U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/17/97 - 01/21/97 ** EVENT NUMBERS ** 31582 31609 31610 31611 31612 31613 31614 31615 31616 31617 31618 31619 31620 31621 31622 31623 31624 31625 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31582 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 01/13/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/13/97 | +------------------------------------------------+EVENT TIME: 14:55[EST]| |NRC NOTIFIED BY: M. DAVID |LAST UPDATE DATE: 01/17/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WHITE RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL FOR PIPING FAILURE DURING ACCIDENT CONDITIONS | | | | WHILE CONDUCTING ENGINEERING EVALUATIONS IN RESPONSE TO NRC GL 96-06, THE | | LICENSEE HAS IDENTIFIED THAT PIPING INSIDE CONTAINMENT ADJACENT TO THE SI | | SYSTEM TEST RETURN LINE COULD BECOME OVERPRESSURIZED DURING CERTAIN DESIGN | | BASIS ACCIDENTS AND CHALLENGE THE INTEGRITY OF CONTAINMENT ISOLATION VALVE | | SI-V-70. ASSUMING A SINGLE FAILURE OF THE OUTBOARD ISOLATION VALVE, THIS | | FAILURE COULD PERMIT CONTAINMENT BYPASS. | | | | THE LICENSEE HAS OPENED THE AFFECTED VALVE, AND REPORTED THAT CONTINUED | | OPERATION WAS PERMITTED BY THE PLANT TECHNICAL SPECIFICATIONS WITH ONLY THE | | OUTBOARD VALVE CLOSED. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | * * * UPDATE AT 1837 ON 01/17/97 BY PAUL FREEMAN ENTERED BY JOLLIFFE * * * | | | | THE FOLLOWING REPORT REPLACES AND UPDATES THE ABOVE REPORT: | | | | WHILE CONDUCTING ENGINEERING EVALUATIONS IN RESPONSE TO NRC GENERIC LETTER | | 96-06, THE LICENSEE IDENTIFIED THAT PIPING INSIDE CONTAINMENT, CONNECTED TO | | THE SAFETY INJECTION SYSTEM TEST LINE, COULD BECOME OVERPRESSURIZED DURING | | CERTAIN DESIGN BASIS ACCIDENTS. THIS OVERPRESSURE CONDITION COULD | | CHALLENGE THE INTEGRITY OF VARIOUS INSIDE CONTAINMENT ISOLATION VALVES. | | ASSUMING A SINGLE FAILURE OF ANY OF THE ASSOCIATED OUTSIDE CONTAINMENT | | ISOLATION VALVES TO CLOSE, COINCIDENT WITH THE OVERPRESSURE CONDITION, | | A CONTAINMENT BYPASS CONDITION COULD OCCUR. | | | | ON 01/17/97, THE LICENSEE IMPLEMENTED A DESIGN CHANGE THAT OPENS A VENT | | VALVE IN THE PIPING UPSTREAM OF THE AFFECTED VALVES. AN ORIFICE AND | | STAINLESS STEEL DRAIN LINE ARE INCLUDED IN THE DESIGN CHANGE. CONTINUED | | PLANT OPERATION IS PERMITTED WITH THE OVERPRESSURE PROTECTION IN PLACE FOR | | THE AFFECTED PIPING AND VALVES. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED R1DO JOHN WHITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31609 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 01/17/97 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 01:40 [ET]| |RX TYPE: [1] CE |EVENT DATE: 01/17/97 | +------------------------------------------------+EVENT TIME: 01:00[EST]| |NRC NOTIFIED BY: MCDOUGOLD |LAST UPDATE DATE: 01/17/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS IDENTIFIED SEVEN POSITIVE SIPPING INDICATIONS OUT OF 64 | | FUEL ASSEMBLIES. | | | | THE LICENSEE'S FUEL SIPPING OPERATIONS HAVE IDENTIFIED 7 POSITIVE SIPPING | | INDICATIONS OUT OF 64 WESTINGHOUSE "FIRST RUN" FUEL ASSEMBLIES. THERE ARE | | 4 MORE WESTINGHOUSE ASSEMBLIES TO BE TESTED. THESE FUEL ASSEMBLIES HAVE | | BEEN RUN DURING THIS CYCLE ONLY. CYCLE 15 HAS BEEN RUN FOR APPROXIMATELY 7 | | MONTHS. ABB/CE IS ASSISTING THE LICENSEE IN THE FUEL SIPPING PROCESS. | | THIRTY TWO ABB/CE FUEL ASSEMBLIES IN CLOSE PROXIMITY TO THE WESTINGHOUSE | | FUEL WERE ALSO SIPPED, BUT WERE FOUND TO HAVE NO