ML20244E387
| ML20244E387 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/16/1986 |
| From: | Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Krimm R Federal Emergency Management Agency |
| Shared Package | |
| ML20244D847 | List:
|
| References | |
| FOIA-88-198 NUDOCS 8610230109 | |
| Download: ML20244E387 (36) | |
Text
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OCT 161986 l MEMORANnVM FOR: Richard W. Krimm Assistant Associate Director Office of Natural and Technological Hazards Program Federal Emergency Management Agency Edward L. Jordan, Director FROM:
Division of Emergency Preparedness and Engineering Response Office of inspection and Enforcement
SUBJECT:
PILGRIM 10 CTR 2.206 PETITION An August 11, 1986 memorandum from David B. Matthews of my staff to Robert S.
Wilkerson of your staff forwarded a petition to prohibit the restart of Pilgrim nuclear power plant and stated that we would request FEMA's support in prepar-ing a final response to this petition.
I am now confirining that FEMA has agreed to provide NRC with their evaluation of the offsite emergency planning and preparedness issues raised in the petition.
As discussed with a member of your staff we understand that you will provide your response by December 15, 1986.
orw n ! s + .d syi 0 Q Men Edward L. Jordan, Director Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement CONTACT: G. E. Simonds, IE Distribution:
492-4870 RW5tarostecki, IE GESimonds, IE JGPartlow, IE JLieberman, OGC BKGrimes, IE Pleech, NRR ELJordan, IE PMcKee, IE SASchwartz, IE WDPaton, OGC DBMatthews, IE DCS KEPerkins, IE DEPER R/F ;
JAAxelrad, IE EPB R/F CRVan Niel, IE FKantor, IE GRKlingler, IE 7+ I E EPB/J E EPp/IE #f!TEP /IE ds CLVah.iel D tthews , SASche rtz ELJordan 0/86 IO/ju86 10/ 10 /86 10/(g/86 10//v/86 g- _
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7:~mzamu=mcz.m2 um.2:ar::xw.2:;ns:m;c:cc :,. - :Anwce: .x "; a;w.2;+ - a k-OPERATING REACTOR EVENTS BRIEFING 86-38 NOVEMBER 3,-1986 MCGUIRE 1 AND 2 BOTH TRAINS OF ECCS INOPERAELE OTHER EVENTS OF INTEREST ZION 1 CATASTROPHIC FAILURE OF EMERGENCY DIESEL GENERATOR IB PILGRIM STANDBY GAS TREATMENT SYSTEM DESIGN DEFICIENCIES ANALYSIS OF REACTOR SCRAM FREQUENCY EARLY IN PLANT.
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. 1 FCGUIRE 18 2 - BOTH TRAINS OF ECCS It,' OPERABLE OCTOBER 28, 1986 - (R. KIESSEL, IE)
PROBLEM:
LICENSEE CHANGES TO MOV TOROUE SWITCH SETTING MADE l VALVE POST ACCIDENT OPERABILITY OUEST10NABLE CAUSE: INSTALLATION ERROR, LICENSEE MADE CHANGES TO MOV TOROUE '
SWITCH SETTINGS WITHOUT CONSULTING VALVE OPERATOR V SIGNIFICANCE:
POTENTIAL COMMON MODE FAILURE OF A SIGNIFICANT NUMBER Ol SAFETY-RELATED VALVES j
D_lSCUSSION: '
