U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/22/95 - 06/23/95 ** EVENT NUMBERS ** 28868 28875 28977 28978 28979 28980 28981 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28868 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 05/30/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:12 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 05/30/95 | +------------------------------------------------+EVENT TIME: 13:35[EDT]| |NRC NOTIFIED BY: MIKE BOURASSA |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |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 Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 125-VOLT DC STATION BATTERY SYSTEM VOLTAGE DEGRADED FOR 20 MINUTES - | | | | WHILE TESTING AN EMERGENCY LIGHTING TRANSFORMER CIRCUIT BREAKER, LICENSEE | | TECHNICIANS RACKED OUT THE BREAKER. THIS UNEXPECTEDLY CAUSED THE 125-VOLT | | DC STATION BATTERY SYSTEM VOLTAGE TO DEGRADE TO 122 VOLTS DC. TECH SPEC | | REQUIRED MINIMUM SYSTEM VOLTAGE IS 125 VOLTS DC. | | | | AT 1335, THE CONTROL ROOM RECEIVED A 125-VOLT DC SYSTEM TROUBLE ALARM. | | | | AT 1355, THE TECHNICIANS RACKED THE BREAKER BACK IN, AND THE SYSTEM TROUBLE | | ALARM CLEARED WITH THE SYSTEM VOLTAGE INDICATED AT 126 VOLTS DC. | | | | THE SYSTEM IS PRESENTLY OPERATING AT AN INDICATED VOLTAGE OF 132 VOLTS DC. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THE SYSTEM VOLTAGE DROP WHEN THE | | BREAKER IS RACKED OUT. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 06/22/95 1515EDT FROM:BOURASSA BY:TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT ON THE BASIS THAT THE LICENSEE DID | | NOT ENTER ANY LIMITING CONDITION FOR OPERATION, AND THE CONDITION ABOVE | | COULD NOT HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF | | STRUCTURES OR SYSTEMS NEEDED TO SHUTDOWN THE PLANT OR MITIGATE THE | | CONSEQUENCES OF AN ACCIDENT. THE COMPONENTS AFFECTED BY THE LOSS OF | | STATION BATTERIES INCLUDE MOTOR-OPERATED VALVES IN THE CORE SPRAY SYSTEM. | | THESE VALVES ARE DESIGNED TO OPERATE WITH DC VOLTAGES AS LOW AS 105 VDC. | | THEREFORE, THE CORE SPRAY SAFETY FUNCTION WOULD HAVE BEEN COMPLETED. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R3DO (JACOBSON) NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28875 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 06/01/95 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 15:47 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 06/01/95 | +------------------------------------------------+EVENT TIME: 14:00[EDT]| |NRC NOTIFIED BY: GORDON FIDLER |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 +------------------------------------------------------------------------------+ | GROUP III ISOLATION OCCURRED DURING REFERENCE LEG BACKFILL. | | | | DURING PERFORMANCE OF PROCEDURE 3M2-12.4 (REFERENCE LEG BACKFILL) THE | | LICENSEE RECEIVED A GROUP III ISOLATION ON REACTOR PRESSURE GREATER THAN 70 | | PSIG. THE CAUSE OF THE PROBLEM WAS TOO HIGH OF A PRESSURE ON THE WATER | | SOURCE FOR THE REFERENCE LEG BACKFILL. THE RHR SYSTEM WAS SECURED AT THE | | TIME, HOWEVER, THE SHUTDOWN COOLING VALVES IN THE SYSTEM WERE