Event Notification Report for July 22, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/21/2015 - 07/22/2015
EVENT NUMBERS
5124751250512545127051273
Power Reactor
Event Number: 51247
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: TODD CASAGRANDE
HQ OPS Officer: DONG HWA PARK
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: TODD CASAGRANDE
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/22/2015
Notification Time: 07:08 [ET]
Event Date: 07/22/2015
Event Time: 00:13 [CDT]
Last Update Date: 07/22/2015
Notification Time: 07:08 [ET]
Event Date: 07/22/2015
Event Time: 00:13 [CDT]
Last Update Date: 07/22/2015
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):
MICHAEL KUNOWSKI (R3DO)
MICHAEL KUNOWSKI (R3DO)
| 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 |
SEISMIC MONITOR INOPERABLE
"[At] 0013 CDT, [on] 7/22/15, the seismic monitor was found inoperable. The seismic monitor was inoperable such that emergency classification at the ALERT level could not be obtained with site instrumentation.
"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).
"[The NRC] Senior Resident Inspector has been notified."
"[At] 0013 CDT, [on] 7/22/15, the seismic monitor was found inoperable. The seismic monitor was inoperable such that emergency classification at the ALERT level could not be obtained with site instrumentation.
"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).
"[The NRC] Senior Resident Inspector has been notified."
Power Reactor
Event Number: 51250
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: JOHN RIDINGER
HQ OPS Officer: DONALD NORWOOD
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: JOHN RIDINGER
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/22/2015
Notification Time: 12:38 [ET]
Event Date: 07/22/2015
Event Time: 04:45 [CDT]
Last Update Date: 07/22/2015
Notification Time: 12:38 [ET]
Event Date: 07/22/2015
Event Time: 04:45 [CDT]
Last Update Date: 07/22/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RANDY MUSSER (R2DO)
RANDY MUSSER (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 |
HPCI DECLARED INOPERABLE
"During the performance of the Unit 1 quarterly surveillance 1-SR-3.6.1.3.5 (HPCI), HPCI [High Pressure Coolant Injection] System Motor Operated Valve Operability, the inboard steam isolation valve failed to close within the required time. The valve was subsequently declared inoperable and Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 (Primary Containment Isolation Valves (PCIVs)) was entered which required the HPCI steam line to be closed and de-activated. To comply with TS LCO 3.6.1.3 Condition A, the outboard steam isolation valve was closed and breaker opened. Due to the steam line being isolated, TS 3.5.1, ECCS Operating, Condition C was entered on July 22, 2015 at 0445 CDT as a result of the inoperable HPCI system. Troubleshooting and repair is in progress and during this inoperability, other systems are available to provide the required safety functions.
"This constitutes an unplanned HPCI system inoperability and requires an 8-hour ENS notification in accordance with 10 CFR 50.72(b)(3)(v)(D), due to the failure of a single train system affecting accident mitigation, and a 60-day written report in accordance with 10 CFR 50.73(a)(2)(v)(D).
"The NRC Resident Inspector has been notified."
"During the performance of the Unit 1 quarterly surveillance 1-SR-3.6.1.3.5 (HPCI), HPCI [High Pressure Coolant Injection] System Motor Operated Valve Operability, the inboard steam isolation valve failed to close within the required time. The valve was subsequently declared inoperable and Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 (Primary Containment Isolation Valves (PCIVs)) was entered which required the HPCI steam line to be closed and de-activated. To comply with TS LCO 3.6.1.3 Condition A, the outboard steam isolation valve was closed and breaker opened. Due to the steam line being isolated, TS 3.5.1, ECCS Operating, Condition C was entered on July 22, 2015 at 0445 CDT as a result of the inoperable HPCI system. Troubleshooting and repair is in progress and during this inoperability, other systems are available to provide the required safety functions.
"This constitutes an unplanned HPCI system inoperability and requires an 8-hour ENS notification in accordance with 10 CFR 50.72(b)(3)(v)(D), due to the failure of a single train system affecting accident mitigation, and a 60-day written report in accordance with 10 CFR 50.73(a)(2)(v)(D).
"The NRC Resident Inspector has been notified."
