U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/25/95 - 08/28/95 ** EVENT NUMBERS ** 29236 29237 29238 29239 29240 29241 29242 29243 29244 29245 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29236 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 08/25/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 04:05 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/25/95 | +------------------------------------------------+EVENT TIME: 01:41[EDT]| |NRC NOTIFIED BY: DONALD E. ROLAND |LAST UPDATE DATE: 08/25/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF THE INBOARD MAIN STEAM LINE DRAIN VALVE TO CLOSE AND OF THE ZONE | | III WALL AND HIGH EXHAUST RADIATION MONITORS TO TRIP DOWNSCALE AS EXPECTED | | DURING A HALF SCRAM AS PART OF A PRE-PLANNED EVOLUTION. | | | | THE REACTOR PROTECTION SYSTEM (RPS) WAS MOMENTARILY DE-ENERGIZED DURING THE | | PERFORMANCE OF A SWAP OF THE RPS POWER SUPPLIES IN PREPARATION FOR | | MAINTENANCE ON ONE OF THE OFFSITE POWER SUPPLY TRANSFORMERS. THIS WAS DUE | | TO THE DESIGN OF THE RPS POWER SUPPLY SYSTEM. IT UTILIZED A BREAK BEFORE | | MAKE CONFIGURATION. THIS CAUSED A HALF SCRAM SIGNAL AND NUMEROUS | | ISOLATIONS AND WAS PART OF AN EXPECTED EVOLUTION. HOWEVER, FOLLOWING THE | | SWAP, THE INBOARD MAIN STEAM LINE DRAIN VALVE DID NOT GO CLOSED AS | | EXPECTED. (IN THE PAST, THE CAUSE OF THIS HAD BEEN EVALUATED AS A RELAY | | RACE.) IN ADDITION, THE ZONE III WALL (REFUEL FLOOR EXHAUST VENTILATION | | SYSTEM) AND HIGH EXHAUST RADIATION MONITORS DID NOT TRIP DOWNSCALE AS | | EXPECTED. | | | | THE LICENSEE SUSPECTED THAT THESE EMERGENCY SAFEGUARD FEATURE FUNCTIONS DID | | NOT OCCUR DUE TO THE SHORT PERIOD OF TIME THAT THE LOGIC WAS ACTUALLY | | DE-ENERGIZED DURING THE SWAP. THE LICENSEE REPORTED THAT THERE HAVE BEEN | | SIMILAR SITUATIONS IN THE PAST. THE LICENSEE'S INVESTIGATION IS CURRENTLY | | ONGOING. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29237 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 08/25/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 09:23 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 08/25/95 | +------------------------------------------------+EVENT TIME: 05:43[EDT]| |NRC NOTIFIED BY: TERRY WHITE |LAST UPDATE DATE: 08/25/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO A DECREASE IN FEEDWATER PUMP SUCTION PRESSURE | | AND THE LOSS OF A CIRCULATING WATER PUMP. | | | | AT 05:41, THE 'B' CIRCULATING WATER PUMP TRIPPED DUE TO POWER FACTOR | | PROBLEMS. THIS RESULTED IN A HOTWELL IMBALANCE AND THE SUBSEQUENT DECREASE | | IN MAIN FEEDWATER PUMP SUCTION PRESSURE TO APPROXIMATELY 100 PSIG. ALTHOUGH | | THE MAIN FEEDWATER PUMPS DID NOT TRIP, THE LICENSEE WAS UNABLE TO RESTORE | | THE MAIN FEEDWATER PUMP SUCTION PRESSURE AND DIRECTED ACTUATION OF A MANUAL | | REACTOR TRIP AT 05:43 WHEN STEAM GENERATOR WATER LEVELS HAD DECREASED TO | | APPROXIMATELY 20% NARROW RANGE. (THE AUTOMATIC REACTOR TRIP SETPOINT FOR | | LOW STEAM GENERATOR LEVEL WAS 17% NARROW RANGE.) ALL RODS INSERTED ON THE | | MANUAL REACTOR TRIP, AND AUXILIARY FEEDWATER AUTOMATICALLY STARTED. ALL | | SYSTEMS FUNCTIONED AS EXPECTED. THE MINIMUM AND MAXIMUM REACTOR COOLANT | | SYSTEM TEMPERATURES AND PRESSURES WERE 537.8 øF, 574.2 øF, 2,004 PSIG, AND | | 2,254 PSIG, RESPECTIVELY. THE MINIMUM AND MAXIMUM PRESSURIZER LEVELS WERE | | 14.4% AND 52.0%, RESPECTIVELY. | | | | THE PLANT IS CURRENTLY STABLE AT 547 øF