U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/25/94 - 08/26/94 ** EVENT NUMBERS ** 27705 27706 27707 27708 27709 27710 27711 27712 27713 27714 27715 27716 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27705 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 08/25/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 06:02 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 03:27[CDT]| |NRC NOTIFIED BY: HENRY |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -Rx SCRAM DUE TO HI APRM FLUX SIGNAL WHEN 5 MAIN STEAM BYPASS VLVS OPENED- | | | | AT 2303 (CDT) ON 08/24/94, WHILE UNIT 2 WAS AT 100% POWER, THE #1 MAIN | | STEAM BYPASS VALVE OPENED, THEN IMMEDIATELY CLOSED FOR UNKNOWN REASONS. | | | | INSTRUMENT MAINTENANCE TECHNICIANS BEGAN TO TROUBLESHOOT THE SYSTEM. | | | | AT 2343 (CDT) ON 08/24/84, THE SAME EVENT HAPPENED AGAIN. | | | | AT 0327 (CDT) ON 08/25/94, ALL 5 MAIN STEAM BYPASS VALVES OPENED | | UNEXPECTEDLY, THEN IMMEDIATELY CLOSED. THE REACTOR THEN SCRAMMED DUE | | TO A HIGH APRM FLUX SIGNAL CAUSED BY THE RESULTING PRESSURE SPIKE AND | | SUBSEQUENT POWER SPIKE. CONTROL ROOM OPERATORS MANUALLY TRIPPED THE MAIN | | TURBINE (NORMAL ACTION AT LASALLE). ALL CONTROL RODS INSERTED COMPLETELY. | | THE 'D' IRM DID NOT DRIVE IN FOLLOWING THE SCRAM. STEAM IS BEING DUMPED | | TO THE MAIN CONDENSER. | | | | UNIT 2 IS STABLE IN CONDITION 3 (HOT SHUTDOWN). | | | | LICENSEE IS INVESTIGATING THE CAUSE AND DETERMINING CORRECTIVE ACTIONS. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27706 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 08/25/94 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 09:47 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 08:23[EDT]| |NRC NOTIFIED BY: STEFFENAUER |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |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 +------------------------------------------------------------------------------+ | -HPCI STEAM SUPPLY ISOLATION VALVE CLOSED DURING A TEST DUE TO HUMAN ERROR- | | | | WHILE PERFORMING INSTRUMENT CALIBRATIONS ON THE UNIT 1, DIVISION 2 RHR | | SYSTEM, TECHNICIANS INSTALLED A MULTIMETER ACROSS THE WRONG TERMINALS | | CAUSING HPCI STEAM SUPPLY OUTBOARD ISOLATION VALVE TO CLOSE RENDERING | | THE HPCI SYSTEM INOPERABLE. | | | | LICENSEE OPENED THE VALVE AND RESTORED THE HPCI SYSTEM TO NORMAL STANDBY | | STATUS. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27707 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 08/25/94 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 12:15 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 11:00[EDT]| |NRC NOTIFIED BY: MICHAEL DeBAY |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE SUBMITTED A LICENSEE EVENT REPORT (LER 94-08-00) ON JUNE 17, | | 1994 TO DOCUMENT A CIRCUIT INTERACTION BETWEEN CLASS 1E AND NON-CLASS 1E | | LOADS THAT WAS DISCOVERED WHILE IMPLEMENTING A PLANT MODIFICATION. DURING | | REFUELING OUTAGE 3, THE LICENSEE REVIEWED SIMILAR CIRCUITS AND EVALUATED | | POTENTIAL RESULTS OF CIRCUIT INTERACTIONS BETWEEN CLASS 1E AND NON-CLASS 1E | | CIRCUITS THAT