ML20210T438
| ML20210T438 | |
| Person / Time | |
|---|---|
| Issue date: | 09/26/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| OREM-86-033, OREM-86-33, NUDOCS 8610090019 | |
| Download: ML20210T438 (18) | |
Text
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EP 29196 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 SEPTEMBER 22, 1986 - MEETING 86-33 On September 22, 1986, an Operating Reactor Events meeting (86-33) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on September 15, 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.
AN Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
See Next Page DISTRIBUTION
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W 2 71966 Harold R. Denton cc: R. Vollmer D. Wagner J. Taylor E. Adensam C. Heltemes E. Sylvester D. Ross D. Muller T. Murley, Reg. I M. Wegner J. Nelson Grace, Reg. II G. Plumlee J. Keppler, Reg. III W. Regan R. D. Martin, Reg. IV J. Wilson J. B. Martin, Reg. V G. Knighton R. Starostecki, Reg. I H. Pastis S. Ebneter, Reg. I J. Stolz R. Walker, Reg. II T. Chan C. Norelius, Reg. III H. Schierling E. Johnson. Reg. IV S. Varga D. Kirsch, Reg. V D. Neighbors H. Thompson K. Heitner F. Miraglia H. Berkow R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron B. Boger D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin 3 P. Baranowsky 4 i
SEP 27 586 ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-33) September 22, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR M. Wegner 01E/DEPER M. Virgilio ORAS/NRR D. Wagner DBL /NRR J. Stewart OIE/DEPER W. Haass IE/VPB K. Heitner DPWR/NRR H. Pastis PWRB/NRR K. West PWRB/NRR D. Vassallo DBL /NRR E. Sylvester DBL /NRR G. Plumlee DLPB/NRR-C. McCracken DPL/NRR G. Knighton PD7/NRR J. Wilson PDf/NRR V. Benaroya PAF0/NRR W. Regan PBF0/NRR B. Boger DHFT/NRR G. Murphy NOAC/0RNL A. Gill DPLA/NRR T. Chan DPLA/NRR P. Shemanski DPLB/,NRR J. Clifford NRR K. Eccleston TOSB/NRR W. Paulson DPLB/NRR D. Crutchfield PWRB/NRR G. Klingler IE/DI/0RPB A. Dromerick IE/DEPER D. Neighbors DPA/NRR J. Giitter IE/DEPER ^ H.' Bailey IE/DEPER H. Ornstein AE0D/R0AB E. Weiss IE/DEPER E. Jordan IE/DEPER J. Rosenthal IE/EAB G. Cwalina NHFT/NRR J. Stolz PWRB/NRR E. Rossi PWRA/NRR C. Miller PWRB/NRR F. Schroeder PWRB/NRR F. Miraglia PWRB/NRR R. Bernero DBL /NRR .W. Swenson ORAS/NRR D. Tarnoff ORAS/NRR F
OPERATING REACTORS EVENTS BRIEFING 86-33 SEPTEMBER 22, 1986 HOPE CREEK 1 LOSS OF 0FFSITE POWER TEST BRUNSWICK 1 SCRAM WITH COMPLICATIONS WATERFORD 3 LOSS OF SHUTDOWN COOLING OCONEE 3 10-INCH LINE BREAK AND SCRAM WITH COMPLICATIONS DIABLO CANYON 2 REACTOR TRIP AND SAFETY INJECTION t INDIAN POINT 2 DROPPED CONTROL RODS AND REACTOR TRIP OTHER EVENT OF INTEREST FORT ST. VRAIN C00LDOWN ANALYSIS ERRORS k i ,-m,,.
