U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/10/97 - 09/11/97 ** EVENT NUMBERS ** 32875 32890 32897 32898 32899 32900 32901 32902 32903 32904 32905 32906 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32875 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/05/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 09:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/05/97 | +------------------------------------------------+EVENT TIME: 08:56[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |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 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO MAINTAIN THE CONTAINMENT RECIRCULATION SUMP 1/4" PARTICULATE | | RETENTION REQUIREMENT (HISTORICAL ISSUE) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "A 1/4" PARTICULATE RETENTION REQUIREMENT FOR THE CONTAINMENT RECIRCULATION | | SUMP WAS NOT PROPERLY ESTABLISHED IN 1979 FOLLOWING SUMP MODIFICATIONS. THE | | CONTAINMENT RECIRCULATION SUMP REQUIREMENT TO RETAIN 1/4" PARTICLES | | IS TO ENSURE THAT CONTAINMENT SPRAY NOZZLES DO NOT BECOME PLUGGED. THE | | CONTAINMENT SPRAY SYSTEM TAKES SUCTION FROM THE CONTAINMENT RECIRCULATION | | SUMP FOLLOWING INJECTION OF THE REFUELING WATER STORAGE TANK SUPPLY DURING | | A LOSS OF COOLANT ACCIDENT." | | | | "IN 1979, MODIFICATIONS WERE PERFORMED ON THE CONTAINMENT RECIRCULATION | | SUMP. ONE OF THE MODIFICATIONS INVOLVED MOVING A 1/4" RETENTION ELEMENT | | FROM INSIDE THE RECIRCULATION SUMP TO THE ENTRANCE OF THE SUMP. WHEN THE | | RETENTION ELEMENT WAS MOVED, THE 1/4" RETENTION REQUIREMENT WAS NOT FULLY | | ADDRESSED, AND PATHWAYS EXCEEDING THE 1/4" REQUIREMENT WERE INADVERTENTLY | | ESTABLISHED. THE INADVERTENT PATHWAYS ESTABLISHED INCLUDED: 3/4" VENTS IN | | THE ROOF OF THE RECIRCULATION SUMP ENTRANCE, THE CONTAINMENT SUMP DRAIN | | LINE FROM THE RECIRCULATION SUMP, AND SMALL GAPS AROUND THE SUMP ENTRANCE. | | THESE PATHWAYS HAVE SINCE BEEN ELIMINATED OR THE 1/4" REQUIREMENT HAS BEEN | | ESTABLISHED." | | | | "[THE LICENSEE IS] REPORTING THE FACT THAT SINCE 1979 UNTIL THE 1/4" | | REQUIREMENT WAS ESTABLISHED OR THE PATHWAY WAS ELIMINATED, THE CONTAINMENT | | RECIRCULATION SUMP DID NOT MEET ITS DESIGN REQUIREMENT." | | | | "[THE] CONTAINMENT RECIRCULATION SUMP CURRENTLY MEETS [THE] 1/4" | | REQUIREMENT. A CONDITION REPORT HAS BEEN WRITTEN TO INITIATE INVESTIGATION | | INTO THIS EVENT AND DETERMINE APPROPRIATE PREVENTIVE ACTIONS." | | | | THIS EVENT WAS DETERMINED TO BE REPORTABLE AT 0856 ON SEPTEMBER 5, 1997. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1905 ON 09/10/97 BY RANDY PTACEK ENTERED BY JOLLIFFE * * * | | | | AFTER FURTHER REVIEW OF THE ABOVE CONDITION, THE LICENSEE CONCLUDED THAT | | THE EMERGENCY CORE COOLING (ECC) SYSTEM WAS OUTSIDE ITS DESIGN BASIS AS A | | RESULT OF THE 1/4" REQUIREMENT NOT BEING MET FOLLOWING THE 1979 PLANT | | MODIFICATIONS. BY NOT ADEQUATELY COVERING THE 1/4" PARTICULATE RETENTION | | REQUIREMENT, LARGER PARTICLES HAD THE POTENTIAL TO ENTER THE RECIRCULATION | | SUMP. THE ECC SYSTEM HAS NOT BEEN ANALYZED FOR THESE LARGER PARTICLES NOR | | IS IT WITHIN THE DESIGN OF THE ECC SYSTEM TO HANDLE THESE LARGER PARTICLES. | | | | THE LICENSEE HAS CONCLUDED THAT THIS EVENT IS ALSO REPORTABLE TO THE NRC | | IN ACCORDANCE WITH THE REQUIREMENTS OF 10CFR50.72(b)(1)(ii)(A) UNANALYZED | | CONDITION, AND 10CFR50.72(b)(2)(iii)(D) ACCIDENT MITIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE OPERATIONS OFFICER | | NOTIFIED THE R3DO (BRENT CLAYTON). | | | | NOTE: SEE RELATED EVENT #32903. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32890 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/08/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 20:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/08/97 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: SAM PARTIN/MARY DePUYDT |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CECIL THOMAS, NRR EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |SULLIVAN FEMA | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS |RICHARD BARRETT IRD | |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 | 57 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 85 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UE DECLARED & TS REQD S/D ON BOTH UNITS DUE TO INOPERABLE CONTAINMENTS - | | | | AS A RESULT OF ISSUES RAISED DURING THE ONGOING ARCHITECT/ENGINEER DESIGN | | INSPECTION, THE LICENSEE WAS REVIEWING THE DESIGN ASPECTS OF THE | | CONTAINMENTS (BOTH UNITS HAVE SIMILAR CONTAINMENTS). AFTER CONSULTING WITH | | THE NUCLEAR STEAM SUPPLY SYSTEM SUPPLIER (WESTINGHOUSE) THE LICENSEE | | DETERMINED THAT CONCERNS EXISTED ABOUT WHETHER ADEQUATE COMMUNICATION (FLOW | | PATHS) EXISTS BETWEEN THE ACTIVE AND INACTIVE PORTIONS OF THE CONTAINMENT | | SUMP. | | | | DURING CERTAIN SCENARIOS, THE VOLUME OF WATER FLOW BACK TO THE CONTAINMENT | | RECIRCULATION SUMP MAY NOT BE ADEQUATE TO SUPPORT LONG-TERM EMERGENCY CORE | | COOLING (ECC) SYSTEMS (RHR SYSTEM, SAFETY INJECTION SYSTEM, CHARGING | | SYSTEM) OR CONTAINMENT SPRAY PUMP OPERATION DURING THE RECIRCULATION PHASE | | OF A LARGE OR SMALL BREAK LOCA. THE CONTAINMENT DRAINAGE SYSTEM IS | | DESIGNED TO ENSURE THAT WATER ENTERING THE CONTAINMENT FROM THE BREACH IN | | THE REACTOR COOLANT SYSTEM, ECC SYSTEMS INJECTION, AND ICE CONDENSER MELT | | FLOWS BACK INTO THE CONTAINMENT RECIRCULATION SUMP VIA DRAINS. LICENSEE | | ANALYSIS WAS UNABLE TO CONFIRM THAT SUFFICIENT COMMUNICATION EXISTED | | BETWEEN INACTIVE AND ACTIVE VOLUMES OF THE CONTAINMENT TO ENSURE ADEQUATE | | DRAINAGE TO THE RECIRCULATION SUMP. WITHOUT ADEQUATE DRAINAGE INTO THE | | SUMP, A LOW SUMP LEVEL WILL RESULT, WHICH JEOPARDIZES LONG TERM OPERATION | | OF THE ECC SYSTEMS AND CONTAINMENT SPRAY PUMPS DUE TO VORTEXING AND AIR | | ENTRAINMENT. | | | | AS A CONSERVATIVE MEASURE BECAUSE OF THESE CONCERNS, THE LICENSEE DECLARED | | BOTH TRAINS OF THE ECC SYSTEMS AND THE CONTAINMENT SPRAY SYSTEM INOPERABLE | | FOR BOTH UNITS AND ENTERED TECH SPEC LCO A/S 3.0.3 TO SHUT DOWN BOTH UNITS. | | THE LICENSEE COMMENCED SHUTTING UNIT 1 DOWN FROM 100% POWER AT 1655 AND | | UNIT 2 DOWN FROM 100% POWER AT 1728. | | | | AT 2000, THE LICENSEE DECLARED AN UNUSUAL EVENT ON BOTH UNITS DUE TO THE | | POTENTIAL LOSS OF CONTAINMENT BARRIER ON BOTH UNITS. | | | | THE LICENSEE PLANS TO PERFORM FURTHER ANALYSIS TO DETERMINE THE EXTENT OF | | THE EXISTING COMMUNICATION BETWEEN THE PORTIONS OF THE SUMPS AND WHETHER | | PLANT MODIFICATIONS WILL BE NECESSARY. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THE DECLARATION OF THE UNUSUAL EVENT. | | | | ***UPDATE @ 0311 EDT ON 09/10/97 BY TILLY TAKEN BY MACKINNON*** | | | | THE UNUSUAL EVENT WAS TERMINATED AND EXITED AT 0303 EDT WHEN UNIT 1 ENTERED | | MODE 5 (COLD SHUTDOWN). UNIT 2 ENTERED MODE 5 AT 0015 EDT (COLD SHUTDOWN). | | | | THE R3DO (RING), NRR EO (BATEMAN), AND FEMA (RISHE) WERE NOTIFIED BY THE | | NRC OPERATIONS CENTER. THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS | | UPDATE BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32897 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/10/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 03:17 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/10/97 | +------------------------------------------------+EVENT TIME: 00:19[EDT]| |NRC NOTIFIED BY: WILLIAM MAGUIRE |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | REACTOR WATER CLEANUP (RWCU) ISOLATED | | | | THE UNIT 1 RWCU SYSTEM ISOLATED DUE TO A HIGH DIFFERENTIAL FLOW CONDITION | | IN THE SYSTEM. AT THE TIME OF THE ISOLATION, A RWCU FILTER DEMINERALIZER | | WAS BEING RETURNED TO SERVICE FOLLOWING MAINTENANCE. THE RWCU SYSTEM | | REMAINS ISOLATED WHILE THE CAUSE OF THE ISOLATION IS BEING INVESTIGATED. | | THE RWCU ISOLATION MAY HAVE BEEN CAUSED BY A PRESSURE SPIKE WHEN THE RWCU | | FILTER DEMINERALIZER WAS BEING RETURNED TO SERVICE CAUSING A RELIEF VALVE | | ON THE RWCU SYSTEM TO OPEN AND THEN CLOSE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | NOTE: SEE RELATED EVENT #32902. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32898 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/10/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 04:02 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/10/97 | +------------------------------------------------+EVENT TIME: 03:01[EDT]| |NRC NOTIFIED BY: STEPHEN M SMITH |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | A/R Y 7 STARTUP | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNEXPECTED REACTOR TRIP WHEN THE MAIN TURBINE TRIPPED DURING STARTUP | | TESTING | | | | DURING PERFORMANCE OF A SURVEILLANCE TEST, 3PT-V06, "TURBINE GENERATOR | | MECHANICAL TRIP TEST," WHILE INSTALLING THE STABS ON 86P/86BU | | (PRIMARY/BACKUP) RELAYS FOLLOWING THE THRUST BEARING OIL PRESSURE PORTION | | OF THE TEST, A REACTOR TRIP OCCURRED. ALL RODS FULLY INSERTED INTO THE | | CORE. THE PLANT WAS AT A POWER LEVEL WHERE A TURBINE TRIP SHOULD NOT HAVE | | INITIATED A REACTOR TRIP (THAT IS, LESS THAN 8.5%). DURING THE COURSE OF | | THE REACTOR TRIP AND RECOVERY, ALL SYSTEMS FUNCTIONED AS REQUIRED, AND THE | | PLANT WAS STABILIZED AT HOT SHUTDOWN CONDITIONS. THE CAUSE OF THE REACTOR | | TRIP IS UNDER INVESTIGATION. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32899 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 09/10/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 11:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/10/97 | +------------------------------------------------+EVENT TIME: 07:10[CDT]| |NRC NOTIFIED BY: DICK NANCE |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | -LIFT SETPOINTS FOR 1 OF 20 MAIN STEAM SAFETY VALVES FOUND OUT-OF-TOLERANCE | | | | WHILE TESTING 20 UNIT 2 MAIN STEAM SAFETY VALVES IN ACCORDANCE WITH | | TECH SPEC SECTION 3.7.1.1, MAIN STEAM SAFETY VALVE #MS-PV-7440 ON STEAM | | GENERATOR 'D' WAS FOUND TO BE OUTSIDE THE +/-3% LIFT SETPOINT TOLERANCE. | | | | SAFETY VALVE NO. REQUIRED SETPOINT AS-FOUND SETPOINT | | MS-PV-7440 1285 PSIG 1342 PSIG | | | | THE LICENSEE HAS ADJUSTED MS-PV-7440 TO WITHIN THE +/-1% LIFT SETPOINT | | REQUIRED BY TECH SPEC SECTION 3.7.1.1. THE PROBABLE CAUSE OF THE HIGH | | OUT-OF-TOLERANCE LIFT IS THE PROMOTION OF OXIDE LOCKING AND GALLING WITH | | SUBSEQUENT BONDING BETWEEN THE VALVE NOZZLE AND DISC. | | | | TWO OF THE VALVES TESTED HAVE BEEN ADJUSTED TO WITHIN THE +/-1% LIFT | | SETPOINT REQUIRED BY TECH SPEC SECTION 3.7.1.1. THE LICENSEE IS TESTING | | THE REMAINING UNIT 2 MAIN STEAM SAFETY VALVES. | | | | LICENSEE EVENT REPORT #97-005 HAS BEEN SUBMITTED TO THE NRC REPORTING TWO | | AS-FOUND OUT-OF-TOLERANCE VALVES FOUND DURING TESTING OF UNIT 1 MAIN STEAM | | SAFETY VALVES. (REFER TO EVENT NUMBER 32863). THE LICENSEE WILL REPORT | | THE AS-FOUND OUT-OF-TOLERANCE MAIN STEAM SAFETY VALVES FOR UNIT 2 AS AN | | ADDENDUM TO LER #97-005. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32900 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 09/10/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 13:44 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/10/97 | +------------------------------------------------+EVENT TIME: 10:40[EDT]| |NRC NOTIFIED BY: ARCHIE FAULKNER |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 76 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL Rx SCRAM FROM 38% DUE TO INOPERABLE 'A' MAIN PHASE TRANSFORMER - | | | | AT 1033 ON 09/10/97, WHILE OPERATING AT 76% POWER, A MAIN TRANSFORMER | | TROUBLE ALARM WAS RECEIVED IN THE CONTROL ROOM. PLANT OPERATORS WERE | | DISPATCHED TO INVESTIGATE AND DETERMINE THE SOURCE OF THE ALARM. PLANT | | OPERATORS DISCOVERED THAT NONE OF THE FANS OR OIL PUMPS ON THE 'A' MAIN | | PHASE TRANSFORMER WERE OPERATING. PLANT OPERATORS ALSO HEARD POPPING | | NOISES AND NOTICED A SMELL COMING FROM THE TRANSFORMER. CONTROL ROOM | | OPERATORS INITIATED A REACTOR RECIRCULATION PUMP RUNBACK WHICH CAUSED | | REACTOR POWER TO DROP FROM 76% TO 38% POWER. | | | | AT 1040, CONTROL ROOM OPERATORS MANUALLY SCRAMMED THE PLANT FROM 38% POWER. | | ALL CONTROL RODS INSERTED COMPLETELY. | | | | AT 1041, CONTROL ROOM OPERATORS MANUALLY TRIPPED THE MAIN GENERATOR. | | STEAM IS BEING DUMPED TO THE MAIN CONDENSER. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE EVENT BUT BELIEVES IT TO | | BE A CONTROL PANEL RELAY MALFUNCTION WHICH CAUSED THE COOLING PUMPS AND | | FANS ON THE 'A' TRANSFORMER TO STOP RUNNING. | | | | DURING PLANT RESTORATION FOLLOWING THE SCRAM, THE 'A' SECONDARY CONDENSATE | | PUMP WOULD NOT TRIP. WHILE ATTEMPTING TO TRIP THE PUMP, PLANT OPERATORS | | DETECTED SMOKE COMING FROM INSIDE THE BREAKER CUBICLE. PLANT OPERATORS | | DEENERGIZED THE ELECTRICAL BUS PROVIDING POWER TO THE PUMP WHICH CUT | | POWER TO 'A' SECONDARY CONDENSATE PUMP, 'A' PRIMARY CONDENSATE PUMP, | | 'A' REACTOR RECIRCULATION PUMP, #10-K-107 STATION SERVICE AIR COMPRESSOR, | | AND THE 'A' AND 'D' TURBINE BUILDING CHILLERS. | | | | THE FOLLOWING EQUIPMENT WAS INOPERABLE AT THE BEGINNING OF THIS EVENT: | | 'B' REACTOR PROTECTION SYSTEM MOTOR-GENERATOR SET, #10-K-107 STATION | | SERVICE AIR COMPRESSOR, ROD SEQUENCE CONTROL SYSTEM, ALL SOURCE RANGE | | MONITORS, AND ALL INTERMEDIATE RANGE MONITORS. | | | | THE PLANT IS STABLE IN OPERATIONAL CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE PROBABLY WILL KEEP THE PLANT SHUTDOWN AND BEGIN THE PLANNED | | REFUELING OUTAGE EARLIER THAN SCHEDULED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY LOCAL | | OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32901 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 09/10/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/10/97 | +------------------------------------------------+EVENT TIME: 11:38[CDT]| |NRC NOTIFIED BY: STEVE PIERSON |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FITNESS FOR DUTY REPORT - | | | | A LICENSED PLANT EMPLOYEE WAS DETERMINED TO BE UNDER THE INFLUENCE OF | | ALCOHOL DURING A FOR-CAUSE TEST. THE EMPLOYEE'S UNESCORTED ACCESS | | AUTHORIZATION TO THE PLANT HAS BEEN DENIED. REFER TO THE HOO LOG FOR | | ADDITIONAL DETAILS. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32902 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/10/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 17:38 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/10/97 | +------------------------------------------------+EVENT TIME: 14:58[EDT]| |NRC NOTIFIED BY: GREG RUPPERT |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - UNIT 1 REACTOR WATER CLEANUP (RWCU) SYSTEM DECLARED INOPERABLE - | | | | PLANT OPERATORS WERE PLACING THE UNIT 1 RWCU SYSTEM BACK IN SERVICE | | FOLLOWING THE SYSTEM ISOLATION THAT OCCURRED AT 0019 ON 09/10/97 | | (EVENT #32897). | | | | AT 1458 ON 09/10/97, WHILE PLANT OPERATORS WERE PLACING THE #1B RWCU | | FILTER-DEMINERALIZER IN SERVICE, THE SYSTEM PRESSURE RELIEF VALVE LIFTED | | FOR UNKNOWN REASONS CAUSING SYSTEM HIGH DIFFERENT FLOW WHICH CAUSED THE | | SYSTEM INLET INBOARD ISOLATION VALVE TO AUTOMATICALLY CLOSE AND THE | | #1B RWCU RECIRCULATION PUMP TO AUTOMATICALLY TRIP. | | | | PLANT OPERATORS MANUALLY CLOSED THE RWCU SYSTEM INLET SUCTION VALVE AND | | MANUALLY LOCALLY ISOLATED THE #1B RWCU FILTER-DEMINERALIZER. | | | | THE LICENSEE DECLARED THE RWCU SYSTEM INOPERABLE AND IS INVESTIGATING THE | | CAUSE OF THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32903 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/10/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 18:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/10/97 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -CONTAINMENT RECIRCULATION SUMP VENT HOLES HAVE BEEN FILLED WITH CONCRETE- | | | | AS A RESULT OF QUESTIONS POSED BY THE NRC ARCHITECT/ENGINEER DESIGN | | INSPECTION TEAM, THE LICENSEE DETERMINED THAT THE INLET VENTING REQUIREMENT | | FOR THE CONTAINMENT RECIRCULATION SUMPS WAS NOT PROPERLY MAINTAINED | | FOLLOWING MODIFICATIONS TO THE UNIT 2 SUMP IN 1996 AND THE UNIT 1 SUMP | | IN 1997 (BOTH UNITS HAVE SIMILAR CONTAINMENTS). | | | | THE CONTAINMENT RECIRCULATION SUMP VENTING REQUIREMENT WAS ESTABLISHED IN | | 1979 AS PART OF THE ORIGINAL SUMP DESIGN TO REDUCE THE POTENTIAL FOR AIR | | ENTRAINMENT THROUGH THE SUMP. THE VENTING REQUIREMENT WAS MET THROUGH THE | | ADDITION OF FIVE 3/4-INCH DIAMETER HOLES DRILLED IN THE ROOF OF THE SUMP | | INLET. (THE HOLES DID NOT MEET THE 1/4-INCH DIAMETER REQUIREMENT AS | | REPORTED IN EVENT #32875.) WHEN THESE HOLES WERE DISCOVERED DURING THE | | UNIT 2 1996 REFUELING OUTAGE AND THE UNIT 1 1997 REFUELING OUTAGE, THEY | | WERE CLASSIFIED AS ABANDONED EQUIPMENT HOLES THAT EXCEEDED THE 1/4-INCH | | PARTICULATE RETENTION REQUIREMENT FOR THE SUMPS AND THEY WERE FILLED WITH | | CONCRETE. | | | | THE LICENSEE IS INVESTIGATING THIS CONDITION AND DETERMINING APPROPRIATE | | CORRECTIVE ACTIONS. | | | | THE LICENSEE DETERMINED THIS CONDITION TO BE REPORTABLE TO THE NRC AT | | 1730 ON 09/10/97. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32904 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/10/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 19:19 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/10/97 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: MARY BETH DePUYDT |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -SINGLE FAILURE DURING RECIRC SUMP SWITCHOVER COULD BE UNANALYZED CONDITION | | | | AS A RESULT OF QUESTIONS POSED BY THE NRC ARCHITECT/ENGINEER DESIGN | | INSPECTION TEAM, THE LICENSEE DETERMINED THAT THE POSSIBILITY OF A SINGLE | | FAILURE DURING AN ACCIDENT WHILE PERFORMING SWITCHOVER OF THE EMERGENCY | | CORE COOLING SYSTEM PUMPS FROM THE REFUELING WATER STORAGE TANK (RWST) | | SUCTION TO THE RECIRCULATION SUMP SUCTION COULD HAVE RESULTED IN THE PLANT | | BEING IN AN UNANALYZED CONDITION. THIS CONDITION IS OUTSIDE THE PLANT | | DESIGN BASIS, AND IT POTENTIALLY COULD HAVE PREVENTED THE FULFILLMENT OF A | | SAFETY FUNCTION OF STRUCTURES OR SYSTEMS. | | | | THE PLANT EMERGENCY OPERATING PROCEDURES (EOP) AS CURRENTLY WRITTEN REQUIRE | | THAT THE WEST RESIDUAL HEAT REMOVAL (RHR) PUMP BE THE FIRST PUMP SWITCHED | | FROM THE RWST SUCTION TO THE RECIRC SUMP SUCTION. ONCE THIS IS | | ACCOMPLISHED, THE CENTRIFUGAL CHARGING (CC) PUMPS' SUCTIONS AND THE SAFETY | | INJECTION (SI) PUMPS' SUCTIONS ARE THEN SWAPPED FROM THE RWST SUPPLY TO THE | | DISCHARGE OF THE WEST RHR PUMP. IF THE WEST RHR PUMP WERE TO FAIL AT THIS | | POINT WHEN ALL CC AND SI PUMPS WERE BEING SUPPLIED FROM ITS DISCHARGE, | | PRIOR TO THE EAST RHR PUMP SUCTION BEING TRANSFERRED FROM THE RWST TO THE | | RECIRC SUMP, ALL CC AND