Event Notification Report for April 07, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/06/2015 - 04/07/2015
EVENT NUMBERS
5096150962509635096550966
Power Reactor
Event Number: 50961
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAN GENEVA
HQ OPS Officer: VINCE KLCO
Region: 1 State: MD
Unit: [1] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAN GENEVA
HQ OPS Officer: VINCE KLCO
Notification Date: 04/07/2015
Notification Time: 15:45 [ET]
Event Date: 04/07/2015
Event Time: 12:45 [EDT]
Last Update Date: 04/09/2015
Notification Time: 15:45 [ET]
Event Date: 04/07/2015
Event Time: 12:45 [EDT]
Last Update Date: 04/09/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION 50.72(b)(3)(v)(B) - POT RHR INOP 50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
MARC FERDAS (R1DO)
JEFFERY GRANT (IRD)
SCOTT MORRIS (NRR)
MARC FERDAS (R1DO)
JEFFERY GRANT (IRD)
SCOTT MORRIS (NRR)
| 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 |
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
DUAL UNIT AUTOMATIC REACTOR TRIPS DUE TO A VOLTAGE TRANSIENT RESULTING IN GENERATOR TRIPS
"A loss of Main Generator Load which caused a Reactor Trip on Units 1 & 2. A switchyard voltage transient from a highline occurred, which caused an undervoltage condition on both units' safety related 4KV buses.
"Unit 1 is on normal heat removal to the condenser.
"Unit 2 is on auxiliary feedwater and normal condenser bypass valves for temperature control. An Auxiliary Feedwater Actuation System (AFAS) actuation occurred on Unit 2.
"The [Unit 2] 2B emergency diesel generator did not start and load on its respective 24-4 KV bus. The 24-4KV Bus was repowered from the alternate feeder breaker. Cause of the emergency diesel failure to start is under investigation.
"All safety functions are met for both units."
All control rods fully inserted. The site is in a normal shutdown electrical configuration powered from offsite. The site plans to stay in Mode 3 pending restart.
The licensee notified the NRC Resident Inspector, State and local authorities. A press release is planned.
* * * UPDATE FROM JAY GAINES TO DANIEL MILLS AT 0129 EDT ON 4/9/2015 * * *
"During post trip review, it was determined that the 21 saltwater pump had to be manually started. With the failure of 2B emergency diesel generator, there were no saltwater pumps running for approximately 12 minutes. Additional troubleshooting determined the 2A emergency diesel generator sequencer did not automatically start 21 saltwater pump. The 2B emergency diesel generator was returned to service on 4/8/2015 at 1730 [EDT]. The loss of saltwater [pump] and emergency diesel generator is reportable as an event that could have prevented fulfillment of a safety function and is also an unanalyzed condition."
The licensee has notified the NRC Resident Inspector. Notified R1DO (Ferdas), IRD MOC (Grant), NRR EO (Morris).
"A loss of Main Generator Load which caused a Reactor Trip on Units 1 & 2. A switchyard voltage transient from a highline occurred, which caused an undervoltage condition on both units' safety related 4KV buses.
"Unit 1 is on normal heat removal to the condenser.
"Unit 2 is on auxiliary feedwater and normal condenser bypass valves for temperature control. An Auxiliary Feedwater Actuation System (AFAS) actuation occurred on Unit 2.
"The [Unit 2] 2B emergency diesel generator did not start and load on its respective 24-4 KV bus. The 24-4KV Bus was repowered from the alternate feeder breaker. Cause of the emergency diesel failure to start is under investigation.
"All safety functions are met for both units."
All control rods fully inserted. The site is in a normal shutdown electrical configuration powered from offsite. The site plans to stay in Mode 3 pending restart.
The licensee notified the NRC Resident Inspector, State and local authorities. A press release is planned.
* * * UPDATE FROM JAY GAINES TO DANIEL MILLS AT 0129 EDT ON 4/9/2015 * * *
"During post trip review, it was determined that the 21 saltwater pump had to be manually started. With the failure of 2B emergency diesel generator, there were no saltwater pumps running for approximately 12 minutes. Additional troubleshooting determined the 2A emergency diesel generator sequencer did not automatically start 21 saltwater pump. The 2B emergency diesel generator was returned to service on 4/8/2015 at 1730 [EDT]. The loss of saltwater [pump] and emergency diesel generator is reportable as an event that could have prevented fulfillment of a safety function and is also an unanalyzed condition."
The licensee has notified the NRC Resident Inspector. Notified R1DO (Ferdas), IRD MOC (Grant), NRR EO (Morris).
Power Reactor
Event Number: 50962
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: CRYSTIAN IOPPOLO
HQ OPS Officer: STEVE SANDIN
Region: 2 State: NC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: CRYSTIAN IOPPOLO
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/07/2015
Notification Time: 16:38 [ET]
Event Date: 04/07/2015
Event Time: 11:47 [EDT]
Last Update Date: 04/09/2015
Notification Time: 16:38 [ET]
Event Date: 04/07/2015
Event Time: 11:47 [EDT]
Last Update Date: 04/09/2015
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):
JAMIE HEISSERER (R2DO)
JAMIE HEISSERER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
REACTOR VESSEL HEAD PENETRATION FLAW IDENTIFIED DURING INSERVICE INSPECTION
"This is a non-emergency report.