Agreement State
Event Number: 51254
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: PHILLIPS 66 BAYWAY REFINERY
Region: 1
City: LINDEN State: NJ
County:
License #: 50897-RAD1500
Agreement: Y
Docket:
NRC Notified By: JACK TWAY
HQ OPS Officer: JEFF ROTTON
Licensee: PHILLIPS 66 BAYWAY REFINERY
Region: 1
City: LINDEN State: NJ
County:
License #: 50897-RAD1500
Agreement: Y
Docket:
NRC Notified By: JACK TWAY
HQ OPS Officer: JEFF ROTTON
Notification Date: 07/23/2015
Notification Time: 14:53 [ET]
Event Date: 07/22/2015
Event Time: 00:00 [EDT]
Last Update Date: 07/23/2015
Notification Time: 14:53 [ET]
Event Date: 07/22/2015
Event Time: 00:00 [EDT]
Last Update Date: 07/23/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
SILAS KENNEDY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
SILAS KENNEDY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
NEW JERSEY AGREEMENT STATE REPORT - FIXED GAUGE WITH STUCK OPEN SHUTTER
The following information was provided by the State of New Jersey via email:
"On 7/22/2015, an inspection was conducted of an Ohio fixed gauge service provider working in NJ under reciprocity for a NJ specific licensee. The inspector was made aware that a fixed gauge had failed to shutter when attempted by the licensee. At this time, it is not known when the shutter failed. The gauge was in otherwise normal condition and no members of the public had access to the gauge due to engineering controls. The service provider replaced the air actuator and rotor during the inspection and the shutter was then functioning normally. The licensee was contacted by NJ and committed to providing the report required by 10 CFR 30.50(c).
"Location: Phillips 66 Bayway Refinery, Linden, NJ
"License No.: 506897-RAD150001
"Device: Vega SH-F1A (with air actuator) serial number 0317 CG, containing 50 mCi (Assay date 1/2001) [Cs-137 contained in gauge]
"Follow-up information will be provided when it is known."
The following information was provided by the State of New Jersey via email:
"On 7/22/2015, an inspection was conducted of an Ohio fixed gauge service provider working in NJ under reciprocity for a NJ specific licensee. The inspector was made aware that a fixed gauge had failed to shutter when attempted by the licensee. At this time, it is not known when the shutter failed. The gauge was in otherwise normal condition and no members of the public had access to the gauge due to engineering controls. The service provider replaced the air actuator and rotor during the inspection and the shutter was then functioning normally. The licensee was contacted by NJ and committed to providing the report required by 10 CFR 30.50(c).
"Location: Phillips 66 Bayway Refinery, Linden, NJ
"License No.: 506897-RAD150001
"Device: Vega SH-F1A (with air actuator) serial number 0317 CG, containing 50 mCi (Assay date 1/2001) [Cs-137 contained in gauge]
"Follow-up information will be provided when it is known."
Power Reactor
Event Number: 51270
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: JULIE BISSEN
HQ OPS Officer: JOHN SHOEMAKER
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: JULIE BISSEN
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 07/27/2015
Notification Time: 18:01 [ET]
Event Date: 07/22/2015
Event Time: 13:30 [CDT]
Last Update Date: 07/27/2015
Notification Time: 18:01 [ET]
Event Date: 07/22/2015
Event Time: 13:30 [CDT]
Last Update Date: 07/27/2015
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):
GREG WARNICK (R4DO)
GREG WARNICK (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
DEGRADED CONDITION DUE TO REACTOR COOLANT SYSTEM LEAK
"On July 8, 2015, Fort Calhoun Station was in Mode 1, 100% when personnel identified an increase in the Reactor Coolant System unidentified leakage rate. As a result, personnel performed a containment entry and identified the source coming from the Reactor Coolant Pump 3A seal area. Based on this observation, a monitoring plan was established and on July 20, 2015 the leak rate exceeded the pre-establish leak limit and operators manually shutdown the reactor. On July 22, 2015, at approximately 1330 CDT, personnel identified the source of the seal leak as a crack on the middle seal inlet line, which is part of the reactor coolant system boundary. Maintenance personnel have since repaired the seal line and it has passed post-maintenance testing.
"The 8-hour verbal report is being made post event due to additional review of the leakage condition identifying the leakage constituted a degraded condition due to be material defects in the primary coolant system."
The leak rate was between 1 and 2 gpm.
The licensee notified the NRC Resident Inspector.
