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Event Notification Report for March 15, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           03/14/2000 - 03/15/2000

                              ** EVENT NUMBERS **

36791  36792  36793  36794  36795  36796  

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|Power Reactor                                    |Event Number:   36791       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR         REGION:  4  |NOTIFICATION DATE: 03/14/2000|
|    UNIT:  [1] [] []                 STATE:  AR |NOTIFICATION TIME: 03:11[EST]|
|   RXTYPE: [1] B&W-L-LP,[2] CE                  |EVENT DATE:        03/14/2000|
+------------------------------------------------+EVENT TIME:        00:05[CST]|
| NRC NOTIFIED BY:  ALAN SMITH                   |LAST UPDATE DATE:  03/14/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |DAVID GRAVES         R4      |
|10 CFR SECTION:                                 |BRUCE BOGER          NRR     |
|ARPS 50.72(b)(2)(ii)     RPS ACTUATION          |                             |
|APRE 50.72(b)(2)(vi)     OFFSITE NOTIFICATION   |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     M/R        Y       82       Power Operation  |0        Hot Shutdown     |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| UNIT 1 MANUALLY TRIPPED FOLLOWING A FAILURE OF THE MAIN TURBINE GOVERNOR     |
| VALVES CONTROL SYSTEM                                                        |
|                                                                              |
| "The Unit 1 Reactor was manually tripped following a failure of the main     |
| turbine governor valves control system. This failure resulted in the main    |
| turbine governor valves inadvertently going closed.  At the time of the      |
| event, Unit 1 was at 82% power and proceeding to 100% power following the    |
| completion of maintenance outage 1P-00-2.                                    |
|                                                                              |
| "Unit 1 has been stabilized in Hot Shutdown (550 degrees F, 2125 psig, and   |
| the reactor is subcritical).  No radioactive releases have occurred nor are  |
| any planned."                                                                |
|                                                                              |
| Prior to the transient the turbine governor valve position limit was acting  |
| erratically.  All control rods fully inserted.  Following the trip, primary  |
| pressure increased to 2300 psig.  Three(3) of  eight(8)  mainsteam (MS)      |
| safeties lifted and reseated on each MS header.  Also, Bus "1H1" which       |
| supplies power to two Reactor Coolant Pumps (RCPs) was slow in transferring  |
| to the startup transformer.  This resulted in both "P32A" and P32C" RCPs     |
| tripping.  The 1H1 bus remained energized during the transient.              |
|                                                                              |
| Unit 1 is currently removing decay heat using RCPs "P32B" and P32D" (one     |
| operating in each reactor coolant loop) with steam discharging to the Main   |
| Condenser.  All safety-related equipment  including the Emergency Diesel     |
| Generators (EDGs) is available, if needed.  I&C is investigating the cause   |
| of the governor valves' control system failure and the Relay Department is   |
| evaluating the slow bus transfer.                                            |
|                                                                              |
| The licensee informed the NRC Resident Inspector and the State of Arkansas.  |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36792       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: SEQUOYAH                 REGION:  2  |NOTIFICATION DATE: 03/14/2000|
|    UNIT:  [1] [] []                 STATE:  TN |NOTIFICATION TIME: 04:01[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        03/14/2000|
+------------------------------------------------+EVENT TIME:        00:35[EST]|
| NRC NOTIFIED BY:  BILL HARRIS                  |LAST UPDATE DATE:  03/14/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |EDWARD MCALPINE      R2      |
|10 CFR SECTION:                                 |BRUCE BOGER          NRR     |
|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          N       0        Cold Shutdown    |0        Cold Shutdown    |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| MANUAL PHASE "A" AND CONTAINMENT VENT ISOLATION INITIATED DUE TO SHUTDOWN    |
| LOSS OF COOLANT ACCIDENT (LOCA).                                             |
|                                                                              |
| "Unit 1 was in Mode 5 with Cycle 10 refueling outage in progress.  At 0017   |
| on 3/14/00 with RCS temperature at 145 F and RCS pressure at 330 psig.  Unit |
| 1 entered Abnormal Operating Procedure R.02 (Shutdown LOCA) due to           |
| decreasing pressurizer level.  A manual Phase A and Containment Vent         |
| Isolation were initiated at 0035 as required by procedure. The loss of RCS   |
