U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/13/95 - 01/17/95 ** EVENT NUMBERS ** 28155 28236 28237 28238 28239 28240 28241 28242 28243 28244 28245 28246 28247 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28155 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/17/94 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 15:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/17/94 | +------------------------------------------------+EVENT TIME: 11:39[EST]| |NRC NOTIFIED BY: SAUER |LAST UPDATE DATE: 01/13/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP SIGNALS GENERATED DURING SAFETY INJECTION SYSTEM LOGIC TESTING | | DUE TO PROCEDURAL PROBLEMS. | | | | A REACTOR TRIP SIGNAL WAS GENERATED DURING MANUAL SAFETY INJECTION (SI) | | SYSTEM LOGIC TESTING AS A RESULT OF SWITCH MANIPULATIONS IN THE SOLID STATE | | PROTECTION SYSTEM (SSPS). THIS RESULTED IN A "GENERAL WARNING" REACTOR | | TRIP (DESCRIBED AS "TWO SEPARATE PROBLEMATIC CONDITIONS IN THE SSPS"). THE | | REACTOR TRIP BREAKERS, WHICH HAD BEEN CLOSED IN TO SUPPORT THE TESTING, | | WERE NOT PROCEDURALLY ANTICIPATED TO OPEN. THE ROD CONTROL SYSTEM WAS OUT | | OF SERVICE AT THE TIME, AND THEREFORE NO CONTROL ROD MOVEMENT OCCURRED. | | | | THE SAME ACTUATION HAD OCCURRED ON THE PREVIOUS DAY (WHILE PERFORMING THE | | SAME TEST FOR THE OTHER SI TRAIN), BUT IT WAS NOT RECOGNIZED AT THE TIME AS | | BEING REPORTABLE. THE CAUSE OF THE TRIP IS ATTRIBUTED TO PROCEDURAL | | INADEQUACY. THE PROCEDURE WAS APPARENTLY REVISED IN OCTOBER, AND THIS | | PROCEDURE IS ONLY PERFORMED DURING REFUELING OUTAGES. THE LICENSEE WILL BE | | FULLY INVESTIGATING THE CAUSE OF THE TRIPS DURING THE TESTS, AND WILL BE | | SUBMITTING A LICENSEE EVENT REPORT. THE LICENSEE INFORMED THE RESIDENT | | INSPECTOR AND LAC TOWNSHIP. | | | | ****RETRACTION BY BRIAN HAMILTON @ 1232 ET 01/13/95 TAKEN BY MACKINNON**** | | | | LICENSEE IS RETRACTING THIS EVENT BECAUSE THE ABOVE ACTUATION WAS CAUSED BY | | AN INVALID ACTUATION SIGNAL (PERSONNEL ERROR). THE ROD CONTROL SYSTEM HAD | | ALREADY BEEN PROPERLY REMOVED FROM SERVICE (SYSTEM HAD BEEN DEENERGIZED AND | | TAGGED OUT OF SERVICE PER A PROCEDURE) AND ALL THE CONTROL RODS WERE FULLY | | INSERTED INTO THE CORE WHEN THE INVALID SIGNAL WAS RECEIVED. R1DO (M | | SHANBAKY) NOTIFIED. | | | | LICENSEE WILL INFORM THEIR RESIDENT INSPECTOR OF THIS RETRACTION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28236 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 01/13/95 | |UNIT: [1] [ ] [ ] STATE: AL |NOTIFICATION TIME: 09:13 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/13/95 | +------------------------------------------------+EVENT TIME: 07:58[CST]| |NRC NOTIFIED BY: GRISSETTE |LAST UPDATE DATE: 01/13/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP/REACTOR TRIP DUE TO LOSS OF DC POWER TO TURBINE | | CONTROL SYSTEM. | | | | AT 0758 CST, THE REACTOR TRIPPED FROM 100% POWER DUE TO A TURBINE TRIP. THE | | FIRST-OUT ANNUNCIATOR INDICATED A LOSS OF DC POWER TO THE DEH (DIGITAL | | ELECTRO-HYDRAULIC) CONTROL SYSTEM. ALL CONTROL RODS INSERTED FOLLOWING THE | | TRIP, AND ALL AUTOMATIC SYSTEMS FUNCTIONED AS REQUIRED. | | | | THE LICENSEE INDICATED THAT NO ACTIVITIES WERE IN PROGRESS WHICH SHOULD | | HAVE CAUSED THE LOSS OF DC POWER. THE LICENSEE PLANS TO INVESTIGATE THE | | CAUSE OF THE POWER FAILURE. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28237 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 01/13/95 | |UNIT: [ ] [2] [ ] STATE: MD |NOTIFICATION TIME: 11:37 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 01/13/95 | +------------------------------------------------+EVENT TIME: 10:47[EST]| |NRC NOTIFIED BY: DENTON |LAST UPDATE DATE: 01/14/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SHANBAKY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP DUE TO ENGINEERED SAFETY FEATURES ACTUATION SIGNAL | | (ESFAS) AND ISOLATION OF MAIN STEAM AND FEEDWATER SYSTEMS | | | | AN AUTOMATIC REACTOR TRIP OCCURRED DUE TO AN ESFAS ACTUATION WHICH CAUSED | | ISOLATION OF MAIN STEAM AND FEEDWATER SYSTEMS. THE CAUSE OF THE TRIP HAS | | NOT BEEN DETERMINED, BUT WAS CAUSED BY EITHER HIGH PRESSURIZER PRESSURE OR | | LOW STEAM GENERATOR LEVEL. FOLLOWING THE REACTOR TRIP, ALL CONTROL RODS | | INSERTED AND THE AUXILIARY FEEDWATER SYSTEM AUTOMATICALLY STARTED TO | | CONTROL STEAM GENERATOR LEVELS. | | | | THE LICENSEE BELIEVES THAT THE ESFAS SIGNAL WAS GENERATED DUE TO TESTING OF | | THE "D" CHANNEL, WITH A SIMULTANEOUS FAILURE OF A WIRE FROM A TRANSMITTER | | ON THE "A" CHANNEL. AT THE TIME OF THE TEST, THE "D" CHANNEL WAS PLACED IN | | THE TRIPPED CONDITION DUE TO ONGOING TESTING. THE LICENSEE BELIEVES THAT A | | TECHNICIAN WAS PERFORMING A FIELD CHECK OF WIRING ASSOCIATED WITH THE "A" | | CHANNEL WHEN A WIRE FROM A TRANSMITTER BROKE. THE LICENSEE STATED THAT NO | | PLANT CONDITION EXISTED WHICH WOULD HAVE RESULTED IN AN ESFAS SIGNAL. THE | | NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | *UPDATE DATE/TIME:1/14/95 @ 0010 EST *FROM LICENSEE:McCAFFERTY BY:McGINTY* | | THE LICENSEE DISCOVERED DURING THE POST-TRIP REVIEW THAT AN "AFAS | | (AUXILIARY FEEDWATER ACTUATION SYSTEM) BLOCK" OCCURRED. THE BLOCK CAME IN | | AND OUT (ABOUT 40 SECONDS DURATION) DUE TO INSTRUMENT MAINTENANCE SHOP | | PERSONNEL COMING OUT OF THE TEST THAT THEY WERE PERFORMING. THE AFAS BLOCK | | WAS AN UNEXPLAINED RESULT OF THE ESFAS ACTUATION, AND PROMPTED THE | | INVESTIGATION TO DETERMINE ITS CAUSE. THE AFAS BLOCK FUNCTIONS TO PREVENT | | FEEDING A FAULTED STEAM GENERATOR WITH EMERGENCY FEEDWATER. THE LICENSEE | | INFORMED THE RESIDENT INSPECTOR. HOO NOTIFIED THE R1DO (SHANBAKY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28238 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 01/13/95 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 12:43 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 12/19/94 | +------------------------------------------------+EVENT TIME: 12:15[PST]| |NRC NOTIFIED BY: JOHN SIMS |LAST UPDATE DATE: 01/13/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | ELECTRICAL SEPARATION BARRIER LOCATED INSIDE ELECTRICAL PANEL P601 | | (ASSOCIATED WITH AUTOMATIC CLOSURE OF RCIC TURBINE STEAM LINE CONTAINMENT | | ISOLATION VALVES) FOUND