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Event Notification Report for April 15, 1999

                    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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!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  |
|                                                   |                          |
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                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.                                                                        |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   35593       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   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.                             |
+------------------------------------------------------------------------------+