Wl"LE LICENSEE PERFORMING IEB 85-03 EVALUATIONS, IT WAS DETERMIN (
- THAT TOROUE SWITCH SETTINGS MAY NOT BE CONSERVATIVE LICENSEE CONCLUDED THAT TWO CHARGING HEADER ISOLATION i VALVES AT EACH UNIT MIGHT NOT CLOSE WHEN REOUIRED '
- LICENSEE LOCKED VALVES CLOSED AND SHUT DOWN BOTH UNITS HPRDS JATA INDICATES THE FOLLOWING APPR0XIMATE DISTRIBU{
VALVES WITH ROTORK OPERATORS I UNIT NUMBER OF VALVES STATUS EACH MCGUIRE 275 S/D EACH CATAWBA 175 S/D FOR OTHER REASONS EACH OCONEE 15 OPERATING 3 ADDITIONAL 30 - 40 VARIOUS 15 ADDITIONAL LESS THAN 10 VARIOUS e
i
~ LICENSEE HAS MADE AN OPERABILITY DETERMINATION FOR ROTORK AT OCONEE ROTORK INFORMATION INDICATES THAT 29 PLANTS OTHER THAN DUKE PLANTS HAVE VALVES WITH THEIR OPERATORS ONLY 13 0F THESE PLANTS ARE SAME AS NPRDS LIST '
NUMBER OF VALVES AT EACH PLANT NOT CURRENTLY KNOWN FOLLOW-UP: l REGION 11 HAS ISSUED A PN LICENSEE IS VERIFYING THAT VALVES AT MCGUIRE HAVE CONSERVATI TOROUE SWITCH SETTINGS l
REGION 11 FOLLOWING LICENSEE ACTIVITIES i REGION 11 AND lE ARE ISSulNG AN INFORMATION NOTICE TO ALL CP AND OL PLANTS l
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PROBLEM WITH ENGINE RUNNING AT APPROXIMATELY 1000 KW CRANK OF ARTICULATED ROD 4 LEFT (4L) BROKE AND ALLOWED ROD SEPARATE FROM CRANK SHAFT,
- RESULTING IMBALANCE AND MECHANIC INTERFERENCE CAUSED ARTICULATED R0D 4L AND COUNTE
' BE THROWN THRU RIGHT. SIDE OF ENGINE CAUSE: MAINTENANCE ERROR SIGNIFICANCE:
PLANT.IN REFUELING OUTAGE SO NEITHER IA NOR IB EDG REQUIRED OPERABLE WITH OFFSITE POWER CIRCUMSTANCES:
IB EDG HAD JUST UNDERGONE PISTON, RINGS AND LINER REPLACEMENT ON CYLINDERS 4L, 7L AND 5 RIGHT ENGINE RUN 50 MIN, AT NO LOAD, I HR, 35 MIN. AT 1000 KW FOR POST-MAINTENANCE TEST
~*
LOUD KNOCKING, VIBRATION CAUSED OPERATORS TO TRIP UNIT AND LEAVE ENGINE ROOM INTERNAL PARTS EXITED THROUGH EXPLOSION COVER AS OPERATORS REACHED DOOR NO PERSONAL INJURIES OR FIRE ENGINE COASTED DOWN (N0 SEIZURE OF CRANK) !
OIL, WATER AND PIECES OF ENGINE IN ROOM SOME SLIGHT MISSILE DAMAGE (CONDUIT AND AIR START RECEIVER)
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ZION 1, (CON'T,')
CIRCUMSTANCES, (CON'T.)
INVESTIGATION DETERMINED THAT INSUFFICIENT TOROUE APPLIED l
ARTICULATED ROD CRANK PIN BOLTS
- TOROUE REQUIRED = 11L0!
FT-LBS (COOPER MAllUAL)
- TOROUE APPLIED = "690 10 FT-LBS" (BY ZION PROCEDURE)
TORQUE APPLIED WAS CORRECT FOR PISTON PIN BOLTS, INCORRECT FOR ARTICULATED ROD' CRANK PIN BOLTS l
PROCEDURE OMITS ALL REFERENCE TO CRANK PIN BOLTS. TOROUE VALUE.FOR PISTON PIN ASSUMED TO APPLY TO CRANK PIN BOLTS.
FOLLOWUP: -
VENDOR REPRESENTATIVES ONSITE EDG ENGINE TO BE REPAIRED Rill TO CONVENE MEETING OF ALL PARTIES ONSITE WEEK OF 11/3/86 TO EVALUATE CORRECTIVE / PREVENTIVE ACTION.
