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Event Notification Report for February 14, 2000

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           02/11/2000 - 02/14/2000

                              ** EVENT NUMBERS **

36665  36667  36679  36680  36681  36682  36683  36684  36685  36686  

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36665       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH                    REGION:  2  |NOTIFICATION DATE: 02/06/2000|
|    UNIT:  [1] [2] []                STATE:  GA |NOTIFICATION TIME: 18:37[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4                    |EVENT DATE:        02/06/2000|
+------------------------------------------------+EVENT TIME:        17:55[EST]|
| NRC NOTIFIED BY:  BRUCE BUTLER                 |LAST UPDATE DATE:  02/11/2000|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KERRY LANDIS         R2      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       93       Power Operation  |93       Power Operation  |
|2     N          Y       98       Power Operation  |98       Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| PUBLIC PROMPT NOTIFICATION SYSTEM INOPERABLE FOR 2 MINUTES                   |
|                                                                              |
| Due to technical difficulties in Jacksonville, Florida, the Public Prompt    |
| Notification System (NOAA weather radio) was lost at 1755 ET and was         |
| restored to service at 1757 ET.  Primary and backup system were inoperable   |
| during this period of time.                                                  |
|                                                                              |
| The NRC Resident will be notified of this event notification by the          |
| licensee.                                                                    |
|                                                                              |
| * * * UPDATE AT 1420 ON 02/11/00 BY TIM BEINKE TO JOLLIFFE * * *             |
|                                                                              |
| The licensee desires to retract this event in accordance with the guidance   |
| contained in NRC NUREG-1022 since the Public Prompt Notification System was  |
| inoperable for less than 15 minutes.                                         |
|                                                                              |
| The licensee plans to notify the NRC Resident Inspector.                     |
|                                                                              |
| The NRC Operations Officer notified the R2DO Mark Lesser.                    |
+------------------------------------------------------------------------------+

!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED  !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36667       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: DRESDEN                  REGION:  3  |NOTIFICATION DATE: 02/07/2000|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 04:28[EST]|
|   RXTYPE: [1] GE-1,[2] GE-3,[3] GE-3           |EVENT DATE:        02/07/2000|
+------------------------------------------------+EVENT TIME:        02:40[CST]|
| NRC NOTIFIED BY:  DAVE KLIMECK                 |LAST UPDATE DATE:  02/11/2000|
|  HQ OPS OFFICER:  DOUG WEAVER                  +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |TONY VEGEL           R3      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| Minimum security personnel staffing requirements not met.  Immediate         |
| compensatory actions taken upon discovery.  The licensee will notify the NRC |
| resident inspector.  Additional details of this event may be obtained by     |
| contacting the NRC operations officer.                                       |
|                                                                              |
| * * * UPDATE AT 2057 ON 02/11/00 BY CHRIS KENT TO JOLLIFFE * * *             |
|                                                                              |
| The licensee desires to retract this event since the commitments in the      |
| approved Plant Physical Security Plan had been complied with during this     |
| event.  The licensee plans to notify the NRC Resident Inspector.  The NRC    |
| Operations Officer notified the R3DO Mike Parker.  Additional details of     |
| this event retraction may be obtained by contacting the NRC Operations       |
| Officer.                                                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36679       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 02/11/2000|
|    UNIT:  [1] [2] []                STATE:  SC |NOTIFICATION TIME: 00:59[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        02/10/2000|
+------------------------------------------------+EVENT TIME:        18:50[EST]|
| NRC NOTIFIED BY:  BROWN                        |LAST UPDATE DATE:  02/11/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|10 CFR SECTION:                                 |                             |
|NLTR                     LICENSEE 24 HR REPORT  |                             |
|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                                   
+------------------------------------------------------------------------------+
| THE LICENSEE SUBMITTED A 24 HOUR OPERATING LICENSE DEVIATION REPORT.         |
|                                                                              |
