U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/07/96 - 06/10/96 ** EVENT NUMBERS ** 30326 30587 30593 30594 30595 30596 30597 30598 30599 30600 30601 30602 30603 30604 30605 30606 30607 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30326 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 04/19/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 15:43 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/19/96 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: HATHAWAY |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |DTHR 73.71(c) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFEGUARDS INFORMATION WAS FOUND TO BE NOT PROPERLY CONTROLLED AND STAMPED | | SAFEGUARDS INFORMATION. THE SAFEGUARDS INFORMATION HAS BEEN RETRIEVED, AND | | CORRECTIVE ACTIONS ARE BEING TAKEN TO PREVENT THIS FROM HAPPENING AGAIN. | | (REFER TO THE HOO LOG FOR ADDITIONAL INFORMATION.) | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | | | | * * * UPDATE AT 1358 ON 06/07/96 BY PETE EBERT ENTERED BY JOLLIFFE * * * | | | | THE LICENSEE DETERMINED THAT THE SUBJECT DOCUMENT, THE SECURITY TRAINING | | AND QUALIFICATION PLAN, CONTAINS NO SAFEGUARDS INFORMATION. THEREFORE, | | THE LICENSEE DESIRES TO RETRACT THIS EVENT. THE LICENSEE WILL INFORM THE | | NRC RESIDENT INSPECTOR. THE HOO NOTIFIED R1DO JENNY JOHANSEN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30587 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 06/06/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 13:44 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/06/96 | +------------------------------------------------+EVENT TIME: 11:26[CDT]| |NRC NOTIFIED BY: CLARK STAFFORD |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -20 OF 20 SRVs LIFTED FOR UNKNOWN REASONS; MANUAL Rx SCRAM FROM 100% POWER- | | | | WITH THE PLANT AT 100% POWER AND REACTOR COOLANT SYSTEM PRESSURE STABLE | | AT 1025 PSIG (NORMAL PRESSURE) AND NO TESTING OR MAINTENANCE ACTIVITIES | | ONGOING, 20 OF 20 SAFETY/RELIEF VALVES (SRVs) LIFTED FOR UNKNOWN REASONS | | AND DUMPED TO THE SUPPRESSION POOL. | | | | AT 1126 (CDT), CONTROL ROOM OPERATORS MANUALLY SCRAMMED THE PLANT FROM | | 100% POWER. ALL CONTROL RODS INSERTED COMPLETELY. STEAM IS BEING DUMPED | | TO THE MAIN CONDENSER. | | | | WITHIN 1 SECOND OF OPENING, 14 OF 20 SRVs CLOSED AND WITHIN 2.5 MINUTES OF | | OPENING, THE REMAINING 6 SRVs CLOSED. SRV OPENING PRESSURE SETPOINTS ARE | | 1103, 1113, & 1123 PSIG. | | | | SUPPRESSION POOL TEMPERATURE INCREASED FROM A NORMAL TEMPERATURE OF 80øF TO | | 108øF. AT 90øF, A HIGH SUPPRESSION POOL TEMPERATURE ALARM WAS RECEIVED IN | | THE CONTROL ROOM. | | | | TECH SPEC LCO A/S 3.6.2.1 REQUIRES THE LICENSEE TO INITIATE THE SUPPRESSION | | POOL COOLING SYSTEM WHEN THE POOL TEMPERATURE INCREASES TO 95øF. AT | | 1130 (CDT), CONTROL ROOM OPERATORS MANUALLY INITIATED THE SUPPRESSION POOL | | COOLING SYSTEM (2 TRAINS OF RHR SYSTEM). AT 1244 (CDT), SUPPRESSION POOL | | TEMPERATURE WAS AT 86øF AND DECREASING. | | | | THE LICENSEE DISCOVERED A BLOWN FUSE TO A POWER SUPPLY TO THE TRIP UNITS | | OF THE SRV LOGIC. IT IS UNCLEAR AT THE PRESENT TIME WHETHER THIS BLOWN | | FUSE CONTRIBUTED TO THE CAUSE OR THE EFFECT OF THIS EVENT. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THIS EVENT. | | | | THE PLANT IS STABLE IN OPERATING CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE @ 1107 EDT 06/07/96 BY MCDONALD TAKEN BY MACKINNON*** | | | | AFTER FURTHER REVIEW IT HAS BEEN DETERMINED THAT 6 SRVs OPENED INSTEAD OF | | 20 SRVs OPENING. | | DUE TO A SHORT IN A CAPACITOR IN A DIVISION 2 INSTRUMENT PANEL FOR THE SRV | | TRIP UNITS, POWER SUPPLY VOLTAGE WAS DEGRADED TO THE POINT THAT THE SUPPLY | | FUSE TO THE CAPACITOR CIRCUIT BLEW. THIS CAUSED THE POWER SUPPLY TO SURGE | | AND SPIKE THE VOLTAGE IN THE SRV PANEL. ALL 20 SRVs RECEIVED AN OPEN SIGNAL | | FOR APPROXIMATELY 200 MILLISECONDS (ENERGIZE TO OPEN) AND THEN RESET. THIS | | WAS NOT ENOUGH TIME FOR THE SRVs TO ACTUATE AND OPEN. WHEN THE POWER SUPPLY | | RETURNED TO NORMAL AFTER 200 MILLISECONDS THE OPEN SIGNAL WAS RESET. | | HOWEVER, THE LOW LOW SETPOINT FUNCTION OF 6 OF THE SRVs HAS A SEAL IN | | FEATURE WHICH DID SEAL IN AND ACTUATE, CAUSING THE 6 LOW LOW SET VALVES TO | | OPEN. 4 OF THE 6 SRVs RAPIDLY CLOSED AND THE OTHER TWO RESET AND CLOSED | | APPROXIMATELY 2.5 MINUTES AFTER THE INITIATION. R4DO (DALE POWERS) & ERB | | (BARRETT) WERE NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS UPDATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30593 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 06/07/96 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 03:25 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/06/96 | +------------------------------------------------+EVENT TIME: 23:44[EDT]| |NRC NOTIFIED BY: GOODHOPE |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 16 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP FROM 16% POWER DUE TO A TURBINE TRIP. | | | | THE TURBINE TRIP WAS DUE TO A HI-HI STEAM GENERATOR (S/G) WATER LEVEL(>75%) | | IN THE "B" S/G WHICH WAS CAUSED BY LEVEL SWELL WHILE THEY WERE MANUALLY | | FEEDING THE S/G. THE HI-HI LEVEL ALSO CAUSED THE MAIN FEED WATER PUMP TO | | TRIP AND THE AUX FEEDWATER INITIATED AS EXPECTED. THE REACTOR COOLANT | | SYSTEM TEMPERATURE DECREASED TO APPROXIMATELY 540 DEGREES F. ALL RODS FULLY | | INSERTED INTO THE CORE AND NO PRIMARY OR SECONDARY SYSTEM SAFETY VALVES OR | | PORV'S LIFTED. NO ECCS OR INJECTION OCCURRED. OFFSITE POWER IS AVAILABLE | | AND ALL EMERGENCY D/G'S ARE OPERABLE. DECAY HEAT REMOVAL IS THROUGH THE | | CONDENSER VIA THE STEAM DUMP VALVES. THE RI WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30594 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 06/07/96 | |UNIT: [ ] [2] [ ] STATE: TN |NOTIFICATION TIME: 04:04 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/07/96 | +------------------------------------------------+EVENT TIME: 02:43[EDT]| |NRC NOTIFIED BY: MARSHALL |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R N 0 STARTUP | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE REACTOR WAS MANUALLY TRIPPED FOLLOWING A DROPPED ROD DURING TESTING. | | | | THIS OCCURRED WHILE THEY WERE WITHDRAWING CONTROL BANK "D" RODS IN | | ACCORDANCE WITH LOW POWER PHYSICS TESTING. ROD "H-14" IN CONTROL BANK "C" | | DROPPED INTO THE CORE AT 02:40. THE UNIT WAS TRIPPED AT 02:43 AS PREVIOUSLY | | DISCUSSED WITH THE SHIFT MANAGER AND THE REACTOR ENGINEER AT THE PRE-TEST | | BRIEFING. ALL RODS FULLY INSERTED INTO THE CORE AND NO SAFETY VALVES | | LIFTED. AUX FEEDWATER INITIATED. THE CAUSE OF THE "H-14" ROD DROP IS BEING | | INVESTIGATED. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30595 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 06/07/96 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 05:25 [ET]| |RX TYPE: [3] CE |EVENT DATE: 06/06/96 | +------------------------------------------------+EVENT TIME: 22:55[CDT]| |NRC NOTIFIED BY: CROWLEY |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THEY COULD HAVE A CONDITION THAT COULD PREVENT THE | | CVC SYSTEM FROM FULFILLING ITS SAFETY FUNCTION. | | | | AT 22:55 ON 6/6/96 A SECOND CHEMICAL VOLUME & CONTROL (CVC) PUMP, THE "B" | | PUMP, WAS STARTED TO PERFORM A SURVEILLANCE TEST. AT THAT INSTANT, CVC FLOW | | INDICATION WAS LOST. THE "B" PUMP WAS IMMEDIATELY SECURED, HOWEVER, CVC | | FLOW INDICATION REMAINED AT ZERO FLOW. THE NUCLEAR AUXILIARY OPERATOR AT | | THE CVC PUMPS REPORTED THAT THE OTHER CVC PUMP, THE "AB" PUMP, WAS LIFTING | | ITS DISCHARGE RELIEF VALVE. AT 22:58 THE "B" CVC PUMP WAS RESTARTED AND THE | | "AB" PUMP WAS SECURED, AT WHICH TIME CVC SYSTEM FLOW INDICATION WAS | | RESTORED. THE "AB" CVC PUMP WAS ISOLATED AND TAGGED OUT. THEY ARE | | TROUBLESHOOTING THE CAUSE OF THE RELIEF VALVE STAYING OPEN. AFTER A 03:20 | | REVIEW IT WAS DECIDED THAT THIS FAILURE COULD PREVENT THAT CVC SYSTEM FROM | | FULFILLING ITS SAFETY FUNCTION, THEREBY MAKING IT REPORTABLE. THE RI WAS | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30596 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 06/07/96 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 07:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/07/96 | +------------------------------------------------+EVENT TIME: 03:34[CDT]| |NRC NOTIFIED BY: CLOUSER |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 76 POWER OPERATION | 76 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THEY HAD A SAFEGUARDS SYSTEM DEGRADATION RELATED | | TO PARAMETER ALARMS. IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON | | DISCOVERY. SEE HOO LOG FOR DETAILS. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30597 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 06/07/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 10:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/07/96 | +------------------------------------------------+EVENT TIME: 09:30[EDT]| |NRC NOTIFIED BY: POLONCZYK |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |DENNIG EO | |ACHE 50.72(b)(1)(vi) CHEM HAZ(TOX GAS REL) |BELCHER FEMA | | |BARRETT ERB | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A TOXIC GAS RELEASE THAT THREATENS PLANT PERSONNEL. | | | | WHILE PERFORMING A PLANNED EVOLUTION TO ADD CHEMICALS TO THE SECONDARY SIDE | | OF THE STEAM GENERATORS, A LIQUID AMMONIA LEAK WAS OBSERVED FROM A PIPING | | CONNECTION. ALL PERSONNEL IN THE