U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/22/95 - 12/26/95 ** EVENT NUMBERS ** 29761 29762 29763 29764 29765 29766 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29761 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 12/23/95 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 03:38 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 12/22/95 | +------------------------------------------------+EVENT TIME: 23:53[EST]| |NRC NOTIFIED BY: KILBY |LAST UPDATE DATE: 12/23/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THE THE PLANT EXCEEDED THEIR MAXIMUM ALLOWABLE POWER | | LEVEL FOR APPROX 4 MINS. | | | | ON 12/22/95 THE PLANT EXCEEDED THE MAXIMUM LICENSED POWER LEVEL OF 3411 | | MWt. THE CAUSE IS UNKNOWN AND BEING INVESTIGATED. THE 8 HOUR AVERAGE | | REACTOR POWER REACHED 3411.07 MWt FOR 4 MINS(23:53-23:57). THE MAIN PLANT | | COMPUTER CALCULATES A CONTINUOUS ROLLING 8 HR AVERAGE OF REACTOR POWER. THE | | 8 HR AVERAGE INCREASED FROM 3410.91 MWt AT 23:49 TO 3411.07 MWt AT 23:53. | | THE OPERATORS PROMPTLY REDUCED POWER UPON THE RECEIPT OF AN ALARM | | INDICATING THE UNIT WAS AT OR ABOVE THE MAXIMUM ALLOWABLE POWER LEVEL. THE | | COMPUTER NORMALLY PROVIDES AN ANTICIPATORY ALARM WHICH ALLOWS THE OPERATORS | | 40 MINS TO REDUCE POWER TO PREVENT EXCEEDING 3411 MWt. HOWEVER, IN THIS | | SITUATION THE ALARM WAS NOT RECEIVED. THE CAUSE FOR THE ALARM NOT BEING | | RECEIVED IS UNKNOWN AND BEING INVESTIGATED. THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29762 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 12/23/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 09:49 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 12/23/95 | +------------------------------------------------+EVENT TIME: 04:40[EST]| |NRC NOTIFIED BY: SCHIENDELMAN |LAST UPDATE DATE: 12/23/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A MANUAL START OF THE STANDBY GAS TREATMENT SYSTEM(MANUAL ESF | | ACTUATION) TO REESTABLISH SECONDARY CONTAINMENT. | | | | THE SECONDARY CONTAINMENT INTEGRITY WAS LOST WHEN THE REACTOR ENCLOSURE | | HVAC CONTROL SYSTEM DEVELOPED SOME PROBLEMS. THE CAUSE IS UNKNOWN AND BEING | | INVESTIGATED, BUT THEY BELIEVE THE PROBLEM MAY HAVE RESULTED FROM THE FLOW | | INSTRUMENTATION FAILING HIGH ON THE REACTOR ENCLOSURE CIRCULATION FANS. | | THIS TYPE OF FAILURE WOULD HAVE CAUSED THE BLADE PITCH ON THE FANS TO HAVE | | DIALED BACK, RESULTING IN THE FANS BEING UNABLE TO MAINTAIN NEGATIVE DELTA | | P IN THE BUILDING. INSTEAD OF WAITING FOR THE AUTOMATIC INITIATION OF THE | | SBGTS, THE LICENSEE MANUALLY INITIATED IT. SUBSEQUENT TO REPAIRS BEING | | COMPLETED, THE SBGTS WILL BE PLACED BACK INTO ITS NORMAL STANDBY MODE. THE | | RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29763 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 12/25/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 08:33 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/25/95 | +------------------------------------------------+EVENT TIME: 07:13[EST]| |NRC NOTIFIED BY: RUSSELL |LAST UPDATE DATE: 12/25/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT WAS MANUALLY TRIPPED FROM 100% POWER DUE TO LOSS OF CONTROL OF | | THE MAIN TURBINE GENERATOR EXCITATION SYSTEM. | | | | THE PLANT HAD A LOSS OF CONTROL OF THE MAIN TURBINE GENERATOR EXCITATION | | SYSTEM AND THE OPERATORS DECIDED TO INSERT A MANUAL REACTOR TRIP WHEN THIS | | DISCOVERY WAS MADE. THE CAUSE OF THE EXCITATION SYSTEM FAILURE IS UNKNOWN | | AND BEING INVESTIGATED. ALL RODS FULLY INSERTED AND ALL SYSTEMS RESPONDED | | AS EXPECTED. THE PLANT IS STABLE AND THE CONDENSER IS THE HEAT SINK. NO ESF | | ACTUATIONS OCCURRED. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29764 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 12/25/95 | |UNIT: [ ] [3] [ ] STATE: PA |NOTIFICATION TIME: 12:31 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 12/25/95 | +------------------------------------------------+EVENT TIME: 09:00[EST]| |NRC NOTIFIED BY: DAVE LEWIS |LAST UPDATE DATE: 12/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE INJECTION (HPCI) DECLARED INOPERABLE FOR 5 MINUTES. | | | | HPCI WAS DECLARED INOPERABLE AND LICENSEE ENTERED TECHNICAL SPECIFICATION | | 3.5.C (7 DAY LIMITING CONDITION OF OPERATION) WHEN A WATER/STEAM LEAK WAS | | DISCOVERED ON PIPING FOR THE HPCI STEAMLINE DRAIN POT LEVEL | | INSTRUMENTATION. MOSTLY WATER WAS LEAKING FROM A TEST CONNECTION (PIPE | | CAP). WATER LEAKING FROM THE HPCI STEAM LINE INDICATES THAT THE STEAM LINE | | TO THE HPCI TURBINE IS NOT PROPERLY DRAINED. LICENSEE OPENED AN AIR | | OPERATED BYPASS VALVE (AOV-53) TO DRAIN THE STEAM LINE TO THE MAIN | | CONDENSER. WITH AOV-53 OPEN (INSURES THAT HPCI STEAM LINE IS DRAINED) | | LICENSEE EXITED TECHNICAL SPECIFICATION 3.5.C AT 0905 ET. LICENSEE WILL | | REPAIR THE LEAKING TEST CONNECTION. ALL THEIR EMERGENCY CORE COOLING | | SYSTEMS WERE FULLY OPERABLE DURING THE TIME PERIOD HPCI WAS DECLARED | | INOPERABLE. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29765 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 12/25/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 13:53 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 12/25/95 | +------------------------------------------------+EVENT TIME: 13:45[EST]| |NRC NOTIFIED BY: JOHN BROOKS |LAST UPDATE DATE: 12/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 +------------------------------------------------------------------------------+ | NATIONAL OCEANIC AND ATMOSPHERIC ADMINISTRATION (NOAA) LINK BETWEEN THE | | SITE AND "JPS" OFFICE LOCATED IN BURLINGTON, VERMONT LOST FOR APPROXIMATELY | | 9 MINUTES. | | NOAA LINE USED TO NOTIFY THE GENERAL PUBLIC THAT AN ACCIDENT HAS OCCURRED | | AT THE PLANT WAS FOUND TO BE INOPERABLE AT 1345 ET. LICENSEE NOTIFIED "JPS" | | (COMMUNICATION COMPANY FOR LICENSEE) THAT THE NOAA LINK WAS INOPERABLE. | | "JPS" FOUND THAT A SWITCH IN THEIR OFFICE ASSOCIATED WITH THE NOAA LINK WAS | | IN THE "OFF" POSITION INSTEAD OF BEING IN THE "ON" POSITION. NOAA LINK WAS | | RESTORED TO SERVICE WHEN THE SWITCH WAS REPLACED TO ITS "ON" POSITION. | | LICENSEE NOTIFIED THE STATES OF VERMONT, NEW HAMPSHIRE AND MASSACHUSETTS | | THAT THEIR NOAA LINK WAS LOST. | | | | RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29766 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 12/25/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 21:15 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/25/95 | +------------------------------------------------+EVENT TIME: 19:15[EST]| |NRC NOTIFIED BY: JAMES MCGINNIS |LAST UPDATE DATE: 12/25/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC FEEDWATER ISOLATION WHILE RETURNING TRAIN "A" SOLID STATE | | PROTECTION SYSTEM (SSPS) TO SERVICE. | | | | TRAIN "A" OF THE SSPS WAS REMOVED FROM SERVICE TO ALLOW TROUBLESHOOTING OF | | A SLAVE RELAY (K603A, RELAY HAD A STICKY CONTACT). AFTER REPLACING THE | | RELAY, TRAIN "A" SSPS WAS RETURNED TO SERVICE. WHILE RETURNING TRAIN "A" | | SSPS TO SERVICE A FEEDWATER ISOLATION SIGNAL WAS GENERATED. ALL COMPONENTS | | AFFECTED BY THE FEEDWATER ISOLATION SIGNAL FUNCTIONED AS DESIGNED. WHILE | | RETURNING TRAIN "A" SSPS TO SERVICE, THE FEEDWATER HAND SWITCHES SHOULD | | HAVE BEEN HELD IN THE RESET POSITION (REACTOR TRIP BREAKERS WERE OPEN | | COINCIDENT WITH LOW REACTOR COOLANT Tave) TO PREVENT THE FEEDWATER | | ISOLATION SIGNAL. THE WORK PROCEDURE DID NOT HAVE A STEP IN IT TO HOLD THE | | FEEDWATER HAND SWITCHES IN THE RESET POSITION WHEN RETURNING SSPS TRAIN "A" | | TO SERVICE. LICENSEE IS INVESTIGATING THIS EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+