U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/04/96 - 10/07/96 ** EVENT NUMBERS ** 31092 31093 31094 31095 31096 31097 31098 31099 31100 31101 31102 31103 31104 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31092 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 10/04/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 10:23 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/04/96 | +------------------------------------------------+EVENT TIME: 09:31[EDT]| |NRC NOTIFIED BY: J. ROBERTSON |LAST UPDATE DATE: 10/05/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOYNER RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF CONTROL ROOM OVERHEAD ANNUNCIATORS FOR APPROXIMATELY 10 SECONDS | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "PLANT ENGINEERING ATTEMPTED TO DOWNLOAD MODIFICATIONS FOR THE OVERHEAD | | ALARM SYSTEM FOR CHANGES TO THE PLANT VENT RADIATION MONITOR SYSTEM. DURING | | MANUAL TRANSFER OF THE OVERHEAD ALARM TO ITS BACKUP COMPUTER (SER 'B'), THE | | OVERHEAD WINDOW BOX ALARMS LOCKED UP AND COULD NOT BE ACKNOWLEDGED. THE | | STATUS OF THE OVERHEAD ALARM CRT AND PRINTER WERE UNKNOWN DURING THIS TIME | | FRAME, THEREFORE OVERALL OHA STATUS WAS IN QUESTION." | | | | THE CONDITION CLEARED APPROXIMATELY 10 SECONDS AFTER TRANSFERRING TO THE | | BACKUP POWER SUPPLY, AND THE ALARMS HAVE PASSED ALL FUNCTIONAL TESTS. | | HOWEVER, THE LICENSEE REPORTED THAT STATUS VERIFICATION CHECKS WILL | | CONTINUE TO BE MADE AT 10-MINUTE INTERVALS UNTIL THE CONDITION IS | | UNDERSTOOD AND CORRECTED. THE UNIT IS CURRENTLY DEFUELED. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | ***UPDATE ON 10/05/96 @ 11:19 BY ROBERTSON TO GOULD*** THE LICENSEE IS | | SUSPENDING THE 10-MINUTE INTERVAL STATUS VERIFICATION CHECKS(AS OF 11:05), | | SINCE THEY HAVE AUTOMATIC CIRCUITRY WHICH CAN MAKE THESE CHECKS AT 4-MINUTE | | INTERVALS AND THEY SEE NO NEED FOR REDUNDANCY AT THIS TIME. ENGINEERING | | PERSONNEL ARE WORKING TO RE-CREATE THE SITUATION, BUT WHAT HAS BEEN DONE | | SINCE THEN IS THAT THEY HAVE REALIGNED THE OVERHEAD ALARM SYSTEM BACK TO A | | NORMAL CONFIGURATION. IT IS FUNCTIONING PROPERLY AND HAS BEEN OPERABILITY | | TESTED SATISFACTORILY, BUT HAS NOT BEEN CONSIDERED OPERABLE BUT IS | | FUNCTIONAL. THE RI WAS INFORMED. REG 1 RDO JOYNER WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31093 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LASALLE COUNTY STATION |NOTIFICATION DATE: 10/04/96 | | CITY: REGION: 3 |NOTIFICATION TIME: 15:35 [ET]| | COUNTY: STATE: IL |EVENT DATE: 09/28/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 12:00[CDT]| | DOCKET: |LAST UPDATE DATE: 10/04/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MR. SUBALUSKY |VERN HODGE NRR | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PART 21 NOTIFICATION ON WKM MODEL 70-13 PNEUMATIC ACTUATORS | | | | ANCHOR DARLING VALVE COMPANY PERFORMED EFFECTIVE DIAPHRAGM AREA (EDA) | | TESTING ON THE VARIOUS WKM MODEL 70-13 PNEUMATIC ACTUATORS (SIZES 35, 70, | | 140, 280). THE PRELIMINARY TEST RESULTS INDICATED THAT THE ORIGINAL | | EFFECTIVE DIAPHRAGM AREA VALUES USED TO CALCULATE THE BENCH SET AND SUPPLY | | AIR SET POINTS WERE INCORRECT. THESE ACTUATORS ARE USED ON VARIOUS PRIMARY | | CONTAINMENT ISOLATION VALVES AND THESE VALVES MAY NOT PROVIDE ADEQUATE | | SYSTEM ISOLATION UNDER DESIGN ACCIDENT CONDITIONS. | | | | LASALLE UNIT ONE IS IN COLD SHUTDOWN AND UNIT TWO IS IN THE REFUEL MODE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31094 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 10/04/96 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 16:06 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 