INDICATIONS. THESE FUEL | | ASSEMBLIES WILL BE TRANSFERRED FROM THE REFUELING CAVITY TO THE SPENT FUEL | | POOL FOR FURTHER TESTING BY THE ULTRASONIC TEST METHOD TO IDENTIFY PIN | | LOCATION. THE DEFECTIVE PINS WILL THEN BE REMOVED FROM THEIR FUEL | | ASSEMBLIES. THE RESIDENT INSPECTOR AND STATE AGENCIES WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31610 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BFI, INC, CHICOPEE, MA |NOTIFICATION DATE: 01/17/97 | | CITY: CHICOPEE REGION: 1 |NOTIFICATION TIME: 09:19 [ET]| | COUNTY: STATE: MA |EVENT DATE: 01/17/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 06:15[EST]| | DOCKET: |LAST UPDATE DATE: 01/17/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN WHITE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: FRED SCHEURITZEL, CT DEP | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | |NAGR AGREEMENT STATE | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LOAD OF MUNICIPAL TRASH SET OFF RADIATION ALARM AT HARTFORD INCINERATOR - | | | | FRED SCHEURITZEL, CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP), | | RADIATION DIVISION, REPORTED THAT A BFI, INC TRAILER TRUCK CARRYING A LOAD | | OF MUNICIPAL TRASH SET OFF A PORTAL RADIATION ALARM WHEN IT ARRIVED AT THE | | HARTFORD RESOURCE RECOVERY FACILITY INCINERATOR IN HARTFORD, CT. | | | | A CT DEP REPRESENTATIVE MEASURED 2 MR/HR WITH A SODIUM IODIDE DETECTOR AND | | 0.5 MR/HR WITH AN ION CHAMBER, BOTH MEASURED ON CONTACT WITH THE TRUCK | | LOAD. THE TYPE OF MATERIAL ON THE TRUCK WAS UNKNOWN. | | | | THE TRUCK WAS SENT BACK TO ITS POINT OF ORIGIN, BFI, INC, IN CHICOPEE, MA. | | IT WAS LATER LEARNED THAT THE LOAD WAS LATER SENT ON TO THE SPRINGFIELD | | RESOURCE RECOVERY INCINERATOR, IN SPRINGFIELD, MA. | | | | THE CT DEP REPRESENTATIVE NOTIFIED THE MA DEPARTMENT OF PUBLIC HEALTH, | | EPA REGION 1, AND NRC REGION 1. | | | | NOTE: SEE RELATED EVENT #31615. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31611 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 01/17/97 | |UNIT: [ ] [2] [ ] STATE: CA |NOTIFICATION TIME: 11:47 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 01/17/97 | +------------------------------------------------+EVENT TIME: 07:00[PST]| |NRC NOTIFIED BY: MALCOLM McGAWN |LAST UPDATE DATE: 01/17/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA RDO | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 1% OF THE TUBES IN UNIT 2 STEAM GENERATOR #E-089 FOUND DEFECTIVE - | | | | DURING THE CURRENT UNIT 2 CYCLE 9 REFUELING OUTAGE, THE LICENSEE INSPECTED | | 100% OF THE TUBES IN ONE OF TWO UNIT 2 STEAM GENERATORS, #E-089. AT 0700 | | (PST) ON 01/17/97, THE LICENSEE DETERMINED THAT 1.0% OF THE TUBES REQUIRE | | REPAIR OR PLUGGING. THESE TUBES HAVE INDICATIONS OF EITHER CIRCUMFERENTIAL | | OR AXIAL CRACKING AND WILL BE REPAIRED OR PLUGGED. | | | | INSPECTION RESULTS OF THE OTHER UNIT 2 STEAM GENERATOR, #E-088, WERE | | REPORTED TO THE NRC ON 01/14/97 (EVENT #31590). | | | | THIS CONDITION IS BEING REPORTED TO THE NRC IN ACCORDANCE WITH UNIT 2 TECH | | SPEC 5.5.2.11, "STEAM GENERATOR TUBE SURVEILLANCE PROGRAM". | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE LICENSEE HAS INFORMED NRC REGION 4 OF THESE RESULTS. | | | | NOTE: SEE EVENT #31590 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31612 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/17/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 12:55 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/17/97 | +------------------------------------------------+EVENT TIME: 12:27[EST]| |NRC NOTIFIED BY: STEVE SMITH |LAST UPDATE DATE: 01/17/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 93 POWER OPERATION | 93 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -CONDITIONS POTENTIALLY OUTSIDE PLANT DESIGN BASIS PER GENERIC LETTER 96-06 | | | | DURING A REVIEW OF GENERIC LETTER 96-06 SCENARIOS, THE LICENSEE'S | | ENGINEERING STAFF DISCOVERED THAT UNIT 3 MAY HAVE BEEN OUTSIDE ITS DESIGN | | BASIS DURING PERIODS OF OPERATION WITH HIGHER SERVICE WATER (SW) AND VAPOR | | CONTAINMENT OPERATING TEMPERATURES. THE VAPOR CONTAINMENT INTEGRITY COULD | | HAVE BEEN VULNERABLE TO A SW PIPING FAILURE DUE TO VOIDING CAUSED BY A | | NEWLY IDENTIFIED SINGLE FAILURE DURING A POSTULATED DESIGN BASIS EVENT | | (DBE) COINCIDENT WITH A LOSS OF OFFSITE POWER. | | | | THE NEW SINGLE FAILURE OCCURS IF THE 480 VOLT BREAKER FOR A FAN COOLER UNIT | | FAILS TO STRIP OFF THE BUS WHILE VAPOR CONTAINMENT TEMPERATURES ARE | | ELEVATED DUE TO A DBE. THE FAN COOLER UNIT WOULD THEN BE POWERED BY THE | | 480 VOLT BUS PRIOR TO THE SW COOLING PUMPS, THEREFORE CAUSING THE SW IN THE | | FAN COOLER TO HEAT UP TO A STEAM FORMATION AND VOIDING CONDITION. | | | | SUBSEQUENTLY, THE SW COOLING FLOW WOULD BE ESTABLISHED AND A WATER HAMMER | | WOULD OCCUR THAT COULD BE BEYOND THE YIELD STRENGTH OF THE PIPING. THE SW | | PIPING IS CONSIDERED PART OF THE CONTAINMENT ISOLATION BOUNDARY AND A | | FAILURE OF THE PIPING WOULD PLACE THE PLANT OUTSIDE ITS DESIGN BASIS. | | | | CURRENTLY, OPERATIONAL LIMITS HAVE BEEN PLACED ON SW TEMPERATURE AND VAPOR | | CONTAINMENT TEMPERATURE TO PROVIDE SUFFICIENT MARGIN, BASED ON A | | PRELIMINARY ANALYSIS TO ENSURE THE DESIGN BASIS OF THE PLANT IS MAINTAINED. | | | | LICENSEE ENGINEERING EVALUATION OF THIS SCENARIO IS ONGOING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31613 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 01/17/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 13:42 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 01/17/97 | +------------------------------------------------+EVENT TIME: 13:10[EST]| |NRC NOTIFIED BY: MAX NELSON |LAST UPDATE DATE: 01/17/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - VARIOUS SYSTEMS COULD EXCEED ASME CODE ALLOWABLE STRESSES PER GL 96-06 - | | | | WHILE PERFORMING ENGINEERING ANALYSIS IN RESPONSE TO NRC GENERIC LETTER | | 96-06, LICENSEE ENGINEERING PERSONNEL DISCOVERED THAT PORTIONS OF THE | | FOLLOWING SYSTEMS COULD EXCEED THEIR ASME B&PV CODE ALLOWABLE STRESSES | | DURING A LARGE BREAK LOSS OF COOLANT ACCIDENT. THE ANALYSIS ALSO CONCLUDED | | THAT THE AFFECTED PIPING WOULD NOT RUPTURE AND THE PENETRATIONS WOULD | | PERFORM THEIR CONTAINMENT INTEGRITY FUNCTION. | | | | THE SYSTEMS AFFECTED ARE AS FOLLOWS: | | - ONCE THROUGH STEAM GENERATOR SAMPLING SYSTEM | | - INTERMEDIATE CLOSED COOLING WATER RETURN SYSTEM | | - RECLAIMED WATER SYSTEM | | - LETDOWN SYSTEM | | - PRESSURIZER/REACTOR COOLANT SYSTEM SAMPLING SYSTEM | | - REACTOR COOLANT PUMP SEAL RETURN SYSTEM | | - REACTOR COOLANT DRAIN TANK SYSTEM | | - REACTOR COOLANT PUMP COOLING RETURN SYSTEM | | - CORE FLOOD SAMPLING SYSTEM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31614 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/17/97 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 15:27 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/17/97 | +------------------------------------------------+EVENT TIME: 15:15[EST]| |NRC