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 THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!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. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021