANUAL, 1 MAIN FEEDWATER PUMP IN AUT0; VALVE TESTING IN PROGRESS MAIN FEEDWATER PUMP SPEED INCREASED AND THEN LOCKED-UP OPERATOR STARTED MOTOR MFW PUMP IN ANTICIPATION OF LOW-WATER LEVEL HI-LEVEL CAUSES RUNBACK OF MFW PUMPS LOW-LEVEL HALF-SCRAM SIGNAL (B/D TRIP SYSTEM); NO CONTROL R0D MOTION ON-COMING SHIFT REALIZED THAT PROTECTION SYSTEM MAY HAVE FAILED.
(LEVEL HAD FALLEN TO 2" VS. SETPOINT OF 12,5")
MANUAL HALF-SCRAM INSERTED INTO THE A/C TRIP SYSTEM THAT HAD APPARENTLY FAILED (B/D TRIP SYSTEM HAD BEEN RESET MANUALLY)
ALERT DECLARED; PLANT SHUTDOWN INITIATED FOLLOWUP:
TESTING OF " BLIND" LEVEL SWITCHES CALIBRATIONS:
3 WITHIN SPECS 1 TRIPPED LOW (CONSERVATIVE)
VERBAL AGREEMENT - NO RESTART W/0 NRC APPROVAL.
REGION III DISPATCHED PERSONNEL TO SITE NRR PROVIDING ON-SITE TECHNICAL SUPPORT CONFIRMATORY ACTION LETTER BEING ISSUED.
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IMPROPER USE OF HEAT SHRINKABLE TUBING ON ELECTRICAL CABLES MAY 14, 1986 (J. T. BEARD, NRR)
PROBLEM:
INSTALLATION OF HEAT SHRINKABLE TUBING OVER ELECTRICAL TERMINATIONS AND SPLICES THAT COULD CAUSE MULTIPLE FAILURES IN OFF-NORMAL AND ACCIDENT CONDITIONS SIGNIFICANCE:
COMMON MODE FAILURE MECHANISM MULTIPLE AND REDUNDANT SYSTEMS IN JEOPARDY, BOTH SAFETY-RELATED AND NON-SAFETY-RELATED GENERIC APPLICABILITY DISCUSSION:
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DAVIS-BESSE:
DISCOVERED DURING MANUFACTURER'S TRAINING SESSION, INSTALLATIONS THROUGHOUT PLANT NOT IN ACCORDANCE WITH MANUFACTURER INSTRUCTIONS OR EQ TEST CONFIGURATION i
SUBSEQUENT SAMPLE OF 71 SPLICES REVEALED:
98% NOT QUALIFIED FOR ACCIDENT CONDITIONS 68% NOT ACCEPTABLE FOR NON-ACCIDENT CONDITIONS TYPES OF DEFICIENCIES:
IMPROPER DIAMETER SELECTION IMPROPER OVERLAP (LENGTH) SELECTION TUBING DIRECTLY OVER FABRIC WIRE COVERING IMPROPER BENDING OF SPLICES INSIDE JUNCTION B0XES BECHTEL INSTALLATION INSTRUCTION INADEQUATE DAVIS-BESSE WILL "FIX" PRIOR TO PLANT RESTART OTHER PLANTS KNOWN TO HAVE SIMILAR PROBLEMS:
DRESDEN 2, COMMANCHE PEAK, WATTS BAR-MANUFACTURER'S INSTRUCTIONS USED DIRECTLY; APPARENT COMBINATION OF POOR WORKMANSHIP AND QA BREAKDOWN BARE ELECTRICAL CONDUCTORS FOUND AT MANY PLANTS FOLLOWUP:
INFORMATION NOTICE BEING DEVELOPED; EXPEDITED ISSUANCE LICENSEES EXPECTED TO MAKE OPERABILITY DETERMINATION FOR EACH DISCREPANCY; TAKE ACTIONS PER REGULATIONS AND TECH SPECS MANUFACTURER OFFERING FREE TRAINING TO NRC TO HELP RESOLVE PROBLEM-ADDITIONAL ACTION (E.G. BULLETIN) TO BE TAKEN IF WARRANTED f