HOPE CREEK - LOSS OF 0FFSITE POWER TEST SEPTEMBER 9, 1986 (ERIC WEISS, IE) PROBLEM: LOSS OF 0FFSITE POWER (LOOP) TEST ABORTED AFTER 4 MINUTES BECAUSE OF COMPLICATIONS CAUSE: MULTIPLE EQUIPMENT MALFUNCTIONS AND PROCEDURAL PROBLEMS-SIGNIFICANCE: LOSS OF 0FFSITE POWER TEST IDENTIFIED PREVIOUSLY UNRECOGNIZED CONDITIONS . CONDITIONS MUST BE ANALYZED TO DETERMINE IF PROBLEM EXISTS, ROOT CAUSE OF PROBLEMS AND CORRECTIVE MEASURES CIRCUMSTANCES: PLANT AT 20% POWER WHEN TEST BEGINS PLANT SCRAMS NORMALLY AND NO ECCS ACTUATIONS REQUIRED REACTOR AUX COOLING SYSTEM (RACS) PUMPS TRIPPED AFFECTS DRYWELL COOLERS AND INSTRUMENT AIR PUMPS TRIP AS A RESULT OF LOW HEAD TANK LEVEL - CHILL WATER SYSTEM INTERFACE ** - LOSS POWER TO MAKEUP PUMP FALSE INDICATION OF FIRE IN INVERTER ROOM; CAUSE ATTRIBUTED TO EDG EXHAUST THROUGH SEALS IN ROOF FIRE CREW HAD TO REMOVE HINGES TO ACCESS DG FIRE PUMP ROOM; DOOR SHOULD NOT HAVE BEEN LOCKED CIRCUIT BREAKER DID NOT TRIP ~0N CIRC WATER BUS UPON LOOP * "B" SAFETY AUX COOLING SYSTEM (SACS) PUMP DID NOT RESTART
- CIRC WATER PUMP DISCHARGE VALVE "D" INDICATION PROBLEM
- A DRYWELL COOLING FAN FAILED TO RESTART
- SRV INDICATED OPEN WHEN NOT; CAUSE ATTRIBUTED TO NOISE FROM OTHER VALVES "A" & "B" DGs SWITCH TO DROOP MODE AFTER OFFSITE POWER IS RESTORED; PROCEDURAL PROBLEM TURBINE BUILDING CHILLED WATER PROBLEM; CAUSE ATTRIBUTED TO LOOSE SET SCREW ON ACTUATOR 18 RODS FAIL TO INDICATE FULL-lN AFTER SCRAM (AT POSITION 00)
- 14 DID NOT PICK UP REED SWITCH; REPLACED CHIPS 4 LAMP PROBLEMS; POSITION 00 WASFINDICATED
~ HOPE CREEK 2 CIRCUMSTANCES - (CONTINUED) SRMs & IRMs COULD NOT BE DRIVEN IN AND ACTUATED; NON-1E POWER TO DRIVES REACTOR BUILDING SUPPLY AND EXHAUST FANS TRIPPED; SYSTEM DAMPERS ON NON-1E POWER ** RSCS AND ACOUSTIC MONITOR FOR SAFETY / RELIEF VALVES LOST POWER ** "C" EDG OUTPUT BREAKER FAILED TO CLOSE; BAILEY LOGIC MODULE PROBLEM FALSE INDICATION OF HOT BEARING ON SCREEN WASH PUMP OTHER MINOR PROBLEMS IDENTIFIED TEST RE-RUN FROM NON-CRITICAL CONDITION ON 9/19 IDENTIFIED ADDITIONAL DEFICIENCIES FOLLOWUP: REGION I FOLLOWING LICENSEE CORRECTIVE ACTION PROGRAM
- INDICATES THAT NO CAUSE WAS FOUND AFTER INVESTIGATION
- INDICATES AN ERROR IN DESIGN IMPLEMENTATION THAT WILL BE CORRECTED d
