U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/17/96 - 01/18/96 ** EVENT NUMBERS ** 29737 29749 29758 29761 29845 29846 29847 29848 29849 29850 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29737 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 12/18/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 16:43 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 12/18/95 | +------------------------------------------------+EVENT TIME: 16:11[EST]| |NRC NOTIFIED BY: HARTNER |LAST UPDATE DATE: 01/17/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MODES RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 94 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN TO REPLACE EXPANSION JOINTS IN RIVER WATER COOLING SYSTEM | | | | AT 1611 ON 12/18/95, THE LICENSEE COMMENCED A UNIT SHUTDOWN IN ACCORDANCE | | WITH TECHNICAL SPECIFICATIONS IN ORDER TO INSPECT AND REPLACE EXPANSION | | JOINTS IN THE RIVER WATER AND COMPONENT COOLING WATER SYSTEMS. THE | | LICENSEE STATED THAT THIS SHUTDOWN IS BEING PERFORMED BECAUSE OF A | | CONSERVATIVE MANAGEMENT DECISION. | | | | ON 12/15/95, AN EXPANSION JOINT ON THE 'A' RIVER COOLING WATER HEADER | | RUPTURED. THE LICENSEE RETRIEVED INSPECTION DATA FOR THIS EXPANSION JOINT | | FROM THE ARCHIVES AND NOTED THAT THE RUPTURE OCCURRED AT A LOCATION WHICH | | HAD SHOWN SOME INDICATION ON AN INSPECTION VIDEOTAPE. AT THE TIME OF THE | | INSPECTION, THE LICENSEE HAD DETERMINED THAT THE INDICATION WAS NOT | | INDICATIVE OF ANY PROBLEM. SUBSEQUENTLY, THE LICENSEE REVIEWED THE | | INSPECTION TAPE FROM THE 'B' HEADER AND NOTICED INDICATIONS SIMILAR TO | | THOSE SEEN ON THE 'A' HEADER. THE LICENSEE REPORTED THAT A NUMBER OF OTHER | | EXPANSION JOINTS THROUGHOUT THE PLANT (APPROXIMATELY EIGHT JOINTS TOTAL) | | ARE OF THE SAME VINTAGE AS THE ONES IN THE RIVER COOLING WATER SYSTEM. | | ADDITIONALLY, REVIEW OF VENDOR INFORMATION INDICATES THAT THESE EXPANSION | | JOINTS MAY BE BEYOND THEIR RECOMMENDED SERVICE LIFE. | | | | THE LICENSEE PLANS TO PLACE THE UNIT IN COLD SHUTDOWN AND REPLACE THE | | EXPANSION JOINTS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | | | * * * UPDATE @ 1554 ON 1/17/96 BY ANDY DULICK ENTERED BY HOO JOLLIFFE * * * | | | | THE WORK REQUIRED TO RESTORE THE 'B' RIVER WATER HEADER TO OPERABLE STATUS | | COULD HAVE BEEN PERFORMED WITHIN THE 72 HOURS PERMITTED BY THE TECH SPEC | | ACTION STATEMENT. LICENSEE MANAGERS MADE THE CONSERVATIVE DECISION TO | | REMOVE UNIT 1 FROM SERVICE BASED ON ADDITIONAL WORK PLANNED TO BE PERFORMED | | AND THIS EVENT SHOULD NOT BE CLASSIFIED AS A PLANT SHUTDOWN REQUIRED BY | | TECHNICAL SPECIFICATIONS. | | | | LICENSEE SUBMITTED A VOLUNTARY LICENSEE EVENT REPORT TO THE NRC ON 1/16/96 | | TO DOCUMENT THE DETAILS OF THE UNIT 1 SHUTDOWN. | | | | THUS, LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R1DO JIM JOYNER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29749 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 12/20/95 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 16:42 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 12/20/95 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: FRANSSEN |LAST UPDATE DATE: 01/17/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MODES RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STANDBY GAS TREATMENT SYSTEM MAY NOT PROVIDE ADEQUATE DIFFERENTIAL PRESSURE | | DURING SPECIFIC LOSS OF COOLANT ACCIDENT CONDITIONS. | | | | DURING MUCH OF THE PLANT LIFETIME, THE STANDBY GAS TREATMENT SYSTEM HAS | | BEEN OPERATED DURING REGENERATION OF THE REACTOR WATER CLEANUP SYSTEM | | DEMINERALIZER RESINS TO REDUCE EFFLUENT RELEASES THROUGH THE PLANT STACK. | | THE LICENSEE HAS DETERMINED THAT USE OF THE 'B' SGTS TRAIN (SHARED BETWEEN | | UNITS) DURING RESIN REGENERATION COULD HAVE DEGRADED THE ABILITY OF THE | | SGTS TO MAINTAIN AN ADEQUATE DIFFERENTIAL PRESSURE (-0.25" WATER) BETWEEN | | THE SECONDARY CONTAINMENT AND THE OUTSIDE ATMOSPHERE DURING LOCA | | CONDITIONS. (THE 'A' TRAIN IS DEDICATED TO UNIT 2, WHILE THE 'C' TRAIN IS | | USED BY UNIT 3.) | | | | SPECIFICALLY, THE LICENSEE REPORTED THAT, DURING A LOCA ON ONE OF THE | | UNITS, THE SINGLE FAILURE OF THE DEDICATED SGTS TRAIN, WHILE THE 'B' TRAIN | | WAS BEING USED FOR RWCU RESIN REGENERATION ON THE OTHER UNIT, COULD RESULT | | IN THE INABILITY OF THE SGTS TO MAINTAIN AN ADEQUATE DIFFERENTIAL PRESSURE | | ON THE UNIT HAVING THE LOCA. THIS IS BECAUSE THE 'B' FAN WOULD BE REQUIRED | | TO PROVIDE SUCTION ON BOTH THE LOCA AND NON-LOCA UNITS. FAN CURVES FOR THE | | SGTS INDICATE THAT THE 'B' TRAIN WOULD LIKELY NOT BE ABLE TO MAINTAIN | | ADEQUATE DIFFERENTIAL PRESSURE ON THE LOCA UNIT. | | | | THE LICENSEE HAS CHANGED PLANT PROCEDURES TO ADDRESS THIS ISSUE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | | | * * * UPDATE AT 1355 ON 01/17/96 BY DAVE FOSS ENTERED BY HOO JOLLIFFE * * * | | | | AFTER FURTHER REVIEW OF OPERATING LOGS, LICENSEE HAS DETERMINED THAT THE | | 'A' AND 'C' STANDBY GAS TREATMENT SYSTEM FANS WERE OPERABLE WHEN THE | | 'B' FAN WAS BEING USED FOR RWCU REGENERATIONS. THEREFORE, NO LOSS OF | | SAFETY FUNCTION FOR THE STANDBY GAS TREATMENT SYSTEM WAS IDENTIFIED. | | SINGLE FAILURE CONCERNS ARE BOUNDED BY EXISTING TECH SPEC LCOs. THUS, | | LICENSEE DESIRES TO RETRACT THIS EVENT. LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. HOO NOTIFIED R1DO JIM JOYNER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29758 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/21/95 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 16:49 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 11/04/95 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 01/17/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RESTRAINTS FOR LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) SYSTEM PIPING | | MAY HAVE BEEN REMOVED WHILE THE SYSTEM WAS STILL REQUIRED TO BE | | OPERATIONAL. | | | | THE LICENSEE DISCOVERED THAT CERTAIN PIPING RESTRAINTS HAD BEEN REMOVED TOO | | EARLY ON ONE TRAIN OF LTOP. THE UNIT WAS POTENTIALLY STILL UNDER LTOP | | CONDITIONS DURING THIS PERIOD. THE RESTRAINTS WERE REINSTALLED PRIOR TO | | ESTABLISHING LTOP CONDITIONS ON THE UNIT 1 RESTART. | | | | THE LICENSEE IS EVALUATING THE EFFECT OF THIS EVENT ON PAST OPERABILITY. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1035 ON 1/17/96 BY NIX TAKEN BY WEAVER * * * | | | | "AS DESCRIBED IN THE REFERENCED PHONE CALL ON 12/21/95, A POTENTIAL | | CONDITION OF LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) VENT PATH | | INOPERABILITY WAS CONSERVATIVELY REPORTED UNTIL A DETAILED PAST OPERABILITY | | EVALUATION COULD BE CONDUCTED. THE PAST OPERABILITY EVALUATION HAS BEEN | | COMPLETED. THE RESULTS OF THIS PAST OPERABILITY EVALUATION INDICATED THAT | | THE SUBJECT LTOP VENT PATH WOULD HAVE BEEN CAPABLE OF PERFORMING ITS | | INTENDED SAFETY FUNCTION DURING ALL POSTULATED LTOP CONDITIONS. THE LTOP | | VENT PATH WAS THEREFORE DETERMINED TO BE PAST OPERABLE." | | | | THE RESIDENT INSPECTOR HAS BEEN INFORMED. THE HOO NOTIFIED R2DO DECKER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29761 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 12/23/95 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 03:38 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/22/95 | +------------------------------------------------+EVENT TIME: 23:53[EST]| |NRC NOTIFIED BY: KILBY |LAST UPDATE DATE: 01/17/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 EXCEEDED THEIR MAXIMUM ALLOWABLE POWER LEVEL FOR APPROX 4 MINS. | | | | ON 12/22/95 THE PLANT EXCEEDED THE MAXIMUM LICENSED POWER LEVEL OF 3411 | | MWt. THE CAUSE IS UNKNOWN AND BEING INVESTIGATED. THE 8 HOUR AVERAGE | | REACTOR POWER REACHED 3411.07 MWt FOR 4 MINS(23:53-23:57). THE MAIN PLANT | | COMPUTER CALCULATES A CONTINUOUS ROLLING 8 HR AVERAGE OF REACTOR POWER. THE | | 8 HR AVERAGE INCREASED FROM 3410.91 MWt AT 23:49 TO 3411.07 MWt AT 23:53. | | THE OPERATORS PROMPTLY REDUCED POWER UPON THE RECEIPT OF AN ALARM | | INDICATING THE UNIT WAS AT OR ABOVE THE MAXIMUM ALLOWABLE POWER LEVEL. THE | | COMPUTER NORMALLY PROVIDES AN ANTICIPATORY ALARM WHICH ALLOWS THE OPERATORS | | 40 MINS TO REDUCE POWER TO PREVENT EXCEEDING 3411 MWt. HOWEVER, IN THIS | | SITUATION THE ALARM WAS NOT RECEIVED. THE CAUSE FOR THE ALARM NOT BEING | | RECEIVED IS UNKNOWN AND BEING INVESTIGATED. THE RI WILL BE INFORMED. | | | | * * * UPDATE @ 1208 ON 01/17/96 BY MIKE DAVID ENTERED BY HOO JOLLIFFE * * * | | | | ON 12/28/95, I & C TECHNICIANS IDENTIFIED AND CORRECTED A ZERO OFFSET ERROR | | IN STEAM GENERATOR BLOWDOWN FLOW TRANSMITTER #1-SB-FT-1905 WHICH WAS | | CAUSING THE INSTRUMENT LOOP TO OVER PREDICT BLOWDOWN FLOW BY +24.6 GPM. | | THUS, THE MAIN PLANT COMPUTER SYSTEM CALORIMETRIC WAS CONSERVATIVELY OVER | | PREDICTING CORE POWER BY AS MUCH AS +0.33 MWt PRIOR TO THE I & C | | CALIBRATION. THEREFORE, THE ACTUAL CORE THERMAL POWER DURING THIS EVENT | | WAS 3410.74 MWt. THUS, THIS EVENT DOES NOT CONSTITUTE A VIOLATION OF THE | | LICENSED POWER LEVEL AND LICENSEE DESIRES TO RETRACT THIS EVENT. LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R1DO JIM JOYNER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29845 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 01/17/96 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 09:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/17/96 | +------------------------------------------------+EVENT TIME: 08:08[CST]| |NRC NOTIFIED BY: ALLAN HALL |LAST UPDATE DATE: 01/17/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT SAFETY INJECTION WITH DISCHARGE TO THE REACTOR COOLANT SYSTEM | | | | AT APPROXIMATELY 0802 CST, THE PLANT RECEIVED A CONTROL ROOM ALARM | | INDICATING A LOSS OF POWER TO