U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/20/96 - 03/21/96 ** EVENT NUMBERS ** 29996 30137 30138 30139 30140 30141 30142 30143 30144 30145 30146 30147 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29996 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 02/19/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 16:42 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 02/19/96 | +------------------------------------------------+EVENT TIME: 15:00[CST]| |NRC NOTIFIED BY: PAUL BREWER |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CAIN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM HVAC COOLING COILS REQUIRED FOR POST LOSS OF COOLANT ACCIDENTS | | HEAT REMOVAL WERE FOUND INCAPABLE OF REMOVING THEIR REQUIRED HEAT LOAD. | | | | AS PART OF TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM, A SURVEILLANCE TEST | | WAS DEVELOPED TO DETERMINE THE HEAT REMOVAL CAPABILITY OF THE CONTROL ROOM | | HVAC UNITS. PERFORMANCE DATA OBTAINED INDICATES THE CONTROL ROOM HVAC UNITS | | MAY NOT HAVE THE CAPABILITY OF REMOVING THE MAXIMUM DESIGN BASED HEAT LOADS | | WITH A SINGLE UNIT OF 658,300 BTU/HR. ENGINEERING EVALUATED THE DATA AND | | DETERMINED THE POST LOCA HEAT REMOVAL CAPABILITY OF THE "A" CONTROL ROOM | | HVAC UNIT COIL TO BE 356,301 BTU/HR AT THE EVALUATED CONDITION, AND THE | | POST LOCA HEAT REMOVAL CAPABILITY OF THE "B" CONTROL ROOM HVAC UNIT COIL TO | | BE 431,725 BTU/HR AT THE EVALUATED CONDITION. THE REQUIRED POST LOCA HEAT | | REMOVAL CAPABILITY FOR EACH OF THE COILS IS 658,300 BTU/HR. LICENSEE SAID | | THAT THIS PROBLEM WAS CORRECTED TWO OR THREE WEEKS AGO AND HE DID NOT KNOW | | WHAT WAS DONE TO CORRECT THE PROBLEM. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | | | | * * * UPDATE AT 0013 ON 03/20/96 BY RUFFIN ENTERED BY HOO JOLLIFFE * * * | | | | LICENSEE DETERMINED THAT THE CONTROL ROOM HVAC UNITS, IN THEIR AS-FOUND | | CONDITION AT THE TIME OF THIS EVENT, WOULD HAVE PERFORMED ADEQUATELY TO | | REMOVE HEAT TO MAINTAIN CONTROL ROOM TEMPERATURE BELOW 120øF, THE DESIGN | | BASIS TEMPERATURE. THUS, LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. HOO NOTIFIED R4DO LINDA | | HOWELL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30137 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NDC SYSTEMS, INC, IRWINDALE, CA |NOTIFICATION DATE: 03/20/96 | | CITY: IRWINDALE REGION: 4 |NOTIFICATION TIME: 10:50 [ET]| | COUNTY: STATE: CA |EVENT DATE: 02/01/96 | |LICENSE#: 1451-70 AGREEMENT: Y |EVENT TIME: 12:00[PST]| | DOCKET: |LAST UPDATE DATE: 03/20/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LINDA HOWELL RDO | | |DON COOL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: DON BUNN, CA RAD HEALTH | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SIGNIFICANT INTERNAL EXPOSURE TO AM-241 OXIDE POWDER BY 2 INDIVIDUALS - | | | | ON 02/01/96, NDC SYSTEMS, INC, IRWINDALE, CA, DISCOVERED A LEAKING | | AMERICIUM-241 SEALED SOURCE MANUFACTURED IN FRANCE BY SACLAY COMPANY. | | NDC SYSTEMS, INC IS LICENSED TO PRODUCE BACKSCATTER GAUGES USING | | RADIOACTIVE MATERIAL. | | | | ON 02/05/96, THE LICENSEE DETECTED GREATER THAN 60,000 DPM ALPHA | | CONTAMINATION FROM AM-241 OXIDE POWDER IN SOME WORK AREAS. THE LICENSEE | | CORDONED OFF THE WORK AREAS AND BEGAN CLEANING UP THE AREAS. THE CLEANUP | | EFFORT LASTED UNTIL 03/13/96. | | | | ON 