NOTIFIED BY: DON GERBER |LAST UPDATE DATE: 01/17/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -VITAL 4160 VOLT SWITCHGEAR CIRCUIT BREAKER TEST EQUIPMENT NOT CALIBRATED- | | | | THE LICENSEE DETERMINED THAT FEELER GAUGES USED TO MEASURE VITAL 4160 VOLT | | SWITCHGEAR CIRCUIT BREAKER CLEARANCES HAVE NOT BEEN CALIBRATED AND HAD | | NOT BEEN INCLUDED IN THE PLANT MAINTENANCE AND TEST EQUIPMENT PROGRAM. | | WHEN TESTED, THESE TEST GAUGES WERE FOUND TO BE OUT OF CALIBRATION BY | | AS MUCH AS 12%. THIS SITUATION RESULTED IN THE 4160 VOLT BREAKERS | | POTENTIALLY BEING SET INCORRECTLY. | | | | THESE BREAKERS SUPPLY THE RESIDUAL HEAT REMOVAL PUMPS, SERVICE WATER PUMPS, | | CHARGING PUMPS, AND EMERGENCY DIESEL GENERATORS. | | | | THE LICENSEE PLANS TO CALIBRATE THE TEST EQUIPMENT, INCLUDE THE TEST | | EQUIPMENT IN THE PLANT MAINTENANCE AND TEST EQUIPMENT PROGRAM, AND | | REMEASURE/RESET THE VITAL 4160 VOLT SWITCHGEAR CIRCUIT BREAKER CLEARANCES. | | | | THE LICENSEE IS DETERMINING IF OTHER UNIT 3 CIRCUIT BREAKER TEST EQUIPMENT | | HAS BEEN CALIBRATED PROPERLY AND IF THIS SAME CONDITION EXISTS ON UNITS | | 1 & 2. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31615 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BFI, INC, CHICOPEE, MA |NOTIFICATION DATE: 01/17/97 | | CITY: CHICOPEE REGION: 1 |NOTIFICATION TIME: 15:52 [ET]| | COUNTY: STATE: MA |EVENT DATE: 01/17/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:20[EST]| | DOCKET: |LAST UPDATE DATE: 01/17/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN WHITE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: FRED SCHEURITZEL, CT DEP | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | |NAGR AGREEMENT STATE | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LOAD OF MUNICIPAL TRASH SET OFF RADIATION ALARM AT HARTFORD INCINERATOR - | | | | FRED SCHEURITZEL, CONNECTICUT DEPARTMENT OF ENVIRONMENTAL PROTECTION (DEP). | | RADIATION DIVISION, REPORTED THAT A BFI, INC TRAILER TRUCK CARRYING A LOAD | | OF MUNICIPAL TRASH SET OFF A PORTAL RADIATION ALARM WHEN IT ARRIVED AT THE | | HARTFORD RESOURCE RECOVERY FACILITY INCINERATOR IN HARTFORD, CT. | | | | (THIS IS THE SAME CT DEP REPRESENTATIVE, SAME INCINERATOR, SAME DRIVER, | | SAME TRUCK TRACTOR, BUT A DIFFERENT TRAILER CONTAINING A DIFFERENT LOAD | | REPORTED THIS MORNING, 01/17/96, IN EVENT #31610.) | | | | THE SAME CT DEP REPRESENTATIVE MEASURED 20 MR/HR (GM) AND 15 MR/HR | | (ION CHAMBER), BOTH MEASURED ON CONTACT WITH THE TRUCK LOAD. THE TYPE | | OF MATERIAL ON THE TRUCK WAS UNKNOWN. | | | | THE TRUCK WAS SENT BACK TO ITS POINT OF ORIGIN, BFI, INC, IN CHICOPEE, MA. | | | | THE CT DEP REPRESENTATIVE NOTIFIED THE MA DEPARTMENT OF PUBLIC HEALTH, | | EPA REGION 1, AND NRC REGION 1. | | | | NOTE: SEE RELATED EVENT #31610. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31616 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ABB-COMBUSTION ENGINEERING |NOTIFICATION DATE: 01/17/97 | | CITY: WINDSOR REGION: 1 |NOTIFICATION TIME: 16:15 [ET]| | COUNTY: STATE: CT |EVENT DATE: 12/06/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/17/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: LORI WHITE | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ABB-CE 10CFR21 REPORT ON PIPING PRESSURE LOSSES BETWEEN SG AND MSSVs - | | | | ON 12/06/96, ABB-COMBUSTION ENGINEERING IDENTIFIED A DEFECT CONCERNING THE | | PIPING PRESSURE LOSSES (i.e., DIFFERENTIAL PRESSURE) BETWEEN THE STEAM | | GENERATOR (SG) AND THE MAIN STEAM