Event Notification Report for April 06, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/05/2012 - 04/06/2012
EVENT NUMBERS
47811478124781347860
Power Reactor
Event Number: 47811
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GUY GRIFFIS
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GUY GRIFFIS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/06/2012
Notification Time: 08:41 [ET]
Event Date: 04/06/2012
Event Time: 04:43 [EDT]
Last Update Date: 04/06/2012
Notification Time: 08:41 [ET]
Event Date: 04/06/2012
Event Time: 04:43 [EDT]
Last Update Date: 04/06/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GERALD MCCOY (R2DO)
GERALD MCCOY (R2DO)
| 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 |
LOSS OF TONE ALERT SYSTEM
"On Friday April 6, 2012, at 0443 EDT, the National Weather Service (NWS) Jacksonville Florida office notified Hatch Nuclear Plant (HNP) of a loss of the NWS Tone Alert Weather Radio System. Site Emergency Procedures define a loss of Tone Alert System for greater than 15 minutes as a significant loss of Emergency Communications.
"The NWS Tone Alert Weather Radios are utilized as the Prompt Notification System (PNS) for HNP. This loss impacts the ability to notify the Emergency Planning Zone (EPZ) population for the HNP. This failure meets NRC 8 hour reporting criteria 10CFR50.72(b)(3)(xiii).
"The State of Georgia Department of Homeland Security / Georgia Emergency Management Agency (GEMA) 24-hour warning point and the '911' dispatch centers of Appling, Jeff Davis, Tattnall and Toombs counties were notified so compensatory measures would be available should the Prompt Notification System be needed. This consists of utilizing route alerting and the 'Code Red' system, which is a reverse 911 feature available from the county 911 center. This notification meets the 4-hour notification reporting criteria 10CFR50.72(b)(2)(xi).
"On Friday April 6, 2012, at 0503 EDT, the NWS Jacksonville Florida office notified HNP that the NWS Tone Alert Weather Radio System had been returned to service."
The licensee notified the NRC Resident Inspector.
"On Friday April 6, 2012, at 0443 EDT, the National Weather Service (NWS) Jacksonville Florida office notified Hatch Nuclear Plant (HNP) of a loss of the NWS Tone Alert Weather Radio System. Site Emergency Procedures define a loss of Tone Alert System for greater than 15 minutes as a significant loss of Emergency Communications.
"The NWS Tone Alert Weather Radios are utilized as the Prompt Notification System (PNS) for HNP. This loss impacts the ability to notify the Emergency Planning Zone (EPZ) population for the HNP. This failure meets NRC 8 hour reporting criteria 10CFR50.72(b)(3)(xiii).
"The State of Georgia Department of Homeland Security / Georgia Emergency Management Agency (GEMA) 24-hour warning point and the '911' dispatch centers of Appling, Jeff Davis, Tattnall and Toombs counties were notified so compensatory measures would be available should the Prompt Notification System be needed. This consists of utilizing route alerting and the 'Code Red' system, which is a reverse 911 feature available from the county 911 center. This notification meets the 4-hour notification reporting criteria 10CFR50.72(b)(2)(xi).
"On Friday April 6, 2012, at 0503 EDT, the NWS Jacksonville Florida office notified HNP that the NWS Tone Alert Weather Radio System had been returned to service."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 47812
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RON FRY
HQ OPS Officer: VINCE KLCO
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RON FRY
HQ OPS Officer: VINCE KLCO
Notification Date: 04/06/2012
Notification Time: 20:33 [ET]
Event Date: 04/06/2012
Event Time: 17:57 [EDT]
Last Update Date: 04/06/2012
Notification Time: 20:33 [ET]
Event Date: 04/06/2012
Event Time: 17:57 [EDT]
Last Update Date: 04/06/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JOHN CARUSO (R1DO)
JOHN CARUSO (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
LOCAL LEAK RATE TEST RESULTS EXCEED PATHWAY TECHNICAL SPECIFICATION LIMITS
"Appendix J local leak rate testing has determined that secondary containment bypass leakage (SCBL) has been exceeded for Unit 1. During performance of leak rate test SE-159-026 for X-9A penetration it was determined the combined SCBL limit of 15 scfh [standard cubic feet per hour] for as-found minimum pathway was exceeded as specified in Tech Spec SR 3.6.1.3.11.
"Acceptance criteria test results were within acceptance criteria for the 10CFR50 Appendix J limits of 0.6 La.
"This event is being reported as a degraded or unanalyzed condition pursuant to 10CFR50.72(b)(3)(ii)."
Licensee corrective actions are to repair the identified valve seats.
The licensee has notified the NRC Resident Inspector.
"Appendix J local leak rate testing has determined that secondary containment bypass leakage (SCBL) has been exceeded for Unit 1. During performance of leak rate test SE-159-026 for X-9A penetration it was determined the combined SCBL limit of 15 scfh [standard cubic feet per hour] for as-found minimum pathway was exceeded as specified in Tech Spec SR 3.6.1.3.11.
"Acceptance criteria test results were within acceptance criteria for the 10CFR50 Appendix J limits of 0.6 La.
"This event is being reported as a degraded or unanalyzed condition pursuant to 10CFR50.72(b)(3)(ii)."
