U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/08/95 - 12/11/95 ** EVENT NUMBERS ** 29569 29685 29686 29687 29688 29689 29690 29691 29692 29693 29694 29695 29696 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29569 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 11/07/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 15:23 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 11/07/95 | +------------------------------------------------+EVENT TIME: 11:35[EST]| |NRC NOTIFIED BY: MIKE BOURASSA |LAST UPDATE DATE: 12/08/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION |ED GOODWIN, NRR EO | | |RICH BARRETT AEOD | | |HENRY BAILEY AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 72 POWER OPERATION | 72 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 2 OF 2 DIESEL GENERATORS INOPERABLE WITH THE PLANT AT 72% POWER - | | | | BIG ROCK POINT HAS A TOTAL OF TWO DIESEL GENERATORS; A TECH SPEC REQUIRED | | EMERGENCY DIESEL GENERATOR (EDG) AND A STANDBY DIESEL GENERATOR (D/G). | | THE STANDBY D/G IS REQUIRED TO BE AVAILABLE FOR OPERATION WITHIN 24 HOURS | | FOLLOWING A LOSS OF COOLANT ACCIDENT IN ACCORDANCE WITH BIG ROCK POINT'S | | FINAL HAZARDS SUMMARY REPORT (FHSR) (aka FSAR), APPENDIX K, EXCEPTION. | | THIS STANDBY D/G IS NOT ADDRESSED IN BIG ROCK POINT TECH SPECS; THEREFORE, | | THERE ARE NO TECH SPEC OPERABILITY REQUIREMENTS FOR THE STANDBY D/G. | | | | ON 11/02/95, LICENSEE PERFORMED A TECH SPEC SURVEILLANCE TEST OF THE | | TECH SPEC EDG AND RECORDED THE TEST RESULTS DATA. | | | | AT 0530 ON 11/06/95, LICENSEE DECLARED THE STANDBY D/G INOPERABLE AFTER IT | | FAILED ITS WEEKLY SURVEILLANCE TEST (FAILED TO START WITHIN THE REQUIRED | | 30 SECONDS) PROBABLY DUE TO BATTERY FAILURE. HOWEVER, THE STANDBY D/G IS | | STILL FUNCTIONAL. | | | | AT 1135 ON 11/07/95, LICENSEE DECLARED THE TECH SPEC EDG INOPERABLE DUE TO | | DEGRADED COOLING WATER FLOW AFTER ANALYZING THE TEST RESULTS DATA TAKEN ON | | 11/02/95. TECH SPEC LCO A/S 11.3.5.3.A.2 REQUIRES THE LICENSEE TO RESTORE | | THE TECH SPEC EDG TO OPERABLE STATUS WITHIN 3 DAYS OR TO PLACE THE PLANT | | IN COLD SHUTDOWN CONDITION WITHIN THE FOLLOWING 36 HOURS. | | | | AT 1235 ON 11/07/95, LICENSEE STARTED THE STANDBY D/G AND MAY RUN IT UNTIL | | THE TECH SPEC EDG IS DECLARED OPERABLE. LICENSEE IS DISCUSSING THIS OPTION | | WITH CATERPILLAR, THE STANDBY D/G SUPPLIER. LICENSEE IS ALSO DISCUSSING | | WITH CATERPILLAR THE POSSIBILITY OF BRINGING ANOTHER D/G TO THE PLANT | | WITHIN 24 HOURS, IF NEEDED. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * 1056 DECEMBER 8, 1995, UPDATE FROM BOURASSA TAKEN BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION FOR THE FOLLOWING | | REASONS: | | | | A LOSS OF ONSITE EMERGENCY AC POWER AT BIG ROCK POINT IS DEFINED AS AN | | INOPERABLE EDG AND THE INABILITY TO SECURE A STANDBY D/G WITHIN 24 HOURS | | FOLLOWING A LOSS OF COOLANT ACCIDENT. FOR THIS EVENT, THE LICENSEE HAS | | CONCLUDED THAT ONSITE EMERGENCY AC POWER WAS NEVER COMPLETELY LOST; | | THEREFORE, THIS CONDITION DID NOT MEET THE THRESHOLD FOR REPORTABILITY. | | THE LICENSEE BELIEVES THAT THE EDG WOULD HAVE BEEN ABLE TO PERFORM ITS | | SAFETY FUNCTION (WITHOUT OVERHEATING UNDER FULL LOAD CONDITIONS) DURING | | THE SUSPECTED PERIOD OF LOW FLOW DUE TO SEASONABLY LOWER INLET WATER | | TEMPERATURES. THE STANDBY D/G (THOUGH DECLARED INOPERABLE DUE TO A | | STARTING FAILURE) WAS STARTED, LOADED, AND DEMONSTRATED AVAILABLE FOR | | SERVICE. IN ADDITION, CATERPILLAR WAS CONTACTED AND PROVIDED ASSURANCE | | THAT ANOTHER DIESEL COULD BE TRANSPORTED TO THE SITE WITHIN 24 HOURS, | | IF NEEDED. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3D0 (LANKSBURY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29685 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 12/08/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 01:15 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/07/95 | +------------------------------------------------+EVENT TIME: 22:35[EST]| |NRC NOTIFIED BY: BOB HEATHCOTE |LAST UPDATE DATE: 12/08/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |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 | M/R Y 32 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO HIGH TURBINE BEARING VIBRATIONS | | | | AS PART OF A PLANNED EVOLUTION, OPERATORS WERE DECREASING REACTOR POWER | | FROM 71% TO 7% TO REMOVE THE TURBINE GENERATOR FROM SERVICE FOR REPAIRS TO | | THE MAIN TRANSFORMER AND ELECTRO-HYDRAULIC CONTROL SYSTEMS. AT | | APPROXIMATELY 49% REACTOR POWER AND COINCIDING WITH THE REMOVAL OF THE | | MOISTURE SEPARATOR REHEATER STEAM SUPPLIES, MAIN TURBINE BEARING #5 | | VIBRATION STARTED TO INCREASE. ATTEMPTS TO REDUCE THE VIBRATION BY | | CHANGING OIL TEMPERATURES, MOISTURE SEPARATOR REHEATER STEAM PRESSURES, AND | | TURBINE LOAD WERE UNSUCCESSFUL. WHEN THE #5 BEARING RIGHT AND LEFT SIDE | | VIBRATION INDICATORS READ 13 MILS AND 7 MILS VIBRATION AND INCREASING, | | RESPECTIVELY, A REACTOR TRIP WAS ORDERED BY THE UNIT SUPERVISOR. AS A | | RESULT, THE REACTOR WAS MANUALLY TRIPPED FROM 32% POWER AT 22:35. (AN | | AUTOMATIC TURBINE TRIP, WHICH WOULD HAVE CAUSED AN AUTOMATIC REACTOR TRIP, | | WOULD HAVE OCCURRED IF ONE LEFT AND ONE RIGHT VIBRATION INDICATOR HAD | | EXCEEDED 12 MILS.) ALL RODS FULLY INSERTED ON THE MANUAL REACTOR TRIP, AND | | ALL SYSTEMS FUNCTION AS REQUIRED. MAIN FEEDWATER ISOLATED, AND AUXILIARY | | FEEDWATER AUTOMATICALLY INITIATED AS EXPECTED. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3. PRESSURIZER HEATERS AND SPRAYS, | | NORMAL CHARGING AND MAKEUP, AND THE REACTOR COOLANT PUMPS ARE BEING USED | | FOR PRIMARY PRESSURE, INVENTORY, AND TRANSPORT CONTROL. AUXILIARY | | FEEDWATER IS BEING SUPPLIED TO THE STEAM GENERATORS, AND SECONDARY STEAM IS | | BEING DUMPED TO THE CONDENSER. UNIT RESTART IS CURRENTLY SCHEDULED FOR | | DECEMBER 10, 1995. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29686 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNIVERSITY OF NORTH CAROLINA |NOTIFICATION DATE: 12/08/95 | | CITY: CHAPEL HILL REGION: 2 |NOTIFICATION TIME: 11:51 [ET]| | COUNTY: STATE: NC |EVENT DATE: 12/08/95 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 12/08/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |VERRELLI RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MEL FRY | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STATE OF NORTH CAROLINA CALLED TO INFORM THE NRC OF SEVERAL LOST | | RADIOACTIVE SOURCES AT THE UNIVERSITY OF NORTH CAROLINA, CHAPEL HILL. | | | | FOUR CS-137 SOURCES (TOTAL ACTIVITY 40 - 50 mCi) WERE IMPLANTED TO TREAT A | | PATIENT, AND WHEN THE LICENSEE ATTEMPTED TO REMOVE THE SOURCES, ALL FOUR | | WERE MISSING. THE LICENSEE BELIEVES THAT THE SOURCES WERE TAKEN TO A LOCAL | | LANDFILL. A SURVEY TEAM HAS BEEN DISPATCHED TO THE LANDFILL. NO FURTHER | | INFORMATION WAS AVAILABLE FROM THE STATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29687 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 