AND 2,235 PSIG. THE LICENSEE IS | | USING AUXILIARY FEEDWATER TO SUPPLY WATER TO THE STEAM GENERATORS AND IS | | STEAMING VIA THE STEAM GENERATOR ATMOSPHERIC RELIEF VALVES. STEAM | | GENERATOR INTEGRITY IS GOOD, AND THERE ARE NO KNOWN STEAM GENERATOR TUBE | | LEAKS. ALL EMERGENCY DIESEL GENERATORS ARE CURRENTLY OPERABLE, AND OFFSITE | | POWER IS AVAILABLE. | | | | THE ROOT CAUSE FOR THE LOSS OF THE MAIN FEEDWATER PUMP SUCTION PRESSURE HAS | | NOT YET BEEN VERIFIED. HOWEVER, THE LICENSEE BELIEVES THAT THERE MAY HAVE | | BEEN A LOSS OF LEVEL IN ONE OF THE TWO HOTWELLS ON THE LOW PRESSURE | | TURBINES AND THAT THIS IN TURN MAY HAVE CAUSED THE CONDENSATE PUMPS TO | | CAVITATE AND THE SUBSEQUENT DROP IN MAIN FEEDWATER PUMP SUCTION PRESSURE. | | THE CAUSES FOR THE LOSS OF THE HOTWELL LEVEL AND FOR THE POWER FACTOR TRIP | | OF THE 'B' CIRCULATING WATER PUMP HAVE NOT YET BEEN DETERMINED. THE | | LICENSEE'S INVESTIGATION IS CURRENTLY ONGOING. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29238 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 08/25/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 10:51 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 08/25/95 | +------------------------------------------------+EVENT TIME: 08:48[CDT]| |NRC NOTIFIED BY: ED KLUND |LAST UPDATE DATE: 08/25/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 60 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM ON HIGH FLUX/HIGH POWER DURING THE PERFORMANCE OF A | | PRESSURE REGULATION SYSTEM STARTUP TEST | | | | DURING THE PERFORMANCE OF SURVEILLANCE QCTS360-2, PRESSURE REGULATION | | SYSTEM STARTUP TEST PROCEDURE, AN AUTOMATIC REACTOR SCRAM WAS RECEIVED AT | | THE POINT WHERE THE 'A' PRESSURE REGULATOR WAS BEING TESTED. ALL RODS | | INSERTED. ALL SYSTEMS FUNCTIONED AS REQUIRED. THE FIRST OUT INDICATOR WAS | | HIGH FLUX/HIGH POWER DUE TO HIGH PRESSURE. THE EMERGENCY DIESEL GENERATORS | | WERE OPERABLE, AND OFFSITE POWER WAS AVAILABLE FOLLOWING THE REACTOR SCRAM. | | | | THE CAUSE OF THE SCRAM IS CURRENTLY UNDER INVESTIGATION, AND THE UNIT IS | | PROCEEDING TO COLD SHUTDOWN. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29239 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/25/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 14:03 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/25/95 | +------------------------------------------------+EVENT TIME: 13:03[EDT]| |NRC NOTIFIED BY: FROEBRICH |LAST UPDATE DATE: 08/25/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CONTE RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INOPERABLE CONTAINMENT | | ISOLATION VALVE. | | | | AT 1203, AUTOMATIC CONTAINMENT ISOLATION VALVE (NNE-AOV-863) BECAME | | INOPERABLE AND COULD NOT BE CLOSED. TECHNICAL SPECIFICATION 3.6.A.3 | | REQUIRES THAT CONTAINMENT INTEGRITY BE RESTORED WITHIN 1 HOUR, OR THAT THE | | UNIT BE PLACED IN HOT SHUTDOWN WITHIN 6 HOURS. AT 1303, A UNIT SHUTDOWN | | WAS COMMENCED IN ACCORDANCE WITH THE TECHNICAL SPECIFICATIONS. AT 1319, | | THE VALVE WAS SUCCESSFULLY CLOSED, AND THE UNIT SHUTDOWN WAS EXITED AT | | 1321. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29240 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 08/25/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:14 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 08/25/95 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: CIGANIK |LAST UPDATE DATE: 08/25/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CONTE RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP / REACTOR SCRAM BYPASS SETPOINT ADJUSTED NONCONSERVATIVELY. | | | | WHILE EVALUATING GE SERVICE INFORMATION LETTER (SIL) 423, THE LICENSEE | | DETERMINED THAT THE BYPASS SETPOINT FOR THE ANTICIPATORY REACTOR SCRAM ON | | MAIN TURBINE TRIP WAS ADJUSTED IN A NONCONSERVATIVE DIRECTION. THE | | TECHNICAL SPECIFICATION SETPOINT LIMIT IS ó40% OF RATED STEAM FLOW (BASED | | UPON THE CAPACITY OF THE TURBINE BYPASS VALVES). THE LICENSEE STATED THAT | | THE ACTUAL SET POINT WAS ADJUSTED TO A HIGHER VALUE. THE LICENSEE ALSO | | STATED THAT THE PLANT HAD BEEN OPERATED FOR SOME TIME WITH THE SETPOINT | | ADJUSTED OUTSIDE OF THE TECHNICAL SPECIFICATION LIMIT. | | | | THE NRC RESIDENT WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29241 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/25/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/25/95 | +------------------------------------------------+EVENT TIME: 14:30[EDT]| |NRC NOTIFIED BY: PTACEK |LAST UPDATE DATE: 08/25/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORGENSEN 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EXCESSIVE CONTAINMENT ISOLATION VALVE LEAKAGE DURING TYPE C TESTING. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "DURING AS-FOUND 1 CFR APP. J TYPE C CONTAINMENT LEAK TESTING, THE | | FOLLOWING VALVES WHEN TOTALED VIA MAXIMUM PATHWAY WITH ALL OTHER VALVES | | TESTED TO DATE HAVE EXCEEDED TS 3.6.1.2.b ALLOWABLE OF 0.60 La. | | | | 1) 1-NS-357 - 41,500 SCCM | | 2) 1-R-157 - 45,600 SCCM | | | | COMBINED WITH ALL VALVES TOTAL LEAKAGE = 92,925 SCCM. THIS IS CALCULATED | | TO BE 0.843 La." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29242 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/26/95 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 03:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/26/95 | +------------------------------------------------+EVENT TIME: 01:49[EDT]| |NRC NOTIFIED BY: ROGER WEST |LAST UPDATE DATE: 08/26/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -TURBINE TRIP/REACTOR TRIP DURING TURBINE VALVE TESTING- | | | | A TURBINE TRIP AND REACTOR TRIP OCCURRED DURING TURBINE VALVE TESTING. THE | | PLANT RESPONDED NORMALLY. ALL RODS FULLY INSERTED. THE TURBINE DRIVEN AND | | BOTH MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS (AFW) STARTED AS EXPECTED. NO | | PRIMARY OR SECONDARY RELIEFS OR SAFETIES LIFTED. DECAY HEAT IS BEING | | REMOVED VIA THE MAIN CONDENSER. NORMAL OFFSITE POWER IS AVAILABLE. THE | | ONLY SAFETY EQUIPMENT INOPERABLE AT THE TIME OF THE TRIP WAS THE APPENDIX R | | CVCS CROSS-TIE TO UNIT 1. | | | | THE CAUSE OF THE TURBINE TRIP IS BELIEVED TO BE A SPURIOUS HIGH-HIGH | | MOISTURE SEPARATOR LEVEL. IN ADDITION, SOURCE RANGE MONITOR (SRM) N-31 | | READ ABNORMALLY LOW AFTER THE TRIP AND IS CONSIDERED INOPERABLE. THESE | | EQUIPMENT MALFUNCTIONS ARE UNDER INVESTIGATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29243 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 08/26/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 22:00 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 08/26/95 | +------------------------------------------------+EVENT TIME: 17:16[CDT]| |NRC NOTIFIED BY: DALY |LAST UPDATE DATE: 08/26/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORGENSEN 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 +------------------------------------------------------------------------------+ | PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP II ISOLATION AND AUTOMATIC START | | OF STANDBY GAS TREATMENT SYSTEM. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AT 1716 HOURS, UNIT 2 WAS IN THE REFUEL MODE WITH ALL FUEL REMOVED FROM | | THE VESSEL AND A FULL SCRAM ALREADY IN WHEN AN INVALID GROUP II ACTUATION | | OCCURRED RESULTING IN THE REPOSITIONING OF DRYWELL VENT VALVE 2-1601-23. | | | | A HALF GROUP II ISOLATION SIGNAL ("A" CHANNEL) WAS ALREADY IN DUE TO THE | | "A" REACTOR PROTECTION SYSTEM (RPS) BUS BEING DEENERGIZED FOR MAINTENANCE. | | THE "A" RPS BUS FEEDS THE "A" CHANNEL FOR GROUP II ISOLATION RELAYS. WHILE | | THE ELECTRICAL MAINTENANCE DEPARTMENT WAS REPLACING SCRAM RELAY 2-590-108F | | ON THE "B" RPS CHANNEL, WIRES WERE LIFTED THAT APPEAR TO HAVE CAUSED A | | BREAK IN A NEUTRAL CIRCUIT WHICH RESULTED IN THE REACTOR LOW WATER LEVEL | | RELAY (2-590-105D) AND THE DRYWELL PRESSURE HI-HI RELAY (2-590-103D) | | DROPPING OUT, CAUSING A FULL GROUP II ISOLATION. AN INVESTIGATION | | CONTINUES." | | | | THE LICENSEE STATED THAT THE STANDBY GAS TREATMENT SYSTEM AUTOMATICALLY | | STARTED AND THE REACTOR BUILDING VENTILATION SYSTEM ISOLATED AS EXPECTED | | DUE TO THE PRIMARY CONTAINMENT ISOLATION SIGNAL. THE NRC RESIDENT HAS BEEN | | INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29244 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 08/27/95 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 11:30 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/27/95 | +------------------------------------------------+EVENT TIME: 10:30[CDT]| |NRC NOTIFIED BY: CHARLES HUTCHESON |LAST UPDATE DATE: 08/27/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE 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 90 POWER OPERATION | 90 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNACCOUNTED FOR SECURITY WEAPON - | | | | IMMEDIATE COMPENSATORY ACTION TAKEN UPON DISCOVERY. THE FULL DETAILS OF | | THIS EVENT ARE CONTAINED IN THE HOO LOG. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29245 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 08/28/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 01:48 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/27/95 | +------------------------------------------------+EVENT TIME: 23:00[EDT]| |NRC NOTIFIED BY: ED MCAVOY |LAST UPDATE DATE: 08/28/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 1 STARTUP | 1 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -RCIC ISOLATION DURING WARM UP- | | | | WHILE PERFORMING S49.1.B (WARM UP, PRESSURIZE & UNISOLATE RCIC), RCIC | | ISOLATED ON A LOW STEAMLINE PRESSURE SIGNAL (64.5 PSIG). REACTOR PRESSURE | | WAS 100 PSIG AT THE TIME OF THE ISOLATION. WITH THE INBOARD ISOLATION | | VALVE OPEN, RCIC ISOLATED WHEN THE WARM UP BYPASS VALVE WAS THROTTLED OPEN. | | BOTH THE INBOARD ISOLATION VALVE AND THE WARM UP BYPASS VALVE ISOLATED ON | | THE LOW PRESSURE SIGNAL AS DESIGNED. | | | | THE LICENSEE BELIEVES THE LOW PRESSURE SIGNAL WAS CAUSED BY WATER DRAINING | | FROM THE SYSTEM WHEN THE WARM UP BYPASS VALVE WAS OPENED. THE ISOLATION | | HAD NO DISCERNIBLE AFFECT ON THE PLANT. THE ISOLATION WAS RESET AT 2305 | | AND PROCEDURE S49.1.B WAS COMPLETED WITHOUT FURTHER INCIDENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+