PILGRIM - SINGLE FAILURE COULD DISABLE ALL REDUNDANT RHR PUMPS MAY 19, 1986 (ERIC WEISS, IE)
PROBLEM:
SINGLE FAILURE OF MINIFLOW LOGIC COULD DISABLE ALL REDUNDANT RHR PUMPS DURING SMALL OR INTERMEDIATE SIZE BREAK LOCA SIGNIFICANCE:
POTENTIAL SINGLE FAILURE CAUSES LOSS OF MULTIPLE SAFETY FUNCTIONS POTENTIAL FOR NO LONG TERM COOLING FROM SAFETY SYSTEMS CIRCUMSTANCES:
LICENSEE REVIEW (PROMPTED BY INF0 NOTICE 85-94) DISCOVERED THAT SINGLE FAILURE OF EITHER MINIFLOW SWITCH COULD PREVENT ALL AUTOMATIC LOW FLOW PROTECTION FOR ALL RHR PUMPS; PUMPS COULD BURN UP IF MANUAL ACTION NOT TAKEN IMMEDIATELY DURING SOME ACCIDENTS OR SPURIOUS ACTUATIONS, RHR PUMPS WOULD BECOME DEAD HEADED FOR EXTENDED PERIOD CURRENT MINIFLOW LOGIC DESIGNED TO BE CONSISTENT WITH LOOP SELECT LOGIC FOR LPCI WHEN FLOW DETECTORS IN EITHER LOOP SENSE ADEQUATE FLOW, BOTH RHR MINIFLOW LINE VALVES CLOSE CONSEQUENCE OF RHR PUMP LOSS IS LOSS OF LONG TERM COOLING WITH RHR HEAT EXCHANGERS, AND OTHER FUNCTIONS INCLUDING:
-SHUTDOWN COOLING MODE
-LOW PRESSURE COOLANT INJECTION
-HEAD SPRAY (REMOVED FROM PILGRIM)
-CONTAINMENT SPRAY
-TORUS SPRAY
-SUPPRESSION POOL COOLING WHICH EVENTUALLY WOULD CAUSE LOSS OF:
-LOW PRESSURE CORE SPRAY
-HIGH PRESSURE COOLANT INJECTION
-REACTOR CORE ISOLATION COOLING GE FIX IS TO ELIMINATE "CLOSE" SIGNAL TO MINIFLOW VALVES; COULD INCREASE PEAK CLAD TEMP 50*F IN SOME BREAK SIZES; NRC CONSIDERS THIS TO BE INTERIM ACTION FOLLOW-UP IE BULLETIN 86-01 ISSUED 5/23/86 IE AND GE ARE DETERMINING GENERIC SIGNIFICANCE NRR WILL REVIEW RESOLUTION FOR PLANTS WITH PROBLEM, INCLUDING TECHNICAL SPECIFICATION ISSUES
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TURKEY POINT UNITS 3 AND 4 - POTENTIAL SINGLE FAILURE OF DIESELS MAY 21, 1986 (D MCDONALD, NRR)
PROBLEM:
POTENTIAL SINGLE FAILURE COULD DISABLE BOTH EMERGENCY DIESEL GENERATORS SIGNIFICANCE:
POTENTIAL LOSS OF ALL ON-SITE POWER SOURCES
' DISCUSSION:
FOUND DURING LICENSEE SELECT SYSTEM DESIGN REVIEW 0F EDG LOADING SINGLE BREAKER SEPARATES NON-SAFETY-RELATED STUB BUS FROM SWING SAFETY-RELATED BUS, BETWEEN BUS 4A AND BUS 3B FAILURE OF BREAKER COULD CAUSE EDG TO TRIP ON OVERLOAD AUTO TRANSFER OF SWING BUS TO OTHER EDG BUS COULD CAUSE 2ND EDG TO TRIP FOLLOW-UP:
AUTO TRANSFER BETWEEN EDGs HAS BEEN DISABLED DEDICATED OPERATOR TO TAKE CORRECTIVE ACTION IF NEEDED.