MISSING. | | | | LICENSEE FOUND THAT AN ELECTRICAL SEPARATION BARRIER INSIDE ELECTRICAL | | PANEL P601 (ECCS CONTROL PANEL LOCATED INSIDE CONTROL ROOM) FOR CONTROLLING | | AUTOMATIC ISOLATION OF RCIC TURBINE STEAM LINE PRIMARY & SECONDARY | | CONTAINMENT ISOLATION VALVES WAS MISSING. IF A FIRE HAD OCCURRED INSIDE THE | | PANEL, AUTOMATIC ISOLATION OF RCIC TURBINE STEAM LINE CONTAINMENT ISOLATION | | VALVES MIGHT NOT HAVE OCCURRED. LICENSEE REINSTALLED THE BARRIER ON | | 12/19/95. LICENSEE THINKS THAT THE FIRE SEPARATION BARRIER WAS REMOVED | | DURING MAINTENANCE (DID NOT KNOW WHEN THE ELECTRICAL SEPARATION BARRIER WAS | | REMOVED). | | INITIAL EVALUATION OF THE IMPACT OF THE MISSING ELECTRICAL SEPARATION DID | | NOT DISCOVER THAT RCIC TURBINE STEAM LINE CONTAINMENT ISOLATION VALVES | | MIGHT NOT HAVE AUTOMATICALLY ISOLATED. LICENSEE MADE THE DETERMINATION | | TODAY THAT THIS EVENT SHOULD BE REPORTED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28239 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/13/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 17:38 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/13/95 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: JOHN JORDAN |LAST UPDATE DATE: 01/13/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INCORRECT FUSE SIZE FOUND IN COMPONENT COOLING WATER PUMP "32", BACKUP | | SERVICE WATER PUMP & CHARGING PUMP FEED. | | | | FUSES ON THE PRIMARY SIDE OF A CONTROL POWER CIRCUIT FOR THE APPENDIX "R" | | ALTERNATE POWER SOURCE FOR COMPONENT COOLING WATER PUMP (CCW PMP) "32" | | WERE DETERMINED TO BE UNDERSIZED (1 AMP RATHER THAN 3 AMP). THE FUSES | | FAILED REPEATEDLY IN A RECENT TEST ALTHOUGH THEY HAD FUNCTIONED PROPERLY IN | | PAST TESTS. THE CONTROLLERS FOR THE OTHER APPENDIX "R" EQUIPMENT (BACKUP | | SERVICE WATER PUMP, & CHARGING PUMP FEED) WERE OF THE SAME DESIGN AND ALSO | | HAD 1 AMP FUSES. ALTHOUGH THIS EQUIPMENT FUNCTIONED DURING RECENT (AND | | PAST) APPENDIX "R" TESTS, THE FUSES COULD HAVE FAILED (THE CIRCUITS WERE OF | | THE SAME DESIGN) AND PREVENTED THE FULFILLMENT OF SAFETY FUNCTIONS REQUIRED | | TO MITIGATE THE FIRES POSTULATED IN ACCORDANCE WITH APPENDIX "R". THE EVENT | | IS UNLIKELY BECAUSE, IF THERE WAS A FIRE, NO SUPPRESSION AND LOSS OF THE | | INDEPENDENT OFFSITE POWER SOURCES AND FEEDS WOULD HAVE HAD TO OCCUR. THE | | CORRECT SIZE FUSES WERE PLACED IN THE CIRCUIT FOR THE "32" CCW PUMP AND | | TESTED SATISFACTORILY. THE OTHER CIRCUIT FUSES WILL BE REPLACED AND TESTED | | PRIOR TO RETURNING THE SYSTEM TO OPERATION. THE UNDERSIZED CCW FUSES WERE | | PREVIOUSLY THE SUBJECT OF LER 93-037, DATED 10-27-93, BECAUSE THEY WERE | | MISSING. THE LER IDENTIFIED THE EVENT DURATION AS BEING FROM MAY 18, 1983 | | (WHEN THE ACCEPTANCE TESTS WERE PERFORMED). | | | | ENGINEERING DID A FOLLOW-UP INVESTIGATION AS TO WHY THE FUSES FOR CCW PUMP | | "32" KEPT FAILING (FUSES KEPT BLOWING), AND THEY DETERMINED THAT THE FUSES | | WERE UNDERSIZED. THE ORIGINAL MANUFACTURERS' DRAWINGS (KLOCKLER-MOELLER) | | SHOW 3 AMP FUSES FOR THE PRIMARY SIDE OF CONTROL POWER TRANSFORMERS (CPTs). | | THE CONDITION IS UNIQUE