TURBINE BUILDING WERE EVACUATED FROM THE | | AREA AS A PRECAUTIONARY MEASURE. THE LEAK HAS BEEN ISOLATED AND THE AMMONIA | | HAS DISPERSED. SAMPLES TAKEN IN THE AREA WERE <50PPM AT ALL LOCATIONS. THE | | HIGHEST CONCENTRATION AT THE SUMP WAS 25PPM. WIND SPEED AT THE 33FT LEVEL | | IS 7MPH WITH THE DIRECTION FROM 160 DEGREES AND NO RAD RELEASES ARE IN | | PROGRESS. NORMAL ACCESS TO ALL AREAS IS PLANNED AS SOON AS THE FURTHER | | INVESTIGATION HAS BEEN COMPLETED. THERE WERE NO INJURIES AND ALL ACTIONS | | WERE PRECAUTIONARY. THE RI WILL BE NOTIFIED. THEY HAVE NOTIFIED THE STATES | | OF NEW JERSEY AND DELAWARE ALONG WITH LOWER ALLOWAYS CREEK TOWNSHIP. | | | | ***UPDATE AT 11:13 ON 6/7/96 BY POLONCZYK TO GOULD*** THE NOUE WAS | | TERMINATED AT 11:02 BECAUSE THE LEAK HAS BEEN SECURED AND THE AMMONIA HAS | | DISPERSED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30598 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 06/07/96 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 13:06 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 06/07/96 | +------------------------------------------------+EVENT TIME: 10:00[CDT]| |NRC NOTIFIED BY: CHRIS KELLEY |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A LICENSEE JANITORIAL SUPERVISOR RANDOMLY TESTED POSITIVE FOR MARIJUANA. | | THE LICENSEE WITHDREW HIS SITE ACCESS AUTHORIZATION FOR 14 DAYS AND | | REFERRED HIM TO THE EMPLOYEE ASSISTANCE PROGRAM. THE LICENSEE IS | | INVESTIGATING THIS SITUATION. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30599 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNITED STATES AIR FORCE |NOTIFICATION DATE: 06/07/96 | | CITY: SAN ANTONIO REGION: 0 |NOTIFICATION TIME: 14:15 [ET]| | COUNTY: STATE: |EVENT DATE: 06/07/96 | |LICENSE#: 42-23539-01 AGREEMENT: |EVENT TIME: 12:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/07/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DALE POWERS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: Mayor PAUL FEESER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBAD 30.50(b)(1)(ii) MATL >5X LOWEST LIMIT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EXIT SIGN CONTAINING 9.5 CURIES OF TRITIUM FELL TO THE GROUND. THE EXIT | | SIGN OUTER COVER IS CRACKED. | | | | A MAJOR AT BROOKS AIR FORCE BASE SAID THAT AN "EXIT" SIGN AT OTIS AIR FORCE | | BASE LOCATED IN MASSACHUSETTS FELL TO THE GROUND AND THE SIGNS OUTER | | COVERING AT THE LETTER "T" IS CRACKED. THE EXIT SIGN CONTAINS 9.5 CURIES OF | | TRITIUM. THE INNER COVER OF THE "EXIT" SIGN APPEARS TO BE INTACT AND NOT | | DAMAGED. SWIPES ARE BEING TAKEN ON AND AROUND THE EXIT SIGN TO SEE IF ANY | | EXTERNAL RADIOACTIVE CONTAMINATION HAS OCCURRED DUE TO TRITIUM ESCAPING | | FROM THE EXIT SIGN. NRC REGION 4 LINDA MCLEAN WAS NOTIFIED OF THIS EVENT BY | | THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30600 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 06/07/96 | |UNIT: [1] [2] [3] STATE: CA |NOTIFICATION TIME: 17:15 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 06/07/96 | +------------------------------------------------+EVENT TIME: 12:00[PDT]| |NRC NOTIFIED BY: CLAY WILLIAMS |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PHYSICAL SECURITY EVENT - | | | | THE LICENSEE DETERMINED THAT PAST RESPONSES TO FALSE INTRUSION SECURITY | | BARRIER ALARMS MAY NOT HAVE ALWAYS SATISFIED THE REQUIREMENTS OF THE PLANT | | PHYSICAL SECURITY PLAN. THE LICENSEE HAS TAKEN APPROPRIATE CORRECTIVE | | ACTIONS TO ENSURE COMPLIANCE WITH THE PLANT PHYSICAL SECURITY PLAN. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | SEE HOO LOG FOR ADDITIONAL DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30601 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 06/07/96 | |UNIT: [ ] [2] [ ] STATE: CA |NOTIFICATION TIME: 20:19 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/19/96 | +------------------------------------------------+EVENT TIME: 10:46[PDT]| |NRC NOTIFIED BY: BOB MAGRUDER |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 | M N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - THE LICENSEE DETERMINED THAT AN EVENT THAT OCCURRED ON 05/19/96 WHEREBY | | THE REACTOR TRIP BREAKERS WERE OPENED AFTER CONTROL RODS HAD BEEN DRIVEN | | COMPLETELY INTO THE CORE DURING A STARTUP TEST WAS REPORTABLE TO THE NRC | | AS A MANUAL REACTOR TRIP EVENT - | | | | ON 05/19/96, WITH UNIT 2 IN OPERATIONAL MODE 3 (HOT STANDBY) AT THE END OF | | A REFUELING OUTAGE, THE LICENSEE WAS PERFORMING THE DIGITAL ROD POSITION | | INDICATION (DRPI) SYSTEM OPERABILITY TEST IN ACCORDANCE WITH SPECIAL TEST | | EXCEPTION 3/4.10.4, "POSITION INDICATION SYSTEM - SHUTDOWN" AND APPROVED | | PLANT PROCEDURES. | | | | DURING THE TEST, CONTROL ROOM OPERATORS WITHDREW SHUTDOWN ROD BANK 'A' AND | | OBSERVED THAT THE DRPI SYSTEM WAS NOT INDICATING THE POSITION OF THE RODS. | | CONTROL ROOM OPERATORS DECLARED THE DRPI SYSTEM INOPERABLE AND DROVE | | SHUTDOWN ROD BANK 'A' BACK INTO THE CORE. AFTER ALL CONTROL RODS WERE | | COMPLETELY INSERTED INTO THE CORE, CONTROL ROOM OPERATORS OPENED THE | | REACTOR TRIP BREAKERS IN COMPLIANCE WITH THE ACTION STATEMENT REQUIREMENTS | | OF TECH SPEC 3.10.4. | | | | ON 05/19/96, CONTROL ROOM OPERATORS DETERMINED THAT THIS CONDITION WAS NOT | | REPORTABLE TO THE NRC BASED ON THE GUIDANCE OF THE PLANT REPORTABILITY | | PROCEDURE, SINCE ALL CONTROL RODS WERE ALREADY FULLY INSERTED INTO THE CORE | | PRIOR TO OPENING THE REACTOR TRIP BREAKERS. | | | | ON 06/07/96, A TECHNICAL REVIEW GROUP (TRG) WAS CONVENED TO INVESTIGATE THE | | CAUSE OF THE EVENT, REVIEW REPORTABILITY, AND DETERMINE APPLICABLE | | CORRECTIVE ACTIONS. THE TRG REVIEWED THE REPORTING GUIDANCE OF NUREG-1022 | | AND CONDUCTED A COMPUTER SEARCH OF SIMILAR EVENTS REPORTED TO THE NRC. | | | | AT 1600 (PDT) ON 06/07/96, THE TRG DETERMINED THAT THIS EVENT WAS | | REPORTABLE TO THE NRC AS A MANUAL REACTOR TRIP EVENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30602 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 06/07/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 20:52 [ET]| |RX TYPE: [1] CE |EVENT DATE: 06/07/96 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: PETE EBERT |LAST UPDATE DATE: 06/07/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LOW BEARING COOLING WATER