~ BRUNSWICK 1 - SCRAM WITH COMPLICATIONS SEPTEMBER 13, 1986 - (M. WEGNER, IE) PROBLEM: POWER SUPPLY LOGIC ALIGNED 1E BUSSES TO EDGs ON SENSING DEGRADED VOLTAGE CONDITIONS WITH PREFERRED OFFSITE POWER STILL.AVAILABLE (AS DESIGNED) SUBSEQUENT REACTOR TRIP COMPLICATED BY HUMAN ERROR AND NUMEROUS HARDWARE MALFUNCTIONS CAUSE: EQUIPMENT MALFUNCTION AND PERSONNEL ERROR SIGNIFICANCE: CHALLENGE TO RPS AND~ECCS OPERATOR ERROR AND EQUIPMENT MALFUNCTION POTENTIAL DESIGN DEFICIENCY DISCUSSION: ON 9/13/86 UNIT WAS AT 100% POWER, TECHNICIANS TROUBLESHOOTING MAIN GENERATOR VOLTAGE REGULATOR CONTROL CIRCUIT CONTROLLER FAILED DECREASING VOLTAGE ON CLASS 1E BUSSES CLASS 1E BUSSES SEPARATED, EDGs STARTED AND LOADED MSIVs ISOLATEDJDN LOSS OF POWER TO STEAM LINE TEMPERATURE SWITCHES AND REACTOR TRIPS REACTOR TRIP AND RECOVERY COMPLICATED BY OPERATOR ERROR AND EQUIPMENT MALFUNCTIONS - HPCI OSCILLATIONS - RCIC RELIEF VALVE FAILURE SRV POSITION INDICATION MALFUNCTIONED RPS M/G SET "B" BREAKER STUCK IN TRIPPED CONDITION IRM "F" CABLE AND CONNECTOR PROBLEMS APRM "F" FAILED UPSCALE MAIN STEAM RAD MONITOR "B" FAILED BACKUP NITROGEN LOW PRESSURE ALARM FOLLOW-UP: NRR AND IE REVIEWING DESIGN CONFORMANCE TO GDC-17 f
O WATERFORD 3 - LOSS 1)F SHUTDOWN COOLING (SDC) JULY 14, 1985 - (G.L. PLUMLEE, NRR) PROBLEM: INTERMITTENT LOSS OF SDC FOR A PERIOD OF APPR0XIMATELY THREE AND ONE-HALF HOURS CAUSE: PERSONNEL ERROR AND PROCEDURAL DEFICIENCY SIGNIFICANCE: LPSI PUMP CAVITATION / LOCALIZED BOILING IN THE CORE PLANT IN POTENTIALLY UNANALYZED CONDITION DISCUSSION: OPERATIONS PERSONNEL WERE DRAINING THE REACTOR COOLANT SYSTEM (RCS) VIA TWO DRAIN PATHS (LPSI AND LETDOWN LEGS) TO FACILITATE RCP SEAL REPLACEMENT - CORE COOLING MAINTAINED BY SDC TRAIN "B" VIA LPSI PUMP "B" - RCS INVENTORY MONITORED LOCALLY THROUGH THE USE OF TYGON TUBING AND IN.THE CONTROL ROOM BY THE REACTOR VESSEL LEVEL MONITORING SYSTEM LOCAL LEVEL INDICATIONS EXPERIENCED PROBLEMS THROUGHOUT THE DRAINING OPERATION (N USED TO MAINTAIN POSITIVE PRESSURE) 2 0113 - DRAINING SECURED (ONLY ONE PATH) WITH BOTH LOCAL AND REMOTE ERR 0NEOUS LEVEL INDICATIONS UPON VENTING, LOCAL INDICATOR INDICATED VESSEL LEVEL AT 9 FEET (WELL BELOW THE HOTLEG) ORIGINAL VENTING OPERATOR SUFFERED HEAT PROSTRATION 1 l