THE 118 VDC BUS 1PC-2. OPERATORS FOLLOWED | | PLANT ABNORMAL OPERATING PROCEDURES AND RESTORED POWER TO BUS 1PC-2 FROM AN | | ALTERNATE POWER SUPPLY AT 0808. A SAFETY INJECTION SIGNAL WAS RECEIVED | | IMMEDIATELY AFTERWARDS BASED ON MAIN STEAM LINE LOW PRESSURE SIGNAL. THE | | LOW PRESSURE CONDITION DID NOT ACTUALLY EXIST. RESTORATION OF POWER TO THE | | BUS SHOULD NOT HAVE CAUSED THIS CONDITION AND THE EVENT IS BEING | | INVESTIGATED. THE CAUSE OF THE ORIGINAL LOSS OF POWER TO BUS 1PC-2 WAS | | ATTRIBUTED TO THE FAILURE OF THE INVERTER SUPPLYING THE BUS. | | | | THE PLANT RESPONDED AS EXPECTED TO THE SAFETY INJECTION SIGNAL. THE PLANT | | TRIPPED AND ALL MSIVs CLOSED. ALL RODS FULLY INSERTED. AUXILIARY | | FEEDWATER STARTED AND INJECTED TO THE STEAM GENERATORS. THE EMERGENCY CORE | | COOLING SYSTEMS INJECTED INTO THE REACTOR COOLANT SYSTEM AND WERE SECURED | | APPROXIMATELY FIFTEEN MINUTES LATER IAW THE EMERGENCY OPERATING PROCEDURES. | | THE MAXIMUM PRESSURIZER LEVEL ATTAINED WAS 82%. DECAY HEAT IS BEING | | REMOVED VIA THE STEAM GENERATOR ATMOSPHERIC DUMPS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29846 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/17/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 10:44 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/17/96 | +------------------------------------------------+EVENT TIME: 08:30[EST]| |NRC NOTIFIED BY: RICK HENRIQUEZ |LAST UPDATE DATE: 01/17/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | ERRORS FOUND IN SOME NUMERICAL VALUES IN THE EMERGENCY OPERATING PROCEDURES | | | | VERMONT YANKEE IS IN THE PROCESS OF UPGRADING THE PLANT COMPUTER. THE | | PLANT COMPUTER SOFTWARE IS BEING CHANGED FROM BASIC TO EXCEL. DURING A | | REVIEW OF THIS CHANGE SOME ERRORS WERE DETECTED REGARDING THE UNITS USED. | | SPECIFICALLY, MEASUREMENTS IN FEET AND TENTHS OF FEET WERE CONFUSED WITH | | MEASUREMENTS IN FEET AND INCHES. THIS IS IMPORTANT BECAUSE THE PLANT EOPs | | WERE DRAFTED FROM THE PLANT COMPUTER CODE. | | | | THE MOST SIGNIFICANT ERROR REPORTED WAS A MISTAKE IN THE MINIMUM CORE | | FLOODING INTERVAL. THE CURRENT VALUE IN THE PROCEDURE IS 58 MINUTES. THIS | | VALUE SHOULD HAVE BEEN 98 MINUTES. THE TIME REFERS TO THE AMOUNT OF TIME | | THE SRVs SHOULD BE MAINTAINED OPEN FOLLOWING CERTAIN ACCIDENTS. | | INVESTIGATION CONTINUES. IN ADDITION, THE SETPOINT FOR INITIATING | | SUPPRESSION CHAMBER SPRAY WAS 14.2 PSIG AND SHOULD HAVE BEEN 10 PSIG. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29847 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 01/17/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:18 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/17/96 | +------------------------------------------------+EVENT TIME: 12:50[CST]| |NRC NOTIFIED BY: JOHN BROWNING |LAST UPDATE DATE: 01/17/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - 1438 POUNDS OF LIQUID SODIUM HYPOCHLORITE LEAKED INTO THE COOLING LAKE - | | | | LICENSEE NOTIFIED THE ILLINOIS EMERGENCY MANAGEMENT AGENCY AND THE DOT | | NATIONAL RESPONSE CENTER THAT 1438 POUNDS OF LIQUID SODIUM HYPOCHLORITE | | HAD LEAKED INTO THE PLANT COOLING LAKE BECAUSE OF EQUIPMENT FAILURE. | | THE AMOUNT OF THIS LEAK EXCEEDS THE NPDES PERMIT SOLID WASTE