U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
04/14/1999 - 04/15/1999
** EVENT NUMBERS **
35583 35591 35592 35593 35594
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
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|Power Reactor |Event Number: 35583 |
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| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 04/12/1999|
| UNIT: [1] [2] [] STATE: AR |NOTIFICATION TIME: 16:59[EDT]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 04/12/1999|
+------------------------------------------------+EVENT TIME: 12:30[CDT]|
| NRC NOTIFIED BY: REHM |LAST UPDATE DATE: 04/14/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA SMITH R4 |
|10 CFR SECTION: | |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
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| THE PLANT HAD AN AUTOMATIC ACTUATION OF THE UNITS 1 & 2 CONTROL ROOM |
| EMERGENCY AIR RECIRCULATION FAN (VSF-9). |
| |
| THE ACTUATION OF VSF-9 WAS DUE TO EXCEEDING THE ACTUATION SETPOINT OF 154 |
| CPM FOR THE UNIT 1 CONTROL ROOM SUPPLY VENTILATION RAD MONITOR |
| (2RITS-8001A). THE EVOLUTION WHICH CAUSED THE BACKGROUND RADIATION LEVELS |
| TO EXCEED THE RAD MONITOR SETPOINT WAS TRANSPORTING A MULTI-ASSEMBLY SEALED |
| BASKET (MSB) CONTAINED IN THE MSB TRANSFER CASK (MTC) FROM THE SPENT FUEL |
| POOL AREA (ELEVATION 404) TO THE RAILROAD BAY (ELEVATION 354). PRIOR TO |
| COMMENCING THIS EVOLUTION, THE CONTROL ROOM VENTILATION SUPPLY WAS ISOLATED |
| AND IN RECIRCULATION MODE USING 2VSF-9 (UNIT 2 CONTROL ROOM EMERGENCY AIR |
| RECIRCULATION FAN). UNITS 1 AND 2 SHARE A COMMON VENTILATION SYSTEM. THE |
| 2RITS-8001A IS LOCATED OUTSIDE OF THE CONTROL ROOM, ADJACENT TO THE SPENT |
| FUEL POOL AREA. THE MOVEMENT OF THE MTC NEAR 2RITS-8001A RESULTED IN |
| INCREASED BACKGROUND RADIATION LEVELS ABOVE THE RAD MONITOR ACTUATION |
| SETPOINT. HOWEVER, THERE WAS NO INCREASE IN THE CONTROL ROOM VENTILATION |
| ACTIVITY LEVELS DUE TO THE CONTROL ROOM VENTILATION SYSTEM SUPPLY BEING |
| ISOLATED. FIVE MINUTES AFTER THE ACTUATION, THE RAD MONITOR INDICATED 300 |
| CPM. THE MONITOR PRESENTLY INDICATES THE NORMAL INDICATION OF 90 CPM. THE |
| RVSF WAS SECURED 2 MINUTES AFTER THE ACTUATION OF VSF-9. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
| |
| *** UPDATE ON 4/14/99 @ 1401 BY SCHEIDE TO GOULD *** RETRACTION |
| |
| THE LICENSEE IS RETRACTING THIS EVENT BASED ON GUIDANCE FROM NUREG 1022, REV |
| 1 WHICH LEADS TO THE CONCLUSION THAT THIS EVENT IS NOT REPORTABLE SINCE THE |
| EVENT INVOLVED THE ACTUATION OF A SINGLE ESF COMPONENT, NOT A TRAIN OR |
| SYSTEM, AND THE PURPOSE OF THE ACTUATION WAS NOT TO MITIGATE THE |
| CONSEQUENCES OF AN ACCIDENT. |
| |
| THE RESIDENT INSPECTOR WAS INFORMED. THE R4DO (LINDA SMITH) WAS NOTIFIED. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35591 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 04/14/1999|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 04:32[EDT]|
| RXTYPE: [1] GE-4 |EVENT DATE: 04/14/1999|
+------------------------------------------------+EVENT TIME: 01:28[CDT]|
