Event Notification Report for May 15, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/14/2000 - 05/15/2000
EVENT NUMBERS
370013700237004370053700637007
Power Reactor
Event Number: 37001
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE HACKLEMAN
HQ OPS Officer: DICK JOLLIFFE
Region: 4 State: CA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVE HACKLEMAN
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 05/15/2000
Notification Time: 04:04 [ET]
Event Date: 05/15/2000
Event Time: 00:43 [PDT]
Last Update Date: 05/16/2000
Notification Time: 04:04 [ET]
Event Date: 05/15/2000
Event Time: 00:43 [PDT]
Last Update Date: 05/16/2000
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a)(1)(i) - EMERGENCY DECLARED 50.72(b)(2)(ii) - ESF ACTUATION COMM ASST BRIEF
10 CFR Section:
50.72(a)(1)(i) - EMERGENCY DECLARED 50.72(b)(2)(ii) - ESF ACTUATION COMM ASST BRIEF
Person (Organization):
CHARLES CAIN (R4)
JOSE CALVO (NRR)
JOSEPH GIITTER (IRO)
EACHES (FEMA)
JOSEPH HIMES (RCT)
CHARLES CAIN (R4)
JOSE CALVO (NRR)
JOSEPH GIITTER (IRO)
EACHES (FEMA)
JOSEPH HIMES (RCT)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNUSUAL EVENT DUE TO AUXILIARY TRANSFORMER EXPLOSION & FIRE; LOSS OF OFFSITE POWER -
At 0043 PDT on 05/15/00, the licensee declared an Unusual Event due to auxiliary transformer #1-1 exploding and catching on fire. This resulted in the loss of offsite power and an automatic trip of Unit 1. The licensee called the offsite fire department and they responded to the plant. Auxiliary transformer #1-1 is located outside the turbine building (north end).
Three of three Unit 1 emergency diesel generators started and loaded and are supplying emergency power to vital Unit 1 buses. Auxiliary transformer #1-1 supplies backup power to Unit 1 emergency buses. The Unit 1 12 KV buses are energized. Unit 1 reactor coolant pumps are running providing forced circulation.
Unit 1 automatically tripped from 100% power. All control rods inserted completely. Steam is being dumped to the atmosphere. Unit 1 has no steam generator tube leaks and no fuel leaks. The auxiliary feedwater system automatically started, as expected. A #1-2 steam generator code safety valve failed open for about 25 - 30 minutes about 30 minutes after the reactor trip. The valve is now closed. There was no safety injection actuation.
Unit 1 is stable in Mode 3 (Hot Standby).
This event had no effect on Unit 2 which is stable at 100% power.
The licensee notified state and local officials and the NRC Resident Inspector.
At 0143 PDT, the fire is out. No personnel were injured.
At 0405 CDT, NRC Region 4 entered the Monitoring Phase of Normal NRC Response Mode.
* * * UPDATE AT 0726 ON 05/15/00 FROM MARK LEMKE TO JOLLIFFE * * *
The licensee determined that an electrical fault on the low voltage side of auxiliary transformer #1-1 caused extensive damage to the 12 KV buswork and nearby buswork used to supply the Unit 1 4 KV buses from offsite power following a plant shutdown. Auxiliary transformer #1-1 did not explode and is intact.
The licensee also determined that there was not a failure of a main steam code safety valve. However, following closure of the main steam isolation valves, a code safety valve on the #1-2 steam generator did lift and did not fully reseat. Plant operators took manual action to lower steam generator pressure, causing the valve to reseat. There was no release of radiation from the plant.
The California Department of Forestry responded to the site.
The licensee is continuing to investigate the cause of this explosion and has issued a press release.
* * * AT 0900 ON 05/15/00 COMMISSIONERS' ASSISTANTS BRIEFING * * *
IRO (Frank Congel, Joe Giitter); NRR Projects (Steve Dembek); OPA (Bill Beecher); OSP (Cardelia Maupin); IP (Howard Faulkner); CA (Tom Combs); Chairman Meserve Asst (Mike Tschiltz); Comm Dicus Asst (Joe Olencz); Comm McGaffigan Asst (Jeff Sharkey); Comm Diaz Asst (Tony Hsia); Comm Merrifield Asst (John Thoma); NRR (Ed Goodwin); R4 (Elmo Collins [Briefer], Bill Jones, et al).
