U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/28/95 - 07/31/95 ** EVENT NUMBERS ** 29125 29126 29127 29128 29129 29130 29131 29132 29133 29134 29135 29136 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29125 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 07/28/95 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 00:06 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 07/27/95 | +------------------------------------------------+EVENT TIME: 21:32[CDT]| |NRC NOTIFIED BY: JIM KURAS |LAST UPDATE DATE: 07/28/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |PHILLIP MCKEE EO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |STINEDURF FEMA | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DECLARED AN UNUSUAL EVENT AT 2211 CDT DUE TO THE LOSS OF BOTH | | EMERGENCY DIESEL GENERATORS (EDGs). | | | | THE LICENSEE DECLARED BOTH EDGs INOPERABLE AND ENTERED TECH SPEC 3.8.1.1 | | ACTION F. THE LCO REQUIRES RESTORATION OF ONE EDG WITHIN 2 HOURS OR BE IN | | HOT STANDBY IN THE NEXT SIX HOURS. THE "KEEP WARM" SYSTEM FOR THE "A" EDG | | HAS FAILED. THE LICENSEE WILL RUN THE "A" EDG TO BRING IT UP TO OPERATING | | TEMPERATURE AND RUN IT PERIODICALLY TO MAINTAIN IT AT OPERATING | | TEMPERATURE. WHEN IT REACHES OPERATING TEMPERATURE THEY WILL DECLARE IT | | OPERABLE. THE FAILURE OF THE "B" EDG IS DUE TO A BROKEN MECHANICAL | | OVER-SPEED TRIP. THE TRIP MECHANISM BROKE WHILE THE LICENSEE WAS SECURING | | THE "B" EDG FOLLOWING A VERIFICATION OF OPERABILITY REQUIRED BY THE | | UNAVAILABILITY OF THE "A" EDG. | | | | WEATHER AT THE SITE IS CLEAR. THREE SOURCES OF OFFSITE POWER ARE AVAILABLE | | TO FEED STATION BUSES, AND THE GRID IS STABLE. THE LICENSEE NOTIFIED THE | | KANSAS DIVISION OF EMERGENCY MANAGEMENT, THE COFFEY COUNTY SHERIFF AND THE | | NRC RESIDENT INSPECTOR. A PRESS RELEASE WILL BE ISSUED BY THE LICENSEE. | | | | * * * UPDATE AT 0333 EDT FROM KURAS TAKEN BY KARSCH * * * | | | | THE LICENSEE TERMINATED THEIR UNUSUAL EVENT AT 0230 CDT BY RESTORING THE | | "A" EDG TO OPERABLE STATUS. THEY RAN THE ENGINE TO BRING IT UP ABOVE THE | | MINIMUM "KEEP WARM" TEMPERATURE. THEY THEN CONFIRMED THAT IT DID NOT | | EXHIBIT THE SAME FAILURE AS EDG "B". EDG "A" WILL BE RUN EVERY TWO HOURS | | TO MAINTAIN TEMPERATURE. THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. R4DO (HOWELL), NRR EO (MCKEE), AND FEMA (STINEDURF) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29126 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 07/28/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 00:16 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/28/95 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: MIKE EMPEY |LAST UPDATE DATE: 07/28/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL CABLES FOR THE SRVs ARE LOCATED IN THE SAME FIRE ZONE, WHICH MAY | | VIOLATE REQUIREMENTS OF APPENDIX R. | | | | THE FOLLOWING IS EXCERPTED FROM A FAX SUBMITTED BY THE LICENSEE: | | "IT HAS BEEN DETERMINED THAT THE CABLES AND PRIMARY CONTAINMENT ELECTRICAL | | PENETRATIONS FOR ALL 4 SRV SOLENOIDS ARE LOCATED IN CLOSE PROXIMITY IN ZONE | | RB-3, AND A SUITABLE FIRE BARRIER TO PROTECT THE REQUIRED SAFE SHUTDOWN | | EQUIPMENT DOES NOT EXIST AND THAT THE REPAIR ACTIVITY AS DESCRIBED IN THE | | SAFE SHUTDOWN CAPABILITY ANALYSIS AND CORRESPONDING PROCEDURE IS NOT | | REALISTIC TO CONSIDER. A FIRE IN THE AREA COULD DAMAGE THE PENETRATION | | CONDUCTORS TO AN EXTENT THAT THE PREPLANNED REPAIR COULD NOT BE PERFORMED. | | OPERATION OF THE SRV IS REQUIRED TO ACHIEVE COLD SHUTDOWN WITHIN 72 HOURS | | AS REQUIRED BY APPENDIX R". | | | | THE LICENSEE WILL STATION A CONTINUOUS FIRE WATCH IN FIRE ZONE RB-3. | | FURTHER CORRECTIVE ACTION IS UNDER EVALUATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | SEE ALSO EVENT #29106. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29127 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 07/28/95 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 13:19 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/28/95 | +------------------------------------------------+EVENT TIME: 12:40[CDT]| |NRC NOTIFIED BY: BEINKE |LAST UPDATE DATE: 07/28/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAS LOST BOTH ENS PHONE LINES AND COMMERCIAL PHONE LINES. | | | | THE LOSS OF BOTH PHONE LINES WAS DUE TO A FIBER OPTIC CABLE CUT BETWEEN | | HATCH AND BAXLEY GA. THEY HAVE NO ESTIMATE ON WHEN IT WILL BE REPAIRED. | | | | THE RI WILL BE INFORMED. | | | | ***UPDATE AT 16:36 @ 7/28/95 BY BEINKE TO GOULD*** | | | | BOTH ENS AND COMMERCIAL TELEPHONE LINES WERE RESTORED AT 16:15. | | | | THE RI HAS NOT BEEN INFORMED. | | | | HOO NOTIFIED R2DO CRLENJAK. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29128 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 07/28/95 | |UNIT: [1] [2] [ ] STATE: AR |NOTIFICATION TIME: 16:40 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 07/26/95 | +------------------------------------------------+EVENT TIME: 01:08[CDT]| |NRC NOTIFIED BY: SCHEIDE |LAST UPDATE DATE: 07/28/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT AN ANO-2 MAINTENANCE DEPARTMENT EMPLOYEE WAS | | ARRESTED OFFSITE FOR PUBLIC INTOXICATION. | | | | AT APPROXIMATELY 0800 CST ON 7/26/95, ANO ACCESS AUTHORIZATION PERSONNEL | | IDENTIFIED THAT AN ANO-2 MAINTENANCE DEPARTMENT EMPLOYEE HAD BEEN ARRESTED | | OFFSITE FOR PUBLIC INTOXICATION DURING THE EARLY MORNING HOURS ON 7/26/95. | | THE INDIVIDUAL'S PLANT ACCESS WAS TEMPORARILY SUSPENDED AT APPROXIMATELY | | 0830 CST ON 7/26/95 PENDING FURTHER INVESTIGATION. | | | | ASSOCIATED DOCUMENTATION WAS COLLECTED AND AN INTERVIEW OF THE INDIVIDUAL | | WAS COMPLETED AT APPROXIMATELY 1200 CST ON 7/27/95. THE INDIVIDUAL, | | WHO WAS NOT CURRENTLY WORKING IN A SUPERVISORY POSITION, BUT OCCASIONALLY | | SERVES IN THE CAPACITY OF "TEMPORARY FOREMAN" HAD BEEN ARRESTED AT | | 0108 CST ON 7/26/95. HE WAS RELEASED FROM JAIL AT APPROXIMATELY 1000 CST | | ON 7/26/95 AND SUBSEQUENTLY NOTIFIED HIS SUPERVISOR OF THE ARREST AT | | 1130 CST ON 7/26/95. | | | | EVALUATION OF THE INFORMATION AND ANO MANAGEMENT REVIEW OF THE EVENT AND | | ASSOCIATED REPORTING REGULATIONS AND GUIDANCE WERE COMPLETED AT 1130 CST | | ON 7/28/95. IT WAS DETERMINED AT THAT TIME THAT THIS EVENT SHOULD BE | | CONSERVATIVELY CONSIDERED REPORTABLE UNDER 10CFR26.73(a)(2)(iv). | | | | THE LACK OF