U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/25/96 - 10/28/96 ** EVENT NUMBERS ** 31209 31210 31211 31212 31213 31214 31215 31216 31217 31218 31219 31220 31221 31222 31223 31224 31225 31226 31227 31228 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31209 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 10/24/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 22:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/24/96 | +------------------------------------------------+EVENT TIME: 20:45[CDT]| |NRC NOTIFIED BY: ALEXANDER |LAST UPDATE DATE: 10/26/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORGENSON 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 +------------------------------------------------------------------------------+ | THREE STEAM GENERATORS DECLARED CATEGORY C-3 DURING INSERVICE INSPECTION. | | | | "ON OCTOBER 24, 1996, A STEAM GENERATOR (SG) TUBE INSERVICE INSPECTION WAS | | INITIATED ON BRAIDWOOD UNIT 1 IN ACCORDANCE WITH TECHNICAL SPECIFICATION | | SURVEILLANCE REQUIREMENT (TSSR) 4.4.5.0. THE INITIAL SAMPLE SIZE OF 100% OF | | ALL AVAILABLE TOP-OF-TUBESHEET ROLL TRANSITIONS WAS SELECTED. TSSR | | 4.4.5.2.c REQUIRES THAT THE RESULTS OF EACH SAMPLE INSPECTION BE CLASSIFIED | | INTO ONE OF THREE CATEGORIES. A SG WILL BE CLASSIFIED IN CATEGORY C-3 IF | | MORE THAN 10% OF THE TOTAL TUBES INSPECTED ARE DEGRADED OR MORE THAN 1% OF | | THE INSPECTED TUBES ARE DEFECTIVE. A SG TUBE IS CONSIDERED DEFECTIVE IF IT | | HAS AN IMPERFECTION OF GREATER THAN OR EQUAL TO 40% NOMINAL TUBE WALL. ON | | OCTOBER 24, 1996, AT 2045 HOURS, THE RESULTS OF THE SAMPLE INSPECTION | | RESULTED IN SG 1A, 1B AND 1D BEING CLASSIFIED INTO CATEGORY C-3 BASED ON | | GREATER THAN 1% OF THE INSERVICE TUBES BEING DEFECTIVE. THE NUMBER OF | | INSERVICE TUBES ARE 4029, 4450, AND 4181 FOR THE 1A, 1B AND 1D SGs, | | RESPECTIVELY. THESE TUBES ARE CONSIDERED DEFECTIVE MAINLY DUE TO | | CIRCUMFERENTIAL CRACK-LIKE INDICATION AT THE HOT LEG TOP-OF-TUBESHEET ROLL | | TRANSITION REGION." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 2025 ON 10/26/96 FROM ALEXANDER TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS COMPLETED THE INSERVICE TUBE INSPECTION OF THE 1C STEAM | | GENERATOR, AND IT TOO, HAS BEEN DECLARED CATEGORY C-3. OF THE 3835 | | INSERVICE TUBES, 618 ARE CONSIDERED TO BE DEFECTIVE, MAINLY DUE TO | | CIRCUMFERENTIAL CRACK-LIKE INDICATIONS AT THE HOT LEG TOP-OF-TUBESHEET ROLL | | TRANSITION REGION. THE HOO NOTIFIED R3DO (JORGENSON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31210 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 10/25/96 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 01:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/25/96 | +------------------------------------------------+EVENT TIME: 01:06[EDT]| |NRC NOTIFIED BY: STEVE ALLISON |LAST UPDATE DATE: 10/25/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ELINOR ADENSAM EO | | |AUSTIN FEMA | | |BARRETT AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 79 POWER OPERATION | 79 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT - LOSS OF 25% OF THE CONTROL ROOM ANNUNCIATORS | | | | A NOTIFICATION OF UNUSUAL EVENT WAS DECLARED ON UNIT 2 AT 0106 ON 10/25/96, | | DUE TO A LOSS OF SEVERAL ALARM PANELS; HOWEVER, ALL CONTROL BOARD | | INDICATIONS ARE AVAILABLE AND ARE BEING MONITORED FREQUENTLY. ADDITIONAL | | OPERATORS ARE IN THE CONTROL ROOM TO AID IN THIS TASK. | | | | THE ANNUNCIATOR PROBLEM OCCURRED AT 2310 ON 10/24/96, WHEN AN I&C | | TECHNICIAN ACCIDENTLY GROUNDED ONE OF THE ANNUNCIATOR ALARM LIGHT SOCKETS | | WHILE MAKING A REPAIR. THE SPECIFIC CAUSE FOR THE LOSS OF ANNUNCIATORS HAS | | NOT BEEN