* * * UPDATE AT 1358 EDT ON 5/16/00 BY D. PETERSON TO FANGIE JONES * * *
The licensee terminated the Unusual Event at 0959 PDT. Offsite power has been restored to the 4 KV vital busses. The diesel generators have been shutdown. The RCS temperature is 380 °F and pressure is 920 psig. The plant will continue to Cold Shutdown after chemistry hold is complete.
The licensee notified the NRC Resident Inspector. The NRC Headquarters Operation Officer notified the R4DO (Bill Jones), IRO (Joseph Giitter), NRR (William Beckner), EDO Office (Mark Satorius), PAO (Sue Gagner), FEMA (Austin).
NRC Region 4 exited the Monitoring Phase of Normal Mode at 1414 EDT.
At 0043 PDT on 05/15/00, the licensee declared an Unusual Event due to auxiliary transformer #1-1 exploding and catching on fire. This resulted in the loss of offsite power and an automatic trip of Unit 1. The licensee called the offsite fire department and they responded to the plant. Auxiliary transformer #1-1 is located outside the turbine building (north end).
Three of three Unit 1 emergency diesel generators started and loaded and are supplying emergency power to vital Unit 1 buses. Auxiliary transformer #1-1 supplies backup power to Unit 1 emergency buses. The Unit 1 12 KV buses are energized. Unit 1 reactor coolant pumps are running providing forced circulation.
Unit 1 automatically tripped from 100% power. All control rods inserted completely. Steam is being dumped to the atmosphere. Unit 1 has no steam generator tube leaks and no fuel leaks. The auxiliary feedwater system automatically started, as expected. A #1-2 steam generator code safety valve failed open for about 25 - 30 minutes about 30 minutes after the reactor trip. The valve is now closed. There was no safety injection actuation.
Unit 1 is stable in Mode 3 (Hot Standby).
This event had no effect on Unit 2 which is stable at 100% power.
The licensee notified state and local officials and the NRC Resident Inspector.
At 0143 PDT, the fire is out. No personnel were injured.
At 0405 CDT, NRC Region 4 entered the Monitoring Phase of Normal NRC Response Mode.
* * * UPDATE AT 0726 ON 05/15/00 FROM MARK LEMKE TO JOLLIFFE * * *
The licensee determined that an electrical fault on the low voltage side of auxiliary transformer #1-1 caused extensive damage to the 12 KV buswork and nearby buswork used to supply the Unit 1 4 KV buses from offsite power following a plant shutdown. Auxiliary transformer #1-1 did not explode and is intact.
The licensee also determined that there was not a failure of a main steam code safety valve. However, following closure of the main steam isolation valves, a code safety valve on the #1-2 steam generator did lift and did not fully reseat. Plant operators took manual action to lower steam generator pressure, causing the valve to reseat. There was no release of radiation from the plant.
The California Department of Forestry responded to the site.
The licensee is continuing to investigate the cause of this explosion and has issued a press release.
* * * AT 0900 ON 05/15/00 COMMISSIONERS' ASSISTANTS BRIEFING * * *
IRO (Frank Congel, Joe Giitter); NRR Projects (Steve Dembek); OPA (Bill Beecher); OSP (Cardelia Maupin); IP (Howard Faulkner); CA (Tom Combs); Chairman Meserve Asst (Mike Tschiltz); Comm Dicus Asst (Joe Olencz); Comm McGaffigan Asst (Jeff Sharkey); Comm Diaz Asst (Tony Hsia); Comm Merrifield Asst (John Thoma); NRR (Ed Goodwin); R4 (Elmo Collins [Briefer], Bill Jones, et al).
* * * UPDATE AT 1358 EDT ON 5/16/00 BY D. PETERSON TO FANGIE JONES * * *
The licensee terminated the Unusual Event at 0959 PDT. Offsite power has been restored to the 4 KV vital busses. The diesel generators have been shutdown. The RCS temperature is 380 °F and pressure is 920 psig. The plant will continue to Cold Shutdown after chemistry hold is complete.
The licensee notified the NRC Resident Inspector. The NRC Headquarters Operation Officer notified the R4DO (Bill Jones), IRO (Joseph Giitter), NRR (William Beckner), EDO Office (Mark Satorius), PAO (Sue Gagner), FEMA (Austin).
