U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/01/97 - 07/02/97 ** EVENT NUMBERS ** 32543 32563 32564 32565 32566 32567 32568 32569 32570 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32543 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 06/26/97 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 12:41 [ET]| |RX TYPE: [1] CE |EVENT DATE: 06/26/97 | +------------------------------------------------+EVENT TIME: 09:14[EDT]| |NRC NOTIFIED BY: BART NIXON |LAST UPDATE DATE: 07/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 +------------------------------------------------------------------------------+ | AN ELECTRICAL TRANSIENT DURING A RELAY REPLACEMENT ON PRIMARY MAKEUP SYSTEM | | CAUSED THE COMPONENT COOLING WATER (CCW) HEAT EXCHANGER (HX) OUTLET SERVICE | | WATER VALVE (CV-0826) TO REPOSITION TO ITS SAFETY POSITION. | | | | A DC BUS GROUND WAS INTRODUCED TO DC BUS 10 WHEN RELAY 63X/0210A WIRING WAS | | RELANDED PER WORK ORDER #2471127B. WHILE RELANDING THE LAST WIRE, A | | TECHNICIAN'S SCREWDRIVER BUMPED UP AGAINST THE CASING OF THE RELAY WHICH | | INTRODUCED A GROUND. THIS CAUSED A VOLTAGE SPIKE ON DC BUS 10 WHICH CAUSED | | A FUSE TO BLOW IN THE CONTROL VALVE CIRCUIT FOR A HIGH CAPACITY SERVICE | | WATER VALVE (CV-0826) ON THE CCW HX OUTLET. THE ELECTRICAL TRANSIENT CAUSED | | CV-0826 TO REPOSITION FROM ITS NORMAL POSITION TO ITS SAFETY POSITION | | (RECIRCULATION ACTUATION POSITION). THE LICENSEE REPLACED THE FUSE AND | | PLACED THE VALVE BACK IN ITS NORMAL POSITION. | | | | THIS INCIDENT ALSO CAUSED SERVICE WATER PUMP 7B TO AUTOMATICALLY START AND | | THE EMERGENCY DIESEL GENERATOR RAW WATER HEADER PRESSURE TO GO TO ALARM | | WHEN THE RAW WATER PRESSURE INCREASED IN PRESSURE. THIS CAUSED EMERGENCY | | DIESEL GENERATOR TROUBLE LIGHTS TO COME ON. PERSONNEL WERE SENT TO MANUALLY | | RESET THE ALARM PANELS; THUS CLEARING THE ALARMS IN THE CONTROL ROOM. THE | | EMERGENCY DIESEL GENERATOR AUTOMATIC START FUNCTION WAS NOT AFFECTED BY | | THIS EVENT, AND THE LICENSEE CONSIDERED THE EMERGENCY DIESEL GENERATORS TO | | BE OPERABLE DURING THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1357 ON 07/01/97, FROM VINCENT TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. UPON FURTHER REVIEW, THE | | LICENSEE HAS CONCLUDED THAT THIS EVENT DID NOT INVOLVE ENGINEERED SAFETY | | FEATURE COMPONENTS AND IS, THEREFORE, NOT REPORTABLE. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R3DO (LEACH). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32563 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 07/01/97 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 09:25 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 07/01/97 | +------------------------------------------------+EVENT TIME: 07:57[EDT]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 07/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILT SHYMLOCK 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP OF GROUP 1 SAFETY RODS AFTER MAIN FEEDWATER (FDW) PUMP | | TRIPPED ON HIGH DISCHARGE PRESSURE. | | | | AT APPROXIMATELY 0730 EDT, WHILE IN HOT SHUTDOWN AND SUBCRITICAL WITH ONE | | GROUP OF SAFETY RODS (GROUP 1) WITHDRAWN TO 50%, THE FDW PUMP TURBINE WAS | | NOT CONTROLLING FDW CONTROL VALVE DIFFERENTIAL PRESSURE PROPERLY IN THE | | AUTOMATIC MODE. AS A RESULT, THE FDW PUMP TURBINE WAS TAKEN TO THE MANUAL | | MODE OF OPERATION. AS THE OPERATORS ATTEMPTED TO STABILIZE FEEDWATER FLOW, | | THE FDW PUMP DID NOT PROPERLY RESPOND AND TRIPPED ON HIGH DISCHARGE | | PRESSURE. AT 0757 EDT, AS AN IMMEDIATE CONSERVATIVE RESPONSE TO THE FDW | | PUMP TRIP, THE UNIT WAS MANUALLY TRIPPED. ALL SAFETY RODS FULLY INSERTED | | INTO THE CORE. UNIT 1 WAS SUBCRITICAL THROUGHOUT THIS EVENT. | | | | UNIT 1 HAS BEEN STABILIZED IN THE HOT SHUTDOWN MODE WITH EMERGENCY FDW | | PROVIDING SECONDARY HEAT REMOVAL. THERE WERE NO AUTOMATIC REACTOR | | PROTECTION SYSTEM ACTUATIONS OR EMERGENCY SAFEGUARDS ACTUATIONS. UNITS 2 | | AND 3 WERE NOT AFFECTED BY THIS EVENT. | | | | THE CAUSE OF THE FDW PUMP TURBINE MALFUNCTION IS BEING INVESTIGATED. | | ACTIONS ARE IN PROGRESS TO RESTORE MAIN FDW AS THE SECONDARY HEAT REMOVAL | | SOURCE. FURTHER DETAILS WILL BE PROVIDED IN THE LICENSE EVENT REPORT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32564 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 07/01/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 09:56 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/01/97 | +------------------------------------------------+EVENT TIME: 09:40[EDT]| |NRC NOTIFIED BY: EMPEY |LAST UPDATE DATE: 07/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 +------------------------------------------------------------------------------+ | CONTROL ROOM VENTILATION SYSTEM TECHNICALLY INOPERABLE DUE TO AIR INLET | | DAMPER WORK | | | | THE SERVICE AIR CONDITIONING UNIT (SAC-1) AIR INLET DAMPER WHICH SERVES THE | | CONTROL ROOM IS BEING DISABLED FOR CORRECTIVE ACTIONS. (THE DAMPER DOES NOT | | MATE CORRECTLY TO ITS SEAL.) TECHNICALLY, THIS MAKES THE CONTROL ROOM | | VENTILATION SYSTEM INOPERABLE PER VERMONT YANKEE'S FINAL SAFETY ANALYSIS | | REPORT; HOWEVER, THE SYSTEM WILL REMAIN AVAILABLE. | | | | THERE ARE NO SPECIFIC ACTIONS REQUIRED AS THIS IS A REPAIR EFFORT WHICH | | SHOULD LAST APPROXIMATELY ONE HOUR. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32565 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 07/01/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:28 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 07/01/97 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: STEVE FULLER |LAST UPDATE DATE: 07/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 +------------------------------------------------------------------------------+ | PROMPT NOTIFICATION SYSTEM INOPERABLE DUE TO HARDWARE PROBLEM WITH THE | | PROMPT NOTIFICATION SYSTEM COMPUTER | | | | TODAY, LICENSEE PERSONNEL WENT TO THE OCEAN COUNTY SHERIFF'S OFFICE TO | | CHECK THE PROMPT NOTIFICATION SYSTEM COMPUTER. UPON ARRIVAL, THEY | | DISCOVERED THAT THE PROMPT NOTIFICATION SYSTEM WAS INOPERABLE DUE TO A | | HARDWARE PROBLEM. THE LICENSEE HAD NOT BEEN NOTIFIED BY THE OCEAN COUNTY | | SHERIFF'S OFFICE THAT THE COMPUTER WAS NOT OPERATING PROPERLY. WITH THE | | COMPUTER INOPERABLE, ALL 42 PROMPT NOTIFICATION SIRENS ARE INOPERABLE. THE | | LAST TIME THE SIRENS WERE KNOWN TO BE OPERABLE WAS 06/23/97. | | | | THE LICENSEE HAS PERSONNEL WORKING TO RESTORE THE COMPUTER BACK TO SERVICE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY STATE | | AND LOCAL OFFICIALS OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32566 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 07/01/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 