DETERMINED; TROUBLESHOOTING IS IN PROGRESS. ABOUT 25 OF THE | | CONTROL ROOM ALARMS INITIALLY LOCKED IN. HOWEVER, FURTHER INVESTIGATION | | REVEALED THAT SOME ALARMS WOULD NOT ACTUATE IF REQUIRED. A TOTAL OF ABOUT | | 25% OF THE CONTROL ROOM ANNUNCIATORS ARE INOPERABLE. | | | | ALL MAJOR SAFETY RELATED EQUIPMENT IS OPERABLE WITH THE FOLLOWING | | EXCEPTIONS, THE "A" TRAIN CONTAINMENT SPRAY PUMP AND ONE OF THREE "A" TRAIN | | COMPONENT COOLING WATER PUMPS. HOWEVER, THE "A" TRAIN CCW SYSTEM IS | | CONSIDERED OPERABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS STATE AND LOCAL | | OFFICIALS. | | | | * * * UPDATE AT 0420 ON 10/25/96 BY ROBINSON TAKEN BY WEAVER * * * | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 0420. ALL CONTROL ROOM | | ANNUNCIATORS HAVE BEEN RETURNED TO SERVICE. THE HOO NOTIFIED THE | | RDO(LANDIS); EO(ADENSAM); AEOD(BARRETT); FEMA(AUSTIN) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31211 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/25/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 12:37 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/25/96 | +------------------------------------------------+EVENT TIME: 11:59[EDT]| |NRC NOTIFIED BY: VANBLARCOM |LAST UPDATE DATE: 10/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WELLING 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 SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM FOLLOWING MAIN GENERATOR RUNBACK | | | | OPERATORS MANUALLY SCRAMMED THE REACTOR AFTER THE MAIN GENERATOR RAN BACK | | DUE TO PROBLEMS WITH THE STATOR COOLING WATER SYSTEM. ALL CONTROL RODS | | INSERTED, AND ALL SYSTEMS FUNCTIONED AS EXPECTED. THE LICENSEE IS CURRENTLY | | INVESTIGATING THE PROBLEM WITH THE STATOR COOLING WATER SYSTEM. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED. THE LICENSEE WILL PROBABLY MAKE A | | PRESS RELEASE REGARDING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31212 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/25/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 13:40 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/25/96 | +------------------------------------------------+EVENT TIME: 13:28[EDT]| |NRC NOTIFIED BY: KULTERMAN |LAST UPDATE DATE: 10/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WELLING RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INCORRECT ORIFICE SIZE IN SERVICE WATER PUMP STRAINERS COULD PERMIT FOULING | | OF HEAT EXCHANGERS | | | | THE LICENSEE DISCOVERED THAT THE SERVICE WATER PUMP DISCHARGE STRAINERS | | HAVE TUBE SHEETS MANUFACTURED TO INCORRECT DIMENSIONS (THE TUBES ARE TOO | | LARGE IN DIAMETER). THIS CONDITION COULD PERMIT FOULING OF HEAT EXCHANGERS | | WHICH ARE CONNECTED TO THE SERVICE WATER SYSTEM. IN PARTICULAR, THE EDG AND | | REACTOR PLANT CLOSED COOLING WATER SYSTEM HEAT EXCHANGERS COULD BE | | AFFECTED, RESULTING IN THE LOSS OF THE EDGs, RHR PUMPS, AND CENTRIFUGAL | | CHARGING PUMPS. | | | | THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR OF THIS ISSUE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31213 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 10/25/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 14:02 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/25/96 | +------------------------------------------------+EVENT TIME: 13:08[EDT]| |NRC NOTIFIED BY: WALDEN |LAST UPDATE DATE: 10/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WELLING 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 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CABLES FOR BOTH CHANNELS OF CONTAINMENT HYDROGEN MONITORING SYSTEM ARE | | ROUTED THROUGH THE SAME CONDUIT. | | | | DURING A WALKDOWN, THE LICENSEE DISCOVERED THAT