HAD NOT BEEN PREVIOUSLY ANALYZED. | | | | ON AUGUST 24, 1994, THE LICENSEE DETERMINED THAT DURING A DESIGN BASIS | | SEISMIC EVENT WITH THE POSTULATED SIMULTANEOUS FAILURE OF ALL NON-CLASS 1E | | LOADS, THE RESULTANT INTERACTION WOULD CAUSE A LOSS OF POWER TO THE POWER | | PANELS SUPPLYING CENTRIFUGAL CHARGING PUMP MINIMUM FLOW VALVE | | INSTRUMENTATION. THIS COULD HAVE RESULTED IN THE VALVES NOT CLOSING DURING | | A SAFETY INJECTION. THE SPECIFIC CIRCUIT INTERACTIONS WERE IDENTIFIED | | DURING REFUELING OUTAGE 3 AND CORRECTED PRIOR TO THE COMPLETION OF THE | | OUTAGE ON JULY 31, 1994. | | | | ON AUGUST 25, 1994 AT 1100 EDT, THE LICENSEE DETERMINED THAT THIS EVENT IS | | REPORTABLE AS AN EVENT FOUND WHILE THE REACTOR WAS SHUTDOWN THAT HAD IT | | BEEN DISCOVERED WHILE THE PLANT WAS OPERATING, WOULD HAVE RESULTED IN THE | | PLANT OPERATING IN AN UNANALYZED CONDITION THAT SIGNIFICANTLY COMPROMISED | | PLANT SAFETY (10 CFR 50.72(B)(2)(I)). | | | | THE LICENSEE WILL DOCUMENT THE FINAL RESULTS OF THE EVALUATION IN AN LER | | SUPPLEMENT. THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27708 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 08/25/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 15:38 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 15:30[EDT]| |NRC NOTIFIED BY: HOLLONQUIST/CONNALLY |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ 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 +------------------------------------------------------------------------------+ | ON AUGUST 11, 1994, AN ENGINEERING EVALUATION DETERMINED THAT TWO PRIMARY | | CONTAINMENT PENETRATIONS (X-52E AND X-52F) DID NOT MEET THE DESIGN | | REQUIREMENTS. | | | | SECTION 2.2.3.2.D OF THE VERMONT YANKEE SAFETY CLASSIFICATION MANUAL | | SPECIFIES THAT THE CLASSIFICATION OF SYSTEMS, COMPONENTS AND STRUCTURES | | WHICH ARE REQUIRED TO PROVIDE OR MAINTAIN PRIMARY CONTAINMENT INTEGRITY BE | | BUILT TO SAFETY CLASS 2 STANDARDS. CONTRARY TO THIS REQUIREMENT, IT WAS | | DETERMINED THAT THESE PENETRATIONS ARE NOT ISOLATED WITH COMPONENTS THAT | | MEET SAFETY CLASS 2 STANDARDS. THE IDENTIFIED NON-SAFETY PORTIONS OF THESE | | PENETRATIONS WERE ISOLATED ON AUGUST 11. | | | | THE LICENSEE DETERMINED THAT THIS EVENT WAS REPORTABLE ON AUGUST 25. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27709 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/25/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 16:50 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: ROBERT BORCHERT |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ENGINEERING EVALUATION HAS IDENTIFIED A POSTULATED CONDITION WHERE A | | STEAM LINE BREAK OUTSIDE OF THE CONTAINMENT COULD CREATE AN ENVIRONMENT | | THAT MAY DEGRADE THE 120 VOLT VITAL AC ELECTRICAL SYSTEM. | | | | A POSTULATED STEAM LINE BREAK IN THE EAST ELECTRICAL PENETRATION ROOM WOULD | | CREATE A STEAM ENVIRONMENT THAT COULD CAUSE A SHORT CIRCUIT IN THE HYDROGEN | | MONITORS. THIS SHORT CIRCUIT IS POSTULATED TO DEGRADE THE 120 VOLT VITAL | | AC ELECTRICAL SYSTEM TO UNACCEPTABLY LOW LEVELS. LOADS SUCH AS THE | | ENGINEERED SAFETY FEATURES SYSTEM MAY NOT FUNCTION AS DESIGNED. | | | | THE LICENSEE IS EVALUATING CORRECTIVE ACTIONS. THE NRC RESIDENT INSPECTOR, | | STATE AND LOCAL OFFICIALS HAVE BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27710 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 08/25/94 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 16:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 14:16[EDT]| |NRC NOTIFIED BY: JILL WELLES |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | A CONTRACTOR EMPLOYEE PERFORMING SUPERVISORY RESPONSIBILITIES AS IDENTIFIED | | IN 10 CFR 26.73 TESTED POSITIVE FOR MARIJUANA DURING A RANDOM TEST. THIS | | WAS A CONFIRMED POSITIVE TEST RESULT. | | | | THE EMPLOYEE HAS NOT PERFORMED DUTIES IN THE PROTECTED AREA SINCE THE | | INITIAL TEST ON AUGUST 22. THE EMPLOYEE'S ACCESS HAS BEEN TERMINATED AT | | THE CATAWBA STATION AND THE EMPLOYEE WILL BE DENIED ACCESS AT ALL DUKE | | POWER FACILITIES. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 27711 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GENERAL ELECTRIC CO. |NOTIFICATION DATE: 08/25/94 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 18:26 [ET]| |COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 08/25/94 | | LEU FABRICATION |EVENT TIME: 14:30[EDT]| | LWR COMMERICAL FUEL |LAST UPDATE DATE: 08/25/94 | | CITY: WILMINGTON REGION: 2 +-----------------------------+ | COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION| |LICENSE#: SNM-1097 AGREEMENT: Y |JACK CRLENJAK RDO | | DOCKET: 07001113 |MIKE BELL EO | +------------------------------------------------+ | |NRC NOTIFIED BY: FRED WELFARE | | |HQ OPS OFFICER: THOMAS ANDREWS | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AT ABOUT 1430 EDT ON AUGUST 25, 1994, THE LICENSEE (GENERAL ELECTRIC, | | WILMINGTON, NC) DISCOVERED THAT A CONDENSATE DRAIN LINE FROM THE HOOD | | VENTILATION SYSTEM IN THE CHEMICAL / METALLURGICAL LABORATORY WAS DIRECTED | | TO A FIVE GALLON PAIL INSTEAD OF TO A SUMP AS WAS BELIEVED. THE LICENSEE | | IS REPORTING THIS CONDITION AS A CONSERVATIVE MEASURE PURSUANT TO NRC | | BULLETIN 91-01. ACCORDING TO THE LICENSEE, THIS SITUATION DOES NOT HAVE ANY | | DIRECT SAFETY SIGNIFICANCE BUT IT MAY BE REPORTABLE SINCE THE EXISTING | | SITUATION WAS NOT AS EXPECTED. | | | | THE SITUATION HAS EXISTED FOR SOME TIME. IT WAS DISCOVERED AT THIS TIME | | BECAUSE A LABORATORY BENCH WAS BEING REPLACED. THIS CONDITION RESULTED | | FROM WORK THAT HAD BEEN STARTED BUT NOT COMPLETED. THE CONDENSATE DRAIN | | ONLY FUNCTIONS WHEN THE HOOD VENTILATION SYSTEM IS NOT OPERATING SO THE | | VOLUME OF LIQUID AND THE URANIUM CONTENT ARE VERY SMALL. THE RESULT WAS A | | FIVE GALLON PAIL CONTAINING ABOUT ONE LITER OF NITRATE CRYSTALS AND ABOUT | | 200 MILLILITERS OF LIQUID. THE MATERIAL REMOVED FROM THE PAIL HAS BEEN | | ANALYZED AS CONTAINING APPROXIMATELY 8.5 GRAMS OF URANIUM. | | | | THIS DRAIN CONFIGURATION HAS BEEN REMOVED AND THE OTHER SIMILAR CONDENSATE | | DRAINS IN THE LABORATORY HAVE BEEN TRACED AND FOUND TO BE ACCEPTABLE. | | | | STATE AND LOCAL OFFICIALS WILL