U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/12/94 - 08/15/94 ** EVENT NUMBERS ** 27663 27664 27665 27666 27667 27668 27669 27670 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27663 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 08/12/94 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 06:04 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 08/12/94 | +------------------------------------------------+EVENT TIME: 04:47[EDT]| |NRC NOTIFIED BY: STASNY |LAST UPDATE DATE: 08/12/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH BARR RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A/R Y 42 POWER OPERATION | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP FROM 42% POWER DUE TO LOSS OF MFW PUMP "3B". | | | | THIS OCCURRED WHILE THEY WERE INCREASING POWER FROM STARTUP AND THE "3B" | | MAIN FEEDWATER PUMP TRIPPED, CAUSE UNKNOWN AND IS BEING INVESTIGATED(THE | | "3A" MFW PUMP WAS NOT IN SERVICE AT THE TIME). THIS IN TURN RESULTED IN AN | | ANTICIPATORY TRIP OF THE MAIN TURBINE/GENERATOR AND REACTOR. ALL RODS FULLY | | INSERTED, NO SI OCCURRED AND NO PRIMARY SAFETY RELIEF VALVES LIFTED. THEY | | DID HAVE SECONDARY STEAM SAFETY RELIEF VALVES LIFT AND THEY FULLY RESEATED | | AT THE APPROPRIATE PRESSURE. THE HEAT SINK IS BOTH STEAM GENERATORS USING | | THE EMERGENCY FEEDWATER. ALL EMERGENCY EQUIPMENT IS OPERABLE. THE RI WAS | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27664 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 08/12/94 | |UNIT: [2] [3] [ ] STATE: PA |NOTIFICATION TIME: 16:41 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 08/12/94 | +------------------------------------------------+EVENT TIME: 18:00[EDT]| |NRC NOTIFIED BY: MIKE KELLY |LAST UPDATE DATE: 08/14/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 79 POWER OPERATION | 79 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TSC WILL BE TEMPORARILY RELOCATED TO THE ADMIN BUILDING | | | | THE TSC WILL BE TEMPORARILY RELOCATED TO THE 4TH FLOOR OF THE ADMIN | | BUILDING. THE RELOCATION IS NECESSARY BECAUSE POWER WILL BE SECURED TO THE | | NORMAL TSC TO SUPPORT ELECTRICAL WORK RELATED TO THE INSTALLATION OF THE | | STATION BLACKOUT LINE. | | | | SHOULD THE TEMPORARY FACILITY BECOME RADIOLOGICALLY UNINHABITABLE, KEY TSC | | PERSONNEL WILL REPORT TO THE CONTROL ROOM AND THE REMAINING PERSONNEL WILL | | RELOCATE OFFSITE AS APPROPRIATE. | | | | THE LICENSEE IS MAKING THIS REPORT BECAUSE THEY CONSIDER IT A LOSS OF THE | | "NORMAL" ASSESSMENT CAPABILITY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | | | * * * UPDATE AT 1850 ON 8/14/94 BY KELLY TAKEN BY WEAVER * * * | | | | NORMAL POWER HAS BEEN RESTORED TO THE TSC. | | HOO NOTIFIED RDO (KEIMIG) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27665 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 08/13/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 06:41 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/13/94 | +------------------------------------------------+EVENT TIME: 06:35[EDT]| |NRC NOTIFIED BY: C. WOOKEY |LAST UPDATE DATE: 08/13/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN 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 +------------------------------------------------------------------------------+ | LICENSEE HAS BEEN NOTIFIED THAT THE AMES HILL EMERGENCY SIREN IS | | INOPERABLE. THERE WAS A LIGHTNING STORM IN PROGRESS AT THE TIME OF THE | | NOTIFICATION THAT MAY BE THE CAUSE OF THE PROBLEM. REPAIR PERSONNEL ARE | | ENROUTE TO INVESTIGATE AND REPAIR THE SIREN. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR AND IS IN THE PROCESS | | OF NOTIFYING STATE AND LOCAL OFFICIALS. | | | | * * * UPDATE BY MAY AT 1255 EDT ON 8/13/94 TAKEN BY WEAVER * * * | | THE SIREN HAS BEEN RETURNED TO SERVICE. | | HOO NOTIFIED THE RDO (KEIMIG). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27666 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 08/13/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 15:15 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/13/94 | +------------------------------------------------+EVENT TIME: 11:00[CDT]| |NRC NOTIFIED BY: BILLESBACH |LAST UPDATE DATE: 08/13/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 +------------------------------------------------------------------------------+ | THE POTENTIAL FOR DIRECT DISCHARGE TO THE SECONDARY CONTAINMENT EXISTS IN | | THE EVENT OF A HIGH ENERGY LINE BREAK IN THE PRIMARY CONTAINMENT. | | | | THE FOLLOWING IS THE TEXT OF A LICENSEE FAX. | | | | "A RE-ASSESSMENT OF THE CONDITION DESCRIBED IN INFORMATION NOTICE 89-055 | | AND THE ENSUING ENGINEERING EVALUATION PERFORMED IN 1989 HAS RESULTED IN | | THE CONCLUSION THAT THE 8" REACTOR EQUIPMENT COOLING (REC) PIPING IN THE | | DRYWELL ADJACENT TO THE REACTOR RECIRCULATION PUMP DISCHARGE PIPING IS | | SUSCEPTIBLE TO JET IMPINGEMENT FORCES IN THE EVENT OF A HIGH ENERGY LINE | | BREAK (HELB) INSIDE CONTAINMENT. SHOULD THAT SCENARIO OCCUR, THE REC | | PIPING COULD DIRECTLY COMMUNICATE WITH PRIMARY CONTAINMENT ATMOSPHERE AND | | BE SUBJECT TO THE PRIMARY CONTAINMENT PRESSURIZATION TRANSIENT. AS | | DESCRIBED IN INFORMATION NOTICE 89-055, THE WATER IN THE REC RETURN PIPING | | FROM THE DRYWELL WOULD BE DISCHARGED OUT OF THE SURGE TANK WHICH, AT CNS, | | IS LOCATED IN THE REACTOR BUILDING (SECONDARY CONTAINMENT) AT ELEVATION 976 | | FEET, EMPTYING THE PIPING AND SURGE TANK AND ALLOWING PRIMARY CONTAINMENT | | ATMOSPHERE TO BE DISCHARGED DIRECTLY TO SECONDARY CONTAINMENT. ON AUGUST | | 13, AT APPROXIMATELY 11:00 AM, THIS CONDITION WAS DETERMINED TO BE | | REPORTABLE. | | | | THIS BREACH OF PRIMARY CONTAINMENT WOULD OCCUR PRIOR TO CLOSURE OF THE | | SINGLE CONTAINMENT ISOLATION VALVE IN THE REC RETURN PIPING FROM THE | | DRYWELL, REC-MOV-709MV. WHILE A CHECK VALVE IN THE REC INLET PIPING TO THE | | DRYWELL WOULD PREVENT THE INLET PIPING FROM BEING PRESSURIZED, THE PRIMARY | | CONTAINMENT ATMOSPHERE WOULD CONTINUE TO BE DISCHARGED TO SECONDARY | | CONTAINMENT UNTIL REC-MOV-709MV WAS CLOSED USING THE REMOTE MANUAL CONTROL | | SWITCH IN THE CONTROL ROOM. (NO AUTOMATIC CLOSURE FEATURE FOR THIS VALVE | | IS PROVIDED; CLOSURE REQUIRES OPERATOR ACTION). IN THE EVENT OF A LOSS OF | | POWER TO THIS VALVE OR FAILURE OF THE MOTOR OPERATOR, THE BREACH OF PRIMARY | | CONTAINMENT WOULD BE NON-ISOLABLE. WITH RESPECT TO THE REC INLET PIPING TO | | THE DRYWELL, ACTUATION OF THE CONTROL SWITCH FOR REC-MOV-709MV ALSO CAUSES | | CLOSURE OF A MOTOR OPERATED VALVE IN THE INLET PIPING, REC-MOV-702MV, | | PROVIDING A SECOND CONTAINMENT ISOLATION BARRIER IN SERIES WITH THE INLET | | CHECK VALVE. | | | | AT THE PRESENT TIME, THE PLANT IS IN COLD SHUTDOWN WITH THE RHR SYSTEM IN | | SERVICE IN THE SHUTDOWN COOLING MODE OF OPERATION. AN EVALUATION TO | | MITIGATE THE EFFECTS OF THIS SCENARIO IS BEING PERFORMED AND THE CONDITION | | WILL BE RESOLVED PRIOR TO PLANT STARTUP. | | | | END OF FAX | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 27667 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ATEC ASSOCIATES INCORPORATED |NOTIFICATION DATE: 08/13/94 | | CITY: CINCINNATI REGION: 3 |NOTIFICATION TIME: 17:17 [ET]| | COUNTY: STATE: OH |EVENT DATE: 08/13/94 | |LICENSE#: 34-18893-01 AGREEMENT: N |EVENT TIME: 11:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/13/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MARK RING RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: LARRY JEFFERS | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NDAM DAMAGE MEASURE GAUGE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ATEC ASSOCIATES, INCORPORATED REPORTED DAMAGE TO A MOISTURE DENSITY GAUGE. | | | | A DENSITY GAUGE CONTAINING CS-137 AND AM 241 WAS RUN OVER BY AN EARTH | | MOVING MACHINE IN LEBANON, OHIO (WARREN COUNTY). THE SOURCE REMAINED IN | | THE SAFE POSITION. THE GAUGE WAS TAKEN TO THE COMPANY'S STORAGE FACILITY IN | | CINCINNATI, OHIO. NO CONTAMINATION WAS FOUND AT THE CONSTRUCTION SITE WHERE | | THE DAMAGE OCCURRED. | | | | THE NOTIFICATION WAS MADE BY THE RADIATION SAFETY OFFICER. HIS OFFICE | | PHONE NUMBER IS 513-771-2112. | | | | HOO NOTIFIED RDO (RING). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27668 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 08/13/94 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 17:51 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 08/13/94 | +------------------------------------------------+EVENT TIME: 14:27[EDT]| |NRC NOTIFIED BY: GORDON NADER |LAST UPDATE DATE: 08/13/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LPCI LOOP SELECT WAS INADVERTENTLY ACTUATED DURING TROUBLE SHOOTING. | | | | DURING TROUBLE SHOOTING ACTIVITIES IN THE DIVISION II RHR RELAY CABINETS, | | AN INADVERTENT ACTUATION OF LPCI LOOP SELECT OCCURRED, LOOP B WAS SELECTED. | | BECAUSE THE REACTOR IS DEFUELED WITH THE FUEL POOL GATES REMOVED (NO MODE | | PER TECH SPECS) THE RHR SYSTEM IS NOT REQUIRED TO BE OPERABLE AND BOTH | | DIVISIONS OF RHR PUMPS WERE IN OFF/RESET. BASED ON THE INITIAL | | INVESTIGATION THE CORRECT VALVE RE-ALIGNMENT AND INDICATIONS OCCURRED. | | TROUBLE SHOOTING ACTIVITIES WERE STOPPED. THE LOGIC WAS RESET AND THE | | VALVES WERE REPOSITIONED TO THEIR STANDBY LINE UP. INVESTIGATION CONTINUES | | TO DETERMINE THE EXACT CAUSE OF THIS EVENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27669 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/14/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 13:40 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/14/94 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: TED DUBAY |LAST UPDATE DATE: 08/14/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ONE TRAIN OF CONTROL ROOM HABITABILITY SYSTEM INOPERABLE | | | | ONE TRAIN OF THE CONTROL ROOM HABITABILITY SYSTEM WAS DECLARED INOPERABLE | | BECAUSE IT COULD NOT BE PLACED FULLY INTO THE RECIRCULATION MODE. ONE | | DAMPER CANNOT BE FULLY REPOSITIONED TO THE RECIRCULATION MODE, THEREFORE | | SOME OF THE AIR FLOW IS NOT BEING DIRECTED THROUGH THE FILTERING SYSTEM. | | THIS LOWERED THE POTENTIAL EFFECTIVENESS OF THE TRAIN AND IT WAS DECLARED | | INOPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE APPROPRIATE STATE | | AND LOCAL NOTIFICATIONS WERE MADE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27670 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 08/14/94 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 17:03 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/13/94 | +------------------------------------------------+EVENT TIME: 18:14[EDT]| |NRC NOTIFIED BY: ROBERT BRAUN |LAST UPDATE DATE: 08/14/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG RDO | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TRANSMISSION LINE TRANSIENT CAUSES REACTOR POWER INCREASE | | | | ON 8/13/94 AT 1814 EDT WITH UNIT 2 OPERATING AT 100% POWER, ONE OF THE | | THREE HIGH VOLTAGE TRANSMISSION LINES IN THE UNIT 2 SUBSTATION TRIPPED OPEN | | AND IMMEDIATELY RECLOSED DURING A STORM. THE UNIT 2 REACTOR OPERATOR | | OBSERVED THE 2A REACTOR RECIRCULATION PUMP SPEED INCREASE AT THE SAME TIME | | THE ELECTRICAL TRANSIENT OCCURRED. THE SPEED INCREASE CAUSED INDICATED | | REACTOR POWER TO INCREASE. AS A RESULT, THE APPROPRIATE PROCEDURES WERE | | ENTERED AND REACTOR POWER WAS DECREASED TO 97.5%. PRELIMINARY REVIEW OF | | THE REACTOR POWER INDICATIONS REVEALED THAT THE LICENSED POWER LIMITATION | | MAY HAVE BEEN EXCEEDED FOR A FEW SECONDS AS INDICATED ON THE AVERAGE POWER | | RANGE MONITORS. FURTHER INVESTIGATION IS ONGOING TO DETERMINE THE CAUSE OF | | THE 2A REACTOR RECIRCULATION PUMP SPEED INCREASE AND WHETHER THE LICENSED | | POWER LEVEL WAS ACTUALLY EXCEEDED. THIS REPORT IS BEING MADE PURSUANT TO | | LIMERICK GENERATING STATION UNIT 2 LICENSE NPF-85, ITEM 2.E. A WRITTEN | | FOLLOW-UP REPORT WILL BE SUBMITTED WITHIN 30 DAYS PURSUANT TO 10CFR50.73. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+