02/08/96, URINE SAMPLES WERE COLLECTED FROM 16 NDC SYSTEMS EMPLOYEES AND | | SENT TO THERMO NUTECK, ALBUQUERQUE, NM, FOR ANALYSIS. | | | | ON 03/13/96, THE URINE TEST RESULTS SHOWED THAT TWO EMPLOYEES HAD INTERNAL | | CONTAMINATION OF 170 REM COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE). | | THE LICENSEE CONTACTED REACTS REGARDING GUIDANCE ON MEDICAL TREATMENT. | | THE LICENSEE SENT THE TWO EMPLOYEES TO THE DOE TRANSURANIC FACILITY IN | | RICHLAND WA, FOR LUNG, LIVER, AND SKELETAL COUNTS, FURTHER EVALUATIONS, | | AND MEDICAL TREATMENT. | | | | ON 03/14/96, THE LICENSEE NOTIFIED DON BUNN, CALIFORNIA STATE RADIOLOGIC | | HEALTH BRANCH. | | | | ON 03/18/96, MR BUNN NOTIFIED DEAN KUNIHIRO, REGION 4 CALIFORNIA FIELD | | OFFICE VIA TELEPHONE. | | | | ON 03/19/96, MR BUNN FAXED A WRITTEN REPORT TO PATRICIA LARKINS, OFFICE OF | | STATE PROGRAMS. | | | | REGION 4 IS PREPARING A PRELIMINARY NOTIFICATION ON THIS EVENT. | | | | SEE HOO LOG FOR MR BUNN'S ADDRESS AND TELEPHONE NUMBERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30138 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 03/20/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 12:13 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/20/96 | +------------------------------------------------+EVENT TIME: 10:30[CST]| |NRC NOTIFIED BY: KELLERHALS |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 72 HOUR LCO ACTION STATEMENT DUE TO THE "2A" EDG FAILING TO START DURING A | | SURVEILLANCE. | | | | AT O9:06 (CST) ON 03/20/96, THE LICENSEE WAS PERFORMING SURVEILLANCE TEST | | "PT-11-DG2A" AND DISCOVERED THAT THE "2A" EDG FAILED TO START. WITH THE | | "2C" REACTOR CONTAINMENT FAN COOLER (RCFC) INOPERABLE, UNIT 2 WAS DECLARED | | TO BE IN AN UNANALYZED CONDITION AT 10:30 (CST) PER THEIR DESIGN BASIS | | ACCIDENT (LOCA W/ LOSS OF OFF SITE POWER) WHICH REQUIRES 3 RCFCs TO BE | | OPERABLE AND ONLY 2 ARE OPERABLE. THE LICENSEE IS ALSO IN A 72 HOUR LCO DUE | | TO THE "2A" EDG BEING INOPERABLE. ENGINEERING IS PERFORMING AN ANALYSIS OF | | THE EXPECTED PEAK CONTAINMENT PRESSURE. THE FAILURE OF THE "2A" EDG TO | | START IS DUE TO ONE TRAIN OF THE EDG STARTING AIR SYSTEM BEING INOPERABLE | | AND THE OTHER TRAIN HAVING A FAILED CHECK VALVE. THE LICENSEE IS REPAIRING | | BOTH TRAINS AND THE RCFC. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30139 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/20/96 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 12:55 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/20/96 | +------------------------------------------------+EVENT TIME: 12:00[EST]| |NRC NOTIFIED BY: CLARKSON |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE ENTERED A 7 DAY LCO ACTION STATEMENT DUE TO "HP-3" AND "HP-4" | | VALVES ON UNITS 1 & 2 BEING DECLARED INOPERABLE. | | | | AT 12:00 ON 3/20/96, THE LICENSEE DETERMINED THAT THE REACTOR COOLANT | | SYSTEM LETDOWN ISOLATION VALVES ON UNITS 1 & 2 ("HP-3" AND "HP-4") ARE NOT | | CAPABLE OF CLOSING DURING AN EVENT WHICH REQUIRES THE STANDBY SHUTDOWN | | FACILITY (SSF) TO BE IN OPERATION. AN ENGINEERING ANALYSIS HAS DETERMINED | | THAT VALVES "HP-3" AND "HP-4" ON UNITS 1 & 2 MAY NOT BE ABLE TO CLOSE | | AGAINST FULL DIFFERENTIAL PRESSURE UNDER CERTAIN ACCIDENT SCENARIOS | | REQUIRING SSF OPERATION. THESE VALVES ARE REQUIRED TO CLOSE TO PREVENT LOSS | | OF REACTOR COOLANT SYSTEM INVENTORY DURING AN SSF EVENT. THE LICENSEE IS | | REQUIRED TO RETURN THE SSF TO OPERABLE STATUS WITHIN 7 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE RELATED EVENTS #30134, #30135, & #30140. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30140 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/20/96 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 12:55 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/20/96 | +------------------------------------------------+EVENT TIME: 12:00[EST]| |NRC NOTIFIED BY: CLARKSON |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED THE "HP-3" AND "HP-4" VALVES ON UNIT 3 INOPERABLE. | | | | AT 12:00 ON 3/20/96, THE LICENSEE DETERMINED THAT THE REACTOR COOLANT | | SYSTEM LETDOWN ISOLATION VALVES ON UNIT 3 ("HP-3" & "HP-4") ARE NOT CAPABLE | | OF CLOSING DURING AN EVENT WHICH REQUIRES THE STANDBY SHUTDOWN FACILITY | | (SSF) TO BE IN OPERATION. AN ENGINEERING ANALYSIS HAS DETERMINED THAT | | VALVES "HP-3" AND "HP-4" ON UNIT 3 MAY NOT BE ABLE TO CLOSE AGAINST FULL | | DIFFERENTIAL PRESSURE UNDER CERTAIN ACCIDENT SCENARIOS REQUIRING SSF | | OPERATION. THESE VALVES ARE REQUIRED TO CLOSE TO PREVENT LOSS OF REACTOR | | COOLANT SYSTEM INVENTORY DURING A SSF EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE RELATED EVENTS #30134, #30135, AND #30139. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30141 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 03/20/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:04 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 03/20/96 | +------------------------------------------------+EVENT TIME: 14:30[EST]| |NRC NOTIFIED BY: TEED |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT - | | | | THE LICENSEE DISCOVERED THAT THEY HAD GRANTED ACCESS TO PLANT PROTECTED AND | | VITAL AREAS TO A CONTRACTOR EMPLOYEE PRIOR TO A COMPLETING A BACKGROUND | | CHECK. THE LICENSEE TOOK IMMEDIATE COMPENSATORY ACTIONS UPON DISCOVERY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30142 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 03/20/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 15:58 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 03/20/96 | +------------------------------------------------+EVENT TIME: 15:48[EST]| |NRC NOTIFIED BY: ESHELMAN |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 94 POWER OPERATION | 94 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE UNIT MAY BE VULNERABLE TO A LOSS OF REMOTE SHUTDOWN CAPABILITY DURING A | | CONTROL ROOM FIRE. | | | | BASED ON A REVIEW OF PALISADES LICENSEE EVENT REPORT #95-015, DAVIS BESSE | | IS CONCERNED WITH POTENTIAL VALVE DAMAGE AS A RESULT OF A SERIOUS CONTROL | | ROOM FIRE SCENARIO. DAVIS BESSE HAS DETERMINED THAT THE PLANT MAY BE | | VULNERABLE TO THE SAME TYPE FAILURES AS DESCRIBED IN NRC INFORMATION NOTICE | | #92-18. THIS CONDITION POTENTIALLY CONSTITUTES A CONDITION OUTSIDE OF THE | | APPENDIX "R" DESIGN BASIS. FURTHER ENGINEERING EVALUATIONS WILL BE | | REQUIRED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30143 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 03/20/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/20/96 | +------------------------------------------------+EVENT TIME: 12:13[CST]| |NRC NOTIFIED BY: MYERS |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RCIC SYSTEM DECLARED INOPERABLE DUE TO A RCIC TURBINE CONTROL SYSTEM | | PROBLEM. | | | | DURING THE PERFORMANCE OF RCIC SYSTEM SURVEILLANCE #6.RCIC.101, THE RCIC | | PUMP FAILED TO START CORRECTLY. UPON PUMP TURBINE START, SPEED INITIALLY | | RAISED TO APPROXIMATELY 4500 RPM (NORMAL SPEED), THEN IT DECREASED AND | | STABILIZED AT 1900 - 2000 RPM. THE GOVERNOR VALVE WAS INITIALLY OPEN, BUT | | STARTED THROTTLING AS SPEED INCREASED. A RCIC LOW LUBE OIL PRESSURE ALARM | | WAS RECEIVED SHORTLY THEREAFTER. THE GOVERNOR VALVE CONTROLLER OUTPUT | | CALLED FOR 100%, THE GOVERNOR VALVE INDICATED CLOSED, AND THE TRIP/THROTTLE | | VALVE INDICATED OPEN. FLOW INDICATED APPROXIMATELY 200 GPM. A RCIC TURBINE | | TRIP WAS INITIATED BY OPERATORS IN ACCORDANCE WITH THE ALARM RESPONSE | | PROCEDURE. HOWEVER, CONTROL OIL PRESSURE WAS NOT SUFFICIENT TO UNLATCH THE | | TRIP/THROTTLE LINKAGE, THEREFORE, THE REMOTE TRIP DID NOT OCCUR (THIS IS | | EXPECTED WITH LOW OIL PRESSURE). THE TURBINE WAS SECURED BY CLOSING THE | | STEAM SUPPLY VALVE. THE RCIC SYSTEM WAS DECLARED INOPERABLE AND A 7 DAY LCO | | ACTION STATEMENT WAS ENTERED WHICH REQUIRES THE HPCI SYSTEM TO IMMEDIATELY | | BE DETERMINED TO BE OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30144 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/20/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 17:17 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/20/96 | +------------------------------------------------+EVENT TIME: 16:55[EST]| |NRC NOTIFIED BY: SUDIGALA |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A LOSS OF A DC BUS COULD CAUSE THE ISOLATION OF THE HYDROGEN MONITORING | | LINES. | | | | THERE ARE 4 CONTAINMENT ISOLATION VALVES ON LINES THAT GO TO THE HYDROGEN | | MONITOR. THE LICENSEE POSTULATED THAT IF A LOSS OF A DC BUS OCCURS (A | | SINGLE FAILURE), THE VALVES ON THESE LINES WOULD FAIL SHUT AND A HYDROGEN | | SAMPLE COULD NOT BE OBTAINED. A LICENSEE PROCEDURE REQUIRES THE | | INSTALLATION OF A BYPASS JUMPER TO GET POWER TO THE FACILITY THAT IS OUT | | AND THE BUSES IN THE CONTROL ROOM CAN BE CROSS TIED TO GET THE VALVES OPEN. | | THE LICENSEE HAS DETERMINED THAT THIS CONDITION DOES NOT MEET THE SINGLE | | FAILURE REQUIREMENTS THAT HAVE BEEN ASSUMED IN THE DESIGN BASIS FOR THIS | | SYSTEM. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30145 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/20/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:17 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/20/96 | +------------------------------------------------+EVENT TIME: 16:26[EST]| |NRC NOTIFIED BY: TUTTLE |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE RAISED A QUESTION ON THE DESIGN BASIS STROKE TIME OF THE | | OUTBOARD CONTAINMENT ISOLATION VALVE ON THE MAIN STEAM DRAIN LINE TO THE | | CONDENSER. | | | | DURING A REVIEW OF SAFETY EVALUATION #96-037 (GEAR SET AND SPRING PACK | | CHANGE FOR "2MSS*MOV208") ON 3/19/96, THE LICENSEE RAISED A QUESTION WITH | | RESPECT TO THE DESIGN BASIS STROKE TIME FOR "2MSS*MOV208" (THE 2 INCH | | OUTBOARD CONTAINMENT ISOLATION VALVE ON THE MAIN STEAM DRAIN LINE TO THE | | CONDENSER). THE SUBJECT DRAIN LINE IS CONNECTED TO THE MAIN STEAM LINES | | OUTSIDE CONTAINMENT BETWEEN THE MSIVs. THE DESIGN BASIS STROKE TIME LIMIT | | FOR