Event Notification Report for September 5, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
09/01/2000 - 09/05/2000
** EVENT NUMBERS **
37281 37282 37283 37284 37285 37286 37287 37288 37289
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37281 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 08/31/2000|
| UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 21:32[EDT]|
| RXTYPE: [1] GE-6 |EVENT DATE: 08/31/2000|
+------------------------------------------------+EVENT TIME: 17:47[CDT]|
| NRC NOTIFIED BY: TIEDEMANN |LAST UPDATE DATE: 09/01/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH R3 |
|10 CFR SECTION: | |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT ENTERED 72 HOUR LCO ACTION STATEMENT WHEN DIVISION III DIESEL |
| GENERATOR WAS DECLARED INOPERABLE |
| |
| During performance of Fire Protection Surveillance 9337.81 (performs a |
| functional check of the Division III Diesel Generator (DG) Carbon Dioxide |
| (CO2) system operation), the Division III DG ventilation system tripped |
| during restoration. Electrical Maintenance personnel were performing a |
| functional check of the Division III DG room thermal detectors when the |
| panel reset push button was depressed. The anticipated resets did not occur |
| and the decision was made to restore the system to a safe condition. During |
| restoration, a sticking relay prevented restoration of the Division III DG |
| ventilation system. The relay has been reset and the ventilation system |
| restored. |
| |
| Division III DG was declared INOPERABLE at 1747 and the plant entered LCO |
| 3.8.1. |
| Action B.1- Perform 9082.01 within 1 hour and every 8 hours thereafter. |
| Action B.2- Declare required features supported by Division Ill DG inop when |
| the redundant required features are inop, within 4 hours. |
| Action B.3.1- Determine Operable DG are not inop due to common cause failure |
| within 24 hours - This action -completed. |
| Action B.4- Restore Div 3 DG to Operable within 72 hrs. |
| Division Ill DG was declared OPERABLE at 1813 and the LCO was exited. |
| |
| The NRC Resident Inspector was notified.. |
| |
| * * * UPDATE ON 09/01/00 @ 1400 BY SHELTON TO GOULD * * * |
| |
| The time the diesel became inoperable was 1420 but it was not declared |
| inoperable until 1747. This event is being reported pursuant to 10CFR50.72 |
| (b)(2)(iii)(D) as a condition that alone could have prevented the |
| fulfillment of the High Pressure Core Spray (HPCS) system, a single-train |
| safety system needed to mitigate the consequences of an accident, since the |
| Div. 3 DG is an essential support system for the HPCS system needed to |
| mitigate a small break LOCA concurrent with a loss of offsite power. |
| |
| The NRC Resident Inspector will be notified. |
| |
| The Reg 3 RDO (Leach) was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Other Nuclear Material |Event Number: 37282 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: ENGELHARDT & ASSOCIATES |NOTIFICATION DATE: 09/01/2000|
|LICENSEE: ENGELHARDT & ASSOCIATES |NOTIFICATION TIME: 10:09[EDT]|
| CITY: MADISON REGION: 3 |EVENT DATE: 06/12/2000|
| COUNTY: STATE: WI |EVENT TIME: [CDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 09/01/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |MELVYN LEACH R3 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: SUSAN ENGELHARDT | |
| HQ OPS OFFICER: STEVE SANDIN | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|BAE1 20.2202(b)(1) PERS OVEREXPOSURE | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AN EMPLOYEE OF A RADIATION CONSULTING FIRM MAY HAVE RECEIVED A PERSONNEL |
| OVEREXPOSURE |
| |
| ENGELHARDT & ASSOCIATES, INC. WAS HIRED BY SOUTHEAST MISSOURI STATE |
| UNIVERSITY LOCATED IN CAPE GIRARDEAU, MO. TO ASSESS AND UPGRADE THE |
| UNIVERSITY'S RADIATION SAFETY PROGRAM. SEVERAL YEARS BEFORE THE UNIVERSITY |
| INFORMED THE NRC THAT A COUPLE OF AMERICIUM-241 SOURCES HAD BEEN REMOVED. |
| DURING AN NRC RIII INSPECTION LATE LAST YEAR, THE SOURCES WERE FOUND ON |
| CAMPUS. DURING THE CONSULTANTS ASSESSMENT, HE DISCOVERED THAT ONE OF THE |
| SOURCES HAD BEEN SPILLED (LIQUID FORM) CAUSING A LARGER PROBLEM THAN |
| INITIALLY BELIEVED. THE EMPLOYEE'S UPTAKE WAS DETERMINED BY ARGONNE |
| NATIONAL LAB TO BE ON THE ORDER OF 9 REM CUMULATIVE DOSE EQUIVALENT. NRC |
| REGION III (WRIGHT, JORGENSEN) WAS INFORMED BY ENGELHARDT. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37283 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 09/01/2000|
| UNIT: [1] [] [] STATE: GA |NOTIFICATION TIME: 12:20[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/01/2000|
+------------------------------------------------+EVENT TIME: 11:30[EDT]|
| NRC NOTIFIED BY: UNDERWOOD |LAST UPDATE DATE: 09/01/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN 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 |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| PLANT HAD CLOSURE OF THE POST ACCIDENT SAMPLING SYSTEM INBOARD PRIMARY |
| CONTAINMENT ISOLATION VALVE |
| |
| During performance of Reactor Building Isolation LSFT (34SV-SUV-027-1S), |