IN THE OPEN | | POSITION. UPON RECEIPT OF THE GROUP III ISOLATION SIGNAL THESE VALVES | | CLOSED (MO1001-47, MO1001-50, AND MO1001-29B). THE ISOLATION SIGNAL HAS | | BEEN RESET AND THESE VALVES HAVE BEEN REOPENED. | | | | THE PRESSURE TRANSMITTER THAT CAUSED THE ISOLATION IS IN THE SAME LINE AS | | THE REFERENCE LEG THAT WAS BEING BACKFILLED AT THE TIME. PRIOR TO THE | | EVOLUTION THERE HAD BEEN SOME DISCUSSION ABOUT A POSSIBLE SPIKE IN PRESSURE | | AND THE LICENSEE HAD CLOSED THE MSIVS, AND THE MAIN STEAM DRAIN LINE VALVES | | TO PREVENT THEM FROM REPOSITIONING IN CASE THERE WAS A PRESSURE SPIKE. THE | | SHUTDOWN COOLING VALVES, HOWEVER, WERE NOT REPOSITIONED PRIOR TO THE | | EVOLUTION. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | | | | *** JUNE 22, 1995, RETRACTION RECEIVED FROM DICROCE AT 12:36 BY TROCINE *** | | | | THE LICENSEE DETERMINED THAT THIS EVENT WAS NOT REQUIRED TO BE REPORTED AND | | RETRACTED THE EVENT. THE LICENSEE WILL NOTIFY THE RESIDENT INSPECTOR. THE | | R1DO (DOERFLEIN) WAS NOTIFIED BY THE OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28977 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 06/22/95 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 14:33 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 06/22/95 | +------------------------------------------------+EVENT TIME: 10:30[MST]| |NRC NOTIFIED BY: BRAD EKLUND |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IF A SAFE SHUTDOWN EARTHQUAKE HAD OCCURRED BETWEEN JULY 17, 1992, AND APRIL | | 28, 1994, A FAILURE OF NON-SEISMIC RADIATION MONITORS COULD HAVE PREVENTED | | THE FULFILLMENT OF THE SAFETY FUNCTION OF ESSENTIAL COOLING WATER. | | | | THE LICENSEE DISCOVERED THAT IF A SAFE SHUTDOWN EARTHQUAKE HAD OCCURRED | | BETWEEN JULY 17, 1992, AND APRIL 28, 1994, A FAILURE OF NON-SEISMIC | | RADIATION MONITORS COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY | | FUNCTION OF THE ESSENTIAL COOLING WATER SYSTEM. THIS CONDITION WAS | | PREVIOUSLY IDENTIFIED, BUT IT WAS DETERMINED AT THAT TIME THAT IT DID NOT | | AFFECT THE OPERABILITY OF THE ESSENTIAL COOLING WATER SYSTEM. HOWEVER, THE | | RADIATION MONITORS HAVE BEEN ISOLATED SINCE APRIL 28, 1994, AS A | | CONSERVATIVE MEASURE. ON JUNE 14, 1995, DURING THE PERFORMANCE OF | | ADDITIONAL EVALUATIONS TO UPGRADE THE RADIATION MONITORS TO SEISMIC | | REQUIREMENTS, THE LICENSEE'S ENGINEERING PERSONNEL DETERMINED THAT THE | | ESSENTIAL COOLING WATER RADIATION MONITORS WERE NOT CAPABLE OF WITHSTANDING | | A SAFE SHUTDOWN EARTHQUAKE. THE LICENSEE EVALUATED THIS CONDITION FOR | | REPORTABILITY AND DETERMINED IT TO BE REPORTABLE ON JUNE 22, 1995. | | | | THE ESSENTIAL COOLING WATER RADIATION MONITORS ARE LOCATED IN LINES | | APPROXIMATELY ONE-INCH IN DIAMETER WHICH GO FROM THE SUCTION SIDE OF THE | | PUMP TO THE DISCHARGE SIDE OF THE PUMP. THE LICENSEE'S EVALUATION | | DETERMINED THAT THERE WAS NOT ENOUGH SEISMIC SUPPORT FOR THESE LINES AND | | THAT IF ONE OF THESE LINES WOULD HAVE BROKEN DURING A SAFE SHUTDOWN | | EARTHQUAKE (WHILE THE LINE WAS NOT ISOLATED AND DEPENDING ON THE SIZE OF A | | POTENTIAL LINE BREAK), SURGE TANK LEVEL COULD HAVE DECREASED LOW ENOUGH SO | | THAT IT COULD HAVE AFFECTED ESSENTIAL COOLING WATER PUMP OPERATIONS. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28978 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 06/22/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 16:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/22/95 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: MIKE HEALY |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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 | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ANALYSIS OF A WESTINGHOUSE BULLETIN REGARDING THE USE OF RIVER WATER AS A | | POTENTIAL BACKUP SOURCE FOR THE STEAM GENERATORS RESULTED IN THE | | DETERMINATION THAT BOTH UNITS PREVIOUSLY OPERATED IN AN UNANALYZED | | CONDITION. | | | | WESTINGHOUSE BULLETIN 89-02 CHANGED THE DESIGN OF THE STATION SUCH THAT THE | | RECOMMENDATION FOR THE USE OF SERVICE WATER (RIVER WATER) AS A BACKUP | | SOURCE OF COOLING WATER FOR THE STEAM GENERATORS WAS DEEMED NOT | | RECOMMENDED. BOTH UNITS HAD OPERATED SINCE THE ISSUANCE OF THE BULLETIN | | WITHOUT ANY CHANGES TO THE STATION, AND IT HAS BEEN DETERMINED THAT A | | MODIFICATION CHANGE WILL BE REQUIRED PRIOR TO THE STARTUP OF EITHER UNIT. | | THE MODIFICATION (WHICH IS STILL UNDER EVALUATION) WOULD INVOLVE THE USE AN | | ALTERNATE SOURCE OF COOLING WATER AND/OR THE COMPLETION OF AN ANALYSIS THAT | | WOULD RECOMMEND THE USE OF RIVER WATER. | | | | THE BULLETIN RESCINDED A RECOMMENDATION FOR THE INITIAL DESIGN FOR ALLOWING | | USE OF THE RIVER WATER, BUT IT HAD A STIPULATION ALLOWING THE USE OF RIVER | | WATER AT A CERTAIN CHLORIDE CONCENTRATION FOR A CERTAIN LENGTH OF TIME. IF | | AN ACCIDENT (EARTHQUAKE/TORNADO) WERE TO OCCUR IN WHICH THE NORMAL STEAM | | GENERATOR COOLING WATER SUPPLY (AUXILIARY FEEDWATER TANKS) WAS LOST, THE | | BULLETIN STIPULATION WOULD ALLOW THE USE OF RIVER WATER FOR ONLY A CERTAIN | | AMOUNT OF TIME IN ORDER TO COOL DOWN. ALTHOUGH THERE IS A CAVEAT IN THE | | WESTINGHOUSE BULLETIN THAT ALLOWS THE USE OF RIVER WATER, THE UNITS ARE | | CURRENTLY NOT DESIGNED TO MEET THE WESTINGHOUSE SPECIFICATIONS TO COOL DOWN | | WITHIN THE 24-HOUR PERIOD SPECIFIED IN THE BULLETIN. | | | | THE RESIDENT INSPECTOR AND LOWER ALLOWAYS CREEK TOWNSHIP WILL BE NOTIFIED | | BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28979 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 06/22/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:01 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/22/95 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: JOHN DEDOMENICO |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH HPCI AND RCIC WERE DETERMINED TO HAVE BEEN INOPERABLE ON 6/21/95. | | | | AT 0622 ON JUNE 21, 1995, THE OPERATING CREW WAS INFORMED OF A CRACK IN THE | | LEAK-OFF LINE OF THE HPCI MINIMUM FLOW LINE CHECK VALVE. A MAINTENANCE | | WORKER DISCOVERED WEEPING AT THE TOE OF THE WELD WHERE IT ATTACHES TO THE | | STUFFING BOX ON THE BODY OF THE VALVE. THE INITIAL OPERABILITY | | DETERMINATION PROVIDED REASONABLE ASSURANCE OF CONTINUED HPCI