Event Notification Report for July 05, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/04/2000 - 07/05/2000
EVENT NUMBERS
371423714337144371453714637147
Power Reactor
Event Number: 37142
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: FUNKHOUSER
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: FUNKHOUSER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/05/2000
Notification Time: 13:01 [ET]
Event Date: 07/05/2000
Event Time: 11:05 [CDT]
Last Update Date: 07/05/2000
Notification Time: 13:01 [ET]
Event Date: 07/05/2000
Event Time: 11:05 [CDT]
Last Update Date: 07/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(v) - OFFSITE MEDICAL
10 CFR Section:
50.72(b)(2)(v) - OFFSITE MEDICAL
Person (Organization):
MICHAEL JORDAN (R3)
MICHAEL JORDAN (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
POTENTIALLY CONTAMINATED PERSON TRANSPORTED TO THE HOSPITAL
"On 7/5/00 at 1105, a potentially contaminated worker was taken offsite by ambulance to John Warner Hospital in Clinton, Illinois. The worker, an Electrician, was working on the Fuel Building bridge on 755' Fuel Building when he passed out. The Electrician was working in a potentially contaminated area. Radiation Protection personnel accompanied the electrician to the hospital but were not able to verify that he was not contaminated at the time he left site to be taken to the hospital. The electrician regained consciousness while on the Fuel Building bridge. At 1132, Radiation Protection personnel frisked the electrician at the hospital and found no contamination on the individual or his clothing. This notification is being made pursuant to 10CFR50.72(b)(2)(v), Offsite Medical."
The NRC Resident Inspector was notified.
"On 7/5/00 at 1105, a potentially contaminated worker was taken offsite by ambulance to John Warner Hospital in Clinton, Illinois. The worker, an Electrician, was working on the Fuel Building bridge on 755' Fuel Building when he passed out. The Electrician was working in a potentially contaminated area. Radiation Protection personnel accompanied the electrician to the hospital but were not able to verify that he was not contaminated at the time he left site to be taken to the hospital. The electrician regained consciousness while on the Fuel Building bridge. At 1132, Radiation Protection personnel frisked the electrician at the hospital and found no contamination on the individual or his clothing. This notification is being made pursuant to 10CFR50.72(b)(2)(v), Offsite Medical."
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 37143
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: COBB
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: COBB
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/05/2000
Notification Time: 13:06 [ET]
Event Date: 07/05/2000
Event Time: 05:32 [EDT]
Last Update Date: 07/05/2000
Notification Time: 13:06 [ET]
Event Date: 07/05/2000
Event Time: 05:32 [EDT]
Last Update Date: 07/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
MICHAEL JORDAN (R3)
MICHAEL JORDAN (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 98 | Power Operation | 98 | Power Operation |
POSITIVE FOR-CAUSE ALCOHOL TEST
A contractor supervisor tested positive for alcohol during a for-cause test upon entering the site. His access was suspended at 0930.
The NRC Resident Inspector was notified.
A contractor supervisor tested positive for alcohol during a for-cause test upon entering the site. His access was suspended at 0930.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 37144
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: FELTNER
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: FELTNER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/05/2000
Notification Time: 13:58 [ET]
Event Date: 07/05/2000
Event Time: 09:20 [CDT]
Last Update Date: 07/05/2000
Notification Time: 13:58 [ET]
Event Date: 07/05/2000
Event Time: 09:20 [CDT]
Last Update Date: 07/05/2000
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):
DAVID GRAVES (R4)
DAVID GRAVES (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
REACTOR CORE COOLING SYSTEM ISOLATION DURING A SURVEILLANCE
"On 7/5/2000 at 0920 CDT, the Reactor Core Isolation Cooling (RCIC) System isolated due to a sensed high steam supply line differential pressure. Instrument technicians were performing required surveillance test STP-207-4248 on Division 1 pressure transmitter, E51-PDTN084A. This surveillance requires the transmitter to be hydraulically isolated from the system in order to perform a calibration and also generates a Division 1 RCIC Isolation signal.
Per the plant design, the Division 1 and 2 pressure transmitters share a common sensing line. While removing the Division 1 transmitter from service, the Division 2 transmitter, E51-PDTN084B, spiked high causing a Division 2 RCIC isolation signal and subsequent closure of E51-MOVF063, RCIC Steam Supply Inboard Isolation Valve.
Although the RCIC system was inoperable for scheduled maintenance at the time of the Division 2 isolation, the containment isolation function was still in service and considered operable. High Pressure Core Spray and all other ECCS systems remained operable while the RCIC system was isolated. RCIC will be returned to service following the completion of the scheduled maintenance activities.
The RCIC System Isolation Instrumentation is designated as an Engineered Safety Features system and this event is therefore reportable in accordance with 10CFR50.72."
