Event Notification Report for February 08, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/07/2013 - 02/08/2013
EVENT NUMBERS
4873348734487354873649576
Power Reactor
Event Number: 48733
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MIKE FULLER
HQ OPS Officer: BILL HUFFMAN
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MIKE FULLER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/08/2013
Notification Time: 11:50 [ET]
Event Date: 02/08/2013
Event Time: 09:45 [CST]
Last Update Date: 02/08/2013
Notification Time: 11:50 [ET]
Event Date: 02/08/2013
Event Time: 09:45 [CST]
Last Update Date: 02/08/2013
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):
DON ALLEN (R4DO)
DON ALLEN (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
MINOR HYDRAULIC OIL SPILL ONSITE
"A hydraulic oil line break occurred on a crane inside of the protected area. The break resulted in a 2-gallon spill of hydraulic oil.
"Wolf Creek has notified the National Response Center and Kansas Department of Health and Environment. The oil spill is being cleaned up by our environmental group."
The licensee has notified the NRC Resident Inspector.
"A hydraulic oil line break occurred on a crane inside of the protected area. The break resulted in a 2-gallon spill of hydraulic oil.
"Wolf Creek has notified the National Response Center and Kansas Department of Health and Environment. The oil spill is being cleaned up by our environmental group."
The licensee has notified the NRC Resident Inspector.
Non-Agreement State
Event Number: 48734
Rep Org: AVERILL ENVIRONMENTAL LABS
Licensee: AVERILL ENVIRONMENTAL LABS
Region: 1
City: PLAINVILLE State: CT
County:
License #: 06-23384-01
Agreement: N
Docket:
NRC Notified By: LAWTON AVERILL
HQ OPS Officer: BILL HUFFMAN
Licensee: AVERILL ENVIRONMENTAL LABS
Region: 1
City: PLAINVILLE State: CT
County:
License #: 06-23384-01
Agreement: N
Docket:
NRC Notified By: LAWTON AVERILL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/08/2013
Notification Time: 14:10 [ET]
Event Date: 02/08/2013
Event Time: 00:00 [EST]
Last Update Date: 02/08/2013
Notification Time: 14:10 [ET]
Event Date: 02/08/2013
Event Time: 00:00 [EST]
Last Update Date: 02/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
10 CFR Section:
20.2201(a)(1)(ii) - LOST/STOLEN LNM>10X
Person (Organization):
RAY POWELL (R1DO)
FSME EVENTS RESOURCE (E-MA)
RAY POWELL (R1DO)
FSME EVENTS RESOURCE (E-MA)
MISSING NICKEL-63 SOURCE USED FOR ELECTRON CAPTURE DETECTOR
The licensee called to report a missing 15 millicurie Nickel-63 source (serial #5404) used in a gas chromatograph electron capture detector. The licensee is in the process of moving their business location and discovered that this specific source was missing. It was last inventoried 29 days ago. All other sources possessed by the licensee have been accounted for. The licensee is still searching for the source which may have been misplaced in the move. However, there is a possibility that the source may have been inadvertently disposed.
The licensee has notified NRC Region 1 (Jackson).
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 licensee called to report a missing 15 millicurie Nickel-63 source (serial #5404) used in a gas chromatograph electron capture detector. The licensee is in the process of moving their business location and discovered that this specific source was missing. It was last inventoried 29 days ago. All other sources possessed by the licensee have been accounted for. The licensee is still searching for the source which may have been misplaced in the move. However, there is a possibility that the source may have been inadvertently disposed.
The licensee has notified NRC Region 1 (Jackson).
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
Part 21
Event Number: 48735
Rep Org: GE HITACHI NUCLEAR ENERGY
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DALE PORTER
HQ OPS Officer: PETE SNYDER
Licensee: GE HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DALE PORTER
HQ OPS Officer: PETE SNYDER
Notification Date: 02/08/2013
Notification Time: 16:32 [ET]
Event Date: 02/08/2013
Event Time: 00:00 [EST]
Last Update Date: 02/08/2013
Notification Time: 16:32 [ET]
Event Date: 02/08/2013
Event Time: 00:00 [EST]
Last Update Date: 02/08/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
RAY POWELL (R1DO)
GEORGE HOPPER (R2DO)
MICHAEL KUNOWSKI (R3DO)
DON ALLEN (R4DO)
PART 21 REACTORS (EMAI)
RAY POWELL (R1DO)
GEORGE HOPPER (R2DO)
MICHAEL KUNOWSKI (R3DO)
DON ALLEN (R4DO)
PART 21 REACTORS (EMAI)
PART 21 - COMPLETED EVALUATION FOR POTENTIAL ERROR IN MAIN STEAM LINE HIGH FLOW CALCULATIONAL METHODOLOGY
"GEH recently discovered that some calculations of the choked flow rate in the Main Steam Lines (MSLs) of GEH BWRs were non-conservative, with potential effects on margins between choked flow conditions and existing MSL high-flow Nominal Trip Setpoints (NTSPs), Allowable Values (AVs), and Analytical Limits (ALs).
"GEH has now completed the evaluation of this condition and has determined this condition is not reportable under 10 CFR 21 for all U.S. BWR/2-6 plants. The effect of the discovered non-conservatisms in choked flow rate values was offset by unintended conservatisms in the GEH recommended formulation for calculating pressure drop across the MSL flow restrictor. As a result, GEH has determined that the flow-instrument pressure remain at conservative values (which would ensure that the associated NTSPs and AVs expressed in psid also remain at conservative values), and the MSL high-flow trip will function as designed. This update to the 60-day Interim Notification issued on December 12, 2012 (MFN 12-111 R1) will be sent to all US BWR/2-6 plants licensed using the GEH design basis and safety analysis."