NRC Region 4 exited the Monitoring Phase of Normal Mode at 1414 EDT.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 37002
Facility: WNP-2
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: J.W. GASTON
HQ OPS Officer: JOHN MacKINNON
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: J.W. GASTON
HQ OPS Officer: JOHN MacKINNON
Notification Date: 05/15/2000
Notification Time: 11:47 [ET]
Event Date: 05/15/2000
Event Time: 04:48 [PDT]
Last Update Date: 06/06/2000
Notification Time: 11:47 [ET]
Event Date: 05/15/2000
Event Time: 04:48 [PDT]
Last Update Date: 06/06/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - ESF ACTUATION
Person (Organization):
BILL JONES (R4)
BILL JONES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 62 | Power Operation | 62 | Power Operation |
OUTBOARD MAIN STEAM ISOLATION (MSIV) VALVE FOUND CLOSED.
At 0448 PDT on 05/15/00, the outboard main steam isolation valve # MSIV-V-28A was found in the closed position (green indicating light on). Follow-up verification of the 'A' main steam line flow (0%) and the plant computer valve position verified that the valve was closed. The plant computer indicated that the valve closed at 0254 PDT and it was discovered closed at 0448 PDT. No work was being performed on the main steam system or in the area of the main steam system when the valve closed. The plant computer indicated that the valve had fast closed. The plant entered the Limiting Condition of Operation for Primary Containment Isolation Valve and placed the control switch for the MSIV in the closed position. There was no valid ESF Actuation signal that caused the valve closure. The plant was operating at 62% power and did not experience a transient as a result of the MSIV closure (no flux tilt). Licensee investigation into the cause of the closure is continuing.
The NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE ON 6/6/00 @ 1155 BY MCBRIDE TO GOULD * * * RETRACTION
The event notification report associated with the above event is hereby retracted. The event and conditions associated with the event do not meet NUREG 1022, Rev. 1, reporting criteria. Only a single component, MSIV-V-28A, actuated (closed). The single component (MSIV) is not sufficient to mitigate the consequences of single events. There was not a manual or automatic ESE system actuation. An ESF signal (valid or invalid) was not generated. Therefore, in accordance with the statements of considerations for NUREG 1022, Rev. 1,( 10CFR50.72(b)(2)(ii), there was not a sufficient number of channels (zero) in a multichannel ESF actuation system to meet the definition of actuation of enough channels to complete the minimum actuation logic for a train or the system. For these reasons, this event does not meet the reporting criteria of 10CFR50.72(b)(2)(ii) and is hereby retracted.
The NRC Resident Inspector was notified. The Reg 4 RDO (Pellet) was notified.
At 0448 PDT on 05/15/00, the outboard main steam isolation valve # MSIV-V-28A was found in the closed position (green indicating light on). Follow-up verification of the 'A' main steam line flow (0%) and the plant computer valve position verified that the valve was closed. The plant computer indicated that the valve closed at 0254 PDT and it was discovered closed at 0448 PDT. No work was being performed on the main steam system or in the area of the main steam system when the valve closed. The plant computer indicated that the valve had fast closed. The plant entered the Limiting Condition of Operation for Primary Containment Isolation Valve and placed the control switch for the MSIV in the closed position. There was no valid ESF Actuation signal that caused the valve closure. The plant was operating at 62% power and did not experience a transient as a result of the MSIV closure (no flux tilt). Licensee investigation into the cause of the closure is continuing.
The NRC Resident Inspector was notified of this event by the licensee.
* * * UPDATE ON 6/6/00 @ 1155 BY MCBRIDE TO GOULD * * * RETRACTION
The event notification report associated with the above event is hereby retracted. The event and conditions associated with the event do not meet NUREG 1022, Rev. 1, reporting criteria. Only a single component, MSIV-V-28A, actuated (closed). The single component (MSIV) is not sufficient to mitigate the consequences of single events. There was not a manual or automatic ESE system actuation. An ESF signal (valid or invalid) was not generated. Therefore, in accordance with the statements of considerations for NUREG 1022, Rev. 1,( 10CFR50.72(b)(2)(ii), there was not a sufficient number of channels (zero) in a multichannel ESF actuation system to meet the definition of actuation of enough channels to complete the minimum actuation logic for a train or the system. For these reasons, this event does not meet the reporting criteria of 10CFR50.72(b)(2)(ii) and is hereby retracted.
The NRC Resident Inspector was notified. The Reg 4 RDO (Pellet) was notified.