10/04/96 | +------------------------------------------------+EVENT TIME: 13:00[CDT]| |NRC NOTIFIED BY: RANDY KNIGHT |LAST UPDATE DATE: 10/04/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON 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 N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF AN OIL SPILL | | | | ON 10/4/96, AT APPROXIMATELY 1300, AN OIL SHEEN WAS NOTED IN THE INTAKE | | FOREBAY. THE SOURCE OF THE OIL WAS FOUND TO BE A LEAKING HYDRAULIC | | CONNECTION ON A BARGE USED TO CLEAR GRASS FROM THE WATER. IT WAS ESTIMATED | | THAT 1 PINT OF OIL WAS RELEASED TO THE RIVER. THE NATIONAL RESPONSE CENTER | | AND THE ALABAMA DEPARTMENT OF ENVIRONMENTAL MANAGEMENT WAS NOTIFIED AT | | 1430. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31095 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FEDERAL EXPRESS STATION |NOTIFICATION DATE: 10/04/96 | | CITY: TRENTON REGION: 1 |NOTIFICATION TIME: 16:10 [ET]| | COUNTY: STATE: NJ |EVENT DATE: 10/04/96 | |LICENSE#: AGREEMENT: N |EVENT TIME: 13:40[EDT]| | DOCKET: |LAST UPDATE DATE: 10/04/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES JOYNER RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MST3 CHECKAN | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CARBON-14 RELEASED AT A FEDERAL EXPRESS STATION IN TRENTON, NJ | | | | THE NATIONAL RESPONSE CENTER REPORTED THAT 18.6 æCi OF C-14 WAS RELEASED AT | | A FEDERAL EXPRESS FACILITY IN TRENTON, NJ. THE RELEASE OCCURRED AT 1340 ON | | 10/4/96. THE RELEASE WAS FROM SOME BROKEN VIALS CONTAINED IN A PACKAGE IN | | THE FACILITY. THE RELEASE HAS BEEN SECURED AND NO DETECTABLE EXTERNAL | | CONTAMINATION HAS BEEN FOUND. | | | | A FEDERAL EXPRESS CONTACT NAME AND PHONE NUMBER IS AVAILABLE IN THE HOO | | LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31096 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 10/04/96 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 18:41 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 10/04/96 | +------------------------------------------------+EVENT TIME: 15:00[PDT]| |NRC NOTIFIED BY: MALCOLM MCGAUN |LAST UPDATE DATE: 10/04/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ENVIRONMENTALLY QUALIFIED (EQ) BARRIER DOOR FOUND BLOCKED OPEN | | | | AN EQ BARRIER DOOR WAS FOUND BLOCKED OPEN BY A BARREL FAN AT 1000 PDT. THE | | DOOR, AC401, IS BETWEEN THE 70' CONTROL BUILDING AND THE SAFETY EQUIPMENT | | BUILDING CORRIDOR. THE CORRIDOR IS SUBJECT TO STEAM INTRUSION DURING A | | MAIN STEAM OR FEEDWATER LEAK. STEAM COULD TRAVERSE THE CORRIDOR AND ENTER | | THE CONTROL BUILDING AREA. THE 70' CONTROL BUILDING IS CONSIDERED A MILD | | AREA, NOT EVALUATED FOR A HARSH ENVIRONMENT. BOTH TRAINS OF ESF COULD BE | | AFFECTED IN THIS SCENARIO. THE FAN WAS REMOVED AND THE DOOR CLOSED BY 1200 | | PDT. THE LICENSEE DOES NOT KNOW EXACTLY HOW LONG THE DOOR WAS OPEN, BUT | | SPECULATES THAT IT WAS OPEN FOR AT LEAST THREE HOURS. | | | | THIS EVENT IS STILL BEING INVESTIGATED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31097 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SOUTHWEST MEMORIAL HOSPITAL |NOTIFICATION DATE: 10/04/96 | | CITY: CORTEZ REGION: 4 |NOTIFICATION TIME: 19:04 [ET]| | COUNTY: STATE: CO |EVENT DATE: 10/04/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 15:00[MDT]| | DOCKET: |LAST UPDATE DATE: 10/04/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |IAN BARNES RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JAKE JACOBY | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PACKAGE RECEIVED WITH EXTERNAL CONTAMINATION | | | | SOUTHWEST MEMORIAL HOSPITAL RECEIVED A PACKAGE WITH EXTERNAL CONTAMINATION. | | THE