Event Notification Report for May 03, 2007
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/02/2007 - 05/03/2007
Power Reactor
Event Number: 43338
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVE FULLER
HQ OPS Officer: JOHN KNOKE
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: STEVE FULLER
HQ OPS Officer: JOHN KNOKE
Notification Date: 05/03/2007
Notification Time: 03:09 [ET]
Event Date: 05/03/2007
Event Time: 01:46 [EDT]
Last Update Date: 05/03/2007
Notification Time: 03:09 [ET]
Event Date: 05/03/2007
Event Time: 01:46 [EDT]
Last Update Date: 05/03/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DANIEL HOLODY (R1)
DANIEL HOLODY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
OFFSITE NOTIFICATION - RELEASE TO ENVIRONMENT
"Notified New Jersey Department of Environmental Protection of a release of sodium hypochlorite to the environment. The amount of sodium hypochlorite released was small (11.5 lbs) and well below the Federal (100 lbs) and state reportability limits for quantity."
Leak was from a hose on the chlorination system that supports the Service Water system.
The licensee notified the NRC Resident Inspector.
"Notified New Jersey Department of Environmental Protection of a release of sodium hypochlorite to the environment. The amount of sodium hypochlorite released was small (11.5 lbs) and well below the Federal (100 lbs) and state reportability limits for quantity."
Leak was from a hose on the chlorination system that supports the Service Water system.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 43452
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: THOMAS STEC
HQ OPS Officer: STEVE SANDIN
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: THOMAS STEC
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/27/2007
Notification Time: 15:17 [ET]
Event Date: 05/03/2007
Event Time: 00:58 [EST]
Last Update Date: 06/27/2007
Notification Time: 15:17 [ET]
Event Date: 05/03/2007
Event Time: 00:58 [EST]
Last Update Date: 06/27/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
JAMNES CAMERON (R3)
JAMNES CAMERON (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
INVALID SYSTEM ACTUATION
"This event is being reported in accordance with 10 CFR 50.73(a)(1) and 10 CFR 50.73(a)(2)(iv)(A). This condition meets the criteria of 10 CFR 50.73(a)(2)(iv)(A) for any event or condition that results in manual or automatic actuation for any of the systems listed in paragraph 10 CFR 50.73(a)(2)(iv)(B). The specific requirements apply here to 'General containment isolation signals affecting containment isolation valves in more than one system.'
"During the performance of surveillance instruction 'Low Pressure Coolant Injection (LPCI) 'B' and 'C' Initiation and Loss of EH12 Response Time Test,' the following valves auto closed during the test activities:
- 1G61-F0075 (Containment Equipment Drain Inboard Isolation),
- 1G61-F0165 (Containment Floor Drain Inboard Isolation),
- 1P11-F0090 (Containment Pools Drain Inboard Isolation), and
- 1P50-F140 (Containment Vessel Chilled Water Inboard Return MOV Isolation)
"The signals are considered to be invalid as the signals were a result of test activities and not actual plant conditions. The valve logic to close the valves was momentarily satisfied due to the sequence of electrical power restoration during the test; however, the test did not address the valve movement and the valve actuations could not be considered to be preplanned. The system actuations were considered to be partial, and the valves functioned successfully as designed.
"The event was captured within the corrective action program under condition report (CR) 07-19866.
"The resident inspector was notified of this event notification."
"This event is being reported in accordance with 10 CFR 50.73(a)(1) and 10 CFR 50.73(a)(2)(iv)(A). This condition meets the criteria of 10 CFR 50.73(a)(2)(iv)(A) for any event or condition that results in manual or automatic actuation for any of the systems listed in paragraph 10 CFR 50.73(a)(2)(iv)(B). The specific requirements apply here to 'General containment isolation signals affecting containment isolation valves in more than one system.'
"During the performance of surveillance instruction 'Low Pressure Coolant Injection (LPCI) 'B' and 'C' Initiation and Loss of EH12 Response Time Test,' the following valves auto closed during the test activities:
- 1G61-F0075 (Containment Equipment Drain Inboard Isolation),
- 1G61-F0165 (Containment Floor Drain Inboard Isolation),
- 1P11-F0090 (Containment Pools Drain Inboard Isolation), and
- 1P50-F140 (Containment Vessel Chilled Water Inboard Return MOV Isolation)
"The signals are considered to be invalid as the signals were a result of test activities and not actual plant conditions. The valve logic to close the valves was momentarily satisfied due to the sequence of electrical power restoration during the test; however, the test did not address the valve movement and the valve actuations could not be considered to be preplanned. The system actuations were considered to be partial, and the valves functioned successfully as designed.
"The event was captured within the corrective action program under condition report (CR) 07-19866.
"The resident inspector was notified of this event notification."