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Event Notification Report for August 6, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           08/05/1999 - 08/06/1999

                              ** EVENT NUMBERS **

35925  35992  35993  35994  35995  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
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|General Information or Other                     |Event Number:   35925       |
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| REP ORG:  TVA FOSSIL POWER GROUP               |NOTIFICATION DATE: 07/16/1999|
|LICENSEE:  TVA FOSSIL POWER GROUP               |NOTIFICATION TIME: 15:41[EDT]|
|    CITY:  CHATTANOOGA              REGION:  2  |EVENT DATE:        07/11/1999|
|  COUNTY:  HAMILTON                  STATE:  TN |EVENT TIME:        18:00[EDT]|
|LICENSE#:                        AGREEMENT:  Y  |LAST UPDATE DATE:  08/05/1999|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |ANN BOLAND           R2      |
|                                                |JOHN GREEVES         NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  MARCIA COOPER                |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| TENNESSEE VALLEY AUTHORITY (TVA) TESTING AND MAINTENANCE DIVISION LOCATED IN |
| CHATTANOOGA, TN, REPORTED THAT A HAND-HELD X-MET ANALYZER CONTAINING 40      |
| MILLICURIES OF IRON-55 AND 10 MILLICURIES OF CADMIUM-109 WAS INADVERTENTLY   |
| LEFT UNATTENDED ON A LOADING DOCK BETWEEN APPROXIMATELY 1000-1100 EDT ON     |
| 07/10/99 THROUGH 1800-2000 EDT ON 07/11/99.   THERE WAS NO INDICATION OF     |
| TAMPERING, CONTAMINATION, OR PERSONNEL OVEREXPOSURE INVOLVED.   THIS DEVICE  |
| IS USED FOR METAL IDENTIFICATION AND FALLS UNDER A GENERAL LICENSE.  THIS    |
| REPORT WAS CONSERVATIVELY MADE UNDER 10 CFR 20.2201(a).                      |
|                                                                              |
| ******************** UPDATE AT 1627 ON 08/05/99 FROM MARCIA COOPER TO        |
| TROCINE ********************                                                 |
|                                                                              |
| TVA Fossil Power Group is retracting this event notification based upon      |
| telephone conversations between the General Manager of the Maintenance and   |
| Testing Services Group (Marcia Cooper) and an NRC Region 2 representative    |
| (Mark Lesser).  The interpretation of the regulation was intended to require |
| reporting of missing licensed material.  Although there was a temporary loss |
| of control of generally licensed material, the material had already been     |
| recovered and was in the licensee's possession when the initial report was   |
| made.                                                                        |
|                                                                              |
| The NRC operations officer notified the R2DO (Fredrickson) and NMSS EO       |
| (Shankman).                                                                  |
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|Power Reactor                                    |Event Number:   35992       |
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| FACILITY: PILGRIM                  REGION:  1  |NOTIFICATION DATE: 08/05/1999|
|    UNIT:  [1] [] []                 STATE:  MA |NOTIFICATION TIME: 12:45[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        08/05/1999|
+------------------------------------------------+EVENT TIME:        09:47[EDT]|
| NRC NOTIFIED BY:  JOHN HOUSE                   |LAST UPDATE DATE:  08/05/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |RICHARD BARKLEY      R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR SCRAM DUE TO A MAIN TURBINE TRIP ON MOISTURE SEPARATOR     |
| HIGH LEVEL DUE TO A CONTROLLER MALFUNCTION                                   |
|                                                                              |
| At 0947, the unit automatically scrammed from 100% power due to a main       |
| turbine trip.  All control rods fully inserted.  The main turbine trip       |
| resulted from moisture separator high level due to a controller malfunction. |
| Following the reactor scram, reactor pressure vessel level decreased to less |
| than 12", and preliminary investigations have shown that all required        |
| engineered safety feature (ESF) actuations functioned as expected.  The ESF  |
| actuations included a full reactor scram, the scram function of the          |
| hydraulic control units, a reactor building isolation, a standby gas         |
| treatment system initiation, a Group II (miscellaneous containment)          |
| isolation, and a Group VI (reactor water cleanup) isolation.  The licensee   |
| is still investigating this event, but stated that there may have been a     |
| momentary safety relief valve actuation on the main turbine trip.  The       |
| safety relief valve is closed at this time.                                  |
|                                                                              |
| The only problem following the scram was that the 'C' source range monitor   |
| would not drive into the core.  This was the result of a blown fuse, and it  |
| has been rectified.                                                          |
|                                                                              |
| The unit is currently stable in Hot Shutdown.   Steam is being dumped to the |
| main condenser, and normal feedwater is supplying water to the reactor       |
| vessel.   The recirculation pumps are operating.  There were no unusual      |
| radiological releases during or after this event, and there were no safety   |
| injections or emergency core cooling system actuations.   There was no loss  |
| of offsite power, and there were no emergency diesel generator actuations.   |
|                                                                              |
| The licensee notified the NRC resident inspector and plans to notify the     |
| state tomorrow.                                                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35993       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PRAIRIE ISLAND           REGION:  3  |NOTIFICATION DATE: 08/05/1999|
|    UNIT:  [1] [2] []                STATE:  MN |NOTIFICATION TIME: 14:54[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        08/05/1999|
+------------------------------------------------+EVENT TIME:        12:50[CDT]|
| NRC NOTIFIED BY:  BRAD ELLISON                 |LAST UPDATE DATE:  08/05/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK RING            R3      |
|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  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| INOPERABILITY OF BOTH CONTROL ROOM SPECIAL VENTILATION SYSTEM TRAINS DUE TO  |
| A BROKEN DOOR LATCH MECHANISM                                                |
|                                                                              |
| At 1250 CDT, door 158 (the entry door to the 122 control room/chiller room)  |
| was identified as having a broken latch mechanism, and the broken latch      |
| resulted in a breech of the control room special ventilation system such     |