SI PUMPS COULD ALSO FAIL DUE TO THE LOSS OF SUCTION | | FLOW. THIS WOULD RESULT IN THE LOSS OF ALL HIGH AND MEDIUM HEAD INJECTION | | WITH ONLY THE FLOW FROM THE EAST RHR PUMP AVAILABLE FOR INJECTION INTO THE | | REACTOR COOLANT SYSTEM. THE LICENSEE IS CURRENTLY REVIEWING THE EOPs TO | | DETERMINE AN ALTERNATE SWITCHOVER SEQUENCE THAT WOULD ELIMINATE THE | | CONDITION AS DESCRIBED ABOVE. | | | | AT 1700, THE LICENSEE DETERMINED THAT THIS EVENT IS REPORTABLE TO THE NRC | | AND INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32905 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 09/10/97 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 20:04 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/10/97 | +------------------------------------------------+EVENT TIME: 17:11[CDT]| |NRC NOTIFIED BY: CHUCK COTTON |LAST UPDATE DATE: 09/10/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - OFFSITE BRUSH FIRE LASTING 12 MINUTES; NO EFFECT ON PLANT OPERATIONS - | | | | A BRUSH FIRE OCCURRED OUTSIDE THE PLANT PROTECTED AREA BUT INSIDE THE OWNER | | CONTROLLED AREA. THE FIRE WAS THE RESULT OF AN ARC WHICH WAS DRAWN WHEN A | | LICENSEE 25KV AIR SWITCH WAS CLOSED. NO SAFEGUARDS EQUIPMENT WAS AFFECTED, | | AND THE FIRE WAS OUT WITHIN 12 MINUTES FROM BEING REPORTED TO THE CONTROL | | ROOM. THE PLANT FIRE BRIGADE RESPONDED TO THE FIRE AND THE LOCAL FIRE | | DEPARTMENT WAS CALLED FOR ASSISTANCE. THE LOCAL FIRE DEPARTMENT ARRIVED | | AT THE SITE AFTER THE FIRE WAS EXTINGUISHED AND ASSISTED IN DETERMINING | | THAT THE FIRE WAS ACTUALLY OUT. THE FIRE HAD NO EFFECT ON PLANT | | OPERATIONS, AND THERE WERE NO PERSONNEL INJURIES. | | | | THE LICENSEE WAS NOT REQUIRED TO DECLARE AN EMERGENCY FOR THIS EVENT. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32906 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/10/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:28 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/10/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:36[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 09/10/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON RDO | | DOCKET: 0707001 |SUSAN SHANKMAN, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MATT MAURER | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - THREE-WAY RECIRCULATING WATER (RCW) FREEZER-SUBLIMER VALVE FAILED - | | | | AT 1036 ON 09/10/97, THE THREE-WAY RCW VALVE ON THE C-337 PROCESS BUILDING | | UNIT 4 CELL 8 FREEZER-SUBLIMER FAILED WHEN THE FREEZER-SUBLIMER WAS | | OPERATED FROM THE COLD STANDBY MODE (MODE F/S-3) TO THE SUBLIME MODE | | (MODE F/S-2). | | | | THE THREE-WAY RCW VALVE IS A SAFETY-RELATED COMPONENT THAT IS REQUIRED | | BY TECHNICAL SPECIFICATION REQUIREMENT (TSR) 2.4.3.1 TO BE AVAILABLE AND | | OPERABLE WHEN THE FREEZER-SUBLIMER IS IN MODE F/S-3. THE FREEZER-SUBLIMER | | WAS DECLARED INOPERABLE AND PLACED OUT OF SERVICE (MODE F/S-6) IN | | ACCORDANCE WITH TSR 2.4.3.1. | | | | THE LICENSEE PLANS TO INVESTIGATE THIS EVENT AND PLANS TO REPAIR/REPLACE | | AND TEST THE VALVE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+