CABLES FOR BOTH CHANNELS OF | | THE CONTAINMENT H2 MONITORING SYSTEM ARE ROUTED THROUGH THE SAME CONDUIT. | | THIS CONDITION IS IN CONFLICT WITH THE CABLE ROUTING METHOD DESCRIBED IN | | CHAPTER 8 OF THE UFSAR. THE LICENSEE HAS DECLARED BOTH CHANNELS OF THE | | CONTAINMENT H2 MONITORING SYSTEM INOPERABLE. | | | | THE LICENSEE PLANS TO TAG OUT ONE OF THE CABLES IN ORDER TO PERMIT THE | | OTHER CHANNEL TO BE DECLARED OPERABLE. THE NRC RESIDENT INSPECTOR WILL BE | | INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31214 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/25/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:52 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 10/25/96 | +------------------------------------------------+EVENT TIME: 14:10[EDT]| |NRC NOTIFIED BY: SQUIRES |LAST UPDATE DATE: 10/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORGENSON 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY/RELIEF VALVES DO NOT LIFT WITHIN REQUIRED PRESSURE RANGE | | | | DURING ONSITE TESTING OF SAFETY/RELIEF VALVES (SRVs), FIVE OF THE SIX | | VALVES TESTED AT THE SITE FAILED TO LIFT IN THEIR SAFETY VALVE MODE WITHIN | | THE REQUIRED PRESSURE RANGE. (THE VALVES ARE REQUIRED TO LIFT WITHIN ñ1% OF | | THEIR LIFT SETPOINT.) THE LICENSEE REPORTED THAT, OF THE VALVES THAT | | FAILED, THE SMALLEST DEVIATION FROM THE SETPOINT WAS +8.3%, AND THE LARGEST | | WAS GREATER THAN +19% (THE VALVE HAD NOT YET LIFTED). THE LICENSEE REPORTED | | THAT THE SETPOINT TESTING WAS PERFORMED USING A NITROGEN PRESSURE TEST | | APPARATUS. | | | | PLANT TECHNICAL SPECIFICATION 3/4.2.1 REQUIRES THAT 11 OF THE 15 SRVs LIFT | | WITHIN ñ1% OF THE SPECIFIED ASME CODE SAFETY FUNCTION LIFT SETPOINT. THE | | LICENSEE HAS REMOVED ALL SRVs, AND WILL BE SHIPPING SELECTED VALVES TO WYLE | | LABORATORIES FOR FURTHER TESTING. THESE VALVES ARE TARGET ROCK TWO-STAGE | | SRVs. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31215 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 10/25/96 | |UNIT: [ ] [ ] [3] STATE: CA |NOTIFICATION TIME: 14:56 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 10/25/96 | +------------------------------------------------+EVENT TIME: 09:55[PDT]| |NRC NOTIFIED BY: MITCHELL |LAST UPDATE DATE: 10/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VANDENBURGH RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTAINMENT PURGE ISOLATION SIGNAL | | | | WITH THE UNIT OPERATING AT 100% POWER, A CONTAINMENT PURGE ISOLATION SIGNAL | | (CPIS) OCCURRED DUE TO HIGH BACKGROUND RADIATION READINGS IN THE VICINITY | | OF RADIATION MONITOR #3RT7804C. THE LICENSEE REPORTED THAT THE SETPOINT OF | | THE RADIATION MONITOR WAS VERY CLOSE TO THE BACKGROUND READINGS IN THE | | VICINITY. THE LICENSEE IS AWARE OF A SMALL LEAK INSIDE CONTAINMENT WHICH IS | | CAUSING THE ELEVATED BACKGROUND READINGS. THE LICENSEE INTENDS TO RAISE THE | | SETPOINT OF THE MONITOR TO PREVENT SPURIOUS ISOLATION SIGNALS. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31216 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UTAH DIVISION OF RADIATION CONTROL |NOTIFICATION DATE: 10/25/96 | | CITY: MIDVALE REGION: 4 |NOTIFICATION TIME: 17:10 [ET]| | COUNTY: SALT LAKE STATE: UT |EVENT DATE: 10/25/96 | |LICENSE#: UT1800298 AGREEMENT: Y |EVENT TIME: 00:00[MDT]| | DOCKET: |LAST UPDATE DATE: 10/25/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |VANDENBURGH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JULIE FELICE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | APPLIED GEOTECHNICAL ENGINEERING CONSULTANTS, INC, A STATE OF UTAH | | LICENSEE, REPORTED THE THEFT OF A TROXLER MODEL 3430 MOISTURE/DENSITY GAUGE | | (S/N 19705). THE UNIT WAS