U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/18/94 - 07/19/94 ** EVENT NUMBERS ** 27545 27546 27547 27548 27549 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27545 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/18/94 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 09:32 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/18/94 | +------------------------------------------------+EVENT TIME: 07:20[CDT]| |NRC NOTIFIED BY: JERRY LIZALEK |LAST UPDATE DATE: 07/18/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |B.J.HOLT 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 Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM INADVERTENTLY RENDERED | | INOPERABLE DURING MAINTENANCE WORK. | | | | UNIT 2 HPCI SYSTEM WAS INADVERTENTLY MADE INOPERABLE ON 7/15/94 DUE TO | | MAINTENANCE BEING PERFORMED ON THE INCORRECT UNIT. UNIT 2 HPCI WAS | | INOPERABLE FOR APPROXIMATELY 20 MINUTES. | | | | DURING A SYSTEM WALKDOWN PERFORMED ON 7/18/94 AT 0720 CDT, IT WAS NOTICED | | THAT THE PIPE PLUGS (OIL DRAIN PLUGS) ON THE UNIT 2 HPCI BOOSTER PUMP | | BEARINGS WERE LEAKING. A CLOSE INSPECTION SHOWED THAT THE PLUGS HAD BEEN | | RECENTLY CHANGED. DISCUSSIONS WITH THE UNIT 3 OUTAGE PERSONNEL REVEALED | | THAT A MAINTENANCE WORK TICKET FOR CHANGEOUT OF THE UNIT 3 HPCI BOOSTER | | PUMP DRAIN PLUG HAD BEEN RECENTLY WORKED. FURTHER INVESTIGATION DETERMINED | | THAT THE UNIT 2 HPCI BOOSTER PUMP BEARING DRAIN PLUGS WERE INADVERTENTLY | | REPLACED DURING THE UNIT 3 HPCI MAINTENANCE WORK. | | | | THE UNIT 2 HPCI BOOSTER PUMP BEARING DRAIN PLUGS WERE IMMEDIATELY TIGHTENED | | AND ALL BEARING OIL LEVELS WERE VERIFIED AS NORMAL. THE UNIT 2 HPCI SYSTEM | | IS CONSIDERED OPERABLE AND WAS CONSIDERED OPERABLE EVEN WITH THE MINOR OIL | | LEAK AT THE BEARING PLUGS. THE HPCI SYSTEM WAS ONLY INOPERABLE DURING THE | | ACTUAL CHANGEOUT OF THE PLUGS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 27546 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COGEMA MINING INCORPORATED |NOTIFICATION DATE: 07/18/94 | | CITY: CASPER REGION: 4 |NOTIFICATION TIME: 17:37 [ET]| | COUNTY: JOHNSON STATE: WY |EVENT DATE: 07/14/94 | |LICENSE#: SUA1341 AGREEMENT: N |EVENT TIME: 20:00[MDT]| | DOCKET: |LAST UPDATE DATE: 07/18/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WILLIAM JOHNSON RDO | | |MALCOLM KNAPP EO | +------------------------------------------------+ | |NRC NOTIFIED BY: DONNA WICHERS | | |HQ OPS OFFICER: JOSEPH SEBROSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COGEMA MINING INCORPORATED OF MILLS, WYOMING, IS MAKING A REPORT DUE TO A | | SPILL OF APPROXIMATELY 2500 GALLONS OF RECOVERY SOLUTION AT ITS CHRISTENSEN | | RANCH FACILITY (AN IN-SITU LEACH MINE). | | | | THE MINE IS LOCATED IN JOHNSON COUNTY APPROXIMATELY 90 MILES NORTH OF | | CASPER, WYOMING. AT APPROXIMATELY 20:00 MDT ON 7/14/94, THE LICENSEE HAD A | | SPILL OF RECOVERY SOLUTION FROM ONE OF THE RECOVERY WELLS IN MINE UNIT #4. | | THE SPILL AMOUNTED TO APPROXIMATELY 2500 GALLONS OF RECOVERY SOLUTION WITH | | A GRADE OF 230 PPM OF U-3O8. THE SPILL ORIGINATED FROM THE TOP OF A | | WELLHEAD AND WAS DUE TO A LOOSE FITTING. THE SPILLED SOLUTION SOAKED INTO | | THE GROUND IMMEDIATELY ADJACENT TO THE WELLHEAD. THE LICENSEE IS IN THE | | PROCESS OF TAKING SOIL SAMPLES TO DETERMINE THE IMPACT TO THE ENVIRONMENT. | | THE WELLHEAD WAS REPAIRED AND HAS BEEN RETURNED TO SERVICE. | | | | THE COMPANY HAS A LICENSE CONDITION (#36) WHICH REQUIRES THE LICENSEE TO | | MAINTAIN A LOG OF ALL SIGNIFICANT SOLUTION SPILLS AND TO NOTIFY THE NRC BY | | TELEPHONE WITHIN 48 HOURS OF A FAILURE WHICH MAY HAVE A RADIOLOGICAL IMPACT | | ON THE ENVIRONMENT. THE LICENSEE IS STILL IN THE PROCESS OF DETERMINING IF | | THIS SPILL MEETS THE REPORTABILITY REQUIREMENT AND WILL BE DISCUSSING THE | | ISSUE FURTHER WITH THE NRC. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27547 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 07/18/94 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 18:18 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 07/18/94 | +------------------------------------------------+EVENT TIME: 15:50[EDT]| |NRC NOTIFIED BY: ROBERT JOYNER |LAST UPDATE DATE: 07/18/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNANALYZED SINGLE FAILURE IDENTIFIED IN ONE TRAIN OF THE EMERGENCY SERVICE | | WATER SYSTEM. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "AT 1550 ON 7/18/94, AN UNANALYZED SINGLE FAILURE WAS IDENTIFIED IN ONE | | TRAIN OF THE EMERGENCY SERVICE WATER (ESW) SYSTEM THAT COULD PREVENT THE | | HIGH HEAD CHARGING/SI PUMPS (CSIPS) FROM PERFORMING THEIR SAFETY FUNCTION | | DUE TO INADEQUATE OIL COOLING. SPECIFICALLY, IF THE 'A' TRAIN RETURN VALVE | | TO THE AUXILIARY RESERVOIR FAILED TO OPEN, A RECIRCULATION PATH WOULD | | DEVELOP BETWEEN THE 'A' ESW DISCHARGE HEADER AND THE 'B' ESW SUPPLY HEADER | | THROUGH A TRAIN CROSS CONNECT AT THE INLET TO THE CSIP OIL COOLERS. | | ADEQUATE ESW FLOW WOULD STILL BE DELIVERED TO THE 'B' CSIP BUT AT AN | | ELEVATED TEMPERATURE. INADEQUATE COOLING OF THE 'B' CSIP OIL COULD RESULT. | | THE 'A' CSIP WOULD HAVE NO COOLING FLOW DUE TO THE ISOLATED RETURN PATH. | | | | THE TRAIN CROSS CONNECT HAS BEEN CLOSED, AND THIS SCENARIO IS NO LONGER | | CREDIBLE. THE CONSEQUENCES OF A SIMILAR FAILURE DO NOT APPLY TO THE 'B' | | TRAIN OF ESW DUE TO DIFFERENCES IN SYSTEM CONFIGURATION. THE LICENSEE IS | | CONTINUING TO EVALUATE THE AFFECTS OF ELEVATED TEMPERATURE FLOW THROUGH THE | | 'B' CSIP OIL COOLERS." END OF TEXT. | | | | THE LICENSEE CONSIDERS BOTH TRAINS OF SI PUMPS OPERABLE. THE PROBLEM WAS | | IDENTIFIED BY THE LICENSEE'S ENGINEERS DURING A REVIEW OF SURVEILLANCE TEST | | DATA FOR THE ESW SYSTEM. THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27548 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 07/18/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:56 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 07/18/94 | +------------------------------------------------+EVENT TIME: 18:15[EDT]| |NRC NOTIFIED BY: VANBLARCON |LAST UPDATE DATE: 07/18/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TECH SPEC REQUIRED SHUTDOWN DUE TO INADEQUATE SEISMIC SUPPORTS FOR ECCS | | RELAYS. | | | | DURING A SEISMIC QUALIFICATION INSPECTION IT WAS DETERMINED THAT RELAY | | PANELS ER8A AND ER8B DO NOT MEET DESIGN BASIS CRITERIA. THE PANELS DO NOT | | MEET THIS CRITERIA BECAUSE THE EXISTING SEISMIC SUPPORTS ARE INADEQUATE TO | | PROTECT THE PANELS AND TO PROTECT THE RELAYS INSIDE THE PANELS DURING A | | DESIGN BASIS SEISMIC EVENT. THE PANELS CONTAIN RELAYS AND WIRING | | ASSOCIATED WITH THE CONTAINMENT SPRAY AND THE AUTOMATIC DEPRESSURIZATION | | SYSTEMS. CONSEQUENTLY THESE SYSTEMS HAVE BEEN DECLARED INOPERABLE AND THE | | PLANT HAS COMMENCED A SHUTDOWN PER TECH SPECS 3.4.C.7 AND 3.4.B.3. THE | | PLANT IS CURRENTLY AT 96% POWER AND TECH SPECS REQUIRE THE PLANT TO BE COLD | | SHUTDOWN CONDITION WITHIN 30 HOURS. | | | | THE LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27549 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 07/18/94 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 22:02 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 07/18/94 | +------------------------------------------------+EVENT TIME: 21:00[EDT]| |NRC NOTIFIED BY: GLEN DISHONG |LAST UPDATE DATE: 07/18/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 Y 88 POWER OPERATION | 88 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE DUE TO A | | FAILED QUARTERLY SURVEILLANCE TEST. | | | | WHILE PERFORMING A NORMALLY SCHEDULED QUARTERLY SURVEILLANCE TEST THE UNIT | | 2 HPCI SYSTEM FAILED TO ACHIEVE DESIGN SPEED AND FLOW. THE TECH SPEC | | REQUIRED SPEED IS 4000 RPM. DURING THE TEST THE HPCI TURBINE SPEED | | OSCILLATED BETWEEN APPROXIMATELY 500 TO 1500 RPM. THE LICENSEE IS | | INVESTIGATING THE CAUSE OF THE PROBLEM. ALL OTHER ECCSs AND THE RCIC | | SYSTEM ARE OPERABLE AT THIS TIME. THE LICENSEE HAS ENTERED A 7 DAY LCO DUE | | TO HPCI BEING DECLARED INOPERABLE. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+