THE MSIVs IS 3.5 TO 5.5 SECONDS. THE TIME FOR ISOLATION USED IN THE | | DESIGN BASIS LOCA AND MAIN STEAM HIGH ENERGY LINE BREAK ACCIDENTS FOR MAIN | | STEAM LINES IS 3.5 TO 5.5 SECONDS. THE 18 SECOND STROKE TIME LIMIT FOR | | "2MSS*MOV208" HAS NOT BEEN ADDRESSED IN THESE ANALYSES. THE LOCA ANALYSIS | | ASSUMES 0 LB/HR FLOW THROUGH THE MAIN STEAM LINES AT TIME = 3.5 SECONDS; | | THE STEAM LINE BREAK ANALYSIS ASSUMES 0 LB/HR FLOW AT TIME = 5.5 SECONDS. | | IN THE EVENT OF A FAILURE OF THE INSIDE MSIV TO CLOSE WHEN THE SUBJECT | | VALVE IS OPEN, A FLOW PATH WOULD EXIST FROM CONTAINMENT THROUGH THE DRAIN | | LINE DURING THE TIME IT TAKES THE VALVES TO ISOLATE (NORMAL STROKE TIME IS | | 9 SECONDS). THE VALVE IS PRESENTLY CLOSED IN THE SAFE POSITION AND HAS BEEN | | TAGGED OUT AND DEENERGIZED UNTIL THIS ISSUE IS RESOLVED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30146 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/20/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:27 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/20/96 | +------------------------------------------------+EVENT TIME: 15:15[EST]| |NRC NOTIFIED BY: HENRIQUEZ |LAST UPDATE DATE: 03/20/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT IS IN A 14 DAY LCO ACTION STATEMENT DUE TO THE EAST AND WEST | | SWITCHGEAR ROOM CO2 FIRE SUPPRESSION SYSTEM BEING INOPERABLE. | | | | THE LICENSEE DETERMINED THAT THEY DID NOT RETEST THE CO2 FIRE SUPPRESSION | | SYSTEM IN 1979 AFTER THE SYSTEM HAD FAILED A TEST OR IN 1982 AFTER THE | | SYSTEM HAD BEEN MODIFIED. THE LICENSEE DECLARED THE CO2 FIRE SUPPRESSION | | SYSTEM INOPERABLE AND ESTABLISHED A 1 HOUR ROVING FIRE WATCH IN ACCORDANCE | | WITH A 14 DAY LCO ACTION STATEMENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30147 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 03/21/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 01:19 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/21/96 | +------------------------------------------------+EVENT TIME: 00:32[EST]| |NRC NOTIFIED BY: JOHN DeDOMENICO |LAST UPDATE DATE: 03/21/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 7 STARTUP | 7 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO HPCI AND AD SYSTEMS INOPERABLE - | | | | AT 2255 ON 03/20/96, LICENSEE DECLARED THE HIGH PRESSURE COOLANT INJECTION | | (HPCI) SYSTEM INOPERABLE DUE TO A FAILED TECH SPEC SURVEILLANCE TEST. | | TECH SPEC LCO A/S 3.5.1.c REQUIRES LICENSEE TO RESTORE THE HPCI SYSTEM TO | | OPERABLE STATUS WITHIN 14 DAYS OR TO PLACE THE PLANT IN AT LEAST HOT | | SHUTDOWN CONDITION WITHIN THE NEXT 12 HOURS PROVIDED THE OTHER EMERGENCY | | CORE COOLING SYSTEMS ARE OPERABLE. | | | | AT 0032 ON 03/21/96, LICENSEE DECLARED THE AUTOMATIC DEPRESSURIZATION (AD) | | SYSTEM INOPERABLE SINCE THEY COULD NOT TEST THE AD SYSTEM BECAUSE THEY | | COULD NOT MEET THE INITIAL TEST CONDITIONS WITH THE PLANT IN OPERATIONAL | | CONDITION 2. TECH SPEC LCO A/S 3.5.1.d REQUIRES LICENSEE TO PLACE THE | | PLANT IN AT LEAST HOT SHUTDOWN CONDITION WITHIN THE NEXT 12 HOURS WITH | | THE AD SYSTEM INOPERABLE. | | | | LICENSEE ENTERED TECH SPEC LCO A/S 3.0.3 WHICH REQUIRES LICENSEE TO PLACE | | THE PLANT IN AT LEAST HOT SHUTDOWN CONDITION WITHIN 6 HOURS WITH BOTH THE | | HPCI AND AD SYSTEMS INOPERABLE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+