PROJECT MANAGER FOLLOWING.
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OTHER EVENT OF INTEREST PILGRIM - STANDBY GAS TREATMENT (SBGT) SYSTEM DESIGN DEFICIENCIES NOVEMBER 3, 1986 - (R. AULUCK, NRR)
PROBLEM:
SINGLE ACTIVE FAILURES WHICH DIMINISH THE ABILITY OF SBGT SYSTEM TO PERFORM ITS SAFETY FUNCTION CAUSE:
DESIGN DEFICIENCY - REDUNDANCY NOT PROVIDED SIGNIFICANCE:
POTENTIAL FOR RELEASE EXCEEDING 10 CFR.PART 100 LIM GIVEN A SINGLE F'AILURE IN STANDBY GAS TREATMENT SYS DISCUSSION:
ON AUGUST 27, 1986, THE LICENSEE (BECO) CONCLUDED THAT SINGLE' ACTIVE FAILURE OF SBGT DELUGE SYSTEM DURING POSTULATED D LOCA OR FUEL HANDLING ACCIDENT COULD RESULT IN OFFSITE DOSE EXCEEDING'PART 100 LIMITS.
- INADEQUATE SBGT SYSTEM / DELUGE SYSTEM INTERACTION CONSIDE THE ORIGINAL DESIGN.
- DELUGE SYSTEM PROVIDL' COOLING AND FIRE PROTECTION SPRAY IN
' RESPONSE TO HIGH TEMPERATURES IN SBGT CHARC0AL FILTERS.
i - INITIATION OF THE DELUGE SYSTEM DUE TO FAILURE OF ANY OF THE AC COMPONENTS WILL RESULT IN SOAKING OF CHARC0AL BEDS AND'THUS RENDERING THAT TRAIN INCAPABLE OF FURTHER IODINE FILTRATION; THUS SYSTEM CANNOT MEET DESIGN BASIS ON OCTOBER 30, 1986, THE LICENSEE (BECO) INFORMED NRC ABOUT TWO ADDITIONAL DESIGN DEFICIENCIES
- FAILURE OF THE CROSSOVER DAMPER RESULTING IN NO COOLING FLOW GASES THROUGH THE STANDBY TRAIN.
- SINGLE FAILURE RESULTING IN A HEATER FAILURE AND LACK OF HUMIDITY CONTROL
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DISCUSSION: CONTINUED l
DAMPER FAILURE
- CROSS TIE DAMPER PROVIDES THE REQUIRED FLOW' PATH THROUGH EITHER FILTER TRAIN WHEN THAT TRAIN IS IN STANDBY.
- PARTIAL OR FULL CLOSURE OF THE DAMPER COULD LEAD TO ELE TEMPERATURES OR FIRE IN THE STANDBY TRAIN.
- PARTIAL OR FULL CLOSURE'WILL INTERRUPT FLOW'THROUGH B THUS SYSTEM:CANNOT MEET DESIGN BASIS.
~
HEATER FAILURE
- FOR CHARC0AL FILTERS TO NAINTAIN THEIR EFFICIENCY FOR FILTERING OUT RADIOI0 DINES THE HUMIDITY OF THE AIR STREAM MUST BE CONTROLLED FOR BOTH PRIMARY AND STANDBY TRAINS.
- IN THE PRESENT DESIGN, THE HEATERS DO NOT HEAT THE AIR PASSING THROUGH THE STANDBY TRAIN ONCE FAN IS DE-ENERGIZEDTHUS, SYSTEM CANNOT MEET DESIGN BASIS
- FAILURE;0F THE HEATER AC POWER OR TEMPERATURE SWITCH ON THE ACTIVE TRAIN COULD ALSO IMPACT OPERABILITY FOLLOW-UP:
LICENSEE WILL RE-EVALUATE DESIGN BASIS DESIGN MODIFICATIONS WILL BE COMPLETED AS NECESSARY
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OTHER EVENT OF INTEREST.