| that both trains were considered to be inoperable.   Door 158 was returned   |
| to an operable status at 1335 CDT (45 minutes after discovery of the         |
| problem) following maintenance repairs on the latch mechanism.  Therefore,   |
| the 1-hour limiting condition for operation action statement for Technical   |
| Specification 3.13.a.1 was met.                                              |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35994       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK               REGION:  4  |NOTIFICATION DATE: 08/05/1999|
|    UNIT:  [1] [] []                 STATE:  KS |NOTIFICATION TIME: 15:32[EDT]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        08/05/1999|
+------------------------------------------------+EVENT TIME:        12:58[CDT]|
| NRC NOTIFIED BY:  SHANE FERGUSON               |LAST UPDATE DATE:  08/05/1999|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TOM STETKA           R4      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     A/R        Y       100      Power Operation  |0        Hot Standby      |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| AUTOMATIC REACTOR TRIP DUE TO CLOSURE OF THE 'D' STEAM GENERATOR FEEDWATER   |
| REGULATION VALVE                                                             |
|                                                                              |
| At 1258 CDT, an automatic reactor trip occurred due to the failure of the    |
| 'D' steam generator feedwater regulation valve.  The valve failed closed,    |
| and steam generator level decreased to the reactor trip setpoint of 23%.     |
| The minimum steam generator level was approximately 20%.  The unit also      |
| received a feedwater isolation and auxiliary feedwater actuation (both       |
| motor-driven and turbine-driven) due to the low-low steam generator levels.  |
| The licensee stated that these were expected for this event.  All control    |
| rods fully inserted, and all safety equipment performed as designed.  One    |
| cooldown steam dump valve failed to fully close, and it was isolated to      |
| allow automatic control of reactor coolant system (RCS) temperature using    |
| the remaining cooldown valves.  The licensee stated that there was not an    |
| excessive cooldown and that RCS temperature decreased to 553 F.  None of    |
| the primary safety relief valves lifted.  Secondary (atmospheric) relief     |
| valves lifted and reseated, and there has been no history of steam generator |
| tube leakage.  There were no radiological releases.                          |
|                                                                              |
| The licensee's investigation is currently in progress, and it is currently   |
| believed that the valve failure may have been the result of an electronic    |
| problem.  The controller for this valve had a 0% output while the others had |
| 100% output.  There were no maintenance or surveillance activities           |
| associated with the 'D' steam generator feedwater regulation valve ongoing   |
| at the time of the event.  The licensee stated that there was nothing that   |
| was unusual or not understood.                                               |
|                                                                              |
| The unit is currently stable in Hot Standby with the RCS at approximately    |
| 559 F and 2,235 psi, steam generator levels at approximately 40%, and       |
| pressurizer level at 28%.  Normal charging and letdown, pressurizer heaters  |
| and sprays, and the reactor coolant pumps are being utilized for primary     |
| system level, pressure, and transport control.  Secondary steam is being     |
| dumped to the main condenser, and auxiliary feedwater is supplying water to  |
| the steam generators.  Grid stability is good, and all normal power feeds    |
| are available.                                                               |
|                                                                              |
| The licensee notified the NRC resident inspector and the applicable state    |
| and county agencies.                                                         |
|                                                                              |
| ***************** UPDATE AT 1749 EDT ON 08/05/99 FROM SHANE FERGUSON TO      |
| TROCINE *****************                                                    |
|                                                                              |
| The licensee plans to issue a media/press release.  The cause of the problem |
| was identified to be a failed valve controller circuitry card.  The unit may |
| be restarted as early as tonight between 2100 CDT and 2200 CDT.              |
|                                                                              |
| The licensee plans to notify the NRC resident inspector.  The NRC operations |
| officer notified the R4DOs (Stetka and Pellet).                              |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   35995       |
+------------------------------------------------------------------------------+
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| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 08/05/1999|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 20:22[EDT]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        08/05/1999|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        17:38[EDT]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  08/05/1999|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |MARK RING            R3      |
|  DOCKET:  0707002                              |SUSAN SHANKMAN       NMSS    |
+------------------------------------------------+CHARLES MILLER       IRO     |
| NRC NOTIFIED BY:  RON CRABTREE                 |                             |
|  HQ OPS OFFICER:  LEIGH TROCINE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
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                                   EVENT TEXT                                   
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| NOTIFICATION TO ANOTHER GOVERNMENT AGENCY (4-HOUR REPORT)                    |
|                                                                              |
| The following text is a portion of a facsimile received from Portsmouth:     |
|                                                                              |
| "At 1738 hours on 08/05/99, it was determined that a Nuclear Criticality     |
| Safety Approval (NCSA) requirement was violated in the X-705 West Annex      |
| which is a Department of Energy (DOE) regulated area of the PORTS site.      |
| This event was reportable to DOE as a loss of one (1) NCSA control.  This    |
| notification to another government agency is reportable to the NRC as a      |
| 4-hour notification report."                                                 |
|                                                                              |
| Portsmouth personnel notified the NRC resident inspector and the DOE site    |
| representative.                                                              |
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