WATERFORD 3 - LOSS OF SHUTDOWN COOLING (SDC) DISCUSSION, (CON'T.)' 0317 - LPSI PUMP "B" CAVITATED - OPERATORS SECURED PUMP AND SECOND DRAIN PATH - "A" PUMP STARTED AND CAVITATED - OPERATORS REALIGNED PUMPS SUCTION TO REFUELING WATER STORAGE POOL 0351-VESSEL LEVEL RESTORED TO 13 FEET (JUST BELOW CENTERLINE OF HOTLEG) 0400 - Tg = 223*F 0658 - SDC RESTORED T INCREASED FROM 138*F TO A MAXIMUM 234*F DURING THIS EVENT H LICENSEE CORRECTIVE ACTION - PROCEDURE REVISIONS AND ENHANCED TRAINING FOLLOW-UP: REGION IV FOLLOW-UP ON LICENSEE'S REPORTING OF THIS EVENT NSSS VENDOR PERFORMING CONFIRMATORY ~ ANALYSIS TO SUPPORT LICENSEE'S INITIAL POST-EVENT ANALYSIS g> 1
OCONEE 3 - TEN-INCH LINE BREAK AND REACTOR TRIP WITH COMPLICATIONS SEPTEMBER 17, 1986 - (H. PASTIS, NRR) PROBLEM: SCRAM COMPLICATED BY SEVERAL INDEPENDENT FAILURES .CAUSE: MULTIPLE EQUIPMENT MALFUNCTIONS SIGNIFICANCE: CHALLENGE TO PLANT SAFETY SYSTEMS AND OPERATORS DISCUSSIONI UNIT 3 AT 100% POWER ICS TAKEN TO MANUAL TO PERFORM RPS ON-LINE CRD BREAKER TEST. ICS TAKEN BACK TO AUTO WHEN FW SWING DEVELOPED. CATASTROPHIC RUPTURE OF A 10-INCH ELBOW IN THE FIRST STAGE REHEATER DRAIN TANK LINE TO "B" HEATERS. OPERATORS INITIATED POWER REDUCTION MANUAL TRIP OF THE REACTOR ONE MINUTE FOLLOWING PIPE RUPTURE; FEEDWATER PUMPS TRIPPED; EMERGENCY FEEDKATER ACTUATED WHILE IN POST-TRIP VITAL PARAMETER CHECK, ICS INVERTER SYSTEM TROUBLE ALARM ACTUATED AND ICS STATIONS TRIPPED TO MANUAL ON LOSS OF KI INVERTER APPROXIMATELY 3 MINUTES FOLLOWING REACTOR TRIP PORV OPENED (FOR ABOUT TWO SECONDS) BUT RECLOSED MSRV 3 FAILED TO RESEAT. OPERATORS LOWERED STEAM HEADER PRESSURE TO 850 PSIG AND VALVE RESEATED. "A" SG EFW LEVEL CONTROL VALVE FAILED. STEAM GENERATOR "A" WATER LEVEL REACHED 80 INCHES IN LIEU OF NORMAL POST TRIP LEVEL SETPOINT 0F 25 INCHES. N0H SAFETY RELATED 600 VOLT MCC TRIPPED ON OVERCURRENT 9/18 - REACTOR RETURNED TO CRITICAL, THEN UP TO 12% POWER AS REPAIRS WERE BEING MADE DUKE ULTRASONICALLY TESTED OTHER ELBOWS IN UNIT 3. SIMILAR TESTING TO BE PERFORMED ON UNITS 1 AND 2. REPLACED 6 ELB0WS ON UNIT 3 AND 2 ON UNIT 1. UNIT 2 IN REFUELING OUTAGE; INSPECTION TO BE DONE BEFORE STARTUP FOLLOWUP: SENIOR RESIDENT INSPECTOR IS FOLLOWING UP ON THE EVENT TO OBTAIN ADDITIONAL INFORMATION U 9 e-r ._y