PACKAGE CONTAINED Tc-99 AND Xe-133 AND HAD 73,000 DPM OF EXTERNAL | | CONTAMINATION. THE PACKAGE CAME FROM DUPONT IN MASSACHUSETTS. THE NAME OF | | THE SHIPPER WAS NOT IMMEDIATELY AVAILABLE. THIS EVENT WAS REPORTED BY THE | | COLORADO DEPARTMENT OF HEALTH. | | | | THE CONTACT PHONE NUMBER IS AVAILABLE IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31098 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/04/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 19:38 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 10/04/96 | +------------------------------------------------+EVENT TIME: 14:50[EDT]| |NRC NOTIFIED BY: JEFF GROFF |LAST UPDATE DATE: 10/04/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CORE THERMAL POWER EXCEEDED DURING PAST OPERATING CYCLES | | | | THE LICENSEE IS MAKING THIS REPORT IN ACCORDANCE WITH LICENSE CONDITION | | 2.F. AN ERROR WAS DISCOVERED IN THE SCALING OF THE PROCESS COMPUTER POINTS | | THAT PROVIDE THE RECIRCULATION PUMP POWER INPUTS INTO THE PROCESS COMPUTER | | PROGRAM THAT CALCULATES CORE THERMAL POWER. THIS SCALING FACTOR ERROR | | APPEARS TO HAVE EXISTED SINCE THE PLANT WAS ORIGINALLY LICENSED. | | | | THE RESULT OF THE PROCESS COMPUTER POINT SCALING ERROR IS THAT | | APPROXIMATELY THREE MWt NONCONSERVATIVE BIAS EXISTS IN THE CALCULATION OF | | CORE THERMAL POWER. DUE TO THIS ERROR, IT IS CONSIDERED LIKELY THAT FERMI | | 2 EXCEEDED ITS LICENSED CORE THERMAL POWER LIMIT OF 3292 MWt ON ONE OR MORE | | OCCASIONS DURING CYCLE 1, AND 3293 MWt ON ONE OR MORE OCCASIONS DURING | | CYCLES 2 AND 3 BY APPROXIMATELY 3 MWt. THE CURRENT LICENSED POWER LIMIT OF | | 3430 MWt HAS NOT BEEN EXCEEDED AS A RESULT OF THIS ERROR. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31099 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 10/04/96 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 20:42 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/04/96 | +------------------------------------------------+EVENT TIME: 19:35[CDT]| |NRC NOTIFIED BY: MIKE SICARD |LAST UPDATE DATE: 10/04/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL TO EXCEED EXPOSURE LIMITS IN THE TSC AND THE CONTROL ROOM DURING | | A LOCA | | | | TRAIN "C" HIGH HEAD SAFETY INJECTION (HHSI) DISCHARGE FLUSH LINE VALVE | | SI-0120C HAD EXCESSIVE LEAKAGE WITH THE VALVE CLOSED. THE LEAKAGE DRAINED | | TO THE FUEL HANDLING BUILDING SUMP. ENGINEERING CALCULATIONS VERIFIED THIS | | LEAKAGE COULD HAVE EXCEEDED THE 10 CFR 50 APPENDIX A, GDC 19 LIMITS FOR THE | | TECHNICAL SUPPORT CENTER AND CONTROL ROOM ENVELOPE. THE PERIOD OF CONCERN | | IS DURING THE POST LOSS OF COOLANT ACCIDENT (LOCA) CONTAINMENT | | RECIRCULATION PHASE OF A LARGE BREAK LOCA. | | | | THE VALVE HAS BEEN REPAIRED AND RETESTING IS IN PROGRESS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31100 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/04/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 23:14 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 10/04/96 | +------------------------------------------------+EVENT TIME: 19:20[EDT]| |NRC NOTIFIED BY: JOE MEYER |LAST UPDATE DATE: 10/06/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ULTIMATE HEAT SINK (UHS) DECLARED INOPERABLE FOR LESS THAN ONE HOUR | | | | DURING SHUTDOWN OF ELECTRICAL BUS 72ED, THE E1150-F602B DIV II RHR | | RESERVOIR CROSS TIE VALVE WAS DE-ENERGIZED CLOSED. THIS OCCURRED AT 1111 | | ON 10/4/96. AT 1920 ON 10/4/96 IT WAS RECOGNIZED THAT TS 3.7.1.5 ACTION C | | WAS ENTERED. IT REQUIRES THAT THE OTHER RHR RESERVOIR CROSS TIE LINE HAVE | | ITS VALVES OPENED AND DE-ENERGIZED WITHIN EIGHT HOURS. SINCE THE EIGHT | | HOURS EXPIRED AT 1911, THIS