"On April 7, 2015, while the Harris Nuclear Plant was shut down for a scheduled refueling outage, the reactor vessel head penetrations were being examined in accordance with Inservice Inspection Program. Ultrasonic examinations identified a flaw in a head penetration nozzle. The unit is in a safe and stable condition. The flaw will be repaired prior to startup from the refueling outage.
"The flaw and repair have no impact to the health or safety of the public.
"The NRC Resident Inspector has been informed."
An extent of condition investigation is on-going.
* * * UPDATE AT 1644 EDT ON 4/9/15 FROM JOHN CAVES TO JEFF HERRERA * * *
"During the ongoing reactor vessel head penetration examinations, two additional flaws were identified in head penetration nozzles. The unit remains in a safe and stable condition. All of the identified flaws will be repaired prior to startup from the refueling outage. The remaining examinations are in progress to determine the extent of condition.
"The NRC Resident Inspector has been notified."
Notified R2DO (Heisserer)
"This is a non-emergency report.
"On April 7, 2015, while the Harris Nuclear Plant was shut down for a scheduled refueling outage, the reactor vessel head penetrations were being examined in accordance with Inservice Inspection Program. Ultrasonic examinations identified a flaw in a head penetration nozzle. The unit is in a safe and stable condition. The flaw will be repaired prior to startup from the refueling outage.
"The flaw and repair have no impact to the health or safety of the public.
"The NRC Resident Inspector has been informed."
An extent of condition investigation is on-going.
* * * UPDATE AT 1644 EDT ON 4/9/15 FROM JOHN CAVES TO JEFF HERRERA * * *
"During the ongoing reactor vessel head penetration examinations, two additional flaws were identified in head penetration nozzles. The unit remains in a safe and stable condition. All of the identified flaws will be repaired prior to startup from the refueling outage. The remaining examinations are in progress to determine the extent of condition.
"The NRC Resident Inspector has been notified."
Notified R2DO (Heisserer)
Agreement State
Event Number: 50963
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: BAYER MATERIALSCIENCE LLC
Region: 4
City: BAYTOWN State: TX
County:
License #: 01577
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Licensee: BAYER MATERIALSCIENCE LLC
Region: 4
City: BAYTOWN State: TX
County:
License #: 01577
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/07/2015
Notification Time: 17:31 [ET]
Event Date: 04/07/2015
Event Time: 00:00 [CDT]
Last Update Date: 04/07/2015
Notification Time: 17:31 [ET]
Event Date: 04/07/2015
Event Time: 00:00 [CDT]
Last Update Date: 04/07/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
AGREEMENT STATE REPORT - STUCK SHUTTER ON A FIXED GAUGE
The following information was received from the State of Texas via fax:
"On April 7, 2015, the Agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer (RSO) that they were unable to close the shutter on a Berthold Model LB 300 IRL Type 1 source holder containing three Cobalt - 60 sources. The licensee found the problem during routine checks. The RSO stated they had contacted the manufacturer for assistance. The RSO stated there was no increased risk of exposure to members of the general public or the employees at the facility. This Agency contacted the manufacturer on April 7, 2015 and requested the seal source and device (SSD) data sheet for the device. At 1206 hours [CDT], the Agency received an email from the manufacturer containing the SSD sheet for the gauge. The email also stated the gauge had been repaired and was now operating properly. The specifics of the event were not provided by the RSO as he was still investigating the event. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9298
The following information was received from the State of Texas via fax:
"On April 7, 2015, the Agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer (RSO) that they were unable to close the shutter on a Berthold Model LB 300 IRL Type 1 source holder containing three Cobalt - 60 sources. The licensee found the problem during routine checks. The RSO stated they had contacted the manufacturer for assistance. The RSO stated there was no increased risk of exposure to members of the general public or the employees at the facility. This Agency contacted the manufacturer on April 7, 2015 and requested the seal source and device (SSD) data sheet for the device. At 1206 hours [CDT], the Agency received an email from the manufacturer containing the SSD sheet for the gauge. The email also stated the gauge had been repaired and was now operating properly. The specifics of the event were not provided by the RSO as he was still investigating the event. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9298
Power Reactor
Event Number: 50965
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HUNTER SCHILL
HQ OPS Officer: STEVE SANDIN
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HUNTER SCHILL
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/07/2015
Notification Time: 18:50 [ET]
Event Date: 04/07/2015
Event Time: 11:00 [CDT]
Last Update Date: 04/07/2015
Notification Time: 18:50 [ET]
Event Date: 04/07/2015
Event Time: 11:00 [CDT]
Last Update Date: 04/07/2015
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):
RAY AZUA (R4DO)
RAY AZUA (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
INOPERABLE SEISMIC INSTRUMENTATION IDENTIFIED DURING HISTORICAL REVIEW
"Luminant Generation Company LLC (Luminant Power) has completed a review of seismic monitor performance at the Comanche Peak Nuclear Power Plant (CPNPP) over the last three years. The CPNPP emergency preparedness plan requires seismic monitoring instruments to diagnose an earthquake for emergency action levels (EAL) HA1.1 seismic event greater than OBE (operating basis earthquake) and HU1.1 identified seismic event that is less than the OBE. The seismic monitor performance review identified one unplanned instance of monitor unavailability and three instances when planned monitor outage durations exceeded 24 hours. Any loss of seismic monitoring capability results in a major loss of assessment capability for the Alert (HA1.1) and a degraded assessment capability for the Unusual Event (HU1.1) emergency classification. The seismic monitor is currently functional, however, it was determined to be non-functional on the following dates:
"Unplanned out-of-service:
12/4/2013 through 12/10/2013
Planned out-of-service lasting greater than 24 hours:
5/16/2012 through 5/24/2012
3/20/2013 through 3/27/2013
9/29/2014 through 10/1/2014
"The loss of assessment capability is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). This report is required per 10 CFR 50.72(a)(1)(ii) as an event that occurred within 3 years of the date of discovery. The seismic monitor issues and the missed reporting of the loss of assessment capability have been documented in the CPNPP corrective action program."