BE NOTIFIED OF THIS REPORT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27712 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 08/25/94 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 15:05[PDT]| |NRC NOTIFIED BY: LEMKE |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING THE INSTALLATION OF NEW RADIATOR FAN BLADES FOR THE EMERGENCY DIESEL | | GENERATORS DURING THE SIXTH REFUELING OUTAGE FOR UNIT 1, THE DESIGN CHANGE | | ACCEPTANCE CRITERIA FOR RADIATOR OUTLET COOLING AIR FLOW (140,000 ACFM) WAS | | NOT OBTAINED. THIS ACCEPTANCE CRITERIA WAS BASED ON THE COMPONENT DESIGN | | BASES WHICH CALLS FOR A RADIATOR INLET AIR TEMPERATURE OF 90 DEGREES F, AN | | EMERGENCY DIESEL GENERATOR LOAD OF 3000 KW, AND A JACKET WATER TEMPERATURE | | OF 180 DEGREES F. | | | | AS A RESULT OF NOT MEETING THE DESIGN CHANGE AIR FLOW ACCEPTANCE CRITERIA, | | THIRTY SEVEN SEPARATE EMERGENCY DIESEL GENERATOR RADIATOR AIR FLOW TESTS | | WERE PERFORMED IN MARCH AND APRIL OF 1994. THE TESTS WERE PERFORMED USING | | A VARIETY OF TECHNIQUES AND MEASUREMENT INSTRUMENTS. THE TEST RESULTS | | EXHIBITED A SUBSTANTIAL DEGREE OF VARIABILITY. THEREFORE, THE TEST | | METHODOLOGY WHICH RESULTED IN THE MOST ACCURATE AIR FLOW MEASUREMENTS COULD | | NOT BE ABSOLUTELY DETERMINED. TO RESOLVE THIS CONCERN, THE LICENSE HAS | | CONTRACTED WITH OUTSIDE TECHNICAL EXPERTS TO ASSESS THE ACCURACY OF THE | | MEASUREMENT TECHNIQUES USED TO ASSESS EMERGENCY DIESEL GENERATOR AIR FLOWS. | | | | A PRELIMINARY CALCULATION WAS PERFORMED TO CONSERVATIVELY ASSESS EMERGENCY | | DIESEL GENERATOR RADIATOR PERFORMANCE BY USING THE LOWEST MEASURED AIR | | FLOWS INCLUDING CORRECTIONS FOR CALIBRATION INACCURACIES. THE CALCULATION | | USED ENGINEERING JUDGMENT TO QUANTIFY THE EFFECTS OF WIND SPEED AND | | DIRECTION ON THE EMERGENCY DIESEL GENERATOR'S RADIATOR AIR FLOW. THE | | RESULT WAS A CALCULATED MAXIMUM ALLOWABLE AMBIENT AIR TEMPERATURES OF 83.7 | | AND 73 DEGREES F WITH THE ROLL-UP DOORS OPENED AND CLOSED, RESPECTIVELY. | | | | THE LICENSING BASIS FOR THE EMERGENCY DIESEL GENERATOR RADIATOR INLET | | AMBIENT TEMPERATURE IS BASED ON THE ASHRAE STANDARD OF 0.1 PERCENT | | PROBABILITY OF OCCURRENCE (HISTORICALLY ESTABLISHED AS 78 DEGREES F). | | ADDITIONALLY, IT MUST BE REASONABLY ASSURED THAT THE EMERGENCY DIESEL | | GENERATORS ARE CAPABLE OF PERFORMING THEIR SAFETY RELATED FUNCTION AT | | AMBIENT TEMPERATURES HIGHER THAN THE 0.1 PERCENT ASHRAE LICENSING BASIS | | VALUE OF 78 DEGREES F. THEREFORE, BASED ON THE CONSERVATIVELY SELECTED AIR | | FLOWS, THE PRELIMINARY CALCULATION RESULTS INDICATE THAT PRIOR TO THE | | IMPLEMENTATION OF THE HOT WEATHER PLAN, OPERATORS MAY NOT HAVE HAD | | SUFFICIENT PROCEDURAL GUIDANCE TO ENSURE THAT EMERGENCY DIESEL GENERATOR'S | | EAST ROLL-UP DOORS WOULD HAVE BEEN OPENED PRIOR TO THE EMERGENCY DIESEL | | GENERATORS OVERHEATING (I.E. JACKET WATER EXCEEDING 200 DEGREES F; NORMAL | | OPERATING TEMPERATURE IS APPROXIMATELY 175 DEGREES F). ACCORDINGLY, THE | | EMERGENCY DIESEL GENERATORS MAY NOT HAVE BEEN CAPABLE OF PERFORMING THEIR | | DESIGN FUNCTION AT AMBIENT