Power Reactor
Event Number: 37004
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DeClemente
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DeClemente
HQ OPS Officer: JOHN MacKINNON
Notification Date: 05/15/2000
Notification Time: 14:25 [ET]
Event Date: 05/15/2000
Event Time: 12:16 [EDT]
Last Update Date: 05/15/2000
Notification Time: 14:25 [ET]
Event Date: 05/15/2000
Event Time: 12:16 [EDT]
Last Update Date: 05/15/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
DAVID LEW (R1)
DAVID LEW (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION TO LOCAL AND STATE AUTHORITIES DUE TO LEAKING FUEL OIL TANK
"This report is being made for an event for which a notification to another government agency (i.e., NYSDEC/WCDOH) has been made. On May 15, 2000 at 1216 hours, a notification was made to the Westchester County Department Of Health (WCDOH) and subsequently a notification to the New York State Department of Conservation (NYSDEC), Spill Report Number 00-01912, for a failed leak tightness test on the sewage treatment plant underground fuel oil storage tank. A vacuum leak test was performed by a NYS qualified vendor on the underground storage tank. A vacuum could not be maintained and air in-leakage could be heard indicating a leak in the tank. Fuel oil is being removed from the tank and excavation initiated to perform visual inspections."
The licensee notified the NRC Resident Inspector.
"This report is being made for an event for which a notification to another government agency (i.e., NYSDEC/WCDOH) has been made. On May 15, 2000 at 1216 hours, a notification was made to the Westchester County Department Of Health (WCDOH) and subsequently a notification to the New York State Department of Conservation (NYSDEC), Spill Report Number 00-01912, for a failed leak tightness test on the sewage treatment plant underground fuel oil storage tank. A vacuum leak test was performed by a NYS qualified vendor on the underground storage tank. A vacuum could not be maintained and air in-leakage could be heard indicating a leak in the tank. Fuel oil is being removed from the tank and excavation initiated to perform visual inspections."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 37005
Facility: BYRON
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SCOT SWANSON
HQ OPS Officer: FANGIE JONES
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SCOT SWANSON
HQ OPS Officer: FANGIE JONES
Notification Date: 05/15/2000
Notification Time: 16:30 [ET]
Event Date: 05/15/2000
Event Time: 06:53 [CDT]
Last Update Date: 05/15/2000
Notification Time: 16:30 [ET]
Event Date: 05/15/2000
Event Time: 06:53 [CDT]
Last Update Date: 05/15/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(vi) - OFFSITE NOTIFICATION
Person (Organization):
JOHN MADERA (R3)
DAVID LEW (R1)
JOSEPH GIITTER (IRO)
SUE GAGNER (PAO)
DON COOL (NMSS)
JOHN MADERA (R3)
DAVID LEW (R1)
JOSEPH GIITTER (IRO)
SUE GAGNER (PAO)
DON COOL (NMSS)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
TRAFFIC ACCIDENT INVOLVING TRUCK TRANSPORTING EQUIPMENT FROM BYRON STATION
"At 0753 EDT on 05/15/00, a traffic accident occurred involving a semi-tractor trailer and a car in the state of Pennsylvania (State Route 4005, New Galilee Road, Darlington Township). The truck was carrying a spent fuel rack shipped from Byron Station as Radiological Material LSA n.o.s 7 UN 2912 Fissile Excepted (ComEd, Byron, Illinois) that was to be recycled by vendor "Alaron" in Wampum, Pennsylvania. The container for the rack was not damaged. There was no affect to the surrounding area due to the shipment. The vehicle accident caused traffic to be suspended on Route 4005. A nearby school utilized a different building for classes. The Pennsylvania State Police responded to the scene and managed the vehicle traffic. A Safety Officer from Alaron responded to the site to confirm there was no radiological issues. The Pennsylvania State Police issued a traffic report discussing hazardous materials involved in a traffic accident. This press release requires notification of NRC in accordance with 10 CFR 50.72(b)(2)(vi)"
The licensee notified the NRC Resident Inspector.
"At 0753 EDT on 05/15/00, a traffic accident occurred involving a semi-tractor trailer and a car in the state of Pennsylvania (State Route 4005, New Galilee Road, Darlington Township). The truck was carrying a spent fuel rack shipped from Byron Station as Radiological Material LSA n.o.s 7 UN 2912 Fissile Excepted (ComEd, Byron, Illinois) that was to be recycled by vendor "Alaron" in Wampum, Pennsylvania. The container for the rack was not damaged. There was no affect to the surrounding area due to the shipment. The vehicle accident caused traffic to be suspended on Route 4005. A nearby school utilized a different building for classes. The Pennsylvania State Police responded to the scene and managed the vehicle traffic. A Safety Officer from Alaron responded to the site to confirm there was no radiological issues. The Pennsylvania State Police issued a traffic report discussing hazardous materials involved in a traffic accident. This press release requires notification of NRC in accordance with 10 CFR 50.72(b)(2)(vi)"
The licensee notified the NRC Resident Inspector.