| While performing the Penetration Seal Firestop Configuration verification    |
| project, engineering determined that 37 firestop penetrations are not        |
| configured in accordance with existing approved details.  Therefore, these   |
| 37 penetrations are not operable, putting the plant in a LCO action          |
| statement.  Remedial action has been taken per Selected License Commitment   |
| 16.9-5 Fire Barrier Penetrations, this action establishes hourly fire        |
| watches on each affected penetration.                                        |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36680       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 02/11/2000|
|    UNIT:  [] [2] []                 STATE:  IL |NOTIFICATION TIME: 07:13[EST]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        02/11/2000|
+------------------------------------------------+EVENT TIME:        02:58[CST]|
| NRC NOTIFIED BY:  OSELAND                      |LAST UPDATE DATE:  02/11/2000|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MICHAEL PARKER       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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       4        Startup          |4        Startup          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HPCI DECLARED INOPERABLE, PLACING THE PLANT IN A LCO ACTION STATEMENT.       |
|                                                                              |
| On 2/11/2000 at 0258 hours, HPCI low pressure operability testing was in     |
| progress following a scheduled refueling outage.  At that time, the HPCI     |
| turbine failed to roll when the motor speed changer was taken to its high    |
| speed stop. There was no change in steam flow as indicated by the main       |
| turbine bypass valve position.  The operator in attendance visually verified |
| HPCI was still on the turning gear.  The surveillance was terminated and the |
| system restored to standby lineup.  At 0341 hours, reactor pressure was      |
| reduced below 150 psig to place the reactor in a condition where HPCI was    |
| not required to be operable, and they exited the LCO at that time.           |
|                                                                              |
| The cause of this failure is under investigation.                            |
|                                                                              |
| The NRC Resident Inspector was notified.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Hospital                                         |Event Number:   36681       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG:  JASPER COUNTY HOSPITAL               |NOTIFICATION DATE: 02/11/2000|
|LICENSEE:  JASPER COUNTY HOSPITAL               |NOTIFICATION TIME: 10:45[EST]|
|    CITY:  RENSSELAER               REGION:  3  |EVENT DATE:        02/11/2000|
|  COUNTY:                            STATE:  IN |EVENT TIME:        08:45[CST]|
|LICENSE#:  13-26527-01           AGREEMENT:  N  |LAST UPDATE DATE:  02/11/2000|
|  DOCKET:                                       |+----------------------------+
|                                                |PERSON          ORGANIZATION |
|                                                |JAMES CREED          R3      |
|                                                |BRIAN SMITH          NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  ROTH                         |                             |
|  HQ OPS OFFICER:  CHAUNCEY GOULD               |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|BAAA 20.1906(d)           SURFACE CONT/ EXT RAD |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| JASPER COUNTY HOSPITAL RECEIVED A SURFACE CONTAMINATED BOX WHICH CONTAINED   |
| NUCLEAR MEDICINE.                                                            |
|                                                                              |
| A METAL AMMO BOX USED TO TRANSPORT NUCLEAR MEDICINE CONTAINED IN INDIVIDUAL  |
| PIGS WAS FOUND TO HAVE SURFACE TECHNICIUM CONTAMINATION ON THE LOCKING CLASP |
| MEASURING 604 DPM/CM2 (LIMIT IS EQUAL TO OR LESS THAN 220 DPM/CM2).  THERE   |
| WAS NO DAMAGE TO THE PIG CONTAINERS INSIDE THE AMMO BOX AND NO CONTAMINATION |
| WAS MEASURED INSIDE THE BOX.  THE SOURCE OF THE CONTAMINATION IS UNKNOWN,    |
| BUT IT COULD HAVE OCCURRED AT THE PHARMACEUTICAL COMPANY, THE TRANSPORTER OR |
| IN THE HOSPITAL LABORATORY.  HOSPITAL PERSONNEL HAVE ISOLATED THE AMMO BOX   |
| AND WILL ALLOW THE TECHNICIUM CONTAMINATION TO DECAY OFF.                    |
|                                                                              |
| (CALL THE NRC OPERATIONS OFFICER FOR A LICENSEE CONTACT TELEPHONE NUMBER.)   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36682       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MILLSTONE                REGION:  1  |NOTIFICATION DATE: 02/11/2000|
|    UNIT:  [] [2] []                 STATE:  CT |NOTIFICATION TIME: 14:32[EST]|
|   RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP           |EVENT DATE:        02/11/2000|
+------------------------------------------------+EVENT TIME:        13:46[EST]|
| NRC NOTIFIED BY:  MIKE BAIN                    |LAST UPDATE DATE:  02/11/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |HAROLD GRAY          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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     M/R        Y       96       Power Operation  |0        Hot Standby      |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| - MANUAL REACTOR TRIP FROM 96% POWER AFTER 2 CONTROL RODS DROPPED INTO THE   |