This review was prompted by a licensee evaluation of industry operating experience. A similar report was received from Limerick Generating Station - EN # 50951.
The licensee informed the NRC Resident Inspector.
"Luminant Generation Company LLC (Luminant Power) has completed a review of seismic monitor performance at the Comanche Peak Nuclear Power Plant (CPNPP) over the last three years. The CPNPP emergency preparedness plan requires seismic monitoring instruments to diagnose an earthquake for emergency action levels (EAL) HA1.1 seismic event greater than OBE (operating basis earthquake) and HU1.1 identified seismic event that is less than the OBE. The seismic monitor performance review identified one unplanned instance of monitor unavailability and three instances when planned monitor outage durations exceeded 24 hours. Any loss of seismic monitoring capability results in a major loss of assessment capability for the Alert (HA1.1) and a degraded assessment capability for the Unusual Event (HU1.1) emergency classification. The seismic monitor is currently functional, however, it was determined to be non-functional on the following dates:
"Unplanned out-of-service:
12/4/2013 through 12/10/2013
Planned out-of-service lasting greater than 24 hours:
5/16/2012 through 5/24/2012
3/20/2013 through 3/27/2013
9/29/2014 through 10/1/2014
"The loss of assessment capability is reportable to the NRC within 8 hours of discovery in accordance with 10 CFR 50.72(b)(3)(xiii). This report is required per 10 CFR 50.72(a)(1)(ii) as an event that occurred within 3 years of the date of discovery. The seismic monitor issues and the missed reporting of the loss of assessment capability have been documented in the CPNPP corrective action program."
This review was prompted by a licensee evaluation of industry operating experience. A similar report was received from Limerick Generating Station - EN # 50951.
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 50966
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: PAUL FINHOLM
HQ OPS Officer: STEVE SANDIN
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: PAUL FINHOLM
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/07/2015
Notification Time: 22:33 [ET]
Event Date: 04/07/2015
Event Time: 17:45 [CDT]
Last Update Date: 04/07/2015
Notification Time: 22:33 [ET]
Event Date: 04/07/2015
Event Time: 17:45 [CDT]
Last Update Date: 04/07/2015
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):
RICHARD SKOKOWSKI (R3DO)
RICHARD SKOKOWSKI (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Standby |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
INADVERTENT EMERGENCY SIREN ACTIVATION
"At approximately 1833 CDT on April 07, 2015, the licensee was notified by the siren vendor (NELCOM) that Dakota County Dispatch reported an inadvertent activation of an emergency siren (D-1), in Dakota County, MN. The cause of the siren activation is unknown. The siren was deactivated at 1810 CDT after sounding for approximately 25 minutes. The siren vendor (NELCOM) has been contacted to repair the siren. The siren remains out of service. This is the only siren out of service within the 10 mile Emergency Planning Zone (EPZ).
"There are 123 Emergency Notification sirens. Of the seven (7) credited sirens in Dakota County, six (6) remain in service. Thus, emergency notification capabilities remain in effect.
"NRC Resident has been informed."
"At approximately 1833 CDT on April 07, 2015, the licensee was notified by the siren vendor (NELCOM) that Dakota County Dispatch reported an inadvertent activation of an emergency siren (D-1), in Dakota County, MN. The cause of the siren activation is unknown. The siren was deactivated at 1810 CDT after sounding for approximately 25 minutes. The siren vendor (NELCOM) has been contacted to repair the siren. The siren remains out of service. This is the only siren out of service within the 10 mile Emergency Planning Zone (EPZ).
"There are 123 Emergency Notification sirens. Of the seven (7) credited sirens in Dakota County, six (6) remain in service. Thus, emergency notification capabilities remain in effect.
"NRC Resident has been informed."