Licensee corrective actions are to repair the identified valve seats.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 47813
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DARRIN GARD
HQ OPS Officer: VINCE KLCO
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DARRIN GARD
HQ OPS Officer: VINCE KLCO
Notification Date: 04/06/2012
Notification Time: 22:18 [ET]
Event Date: 04/06/2012
Event Time: 14:44 [CDT]
Last Update Date: 04/06/2012
Notification Time: 22:18 [ET]
Event Date: 04/06/2012
Event Time: 14:44 [CDT]
Last Update Date: 04/06/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GERALD MCCOY (R2DO)
GERALD MCCOY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
VALID LOAD SHED SIGNAL OCCURRED DUE TO LOSS OF THE 1B STARTUP TRANSFORMER
"At 1444 [CDT] on April 6, 2012, during a planned refueling outage on Unit 1, maintenance activities in the high voltage switchyard caused feeder breaker 820 to inadvertently trip. With the second feeder breaker, 924, already out of service, power was lost to the 1B startup transformer. An undervoltage condition was then experienced on the 1G 4160 V emergency bus. As a result, the B1G Sequencer initiated a valid load shed of the 1G 4160 V emergency bus. Due to outage conditions, the B-Train, 1B Emergency Diesel Generator (EDG) was tagged out and did not automatically start but did receive a valid start signal. None of the ESF loads supplied by the 1G bus started automatically since the 1B EDG was out of service. With a B-Train equipment outage in progress, the 1A RHR pump (A-Train) remained in service for shutdown cooling throughout the event. Although the bus safety function was not needed for plant conditions a valid load shed signal occurred and therefore this event is considered reportable.
"The 1G 4160 V emergency bus was restored to service at 1542 on April 6, 2012. Investigation revealed a technical inaccuracy in the instructions used during the maintenance activity in the high voltage switchyard that caused feeder breaker 820 to trip."
The licensee notified the NRC Resident Inspector.
"At 1444 [CDT] on April 6, 2012, during a planned refueling outage on Unit 1, maintenance activities in the high voltage switchyard caused feeder breaker 820 to inadvertently trip. With the second feeder breaker, 924, already out of service, power was lost to the 1B startup transformer. An undervoltage condition was then experienced on the 1G 4160 V emergency bus. As a result, the B1G Sequencer initiated a valid load shed of the 1G 4160 V emergency bus. Due to outage conditions, the B-Train, 1B Emergency Diesel Generator (EDG) was tagged out and did not automatically start but did receive a valid start signal. None of the ESF loads supplied by the 1G bus started automatically since the 1B EDG was out of service. With a B-Train equipment outage in progress, the 1A RHR pump (A-Train) remained in service for shutdown cooling throughout the event. Although the bus safety function was not needed for plant conditions a valid load shed signal occurred and therefore this event is considered reportable.
"The 1G 4160 V emergency bus was restored to service at 1542 on April 6, 2012. Investigation revealed a technical inaccuracy in the instructions used during the maintenance activity in the high voltage switchyard that caused feeder breaker 820 to trip."
The licensee notified the NRC Resident Inspector.
Agreement State
Event Number: 47860
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: RENEGADE TESTING & INSPECTION, INC.
Region: 1
City: TAMPA State: FL
County:
License #: 3891-2
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: HOWIE CROUCH
Licensee: RENEGADE TESTING & INSPECTION, INC.
Region: 1
City: TAMPA State: FL
County:
License #: 3891-2
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/24/2012
Notification Time: 14:03 [ET]
Event Date: 04/06/2012
Event Time: 00:00 [EDT]
Last Update Date: 04/24/2012
Notification Time: 14:03 [ET]
Event Date: 04/06/2012
Event Time: 00:00 [EDT]
Last Update Date: 04/24/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
TODD JACKSON (R1DO)
ANGELA MCINTOSH (FSME)
TODD JACKSON (R1DO)
ANGELA MCINTOSH (FSME)
FLORIDA AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE TO RADIOGRAPHER
The following information was obtained from the State of Florida via email:
"On April 16, [a licensee] employee notified [the] RSO that his 0-200 pocket detector had gone off scale ten days earlier. His film badge was immediately sent to Rad Detection Services for processing. It was reported to have 25 Rem whole body exposure. This office [Florida Bureau of Radiation Control] was informed on 24 April. The RSO has tried to recreate the scenario but he can't come up with a 4.5 minute exposure scenario. RSO is considering a blood test. Licensee will provide a written report. Florida is investigating."
FL Incident No. FL 12-039
The camera involved was an INC IR-100 Model 32, serial number R887, with a 65 Ci Ir-192 source.
The following information was obtained from the State of Florida via email:
"On April 16, [a licensee] employee notified [the] RSO that his 0-200 pocket detector had gone off scale ten days earlier. His film badge was immediately sent to Rad Detection Services for processing. It was reported to have 25 Rem whole body exposure. This office [Florida Bureau of Radiation Control] was informed on 24 April. The RSO has tried to recreate the scenario but he can't come up with a 4.5 minute exposure scenario. RSO is considering a blood test. Licensee will provide a written report. Florida is investigating."
FL Incident No. FL 12-039
The camera involved was an INC IR-100 Model 32, serial number R887, with a 65 Ci Ir-192 source.