| 1E41-F122, Post Accident Sampling System Inboard PCIV, failed closed between |
| approximately 1145 and 1230 on 08/31/00. 1E41-H22 was verified to be open at |
| approximately 1145 following completion of channel A performance test |
| (section 7.2). After returning from lunch break, operators observed |
| 1E41-F122 closed and could not be reopened with control switch. |
| |
| The isolation has not been reset and they have also isolated the outboard |
| valve by TS requirement. Investigation into cause of closure is continuing. |
| |
| During discussions with Nuclear Safety and Compliance Department at 1130 on |
| 09/01/00 it was determined that this PCIV failing closed was a reportable |
| ESF actuation. |
| |
| |
| The NRC Resident Inspector will be notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37284 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 09/01/2000|
| UNIT: [] [2] [] STATE: IL |NOTIFICATION TIME: 18:49[EDT]|
| RXTYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 09/01/2000|
+------------------------------------------------+EVENT TIME: 14:19[CDT]|
| NRC NOTIFIED BY: HOPMAN |LAST UPDATE DATE: 09/01/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |MELVYN LEACH R3 |
|10 CFR SECTION: | |
|AESF 50.72(b)(2)(ii) ESF ACTUATION | |
|NLCO TECH SPEC LCO A/S | |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
| | |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR CORE ISOLATION COOLING SYSTEM RECEIVED AN ISOLATION SIGNAL DURING |
| MAINTENANCE. |
| |
| Unit 2 was operating at 100% power. The Reactor Core Isolation Cooling |
| System was removed from service for scheduled maintenance. Following valve |
| packing adjustment, the Reactor Core Isolation Cooling system steam supply |
| outboard isolation valve was opened per approved procedure. Approximately |
| 10 seconds after the Reactor Core Isolation Cooling system steam inboard |
| isolation bypass valve was throttled open for warming. "Division 2 Reactor |
| Core isolation Cooling system steam line DP hi" and "Reactor Core Isolation |
| Cooling system Steam Line/Turbine isolation" alarms were received. The |
| Reactor Core Isolation Cooling system steam inboard isolation bypass valve |
| automatically closed due to an isolation signal. The Reactor Core Isolation |
| Cooling system remains isolated by the inboard isolation valves. The cause |
| of the isolation signal is unknown at this time. An investigation is in |
| progress to determine the cause of the isolation and initiate actions to |
| restore the Reactor Core Isolation Cooling system to an operable and |
| available status and exit the LCO action statement. |
| |
| The NRC Resident Inspector was notified. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37285 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 09/01/2000|
| UNIT: [1] [] [] STATE: MA |NOTIFICATION TIME: 21:08[EDT]|
| RXTYPE: [1] GE-3 |EVENT DATE: 09/01/2000|
+------------------------------------------------+EVENT TIME: 19:40[EDT]|
| NRC NOTIFIED BY: MCDONNELL |LAST UPDATE DATE: 09/01/2000|
| HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |PETE ESELGROTH R1 |
|10 CFR SECTION: | |
|AINB 50.72(b)(2)(iii)(B) POT RHR INOP | |
|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 |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE PLACING THE PLANT IN A |
| 14 DAY LCO ACTION STATEMENT. |
| |
| During the performance of 8.5.4.1 (HPCI operability test), HPCI failed to |
| meet acceptance criteria. The HPCI pump failed to meet the required flow, |
| pressure and rpm requirements. Troubleshooting of the problem is in |
| progress to make HPCI operable within the 14 day LCO action statement |
| requirement. |
| |
| The NRC Resident Inspector was informed. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37286 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 09/03/2000|
| UNIT: [2] [] [] STATE: NY |NOTIFICATION TIME: 15:49[EDT]|
| RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 09/03/2000|
+------------------------------------------------+EVENT TIME: 15:10[EDT]|
| NRC NOTIFIED BY: DAVE OWEN |LAST UPDATE DATE: 09/03/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: UNU |PETE ESELGROTH R1 |
|10 CFR SECTION: |STUART RICHARDS NRR |
|AAEC |JOSEPH GIITTER IRO |
| |CALDWELL FEMA |
| | |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|2 N N 0 Refueling |0 Refueling |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNUSUAL EVENT - FIRE IN CONTAINMENT |
| |
| The licensee declared an unusual event at 1510 because of a fire in |
| containment that lasted more than 15 minutes. A fire was reported at 1440 |
| in a tarp that was being used in containment. The tarp is believed to have |
| been ignited by some cutting or grinding going on in the vicinity. The |
| licensee called for assistance from the local fire department, but they |
| extinguished the fire before the fire company could assist. The fire was |
| reported out at 1509. The unusual event was terminated at 1615. |
| |
| The reactor is defueled with all fuel having been moved to the spent fuel |