"On July 8, 2015, Fort Calhoun Station was in Mode 1, 100% when personnel identified an increase in the Reactor Coolant System unidentified leakage rate. As a result, personnel performed a containment entry and identified the source coming from the Reactor Coolant Pump 3A seal area. Based on this observation, a monitoring plan was established and on July 20, 2015 the leak rate exceeded the pre-establish leak limit and operators manually shutdown the reactor. On July 22, 2015, at approximately 1330 CDT, personnel identified the source of the seal leak as a crack on the middle seal inlet line, which is part of the reactor coolant system boundary. Maintenance personnel have since repaired the seal line and it has passed post-maintenance testing.
"The 8-hour verbal report is being made post event due to additional review of the leakage condition identifying the leakage constituted a degraded condition due to be material defects in the primary coolant system."
The leak rate was between 1 and 2 gpm.
The licensee notified the NRC Resident Inspector.
Agreement State
Event Number: 51273
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: DOMTAR PAPER COMPANY, LLC
Region: 1
City: PLYMOUTH State: NC
County:
License #: NC RAM #094-0
Agreement: Y
Docket:
NRC Notified By: DAVID CROWLEY
HQ OPS Officer: JOHN SHOEMAKER
Licensee: DOMTAR PAPER COMPANY, LLC
Region: 1
City: PLYMOUTH State: NC
County:
License #: NC RAM #094-0
Agreement: Y
Docket:
NRC Notified By: DAVID CROWLEY
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 07/28/2015
Notification Time: 16:59 [ET]
Event Date: 07/22/2015
Event Time: 00:00 [EDT]
Last Update Date: 07/28/2015
Notification Time: 16:59 [ET]
Event Date: 07/22/2015
Event Time: 00:00 [EDT]
Last Update Date: 07/28/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RAY MCKINLEY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
RAY MCKINLEY (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
AGREEMENT STATE REPORT - FIXED GAUGE WITH SHUTTER STUCK CLOSED
The following report was received from the State of North Carolina (NC) via email:
The licensee was performing routine maintenance and leak testing checks on a Berthold fixed nuclear density gauge when they discovered its shutter was stuck in the closed position. This maintenance record was dated for 7/22/2015 and listed that the device needed cleaning, showed signs of mild to moderate corrosion, the shutter failed to open, and replacement was necessary. The closed shutter was verified by a survey meter and its detector response. The [North Carolina] State was notified the following week, on 7/27/2015. The gauge manufacturer, Berthold, had already been contracted to dispose of the source and device. No exposures or radiation safety concerns have resulted from this failed shutter at this time and none are expected.
The Berthold Fixed Nuclear Gauge is serial #6625, model# LB7440 with a Berthold source serial #1329, model #D7547, 20 mCi Cs-137 source (as of 5/98). The last leak test performed March 28, 2013, that passed according to Thermofisher (3 year leak test requirement). Berthold will perform another leak test before transporting off site.
The cause of the stuck shutter is dirt and corrosion products that appear to be the leading cause of the shutter failing in the closed position. NC will follow up with the licensee to determine if dirt accumulation and corrosion occurred by operating in environmental conditions outside of the manufacturer's intentions.
NC State report: NC NMED #150022.
The following report was received from the State of North Carolina (NC) via email:
The licensee was performing routine maintenance and leak testing checks on a Berthold fixed nuclear density gauge when they discovered its shutter was stuck in the closed position. This maintenance record was dated for 7/22/2015 and listed that the device needed cleaning, showed signs of mild to moderate corrosion, the shutter failed to open, and replacement was necessary. The closed shutter was verified by a survey meter and its detector response. The [North Carolina] State was notified the following week, on 7/27/2015. The gauge manufacturer, Berthold, had already been contracted to dispose of the source and device. No exposures or radiation safety concerns have resulted from this failed shutter at this time and none are expected.
The Berthold Fixed Nuclear Gauge is serial #6625, model# LB7440 with a Berthold source serial #1329, model #D7547, 20 mCi Cs-137 source (as of 5/98). The last leak test performed March 28, 2013, that passed according to Thermofisher (3 year leak test requirement). Berthold will perform another leak test before transporting off site.
The cause of the stuck shutter is dirt and corrosion products that appear to be the leading cause of the shutter failing in the closed position. NC will follow up with the licensee to determine if dirt accumulation and corrosion occurred by operating in environmental conditions outside of the manufacturer's intentions.
NC State report: NC NMED #150022.