Event Notification Report for July 22, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/21/2014 - 07/22/2014
EVENT NUMBERS
50298502965029350294
Agreement State
Event Number: 50298
Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: EPSILON ENGINEERING & MATERIAL, LLC
Region: 4
City: GOODYEAR State: AZ
County:
License #: AZ 7-534
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: STEVE SANDIN
Licensee: EPSILON ENGINEERING & MATERIAL, LLC
Region: 4
City: GOODYEAR State: AZ
County:
License #: AZ 7-534
Agreement: Y
Docket:
NRC Notified By: AUBREY GODWIN
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/23/2014
Notification Time: 13:35 [ET]
Event Date: 07/22/2014
Event Time: 15:00 [MST]
Last Update Date: 07/25/2014
Notification Time: 13:35 [ET]
Event Date: 07/22/2014
Event Time: 15:00 [MST]
Last Update Date: 07/25/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
GEOFFREY MILLER (R4DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
MEXICO (FAX)
GEOFFREY MILLER (R4DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
MEXICO (FAX)
AGREEMENT STATE REPORT - TROXLER MOISTURE DENSITY GAUGE STOLEN FROM BACK OF A TRUCK
The following information was received from the State of Arizona via email:
"At approximately 1830 MST on July 22, 2014, the Agency [Arizona Radiation Regulatory Agency] was informed that the licensee had a Troxler Model 3430, SN 35843, portable moisture density gauge stolen from the back of a truck. The theft occurred at approximately 1500 MST. The gauge was locked in a metal box fastened to the bed of the truck which was parked unattended at the Fry's parking lot. The gauge contains 10 mCi of Cesium-137 and 40 mCi Am-241:Be.
"Phoenix Police Department [Maryvale] is investigating and has issued report number 20141264003.
"The Agency continues to look for the source.
"The states of CA, NV, CO, UT, and NM, Mexico, U.S. NRC and FBI are being notified of this event."
* * * UPDATE FROM AUBREY GODWIN TO VINCE KLCO AT 1135 EDT ON 7/25/14 * * *
Clarification provided that police department is Phoenix (Maryvale). Address of the incident is 4320 West McDowell Road, Phoenix, AZ 85009.
Notified R4DO (Miller), FSME and ILTAB via email.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
The following information was received from the State of Arizona via email:
"At approximately 1830 MST on July 22, 2014, the Agency [Arizona Radiation Regulatory Agency] was informed that the licensee had a Troxler Model 3430, SN 35843, portable moisture density gauge stolen from the back of a truck. The theft occurred at approximately 1500 MST. The gauge was locked in a metal box fastened to the bed of the truck which was parked unattended at the Fry's parking lot. The gauge contains 10 mCi of Cesium-137 and 40 mCi Am-241:Be.
"Phoenix Police Department [Maryvale] is investigating and has issued report number 20141264003.
"The Agency continues to look for the source.
"The states of CA, NV, CO, UT, and NM, Mexico, U.S. NRC and FBI are being notified of this event."
* * * UPDATE FROM AUBREY GODWIN TO VINCE KLCO AT 1135 EDT ON 7/25/14 * * *
Clarification provided that police department is Phoenix (Maryvale). Address of the incident is 4320 West McDowell Road, Phoenix, AZ 85009.
Notified R4DO (Miller), FSME and ILTAB via email.
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 50296
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL JONES
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CARL JONES
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/22/2014
Notification Time: 21:36 [ET]
Event Date: 07/22/2014
Event Time: 13:43 [EDT]
Last Update Date: 09/02/2014
Notification Time: 21:36 [ET]
Event Date: 07/22/2014
Event Time: 13:43 [EDT]
Last Update Date: 09/02/2014
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):
MEL GRAY (R1DO)
MEL GRAY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
DIESEL GENERATOR FOR HIGH PRESSURE CORE SPRAY DECLARED INOPERABLE DURING SURVEILLANCE TESTING
"This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to Mitigate the Consequences of an Accident. During the conduct of the Unit 2 Division 3 High Pressure Core Spray (HPCS) Diesel Generator (DG) surveillance test, one of 2 Cooling Water Outlet Valves failed to automatically open. The Division 3 Diesel is supplied by two redundant trains of cooling water one from each Service Water Divisional Header. Although the redundant cooling water supply was fully available and supplied adequate cooling to the diesel generator, the DG was at reduced margin to have adequate cooling water supply, if required during a loss of offsite power. Due to this loss of margin and inoperable condition, it has been determined that this failure could potentially affect the safety function of this system, and is being reported as an 8 hour ENS notification."