The NRC Resident Inspector was notified.
"On 7/5/2000 at 0920 CDT, the Reactor Core Isolation Cooling (RCIC) System isolated due to a sensed high steam supply line differential pressure. Instrument technicians were performing required surveillance test STP-207-4248 on Division 1 pressure transmitter, E51-PDTN084A. This surveillance requires the transmitter to be hydraulically isolated from the system in order to perform a calibration and also generates a Division 1 RCIC Isolation signal.
Per the plant design, the Division 1 and 2 pressure transmitters share a common sensing line. While removing the Division 1 transmitter from service, the Division 2 transmitter, E51-PDTN084B, spiked high causing a Division 2 RCIC isolation signal and subsequent closure of E51-MOVF063, RCIC Steam Supply Inboard Isolation Valve.
Although the RCIC system was inoperable for scheduled maintenance at the time of the Division 2 isolation, the containment isolation function was still in service and considered operable. High Pressure Core Spray and all other ECCS systems remained operable while the RCIC system was isolated. RCIC will be returned to service following the completion of the scheduled maintenance activities.
The RCIC System Isolation Instrumentation is designated as an Engineered Safety Features system and this event is therefore reportable in accordance with 10CFR50.72."
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 37145
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MUELLER
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MUELLER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/05/2000
Notification Time: 14:17 [ET]
Event Date: 07/05/2000
Event Time: 13:07 [EDT]
Last Update Date: 07/05/2000
Notification Time: 14:17 [ET]
Event Date: 07/05/2000
Event Time: 13:07 [EDT]
Last Update Date: 07/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - RPS ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - RPS ACTUATION
Person (Organization):
STEVEN DENNIS (R1)
STEVEN DENNIS (R1)
| 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 |
REACTOR TRIP FROM 100% POWER DUE TO TURBINE TRIP.
The plant had a reactor trip from 100% power due to a turbine trip. Cause of the turbine trip is being investigated. All control rods fully inserted and no relief valves lifted or ECCS actuated. The plant is stable in mode 3 with RCS temperature and pressure at 547°F and 2235 Psig. There were no radiological releases and no RCS or steam generator tube leaks. All safety related equipment functioned as required and remains operable. The aux feed system started as expected and decay heat is being removed via the steam bypass system to the condenser.
The NRC Resident Inspector was notified.
The plant had a reactor trip from 100% power due to a turbine trip. Cause of the turbine trip is being investigated. All control rods fully inserted and no relief valves lifted or ECCS actuated. The plant is stable in mode 3 with RCS temperature and pressure at 547°F and 2235 Psig. There were no radiological releases and no RCS or steam generator tube leaks. All safety related equipment functioned as required and remains operable. The aux feed system started as expected and decay heat is being removed via the steam bypass system to the condenser.
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 37146
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: LANGAN
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: CT
Unit: [] [] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: LANGAN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/05/2000
Notification Time: 15:16 [ET]
Event Date: 07/05/2000
Event Time: 15:00 [EDT]
Last Update Date: 07/05/2000
Notification Time: 15:16 [ET]
Event Date: 07/05/2000
Event Time: 15:00 [EDT]
Last Update Date: 07/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
STEVEN DENNIS (R1)
STEVEN DENNIS (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 |
CONTRACT EMPLOYEE FAILS FITNESS FOR DUTY TEST
A contractor employee failed a Fitness For Duty test administered on July 5, 2000. Specific details of the event are not for public disclosure. Appropriate action has been taken accordance with the company Fitness For Duty program.
The NRC Resident Inspector will be notified. State and Local agencies have been notified.
A contractor employee failed a Fitness For Duty test administered on July 5, 2000. Specific details of the event are not for public disclosure. Appropriate action has been taken accordance with the company Fitness For Duty program.
The NRC Resident Inspector will be notified. State and Local agencies have been notified.
Power Reactor
Event Number: 37147
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JERNIGAN
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: JERNIGAN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/05/2000
Notification Time: 17:14 [ET]
Event Date: 07/05/2000
Event Time: 10:35 [EDT]
Last Update Date: 07/05/2000
Notification Time: 17:14 [ET]
Event Date: 07/05/2000
Event Time: 10:35 [EDT]
Last Update Date: 07/05/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
GEORGE BELISLE (R2)
GEORGE BELISLE (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 |
USE OF ILLEGAL CONTROLLED SUBSTANCE
An employee was tested for cause for illegal controlled substance with the results being negative. However, he admitted during the interview he had used such substance.
The NRC Resident Inspector was notified.
An employee was tested for cause for illegal controlled substance with the results being negative. However, he admitted during the interview he had used such substance.
The NRC Resident Inspector was notified.