Event Notification Report for June 16, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/15/2013 - 06/16/2013
Power Reactor
Event Number: 49121
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: BILL HUFFMAN
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 06/16/2013
Notification Time: 02:42 [ET]
Event Date: 06/16/2013
Event Time: 00:00 [EDT]
Last Update Date: 06/16/2013
Notification Time: 02:42 [ET]
Event Date: 06/16/2013
Event Time: 00:00 [EDT]
Last Update Date: 06/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ERIC DUNCAN (R3DO)
ERIC DUNCAN (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 8 | Power Operation | 8 | Power Operation |
TECHNICAL SPECIFICATION SHUTDOWN DUE TO SMALL REACTOR COOLANT LEAK ON A RECIRCULATION FLOW CONTROL VALVE VENT LINE
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(i) and 50.72(b)(3)(ii)(A).
"On June 16, 2013 at 0200 EDT, the Perry Nuclear Power Plant commenced a controlled plant shutdown. The shutdown was due to a small leak through the base of a vent line on the 'B' Reactor Recirculation Flow Control Valve.
"On June 15, 2013 at 2250 EDT, the leak was identified and was subsequently determined to require a plant shutdown in accordance with Technical Specification 3.4.5, Action (C) which requires the plant to be in Mode 3 within 12 hours.
"The NRC Resident Inspector has been notified." The licensee will also be notifying state and local authorities.
The licensee had come down in power to make a drywell entry and investigate drywell leakage indications. Steam was observed to be coming from a vent line that comes off the top of the recirc flow control valve. The licensee was unable to characterize the leak rate other than a small leak. The licensee stated that the steam appeared be coming from a weld location where the vent line comes out of the flow control valve which would classify it as pressure boundary leakage.
"This event is being reported in accordance with 10 CFR 50.72(b)(2)(i) and 50.72(b)(3)(ii)(A).
"On June 16, 2013 at 0200 EDT, the Perry Nuclear Power Plant commenced a controlled plant shutdown. The shutdown was due to a small leak through the base of a vent line on the 'B' Reactor Recirculation Flow Control Valve.
"On June 15, 2013 at 2250 EDT, the leak was identified and was subsequently determined to require a plant shutdown in accordance with Technical Specification 3.4.5, Action (C) which requires the plant to be in Mode 3 within 12 hours.
"The NRC Resident Inspector has been notified." The licensee will also be notifying state and local authorities.
The licensee had come down in power to make a drywell entry and investigate drywell leakage indications. Steam was observed to be coming from a vent line that comes off the top of the recirc flow control valve. The licensee was unable to characterize the leak rate other than a small leak. The licensee stated that the steam appeared be coming from a weld location where the vent line comes out of the flow control valve which would classify it as pressure boundary leakage.
Power Reactor
Event Number: 49122
Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DANIEL PIPKIN
HQ OPS Officer: PETE SNYDER
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DANIEL PIPKIN
HQ OPS Officer: PETE SNYDER
Notification Date: 06/16/2013
Notification Time: 13:32 [ET]
Event Date: 06/16/2013
Event Time: 04:56 [CDT]
Last Update Date: 06/16/2013
Notification Time: 13:32 [ET]
Event Date: 06/16/2013
Event Time: 04:56 [CDT]
Last Update Date: 06/16/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HEATHER GEPFORD (R4DO)
HEATHER GEPFORD (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
BROKEN DAMPER BLADE LINKAGE FOUND ON TECHNICAL SUPPORT CENTER VENTILATION LINE
"At 0456 CDT, while performing scheduled maintenance on HVL-AOD408, HVL-AHU1 Suction AOD [Air Operated Damper], the linkage inside the damper connecting the two damper blades was found to be broken. HVL-AHU1, Service Bldg. TSC A/C Unit, provides ventilation to the Technical Support Center. With the linkage on HVL-AOD408 broken, there is the potential that a filtered air supply cannot be provided to the TSC. As a result the TSC ventilation was placed in Emergency Mode and positive pressure could not be maintained. Investigation revealed, in addition to [the broken linkage on] HVL-AOD 408, a broken seal on bottom of door SB-123-19.
"A contingency plan is in place to relocate personnel if needed per EIP-2-018, 'Technical Support Center' and EIP-2-016, 'Operations Support Center.'"
The licensee notified the NRC Resident Inspector.
"At 0456 CDT, while performing scheduled maintenance on HVL-AOD408, HVL-AHU1 Suction AOD [Air Operated Damper], the linkage inside the damper connecting the two damper blades was found to be broken. HVL-AHU1, Service Bldg. TSC A/C Unit, provides ventilation to the Technical Support Center. With the linkage on HVL-AOD408 broken, there is the potential that a filtered air supply cannot be provided to the TSC. As a result the TSC ventilation was placed in Emergency Mode and positive pressure could not be maintained. Investigation revealed, in addition to [the broken linkage on] HVL-AOD 408, a broken seal on bottom of door SB-123-19.
"A contingency plan is in place to relocate personnel if needed per EIP-2-018, 'Technical Support Center' and EIP-2-016, 'Operations Support Center.'"
The licensee notified the NRC Resident Inspector.