| coolant was initially contained in the Pressurizer Relief Tank (PRT) until   |
| the PRT rupture disc ruptured.  At 0125, AOP R.02 was completed and plant    |
| conditions were stabilized with RCS temperature at 156 F and RCS pressure at |
| 145 psig.  At present there is no RCS leakage, plant conditions are stable,  |
| and suspected cause is the RHR suction or discharge piping relief valve.     |
| Investigation is in progress."                                               |
|                                                                              |
| The transient lasted approximately 30 minutes.  The licensee suspects that   |
| when RCS pressure was lowered per the AOP, the relief valve reseated.  There |
| is no estimate of the lost RCS inventory at this time.                       |
|                                                                              |
| The licensee informed the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36793       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT      |NOTIFICATION DATE: 03/14/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 08:40[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        03/13/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        22:25[CST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  03/14/2000|
|    CITY:  PADUCAH                  REGION:  3  +-----------------------------+
|  COUNTY:  McCRACKEN                 STATE:  KY |PERSON          ORGANIZATION |
|LICENSE#:  GDP-1                 AGREEMENT:  Y  |JOHN JACOBSON        R3      |
|  DOCKET:  0707001                              |DON COOL             NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  E.G. WALKER                  |                             |
|  HQ OPS OFFICER:  STEVE SANDIN                 |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NCFR                     NON CFR REPORT REQMNT  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 24-HOUR NON-CFR REPORT INVOLVING ACTUATION OF A SAFETY SYSTEM DUE TO A VALID |
| SIGNAL                                                                       |
|                                                                              |
| "At 2225 on 03/13/00, the PSS office was notified that a primary condensate  |
| alarm was received on the C-333A position 2 North autoclave Water Inventory  |
| Control System (WICS). The WICS system is required to be operable while      |
| heating in mode 5 according to TSR 2.2.4.2.  The autoclave was checked       |
| according to the alarm response procedure, removed from service and the      |
| Water Inventory Control System was declared inoperable by the Plant Shift    |
| Superintendent. Troubleshooting was initiated and is continuing in order to  |
| determine the reason for the alarm.                                          |
|                                                                              |
| "The safety system actuation Is reportable to the NRC as required by Safety  |
| Analysis Report, section 8.9, table 1 criteria J.2, Safety System actuation  |
| due to a valid signal as a 24-hour event notification.                       |
|                                                                              |
| "The NRC resident inspector has been notified of this event."                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|General Information or Other                     |Event Number:   36794       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  DEPARTMENT OF THE ARMY               |NOTIFICATION DATE: 03/14/2000|
|LICENSEE:  DEPARTMENT OF THE ARMY               |NOTIFICATION TIME: 14:52[EST]|
|    CITY:  ROCK ISLAND              REGION:  3  |EVENT DATE:        03/13/2000|
|  COUNTY:                            STATE:  IL |EVENT TIME:        12:00[CST]|
|LICENSE#:  12-00722-06           AGREEMENT:  Y  |LAST UPDATE DATE:  03/14/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JOHN JACOBSON        R3      |
|                                                |DAVID GRAVES         R4      |
+------------------------------------------------+FRITZ STURZ          NMSS    |
| NRC NOTIFIED BY:  HAVENNER                     |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAB1 20.2201(a)(1)(i)    LOST/STOLEN LNM>1000X  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE DEPARTMENT OF THE ARMY REPORTED A CHEMICAL AGENT DETECTOR (CAD) WAS LOST |
| AT FT. HOOD, TX.                                                             |
|                                                                              |
| A M43A1 CAD CONTAINING 250 MICROCURIES OF AM-241 WAS LOST FOLLOWING A FIELD  |
| TRAINING EXERCISE  AT FT. HOOD, TX.  THE DEVICE WAS RUN OVER BY A VEHICLE ON |
| 3/1/00 AND UPON RETRIEVAL, THE PIECES WERE PLACED IN TWO OPAQUE PLASTIC BAGS |
| AND TAKEN BACK TO THE INSTALLATION WHERE IT WAS DETERMINED (ON 3/7/00) THEY  |
| HAD BEEN LOST.  IT IS BELIEVED THAT THE TWO BAGS WERE DISCARDED WITH THE     |
| TRASH IN THE ON-POST LANDFILL.  A SEARCH OF THE LANDFILL WAS IMPLEMENTED,    |
| BUT THE BAGS COULD NOT BE FOUND.  SINCE THE GENERAL PUBLIC DOES NOT HAVE     |