CLARITY OF THE REGULATIONS AND GUIDANCE REGARDING DEFINITIONS | | OF TERMS SUCH AS SUPERVISORY PERSONNEL, ASSIGNED DUTIES, AND UNFITNESS DUE | | TO CONSUMPTION OF ALCOHOL, WHICH COULD LEAD TO DIFFERING INTERPRETATIONS, | | COMPLICATED THIS REVIEW. | | | | THE RI WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29129 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 07/28/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 18:13 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/28/95 | +------------------------------------------------+EVENT TIME: 15:17[EDT]| |NRC NOTIFIED BY: MCAVOY |LAST UPDATE DATE: 07/28/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED AN ESF ACTUATION DUE TO PERSONNEL ERROR DURING A | | SURVEILLANCE TEST. | | | | DURING THE PERFORMANCE OF A SURVEILLANCE TEST, AN I&C TECHNICIAN GROUNDED | | THE LEAD WHICH CAUSED A LOGIC FUSE TO BLOW WHICH RESULTED IN VARIOUS | | PRIMARY CONTAINMENT ISOLATIONS SUCH AS RWCU, REACTOR ENCLOSURE, HVAC, | | PRIMARY CONTAINMENT INSTRUMENT GAS, REACTOR ENCLOSURE COOLING WATER, AND | | MISCELLANEOUS SAMPLE SYSTEMS. THE BLOWN FUSE WAS REPLACED AND ALL SYSTEMS, | | WITH THE EXCEPTION OF THE RWCU, WERE RESTORED TO OPERABLE STATUS WITHIN | | 1 HOUR, 43 MINUTES. | | | | THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29130 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 07/28/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 19:07 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 07/28/95 | +------------------------------------------------+EVENT TIME: 18:32[EDT]| |NRC NOTIFIED BY: DUBAY |LAST UPDATE DATE: 07/28/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A CONDITION WHERE THE COOLING WATER FLOW TO THE | | VENTILATION SYSTEM IN THE EMERGENCY SAFEGUARDS ROOMS WAS NOT ADEQUATE | | DURING AN ACCIDENT. | | | | A CONDITION EXIST DURING AN ACCIDENT WHERE THE PLANT GOES TO SUMP RECIRC, | | AND AN ADDITIONAL HEAT EXCHANGER IS ADDED TO THE COOLING WATER SYSTEM. AN | | ENGINEERING ANALYSIS HAS POSTULATED THAT WHEN THIS SPECIAL HEAT EXCHANGER | | IS ADDED TO THE SYSTEM, THE COOLING WATER FLOW WOULD DECREASE FROM 60 GPM | | TO 48 GPM. THEY NEED 60 GPM IN ORDER TO MAINTAIN THE CORRECT TEMPERATURE | | IN THE EMERGENCY SAFEGUARDS ROOMS. CORRECTIVE MEASURES TO BE TAKEN ARE TO | | CHANGE THE PROCEDURES TO INCREASE THE FLOW TO THE ROOMS AND ALSO TO PERFORM | | ANOTHER ENGINEERING ANALYSIS TO DETERMINE HOW HIGH THE TEMPERATURE WILL | | RISE IN THE ROOMS AND WHETHER OR NOT THE PUMP MOTORS WILL BE ADVERSELY | | AFFECTED. | | | | THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29131 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 07/29/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 02:48 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/29/95 | +------------------------------------------------+EVENT TIME: 02:27[EDT]| |NRC NOTIFIED BY: MIKE EMPEY |LAST UPDATE DATE: 07/29/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - AMES HILL NOAA TRANSMITTER IS INOPERABLE AND BEING REPAIRED - | | | | JBS COMMUNICATIONS, INC NOTIFIED LICENSEE THAT THE AMES HILL NOAA | | TRANSMITTER WHICH BROADCASTS THE PUBLIC EMERGENCY RADIO NOTIFICATION SIGNAL | | TO THE LOCAL AREA IS INOPERABLE. | | | | JBS COMMUNICATIONS IS REPAIRING THE TRANSMITTER. | | | | LICENSEE WILL NOTIFY STATE OFFICIALS AND DID NOT NOTIFY THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE AT 0541 BY MIKE EMPEY TAKEN BY HOO JOLLIFFE * * * | | | | AT 0530, AMES HILL NOAA TRANSMITTER WAS RESTORED TO OPERABLE STATUS. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R1DO RICK KEIMIG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29132 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 07/29/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 02:53 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/28/95 | +------------------------------------------------+EVENT TIME: 23:15[EDT]| |NRC NOTIFIED BY: MIKE KANE |LAST UPDATE DATE: 07/29/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTAINMENT HIGH PRESSURE REACTOR TRIP SIGNAL INOPERABLE SINCE 02/92 - | | | | DURING THE PERFORMANCE OF A TEST OF A PLANT MODIFICATION THAT WAS INSTALLED | | DURING THE CURRENT REFUELING OUTAGE, LICENSEE DISCOVERED A PLANT CONDITION | | THAT HAS RENDERED THE CONTAINMENT HIGH PRESSURE REACTOR TRIP SIGNAL | | INOPERABLE. | | | | THE REACTOR PROTECTION SYSTEM (RPS) VENDOR (ABB BROWN BOVERI; FORMALLY | | COMBUSTION ENGINEERING) THAT DESIGNED AND INSTALLED THE RPS UPGRADED | | SYSTEM DURING THE 1992 REFUELING OUTAGE (2 OPERATING CYCLES AGO) | | APPARENTLY INCLUDED AN ELECTRICAL JUMPER THAT PREVENTED ALL FOUR CHANNELS | | OF THE CONTAINMENT HIGH PRESSURE REACTOR TRIP SIGNAL FROM FULFILLING THEIR | | FUNCTION. | | | | POST PLANT MODIFICATION TESTING AT THE TIME OF THE FEBRUARY 1992 PLANT | | MODIFICATION APPARENTLY WAS INADEQUATE TO IDENTIFY THIS CONDITION AS WAS | | ON-LINE TESTING DURING THE LAST 2 OPERATING CYCLES. | | | | LICENSEE HAS SATISFACTORILY TESTED ALL 10 OTHER REACTOR TRIP PARAMETERS | | AND EACH FUNCTIONS PROPERLY. | | | | LICENSEE PLANS TO REMOVE THE JUMPER AND TEST / RETEST THE SYSTEM, | | AS NECESSARY, PRIOR TO PLANT RESTART PRESENTLY SCHEDULED FOR 08/21/95. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29133 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR INTERNATIONAL CORP |NOTIFICATION DATE: 07/29/95 | | CITY: DUNCANVILLE REGION: 1 |NOTIFICATION TIME: 17:37 [ET]| | COUNTY: STATE: PA |EVENT DATE: 07/28/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 18:00[EDT]| | DOCKET: |LAST UPDATE DATE: 07/29/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RICHARD KEIMIG RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: TORCHIA | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THE FUME HOOD FAILED DUE TO A POWER LOSS. | | | | THE LOSS OF POWER FOR 15-30 MINUTES RESULTED IN THE FAILURE OF THE FUME | | HOOD. THE FUME HOOD CONTAINED SOLUTIONS OF I-131 & XE IN CLOSED | | CONTAINERS. WHEN POWER WAS RESTORED THEY TOOK SURVEYS AND EVERYTHING WAS | | WITHIN LIMITS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29134 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 07/30/95 | |UNIT: [ ] [3] [ ] STATE: PA |NOTIFICATION TIME: 07:46 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 07/30/95 | +------------------------------------------------+EVENT TIME: 