DIABLO CANYON 2 - REACTOR TRIP AND SAFETY INJECTION SEPTEMBER 18, 1986 - (T. CHAN, NRR) PROBLEM: REACTOR TRIP WITH COMPLICATIONS CAUSE: EQUIPMENT MALFUNCTION SIGNIFICANCE: POTENTIAL FOR OVERC00 LING OF RCS AND OTHER COMPLICATIONS FROM INADVERTENT SAFETY INJECTION SIGNAL CIRCUMSTANCES: UNIT 1 DOWN FOR REFUELING, UNIT 2 AUXILIARY BOILER NOT FUNCTIONAL NEW MFP 2-2 CONTROLLER IN MANUAL, AND BEING ADJUSTED ONE ESFAS HI STEAM FLOW BISTABLE IN TRIP FOR MAINTENANCE DISCUSSION: MFP 2-2 CONTROLLER FAILED LOW RESULTING IN MINIMUM FLOW - NO PUMP TRIP REACTOR TRIP FROM 100% POWER DUE TO LOW SG LEVEL COINCIDENT 'WITH STEAM FLOW / FEED FLOW MISMATCH RESULTING TURBINE TRIP / FLOW DYNAMICS RESULT IN FLICKERING OF HI STEAM FLOW BISTABLE SAFETY INJECTION DUE TO HIGH STEAM FLOW COINCIDENT W/ LOW LOW TAVE (543*F) MSIVs DID NOT CLOSE DUE TO MOMENTARY FLICKER OF THE HIGH STEAM FLOW BISTABLE (SIGNAL DID NOT SEAL IN) ALL SYSTEMS RESPONDED NORMALLY SI SECURED AFTER APPROXIMATELY 4 MINUTES MIN. TAVE 516 F - 520*F, MIN. RCS PRESS. 1985 PSIG MIN. PRESS. LEVEL 26%; LOWER THAN ANTICIPATED TAVE CAUSED BY USE OF REACTOR STEAM RATHER THAN AUXILIARY STEAM FOR GLAND SEALING, TURBINE DRIVEN AUXILIARY FEED PUMP, ETC. - FOLLOW-UP: LICENSEE IS FOLLOWING UP DN FEED PUMP CONTROLLER FAILURE AND SPURIOUS HIGH STEAM FLOW SIGNAL
INDI AN POINT 2 - DROPPED CONTROL RODS AND REACTOR TRIP SEPTEMBER 16, 1986 - (D, NEIGHBORS, NRR) PROBLEM: DROPPED CONTROL ROD, MANUAL REACTOR TRIP AND STUCK PRESSURIZER SPRAY VALVE CAUSE: EQUIPMENT MALFUNCTION SIGNIFICANCE: MANUAL' REACTOR SCRAM COMPLICATED BY STUCK PRESSURIZER SPRAY VALVE , DISCUSSION: UNIT 2 AT 100% POWER, CONTROL ROD TESTING IN PROGRESS CONTROL R0D E-9.IN SHUTDOWN BANK A, GROUP 2 HAD EXPERIENCED PREVIOUS DROPS DURING R0D TESTING JUMPER APPLIED ACROSS SAMPLING RESISTOR IN CIRCUIT TO E-9 IN AN ATTEMPT TO PREVENT R0D DROP CAUSED LOWER VOLTAGE TO 3 OTHER RODS IN SAME BANK, WHICH DROPPED DURING R0D EXERCISE OPERATOR MANUALLY TRIPPED REACTOR SAFETY INJECTION SIGNAL ON LOW TAVE COINCIDENT WITH HI-STEAM FLOW RESULTED IN GENERATOR TRIP - * - TRIP CAUSED TURBINE OVERSPEED TRIP POST-TRIP REVIEW FOUND THAT PRESSURIZER SPRAY VALVE DID NOT OPEN FOR 10 MINUTES SUBSEQUENT EXERCISES DEMONSTRATED SPRAY VALVE OPERABLE FOLLOW-UP: WESTINGHOUSE AND LICENSEE ANALYZING R0D PROBLEM LICENSEE EVALUATING STUCK SPRAY VALVE TO DETERMINE ROOT CAUSE