| NRC NOTIFIED BY: FRED SCHIZAS |LAST UPDATE DATE: 04/14/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA SMITH R4 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| - RCIC SYSTEM DECLARED INOPERABLE DUE TO FAILED SYSTEM COOLING VALVE DURING |
| A TEST - |
| |
| AT 0128 CDT ON 04/14/99, THE LICENSEE DECLARED THE REACTOR CORE ISOLATION |
| COOLING (RCIC) SYSTEM INOPERABLE DUE TO THE FAILURE OF THE RCIC SYSTEM |
| COOLING VALVE, #RCIC-MO-132. WHEN THE VALVE CONTROL SWITCH WAS PLACED IN |
| THE CLOSE POSITION IN ORDER TO RECORD THE VALVE STROKE TIME DURING THE RCIC |
| POWER OPERATED VALVE OPERABILITY SURVEILLANCE TEST, THE VALVE MOVED TO THE |
| INTERMEDIATE POSITION AND STOPPED. STATION OPERATORS VERIFIED THAT THE |
| VALVE WAS NOT CLOSED AND ISOLATED THE RCIC SYSTEM STEAM SUPPLY AND SUCTION |
| AND DISCHARGE PATHS IN ORDER TO PREVENT SYSTEM INITIATION, EVIDENCE |
| PRESERVATION, AND EXCESSIVE CYCLING OF THE BAROMETRIC CONDENSER PUMP. |
| STATION OPERATORS ALSO VERIFIED THAT THE HIGH PRESSURE COOLANT INJECTION |
| SYSTEM WAS OPERABLE. |
| |
| TECH SPEC LCO A/S 3.5.3.A REQUIRES THE LICENSE TO RESTORE THE RCIC SYSTEM TO |
| OPERABLE STATUS WITHIN 14 DAYS OR SHUT THE PLANT DOWN. |
| |
| STATION OPERATORS ARE INVESTIGATING THE CAUSE OF THE VALVE FAILURE AND PLAN |
| TO REPAIR THE VALVE. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
+------------------------------------------------------------------------------+
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|Power Reactor |Event Number: 35592 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/14/1999|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 06:50[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/14/1999|
+------------------------------------------------+EVENT TIME: 04:33[CDT]|
| NRC NOTIFIED BY: PAT HABEL |LAST UPDATE DATE: 04/15/1999|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN JACOBSON R3 |
|10 CFR SECTION: | |
|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 85 Power Operation |0 Hot Standby |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - AUTO Rx TRIP FROM 85% POWER DUE TO MAIN GENERATOR FAULT FOR UNKNOWN |
| REASONS - |
| |
| AT 0433 CDT ON 04/14/99, UNIT 2 AUTOMATICALLY TRIPPED FROM 85% POWER DUE TO |
| A MAIN GENERATOR TRIP CAUSED BY A MAIN GENERATOR FAULT FOR UNKNOWN REASONS. |
| ALL CONTROL RODS INSERTED COMPLETELY. BOTH TRAINS OF THE AUXILIARY |
| FEEDWATER SYSTEM ACTUATED TO RESTORE STEAM GENERATOR WATER LEVELS TO NORMAL. |
| NO SAFETY OR RELIEF VALVES LIFTED. STEAM IS BEING DUMPED TO THE MAIN |
| CONDENSER. ALL SYSTEMS FUNCTIONED AS DESIGNED. |
| |
| UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). THE LICENSEE IS INVESTIGATING THE |
| CAUSE OF THE MAIN GENERATOR FAULT. |
| |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. |
| |
| * * * UPDATE AT 0408 ON 04/15/99 BY JOLLIFFE * * * |
| |
| THE AUTOMATIC REACTOR TRIP WAS CAUSED BY A PROBLEM WITH A MAIN GENERATOR GIX |
| GROUND FAULT RELAY. THE LICENSEE HAS BYPASSED THE RELAY AND RESTARTED UNIT |
| 2. THE LICENSEE IS CONTINUING TO INVESTIGATE THE ROOT CAUSE OF THE REACTOR |
| TRIP. |
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+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 35593 |