06:40[EDT]| |NRC NOTIFIED BY: RICH TRUAX |LAST UPDATE DATE: 07/30/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | A/R Y 67 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -UNIT 3 SCRAM FROM 67% DUE TO Rx FEED PUMP TURBINE CONTROL SIGNAL FAILURE- | | | | UNIT 3 REACTOR AUTO SCRAMMED FROM 67% POWER DUE TO THE MAIN TURBINE TRIP | | DUE TO HIGH REACTOR VESSEL WATER LEVEL (45 INCHES) DUE TO THE #3A REACTOR | | FEEDWATER PUMP TURBINE CONTROL SIGNAL FAILING HIGH FOR UNKNOWN REASONS. THE | | HIGHEST REACTOR VESSEL WATER LEVEL REACHED WAS 45 INCHES (NORMAL LEVEL IS | | 23 INCHES). | | | | ALL CONTROL RODS INSERTED COMPLETELY. | | | | PCIS GROUP 2 (RWCU SYSTEM) AND GROUP 3 (CONTAINMENT VENTILATION SYSTEM) | | ISOLATED WHEN REACTOR VESSEL WATER LEVEL DROPPED TO 0 INCHES, AS DESIGNED | | (LOWEST REACTOR VESSEL WATER LEVEL REACHED WAS -15 INCHES). | | | | REACTOR VESSEL WATER LEVEL HAS BEEN RESTORED TO NORMAL AND STEAM IS BEING | | DUMPED TO THE MAIN CONDENSER. | | | | UNIT 3 IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | LICENSEE IS DETERMINING CAUSE AND CORRECTIVE ACTIONS. | | | | LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29135 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 2 |NOTIFICATION DATE: 07/30/95 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 13:43 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 07/30/95 | +------------------------------------------------+EVENT TIME: 11:48[CDT]| |NRC NOTIFIED BY: CADE |LAST UPDATE DATE: 07/30/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK 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 SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM FROM 100% POWER DUE TO A MAIN TURBINE/GENERATOR TRIP. | | | | THE PLANT HAD A REACTOR SCRAM FROM 100% POWER DUE TO A MAIN TURBINE TRIP | | WHICH WAS DUE TO A MAIN GENERATOR TRIP ON THE "A" PHASE CURRENT | | DIFFERENTIAL SIGNAL FOR UNKNOWN REASONS. ALL RODS FULLY INSERTED AND | | NO SAFETY RELIEF VALVES LIFTED. THE BYPASS VALVE IS BEING USED TO CONTROL | | PRESSURE AND THE HEAT SINK IS THE MAIN CONDENSER. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29136 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 07/30/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 14:48 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 07/30/95 | +------------------------------------------------+EVENT TIME: 14:33[EDT]| |NRC NOTIFIED BY: JONES |LAST UPDATE DATE: 07/30/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE CALLED TO SAY THEY ARE REDUCING POWER FROM 100% TO 88% DUE TO | | LOSS OF COOLING TO THE PHASE STEP-UP TRANSFORMER. | | | | THIS POWER REDUCTION IS DUE TO A PARTIAL LOSS OF SOME OF THEIR FANS AND OIL | | PUMPS TO THEIR STEP-UP TRANSFORMERS. THEY HAVE AN "A" PHASE TRANSFORMER | | THAT LOST 40% OF ITS FORCED COOLING WHEN A BREAKER TRIPPED AND COULD NOT BE | | RESET. CAUSE OF THE BREAKER TRIPPING IS UNKNOWN AND BEING INVESTIGATED. | | TO PREVENT FROM OVERHEATING THE TRANSFORMER THEY DECIDED TO REDUCE POWER. | | AFTER POWER REDUCTION THEY WILL FURTHER EVALUATE THE TRANSFORMER. THE RI | | WAS NOTIFIED. | +------------------------------------------------------------------------------+