The licensee has attributed the failure to high resistance in a relay which is currently being replaced. This places Unit 2 in the Technical Specification Action Statement 3.8.1, which requires restoration of Diesel Generator within 72 hours or commence a Reactor Shutdown. All other ECCS Systems have been verified operable.
The licensee informed the NRC Resident Inspector and will inform the State of New York.
* * * RETRACTION AT 1940 EDT ON 9/2/2014 FROM ANTHONY PETRELLI TO MARK ABRAMOVITZ * * *
"This update retracts Event Notification #50296, which reported an event or condition that could have potentially prevented fulfillment of a Safety Function needed to mitigate the consequences of an accident. Upon further review, it was determined that the ability of the HPCS system (single supported train) remained operable and capable of performing its safety function as evaluated by the NMP Unit 2 Safety Function Determination Process (TS 5.5.11).
"The NRC Resident Inspector has been notified."
Notified the R1DO (Ferdas).
"This report is being made pursuant to 10CFR50.72(b)(3)(v)(D), Event or Condition that could have prevented fulfillment of a Safety Function needed to Mitigate the Consequences of an Accident. During the conduct of the Unit 2 Division 3 High Pressure Core Spray (HPCS) Diesel Generator (DG) surveillance test, one of 2 Cooling Water Outlet Valves failed to automatically open. The Division 3 Diesel is supplied by two redundant trains of cooling water one from each Service Water Divisional Header. Although the redundant cooling water supply was fully available and supplied adequate cooling to the diesel generator, the DG was at reduced margin to have adequate cooling water supply, if required during a loss of offsite power. Due to this loss of margin and inoperable condition, it has been determined that this failure could potentially affect the safety function of this system, and is being reported as an 8 hour ENS notification."
The licensee has attributed the failure to high resistance in a relay which is currently being replaced. This places Unit 2 in the Technical Specification Action Statement 3.8.1, which requires restoration of Diesel Generator within 72 hours or commence a Reactor Shutdown. All other ECCS Systems have been verified operable.
The licensee informed the NRC Resident Inspector and will inform the State of New York.
* * * RETRACTION AT 1940 EDT ON 9/2/2014 FROM ANTHONY PETRELLI TO MARK ABRAMOVITZ * * *
"This update retracts Event Notification #50296, which reported an event or condition that could have potentially prevented fulfillment of a Safety Function needed to mitigate the consequences of an accident. Upon further review, it was determined that the ability of the HPCS system (single supported train) remained operable and capable of performing its safety function as evaluated by the NMP Unit 2 Safety Function Determination Process (TS 5.5.11).
"The NRC Resident Inspector has been notified."
Notified the R1DO (Ferdas).
Power Reactor
Event Number: 50293
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: WILLIAM TAYLOR
HQ OPS Officer: DONG HWA PARK
Region: 2 State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: WILLIAM TAYLOR
HQ OPS Officer: DONG HWA PARK
Notification Date: 07/22/2014
Notification Time: 07:53 [ET]
Event Date: 07/22/2014
Event Time: 04:14 [EDT]
Last Update Date: 07/22/2014
Notification Time: 07:53 [ET]
Event Date: 07/22/2014
Event Time: 04:14 [EDT]
Last Update Date: 07/22/2014
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 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 | A/R | Y | 48 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR LEVEL
"At 0414 [EDT on 7/22/2014], VC Summer Nuclear Station automatically tripped due to decreasing water level in the 'C' Steam Generator. The trip occurred when valve XVB-09210 WI System Condensate Bypass Valve failed to open as required while the station was removing the Condensate Polishing System during startup. The Condensate Polishing System is used to purify and filter the condensate from the non-nuclear, secondary side of the plant. This valve failure caused low level in the Deaerator Storage Tank, which consequently tripped all feedwater pumps. This loss of feedwater led to Lo-Lo Steam Generator level in the 'C' Steam Generator. All Emergency Feedwater pumps automatically started on Lo-Lo Steam Generator level and all control rods inserted fully. The Steam Generator levels recovered quickly.