| CORE -                                                                       |
|                                                                              |
| During the performance of a tech spec surveillance test of control rod       |
| motion with Unit 2 at 100% power, one control rod dropped into the core for  |
| unknown reasons.  Control room operators reduced power.  With Unit 2 at 96%  |
| power, a second control rod dropped into the core for unknown reasons.       |
| Control room operators manually tripped Unit 2 from 96% power.  All control  |
| rods inserted completely into the core.  The auxiliary feedwater system      |
| actuated, as expected.  Control room operators manually secured the          |
| auxiliary feedwater system. Steam generator water levels are being           |
| maintained in their normal range by the main feedwater system.  Steam is     |
| being dumped to the main condenser.  No safety or relief valves lifted.      |
| Unit 2 is stable in Mode 3 (Hot Standby).  The licensee is investigating the |
| cause of the control rods dropping into the core.                            |
|                                                                              |
| The licensee notified state and local officials and the NRC Resident         |
| Inspector and plans to issue a press release.                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Fuel Cycle Facility                              |Event Number:   36683       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT   |NOTIFICATION DATE: 02/11/2000|
|   RXTYPE: URANIUM ENRICHMENT FACILITY          |NOTIFICATION TIME: 16:27[EST]|
| COMMENTS: 2 DEMOCRACY CENTER                   |EVENT DATE:        02/10/2000|
|           6903 ROCKLEDGE DRIVE                 |EVENT TIME:        23:30[EST]|
|           BETHESDA, MD 20817    (301)564-3200  |LAST UPDATE DATE:  02/11/2000|
|    CITY:  PIKETON                  REGION:  3  +-----------------------------+
|  COUNTY:  PIKE                      STATE:  OH |PERSON          ORGANIZATION |
|LICENSE#:  GDP-2                 AGREEMENT:  N  |JAMES CREED          R3      |
|  DOCKET:  0707002                              |JOSEPHINE PICCONE    NMSS    |
+------------------------------------------------+                             |
| NRC NOTIFIED BY:  RICK LARSON                  |                             |
|  HQ OPS OFFICER:  DICK JOLLIFFE                |                             |
+------------------------------------------------+                             |
|EMERGENCY CLASS:          N/A                   |                             |
|10 CFR SECTION:                                 |                             |
|NBNL                     RESPONSE-BULLETIN      |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| NRC Bulletin 91-01, 24 Hour Report - Loss of 1 of 2 Controlled Parameters    |
| (Geometry) -                                                                 |
|                                                                              |
| At 2330 on 02/10/00, the Plant Shift Superintendent (PSS) was notified that  |
| a Nuclear Criticality Safety Approval (NCSA) requirement was not being       |
| maintained in the X-705 decontamination facility.  While performing an NCS   |
| Self Assessment, facility personnel noticed an operation where requirements  |
| for the control of "Inadvertent Containers" was not being met.  The          |
| Inadvertent container was a rectangular support structure for a ventilator   |
| that was approximately 5.5 inches deep and did not have any holes or slots   |
| to provide drainage.  The critical height dimension is 1.5 inches from the   |
| bottom of the container.                                                     |
|                                                                              |
| Requirement #5 of NCSA-0705-076.A00 states, in part that modifications to    |
| inadvertent containers, where practical, shall be accomplished by drilling   |
| holes or making slots in the container to provide drainage.  This structure, |
| not having drainage holes, was a loss of one control (geometry).  The other  |
| control (concentration) was maintained.                                      |
|                                                                              |
| At the direction of the PSS, the requirements for an NCS anomalous condition |
| were established per plant procedures.  At approximately 0130 on 02/11/00,   |
| double contingency controls were reestablished.                              |
|                                                                              |
| SAFETY SIGNIFICANCE OF THE EVENT:                                            |
|                                                                              |
| The safety significance of this event is low.  The inadvertent container is  |
| an iron support structure for a ventilator that is approximately 5.5 inches  |
| deep by 24 inches wide and just over 60 inches long.  This structure is in   |
| the high bay of the X-705 building bolted to the floor under the overhead    |
| storage system.  However, there were no indications that any solution had    |
| collected in the container or that any leakage had occurred from the         |