FLOW COULD DAMAGE SERVICE WATER PUMPS - | | | | MAINE YANKEE HAS FOUR SERVICE WATER PUMPS (#P-29A, B, C, & D). | | | | THE LOWER BEARINGS OF THE 'B' & 'C' PUMPS ARE NORMALLY COOLED WITH FRESH | | WATER AND HAVE A BACKUP SALT WATER SUPPLY. THE BEARING COOLING WATER | | SYSTEM IS DESIGNED SUCH THAT IF THE FRESH WATER SUPPLY PRESSURE DROPS | | FROM A NORMAL PRESSURE OF 25 PSIG TO 2 PSIG, THE BACKUP SALT COOLING WATER | | SUPPLY IS AUTOMATICALLY INITIATED. | | | | ENGINEERING DEPARTMENT PERSONNEL CALCULATED THAT IF THE FRESH WATER SUPPLY | | PRESSURE DROPPED BELOW 6.4 PSIG, THE FRESH WATER SUPPLY FLOW WOULD DROP | | BELOW THE 3 GPM MINIMUM COOLING FLOW SPECIFIED BY THE PUMP VENDOR. | | | | THE 'A' & 'D' SERVICE WATER PUMPS ARE NOT SUBJECT TO THIS CONDITION | | BECAUSE THEY ONLY HAVE THE SALT COOLING WATER SUPPLY. THERE ARE NO | | RESTRICTIONS ON REMOVING THE 'A' & 'D' PUMPS FROM SERVICE. THUS, WHEN | | THE 'A' & 'D' PUMPS ARE OUT OF SERVICE, THE 'B' & 'C' PUMPS ARE THE ONLY | | SERVICE WATER PUMPS AVAILABLE TO SATISFY THE DESIGN BASIS REQUIREMENTS. | | | | THE LICENSEE MANUALLY PLACED THE SALT COOLING WATER SUPPLY TO THE | | 'B' & 'C' SERVICE WATER PUMPS IN SERVICE. | | | | THERE IS NO EVIDENCE THAT THE POTENTIAL LOW FRESH COOLING WATER PRESSURE | | CONDITION EVER ACTUALLY OCCURRED NOR HAS THERE BEEN ANY BEARING DAMAGE | | WHICH HAS BEEN ATTRIBUTED TO A LOW FRESH COOLING WATER FLOW CONDITION. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30603 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/08/96 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 01:06 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 06/07/96 | +------------------------------------------------+EVENT TIME: 23:23[EDT]| |NRC NOTIFIED BY: MERRILL |LAST UPDATE DATE: 06/08/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON 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 +------------------------------------------------------------------------------+ | THE PLANT HAD AN INADVERTENT START OF THE "1B" EMERGENCY DIESEL GENERATOR. | | | | THIS OCCURRED WHILE THEY WERE PERFORMING A SURVEILLANCE ON THE "B" CHANNEL | | OF THE CONTAINMENT ISOLATION SYSTEM. THE CAUSE OF THIS AUTO START IS UNDER | | INVESTIGATION. THE EDG WAS SECURED WITHIN 20 MINUTES. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30604 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/08/96 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 16:00 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 06/08/96 | +------------------------------------------------+EVENT TIME: 13:55[EDT]| |NRC NOTIFIED BY: JACK BREEN |LAST UPDATE DATE: 06/08/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON 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 +------------------------------------------------------------------------------+ | -ESF ACTUATIONS CAUSED BY A BLOWN FUSE DURING PLANT MAINTENANCE ACTIVITIES- | | | | WHILE IN OPERATIONAL MODE 6 IN A REFUELING OUTAGE WITH THE PLANT ELECTRICAL | | 'B' TRAIN OUT OF SERVICE, I & C TECHNICIANS WERE REPLACING A COMPUTER | | CIRCUIT CARD IN 1 OF 2 ESF SYSTEM AUCTIONEERED POWER SUPPLIES IN THE 