c OTHER EVENT OF INTEREST FORT ST VRAIN - C00LDOWN ANALYSIS ERRORS SEPTEMBER 17, 1986 - (K. HEITNER, NRR) PROBLEM: LICENSEE REANALYSIS OF C00LDOWN SCENARIOS IhDICATES ORIGINAL LICENSING BASIS CANNOT BE MET CAUSE: N/A SIGNIFICANCE: REACTOR COULD NOT BE SHUTDOWN WITH CLASS 1E SYSTEMS FROM FULL POWER WITHOUT FUEL OR EQUIPMENT DAMAGE REACTOR POWER WOULD HAVE TO BE LIMITED DISCUSSION: C00LDOWN SCENARIOS REANALYZED IN EQUIPMENT QUALIFICATION PROGRAM LIMITATIONS ON REHEATER C00LDOWN ANALYSIS PREVIOUSLY REPORTED: - 50.72 REPORT 7/11/86 LER 86-020 8/11/86 CURRENT REPORT IS FOR LIMITATIONS ON ECONOMIZER EVAPORATOR -- SUPERHEATER C00LDOWN ANALYSIS LICENSEE CONTINUING TO REFINE ANALYSIS BY VARYING POWER LEVELS, HELIUM FLOWS, ETC. MAY ALSO AFFECT APPENDIX R SAFE SHUTDOWN ANALYSIS FOLLOW-UP: NRR TO PROPOSE LETTER TO LICENSEE REQUESTING: - SCHEDULE FOR COMPLETING ANALYSIS - SUBMITTAL OF ANALYSIS - COMMITMENT TO NECESSARY LIMITS NRR TO REVIEW ANALYS!S PRIOR TO RESTART (SCHEDULED 12/1/86) NRR TO MODIFY LICENSE AS APPROPRIATE l-
FORT ST. VRAIN ( STORAGE PONDS REHEATER TO i n V 0C 1 p CIRCULATING J k l2k 2k WATER MAKEUP PUMPS AND PIT b V V ECONOMlZER TO EVAPORATOR ~ SERVICE m SUPERHEATER ~ SECTION p' g WATER r SUPPLY l h CIRCULATOR rm 1 V 1 V FIRE FIRE WATER / PUMP PUMP DRIVE / .BOU RY PIT PIT ~ ~ ~~ ENGINE ORIVEN i 4- ~ FIRE PUMPS q ] O \\.y EMERGENCY WATE_R BOOFER MOTOR PUMPS ORIVEN I J L 4 EMERGENCY CONDENSATE LINE EMERGENCY FEE 0 WATER LINE l l i Schematic Flow Diagram: Cooling with Safe Shutdown Equipment ( l
~ REACTOR SCRAM'
SUMMARY
WEEK ENDING 09/21/G6 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE BELOW ~ TOTAL 15% 15% O?/15/86 SAINT LUCIE 2 100 A EQUIP / MECH. NO 2 1 3 09/16/86 INDIAN POINT 2 100 M PERS./ ROD TEST. YES 7 1 8 09/17/96 OCONEE O 100 M EQUIP /PIFE RUPT YES 2 0 2 09/17/86 LRUNSWICK 1 6M EQUIP / MECH NO 4 2 6 07/10/86 LACROSSE 1 74 A EQUIPMENT NO 5 9 14 09/10/86 DIAbLO CANYCN 2 100 A PERSONNEL / TEST YES 10 1 11 O?/19/86 SAINT LUCIE 1 100 M EQUIP./ MECH. NO 3 0 3 09/19/86 SAINT LUCIE 1 10 A EQUIP /SG LVL CN NO 3 1 4 09/1?/a6 SURRY 1 20 M EQUIP / ROD DROP NO 3 1 4 09/20/06 LACROSSE 1 OM EQUIPMENT NO 5 10 15 C?/20/96 ZION 2 10 A EQUIP./ MECH. NO 3 1 4 09/21/86 TURKEY POINT 3 100 A EQUIP./ TEST NO 5 1 6 r
SUMMARY
OF COMPLICATIONS SITE UNIT COMPLICATIONS ' *1 INDIAN POINT 2 PRESSURIZER SPRAY VLV FAILED TO OPEN ON DEMAND OCONEE 3. LOSS OF KI INVERTER EFW LEVEL CONTROL VALVE FAILED DIAELO CANYON 2 FALSE HIGH STEAM FLOW SIGNAL RESULTS IN SI