TO KLOCKLER-MOELLER MCC312A BECAUSE OTHER MCCs HAVE | | FUSES ON THE 120V SIDE OF THE CPT. THIS CONDITION HAS APPARENTLY EXISTED | | SINCE ORIGINAL INSTALLATION. THE MAY 1994 APPENDIX "R" FUSE WALKDOWN FOUND | | 1 AMP FUSES WHICH ENGINEERING EVALUATED AS ACCEPTABLE BECAUSE THE WALKDOWN | | DID NOT IDENTIFY THAT THE CONTACTOR WAS ON THE PRIMARY (480V) SIDE OF THE | | CPT (THE EVALUATION CONSIDERED THE RATING OF THE CPT WITHOUT THE | | CONTACTOR). | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28240 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/13/95 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 20:39 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/13/95 | +------------------------------------------------+EVENT TIME: 15:15[EST]| |NRC NOTIFIED BY: JOHN JOHNSTONE |LAST UPDATE DATE: 01/13/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVE VERRELLI RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTRACT FURMANITE SUPERVISOR EMPLOYEE TESTED POSITIVE FOR ILLEGAL DRUG. | | | | RANDOM FITNESS FOR DUTY TEST WAS PERFORMED ON 01/10/95. RESULTS WERE | | CONFIRMED POSITIVE FOR A CONTRACT FURMANITE SUPERVISOR. WHEN HE WAS | | CONFIRMED POSITIVE HE WAS NOT ON SITE. HIS ACCESS WAS PULLED. CONTRACT | | EMPLOYEE WAS NOTIFIED THAT HIS ACCESS WAS PULLED BECAUSE HE HAD TESTED | | POSITIVE FOR AN ILLEGAL DRUG. LICENSEE NOTIFIED SURRY NUCLEAR POWER PLANT | | THAT THIS CONTRACT EMPLOYEE HAD TESTED POSITIVE FOR ILLEGAL DRUGS. | | | | RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28241 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 01/14/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 10:08 [ET]| |RX TYPE: [1] CE |EVENT DATE: 01/14/95 | +------------------------------------------------+EVENT TIME: 08:39[EST]| |NRC NOTIFIED BY: EBERT |LAST UPDATE DATE: 01/14/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 99 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP FROM 99% DUE TO INDICATIONS OF GENERATOR PROBLEMS. | | | | AT 0839EST A MANUAL TRIP OF THE PLANT WAS INITIATED FROM 99% POWER DUE TO | | INDICATIONS OF A PROBLEM WITH THE MAIN GENERATOR (HIGH GENERATOR BEARING | | TEMPERATURE, GENERATOR CONDITION CHANGE, GENERATOR GROUND FLAG AND A | | FREQUENCY MONITOR SPIKE). PLANT RESPONSE TO THE TRANSIENT WAS NORMAL, AND | | ALL SYSTEMS FUNCTIONED AS REQUIRED. | | | | ALL RODS FULLY INSERTED ON THE TRIP. THE LICENSEE IS STEAMING TO THE MAIN | | CONDENSER VIA THE BYPASSES, AND FEEDING WITH MAIN FEED. THE UNIT DID NOT | | EXPERIENCE ANY PROBLEMS WITH THE TRANSFER OF ELECTRICAL BUSES. NO PRIMARY | | OR SECONDARY RELIEF VALVES LIFTED IN RESPONSE TO THE TRIP. ALL ECCSs AND | | EDGs ARE OPERABLE, AND THERE WERE NO ABNORMAL LEVEL OR PRESSURE TRANSIENTS. | | | | THE LICENSEE WILL BE INVESTIGATING THE SOURCE OF THE PROBLEMS, BEGINNING | | WITH AN INSPECTION OF THE GENERATOR. THE LICENSEE INFORMED THE RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28242 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/15/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 01:22 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/14/95 | +------------------------------------------------+EVENT TIME: 23:38[EST]| |NRC NOTIFIED BY: PLUMPTON |LAST UPDATE DATE: 01/15/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNPLANNED RX BUILDING VENTILATION ISOLATION DUE TO THE PERFORMANCE OF AN | | INSTRUMENT CALIBRATION DURING A VITAL BUS OUTAGE. | | | | FITZPATRICK EXPERIENCED AN UNPLANNED ESF ACTUATION DURING THE PERFORMANCE | | OF "ISP-201D" (RPS PCIS INSTRUMENT CALIBRATION ON THE "D" TRAIN) THE | | REACTOR BUILDING ISOLATED AND VALVE 20-AOV-83 (A DRYWELL SUMP ISOLATION | | VALVE) CLOSED. RPS TRANSFORMER EPA's WERE DE-ENERGIZED AT THE TIME, DUE TO | | THE 10500 BUS (4160V VITAL BUS) RESTORATION. BOTH LOGIC TRAINS FOR THE | | OUTBOARD PCIS VALVES WERE MADE UP AND THE OUTBOARD VALVES CLOSED. WITH THE | | BUS TRANSFORMERS ALREADY OUT FOR THE BUS RESTORATION, ONE RELAY WAS ALREADY | | MADE UP. WHEN THE INSTRUMENT TECH PERFORMED THE TEST, THAT MADE UP THE | | SECOND RELAY, COMPLETING THE ISOLATION LOGIC FOR THE OUTBOARD VALVES. TO | | AVOID THE ISOLATION, THE TWO EVOLUTIONS SHOULD NOT HAVE BEEN PERFORMED AT | | THE SAME TIME. | | | | FITZPATRICK IS CURRENTLY DEFUELED. OPERATORS RESET THE SIGNAL AND RESTORED | | FROM THE ISOLATIONS. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28243 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/15/95 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 02:23 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/15/95 | +------------------------------------------------+EVENT TIME: 00:55[EST]| |NRC NOTIFIED BY: STAUBER |LAST UPDATE DATE: 01/15/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM EMERGENCY BREATHING AIR SYSTEM ACTUATED DUE TO AN ELECTRICAL | | SPIKE ON A CONTROL ROOM RADIATION MONITOR WHILE RESTORING POWER TO AN | | ADJACENT CONTAINMENT RAD MONITOR. | | | | MAINTENANCE ACTIVITY WAS BEING PERFORMED ON UNIT 1 CONTAINMENT RAD MONITOR | | "219-A" TO RESTORE ELECTRICAL POWER TO THAT RAD MONITOR. AN ELECTRICAL | | SPIKE ON AN IMMEDIATELY ADJACENT CONTROL ROOM RAD MONITOR "218-A" OCCURRED, | | RESULTING IN AN ACTUATION OF THE CONTROL ROOM EMERGENCY BREATHING AIR | | SYSTEM (CREBAS). THE SYSTEM BOTTLES DISCHARGED (PROVIDING AIR TO THE | | CONTROL ROOMS) AND THE DAMPERS FOR UNIT 2 RE-ALIGNED. THE ACTUATION WAS | | VERIFIED TO BE SPURIOUS, WAS RESET, AND THE LINEUP IS BEING RESTORED. | | | | RADIATION MONITOR "218-A" IS A UNIT 1 RAD MONITOR, BUT THE ACTUATION OF THE | | CREBAS AFFECTS BOTH UNITS SINCE THERE IS A COMMON CONTROL ROOM. THE UNIT 1 | | DAMPERS WERE ALREADY DE-ENERGIZED IN THE FAIL POSITION DUE TO THE OUTAGE, | | WHILE THE UNIT 2 DAMPERS FUNCTIONED AS DESIGNED TO COMPLETELY ISOLATE THE | | CONTROL ROOM BOUNDARY. THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28244 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 01/15/95 | |UNIT: [ ] [2] [ ] STATE: MD |NOTIFICATION TIME: 04:18 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 01/15/95 | +------------------------------------------------+EVENT TIME: 02:46[EST]| |NRC NOTIFIED BY: McCAFFERTY |LAST UPDATE DATE: 01/15/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 12 STARTUP | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP DURING STARTUP DUE TO PROBLEMS WITH MAIN FEEDWATER PUMP | | OPERATION. | | | | UNIT 2 WAS STARTING UP AFTER HAVING TRIPPED ON 1/13/95 (SEE EVENT #28237). | | REACTOR POWER WAS APPROXIMATELY 4% WITH Tavg AT 533øF, WHEN DIFFICULTIES | | WITH A LINE-UP SHIFT ON THE MAIN FEED PUMPS CAUSED AN OVER-FEED OF THE | | STEAM GENERATORS, A COOLDOWN AND POWER INCREASE, AND AN AUTOMATIC REACTOR | | TRIP ON "LOSS OF LOAD". A "LOSS OF LOAD" REACTOR TRIP OCCURS WHEN REACTOR | | POWER IS GREATER THAN 12% AND THE TURBINE IS NOT ON-LINE, AND IS NOT PART | | OF THE PRE-PLANNED RPS SYSTEM (CALVERT CLIFFS HAD IT ADDED ON). | | | | OPERATORS WERE SHIFTING MAIN FEEDPUMP STEAM SUPPLY CONTROLS FROM AUX STEAM | | TO MAIN STEAM, BUT THE #22 PUMP DID NOT RESPOND ON MAIN STEAM, SO OPERATORS | | SHIFTED IT BACK TO AUX STEAM. UPON BEING RETURNED TO AUX STEAM, THE PUMP | | SPED UP, BUT OPERATORS WERE NOT ABLE TO DRIVE THE SPEED BACK DOWN WITH THE | | CONTROLLERS. STEAM GENERATOR LEVELS, WHICH HAD GONE LOWER WHEN OPERATORS | | WERE ATTEMPTING TO SHIFT THE CONTROLS TO MAIN STEAM, INCREASED DUE TO THE | | PUMP SPEED-UP WHEN IT WAS SHIFTED BACK TO AUX STEAM. THIS CAUSED AN | | OVER-COOLING EVENT WITH THE REACTOR AT SUCH A LOW POWER, DROPPING THE AVG | | COOLANT TEMPERATURE FROM 533øF TO 515øF, AND CAUSED A RX POWER INCREASE. | | | | THE SHIFT SUPERVISOR ORDERED A MANUAL REACTOR TRIP AT THIS POINT, HOWEVER, | | THE AUTOMATIC "LOSS OF LOAD" REACTOR TRIP OCCURRED FIRST. A SEQUENCE OF | | EVENTS PRINTOUT IS BEING REVIEWED TO CLEARLY ASCERTAIN THE FIRST OUT, | | BECAUSE THE AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR PRESSURES WAS | | ALSO VERY CLOSE TO OCCURRING. SOME PROBLEMS WERE ALSO EXPERIENCED WITH THE | | RESPONSE OF THE #21 MAIN FEED PUMP, BUT THE #22 PUMP WAS THE PRIMARY FEED | | SOURCE AT THE TIME OF THE EVENT. THE LICENSEE WILL BE INVESTIGATING THE | | ROOT CAUSE OF THIS EVENT. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28245 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 01/17/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 01:10 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/16/95 | +------------------------------------------------+EVENT TIME: 23:39[CST]| |NRC NOTIFIED BY: RATZLAFF |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRIMARY CONTAINMENT NITROGEN SUPPLY AND TIP VALVES WILL RE-OPEN UPON | | RESETTING A GROUP TWO ISOLATION SIGNAL IF THEIR RESPECTIVE SWITCHES ARE | | LEFT IN THE "OPEN" POSITION. | | | | USAR (UPDATED SAFETY ANALYSIS REPORT) SAFETY DESIGN BASIS FOR PCIS (PRIMARY | | CONTAINMENT ISOLATION SYSTEM) SPECIFIES THAT PRIMARY CONTAINMENT ISOLATION | | VALVES WILL NOT RESET WHEN THE ISOLATION SIGNAL IS RESET. NUREG-0578 ALSO | | ADDRESSES THIS DESIGN CONDITION, STATING SPECIFICALLY THAT "OPERATOR ACTION | | TO TAKE THE VALVE CONTROL SWITCH TO CLOSE, TO ENSURE THE VALVE WILL NOT | | RE-OPEN ON ISOLATION RESET". THE ENGINEERING EVALUATION HAS DETERMINED | | THIS TO BE "INAPPROPRIATE" FOR PRIMARY CONTAINMENT NITROGEN SUPPLY AND TIP | | VALVES . | | | | THE PRIMARY CONTAINMENT MOV 13-XX SERIES OF VALVES (PRIMARY CONTAINMENT | | NITROGEN SUPPLY) AND THE TRAVERSING IN-CORE PROBE (TIP) VALVES ARE | | AUTOMATICALLY RE-OPENED WHEN THE GROUP TWO ISOLATION SIGNAL IS RESET, IF | | THEIR RESPECTIVE CONTROL SWITCHES ARE IN THE OPEN POSITION. THE SWITCH | | DESIGN IS SUCH THAT THE OPEN POSITION IS A "MAINTAIN POSITION" WHEN | | SELECTED. THIS PROBLEM WAS EVALUATED DUE TO A CONDITION REPORT THAT HAD | | BEEN INITIATED. | | | | THE LICENSEE WILL BE FURTHER EVALUATING THIS CONDITION TO ASSESS THE NEED | | FOR CORRECTIVE ACTION. THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28246 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 01/17/95 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 02:09 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 01/17/95 | +------------------------------------------------+EVENT TIME: 00:39[EST]| |NRC NOTIFIED BY: SANTINI |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 89 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/RX TRIP ON LOW TURBINE CONTROL AUTO-STOP OIL PRESSURE. | | | | UNIT 2 EXPERIENCED A TURBINE TRIP ON TURBINE CONTROL OIL "AUTO-STOP". THE | | COINCIDENCE IS 2 OUT OF 3 AUTO-STOP OIL PRESSURE < 45 psig. THE REACTOR | | TRIPPED ON THE TURBINE TRIP. THE CAUSE OF THE LOW AUTO-STOP OIL PRESSURE | | IS UNDER INVESTIGATION. ALL AUTOMATIC ACTIONS OCCURRED AS REQUIRED FOR | | BOTH TURBINE AND REACTOR TRIPS, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. THE | | UNIT IS STABLE IN HOT STANDBY. | | | | IP-2 WAS OPERATING AT 89% POWER FOR FUEL OPTIMIZATION AND DUE TO A SMALL | | (4-5 gpd) TUBE LEAK ON THE #24 STEAM GENERATOR. THE ATMOSPHERIC STEAM | | DUMPS WERE NOT UTILIZED FOR STEAMING IN RESPONSE TO THE TRIP. CURRENTLY, | | ALL STEAM IS BEING DIRECTED TO SECONDARY LOADS AND THERE IS NO NEED TO | | STEAM TO THE MAIN CONDENSER OR VIA THE ATMOSPHERIC STEAM DUMPS TO REMOVE | | HEAT. ALL RODS FULLY INSERTED ON THE RX TRIP, AND THERE WERE NO PROBLEMS | | WITH THE TRANSFER OF ELECTRICAL BUSES. NO PRIMARY OR SECONDARY RELIEF | | VALVES LIFTED IN RESPONSE TO THE TRIP. ALL ECCS's AND EDG's ARE OPERABLE | | AND IN STANDBY. THE STEAM GENERATORS ARE BEING FED VIA THE AUXILIARY BOILER | | FEED PUMPS. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28247 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 01/17/95 | |UNIT: [1] [2] [3] STATE: CA |NOTIFICATION TIME: 06:00 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 01/17/95 | +------------------------------------------------+EVENT TIME: 02:25[PST]| |NRC NOTIFIED BY: MAHER |LAST UPDATE DATE: 01/17/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA 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 DECOMMISSIONED | 0 DECOMMISSIONED | | 2 | N Y 97 POWER OPERATION | 97 POWER OPERATION | | 3 | N Y 97 POWER OPERATION | 97 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ASSAULT MADE WITHIN THE PROTECTED AREA (TWO INDIVIDUALS HAD A FIGHT). | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. INDIVIDUALS WERE | | NON-SUPERVISORY AND ARE NOT LICENSED OPERATORS. LICENSEE INFORMED THE | | RESIDENT INSPECTOR. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+