12/08/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 12:26 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/08/95 | +------------------------------------------------+EVENT TIME: 11:14[EST]| |NRC NOTIFIED BY: HOLLENQUIST |LAST UPDATE DATE: 12/08/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PASCIAK 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 | A/R Y 80 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM DUE TO HIGH REACTOR VESSEL WATER LEVEL. | | | | AT 1114, THE UNIT RECEIVED AN AUTOMATIC REACTOR SCRAM FROM 80% REACTOR | | POWER DUE TO HIGH REACTOR VESSEL WATER LEVEL. THE LICENSEE WAS IN THE | | PROCESS OF REDUCING REACTOR POWER TO 50% IN ORDER TO REMOVE THE 'A' | | FEEDWATER REGULATING VALVE FROM SERVICE FOR REPAIRS. THE LICENSEE HAD | | OBSERVED FLOW OSCILLATION PROBLEMS WITH THE VALVE DURING THE PREVIOUS TWO | | DAYS. ALL CONTROL RODS COMPLETELY INSERTED, AND ALL SYSTEMS FUNCTIONED AS | | EXPECTED. | | | | AT 0935, WITH THE UNIT AT 79% REACTOR POWER, THE FEEDWATER PIPING LOCATED | | IN THE FEED PUMP ROOM BEGAN TO SHAKE. THE 'A' FEED REG VALVE WAS PLACED IN | | LOCAL MANUAL CONTROL BY THE INSERTION OF A TAPERED PIN. THIS ACTION | | REDUCED SYSTEM VIBRATION, AND THE LICENSEE HELD IN THIS CONDITION TO PERMIT | | CLEANUP OF ASBESTOS INSULATION SHAKEN LOOSE FROM THE FEEDWATER PIPING, AND | | TO ALLOW THE LICENSEE TO PERFORM AN ENGINEERING ANALYSIS OF THE FEEDWATER | | PIPING. SUBSEQUENTLY, THE TAPERED PIN VIBRATED OUT OF POSITION, RELEASING | | MANUAL CONTROL OF THE 'A' FEED REG VALVE, AND THE REACTOR SCRAMMED DUE TO | | HIGH REACTOR VESSEL WATER LEVEL (+177"). THE LICENSEE STATED THAT THE | | WATER LEVEL REACHED A MAXIMUM OF +190" (THE STEAM LINES ARE LOCATED AT | | +234"), BEFORE BEING RETURNED TO THE NORMAL CONTROL BAND. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29688 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 12/08/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 16:16 [ET]| |RX TYPE: [1] CE |EVENT DATE: 12/08/95 | +------------------------------------------------+EVENT TIME: 14:15[EST]| |NRC NOTIFIED BY: WALDMAN |LAST UPDATE DATE: 12/08/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PASCAIK 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED STATE OF MAINE REGARDING OIL SPILL ONSITE. | | | | THE LICENSEE CONTACTED THE STATE OF MAINE REGARDING 10 GALLONS OF OIL WHICH | | WERE SPILLED ONTO THE GROUND AT THE SITE. THE OIL HAS BEEN CLEANED UP BY | | THE LICENSEE. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29689 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 12/08/95 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 16:24 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 12/08/95 | +------------------------------------------------+EVENT TIME: 00:00[EST]| |NRC NOTIFIED BY: TREPANIER |LAST UPDATE DATE: 12/08/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PASCIAK 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COURTESY NOTIFICATION REGARDING POSSIBLE INACCURACY IN CORE THERMAL HEAT | | BALANCE. | | | | AFTER REVIEW OF INPO REPORTS FROM NINE MILE POINT AND GRAND GULF (SEE | | RELATED EVENT NOTIFICATION NOS. 29603 AND 29667), THE LICENSEE HAS | | DETERMINED THAT APPROXIMATELY 10 GPM OF FLOW FROM THE CONTROL ROD DRIVE | | (CRD) SYSTEM, WHICH IS USED TO PURGE THE SEALS OF THE REACTOR RECIRCULATION | | PUMPS, IS NOT ACCOUNTED FOR IN THE CORE THERMAL HEAT BALANCE. THE LICENSEE | | HAS CALCULATED THAT A MAXIMUM ERROR OF 1.63 MWt IN THE INDICATED CORE | | THERMAL POWER LEVEL COULD OCCUR ASSUMING MAXIMUM FLOW RATE AND ENTHALPY | | CHANGE. | | | | REACTOR POWER HAS BEEN REDUCED BY 2 MWt (FROM 1998 TO 1996 MWt INDICATED) | | TO ACCOUNT FOR THIS ERROR. THE LICENSEE REPORTED THIS EVENT BECAUSE OF | | POTENTIAL INTEREST TO OTHER BOILING WATER REACTOR FACILITIES. PILGRIM IS | | OF AN EARLIER VINTAGE THAN NINE MILE POINT 2 AND GRAND GULF AND WAS NOT | | EXPECTED TO HAVE THIS PROBLEM. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29690 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 12/08/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:50 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 12/08/95 | +------------------------------------------------+EVENT TIME: 17:05[EST]| |NRC NOTIFIED BY: LIJOI |LAST UPDATE DATE: 12/08/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PASCIAK RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTAINMENT VENTILATION ISOLATION DUE TO RADIATION MONITOR LOW FLOW ALARM. | | | | WHILE PERFORMING A CONTAINMENT ATMOSPHERE PRESSURE RELIEF, RADIATION | | MONITOR R43/44 (PARTICULATE/IODINE MONITOR) RECEIVED A LOW FLOW ALARM. THIS | | CAUSED THE CONTAINMENT VENTILATION PRESSURE RELIEF VALVES TO AUTOMATICALLY | | CLOSE. THE LICENSEE HAS DETERMINED THAT NO LOW FLOW CONDITION EXISTED WITH | | THE RADIATION MONITOR, AND THE MONITOR HAS BEEN RESET. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29691 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 12/08/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:46 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 12/08/95 | +------------------------------------------------+EVENT TIME: 16:00[CST]| |NRC NOTIFIED BY: LIZALEK |LAST UPDATE DATE: 12/08/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LANKSBURY RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT REQUIRED BY UNIT OPERATING LICENSE DUE TO ERROR IN CORE | | THERMAL HEAT BALANCE. | | | | THE LICENSEE HAS DETERMINED THAT, DUE TO THE FAILURE TO ACCOUNT FOR ALL | | CONTROL ROD DRIVE FLOW INTO THE REACTOR, RESULTS OF THE CORE THERMAL HEAT | | BALANCE COULD BE UP TO 1.0 MWt TOO LOW. DUE TO THIS ERROR, THE LICENSEE | | BELIEVES THAT THE UNIT MAY HAVE OPERATED ABOVE ITS LICENSED THERMAL POWER | | LIMIT. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. SEE | | RELATED EVENT NOTIFICATIONS 29603, 29667 AND 29689. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29692 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 12/08/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 23:24 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/08/95 | +------------------------------------------------+EVENT TIME: 21:56[EST]| |NRC NOTIFIED BY: PORTER |LAST UPDATE DATE: 12/08/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI RDO | |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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO PROBLEMS WITH MAIN FEEDWATER REGULATING VALVE. | | | | AT 2156, OPERATORS MANUALLY TRIPPED THE UNIT FROM 100% POWER AFTER LOSING | | LEVEL CONTROL IN THE #4 STEAM GENERATOR. FOLLOWING THE TRIP, ALL CONTROL | | RODS INSERTED, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THE CAUSE OF THE | | LEVEL CONTROL PROBLEM WAS A LEAKING CONTROL AIR FITTING ON THE #4 MAIN | | FEEDWATER REGULATING VALVE. MINIMUM LEVEL IN THE #4 STEAM GENERATOR WAS | | 13% NARROW RANGE AT THE TIME OF THE TRIP. | | | | THE LICENSEE REPORTED THAT A LEVEL TRANSIENT OCCURRED ON THE #4 