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| REP ORG: COGEMA MINING INC. |NOTIFICATION DATE: 04/14/1999|
|LICENSEE: COGEMA MINING INC. |NOTIFICATION TIME: 12:43[EDT]|
| CITY: REGION: 4 |EVENT DATE: 04/12/1999|
| COUNTY: CAMPBELL STATE: WY |EVENT TIME: 14:00[MDT]|
|LICENSE#: SUA-1341 AGREEMENT: N |LAST UPDATE DATE: 04/14/1999|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA SMITH R4 |
| |TOM ANDREWS R4 |
+------------------------------------------------+CHARLES MILLER IRO |
| NRC NOTIFIED BY: VASELIN |KEVIN RAMSEY EO NMSS |
| HQ OPS OFFICER: CHAUNCEY GOULD |JOE STAMBAUGH DOE |
+------------------------------------------------+STORER FEMA |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
| | |
| | |
| | |
| | |
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EVENT TEXT
+------------------------------------------------------------------------------+
| A WELLFIELD INJECTION SOLUTION SPILL OCCURRED IN MINE UNIT 6 OF THE |
| CHRISTENSEN MINE IN CAMPBELL COUNTY, WY. |
| |
| THE SPILL, WHICH WAS ESTIMATED TO BE 32,400 GALLONS WITH A URANIUM |
| CONCENTRATION OF 0.8mg/l, IS THE RESULT OF A CASING FAILURE ON INJECTION |
| WELL 6V27-1. THE SPILL WAS REPORTED SINCE IT IS GREATER THAN 10,000 |
| GALLONS, WHICH IS CONSIDERED SIGNIFICANT FROM AN OPERATIONS STANDPOINT. |
| |
| THE SOLUTION DOES NOT POSE A HEALTH OR ENVIRONMENTAL HAZARD DUE TO ITS LOW |
| CONCENTRATION OF URANIUM. HOWEVER, THE SPILL DID ENTER A NEARBY DRAW WHICH |
| WAS FLOWING AT AN ESTIMATE 1-2 CFM WITH SNOW MELT. THUS THE SOLUTION MIGHT |
| HAVE LEFT THE NRC PERMITTED AREA IN A HIGHLY DILUTED STREAM. LINCH, WY. , |
| 15 MILES TO THE SOUTHEAST, IS THE NEAREST COMMUNITY. |
| |
| INJECTION WELL 6V27-1 WAS SHUT DOWN AND WILL NOT BE USED UNTIL THE WELL |
| CASING CAN BE REPAIRED. A SOIL SAMPLE HAS BEEN COLLECTED AT THE SPILL |
| LOCATION AND WILL BE ANALYZED FOR Ra-226 TO DETERMINE IF SOIL CLEAN-UP IS |
| NEEDED. |
| |
| HOO NOTE: SEE SIMILAR EVENTS #35524 AND #35542 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35594 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/14/1999|
| UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 18:40[EDT]|
| RXTYPE: [1] CE |EVENT DATE: 04/14/1999|
+------------------------------------------------+EVENT TIME: 16:52[CDT]|
| NRC NOTIFIED BY: CHRISTENSEN |LAST UPDATE DATE: 04/14/1999|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LINDA SMITH R4 |
|10 CFR SECTION: | |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| THE LICENSEE NOTIFIED THE NEBRASKA STATE ENVIRONMENTAL AGENCY THAT THEY |
| EXCEEDED THEIR NPDES DISCHARGE LIMITS FOR HYDRAZINE. |
| |
| THE HYDRAZINE DISCHARGE AT OUTFALL 001 (CIRCULATING WATER DISCHARGE) WAS IN |
| EXCESS OF THEIR NPDES (NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM) |
| DISCHARGE LIMIT OF 2 PPB. THE MEASURED DISCHARGE RATE AT THE OUTFALL WAS 3 |
| PPB, BUT THERE WAS NO NET INCREASE IN HYDRAZINE DISCHARGE CONCENTRATION FROM |
| THE SITE SINCE UPSTREAM RIVER CONCENTRATION IS ALSO 3 PPB. |
| |
| THE RESIDENT INSPECTOR WAS NOTIFIED. |
| |
| HOO NOTE: SEE SIMILAR EVENTS #35524 AND #35542. |
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