Event Notification Report for July 20, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/19/2000 - 07/20/2000
Power Reactor
Event Number: 37178
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TESORIERO
HQ OPS Officer: BOB STRANSKY
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: TESORIERO
HQ OPS Officer: BOB STRANSKY
Notification Date: 07/20/2000
Notification Time: 04:28 [ET]
Event Date: 07/20/2000
Event Time: 03:52 [EDT]
Last Update Date: 07/20/2000
Notification Time: 04:28 [ET]
Event Date: 07/20/2000
Event Time: 03:52 [EDT]
Last Update Date: 07/20/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
Person (Organization):
GREGORY CRANSTON (R1)
GREGORY CRANSTON (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 |
UNIT OUTSIDE OF DESIGN BASIS
"On July 20, 2000 at 0352 hours a Reactor Coolant system leakrate of 0.30 gpm was calculated. Currently the Charging and Letdown systems are isolated for maintenance. Investigation revealed the leakage being from the Excess Letdown system to the systems isolated for maintenance, which are located outside Containment. This leakrate exceeds the limit of 0.68 gph outside Containment and therefore is a condition outside the design basis of the plant. The Control Room Ventilation system is inoperable and a 72 hour limiting condition of operation has been entered."
The NRC resident inspector will be informed of this event by the licensee.
"On July 20, 2000 at 0352 hours a Reactor Coolant system leakrate of 0.30 gpm was calculated. Currently the Charging and Letdown systems are isolated for maintenance. Investigation revealed the leakage being from the Excess Letdown system to the systems isolated for maintenance, which are located outside Containment. This leakrate exceeds the limit of 0.68 gph outside Containment and therefore is a condition outside the design basis of the plant. The Control Room Ventilation system is inoperable and a 72 hour limiting condition of operation has been entered."
The NRC resident inspector will be informed of this event by the licensee.
Power Reactor
Event Number: 37179
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: HAISLETT
HQ OPS Officer: BOB STRANSKY
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: HAISLETT
HQ OPS Officer: BOB STRANSKY
Notification Date: 07/20/2000
Notification Time: 08:55 [ET]
Event Date: 07/20/2000
Event Time: 08:15 [EDT]
Last Update Date: 07/20/2000
Notification Time: 08:55 [ET]
Event Date: 07/20/2000
Event Time: 08:15 [EDT]
Last Update Date: 07/20/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
10 CFR Section:
50.72(b)(1)(v) - EMERGENCY SIREN INOP
Person (Organization):
GREGORY CRANSTON (R1)
GREGORY CRANSTON (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
EMERGENCY SIRENS INOPERABLE
The licensee reported that offsite emergency sirens are inoperable due to a transmitter failure. The transmitter associated with one of the sirens has failed in the transmit mode, and radio interference from this siren is affecting the ability to activate all of the other sirens. The licensee is attempting to locate the failed siren and deenergize the transmitter. The NRC resident inspector has been informed of this event.
The licensee reported that offsite emergency sirens are inoperable due to a transmitter failure. The transmitter associated with one of the sirens has failed in the transmit mode, and radio interference from this siren is affecting the ability to activate all of the other sirens. The licensee is attempting to locate the failed siren and deenergize the transmitter. The NRC resident inspector has been informed of this event.
Power Reactor
Event Number: 37180
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL MOOKHOEK
HQ OPS Officer: DOUG WEAVER
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL MOOKHOEK
HQ OPS Officer: DOUG WEAVER
Notification Date: 07/20/2000
Notification Time: 13:54 [ET]
Event Date: 07/20/2000
Event Time: 10:15 [CDT]
Last Update Date: 07/20/2000
Notification Time: 13:54 [ET]
Event Date: 07/20/2000
Event Time: 10:15 [CDT]
Last Update Date: 07/20/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MARK SHAFFER (R4)
MARK SHAFFER (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 |
INACTIVE LICENSED REACTOR OPERATOR STOOD WATCH FOR ONE HOUR
On July 20, 2000, at 0915 hours, it was determined that a violation of Technical Specification 6.2.2.b occurred.
This notification is being made pursuant to Operating License NPF-76 Condition 2.G for a condition prohibited by
Technical Specifications.
On July 17, 2000, a licensed reactor operator with an inactive license stood a watch for one hour to cover shift duties. The normal watchstander for day shift was late and a day staff reactor operator was requested to provide shift coverage. According to the posted active license list, the reactor operator's license was active. It was later determined that the active license list was in error and the license was not active. While on watch this individual performed no reactivity manipulations, and was supervised by two licensed Senior Reactor Operators.
Section 6.2.2.a of Technical Specifications requires specific staffing levels for the operating shift crew. The required shift staffing was not met at all times and is therefore reportable as a violation of Technical Specifications.
This event presented no risk to the health and safety of the general public.
The licensee notified the NRC resident inspector.
On July 20, 2000, at 0915 hours, it was determined that a violation of Technical Specification 6.2.2.b occurred.
This notification is being made pursuant to Operating License NPF-76 Condition 2.G for a condition prohibited by
Technical Specifications.
On July 17, 2000, a licensed reactor operator with an inactive license stood a watch for one hour to cover shift duties. The normal watchstander for day shift was late and a day staff reactor operator was requested to provide shift coverage. According to the posted active license list, the reactor operator's license was active. It was later determined that the active license list was in error and the license was not active. While on watch this individual performed no reactivity manipulations, and was supervised by two licensed Senior Reactor Operators.
Section 6.2.2.a of Technical Specifications requires specific staffing levels for the operating shift crew. The required shift staffing was not met at all times and is therefore reportable as a violation of Technical Specifications.
This event presented no risk to the health and safety of the general public.
The licensee notified the NRC resident inspector.