| overhead storage in this area.   Also, data on the concentration of uranium  |
| in the overhead storage indicates that it is currently less than 500 ppm.    |
|                                                                              |
| POTENTIAL CRITICALITY PATHWAYS INVOLVED [BRIEF SCENARIO(S) OF HOW            |
| CRITICALITY COULD OCCUR]:                                                    |
|                                                                              |
| The potential pathway for a criticality is a failure of the overhead storage |
| system.  This would allow uranium bearing solution to collect in the         |
| container.  Since the container has a depth greater than the safe slab depth |
| of 1.5 inches for 100% enriched material, a criticality could occur if the   |
| collected solution's depth exceeds 1.5 inches and the uranium concentration  |
| of the solution exceeds 11,600 ppm.                                          |
|                                                                              |
| CONTROLLED PARAMETERS (MASS, MODERATION, GEOMETRY. CONCENTRATION, ETC.):     |
|                                                                              |
| The parameters being controlled are geometry (container geometry and         |
| overhead storage piping) and concentration of solution in the overhead       |
| storage.                                                                     |
|                                                                              |
| ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL (INCLUDE PROCESS     |
| LIMIT AND PER CENT WORST CASE OF CRITICAL MASS):                             |
|                                                                              |
| There was no uranium material involved with this event.  If the overhead     |
| storage were to leak, the enrichment is considered to be 100% and the form   |
| would be U02F2 solution (worst case).                                        |
|                                                                              |
| NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION   |
| OF THE FAILURES OR DEFICIENCIES:                                             |
|                                                                              |
| The geometry control of container was lost.  The NCSA requires that holes or |
| slots be added to the container to limit the height of the solution that     |
| could collect to less than 1.5 inches.                                       |
|                                                                              |
| CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEM AND WHEN EACH WAS IMPLEMENTED:   |
|                                                                              |
| Compliance was regained at 0130 on 02/11/00 when plastic has placed over the |
| container to prevent the introduction of solution.                           |
|                                                                              |
| There was no loss of hazardous or radioactive material nor radioactive or    |
| radiological contamination exposure as a result of this event.               |
|                                                                              |
| Portsmouth personnel notified the NRC Resident Inspector and the Site DOE    |
| Representative.                                                              |
|                                                                              |
| PTS-2000-009  PR-PTS-00-00829                                                |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36684       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOPER                   REGION:  4  |NOTIFICATION DATE: 02/11/2000|
|    UNIT:  [1] [] []                 STATE:  NE |NOTIFICATION TIME: 20:13[EST]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        02/11/2000|
+------------------------------------------------+EVENT TIME:        17:07[CST]|
| NRC NOTIFIED BY:  STEVE WHEELER                |LAST UPDATE DATE:  02/11/2000|
|  HQ OPS OFFICER:  DICK JOLLIFFE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA HOWELL         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                                   
+------------------------------------------------------------------------------+
| - Nebraska Game and Parks Department notified of a dead American Bald Eagle  |
| found onsite -                                                               |
|                                                                              |
| At 1707 CST on 02/11/00, a licensee employee found an American Bald Eagle    |
| under a 345 kV line on licensee property.  The licensee notified the         |
| Nebraska Game and Parks Department.  A Nebraska Game Warden reported to the  |
| site and took possession of the eagle. The warden stated that the eagle had  |
| been dead for some time.  The warden plans to notify the Fish and Wildlife   |
| Service of this incident and to send the bird to them.                       |
|                                                                              |
| The licensee notified the NRC Resident Inspector.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36685       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CALLAWAY                 REGION:  4  |NOTIFICATION DATE: 02/13/2000|