PLACED IN A LOCKED CABINET AT THE LICENSEE'S | | FACILITY IN MIDVALE ON 9/4/96. THE UNIT WAS DISCOVERED MISSING DURING AN | | AUDIT PERFORMED DURING THE SECOND WEEK OF OCTOBER. THE LICENSEE HAS | | CONTACTED ALL TECHNICIANS TO SEE IF ONE OF THEM HAD REMOVED THE UNIT. THE | | LICENSEE'S CONTRACTOR FOR CALIBRATING THE UNITS WAS ALSO CONTACTED. | | | | THE LICENSEE HAS REPORTED THE STOLEN UNIT TO THE MIDVALE POLICE DEPARTMENT | | (CASE NO. 96-4130). THE STATE PLANS TO ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31217 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FL DIVISION OF RADIATION CONTROL |NOTIFICATION DATE: 10/25/96 | | CITY: LIVE OAK REGION: 2 |NOTIFICATION TIME: 17:54 [ET]| | COUNTY: SUWANNEE STATE: FL |EVENT DATE: 10/25/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 10/25/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LANDIS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DAVID FERGUSON | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | THE STATE OF FLORIDA WAS NOTIFIED THAT AN OLD (1960'S VINTAGE) GAS | | CHROMATOGRAPH HAD BEEN CRUSHED AND SENT FROM THE RECYCLING CENTER IN LIVE | | OAK, FL, TO A SCRAP YARD IN BALDWIN, FL, WHERE IT WAS REJECTED AFTER | | SETTING OFF THE PORTAL RADIATION MONITOR. THE STATE HAS CONTACTED THE | | MANUFACTURER, BUT NO INFORMATION ON THIS MODEL WAS AVAILABLE, AS IT HAS NOT | | BEEN MANUFACTURED SINCE 1967. THE STATE PLANS TO DISASSEMBLE THE UNIT TO | | ACCESS THE SOURCE TUBE, WHICH APPARENTLY CONTAINS A SMALL QUANTITY OF | | RADIUM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31218 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/25/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 20:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/25/96 | +------------------------------------------------+EVENT TIME: 16:36[CDT]| |NRC NOTIFIED BY: HITZEL |LAST UPDATE DATE: 10/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VANDENBURGH RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TWO AIR-OPERATED ISOLATION VALVES DECLARED INOPERABLE | | | | "ON OCTOBER 25, 1996, AT 1646 (CDT), COOPER NUCLEAR STATION DECLARED | | REACTOR WATER SAMPLE LINE ISOLATION VALVES RR-740AV AND RR-741AV | | INOPERABLE. IN ACCORDANCE WITH CNS TECHNICAL SPECIFICATION 3.7.D.2, CNS | | PLACED THESE VALVES IN THE ISOLATED POSITION. THE REACTOR WAS IN FULL POWER | | OPERATION. | | | | THESE VALVES ARE AIR-OPERATED ISOLATION VALVES WHICH ISOLATE THE REACTOR | | WATER SAMPLE LINE ON A GROUP 7 ISOLATION (REACTOR LOW-LOW-LOW WATER LEVEL | | OR MAIN STEAM HIGH RADIATION SIGNAL). THESE AIR-OPERATED VALVES ARE | | CONTROLLED VIA SOLENOID-OPERATED PILOT VALVES WHICH ACTUATE THE ISOLATION | | VALVES. THESE VALVES OPERATE OFF A COMMON SUPPLY HEADER SERVED BY A SINGLE | | PRESSURE REGULATOR. | | | | NRC GENERIC LETTER 91-15 IDENTIFIED THAT EXCEEDING THE MAXIMUM OPERATING | | PRESSURE DIFFERENTIAL OF AN SOV COULD CAUSE THE SOV TO FAIL TO CLOSE, OR | | SPURIOUSLY OPEN. IN RESPONSE TO THIS ISSUE, CNS INSTALLED A RELIEF VALVE ON | | THE AIR SUPPLY HEADER TO RR-740AV AND RR-741AV TO PROVIDE PROTECTION | | AGAINST SUCH A FAILURE. DURING REVISION OF A DESIGN BASIS DOCUMENT, IT WAS | | DETERMINED THAT THE SETPOINT OF THE RELIEF VALVE INSTALLED (120 PSI) | | EXCEEDED THE MAXIMUM OPERATING DIFFERENTIAL PRESSURE OF THE SOLENOID VALVES | | ASSOCIATED WITH RR-740AV AND RR-741AV (110 PSI). THEREFORE, THERE EXISTED A | | POTENTIAL FOR THE LOSS OF THE ISOLATION CAPABILITY FOR BOTH ISOLATION | | VALVES ON THE REACTOR WATER SAMPLE LINE UPON THE SINGLE FAILURE OF THE | | ASSOCIATED PRESSURE REGULATOR." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31219 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 10/25/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 21:19 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/25/96 | +------------------------------------------------+EVENT TIME: 21:10[EDT]| |NRC NOTIFIED BY: KRUEGER |LAST UPDATE DATE: 10/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WELLING 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 +------------------------------------------------------------------------------+ | SAFETY AUXILIARIES COOLING SYSTEM PUMP COULD TRIP DUE TO RUNOUT CONDITION | | | | THE LICENSEE HAS DETERMINED THAT EXISTING PLANT PROCEDURES, IN PLACE SINCE | | 1987, WOULD PERMIT OPERATORS TO PLACE THE SAFETY AUXILIARIES COOLING SYSTEM | | (SACS) IN A CONDITION IN WHICH A SINGLE RUNNING SACS PUMP COULD TRIP DUE TO | | PUMP RUNOUT. EACH OF THE TWO SACS SUBSYSTEMS PROVIDES COOLING WATER TO AN | | RHR HEAT EXCHANGER, TWO EDGs, AND TO OTHER ESSENTIAL LOADS. SPECIFICALLY, | | IF ONE OF THE TWO SACS PUMPS IN A SUBSYSTEM IS INOPERABLE, PROCEDURES | | PERMIT OPERATORS TO OPEN THE FLOW CONTROL VALVE FOR THE RHR HEAT EXCHANGER | | SERVED BY THE SUBSYSTEM. IN THIS CONFIGURATION, THE OPERATING PUMP COULD | | TRIP DUE TO PUMP RUNOUT, CAUSING A LOSS OF COOLING WATER FLOW TO ALL | | COMPONENTS SERVED BY THE SUBSYSTEM. | | | | THE LICENSEE IS REVISING ADMINISTRATIVE PROCEDURES TO MAINTAIN SACS SYSTEM | | OPERABILITY. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | (HOO NOTE: THIS EVENT IS RELATED TO EVENT #30915, REPORTED ON 8/22/96.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31220 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 10/26/96 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 08:06 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/26/96 | +------------------------------------------------+EVENT TIME: 06:33[CDT]| |NRC NOTIFIED BY: KEVIN STEIMER |LAST UPDATE DATE: 10/26/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -DISCONNECTED LPRMs CAUSED NONCONSERVATIVE APRM 15% HIGH FLUX SCRAM SIGNAL- | | | | WHILE MOVING FUEL DURING A REFUELING OUTAGE, THE LICENSEE DISCOVERED THAT | | 6 OF 20 LOCAL POWER RANGE MONITOR (LPRM) STRING UNITS (4 LPRMs PER STRING) | | WERE DISCONNECTED FROM THEIR ANPHENOL CONNECTORS WHILE THEIR LPRM MODE | | SELECTOR SWITCHES WERE IN THE "OPERATE" POSITION. THE APRM UNITS AVERAGED | | THE ZERO INPUT SIGNALS FROM THESE LPRMs DUE TO THEIR MODE SELECTOR SWITCH | | POSITION. THIS CONDITION RENDERED THE APRM 15% HIGH FLUX SCRAM SIGNAL TO | | BE NONCONSERVATIVE. | | | | TECH SPEC TABLE 3.1-1 A/S REQUIRES THE LICENSEE TO SUSPEND ALL CORE | | ALTERATION ACTIVITIES AND INSERT ALL CONTROL RODS WITHIN 1 HOUR WITH | | THE APRM HIGH FLUX SCRAM SIGNAL SET AT GREATER THAN 15% OF RATED POWER. | | THE LICENSEE IMMEDIATELY STOPPED ALL FUEL MOVEMENT AND VERIFIED THAT ALL | | CONTROL RODS WERE COMPLETELY INSERTED. | | | | THE LICENSEE IS DETERMINING THE CAUSE AND CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31221 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/26/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 08:59 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/26/96 | +------------------------------------------------+EVENT TIME: 04:13[CDT]| |NRC NOTIFIED BY: PHIL SHORT |LAST UPDATE DATE: 10/26/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTAINMENT ISOLATION VALVES CLOSED DUE TO MISSED TEST PROCEDURE STEPS - | | | | WITH THE PLANT IN A REFUELING OUTAGE, THE LICENSEE WAS PERFORMING A PORTION | | OF A DIVISION 1 EMERGENCY DIESEL GENERATOR INTEGRATED SURVEILLANCE TEST | | (LOSS OF POWER/EMERGENCY CORE COOLING SYSTEM ACTUATION). DURING THE | | PERFORMANCE OF THE TEST, A CONTAINMENT ISOLATION SIGNAL WAS RECEIVED ON | | EIGHT