ANALYSIS OF REACTOR SCPAM FREQUENCY EARLY IN PLANT LIFE (M. CARUS 0, NRR)
I PURPOSE AND SCOPE IDENTIFY CURRENT NEW PLANT PERFORMANCE TRENDS
COMPARISON OF PERFORMANCE IN EARLY YEARS BETWEEN MODERN PLANTS AND EARLY VINTAGE PLANTS DATA COMPILATION SCRAM COUNTS FOR TWENTY-THREE MODERN PLANTS FROM LERs AND "50.72 EVENT REPORTS SCRAM COUNTS FOR TWELVE EARLY VINTAGE PLANTS FROM A PREVIOUS STUDY IN LITERATURE EFFECTIVE FULL POWER HOURS USED AS NORMALIZATION FOR OPERATING T OPERATING TIME DATA TAKEN FROM NUREG-0020 AND ERDA-76/125 RESULTS SCRAM FREQUENCY INITIALLY HIGH, BUT DECREASES RAPIDLY IN FIRST YEAR; RELATIVE STABILITY ACHIEVED IN SECOND YEAR
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SIGNIFICANT VARIATION IN SCRAM FREQUENCY AMONG PLANTS DIFFERENCE IN MEDIAN SCRAM FREQUENCY BETWEEN MODERN AND EARLY VINTAGE PLANTS NOT SIGNIFICANT
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$16NIFICANCE DATE G' MCSUIRE I 10/28/96 FOUR ECCS CHARSING HEADER ISOLATION VALVES POTENTIAL FOR OR ACTUAL DESRADAT10N OF i
]NCPERABLE. LICENSEE'S CHANEES TO MOV TOROUE EQUIPMENT SAFETY-RELATED SWITCH SETTINS WITHOUT CONSULTING OPERATOR VENDOR RESULTED IN POTENTIAL COMMON MODE FAILURE OF SAFETY-RELATED VALVES MC6UIRE 2 10!28/86 FOUR ECCS CHARGING HEADER ISOLATION VALVES POTENTIAL FOR OR ACTUAL DEGRADATION OF INOPERABLE. LICENSEE'S CHANGES TO MOV TORGUE SAFETY-PELATED EQUIPMENT SWITCH SETTING WITHOUT CONSULT!NS OPERATDR
- VENDOR RESULTED IN POTINTIAL COMMON MODE FAILURE 0F SAFETY-RELATED VALVES
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4 OPERATING REACTORS EVENTS BRIEFING 86-40 NOVEMBER 17, 1986 NINE MILE POINT 2 FUEL HANDLING PROBLEMS
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l OTHER EVENTS OF INTEREST !
PILGRIM FIRE WATER SYSTEM INOPERABLE CRYSTAL RIVER 3 EFW ACTUATION DURING SHUTDOWN RANCHO SECO EMERGENCY CONTROL ROOM HVAC INOPERABLE
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NINE MILE POINT 2 FUEL HANDLING PROBLEMS ,
NOVEMBER, 1986 - M. S. WEGNER, IE PROBLEM:
RPS ACTUATIONS, TECHNICAL SPECIFICATION (TS) VIOLATIONS, AND j OTHER PROBLEMS DURING FUEL LOADING j CAUSE: PERSONNEL ERRORS AND EQUIPPENT FAILURE l SIGNIFICANCE: 1 DEGRADED RPS DURING FUEL LOAD, LOSS OF RAD DETECTION, UNNECESSARY CHALLENGES TO RPS REPEATED VIOLATIONS OF TECHNICAL SPECIFICATIONS DISCUSSION:
ON 11/05 INTERMEDIATE RANGE MONITOR (IRM) "D" SPIKED CAUSING SCRAM SIGNAL - APPARENT CAUSE WAS BUMPING BY FUEL BUNDLE BEING INSERTED.