SAFETY VALVE (MSSV) INLETS WHEN THE MSSVs | | ARE ACTIVATED. OMISSION OF THE SUBJECT PRESSURE LOSS FROM ANALYSES OF | | OCCURRENCES DURING WHICH MSSVs ACTUATE COULD ADVERSELY AFFECT THE RESULTS | | OF CORRESPONDING LOCA AND NON-LOCA THERMAL HYDRAULIC SAFETY ANALYSES, | | MSSV PERFORMANCE, AND PIPING SYSTEM STRUCTURAL ANALYSES. THE MAGNITUDE | | OF THE PIPING PRESSURE LOSSES THAT ABB-CE HAS EXAMINED RANGES FROM | | APPROXIMATELY 10 PSI TO MORE THAN 50 PSI. | | | | ABB-CE DETERMINED THAT THIS OMISSION WAS APPLICABLE TO ALL SAFETY ANALYSES | | DURING WHICH THE MSSVs ARE ACTIVATED FOR NUCLEAR POWER PLANTS FOR WHICH | | ABB-CE WAS THE NUCLEAR STEAM SUPPLY SYSTEM (NSSS) SUPPLIER. | | | | ON 01/16/97, ABB-CE NOTIFIED EACH LICENSEE FOR WHICH IT WAS THE NSSS | | SUPPLIER OF THIS ISSUE. | | | | ABB-CE CONSIDERS THAT THIS ISSUE MAY BE APPLICABLE TO NUCLEAR POWER PLANTS | | OTHER THAN THOSE FOR WHICH ABB-CE WAS THE NSSS SUPPLIER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31617 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/17/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 21:22 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/17/97 | +------------------------------------------------+EVENT TIME: 18:30[CST]| |NRC NOTIFIED BY: RANDY GIDEON |LAST UPDATE DATE: 01/17/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - I&C TECHNICIAN SET REACTOR SCRAM SIGNAL SETPOINT NONCONSERVATIVELY - | | | | AT 0307 (CST) ON 01/09/97, AN I&C TECHNICIAN ERRONEOUSLY SET THE SETPOINT | | FOR THE 45% REACTOR POWER BYPASS FOR THE LOAD REJECT/TURBINE TRIP SCRAM | | SIGNAL NONCONSERVATIVELY AT A PRESSURE CORRESPONDING TO APPROXIMATELY | | 50% POWER. | | | | AT 0518 (CST) ON 01/13/97, CONTROL ROOM OPERATORS DISCOVERED THIS INCORRECT | | SETPOINT. I&C TECHNICIANS ADJUSTED THE SETPOINT TO THE CORRECT SETTING. | | | | AT 1830 (CST) ON 01/17/97, LICENSEE ENGINEERING PERSONNEL DETERMINED THAT | | BETWEEN 0307 (CST) ON 01/09/97 AND 1250 (CST) ON 01/13/97, A REACTOR SCRAM | | WOULD NOT HAVE OCCURRED BETWEEN 45% AND 50% REACTOR POWER AFTER A MAIN | | GENERATOR REJECT OR MAIN TURBINE TRIP. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31618 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 01/18/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 02:15 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 01/18/97 | +------------------------------------------------+EVENT TIME: 00:23[CST]| |NRC NOTIFIED BY: SHANE FERGUSION |LAST UPDATE DATE: 01/18/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 +------------------------------------------------------------------------------+ | UNIT 1 ENTERED T.S. 3.0.3 AFTER DECLARING 3 OF THE 4 ECCS ACCUMULATORS | | INOPERABLE. | | | | "PLANT ENTERED T.S. 3.0.3 DUE TO 3 OF 4 ECCS ACCUMULATORS (EP SYSTEM) BEING | | DECLARED INOPERABLE. THE ECCS ACCUMULATORS WERE DECLARED INOPERABLE DUE TO | | LOW TEMPERATURE. TEMPERATURES WERE MEASURED LOCALLY IN CONTAINMENT AND ARE | | A RESULT OF LOW CONTAINMENT TEMPERATURE. ONE OF FOUR CONTAINMENT COOLERS | | WAS SECURED TO ALLOW CONTAINMENT TEMPERATURES TO INCREASE. CONTAINMENT | | TEMPERATURE IS CURRENTLY 67øF." | | | | "PLANT EXITED T.S. 3.0.3 AT 0110CST PER INFORMATION RECEIVED FROM | | WESTINGHOUSE." | | | | THE LICENSEE DISCOVERED THAT A DESIGN BASIS DRAWING IDENTIFIED A MINIMUM | | TEMPERATURE OF 60øF FOR THE ACCUMULATORS. THE ACCUMULATOR TEMPERATURE | | MEASURED LOCALLY SHOWED 55øF AT WHICH POINT THE LICENSEE ENTERED T.S. | | 3.0.3. WESTINGHOUSE REVIEWED THE DESIGN BASIS DRAWING REFERENCE OF 60øF | | AND FOUND THAT IT WAS ARBITRARY AND THAT OTHER PLANTS SHOWED A LOWER | | TEMPERATURE OF 40øF. BASED ON THIS INFORMATION THE LICENSEE EXITED T.S. | | 3.0.3. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31619 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 01/18/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 06:12 [ET]| |RX TYPE: [3] CE |EVENT DATE: 01/18/97 | +------------------------------------------------+EVENT TIME: 04:20[CST]| |NRC NOTIFIED BY: WESLEY |LAST UPDATE DATE: 01/18/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |WILLIAM BECKNER EO | | |RICHARD BARRETT IRD | | |HENRY BAILEY RCT | | |JOE CALLAN RA | | |FRANK MIRAGLIA NRR | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DECLARED AN ALERT DUE TO A TOXIC CHEMICAL SPILL APPROXIMATELY 10 | | MILES NORTH OF THE SITE ON THE MISSISSIPPI RIVER. | | | | AT APPROXIMATELY 0145CST A TANKER CARRYING PYROLYSIS GASOLINE (MAJOR | | COMPONENT BENZENE) RAN AGROUND ON THE MISSISSIPPI RIVER IN THE ST. JOHN | | PARISH BY GARYVILLE, LA. THE LICENSEE WAS NOTIFIED AT 0420CST, AT WHICH | | TIME THEY DECLARED AN ALERT BASED ON INITIATING CONDITION EP-4-010 TOXIC | | CHEMICAL RELEASE. AS A PRECAUTIONARY MEASURE, THE CONTROL ROOM AIR INTAKE | | WAS ISOLATED AND ONSITE PERSONNEL SHELTERED. THE INITIAL ESTIMATE FROM THE | | COAST GUARD WAS THAT APPROXIMATELY 250,000 GALLONS HAD BEEN RELEASED, | | HOWEVER, THIS QUANTITY WAS LATER REDUCED TO 100,000 GALLONS. THE LICENSEE | | ESTIMATED THAT THE RIVER BORNE SPILL WOULD HAVE REACHED THE SITE BY ABOUT | | 0400CST AND DUE TO THE DISTANCE TRAVELLED AND RELATIVELY SMALL QUANTITY | | INVOLVED, WOULD POSE NO THREAT TO THE 1,000,000 GALLON/MINUTE INTAKE FLOW. | | NO ILL EFFECTS WERE OBSERVED ONSITE. THE COAST GUARD WAS RESPONDING AT THE | | TIME OF NOTIFICATION. THE LICENSEE ACTIVATED ERDS WITHIN THE REQUIRED 1 | | HOUR OF DECLARING AN ALERT. THE LICENSEE INFORMED STATE/LOCAL AGENCIES AND | | WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | ESTABLISHED A CONFERENCE BRIDGE BETWEEN THE LICENSEE AND NRC (RDO[TAPIA], | | NRR EO[BECKNER], IRD[BARRETT], RCT[BAILEY], NRR ET[MIRAGLIA], RA[CALLAN] | | AND DEPUTY RA[DWYER]. THE NRC DECISION WAS TO REMAIN IN NORMAL MODE BASED | | ON THE CURRENT INFORMATION. | | | | * * * UPDATE 0721EST 1/18/97 FROM WESLEY TO S. SANDIN * * * | | | | THE LICENSEE DOWNGRADED THE ALERT TO AN UNUSUAL EVENT AT 0604CST BASED ON A | | COAST GUARD ASSESSMENT OF CURRENT CONDITIONS. THE LICENSEE INFORMED | | STATE/LOCAL AGENCIES AND WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED | | RDO(TAPIA), NRR EO(BECKNER), IRD (BARRETT) AND HDQTRS PAO(DRICKS). | | | | THE FOLLOWING FEDERAL AGENCIES WERE NOTIFIED: DOE(JOHNSON, MOORE), EPA & | | DOT(BRIGHT), USDA(BICKERTON), HHS(DAVIS) AND FEMA(RISHE). | | | | * * * UPDATE 0825EST 1/18/97 FROM RODRIQUE TO S. SANDIN * * * | | | | THE LICENSEE TERMINATED THE UE AT 0713CST BASED ON THE SPILL HAVING PAST | | THE SITE AND IS NO LONGER A HAZARD. THE LICENSEE WILL PROBABLY ISSUE A | | PRESS RELEASE. THE LICENSEE INFORMED STATE/LOCAL AGENCIES AND THE NRC | | RESIDENT INSPECTOR. NOTIFIED RDO(TAPIA), NRR EO(BECKNER) AND FEMA(BAGWELL). | | | | HOONOTE: THE RDO(TAPIA) AND NRR EO(BECKNER) AGREED THAT A COMMISSIONER | | ASSISTANTS BRIEFING WAS NOT REQUIRED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31620 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 01/18/97 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 09:29 