AIR TEMPERATURES ABOVE 73 DEGREES F. THIS | | TEMPERATURE IS BELOW THE LICENSING BASIS AMBIENT AIR TEMPERATURE OF 78 | | DEGREES F. | | | | A SERIES OF ANNUNCIATOR RESPONSE PROCEDURE REVISIONS HAVE BEEN MADE (HOT | | WEATHER PLAN) WHICH WILL ENSURE THAT THE EMERGENCY DIESEL GENERATOR'S EAST | | ROLL-UP DOORS WILL BE OPENED WHENEVER THE AMBIENT AIR TEMPERATURE EXCEEDS | | 70 DEGREES F. THE PLAN ALSO REQUIRES A DESIGNATED OPERATOR TO BE STATIONED | | AT THE EMERGENCY DIESEL GENERATOR ROOMS TO CONTINUOUSLY MONITOR JACKET | | WATER TEMPERATURES FOR ALL RUNNING EMERGENCY DIESEL GENERATORS WHENEVER | | AMBIENT AIR TEMPERATURE EXCEEDS 80 DEGREES F. THIS HOT WEATHER PLAN | | ENSURES THAT THE EMERGENCY DIESEL GENERATORS ARE CAPABLE OF PERFORMING | | THEIR DESIGN BASIS FUNCTIONS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27713 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 08/25/94 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 18:40 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 16:45[EDT]| |NRC NOTIFIED BY: DAVE STEFFENAUER |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATIONS TO GOVERNMENT AGENCIES WILL BE MADE CONCERNING A | | SPILL OF ETHYLENE-GLYCOL AS SUSQUEHANNA'S WASTE ACCUMULATION AREA. THE | | AREA IS LOCATED ON THE LICENSEE'S PROPERTY BUT IS OUTSIDE THE PLANT'S | | PROTECTED AREA. | | | | A 55 GALLON DRUM CONTAINING A 50% SOLUTION OF ETHYLENE-GLYCOL, THAT HAS A | | DEFAULT 1 POUND SPILL REPORTABLE QUANTITY PER THE COMPREHENSIVE | | ENVIRONMENTAL RESPONSE COMPENSATION LIABILITY ACT (SUPER FUND), DEVELOPED A | | LEAK THAT PERMITTED THE CONTENTS TO ESCAPE INTO A BERMED AREA DESIGNED TO | | PREVENT LIQUID MATERIAL FROM CONTACTING THE GROUND. THE MATERIAL PASSED | | THROUGH A JOINT IN THE SPILL PROTECTION BERM. IT IS BELIEVED THAT | | APPROXIMATELY 250 POUNDS OF ETHYLENE-GLYCOL REACHED THE ENVIRONMENT. | | | | THE PROPOSED REPORTABLE QUANTITY CURRENTLY UNDER REVIEW BY THE EPA FOR | | ETHYLENE-GLYCOL IS 5000 POUNDS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. THE LICENSEE HAS NOTIFIED | | STATE, LOCAL, AND OTHER GOVERNMENT AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27714 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 08/25/94 | |UNIT: [ ] [2] [ ] STATE: TN |NOTIFICATION TIME: 20:04 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 17:11[EDT]| |NRC NOTIFIED BY: DENNIS DIMOPOULOS |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK 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 +------------------------------------------------------------------------------+ | DURING PERFORMANCE OF INSTRUMENT CALIBRATION ON A NON-ESSENTIAL CONTROL AIR | | CONTAINMENT ISOLATION VALVE, CONTROL AIR TO UNIT 2 CONTAINMENT WAS | | INADVERTENTLY ISOLATED, RESULTING IN SEVERAL COMPONENTS FAILING TO THE | | CLOSED POSITION. AFFECTED SYSTEMS WERE: | | | | - RADIATION MONITORING | | - WASTE DISPOSAL | | - CONTROL AIR | | - ICE CONDENSER (GLYCOL) | | - VENTILATION | | | | UNIT 2 IS DEFUELED AND THIS EVENT DID NOT RESULT IN AN INCREASE IN | | REACTIVITY OR A RADIATION RELEASE. THE ISOLATION OCCURRED