SCRAM DISCHARGE VOLUME HIGH LEVEL SCRAM OCCURRED WHEN OPERATOR FAILED TO FOLLOW PROCEDURE FOR RESETTING PREVIOUS SCRAM ON 11/07 SOURCE RANGE MONITOR (SRM) "C" TRIP FUNCTIONS WERE BYPASSED TO PERFORM FUNCTIONAL CHECKS AND LEFT IN THIS CONDITION FOR SEVERAL HOURS. !
WITH ALL TRIP FUNCTIONS OF SRM "C" INOPERABLE, 19 FUEL BUNDLES WERE LOADED IN THE QUADRANT, CONTRARY TO TS REQUIREMENTS ON 11/08, THE RAD MONITOR FOR THE REACTOR BUILDING BELOW THE REFUELING FLOOR WAS REMOVED FROM SERVICE FOR MAINTENANCE WHILE FUEL LOADING WAS IN PROGRESS; CONTRARY TO TS REQUIREMENTS, THE STANDBY GAS TREATMENT SYSTEM WAS NOT PLACED IN SERVICE ON 11/09, TWO APRM-HI TRIPS ON CHANNEL ^C" WERE RECEIVED.
- THE FIRST WAS ATTRIBUTED TO WELDING IN THE AREA 0F THE LPRM CABLES
- AFTER THE SECOND OCCURRED WITH NO WELDING IN PROGRESS, A FAULTY CARD IN THE LPRM CIRCUITRY WAS FOUND. ,
DURING FUEL LOADING, ROD BLOCKS WERE BYPASSED DUE TO A TRAINING PROBLEM, CONTRARY TO TS REQUIREMENTS FOLLOWUP: I REGION IS FOLLOWING OPERATIONS CLOSELY AND DISCUSSING EVENTS WITH LICENSEE ENFORCEMENT CONFERENCE ON TS VIOLATIONS TO BE SCHEDULED IN EARLY DECEMBER LICENSEE IS TAKING CORRECTIVE ACTIONS, (E.G. DISCIPLINARY ACTION)
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OTHER EVENT OF INTEREST PILGRIM - FIRE WATER SYSTEM INOPERABLE NOVEMBER 10, 1986 (R. AULUCK, NRRl PROBLEM: NON AVAILABILITY OF WATER FOR THE FIRE SUPPRESSION WATER SYSTEM CAUSE: INCORRECT LABELING OF THE VALVES SIGNIFICANCE: LACK 0F FIRE PROTECTION CAPABILITY IN MANY AREAS OF THE STATION DISCUSSION:
ON NOVEMBER 5, 1986, WATER TANK "B" WAS DRAINED IN ORDER TO WORK ON THE HEATING C0ILS.
ON NOVEMBER 10, WHILE ATTEMPTING TO FLUSH TANK "B" WITH FIRE H0SE, THE PUMPS TRIPPED ON LOW SUCTION PRESSURE. ELECTRIC PUMP '
-DAMAGED BUT DIESEL DRIVEN PUMP REMAINED OPERABLE.
BEC0 FOUND THAT THE LOW SUCTION PRESSURE WAS CAUSED BY THE TANK'S l
SUCTION VALVES BEING MIS-LABELED RESULTING IN THE ISOLATION OF THE "A" TANK INSTEAD OF THE "B" TANK.
VALVES LABELED INCORRECTLY SINCE PLANT FIRST PUT INTO SERVICE.
MIS-LABELING WAS CORRECTED AND THE SYSTEM RESTORED.
ERROR ALSO DISCOVERED IN THE SYSTEM P81D. TANK "A" FEEDS TO MOTOR DRIVEN PUMP AND NOT THE DIESEL DRIVEN PUMP AS SHOWN. ,
BACKUP SUPPLY OF FIRE WATER WAS AVAILABLE CITY WATER FROM ONE OF TWO HYDRANTS AGREEMENT WITH THE LOCAL FIRE DEPARTMENT RESIDENT INSPECTOR PERFORMED AN INSPECTION ON THE MAINTENANCE HISTORY OF THE SYSTEM. NO OTHER PROBLEMS NOTED.