'SB' | | ACTUATION CABINET WHEN UNIT 1 RECEIVED A CHANNEL 'B' SAFETY INJECTION | | ACTUATION SIGNAL AND A CHANNEL 'B' CONTAINMENT ISOLATION ACTUATION SIGNAL. | | | | THIS ACTION CAUSED THE #1B3 4.16 KV ELECTRICAL BUS CIRCUIT BREAKER TO | | OPEN TO DEENERGIZE THE #1B3 4.16 KV ELECTRICAL BUS. THE #1B EDG DID NOT | | START BECAUSE IT WAS OUT OF SERVICE. ALL 'B' TRAIN COMPONENTS ACTUATED, | | AS EXPECTED. | | | | THE INITIATING CAUSE APPEARS TO BE A BLOWN REGULATING POWER SUPPLY FUSE IN | | THE 'SB' ACTUATION CABINET. | | | | THE LICENSEE IS INVESTIGATING THE ROOT CAUSE OF THIS EVENT AND WILL SUBMIT | | AN LER TO THE NRC WITHIN 30 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30605 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 06/09/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 10:00 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 06/09/96 | +------------------------------------------------+EVENT TIME: 09:35[EDT]| |NRC NOTIFIED BY: VITO MESSINA |LAST UPDATE DATE: 06/09/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BILL BATEMAN EO | | |DAN RISHE FEMA | | |FRANK CONGEL (IRD) AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | HYDROGEN DRYER #32 CONTROL PANEL DOOR BLEW OFF DUE TO HYDROGEN EXPLOSION. | | UNUSUAL EVENT DECLARED DUE TO REPORT OF EXPLOSION IN THE PROTECTED AREA. | | | | ONE OF TWO HYDROGEN DRYER CONTROL PANEL DOORS ASSOCIATED WITH THE MAIN | | TURBINE GENERATOR BLEW OFF. LICENSEE BELIEVES THAT HYDROGEN LEAKED THROUGH | | THE ELECTRICAL CONDUIT INTO THE HYDROGEN DRYER ELECTRICAL CONTROL PANEL. | | LICENSEE BELIEVES THAT THE HYDROGEN IGNITED INSIDE THE HYDROGEN DRYER | | ELECTRICAL CONTROL PANEL CAUSING THE PANEL DOOR TO BLOW OFF. THE CONTROL | | PANEL WAS ISOLATED ELECTRICALLY AND MECHANICALLY AND THEN IT WAS | | DEPRESSURIZED. LICENSEE PLANS TO PURGE THE CONTROL PANEL WITH NITROGEN AND | | THEN REPAIR THE PANEL. THE DOOR IS APPROXIMATELY 2' BY 2' IN SIZE AND IT | | LANDED ON THE TURBINE BUILDING DECK. THEIR WAS NO DAMAGE TO OTHER EQUIPMENT | | DUE TO THE EXPLOSION, NO FIRE, AND NOBODY WAS INJURED BY THE EXPLOSION. | | LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | | | | ****UPDATE @ 1118EDT 06/09/96 BY DeCLEMENTE TAKEN BY MACKINNON*** | | | | UNUSUAL EVENT TERMINATED AT 1110 EDT. OPERABILITY OF THE PLANT WAS NOT | | AFFECTED BY THE EXPLOSION. LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS THAT | | THE UNUSUAL EVENT WAS TERMINATED AND ISSUED A PRESS RELEASE. R1DO (JENNY | | JOHANSEN), NRR EO (BILL BATEMAN), AND FEMA (CARR) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED THAT THE UNUSUAL EVENT WAS | | TERMINATED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30606 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 06/09/96 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 21:53 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 06/09/96 | +------------------------------------------------+EVENT TIME: 20:13[CDT]| |NRC NOTIFIED BY: DUANE BISTODEAU |LAST UPDATE DATE: 06/10/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 | A/R Y 54 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MAIN TURBINE