DRYWELL COOLING VALVES. ALL EIGHT CONTAINMENT ISOLATION VALVES | | CLOSED UPON RECEIPT OF THE ISOLATION SIGNAL. | | | | THE LICENSEE HAS DETERMINED THAT SEVERAL PROCEDURE STEPS WERE OVERLOOKED | | AND NOT PERFORMED DURING THE TEST. | | | | THE LICENSEE IS DETERMINING THE CAUSE(S) AND CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31222 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 10/26/96 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 13:58 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 10/26/96 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: RICE |LAST UPDATE DATE: 10/26/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LANDIS 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 +------------------------------------------------------------------------------+ | APPENDIX R ANALYSIS DID NOT CONSIDER EFFECT ON SAFETY INJECTION ISOLATION | | VALVE | | | | DURING AN ONGOING 10 CFR 50, APPENDIX R REVIEW, THE LICENSEE IDENTIFIED A | | CONDITION NOT PREVIOUSLY CONSIDERED FOR ALTERNATE HIGH HEAD SAFETY | | INJECTION COLD LEG RECIRC ISOLATION VALVE, XVG-8885-SI. THE ANALYSIS HAD | | FAILED TO CONSIDER SPURIOUS OPERATION OF THE VALVE. THE LICENSEE HAS | | DETERMINED THAT A POTENTIAL EXISTS FOR THE VALVE TO SPURIOUSLY OPERATE DUE | | TO A HOT SHORT IN THE MAIN CONTROL BOARD. | | | | THE LICENSEE IS CURRENTLY REVISING STATION FIRE EMERGENCY PROCEDURE FEP-4, | | "CONTROL ROOM EVACUATION DUE TO FIRE," AND EXPECTS THE CHANGES TO BE | | COMPLETED LATER TODAY. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31223 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/27/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 02:10 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/27/96 | +------------------------------------------------+EVENT TIME: 00:30[EST]| |NRC NOTIFIED BY: FRANK CIGANIK |LAST UPDATE DATE: 10/27/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAKE WELLING 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 +------------------------------------------------------------------------------+ | -PRIMARY CONTAINMENT LEAK RATE 2X TECH SPEC MAX ALLOWED WHILE PLANT IS S/D- | | | | WITH THE PLANT IN CONDITION 4 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE, | | A LICENSEE PRELIMINARY ANALYSIS OF GROSS PRIMARY CONTAINMENT LEAK RATE | | CALCULATION DATA INDICATES THAT THE LEAK RATE IS APPROXIMATELY TWICE THE | | TECH SPEC MAXIMUM ALLOWED RATE OF 426 SCFH. PRIMARY CONTAINMENT INTEGRITY | | IS NOT REQUIRED WHILE THE PLANT IS IN OPERATIONAL CONDITION 4. | | | | HAD THIS OCCURRED WHILE THE PLANT WAS OPERATING AT POWER, A PRINCIPAL | | SAFETY BARRIER WOULD HAVE BEEN DEGRADED OR PLANT SAFETY WOULD HAVE BEEN | | COMPROMISED. | | | | THE LICENSEE PLANS TO LOCATE AND REPAIR THE LEAKS PRIOR TO RESTARTING THE | | PLANT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31224 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/27/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 10:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/27/96 | +------------------------------------------------+EVENT TIME: 08:48[CST]| |NRC NOTIFIED BY: GREG SMITH |LAST UPDATE DATE: 10/27/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SECURITY EVENT - VITAL AREA BARRIER OPENED FOR 5 MINUTES W/O GUARD POSTED | | | | A 10 FOOT X 10 FOOT HATCH IN THE SERVICE WATER PUMP INTAKE CRIB HOUSE WAS | | OPENED WITHOUT A SECURITY GUARD BEING POSTED AT THE OPENING. A SECURITY | | GUARD WAS POSTED 5 MINUTES AFTER THE HATCH WAS OPENED. A LICENSEE | | EMPLOYEE HAD BEEN PRESENT AT THIS VITAL AREA BARRIER OPENING FOR THE | | ENTIRE 5 MINUTES. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31225 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 10/27/96 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 21:16 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/27/96 | +------------------------------------------------+EVENT TIME: 19:30[EST]| |NRC NOTIFIED BY: FIELDS |LAST UPDATE DATE: 10/27/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LANDIS 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 +------------------------------------------------------------------------------+ | INVALID CONTAINMENT VENTILATION ISOLATION | | | | THE LICENSEE REPORTED THAT AN INVALID CONTAINMENT GROUP '7A' ISOLATION | | OCCURRED DUE TO A FAILED RELAY IN THE 'A' CHANNEL LOGIC. THE INVALID SIGNAL | | CAUSED THE CONTAINMENT VENTILATION SYSTEM TO REALIGN TO RECIRCULATION MODE. | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31226 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 10/27/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 23:16 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 10/27/96 | +------------------------------------------------+EVENT TIME: 23:00[EST]| |NRC NOTIFIED BY: NICE |LAST UPDATE DATE: 10/28/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JORGENSON RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ADENSAM EO | |DDDD 73.71 UNSPECIFIED PARAGRAPH |AUSTIN FEMA | | |BARRETT IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO BOMB THREAT. IMMEDIATE COMPENSATORY MEASURES | | TAKEN. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY LICENSEE. SEE HOO | | LOG FOR DETAILS. | | | | * * * UPDATE AT 0106 EST ON 10/28/96 FROM CSER TAKEN BY KARSCH * * * | | THE UNUSUAL EVENT WAS TERMINATED AT 0105 EST BECAUSE NOTHING WAS FOUND. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. R3DO (JORGENSEN), NRR EO | | (ADENSAM), AND FEMA (AUSTIN) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31227 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/28/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 03:03 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/28/96 | +------------------------------------------------+EVENT TIME: 01:10[CST]| |NRC NOTIFIED BY: RON RUSTICK |LAST UPDATE DATE: 10/28/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 | | 2 | N Y 24 POWER OPERATION | 24 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | "B" TRAIN OF CONTROL ROOM HVAC IS INOPERABLE. | | | | WHILE OPERATING THE "B" TRAIN OF CONTROL ROOM HVAC, IT WAS FOUND THAT THE | | CONTROL ROOM WAS NOT GREATER THAN OR EQUAL TO 1/8 INCH OF WATER POSITIVE | | PRESSURE WITH RESPECT TO THE CABLE SPREADING ROOM AND ADJACENT AREAS. THE | | "B" TRAIN CONTROL ROOM HVAC WAS DECLARED INOPERABLE AND A 7 DAY LCO PER | | TECH SPEC 3.8.D.1 WAS ENTERED. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31228 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 10/28/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 03:04 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 10/28/96 | +------------------------------------------------+EVENT TIME: 00:00[EST]| |NRC NOTIFIED BY: FRANK CIGANIK |LAST UPDATE DATE: 10/28/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAKE WELLING RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLTR LICENSEE 24 HR REPORT | | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM AND CONTAINMENT ISOLATION. | | | | LOSS OF POWER TO THE "D" 4160 VOLT BUS RESULTED IN A REACTOR SCRAM (NO | | CONTROL ROD MOTION, RODS WERE ALREADY INSERTED) AND A CONTROL ROOM | | ISOLATION. THE CONTROL ROOM ISOLATION CAUSED THE LOSS OF THE REACTOR | | VESSEL VENT PATH FOR 13 MINUTES. COLD SHUTDOWN REQUIREMENTS SPECIFY THAT A | | VENT PATH MUST BE MAINTAINED. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+