STEAM | | GENERATOR AT 2122. OPERATORS WERE DISPATCHED TO INVESTIGATE, AND THEY | | DISCOVERED A BROKEN FITTING ON CONTROL AIR SUPPLY TO THE #4 MAIN FEEDWATER | | REG VALVE. THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY | | THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29693 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 12/09/95 | |UNIT: [1] [2] [ ] STATE: AZ |NOTIFICATION TIME: 08:55 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 12/09/95 | +------------------------------------------------+EVENT TIME: 03:22[MST]| |NRC NOTIFIED BY: JIM MORELAND |LAST UPDATE DATE: 12/09/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |RICHARD WESSMAN EO | |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 40 POWER OPERATION | 0 HOT STANDBY | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -UNIT 1 REACTOR TRIP FROM 40% CAUSED BY LOSS OF 1 OF 3 STARTUP TRANSFORMERS | | | | UNIT 1 WAS OPERATING AT 40% POWER, AND UNIT 2 WAS OPERATING AT 100% POWER. | | | | AT 0322 (MST), PALO VERDE LOST 1 OF 3 STARTUP TRANSFORMERS (#NAN-X03) FOR | | UNKNOWN REASONS. THIS TRANSFORMER FEEDS POWER TO UNIT 1 14-KV STARTUP YARD | | BUS #1S05 (NORMAL FEED) AND UNIT 2 14-KV STARTUP YARD BUS #2S06 (NORMAL | | FEED). | | | | WHEN UNIT 1 POWER (WHICH IS NORMALLY FED FROM BUS #1S05 TO THE 14-KV UNIT | | INTERMEDIATE STARTUP BUS #1S03 AND THEN TO THE 4-KV TRAIN 'A' BUS #1PBAS03) | | WAS LOST, THIS CAUSED A LOSS OF POWER TO THE MAIN FEEDWATER CONTROL SYSTEM. | | THIS CAUSED THE MAIN FEEDWATER PUMPS TO GO TO MINIMUM SPEED WHICH CAUSED | | THE WATER LEVEL IN 2 OF 2 STEAM GENERATORS TO DECREASE TO THE REACTOR TRIP | | SETPOINT. THE REACTOR TRIPPED ON LOW WATER LEVEL ON #2 STEAM GENERATOR. | | ALL CONTROL RODS INSERTED COMPLETELY. | | | | THE LOSS OF POWER TO BUS #1S03 ALSO CAUSED A LOSS OF POWER TO 14-KV | | NON-CLASS 1E BUS #1S01 WHICH CAUSED 2 OF 4 REACTOR COOLANT PUMPS TO TRIP. | | THE TRAIN 'A' EDG (1 OF 2 EDGs) STARTED AND LOADED. | | | | CONTROL ROOM OPERATORS RESTORED WATER LEVEL IN BOTH STEAM GENERATORS USING | | THE MAIN FEEDWATER SYSTEM IN MANUAL CONTROL MODE. THE WATER LEVELS IN THE | | STEAM GENERATORS DID NOT DECREASE LOW ENOUGH TO AUTOMATICALLY START THE | | AUXILIARY FEEDWATER SYSTEM. CONTROL ROOM OPERATORS MANUALLY STARTED THE | | AUXILIARY FEEDWATER SYSTEM. | | | | STEAM IS BEING DUMPED TO THE ATMOSPHERE. UNIT 1 IS STABLE IN MODE 3 (HOT | | STANDBY). | | | | WHEN UNIT 2 POWER (WHICH IS NORMALLY FED FROM BUS #2S06 TO THE 14-KV UNIT | | INTERMEDIATE STARTUP BUS #2SO4 AND THEN TO THE 4-KV TRAIN 'B' BUS #2PBBS04) | | WAS LOST, TRAIN 'B' EDG (1 OF 2 EDGs) STARTED AND LOADED. | | | | OFFSITE POWER WAS RESTORED TO UNIT 2 BY 0645 (MST). UNIT 2 REMAINED AT | | 100% POWER THROUGHOUT THIS EVENT. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE LOSS OF TRANSFORMER #NAN-X03. | | THERE WERE NO PERSONNEL INJURIES DURING THIS EVENT. | | | | UNIT 3 IS UNAFFECTED BY THIS EVENT. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29694 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 12/09/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 12:03 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/08/95 | +------------------------------------------------+EVENT TIME: 17:25[EST]| |NRC NOTIFIED BY: MORRIS |LAST UPDATE DATE: 12/09/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PASCIAK 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 +------------------------------------------------------------------------------+ | 24-HOUR REPORT REQUIRED BY PLANT OPERATING LICENSE DUE TO ERROR IN REACTOR | | CORE THERMAL HEAT BALANCE. | | | | AFTER REVIEW OF INPO REPORTS, THE LICENSEE HAS DETERMINED THAT | | APPROXIMATELY 5 GPM OF FLOW FROM THE CONTROL ROD DRIVE (CRD) SYSTEM IS NOT | | ACCOUNTED FOR IN THE CORE THERMAL HEAT BALANCE. THE LICENSEE REPORTED THAT | | DUE TO THIS ERROR, A MAXIMUM ERROR OF 0.6 MWt IS POSSIBLE IN THE CORE | | THERMAL HEAT BALANCE CALCULATION. THE LICENSEE IS CURRENTLY REVIEWING | | PLANT OPERATING HISTORY TO DETERMINE WHETHER THE LICENSED CORE THERMAL | | POWER LIMIT HAS BEEN EXCEEDED. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED BY THE LICENSEE. SEE RELATED EVENT NOTIFICATIONS 29603, 29667, | | 29689, AND 29691. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29695 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 12/09/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:06 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/09/95 | +------------------------------------------------+EVENT TIME: 12:49[CST]| |NRC NOTIFIED BY: RATZLAFF |LAST UPDATE DATE: 12/09/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |STETKA 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SHUTDOWN COOLING ISOLATION VALVES CLOSED DUE TO SPURIOUS SIGNAL | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT 1249 ON 12/9/95 'A' RHR PUMP TRIPPED WHILE OPERATING IN SHUTDOWN | | COOLING MODE OF RHR DUE TO THE SHUTDOWN COOLING ISOLATION VALVES | | AUTOMATICALLY CLOSING. INITIAL INVESTIGATION INDICATES THE LOGIC CLOSED | | THE VALVES ON A HIGH REACTOR PRESSURE ISOLATION SIGNAL. THE HIGH REACTOR | | PRESSURE SETPOINT IS LESS THAN OR EQUAL TO 75 PSIG. NO IMMEDIATE CAUSE FOR | | THE SUSPECTED SPURIOUS ISOLATION SIGNAL HAS BEEN DETERMINED. FURTHER | | INVESTIGATION INTO THE CAUSE IS ONGOING. THE PLANT IS IN A COLD SHUTDOWN | | CONDITION WITH THE RPV VENTED. | | | | AT 1333 'A' RHR PUMP WAS RESTARTED IN SHUTDOWN COOLING. REACTOR COOLANT | | TEMPERATURE HAD RISEN BY ~3øF WHILE SHUTDOWN COOLING WAS OFF. AN UNPLANNED | | AUTOMATIC CLOSURE OF THE SHUTDOWN COOLING SUCTION ISOLATION VALVES IS AN | | ESF ACTUATION." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29696 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 12/10/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 12:25 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/10/95 | +------------------------------------------------+EVENT TIME: 11:58[EST]| |NRC NOTIFIED BY: STEWART |LAST UPDATE DATE: 12/10/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |PASCIAK RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |WESSMAN EO | |AFIR 50.72(b)(1)(vi) FIRE (ONSITE) |MIKE FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO FIRE ONSITE. | | | | THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO A FIRE LASTING LONGER THAN 10 | | MINUTES IN THE D23 EMERGENCY DIESEL GENERATOR BAY. THE FIRE WAS IN AN | | OVERHEAD LIGHTING FIXTURE AND DID NOT AFFECT THE DIESEL GENERATOR. THE | | FIRE HAS BEEN EXTINGUISHED, BUT THE LICENSEE IS WAITING TO SEE IF IT | | REFLASHES BEFORE EXITING THE UNUSUAL EVENT. THE NRC RESIDENT INSPECTOR | | WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE 1234 12/10/95, FROM STEWART TAKEN BY STRANSKY * * * | | | | THE UNUSUAL EVENT HAS BEEN TERMINATED. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED. NOTIFIED R1DO (PASCIAK), EO (WESSMAN), FEMA (MIKE). | +------------------------------------------------------------------------------+