TRIP/Rx SCRAM DUE TO LOSS OF MAIN GEN STATOR WATER COOLING - | | | | THE PLANT WAS OPERATING AT 100% POWER WITH 1 OF 2 MAIN GENERATOR STATOR | | WATER COOLING PUMPS INOPERABLE. | | | | AT 2010 (CDT), THE SECOND MAIN GENERATOR STATOR WATER COOLING PUMP SEIZED | | FOR UNKNOWN REASONS. THIS CAUSED THE MAIN TURBINE TO RUN BACK. CONTROL | | ROOM OPERATORS REDUCED REACTOR POWER IN ACCORDANCE WITH PLANT PROCEDURES. | | | | AT 2013 (CDT), THE MAIN TURBINE TRIPPED DUE TO THE LOSS OF THE MAIN | | GENERATOR STATOR WATER COOLING SYSTEM. THIS CAUSED THE REACTOR TO | | AUTOMATICALLY SCRAM FROM 54% POWER. ALL CONTROL RODS INSERTED COMPLETELY. | | STEAM IS BEING DUMPED TO THE MAIN CONDENSER. | | | | THE PLANT IS STABLE IN OPERATIONAL CONDITION 3 (HOT SHUTDOWN). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE PUMP SEIZURE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE 0042 EDT ON 06/10/96 BY DUANE BISTODEAU BY MACKINNON*** | | | | A DECREASE IN REACTOR VESSEL WATER LEVEL IN RESPONSE TO THE REACTOR SCRAM | | CAUSED PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 (DRYWELL PURGE AND | | SAMPLE ISOLATION) AND GROUP 3 (REACTOR WATER CLEANUP) ISOLATIONS. THESE ARE | | THE NORMAL ISOLATIONS THEY RECEIVE ON A REACTOR SCRAM . ALL ISOLATIONS | | HAVE BEEN RESET AND THE SYSTEMS HAVE BEEN RETURNED TO THEIR NORMAL LINEUP. | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THE ESF ACTUATIONS BY THE | | LICENSEE. R3DO ( ) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30607 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 06/10/96 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 04:50 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/10/96 | +------------------------------------------------+EVENT TIME: 01:06[PDT]| |NRC NOTIFIED BY: GLENN GOELZER |LAST UPDATE DATE: 06/10/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 60 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR MANUALLY TRIPPED WHEN SECOND MAIN FEEDWATER PUMP TRIPPED. | | | | REACTOR POWER WAS MANUALLY REDUCED RAPIDLY FROM 100% TO 60% AFTER IT WAS | | NOTICED THAT MAIN FEEDWATER PUMP 1-1 SUCTION PRESSURE WAS DECREASING. | | REACTOR POWER WAS BEING STABILIZED AT 60% WHEN MAIN FEEDWATER PUMP 1-1 | | TURBINE TRIPPED FOR AN UNKNOWN REASON. APPROXIMATELY ONE MINUTE LATER MAIN | | FEEDWATER PUMP 1-2 TURBINE TRIPPED. THE REACTOR WAS MANUALLY TRIPPED AFTER | | THE LOSS OF THE SECOND OPERATING MAIN FEEDWATER PUMP. ALL RODS FULLY | | INSERTED INTO THE CORE. THE TURBINE DRIVEN AND BOTH MOTOR DRIVEN AUXILIARY | | FEEDWATER PUMPS AUTOMATICALLY STARTED ON THE LOSS OF BOTH MAIN FEEDWATER | | PUMPS. LOWEST STEAM GENERATOR WATER LEVEL ON NARROW RANGE INDICATION WAS | | 15%. CURRENT REACTOR COOLANT TEMPERATURE IS 544.4øF DUE TO FILLING THE | | STEAM GENERATORS FROM 15% BACK TO THEIR NORMAL OPERATING WATER LEVEL RANGE. | | REACTOR COOLANT SYSTEM TEMPERATURE IS SLOWLY INCREASING BACK TO ITS Tave NO | | LOAD TEMPERATURE OF 547øF. THE STEAM DUMP BYPASS CONTROL SYSTEM AND MAIN | | CONDENSER ARE FULLY OPERABLE. LICENSEE IS INVESTIGATING WHY BOTH MAIN | | FEEDWATER PUMPS TRIPPED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+