JC0 PREPARED FOR INTERIM FIX LONG TERM CORRECTIVE ACTIONS WOULD INVOLVE REMOVAL 0F NON-SAFETY LOADS FROM STUB BUS REGION II FOLLOW-UP COMPLETED ON INTERIM FIX NRR REVIEWING EDG LOADS
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ST. LUCIE UNIT 1 - STEAM GENERATOR TUBE INDICATIONS EXCEEDING PLUGGING LIMIT MAY 23, 1986 (E. MURPHY, NRR)
PROBLEM:
RE-EVALUATION OF EDDY CURRENT TEST DATA FROM 1985 INSPECTION REVEALS 17 STEAM GENERATOR TUBES WHICH EXCEED 40% PLUGGING LIMIT IN TECH SPECS, BUT WHICH WERE NOT PLUGGED PRIOR TO PLANT STARTUP SIGNIFICANCE:
ADHERENCE TO PLUGGING LIMITS IS NECESSARY TO PRECLUDE RUPTURE UNDER NORMAL OPERATING, TRANSIENT, OR-ACCIDENT CONDITIONS (GDC 14, 31)
STEAM GENERATOR TUBE RUPTURE ACCIDENTS ARE COMPLEX EVENTS IN-VOLVING RELATIVELY HIGH POTENTIAL FOR SIGNIFICANT OFFSITE RELEASES MORE AGGRESSIVE EFFORT BY LICENSEE TO EVALUATE DISTORTED EDDY CURRENT TEST SIGNALS COULD HAVE REVEALED SITUATION PRIOR TO PLANT STARTUP LICENSEE DID NOT RECOGNIZE HE WAS OPERATING IN VIOLATION OF TECH SPECS AFTER PROBLEM WAS FIRST DISCOVERED ON ABOUT 5/23/86 CIRCUMSTANCES:
1985 0UTAGE INCLUDED A 100% STEAM GENERATOR TUBE INSPECTION ON EACH STEAM GENERATOR LICENSEE WAS STUDYING TUBE SAMPLES REMOVED FROM STEAM GENERATORS DURING 1985 0UTAGE AND RE-EVALUATING EDDY CURRENT TEST DATA FOR PURPOSES OF IDENTIFYING CORROSION MECHANISM AND TO RESOLVE NATURE OF DISTORTED EDDY CURRENT TEST SIGNALS SEEN ON APPR0XIMATELY 400 TUBES DURING 1985 INSPECTION 5/27/86 - NRR LEARNS OF SITUATION 5/28/86-NRRISSUED48-HOURWA)VERBASEDON5/29/86 LETTER FROM LICENSEE
ST, LUCIE UNIT 1 - CONTINUED CIRCUMSTANCES:
5/29/86 - LICENSEE MET WITH STAFF
- STAFF CONCLUDED THERE WAS INADEQUATE BASIS TO AMEND TECH SPECS TO PERMIT THE 17 TUBES TO REMAIN UNPLUGGED UNTIL NEXT REFUELING CYCLE
- STAFF WILL ALLOW ONE MONTH OPERATION WITH TIGHTER ADMINISTRATIVE CONTROLS ON PRIMARY TO SECONDARY LEAKAGE 5/30/86 - NRR ISSUED EMERGENCY TECH SPEC CHANGE ALLOWING ONE MONTH OPERATION WITH TUBES UNPLUGGED FOLLOW-UP:
CONSIDER NEED FOR IE INFORMATION NOTICE ON EDDY CURRENT TESTING CONSIDER UPGRADING CURRENTLY INACTIVE (" MEDIUM PRIORITY")
STAFF ACTION PERTAINING TO IMPROVED EDDY CURRENT TEST TECHNIQUES (G.I. 67) TO "HIGH PRIORITY"
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SUSQUEHANNA UNITS 1 AND 2 - LOSS OF ESW PUMPS MAY 23 - 24, 1986 (M. CAMPAGNONE, NRR)
PROBLEM:
LOSS OF THE "C" ESW PUMP, LICENSEE'S INVESTIGATION FOUND PROBLEM COMMON TO ALL ESW PUMPS SIGNIFICANCE:
LOSS OF THE ESW SYSTEM CAUSING LOSS OF COOLING TO DIESELS, RHR PUMP MOTOR LUBE OIL AND SEAL WATER COOLERS, ECCS ROOM COOLERS.
NO ALTERNATE SOURCE OF WATER IS AVAILABLE TO COOL THESE LOADS.
CIRCUMSTANCES:
NO INDICATION OF PUMP TROUBLE PRIOR TO CATASTROPHIC FAILURE OF THE ESW PUMP.
ALL PUMPS PASSED THEIR IST INSPECTIONS IN APRIL '86 MAY 21 CONTROL ROCM OPERATORS HAD INDICATION THAT ESW PUMP "C" WAS DAMAGED (PUMP MOTOR RUNNING NO FLOW).