FOLLOWUP:
LICENSEE TO REVISE P&ID AND PLANT PROCEDURES PER PLANT TECH SPECS, THE LICENSEE TO SUBMIT A REPORT TO THE COMMISSION OUTLINING THE CAUSE OF THE MALFUNCTIONS AND THE ACTIONS TAKEN REGION FOLLOWING LICENSEE'S FOLLOWUP ACTION
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OTHER EVENT OF INTEREST CRYSTAL-RIVER 3 - EFW ACTUATION DURING SHUTDOWN NOVEMBER 12, 1986 - (H. SILVER, NRR)
PROBLEM:
MAIN FEED PERTURBATION CAUSED EFW ACTUATION STEAM-DRIVEN EFW PUMP TRIPPED ON OVERSPEED (ELECTRIC PUMP STARTED AS DESIGNED)
CAUSE:
AUX STEAM VALVE MALFUNCTION, POSSIBLE OPERATOR ERROR
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EFW STEAM-DRIVEN PUMP TRIP ON OVERSPEED PROBABLY DUE TO WATER IN LINE .
SIGNIFICANCE:
EFW RELIABILITY MAY BE LESS THAN DESIRABLE (ONE OF SEVEN PLANTS WITH ONLY TWO TRAINS OR EFW)
MFW RELIABILITY QUESTIONABLE AT LOW POWER LEVELS AND TRANSITION POINTS DISCUSSION:
PLANT AT 20% POWER SHUTTING DOWN FOR CRDM PROBLEM OPENED MANUAL VALVE ON AUX STEAM LINE IN PREPARATION TO SWITCH FROM MAIN STEAM FOR MFW TURBINE PRESSURE CONTROL VALVE (PCV) ON AUX STEAM WENT WIDE OPEN, SHUTTING MAIN STEAM PRESSURE CONTROL VALVE TO MFW TURBINE OPERATORS CLOSED AUX STEAM MANUAL VALVE MAIN STEAM PRESSURE CONTROL VALVE COULD NOT OPEN FAST EN0 UGH TO MAINTAIN PUMP SPEED - MFW FLOW DECREASED AND OTSG LEVEL DROPPED TO EFIC ACTUATION SETPOINT EFIC INITIATED EFW. BOTH ELECTRIC AND STEAM PUMP STARTED, BUT STEAM TURBINE TRIPPED ON OVERSPEED POSSIBLE CAUSE OF OVERSPEED TRIP - EFW STEAM BYPASS VALVE CLOSED, WHICH PREVENTED SMALL STEAM FLOW TO KEEP LINE HOT AND ALLOWED BUILDUP 0F WATER IN LINE FOLLOWUP:
NRR WILL CONSIDER THIS OCCURRENCE IN EVALUATION OF EFW RELIABILITY STUDY RII FOLLOWING PLANT ACTION
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OTHER EVENT OF INTEREST RANCHO SEC0 - EMERGENCY CONTROL ROOM HVAC INOPERABLE NOVEMBER 13, 1986 - (G, KALMAN, NRR)
PROBLEM: WHEN OPERATING ON OFFSITE POWER, SUPPLY VOLTAGE TO A FLOW CONTROL DAMPER IN THE EMERGENCY CONTROL ROOM (CR) HVAC SYSTEM COULD DROP BELOW MINIMUM REQUIRED VOLTAGE. AS A RESULT, EMERGENCY CR HVAC WAS DECLARED INOPERABLE, CAUSE:
INADEQUATE DESIGN REVIEW 0F PLANT MODIFICATION FOXBORO TRANSMITTER OUTSIDE DESIGN ENVELOPE SIGNIFICANCE:
POTENTIAL IMPACT ON COMPONENT OPERABILITY SYSTEMATIC ENGINEERING REVIEW OF PLANT EQUIPMENT POWER SUPPLY REQUIREMENTS AS PART OF RESTART PROGRAM DISCUSSION:
OFFSITE POWER SUPPLY TO RANCHO SECO IS AT A NOMINAL 230 KV BASED ON ESF EQUIPMENT REQUIREMENTS, 217 KV WAS ESTABLISHED (TECH SPECS) AS A MINIMUM ACCEPTABLE OFFSITE VOLTAGE IF 0FFSITE VOLTAGE DROPS TO 217 KV, HVAC DAMPER POWER SUPPLY WILL DROP TO 98.3 VOLTS (UNACCEPTABLE) REQUIRES 102 VAC FOLLOWUP:
LICENSEE PROPOSED TO SWITCH TO A BATTERY BACKED SUPPLY SOURCE TO ASSURE 102 VAC NRR CHECK ADEQUACY OF TECH SPECS NRR REVIEW LICENSEE EVALUATION (SYSTEM REVIEW AND TEST PROGRAM) AS PART OF RESTART PROGRAM
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Page No. 1 11/17/86 SIGNIFICANT EVENTS FREQUENCY PERFORMANCE INDICATOR No. 3 i PLANT NAME EVENT EVENT DESCRIPTION SIGNIFICANCE GiR DATE NINE MILE POINT 2 !!/07/B6 WITH PLANT IN INITIAL FUEL LOAD,19 BUNDLES OF FOTENTIAL FOR OR ACTUAL BREAtDOWN IN MANAGEMENT 1 FUEL LOADED INTO THE "C'0UADRANT WITH THE 'C' OR ADMINISTRATIVE CONTROLS (E.S. TRAININS, SRM'S IN BY-PASS PROCEDURES, PROGRAMS)
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SUMMARY
WEEK ENDING 11/16/86 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI- YTD YTD YTD'
. CATIONS ABOYE BELOW TOTAL 15% 154 11/10/86 TURKEY POINT 4 100 A EQUIP /MF REG VL NO 2 1 3 11/10/86 DRESDEN 3 98 A PERS/ PROCEDURE NO 4 0 4 11/13/06 DRESDEN 3 95 A PERSONNEL /MAINT NO 5 0 11/14/86 BOPE CREEK 5 1 97 A PERSONNEL / PROC NO 3 8 11 11/14/88 INDIAN POINT 3 100 A PERSONNEL /MAINT NO 7 2 9 11/14/86 TROJAN 1 100 A EQUIP / TURBINE NO 4 0 4
11/15/86 MAINE YANKEE 1 100 A EQUIP /TDMWP NO - 6 0 6 i
11/16/86 BRUNSWICK 1 94 A PERSONNEL NO 5 2 7 l
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II. COMPARISON OF. WEEKLY STATISTICS WITS INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 11/16/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE YTD (3)(4)
- POWER >15%
EQUIP. RELATED >15% 3 4.4 5.4 (68%)
PERS. RELATED(6) >15% 5 2.0 2.0 (25%)
OTHER(7) >15% 0 0.5 0.6 ( 7%)
- Subtotal **
8 6.9 8.0
- POWER <15%-
EQUIP. RELATED <15% 0 1.4 1.3 (54%)
PERS. RELATED <15% 0 0.8 0.9 (38%)
OTHER <15% 0 0.2 0.2 ( 8%)
- Subtotal **
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- Total ***
8 9.3 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANCAL SCRAMS 0 1.0 1.0 AUTOMATIC SCRAMS 8 8.2 9.4 I
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NOTES 1.- - PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS HIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
- 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 MANUALUNPLANNEDREACTORTRIPSAT93 REACTORS (HOLDINGFULL POWERLICENSES). THIS YIELDS AN AVERAGE RATE OF 5.B 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.
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- 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),SYSTEMDESIGN,ORUNKNOWNCAUSE.
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