INVOKED TS 3.7.1.5 ACTION E.2 AND E.3 WHICH | | REQUIRED THE UHS BE DECLARED INOPERABLE. THIS IN TURN MADE DIVISION I | | SHUTDOWN COOLING INOPERABLE. | | | | REACTOR COOLANT SYSTEM TEMPERATURE (89øF) REMAINED UNCHANGED DURING THIS | | EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1359 ON 10/6/96 BY MAREK TAKEN BY WEAVER * * * | | TECH SPEC 3.7.1.5.c. ACTION STATEMENT REQUIRES THAT BOTH VALVES IN AT LEAST | | ONE CROSS CONNECT LINE FOR THE RHR RESERVOIRS BE OPENED AND DE-ENERGIZED. | | THE ACTION STATEMENT WAS SATISFIED WHEN THE E1150F601A CROSS TIE VALVE WAS | | OPENED ESTABLISHING A CROSS TIE FLOW PATH FROM THE DIVISION I RHR RESERVOIR | | TO THE DIVISION II RESERVOIR THROUGH VALVES F601A AND F601B. | | | | AT 1554 HOURS ON OCTOBER 5, 1996, VALVE F602B WAS OPENED TO MAINTAIN A FLOW | | PATH THROUGH THE REDUNDANT CROSS TIE LINE, WHICH CONTAINS VALVES F602A AND | | F602B. THIS WAS DONE TO ALLOW STROKING OF VALVE F601B FOR DIVER | | INSPECTION. OPERATORS OBSERVED THAT DIVISION I AND DIVISION II RESERVOIR | | LEVELS EQUALIZED SLOWLY. THIS INDICATED AN APPARENT LACK OF FLOW THROUGH | | THE F601A/F601B CROSS TIE PATH. THE CAUSE OF THE POTENTIAL PLUGGING IS | | BEING INVESTIGATED. THIS RESIDENT INSPECTOR WAS INFORMED OF THIS | | DEVELOPMENT. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31101 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 10/05/96 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 14:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/05/96 | +------------------------------------------------+EVENT TIME: 13:13[EDT]| |NRC NOTIFIED BY: JEFF EPPERSON |LAST UPDATE DATE: 10/05/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |WILLIAM BATEMAN EO | | |CALDWELL FEMA | | |BARRETT IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | EXPLOSION OF A POTENTIAL TRANSFORMER IN THE PROTECTED AREA | | | | AT 1412 EDT, A NOTIFICATION OF UNUSUAL EVENT WAS MADE AND TERMINATED AT | | SEQUOYAH FOLLOWING AN EXPLOSION WHICH OCCURRED WITHIN THE PROTECTED AREA. | | | | AT 1313 EDT, A POTENTIAL TRANSFORMER ON BUS 1 OF THE 500 KV SWITCHYARD | | EXPLODED. SWITCHYARD RELAYS SENSED THE ELECTRICAL FAULT AND OPENED POWER | | CIRCUIT BREAKERS TO CLEAR THE DIFFERENTIAL FAULT. AMONG THE DEVICES | | CLEARED WERE THE 500 KV TO 161 KV INTER-TIE TRANSFORMER (A SOURCE OF | | OFFSITE POWER) AND ONE OF UNIT 1's TWO MAIN GENERATOR OUTPUT BREAKERS. BOTH | | UNITS REMAINED ON LINE AND AT FULL POWER. NO ESF EQUIPMENT WAS CALLED UPON | | TO START. | | | | A FIRE (FUELED BY OIL FROM THE POTENTIAL TRANSFORMER) CONTAINED WITHIN THE | | 500 KV SWITCHYARD WAS EXTINGUISHED BY 1329 EDT. | | | | SHRAPNEL FROM THE EXPLOSION PUNCTURED A COOLING FIN OF THE INTER-TIE | | TRANSFORMER. THE RESULTANT OIL LEAK WAS ISOLATED. NO EQUIPMENT IDENTIFIED | | AS SAFETY RELATED WAS AFFECTED. | | | | SEQUOYAH STILL POSSESSES TWO OPERABLE SOURCES OF OFFSITE POWER AVAILABLE | | FOR THE 1E BUSES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND STATE OFFICIALS. A | | PRESS RELEASE IS PLANNED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31102 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/05/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:48 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/05/96 | +------------------------------------------------+EVENT TIME: 13:39[CDT]| |NRC NOTIFIED BY: MATT POHL |LAST UPDATE DATE: 10/05/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 | A N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR PROTECTION SIGNAL GENERATED ON LOW STEAM PRESSURE | | | | AT 1339 ON 10/5/96, FORT CALHOUN WAS PERFORMING A PLANT COOLDOWN TO 400øF | | PER PROCEDURE OP-3A WHEN STEAM GENERATOR