OPERABILITY. | | (THE UNIT HAS A SINGLE HPCI PUMP THAT PROVIDES BOTH THE HIGH PRESSURE CORE | | SPRAY AS WELL AS THE THE HIGH PRESSURE FEED THROUGH THE FEEDWATER LINE.) AT | | 1630 ON 6/22/95, FURTHER ANALYSIS OF THE ASME BOILER AND PRESSURE VESSEL | | CODE REQUIREMENTS RESULTED IN THE DETERMINATION THAT TECHNICAL | | SPECIFICATION 3.4.8 (STRUCTURAL INTEGRITY) WERE NOT MET. THE ACTION | | REQUIREMENT FOR THIS TECHNICAL SPECIFICATION IS TO ISOLATE THE AFFECTED | | COMPONENT. THIS RENDERS THE HPCI SYSTEM INOPERABLE. MAINTENANCE | | ACTIVITIES ARE IN PROGRESS TO PERFORM REPAIRS AND RESTORE THE OPERABILITY | | OF THE MINIMUM FLOW CHECK VALVE AND THE HPCI SYSTEM TONIGHT. | | | | IN ADDITION, THE RCIC PUMP HAD BEEN DECLARED OUT-OF-SERVICE AT 0348 ON JUNE | | 20, 1995, DUE TO A MOMENTARY LOW SUCTION PRESSURE RCIC TRIP ALARM AND THE | | OBSERVANCE OF LOW SUCTION PRESSURE SPIKES DURING THE PERFORMANCE OF THE | | MONTHLY HPCI SURVEILLANCE. (THE SINGLE HPCI AND RCIC PUMPS SHARE A COMMON | | SUCTION LINE FROM THE CONDENSATE STORAGE TANK.) FOLLOWING AN EVALUATION, | | THE RCIC PUMP WAS RETURNED TO SERVICE AT 1410 ON JUNE 21, 1995. THE | | LICENSEE DETERMINED THAT THE LOW SUCTION PRESSURE SPIKES WERE ASSOCIATED | | WITH THE DIFFERENCES IN THE FLOW PATHS FOR THE TEST AND OPERATING VALVE | | LINE UPS. WHEN HPCI IS OPERATED NORMALLY, THE FLOW DOES NOT INCREASE AS | | QUICKLY AS IN THE TEST LINEUP BECAUSE THE VALVES ACTUALLY STROKE OPEN DUE | | TO THE INITIATION SIGNAL; WHEREAS THE VALVES IN THE TEST FLOW PATH ARE | | ALIGNED PRIOR TO THE INITIATION OF HPCI AND THE SYSTEM HAS MINIMAL | | RESISTANCE. THE RAPID INITIATION OF HPCI FLOW THROUGH THE COMMON SUCTION | | LINE CAUSED THE RCIC SUCTION PRESSURE TO SPIKE LOW. | | | | AT THE TIME OF THE DISCOVERY OF THE FLAW IN THE HPCI MINIMUM FLOW CHECK | | VALVE, THE RCIC PUMP WAS INOPERABLE. SINCE RCIC WAS INOPERABLE AT THE TIME | | OF DISCOVERY OF THE HPCI FLAW, THE LICENSEE DID NOT MEET THE LIMITING | | CONDITION FOR OPERATION FOR HPCI OR RCIC AS PROVIDED IN THE ASSOCIATED | | ACTION REQUIREMENTS. THEREFORE, TECHNICAL SPECIFICATION 3.0.3 WAS | | APPLICABLE FROM 0622 TO 1410 ON JUNE 21, 1995, BUT WAS NOT ENTERED BECAUSE | | HPCI WAS BELIEVED TO BE OPERABLE AT THE TIME. | | | | THIS UNIT HAS FOUR LPCI PUMPS AND FOUR LPCS PUMPS. THESE PUMPS WERE | | OPERABLE THROUGHOUT THIS EVENT. | | | | THE RESIDENT INSPECTOR AND THE LOCAL TOWNSHIP WILL BE NOTIFIED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28980 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 06/22/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 23:08 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/22/95 | +------------------------------------------------+EVENT TIME: 22:30[EDT]| |NRC NOTIFIED BY: JOE SERWAN |LAST UPDATE DATE: 06/22/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CURTIS COWGILL 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 | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE ENGINEERING ASSUMPTIONS CONTAINED IN WCAP-11634 ARE NOT IN AGREEMENT | | WITH UFSAR SECTION 3.6.5.2 WHICH RESULTS IN BOTH UNITS POTENTIALLY | | OPERATING OUTSIDE