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/18/97 | +------------------------------------------------+EVENT TIME: 06:12[CST]| |NRC NOTIFIED BY: PAUL BREWER |LAST UPDATE DATE: 01/18/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOCAL TELEVISION STATIONS CONTACTED REGARDING SPURIOUS EMERGENCY SIREN | | ACTUATION. | | | | "GRAND GULF NUCLEAR STATION WAS NOTIFIED BY TENSAS PARISH EMERGENCY | | PREPAREDNESS THAT EMERGENCY SIREN LAB #41 AT WESTERN AUTO ACTUATED FOR | | UNKNOWN REASONS AT 0534CST. THE SIREN WAS SILENCED AT 0539CST. LOCAL | | TELEVISION STATIONS ARE BEING NOTIFIED BY TENSAS PARISH." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31621 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 01/20/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 06:05 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 01/20/97 | +------------------------------------------------+EVENT TIME: 04:05[CST]| |NRC NOTIFIED BY: DARCEY HELD |LAST UPDATE DATE: 01/20/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNAUTHORIZED ENTRY INTO THE PROTECTED AREA BY CONTRACT EMPLOYEE. IMMEDIATE | | COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. | | | | * * * UPDATE 0947EST 1/20/97 FROM DORWICK TO S.SANDIN * * * | | THE LICENSEE ERRONEOUSLY REPORTED THE EVENT TIME AS 0359CST. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31622 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/20/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 16:49 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/20/97 | +------------------------------------------------+EVENT TIME: 16:25[EST]| |NRC NOTIFIED BY: BRENT HURSEY/D. VAIL |LAST UPDATE DATE: 01/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ELECTRICAL SEPARATION CRITERIA NOT MET. | | | | AMENDMENT 16 OF MILLSTONE UNIT 1 PROVISIONAL LICENSE ISSUED BACK IN 1969 | | STATED THAT THE S1 POWER SUPPLY (POWER FROM THE GAS TURBINE) AND THE S2 | | POWER SUPPLY (POWER FROM THE EMERGENCY DIESEL GENERATORS) FOR THE SERVICE | | WATER SYSTEM AND THE TURBINE BUILDING SECONDARY CLOSED COOLING WATER | | SYSTEMS MUST BE SEPARATED. THE LICENSEE DETERMINED THAT THE POWER SUPPLY | | CABLE FROM THE S2 SERVICE WATER TRAIN HAD BEEN RUN INTO AND OUT OF THE S1 | | SERVICE WATER TRAIN WITHOUT MEETING AMENDMENT 16 CRITERIA. AMENDMENT 16 | | STATES THAT THE REDUNDANT POWER SUPPLIES (S1 & S2) MUST EITHER BE SEPARATED | | FROM EACH OTHER BY 3 FEET OR HAVE A BARRIER BETWEEN THE TWO CABLES. THE S1 | | AND S2 POWER SUPPLY CABLES FOR THE SERVICE WATER PUMPS ARE WITHIN ONE FOOT | | OF EACH OTHER WITHOUT A BARRIER BETWEEN THE CABLES. THIS PROBLEM WILL BE | | CORRECTED. THE LICENSEE WROTE ADVERSE CONDITION REPORT # 6476 ON THIS | | PROBLEM BACK IN NOVEMBER 1995. THE TURBINE BUILDING SECONDARY CLOSED | | COOLING WATER SYSTEM PUMP'S REDUNDANT CONTROL POWER SUPPLY CABLES WERE | | FOUND TO BE WITHIN THE SAME ISOLATION BOX. THIS PROBLEM WAS CORRECTED BACK | | IN NOVEMBER 1995. THE LICENSEE WROTE ADVERSE CONDITION REPORT # 3113 ON | | THIS PROBLEM BACK IN JUNE 1995. THE LICENSEE IS LOOKING INTO THE ELECTRICAL | | SEPARATION ISSUES AT THEIR UNIT. THE STATE AND LOCAL OFFICIALS WERE | | NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31623 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 01/20/97 | |UNIT: [ ] [3] [ ] STATE: PA |NOTIFICATION TIME: 17:15 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 01/20/97 | +------------------------------------------------+EVENT TIME: 15:05[EST]| |NRC NOTIFIED BY: BOB FRANSSEN |LAST