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 09/21/86 SCRAM CAUSE POWER NUMDER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE YTD (3) (4)
- POWER '>15%
EQUIP. RELATED >15% 6 4.9 5.4 (68%) PERS. RELATED(6) >15% 2 2.0 2.0 (25%) OTHER(7) >15% O O.6 0.6 ( 7 , ) +* Subtotal *+ 8 7.5 8.0
- POWER <15%
EQUIP. RELATED <15% 4 1.6 1.3 (54%) PERS. RELATED <15% 0 0.9 0.9 (38%) OTHER <15% 0 0.2 0.2 ( 8%)
- Subtotal **
4 2.7 2.4
- Total ***
12 10.2 10.4 o MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 6 1.1 1.0 AUTOMATIC SCRAMS 6 9.0 9.4 --i r.,
W NOTES 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY 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. REC 0VERY 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 YIELDS 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 100 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.
ENCOSURE 3
- age No.
8 )9/25/86 CPERATIN6 REACTORS EVENTS MEETING FOLLOWUP ITEMS AS OF MEETIh6 86-33 DN SEPTEMBER 22,1986 (IN ASCENDIN6 MEETING DATE, NSSS VENDOR, FACILITY ORDER) tEETIN6 FACILITY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS fjMBER/ NSSS VEhCOR/ DIVISION / COMPLET. BY DOCUMENT, IEETINS. EVENT DESCRIP. INDIVIDUAL DATE(S) MEETING,ETC. ) ATE D-10 OYSTER CREEK NRR / HOUSTON N RESOLVE THE QUESTION OF THE 10/30/86 DPEN // FOLLOWUP ACTION TD )3/31/86 EE / LEVEL / ACCEPTABILITY OF BLIND SWITCHES // BE INCORPORATED IN SWITCH SETPOINT AND DELETION OF DAILY CHANNEL // REVIEW 0F JUNE DRIFT CHECK 1,1986 EVENT AT LASSALLE 16-21 VERPCNTYANKEE NRR /HOLAHAN 6. DETERMINE STATUS AND 09/30/86 QPEN // 16/23/86 SE / PROBLEMS / EFFECTIVENESS OF STAFF AND // WITH SCRAM LICENSEE ACTION ON // 50LEN0!D VALVES POST-MAINTENANCE TESTING (6L 83-28). DEVELOP RECOMMENCATIONS FOR FURTHER ACTION 36-23 MULTI NRR / HOUSTON W. DETERMINC APPROPRIATE 09/30/86 OPEN // 27/07/86 NA / / RESULATORY REDUIREPENTS BASED // BWRS-RESIDUAL ON RECOMMENDATIONS DISCUSSED AT // HEAT REMOVAL BRIEFING PUMP / WEAR RING FAILURES - FOLLOWUP. 86-28 ERAND GULF IE /JOREAN E. ASSESS POTENTIAL FOR GENERIC 09/30/86 OPEN // OS/11/E6 _6E / CONTROL ROD / APPLICABILITY // WITHDRAWAL / / PROBLEM 86-32 NINE MILE PT 1 NRR / ROSA F. DISCUSS WITH LICENSEE AND 10/24/86 DPEN // 09/15/86 SE / SCRAM NRR /ZWOLINSK! J. RES!0N LICENSEE'S ./ / DUTLET VALVE IMPLEMENTATION OF 6L 83-28 IN / / DIAFHSRAM REFERENCE TO 09/08/86 EVENT FAILURE File has hee deleted. -}}