THE DESIGN BASIS. | | | | WCAP-11634 DATED OCTOBER 20, 1987, HAS BEEN USED AS THE BASIS FOR | | ENVIRONMENTAL QUALIFICATION OF EQUIPMENT IN THE STEAM LINE PENETRATION AREA | | SINCE THE IMPLEMENTATION OF THE BORON INJECTION TANK REMOVAL LICENSE | | AMENDMENTS (NOS. 78 AND 52 FOR UNITS 1 AND 2, RESPECTIVELY) DATED APRIL 7, | | 1987. THE WCAP DOES NOT AGREE WITH THE UFSAR ASSUMPTIONS OF THE PIPE BREAK | | SIZE. ADDITIONALLY, THE WCAP USED THE ASSUMPTION THAT THE SUBJECT MAIN | | STEAM SYSTEM PIPING IS DESIGNED TO SUPERPIPE CRITERIA WITHOUT PROVIDING A | | DETAILED DEMONSTRATION OF THE CONFORMANCE TO THE NRC PIPE BREAK EXCLUSION | | CRITERIA OF BRANCH TECHNICAL POSITION MEB 3-1. THIS RESULTS IN BOTH UNITS | | POTENTIALLY OPERATING OUTSIDE THE DESIGN BASIS. RESOLUTION OF THIS ISSUE | | IS REQUIRED PRIOR TO RESTART OF EITHER UNIT, AND THE LICENSEE'S | | INVESTIGATION IS CURRENTLY ONGOING. | | | | THE LICENSEE HAS NOTIFIED THE RESIDENT INSPECTOR AND WILL NOTIFY THE LOWER | | ALLOWAYS CREEK TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28981 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 06/23/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 04:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/23/95 | +------------------------------------------------+EVENT TIME: 03:27[EDT]| |NRC NOTIFIED BY: EPPERSON |LAST UPDATE DATE: 06/23/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP FROM 100% WHEN A NON-LICENSED PLANT EQUIPMENT OPERATOR | | INCORRECTLY OPENED A BREAKER TO PROCESS PROTECTION SET 1. | | | | THE UNIT 1 REACTOR TRIPPED FROM FULL POWER AT 0327 EDT ON 6/23/95. THE | | INITIATING SIGNAL WAS LOW-LOW LEVEL IN STEAM GENERATOR #2. THIS OCCURRED | | APPROXIMATELY 45 SECONDS AFTER THE 120 VAC VITAL POWER SUPPLY TO PROCESS | | PROTECTION SET 1 WAS INCORRECTLY OPENED BY A NON-LICENSED PLANT EQUIPMENT | | OPERATOR WHO WAS IN THE PROCESS OF PLACING AN EQUIPMENT CLEARANCE FOR | | ANOTHER DEVICE. | | | | THE PROCESS PROTECTION SETS (4) MONITOR VARIOUS PLANT PARAMETERS AND | | PROVIDE INPUT TO THE REACTOR PROTECTION SYSTEM LOGIC TRAINS AS WELL AS | | INPUT TO VARIOUS CONTROL SYSTEMS. THE OPENING OF THE POWER SUPPLY BREAKER | | APPARENTLY AFFECTED THE CONTROL OF THE MAIN FEEDWATER (STEAM GENERATOR | | WATER LEVEL CONTROL) SYSTEM, RESULTING IN THE REACTOR TRIP ON AN ACTUAL | | LOW-LOW LEVEL CONDITION IN STEAM GENERATOR #2. THE OTHER THREE PROTECTION | | SETS REMAINED ENERGIZED THROUGHOUT THE EVENT. | | | | ALL RODS FULLY INSERTED IN RESPONSE TO THE REACTOR TRIP. THERE WERE NO | | UNUSUAL PRIMARY LEVEL OR PRESSURE TRANSIENTS, AND NO PRIMARY RELIEF VALVES | | LIFTED. THE STEAM GENERATOR PORV's OPENED MOMENTARILY, AS EXPECTED, DUE TO | | THE TRANSIENT. THE PLANT IS STABLE IN HOT STANDBY, STEAMING VIA THE | | BYPASSES TO THE MAIN CONDENSER AND FEEDING THE STEAM GENERATORS WITH AUX | | FEEDWATER (AFW AUTO-STARTED, AS EXPECTED). THERE WERE NO PROBLEMS WITH BUS | | TRANSFERS. THE EDG's AND ECCS's ARE OPERATIONAL AND IN STANDBY. THE | | LICENSEE HAS INITIATED AN INVESTIGATION OF THE CAUSE, AND HAS INFORMED THE | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+