AS A RESULT OF | | STEPS IN THE CALIBRATION PROCEDURE BEING PERFORMED OUT OF SEQUENCE CAUSING | | THE LOSS OF AIR FLOW TO CONTAINMENT. | | | | UNIT OPERATORS NOTICED THE ISOLATION WHEN THEY SAW THE GLYCOL VALVE | | CHANGING POSITION ON THE STATUS MONITOR PANEL. ACTIONS WERE IMMEDIATELY | | TAKEN TO RESTORE AIR FLOW. BY 1722 EDT, ALL EQUIPMENT THAT HAD ISOLATED AS | | A RESULT OF THE LOSS OF AIR HAD BEEN RETURNED TO NORMAL STATUS. A LIMITED | | NUMBER OF COMPONENTS WERE AFFECTED SINCE THE UNIT IS IN A REFUELING OUTAGE | | AND A LARGE NUMBER OF COMPONENTS ARE TAGGED OUT OF SERVICE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27715 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 08/25/94 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 20:50 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 20:32[EDT]| |NRC NOTIFIED BY: RANDY KENNEDY |LAST UPDATE DATE: 08/25/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |MARTIN VIRGILIO EO | |ANTO 50.72(b)(1)(iii) TORNADO |DAN SULLIVAN FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO A TORNADO WARNING BEING | | DECLARED FOR THE AREA AROUND THE PLANT. A TORNADO WAS SPOTTED ABOUT 10 | | MILES UP RIVER MOVING DOWN RIVER (SOUTH-EAST) IN THE GENERAL DIRECTION OF | | THE PLANT. | | | | THE UNUSUAL EVENT WILL BE TERMINATED WHEN THE TORNADO WARNING IS LIFTED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. THE LICENSEE HAS NOTIFIED | | STATE AND LOCAL OFFICIALS. | | | | **** UPDATE AT 2147 EDT ON 08/25/94 BY KENNEDY TAKEN BY ANDREWS **** | | LICENSEE TERMINATED UNUSUAL EVENT AT 2133 EDT WHEN THE TORNADO WARNING WAS | | LIFTED. THE GRID IS PRESENTLY STABLE AND THE DIESEL GENERATORS ARE | | AVAILABLE AND OPERABLE IF NEEDED. THE NRC RESIDENT INSPECTOR WILL BE | | NOTIFIED. | | | | THE LICENSEE HAS NOTIFIED STATE AND LOCAL OFFICIALS OF THE TERMINATION. | | | | HOO NOTIFIED R1DO (SHANBAKY), EO (VIRGILLIO), FEMA (BAGWELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27716 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 08/26/94 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 01:44 [ET]| |RX TYPE: [3] CE |EVENT DATE: 08/25/94 | +------------------------------------------------+EVENT TIME: 23:32[CDT]| |NRC NOTIFIED BY: ESQUIVER / WALSH |LAST UPDATE DATE: 08/26/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LOSS OF SPD, PMC, AND COLS COMPUTER SYSTEMS FOR LONGER THAN 1 HOUR - | | | | AT 2332 (CDT) ON 08/25/94, THE PLANT LOST THE SAFETY PARAMETER DISPLAY | | (SPD) SYSTEM FOR UNKNOWN REASONS. | | | | AT 2344 (CDT) ON 08/25/94, THE PLANT LOST THE PLANT MONITORING COMPUTER | | (PMC), 'A' COMPLEX, FOR UNKNOWN REASONS. THIS CAUSED A LOSS OF THE CORE | | OPERATING LIMIT SUPERVISORY (COLS) SYSTEM SINCE THE PMC, 'B' COMPLEX WAS | | INOPERABLE, AT THE TIME. | | | | TECH SPEC LCO A/S 3.2.1 AND 3.2.4 REQUIRE LICENSEE TO RESTORE THE COLS | | SYSTEM TO OPERABLE STATUS WITHIN 4 HOURS OR REDUCE POWER TO LOWER THE | | DNBR AND LINEAR HEAT RATE LEVELS TO ACCEPTABLE LIMITS. | | | | PLANT TECHNICIANS ARE TROUBLESHOOTING THE SYSTEMS. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+