| ACCESS TO THIS LANDFILL, THE ARMY HAS TERMINATED ITS SEARCH.                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36795       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 03/14/2000|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 16:12[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/14/2000|
+------------------------------------------------+EVENT TIME:        13:18[EST]|
| NRC NOTIFIED BY:  UNDERWOOD                    |LAST UPDATE DATE:  03/14/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| THE PLANT HAD AN ESF ACTUATION WHILE PERFORMING A LEAK RATE TEST.            |
|                                                                              |
| While performing leak rate testing on 2E11-F041D, Drywell Pressure Sensing   |
| Line Isolation Valve, a High Drywell Pressure Signal was received resulting  |
| in the following actuations:                                                 |
|                                                                              |
| Reactor Scram Signal (RPS),(no rod motion)                                   |
| Unit 1 and Unit 2 Standby Gas Treatment System actuation,                    |
| Unit 1 Reactor Building Ventilation isolation.                               |
|                                                                              |
| Group 2 Isolation of:                                                        |
| Drywell Sump Isolation Valve (2G11-F004),                                    |
| Post Accident Sampling Valve (2E41-F121),                                    |
| Fission Product Monitor Valve (2D1 l-F072), and                              |
| Unit 1 and Unit 2 Refueling Ventilation Isolation.                           |
|                                                                              |
| Other valves did not activate on the Group 2 Isolation signal from High      |
| Drywell Pressure because they were out of service for refueling outage       |
| maintenance activities.                                                      |
|                                                                              |
| Investigation is ongoing as to the cause of this event.                      |
|                                                                              |
| All systems have been returned to normal status.                             |
|                                                                              |
| The NRC Resident Inspector will be notified.                                 |
|                                                                              |
| Refer to related event #36796.                                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36796       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 03/15/2000|
|    UNIT:  [] [2] []                 STATE:  GA |NOTIFICATION TIME: 00:58[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        03/14/2000|
+------------------------------------------------+EVENT TIME:        22:45[EST]|
| NRC NOTIFIED BY:  BRUCE BUTLER                 |LAST UPDATE DATE:  03/15/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |AL BELISLE           R2      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - ESF ACTUATIONS DURING A RELAY REPLACEMENT CAUSED BY AN ELECTRICAL SHORT  - |
|                                                                              |
|                                                                              |
| While replacing the relay for TIP withdrawal & RHR valve #2A71B-K5C in       |
| Reactor Protection System relay panel #2H11-P609, an electrician caused an   |
| electrical short which resulted in the following:                            |
|                                                                              |
| - Units 1 & 2 Standby Gas Treatment System actuation (1A, 1B, 2A and 2B      |
| trains/fans started)                                                         |
| - Units 1 & 2 Outboard [B] Reactor Building Ventilation System isolation     |
| - Units 1 & 2 Outboard [B] Refueling Floor Ventilation System isolation      |
| - Discovered Group 2 Outboard Post Accident Sampling Isolation Valve         |
| #2E41-F121 closed                                                            |
| - Discovered Group 2 Outboard Fission Product Monitor Valve #2D11-F072       |
| closed                                                                       |
|                                                                              |
| The licensee is investigating the cause of this event.                       |
|                                                                              |
| The licensee plans to return the above systems and components to normal      |
| status as soon as possible.                                                  |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
|                                                                              |
| Refer to related event #36795.                                               |
+------------------------------------------------------------------------------+