| pool. No radioactivity was released. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37287 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 09/04/2000|
| UNIT: [1] [] [] STATE: KS |NOTIFICATION TIME: 15:00[EDT]|
| RXTYPE: [1] W-4-LP |EVENT DATE: 09/04/2000|
+------------------------------------------------+EVENT TIME: 11:32[CDT]|
| NRC NOTIFIED BY: JIM GILMORE |LAST UPDATE DATE: 09/04/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVE LOVELESS R4 |
|10 CFR SECTION: |STUART RICHARDS NRR |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION |VICTOR DRICKS PAO |
|AESF 50.72(b)(2)(ii) ESF 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 A/R Y 100 Power Operation |0 Hot Standby |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| REACTOR TRIP DUE TO FIRE IN UNIT AUXILIARY TRANSFORMER |
| |
| At about 1132 CDT a fire was reported in the unit auxiliary transformer, |
| alarms were received in the control room with a unit trip, all rods fully |
| inserted. The on-site fire brigade and the off-site fire department were |
| called to respond. The fire was extinguished by installed fire suppression |
| equipment and declared out at 1143 CDT. The fire is being investigated by |
| fire protection personnel. The off-site fire department was released. |
| |
| The plant is stable in Hot Standby at normal temperature and pressure. Heat |
| removal is via the main condensers with steam generator level being |
| maintained by auxiliary feedwater. |
| |
| The auxiliary feedwater system, both turbine and motor driven, started |
| automatically on low steam generator level as expected with this event. All |
| safety equipment performed as designed. |
| |
| Concurrent with the reactor trip, the 'C' and 'D' reactor coolant pumps |
| tripped along with other loads due to one (PA02) of the two non-vital busses |
| not automatically transferring as expected to off-site power. The bus is |
| presently energized by off-site power and the 'D' reactor coolant pump was |
| restarted. The actual cause of the problem is being investigating. |
| |
| One of the reactor coolant system power operated relief valve opened and |
| closed one time due the transient of the 'D' reactor coolant pump trip and |
| subsequent loss of pressurizer spray. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37288 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 09/04/2000|
| UNIT: [] [2] [] STATE: GA |NOTIFICATION TIME: 15:30[EDT]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/04/2000|
+------------------------------------------------+EVENT TIME: 14:16[EDT]|
| NRC NOTIFIED BY: ANDY DISMUKE |LAST UPDATE DATE: 09/04/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN 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 Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INADVERTENT DEENERGIZATION OF THE '2A' RPS MG SET CAUSED GROUP 2 AND 5 |
| ISOLATIONS |
| |
| Plant personnel inadvertently tripped breaker to the '2A' reactor protection |
| system motor generator (RPS MG) set resulting in de-energization of the '2A' |
| RPS bus. This resulted in the closure of the inboard Group 2 containment |
| isolation valves, the inboard Group 5 reactor water cleanup valve, inboard |
| reactor water sample valve, the control room ventilation swapped to the |
| pressurization mode of operation, and a half scram in the 'A' RPS channel. |
| All actuations have been reset and the '2A' RPS bus is energized from the |
| alternate supply while an investigation is being conducted. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 37289 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/05/2000|
| UNIT: [] [2] [] STATE: NC |NOTIFICATION TIME: 05:42[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/05/2000|
+------------------------------------------------+EVENT TIME: 02:00[EDT]|
| NRC NOTIFIED BY: R.T. ELLIOT |LAST UPDATE DATE: 09/05/2000|
| HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CAUDLE JULIAN 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 Cold Shutdown |0 Cold Shutdown |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| "2B" AUXILIARY FEEDWATER PUMP RAN 2 HOURS AND 55 MINUTES BEFORE IT WAS |
| DISCOVERED THAT IT WAS OPERATING. STEAM GENERATORS WERE ISOLATED FROM THE |
| AFW SYSTEM. |
| |
| At 0200 ET the "B" Train of the Solid State Protection System (SSPS) was |
| deenergized for part of their refueling outage maintenance. When the SSPS |
| was deenergized the blocks for the Main Feedwater Pump blocks clear which |
| gave an automatic start signal to the "2B" AFW pump. The on shift reactor |
| operator did not notice that the "2B" AFW pump run light was on until 0455 |
| ET due to refueling outage maintenance activities in Control Room. "2B" AFW |
| pump recirculated water to the Upper Surge Tank since the Steam Generators |
| were isolated. NO damage occurred to the AFW pump. The licensee is |
| investigating this event. |
| |
| The NRC Resident Inspector will be notified of this event. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021