LICENSEE ENTERED 7 DAY LCO MAY 23 PULLED PUMP "C" OUT OF WATER FOUND SEVERELY ER0DED IMPELLER, SUCTION BELL HAD FALLEN OFF, PUMP SHAFT SPLIT LICENSEE REQUESTED DIVER TO INVESTIGATE THE A ESW AND RHRSW PUMPS "A" RHRSW PUMP IN TACT, "A" ESW PUMP SEVERELY ERODED BOTH LOOPS OF ESW WERE DECLARED INOPERABLE AT 12:00 NOON LICENSEE COMMENCED AN ORDERLY SHUTDOWN, UNIT 2 SHUTDOWN AT 3:20 P.M., UNIT 1 SHUTDOWN AT 5:55 P.M.
BYRON JACKSON 24 BXF 1 STAGE PUMPS MADE ESPECIALLY FOR SUSQUEHANNA FOLLOW-UP:
LICENSEE IS HAVING REPLACEMENT PARTS MADE FOR ALL ESW PUMPS PUMP "C" HAS INTERIM FIX FOR COLD SHUTDOWN CONDITION ONLY LICENSEE HAS SENT PUMP MATERIAL TO A LAB TO INVESTIGATE ROOT CAUSE REGION I IS FOLLOWING REPAIR 1
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PALISADES - REACTOR TRIP MAY 19, 1986 (T WAMBACH, NRR)
PROBLEM:
MULTIPLE FAILURES TURBINE BY-PASS VALVE FAILED TO OPEN 1 STEAM DUMP VALVE FAILED TO OPEN BACKPRESSURE REGULATOR IN LET-DOWN LINE FAILED CLOSED PRESSURIZER SPRAY VALVE FAILED TO FULLY CLOSE l
VARIABLE SPEED CHARGING PUMP TRIPPED 5 TIMES SIGNIFICANCE:
UNNECESSARY CHALLENGES TO SAFETY EQUIPMENT INCREASED BURDEN ON OPERATORS TO COMPENSATE FOR FAILED OR DEFICIENT EQUIPMENT IMPLICATIONS CONCERNING THE QUALITY OF MAINTENANCE AND POST-MAINTENANCE TESTING SEQUENCE OF EVENTS:
PM ON TURBINE VALVE CONTROL CABINET FANS TURBINE VALVES CLOSED REACTOR TRIP ON HIGH PRESSURIZER PRESSURE TURBINE TRIP FIRST ATMOSPHERIC DUMP VALVE OPENED, AFW PUMP P-8A STARTED 2ND ATMOSPHERIC DUMP VALVE OPENED 3RD ATMOSPHERIC DUMP VALVE OPENED CHARGING PUMP P-55A STARTED (55B & C ALREADY RUNNING)
PRESSURIZER LEVEL LOW LAST LETDOWN ISOLATED CHARGING PUMP 55A TRIPPED THIS PUMP WAS RESTARTED 4 MORE TIMES TRIPPING 30 SECONDS LATER AFTER EACH START 14:22:15 PRESSURIZER LEVEL NORMAL PLANT PARAMETERS:
PRESSURIZER PRESSURE MAX 2245 PSIA, MIN 1689 PSIA T/ HOT MAX 594*F, MIN 535'F T/ COLD MAX 557'F, MIN 535*F S/G PRESSURE MAX 1025 PSIA S/G LEVEL DROPPED FROM 70 TO 12 PERCENT FOLLOWUP:
REGION III ISSUED A CONFIRMATORY ACTION LETTER REQUIRING REGION III APPROVAL PRIOR TO RESTART REGION III FORMED AN AIT WITH HQ.