LOW PRESSURE TRIP SIGNALS WERE | | RECEIVED ON TWO OF THE FOUR INSTALLED CHANNELS OF THE REACTOR PROTECTION | | SYSTEM. THE REACTOR TRIP SIGNAL WAS THE RESULT OF NOT INSTALLING THE | | BYPASS KEYS PRIOR TO REACHING THE LOW PRESSURE TRIP SETPOINT. | | | | THE REACTOR WAS IN AN ALL-RODS-IN CONFIGURATION (MODE 3) AT THE TIME THE | | REACTOR TRIP SIGNAL WAS RECEIVED. THE STEAM GENERATOR LOW PRESSURE BYPASS | | KEYS WERE INSERTED AND THE REACTOR TRIP SIGNAL WAS RESET. FORT CALHOUN IS | | CURRENTLY IN MODE 3 AND WILL BE GOING TO MODE 5 FOR ITS SCHEDULED REFUELING | | OUTAGE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31103 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 10/05/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 19:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/05/96 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: JOHN ROBERTSON |LAST UPDATE DATE: 10/05/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER 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 +------------------------------------------------------------------------------+ | ESF ACTUATION - EMERGENCY BUS UNDERVOLTAGE RELAYS ACTUATED | | | | AT 1548, UNIT 2 CONTROL ROOM RECEIVED AN OVERHEAD ALARM ASSOCIATED WITH A | | POTENTIAL UNDERVOLTAGE CONDITION ON 2A 4KV VITAL BUS. UP TO THIS POINT NO | | ESF ACTUATIONS HAD OCCURRED. SUBSEQUENTLY, AN OPERATOR WAS DISPATCHED AND | | A SINGLE BUS UNDERVOLTAGE RELAY WAS FOUND IN THE TRIPPED CONDITION. UPON | | FURTHER INVESTIGATION, INDIVIDUAL BUS PHASE TO PHASE VOLTAGES WERE CHECKED | | USING INSTALLED METERING ON THE 2A 4KV VITAL BUS. AT THAT TIME A SECOND UV | | RELAY TRIPPED CAUSING THE 2A SAFETY EQUIPMENT CABINET TO STRIP THE 2A BUS | | AND ENERGIZED IT FROM ITS ASSOCIATED DIESEL. ALL AVAILABLE EQUIPMENT ON | | THE 2A BUS LOADED ON DEMAND. | | | | THE LICENSEE PLANS TO LEAVE THE 2A EDG LOADED WHILE THIS EVENT IS | | INVESTIGATED. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31104 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 10/06/96 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 04:53 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 10/06/96 | +------------------------------------------------+EVENT TIME: 02:54[EDT]| |NRC NOTIFIED BY: KOVALCHICK |LAST UPDATE DATE: 10/06/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER 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 88 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT SCRAMMED FROM 88% ON A TURBINE CONTROL VALVE FAST CLOSURE SIGNAL. | | | | THIS LOAD REJECT SIGNAL WAS INITIATED BY GENERATOR PROTECTIVE RELAYING | | ASSOCIATED WITH THE GENERATOR STATOR CURRENT UNBALANCE ALARM. THIS TIME | | DELAY ALARM COULD NOT BE CORRECTED PRIOR TO THE LOAD REJECTION. NO APPARENT | | TURBINE DAMAGE OCCURRED, BUT THE CAUSE IS UNKNOWN AND INVESTIGATIONS ARE | | ONGOING. THEY ALSO RECEIVED A HIGH REACTOR PRESSURE SCRAM SIGNAL AS WELL AS | | A LOW REACTOR LEVEL SIGNAL. THE ALTERNATE ROD INSERTION (ARI) SIGNAL | | INITIATED ON HIGH REACTOR PRESSURE. THIS SIGNAL TRIPS THEIR RECIRCULATION | | PUMPS, HOWEVER, THE PUMPS HAD ACTUALLY TRIPPED PRIOR TO RECEIVING THE ARI | | SIGNAL SINCE THE LOAD REJECTION SIGNAL CAUSES A FAST TRANSFER ON THE 13KV | | BUSES AND THAT AUTOMATICALLY TRIPS THE RECIRC PUMPS. THE LOW REACTOR LEVEL | | CAUSED GROUP 2 AND 3 PRIMARY CONTAINMENT ISOLATION SIGNALS. ALL RODS FULLY | | INSERTED, NO INJECTION OCCURRED AND NO SAFETY RELIEF VALVES LIFTED. THE | | REACTOR IS STABLE AND THE CONDENSER IS THEIR HEAT SINK. THEY WILL TRY TO | | RESTART ONE OF THEIR RECIRC PUMPS WHEN THEY REACH THE CORRECT REACTOR | | PRESSURE. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+