Fuel Cycle Facility
Event Number: 37006
Facility: PORTSMOUTH GASEOUS DIFFUSION PLANT
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: JOE HALCOMB
HQ OPS Officer: FANGIE JONES
Region: 3 State: OH
Unit: [] [] []
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
NRC Notified By: JOE HALCOMB
HQ OPS Officer: FANGIE JONES
Notification Date: 05/15/2000
Notification Time: 18:50 [ET]
Event Date: 05/15/2000
Event Time: 15:30 [EDT]
Last Update Date: 05/15/2000
Notification Time: 18:50 [ET]
Event Date: 05/15/2000
Event Time: 15:30 [EDT]
Last Update Date: 05/15/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
JOHN MADERA (R3)
THOMAS ESSIG (NMSS)
JOHN MADERA (R3)
THOMAS ESSIG (NMSS)
REPORTABLE QUANTITY FOR OIL DISCHARGE EXCEEDED
"On 05/15/00 at 1530, it was determined that the Reportable Quantity (RQ) value for oil (i.e, greater than 25 gallons) was exceeded. Operations personnel reported that a lubrication oil spill had occurred on the roof of the X-330 Process Building and after an investigation was initiated by Environmental Compliance personnel, it was determined that the total quantity of the spill was approximately 500 gallons. The cause of the spill is still under investigation.
"The spill resulted in a release of oil to the environment exceeding the RQ in accordance with Ohio Administrative Code Rule 3750-25-20 thereby initiating the release reporting requirements contained therein. Oil was discharged via the storm sewer system to the X-230J-7 East Holding Pond and the southernmost branch of the West Drainage Ditch.
"At the time of this report, the oil is contained on-site and no off-site consequences have occurred. The spill is currently being cleaned up by Chemical Operations personnel using oil diversion equipment and absorbent material."
The licensee notified the NRC Resident Inspector as well as local and state authorities.
"On 05/15/00 at 1530, it was determined that the Reportable Quantity (RQ) value for oil (i.e, greater than 25 gallons) was exceeded. Operations personnel reported that a lubrication oil spill had occurred on the roof of the X-330 Process Building and after an investigation was initiated by Environmental Compliance personnel, it was determined that the total quantity of the spill was approximately 500 gallons. The cause of the spill is still under investigation.
"The spill resulted in a release of oil to the environment exceeding the RQ in accordance with Ohio Administrative Code Rule 3750-25-20 thereby initiating the release reporting requirements contained therein. Oil was discharged via the storm sewer system to the X-230J-7 East Holding Pond and the southernmost branch of the West Drainage Ditch.
"At the time of this report, the oil is contained on-site and no off-site consequences have occurred. The spill is currently being cleaned up by Chemical Operations personnel using oil diversion equipment and absorbent material."
The licensee notified the NRC Resident Inspector as well as local and state authorities.
Power Reactor
Event Number: 37007
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: CHUCK McKINNEY
HQ OPS Officer: DICK JOLLIFFE
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: CHUCK McKINNEY
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 05/16/2000
Notification Time: 07:28 [ET]
Event Date: 05/15/2000
Event Time: 09:30 [EDT]
Last Update Date: 05/16/2000
Notification Time: 07:28 [ET]
Event Date: 05/15/2000
Event Time: 09:30 [EDT]
Last Update Date: 05/16/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
BRIAN BONSER (R2)
BRIAN BONSER (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
24 HOUR FITNESS FOR DUTY EVENT -
At 0930 on 05/15/00, a licensee supervisor tested positive for alcohol during a random drug and alcohol test. The licensee withdrew the employee's access authorization to the plant protected area after verification of the positive test. The licensee is determining further corrective actions.
The licensee notified the NRC Resident Inspector.
At 0930 on 05/15/00, a licensee supervisor tested positive for alcohol during a random drug and alcohol test. The licensee withdrew the employee's access authorization to the plant protected area after verification of the positive test. The licensee is determining further corrective actions.
The licensee notified the NRC Resident Inspector.