11:34 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/01/97 | +------------------------------------------------+EVENT TIME: 11:30[EDT]| |NRC NOTIFIED BY: EMPEY |LAST UPDATE DATE: 07/01/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SHANBAKY 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 +------------------------------------------------------------------------------+ | THREE OUT OF FOUR TARGET ROCK SAFETY RELIEF VALVES (SRV) HAD EXCESSIVE | | DELAY TIMES WHEN TESTED. | | | | THE LICENSEE WAS INFORMED THAT 3 OUT OF 4 TARGET ROCK MODEL-67F SRVs, WHICH | | WERE REMOVED DURING THE MOST RECENT REFUELING OUTAGE (RFO 19), EXHIBITED | | UNACCEPTABLE DELAY TIMES WHEN TESTED AT WYLE LABS ON 06/25/97. DELAY TIME | | IS THE PERIOD BETWEEN THE OPENING OF THE PILOT VALVE AND THE OPENING OF THE | | MAIN VALVE. FINAL SAFETY ANALYSIS REPORT SECTION 4.5 REQUIRES THAT THE | | DELAY TIME FOR THE SRVs BE ó0.4 SECONDS. THE AFFECTED VALVES AND THEIR | | DELAY TIMES ARE LISTED BELOW: | | | | VALVE DELAY TIME | | | | RV-2-71A 4.67 SECONDS | | RV-2-71B 1.896 SECONDS | | RV-2-71C 0.51 SECONDS | | | | THE LICENSEE REPORTED THAT WHEN VALVE RV-2-71B WAS RETESTED, ITS DELAY TIME | | DECREASED TO <0.4 SECONDS. THE OTHER VALVES WERE NOT RETESTED, AND THEY | | HAVE BEEN DISASSEMBLED FOR INSPECTION. THE VALVES ARE CURRENTLY IN THE | | POSSESSION OF WYLE LABS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32567 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 07/01/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 15:09 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/01/97 | +------------------------------------------------+EVENT TIME: 11:17[EDT]| |NRC NOTIFIED BY: DAUGHERTY |LAST UPDATE DATE: 07/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |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 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR COOLANT SYSTEM (RCS) LETDOWN ISOLATION AND P-12 PERMISSIVE DURING | | STEAM DUMP MAINTENANCE | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "I&C TECHNICIANS COMMENCED WORK ON CONDENSER STEAM [SYSTEM] DUMP FOR VALVE | | CONTROL REPAIRS. DURING VALVE CONTROLLER REMOVAL FROM SERVICE, THE FIRST | | BANK OF VALVES FAILED CLOSED. WHILE THESE VALVES WERE CLOSED, RCS | | [TEMPERATURE] SLOWLY ROSE FROM 547øF TO 550øF, AND [THE] STEAM DUMP | | [SYSTEM] BEGAN TO MODULATE ON THE SECOND BANK OF VALVES. ONLY 1 VALVE IN | | THE BANK HAD BEEN ACTIVELY CONTROLLING RCS TEMPERATURE PRIOR TO FAILURE OF | | THE FIRST BANK." | | | | "DURING RESTORATION OF THE VALVE CONTROLLER TO SERVICE, THE FIRST BANK OF | | VALVES ALSO RETURNED TO SERVICE AND OPENED TO RESTORE Tave TO THE ORIGINAL | | SETPOINT OF 547øF. THE SPEED OF THE RETURN TO SERVICE RESULTED IN RAPID | | OPENING OF 2 STEAM DUMPS AND AN RCS COOLDOWN." | | | | "ACTION WAS TAKEN WITHIN 1 MINUTE TO CLOSE THE OPENED VALVES, BUT | | TEMPERATURE DROPPED MORE PRIOR TO STABILIZATION AND ACHIEVED THE P-12 [HIGH | | STEAM FLOW SAFETY INJECTION BLOCK PERMISSIVE] SETPOINT OF 543øF." | | | | "A[N RCS] LETDOWN ISOLATION ALSO OCCURRED AS A RESULT OF THE RCS | | TEMPERATURE REDUCTION." | | | | THE NRC RESIDENT WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 32568 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FEDERAL EXPRESS |NOTIFICATION DATE: 07/01/97 | | CITY: SACRAMENTO REGION: 4 |NOTIFICATION TIME: 19:07 [ET]| | COUNTY: SACRAMENTO STATE: CA |EVENT DATE: 06/29/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[PDT]| | DOCKET: |LAST UPDATE DATE: 07/01/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BILL JONES RDO | | |LARRY CAMPER/MNSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: FLETCHER (USCG) | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Xe-133 SOURCE LOST DURING TRANSPORTATION | | | | THE U.S. COAST GUARD NATIONAL RESPONSE CENTER WAS NOTIFIED BY FEDERAL | | EXPRESS (DR. ROY PARKER) THAT A BOX CONTAINING AN 8.51 GBq (230 mCi) Xe-133 | | SOURCE FELL FROM A TRUCK AND WAS LOST. THE INCIDENT OCCURRED ON INTERSTATE | | 5 NEAR THE AIRPORT. APPARENTLY, THE REAR CARGO DOORS WERE NOT SECURED AND | | OPENED WHILE THE VEHICLE WAS MOVING, PERMITTING THE PACKAGE TO FALL INTO | | THE ROADWAY. A SEARCH WAS CONDUCTED, AND THE OUTER BOX WAS FOUND. HOWEVER, | | THE INNER CONTAINER WAS NOT. DR. PARKER REPORTED THAT THE TRUCK WAS BEING | | OPERATED BY B AND G DELIVERY OF SACRAMENTO. | | | | THE NATIONAL RESPONSE CENTER NOTIFIED EPA REGION IX AND DOI OEPC. THE NRC | | REGION 4 OFFICE PLANS TO NOTIFY THE STATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32569 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 07/01/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 19:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/01/97 | +------------------------------------------------+EVENT TIME: 13:07[PDT]| |NRC NOTIFIED BY: ANDERSON |LAST UPDATE DATE: 07/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JONES RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REQUESTED OFFSITE ASSISTANCE DUE TO A WILDFIRE NEAR THE SITE. | | | | THE LICENSEE CONTACTED THE CALIFORNIA STATE DEPARTMENT OF FORESTRY TO | | REQUEST ASSISTANCE IN EXTINGUISHING A SMALL WILD LAND FIRE NEAR THE SITE. | | THE FIRE WAS EXTINGUISHED BY THE TIME THE DEPARTMENT OF FORESTRY PERSONNEL | | ARRIVED. THE FIRE WAS LOCATED NEAR THE PLANT'S STARTUP OFFSITE POWER LINE | | RIGHT OF WAY; HOWEVER, THE TRANSMISSION LINES WERE NEVER IN JEOPARDY. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32570 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 07/01/97 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 22:18 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 07/01/97 | +------------------------------------------------+EVENT TIME: 19:26[CDT]| |NRC NOTIFIED BY: BISTODEAU |LAST UPDATE DATE: 07/01/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LEACH 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 +------------------------------------------------------------------------------+ | MOMENTARY LOSS OF POWER TO LOAD CENTER CAUSES CONTAINMENT ISOLATION. | | | | A MOMENTARY LOSS OF POWER TO LOAD CENTER 101 DUE TO A SEVERE THUNDERSTORM | | CAUSED REACTOR PROTECTION SYSTEM (RPS) BUS 'A' TO BECOME DEENERGIZED. LOSS | | OF THE RPS BUS CAUSED THE 'A' AND 'C' MAIN STEAM LINE RADIATION MONITORS TO | | TRIP GENERATING A PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 ISOLATION | | AND A TRIP OF THE REACTOR BUILDING VENTILATION FANS. ADDITIONALLY, THE 'A' | | CONTROL ROOM INTAKE RADIATION MONITOR TRIPPED CAUSING THE CONTROL ROOM | | VENTILATION TO ALIGN TO THE EMERGENCY FILTRATION SYSTEM IN 'HIGH RAD' MODE. | | POWER HAS BEEN RESTORED, AND ALL SYSTEMS HAVE BEEN RETURNED TO NORMAL. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+