"Presently the plant is in Mode 3. Decay heat is being removed by dumping steam to the condenser. A station response team is actively investigating the cause of the event.
"The NRC Resident Inspector has been notified."
The licensee will notify the State and local governments.
"At 0414 [EDT on 7/22/2014], VC Summer Nuclear Station automatically tripped due to decreasing water level in the 'C' Steam Generator. The trip occurred when valve XVB-09210 WI System Condensate Bypass Valve failed to open as required while the station was removing the Condensate Polishing System during startup. The Condensate Polishing System is used to purify and filter the condensate from the non-nuclear, secondary side of the plant. This valve failure caused low level in the Deaerator Storage Tank, which consequently tripped all feedwater pumps. This loss of feedwater led to Lo-Lo Steam Generator level in the 'C' Steam Generator. All Emergency Feedwater pumps automatically started on Lo-Lo Steam Generator level and all control rods inserted fully. The Steam Generator levels recovered quickly.
"Presently the plant is in Mode 3. Decay heat is being removed by dumping steam to the condenser. A station response team is actively investigating the cause of the event.
"The NRC Resident Inspector has been notified."
The licensee will notify the State and local governments.
Power Reactor
Event Number: 50294
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: NICHOLAS E. RULLMAN
HQ OPS Officer: STEVE SANDIN
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: NICHOLAS E. RULLMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/22/2014
Notification Time: 16:57 [ET]
Event Date: 07/22/2014
Event Time: 06:35 [PDT]
Last Update Date: 07/28/2014
Notification Time: 16:57 [ET]
Event Date: 07/22/2014
Event Time: 06:35 [PDT]
Last Update Date: 07/28/2014
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):
GEOFFREY MILLER (R4DO)
GEOFFREY MILLER (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
RADIATION MONITORING SAMPLE RACK DECLARED NON-FUNCTIONAL
"At 0635 hours PDT on July 22, 2014, Turbine Building Exhaust Air Radiation Indicating Switch (TEA-RIS-13) and the Turbine Building Process Radiation Monitoring Sample Rack (TEA-SR-26) were declared non-functional. The cause of the malfunction is under investigation. Compensatory measures have been implemented to obtain radiation readings from the associated effluent release pathway. Field team assessment function was unaffected and remains available.
"This event is being reported as a major loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE FROM DUANE SALSBURY TO DONALD NORWOOD AT 2018 EDT ON 7/28/2014 * * *
"At 1351 PDT on 7/28/2014, Turbine Building Exhaust Air Radiation Indicating Switch (TES-RIS-13) and Turbine Building Process Radiation Monitoring Sample Rack (TES-SR-26) were declared functional.
"The NRC Resident Inspector has been notified."
Notified R4DO (O'Keefe).
"At 0635 hours PDT on July 22, 2014, Turbine Building Exhaust Air Radiation Indicating Switch (TEA-RIS-13) and the Turbine Building Process Radiation Monitoring Sample Rack (TEA-SR-26) were declared non-functional. The cause of the malfunction is under investigation. Compensatory measures have been implemented to obtain radiation readings from the associated effluent release pathway. Field team assessment function was unaffected and remains available.
"This event is being reported as a major loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE FROM DUANE SALSBURY TO DONALD NORWOOD AT 2018 EDT ON 7/28/2014 * * *
"At 1351 PDT on 7/28/2014, Turbine Building Exhaust Air Radiation Indicating Switch (TES-RIS-13) and Turbine Building Process Radiation Monitoring Sample Rack (TES-SR-26) were declared functional.
"The NRC Resident Inspector has been notified."
Notified R4DO (O'Keefe).