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