UPDATE DATE: 01/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE INJECTION (HPCI) DECLARED INOPERABLE | | | | DURING ROUTINE SURVEILLANCE TESTING ON HPCI, A LEAK FROM THE HPCI GLAND | | SEAL CONDENSER WAS DISCOVERED. HPCI SUCTION ISOLATION VALVES WERE CLOSED | | AND THE HPCI AUXILIARY OIL PUMP WAS PLACED IN PULL TO LOCK POSITION. | | LICENSEE ENTERED TECHNICAL SPECIFICATION 3.5.1 (14 DAYS TO RETURN HPCI TO | | SERVICE OR SHUTDOWN). ALL OTHER EMERGENCY CORE COOLING SYSTEMS AND RCIC ARE | | FULLY OPERABLE IF NEEDED. LICENSEE HAS CALLED IN MAINTENANCE AND | | ENGINEERING TO RESTORE HPCI TO SERVICE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31624 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 01/20/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 17:50 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/20/97 | +------------------------------------------------+EVENT TIME: 16:00[CST]| |NRC NOTIFIED BY: TODD MIELKE |LAST UPDATE DATE: 01/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 90 POWER OPERATION | 90 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PROMPT OPERABILITY OF THE SUMP RECIRCULATION SYSTEM AND LONG TERM CORE | | COOLING MAY NOT BE MET AFTER A DESIGN BASIS LOSS OF COOLANT ACCIDENT. | | | | DURING EVALUATION OF CONDITION REPORT 96-1848, IT WAS DISCOVERED THAT A | | MORE CONSERVATIVE ASSUMPTION WAS NECESSARY IN THE POINT BEACH NUCLEAR POWER | | PLANT DESIGN BASIS LOSS OF COOLANT ACCIDENT ANALYSIS. THE POTENTIAL EXISTS | | TO TRAP APPROXIMATELY 45,000 GALLONS OF WATER IN THE REFUELING CAVITY | | MAKING IT UNAVAILABLE FOR SUMP RECIRCULATION AND LONG TERM CORE COOLING. A | | PROMPT OPERABILITY DETERMINATION HAS BEEN WRITTEN WHICH DOCUMENTS THE | | CONTINUED ABILITY OF THE EMERGENCY CORE COOLING SYSTEM TO PERFORM ITS | | DESIGN FUNCTION. A CLARIFYING EMERGENCY OPERATING PROCEDURE CHANGE IS BEING | | DEVELOPED TO ENSURE THAT SUFFICIENT REFUELING WATER STORAGE TANK VOLUME IS | | TRANSFERRED TO CONTAINMENT DURING A DESIGN BASIS ACCIDENT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31625 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 01/20/97 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 18:17 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 01/20/97 | +------------------------------------------------+EVENT TIME: 18:07[EST]| |NRC NOTIFIED BY: T TREPANIER |LAST UPDATE DATE: 01/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |KFIS 70.52(b) LOSS OF SNM/FISSILE |BECKNER / HICKEY EO | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X |BARRETT IRD | | |McPEEK (NRR) IAT | | |DAVIDSON (NMSS) IAT | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL LOSS OF SPECIAL NUCLEAR MATERIAL (SNM). | | | | IN 1986-1987, THE LICENSEE PERFORMED A PAPER INVENTORY OF THE AMOUNT OF SNM | | THEY HAD IN THE SPENT FUEL POOL. THEY USED THIS AMOUNT FOR THE BASELINE OF | | HOW MUCH SNM THEY HAD AT THEIR SITE. IN THE FALL OF 1996, THE LICENSEE | | PERFORMED A PHYSICAL INVENTORY OF THEIR SPENT FUEL POOL (SRMs, IRMs, TIPs, | | LPRMs, FUEL AND FUEL CHAMBERS) TO FIND OUT HOW MUCH SNM THEY HAD. WHEN THE | | 1996 PHYSICAL INVENTORY OF SNM WAS COMPARED AGAINST THE 1986-1987 SNM | | BASELINE DATA, THEY FOUND THAT 0.056 GRAMS OF SNM WAS MISSING. THIS IS | | EQUIVALENT TO 14 SRMs/IRMs PLUS 4 TIPs. THE LICENSEE AT THIS TIME, CANNOT | | PROVE THAT THEY DID NOT LOSE 0.056 GRAMS OF SNM. THE TOTAL ACTIVITY OF THE | | MISSING URANIUM-235 SNM IS O.12 æCi. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+