SITE VISIT'MAY 22 THRU 25 LICENSEE FORMED TASK FORCE TO STUDY IMPLICATIONS ON PLANT MAINTENANCE
OTHER EVENTS OF INTEREST BYRON UNIT 1 - DERATING T0 75% POWER MAY 18, 1986 (L. OLSHAN, NRR)
PROBLEM:
STRESS CORROSION CRACKING ON PRIMARY SIDE OF STEAM GENERATOR HOT LEG TUBES SIGNIFICANCE:
POTENTIAL FOR LEAKING OR RUPTURED TUBES 1
DISCUSSION:
WESTINGHOUSE IDENTIFIED PROBLEM IN MODEL D AND E S.G. WITH MILL-ANNEALED INCONEL TUBES THAT HAVE FULL-LENGTH ROLL PROBLEM RELATED TO TEMPERATURE - BYRON 1 DERATED TO 75%
POWER TO LOWER HOT LEG TEMPERATURE;. PREVENTATIVE MEASURE OTHER OPERATING PLANTS EFFECTED MCGUIRE 1 - WILL SHOT-PEEN TUBES STARTING 6/1 MCGUIRE 2 - MAY SH0T-PEEN TUBES NEXT REFUELING RSUMMER 1 -
TUBES WERE ROT 0-PEENED CATAWBA 1 - MAY SHOT-PEEN TUBES NEXT REFUELING ALSO AFFECTS SOME PLANTS UNDER CONSTRUCTION AND FOREIGN REACTORS FOLLOW-UP:
BYRON 1 MAY SHOT-PEEN TUBES DURING NEXT OUTAGE STAFF TO MEET WITH LICENSEE REGARDING ISSUE
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J CATAWBA UNIT 2 - CONTINUING FEEDWATER CONTROL PROBLEMS MAY 1986 (K. JABBOUR, NRR)
PROBLEM:
DIFFICULTY IN LEVEL CONTROL OF NEW D5 STEAM GENERATOR 3 TRIPS AND 5 AFW ACTUATIONS IN FIRST 2 WEEKS AFTER LICENSING SIGNIFICANCE:
CONTINUED INTERRUPTION OF MFW AND CHALLENGES TO SAFETY SYSTEMS DISCUSSION:
NEW D5 S/G HAS SMALLER NARROW-RANGE INSTR. RANGE; CONSTANT-LEVEL CONTROL SYSTEM MAY BE T00 SENSITIVE NUMEROUS HI-LEVEL, LOW-LEVEL TRIPS; CAUSE NOT FULLY UNDERSTOOD WESTINGHOUSE CALLED FOR ASSISTANCE OPERATORS LEARNING HOW TO HANDLE CONTROL 4
FOLLOW-UP:
LICENSEE'S STATION AND MANAGEMENT PERSONNEL TRYING TO FIND SOLUTION NRR, RII FOLLOWING UP t
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RIVER BEND STATION - MULTIPLE MOTOR-0PERATED VALVE ELECTRICAL QUALIFICATION PROBLEMS JUNE 2, 1986 (S. STERN, NRR)
PROBLEM:
ENVIRONMENTAL QUALIFICATION OF LIMITOROUE MOTOR OPERATED VALVES (MOVs) IN QUESTION DUE TO UNLABELED WIRES INSIDE MOTOR OPERATOR SIGNIFICANCE:
OPERATION BEYOND COMMISSION DEADLINE FOR EQ WITH MOVs THAT MAY NOT HAVE FUNCTIONED UNDER HARSH ENVIRONMENT CONDITIONS ADEQUACY AND TIMELINESS OF LICENSEE ACTIONS EFFICACY OF INFORMATION NOTICE DISCUSSION:
IN 1983 AND 1986, IE ISSUED INFORMATION NOTICES 83-72 AND 86-03 IN-FORMING LICENSEES OF PROBLEMS WITH ENVIRONMENTAL QUALIFICATION (E0)
ON LIMITOROUE MOV WIRING SECY 86-122, " POLICY FOR ENFORCEMENT OF ENVIRONMENTAL QUALIFICATION REQUIREMENTS", CURRENTLY BEFORE THE COMMISSION TI 2515/75 (ISSUED 3/27/86) DEFINES INSPECTION CRITERIA FOR LIMITOROUE MOV WIRING LATE 1985, LICENSEE INSPECTS ALL MOVs INSIDE CONTAINMENT AND SAMPLE OUTSIDE CONTAINMENT 5/1/86 - REGION IV INSPECTOR IDENTIFIES ONE MOV OUTSIDE CONTAINMENT WITH QUESTIONABLE 2 INCH JUMPER WIRE LICENSEE INSPECTS SAMPLE MOVs OUTSIDE CONTAINMENT, IDENTIFIES 7 MOVs WITH QUESTIONABLE JUMPER WIRES 5/23/86 - LICENSEE AUDITS LIMITOROUE (AT LIMITOROUE)
IDENTIFIES 78 MOVs WITH QUESTIONABLE EQ DOCUMENTATION (BILL OF MATERIAL) 60 MOVs WITH ADEQUATE DOCUMENTATICN 5/29/86 - PLANT IN PLANNED OUTAGE ALL 78 MOVs WITH QUESTIONABLE EQ DOCUMENTATION INSPECTED 15% MOVs WITH ADEQUATE EQ DOCUMENTATION INSPECTED RESULTS OF LICENSEE INSPECTION 11 WIRES (IN 78 MOVs) WERE OF QUESTIONABLE QUALIFICATION; ALL REPLACED NO PROBLEMS IDENTIFIED IN MOVs WITH ADEQUATE DOCUMENTATION
RIVERBEND - CONTINUED FOLLOWUPi l
RESIDENT - REVIEWING LICENSEE RESULTS REGION IV - SPECIALIST FOLLOWUP e
CONSIDER THE NEED FOR ADDITIONAL GENERIC ACTION (E.G. ISSUE BULLETIN, PM CONTACT LICENSEES) ON LIMITOROUE MOVs EQ ISSUES l
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REACTOR SCRAM
SUMMARY
WEEK ENDING 05/25/86 1.
PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD CATIONS TOTAL 05/19/86 FARLEY 1
99 A EQUIP / TURBINE NO 2
05/19/86 PRAIRE ISLAND 2
100 A PERSONNEL / TEST NO 1
05/19/86 INDIAN POINT 3
25 A PERSONNEL NO 3
05/19/86 CATAWBA 2
17 A EQUIP /MFW CNTL YES 3
05/19/86 PALISADES 1
99 A EQUIP /EHC YES 2
05/19/86 RIVER BEND 1
75 A EDUIP/ TURBINE NO 11 05/19/86 INDIAN POINT 3
OA EQUIP /SR DETCTR NO 4
05/19/86 ZION 2
100 A PERSONNEL NO 2
05/20/86 PRAIRE ISLAND 2
19 A PERSONNEL NO 2
05/20/86 NORTH ANNA i
100 A UNKNOWN NO 4
05/21/86 MILLSTONE 1
10 M EQUIP /TURB NO 2
05/21/86 HATCH 1
85 A EQUIP NO 2
05/21/86 CALVERT CLIFFS 2
100 M EQUIP /MFW NO 2
05/23/86 INDIAN POINT 3
73 A UNKNOWN NO 5
05/23/86 INDIAN POINT 2
OA PERSONNEL / TEST NO 2
05/25/86 PALO VERDE 2
14 A PERSONNEL YES 1
SUMMARY
OF COMPLICATIONS SITE UNIT COMPLICATIONS CATAWBA 2 SECONDARY PORVS LIFTED PALISADES 1 ADDITIONAL EQUIPMENT FAILURES PALO VERDE 2 OVERCOOLING HPSI AND LPSI SETPOINTS REACHED
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s II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 05/25/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAGd YTD (3) (4)
- POWER'>15%
EQUIP.'RELATED
>15%
6 4.0 5.4 (68%)
PERS. RELATED(6) >15%
4 2.2 2.0 (25%)
4 OTHERf7)
>15%
2 O.1 O.6 ( 7%)
- Subtotal **
12-6.3 8.0
-** POWER <15%
~'
EQUIP. RELATED
<15%
2' 1.6 1.3 (54%)
4 PERS. RELATED
<15%
2 1.2,
- 0. 9 ~(38%)
OTHER
<15%
0
~'
0.1 0.2 ( 8%)
1
- Subtotal **
'4 2.9 2.4-
- Total ***
16 9.2 10.4 l
MANUAL VS AUTO SCRAMS i
TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS-AVERAGE AVERAGE YTD J
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MANUAL SCRAMS 2
0.7 1.0 AUTOMATIC SCRAMS 14 8.4 9.4 I_
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REACTOR SCRAM
SUMMARY
WEEK ENDING 06/01/86 I.
PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD CATIONS TOTAL 05/26/86 INDIAN POINT 3
16 A EQUIP /MFW YES 6
05/27/86 CALVERT CLIFFS 2
100 A EQUIP /MFW PMP NO 3
05/28/86 COOK 1
90 A EQu'IP/ TURBINE NO 1
05/28/86 INDIAN POINT 2
30 A EQUIP /TURB BYPS YES 3
05/29/96 NORTH ANNA 2
100 A PERSONNEL NO 3
05/31/86 SUMMER 1
100 A PERSONNEL / TEST NO 4
05/31/86 PALO VERDE 2
33 A EQUIP /TURB-GEN NO 2
05/31/86 NORTH ANNA 1
100 A EQUIP NO 5
06/01/86 MILLSTONE 2
18 A EQUIP / ELECT NO 1
06/01/86 YANKEE ROWE 1
100 A EQUIP / ELECT NO 1
SUMMARY
OF COMPLICATIONS SITE UNIT COMPLICATIONS i
INDIAN POINT 3 MAIN TRANSFORMER PROBLEM RC PUMP TRIPPED ON BUS TRANSFER INDIAN POINT 2 TRAIN B SAFETY INJECTION FAILURE ON DEMAND l
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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 06/01/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAGE YTD (3) (4)
- POWER >15%
EQUIP. RELATED
>15%
8 4.2
' 5. <4 (68%)
PERS. RELATED(6) >15%
2 2.2 2.0 (25%)
OTHER(7)
>15%
0 0.1 0.6 ( 7%)
- Subtotal **
10 6.5 8.0
- POWER <15%
EQUIP. RELATED
<15%
0 1.5 1.3 (54%)
PERS. RELATED
<15%
0 1.1 0.9 (38%)
OTHER
<15%
0 0.1 0.2 ( 8%)
- Subtotal **
O 2.7 2.4
- Total ***
10 9.2-10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS O
O.7
.1.0 AUTOMATIC SCRAMS 10 8.5 9.4-
NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST.
PERIOD IS MIDNIGHT SUN THROUGH MIDNIGHT SUN. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
2.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
3.
1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF UNPLANNED REACTOR TRIPS IN 1985.
WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
4.
IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES).
THIS YlELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
5.
BASED ON 95 REACTORS HOLDING A FULL POWER 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.
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ENCLOSURE 3 s
Page No.
1 05 4/86 OPERATING REACTORS EVENTS MEETIN6 FOLLOWUP ITEMS AS OF MEETING 86-18 DN JUNE 2, 1986 (IN ASCENDING MEETING DATE, NSSS VENDOR, FACILITY ORDER)
MEETING FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS NUCBER/
NSSS VENDOR /
DIVISION /
COMPLET. BY DOCUMENT, MEETING EVENT DESCRIP.
INDIVIDUAL DATE(S)
MEETIN6,ETC.
DATE 86-10 OYSTER CREEK NRR / HOUSTON W RESOLVE THE QUESTION OF THE 06/30/86 DPEN
/ /
FOLLOWUP ACTION TO 03/31/86 GE / LEVEL
/
ACCEPTABILITY OF BLIND SWITCHES
//
BE INCORPORATED IN SWITCH SETPOINT AND CELETION OF DAILY CHANNEL
//
REVIEW 0F JUNE DRIFT CHECK 1,1986 EVENT AT LASSALLE 85-10 BRAIDWOOD 1 hcR /NCCNAN V REQUEST REPORT OF EVENT FROM 06/30/86 OPEN
//
03/31/86 W / WATER
/
LICENSEE 05/30/86 HAMMER IN MAIN 05/01/86 STEAM LINE E6-10 HADDAM NECK NRR /SPEIS T ASSESS THE POTENTIAL FOR 05/30/86 CLOSED 06/03/86 03/31/86 W / NEW SMALL
/
SENERIC APPLICABILITY
/ /
MAY 19, 1986 BREAK LOCA
//
MEMO T. SPE!S RESULTS TD 6. HOLAHAN 86-13 FEACHBOTTOM IE /JCRDAN E EVALUATE NEED FOR IE NOTICE 05/30/86 CLOSED 06/03/86 04/21/86 SE / LOSS OF
/
/ /
IE NOTICE WILL CFFSITE POWER
//
NOT BE ISSUED SOURCE DUE TO A TRANSFORMER FIRE AND EDS FAILURE 96-13 RIVER BEND IE / JORDAN E DETERMINE NEED FOR VENDOR 06/25/86 OPEN
//
04/21/86 W / GA CONCERNS
/
INSFECTION 05/30/86 INVOLVINS
/ /
ARCHITECT ENGINEER l
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