|    UNIT:  [1] [] []                 STATE:  MO |NOTIFICATION TIME: 11:11[EST]|
|   RXTYPE: [1] W-4-LP                           |EVENT DATE:        02/13/2000|
+------------------------------------------------+EVENT TIME:        07:34[CST]|
| NRC NOTIFIED BY:  ROBERT BARTON                |LAST UPDATE DATE:  02/13/2000|
|  HQ OPS OFFICER:  STEVE SANDIN                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |LINDA HOWELL         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 ON LOSS OF REACTOR COOLANT SYSTEM (RCS) FLOW          |
|                                                                              |
| THE UNIT EXPERIENCED AN AUTOMATIC REACTOR TRIP-TURBINE TRIP FROM 100% POWER  |
| DUE TO THE LOSS OF RCS FLOW CAUSED BY THE TRIP OF THE REACTOR COOLANT PUMPS  |
| (INITIALLY "B" RCP FOLLOWED BY THE "A", "C" AND "D").  FLUCTUATING GRID      |
| VOLTAGE DUE TO AN ELECTRICAL PROBLEM IN SOUTHEAST MISSOURI CAUSED THE LOSS   |
| OF THE RCPs AND THE OPERATING CIRCULATING WATER (CW) PUMPS.  DURING THE      |
| PERIOD TIME BEFORE THE RCPs WERE RESTARTED, RCS PRESSURE INCREASED CAUSING   |
| ONE (1) PRESSURIZER PORV TO LIFT AND RESEAT (SETPOINT 2335 PSIG - PRIMARY    |
| SAFETY SETPOINT IS 2485 PSIG).  A SLIGHT INCREASE IN THE PRESSURIZER RELIEF  |
| TANK PRESSURE WAS OBSERVED.  A FEEDWATER ISOLATION SIGNAL OCCURRED WITH ALL  |
| SYSTEMS FUNCTIONING AS EXPECTED INCLUDING AUTOSTART OF ALL AUXILIARY         |
| FEEDWATER PUMPS (BOTH MOTOR-DRIVEN AND THE TURBINE-DRIVEN PUMPS).  CONDENSER |
| VACUUM WAS LOST AS A RESULT OF THE CW PUMP TRIPS.  HOWEVER, TWO (2) CW PUMPS |
| WERE RESTARTED AND THE MAIN CONDENSER PLACED BACK IN SERVICE AS THE HEAT     |
| SINK.  THE LICENSEE ESTIMATES THAT THE STEAM GENERATOR ATMOSPHERIC DUMPS     |
| WERE USED FOR NO MORE THAN 20 MINUTES DURING THE PERIOD OF TIME WHEN THE     |
| MAIN CONDENSER WAS NOT AVAILABLE.  THERE IS NO INDICATION OF ANY             |
| PRIMARY-SECONDARY LEAKAGE PRIOR TO THIS EVENT. THE PLANT IS CURRENTLY STABLE |
| WITH OPERATORS RESTORING MAIN FEEDWATER.  BOTH EMERGENCY DIESELS ARE IN      |
| STANDBY AND AVAILABLE, IF NEEDED.  THE UNIT WILL REMAIN IN MODE 3 PENDING    |
| THE OUTCOME OF THE INVESTIGATION INTO THE GRID ELECTRICAL TRANSIENT.         |
|                                                                              |
| THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR.                            |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36686       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CATAWBA                  REGION:  2  |NOTIFICATION DATE: 02/13/2000|
|    UNIT:  [1] [] []                 STATE:  SC |NOTIFICATION TIME: 19:56[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        02/13/2000|
+------------------------------------------------+EVENT TIME:        18:32[EST]|
| NRC NOTIFIED BY:  J. K. McCONNELL              |LAST UPDATE DATE:  02/13/2000|
|  HQ OPS OFFICER:  LEIGH TROCINE                +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |MARK LESSER          R2      |
|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 A TURBINE TRIP FOR UNKNOWN REASONS             |
|                                                                              |
| The following text is a portion of a facsimile received from the licensee:   |
|                                                                              |
| "Unit 1 reactor trip occurred at 1832 hours on 02/13/2000.  Control room     |
| annunciators indicate that the cause of the reactor trip was a turbine trip. |
| At this time, the cause of the turbine trip is unknown.  All systems and     |
| plant responses to the reactor trip were normal."                            |
|                                                                              |
| The licensee stated that all control rods fully inserted and that all        |
| support systems functioned correctly.  None of the primary or secondary      |
| system safety relief valves lifted.  There were no emergency core cooling    |
| system actuations, and none were required.  The following three engineered   |
| safety feature actuations occurred:  turbine trip (for unknown reasons),     |
| feedwater isolation, and auxiliary feedwater automatic start.  Feedwater     |
| isolated and auxiliary feedwater automatically started as designed.          |
|                                                                              |
| The cause of the turbine trip is unknown but is currently believed to be     |
| electrical in nature.  There were no related maintenance or surveillance     |
| activities ongoing at the time of the event.                                 |
|                                                                              |
| The unit is currently stable in Mode 3 (Hot Standby).  Normal charging and   |
| letdown, pressurizer heaters and sprays, and the reactor coolant pumps are   |
| being utilized at this time for primary system level, pressure, and          |
| transport control.  Auxiliary feedwater is supplying water to the steam      |
| generators, and secondary steam is being dumped to the condenser.  The       |
| electrical grid is stable.                                                   |
|                                                                              |
| The licensee notified the NRC resident inspector.                            |
+------------------------------------------------------------------------------+