ISSUE LIMITS | | PER 40CFR302. LICENSEE HAS STOPPED THE LEAK AND IS INVESTIGATING THE | | CAUSE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE SIMILAR EVENT #29840 AT DRESDEN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 29848 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CLARA MAASS MEDICAL CENTER |NOTIFICATION DATE: 01/17/96 | | CITY: BELLEVILLE REGION: 1 |NOTIFICATION TIME: 14:52 [ET]| | COUNTY: STATE: NJ |EVENT DATE: 01/17/96 | |LICENSE#: 29-03163-03 AGREEMENT: N |EVENT TIME: 14:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/17/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES JOYNER RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: LEE ANNE ZARGER | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - IR-192 SEEDS PARTIALLY DISLODGED FROM PATIENT'S THROAT - | | | | AT 1600 ON 01/16/96, A FEMALE PATIENT WAS TREATED FOR AN ENDOBRONCHIAL | | LESION WITH A SINGLE STRAND OF SIX IR-192 SEEDS TOTALING 7.68 mg Ra | | EQUIVALENT (13.6 MILLICURIES). THE INTENDED DOSE WAS 1500 CENTIGRAYS | | FOR 25 HOURS. THE SEEDS HAD BECOME PARTIALLY DISLODGED DURING THE NIGHT. | | AT 1600 ON 01/17/96, THE SEEDS WERE REMOVED FROM THE PATIENT. ADVERSE | | EFFECTS TO THE PATIENT WERE MINIMAL. THE PATIENT AND HER DOCTOR WERE | | NOTIFIED. | | | | LICENSEE WILL SUBMIT A WRITTEN REPORT TO THE NRC WITHIN 15 DAYS. | | | | LICENSEE DISCUSSED THIS EVENT WITH R1 TOM THOMPSON. | | | | NOTE: SEE HOO LOG FOR TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29849 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/17/96 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 15:48 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/17/96 | +------------------------------------------------+EVENT TIME: 15:00[CST]| |NRC NOTIFIED BY: JOEY CLARK |LAST UPDATE DATE: 01/17/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNTAGGED OBSTRUCTIONS IN CONTAINMENT/FUEL BUILDING AIRLOCK DOOR - | | | | WITH THE PLANT IN CONDITION 5 IN A REFUELING OUTAGE, LICENSEE WAS MOVING | | FUEL. | | | | WHILE PERFORMING A QUALITY ASSURANCE SURVEILLANCE, LICENSEE IDENTIFIED THAT | | ONE HOSE AND ONE CABLE ROUTED THROUGH A CONTAINMENT/FUEL BUILDING AIRLOCK | | DOOR DID NOT HAVE A REQUIRED TAG ATTACHED TO EACH END. THESE TAGS CONTAIN | | SPECIFIC INSTRUCTIONS TO EXPEDITE REMOVAL OF THE HOSES AND CABLES IN ORDER | | TO CLOSE THE DOOR. THIS SITUATION IS IN VIOLATION OF OPERATING LICENSE | | CONDITION 2.C(17), AMENDMENT 85 & IS REPORTABLE TO THE NRC PER SECTION 2.E. | | | | WHEN THE CONTROL ROOM WAS NOTIFIED OF THIS SITUATION, THEY STOPPED CORE | | ALTERATIONS AND PLACED THE PROPER TAGS ON THE CABLE AND HOSE. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29850 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/17/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:02 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/17/96 | +------------------------------------------------+EVENT TIME: 15:50[EST]| |NRC NOTIFIED BY: RICH HENRIQUEZ |LAST UPDATE DATE: 01/17/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE REMOVED THE SAFETY PARAMETER DISPLAY SYSTEM FROM SERVICE FOR | | GREATER THAN 8 HOURS (0750 TO 1602) TO REPLACE A COMPUTER PROCESSOR. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+