See previous NRC Event Report 48350.
"GEH recently discovered that some calculations of the choked flow rate in the Main Steam Lines (MSLs) of GEH BWRs were non-conservative, with potential effects on margins between choked flow conditions and existing MSL high-flow Nominal Trip Setpoints (NTSPs), Allowable Values (AVs), and Analytical Limits (ALs).
"GEH has now completed the evaluation of this condition and has determined this condition is not reportable under 10 CFR 21 for all U.S. BWR/2-6 plants. The effect of the discovered non-conservatisms in choked flow rate values was offset by unintended conservatisms in the GEH recommended formulation for calculating pressure drop across the MSL flow restrictor. As a result, GEH has determined that the flow-instrument pressure remain at conservative values (which would ensure that the associated NTSPs and AVs expressed in psid also remain at conservative values), and the MSL high-flow trip will function as designed. This update to the 60-day Interim Notification issued on December 12, 2012 (MFN 12-111 R1) will be sent to all US BWR/2-6 plants licensed using the GEH design basis and safety analysis."
See previous NRC Event Report 48350.
Power Reactor
Event Number: 48736
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MATTHEW GALLERANI
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MATTHEW GALLERANI
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/08/2013
Notification Time: 22:50 [ET]
Event Date: 02/08/2013
Event Time: 22:00 [EST]
Last Update Date: 02/10/2013
Notification Time: 22:50 [ET]
Event Date: 02/08/2013
Event Time: 22:00 [EST]
Last Update Date: 02/10/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
RAY POWELL (R1DO)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
ERIC LEEDS (NRR)
DAVE LEW (R1)
RAY POWELL (R1DO)
MICHELE EVANS (NRR)
JANE MARSHALL (IRD)
ERIC LEEDS (NRR)
DAVE LEW (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 80 | Power Operation | 0 | Hot Shutdown |
UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER
"Pilgrim Station scrammed on a loss of offsite power. All systems performed as designed. Groups I, II, VI went to completion. Reactor Core Isolation Cooling (RCIC) is injecting to the vessel controlling level. High Pressure Coolant Injection is in pressure control and slowly cooling down. Offsite power was lost multiple times. The Startup Transformer has been declared inoperable. The Unusual Event was declared under EAL SU 1.1 based on loss of offsite power greater than 15 minutes [at 2200 EST]."
The licensee originally experienced an automatic reactor scram at 2117 EST due to a load reject with a turbine trip/reactor scram due to loss of power. Offsite power availability has been fluctuating in and out to the site. The licensee states that all systems are functioning as required. All rods fully inserted and the reactor is stable in Mode 3. Both Emergency Diesel Generators are providing power to the safety related buses. The loss of offsite power is believed to be weather related.
The licensee has notified the State and local authorities and the NRC Resident Inspector.
Notified DHS SWO, FEMA, USDA, HHS, DOE, DHS NICC, EPA, and NuclearSSA via email.
* * * UPDATE FROM PAUL GALLANT TO VINCE KLCO AT 2/10/13 AT 1108 EST* * *
Pilgrim terminated the Unusual Event and has transitioned to recovery effective at 10:55 AM on 02/10/2013. Offsite power has been restored to safety-related and non-safety-related electrical buses through the station Startup Transformer via a single 345 KV line. The other two offsite power sources remain out of service. The emergency diesel generators have been secured and are in standby. Residual heat removal is in shutdown cooling mode maintaining the reactor in cold shutdown. Fuel Pool Cooling is in service with fuel pool coolant temperatures trending down.
The licensee notified State, local authorities and the NRC Resident Inspector. Notified R1 RA (Dean), R1DO (Powell), NRR DIR(Leeds) NRR EO (Evans) and NSIR IRD (Marshall).
Notified DHS SWO, FEMA, USDA, HHS, DOE, DHS NICC, EPA, and NuclearSSA via email.
"Pilgrim Station scrammed on a loss of offsite power. All systems performed as designed. Groups I, II, VI went to completion. Reactor Core Isolation Cooling (RCIC) is injecting to the vessel controlling level. High Pressure Coolant Injection is in pressure control and slowly cooling down. Offsite power was lost multiple times. The Startup Transformer has been declared inoperable. The Unusual Event was declared under EAL SU 1.1 based on loss of offsite power greater than 15 minutes [at 2200 EST]."
The licensee originally experienced an automatic reactor scram at 2117 EST due to a load reject with a turbine trip/reactor scram due to loss of power. Offsite power availability has been fluctuating in and out to the site. The licensee states that all systems are functioning as required. All rods fully inserted and the reactor is stable in Mode 3. Both Emergency Diesel Generators are providing power to the safety related buses. The loss of offsite power is believed to be weather related.
The licensee has notified the State and local authorities and the NRC Resident Inspector.
Notified DHS SWO, FEMA, USDA, HHS, DOE, DHS NICC, EPA, and NuclearSSA via email.
* * * UPDATE FROM PAUL GALLANT TO VINCE KLCO AT 2/10/13 AT 1108 EST* * *
Pilgrim terminated the Unusual Event and has transitioned to recovery effective at 10:55 AM on 02/10/2013. Offsite power has been restored to safety-related and non-safety-related electrical buses through the station Startup Transformer via a single 345 KV line. The other two offsite power sources remain out of service. The emergency diesel generators have been secured and are in standby. Residual heat removal is in shutdown cooling mode maintaining the reactor in cold shutdown. Fuel Pool Cooling is in service with fuel pool coolant temperatures trending down.
The licensee notified State, local authorities and the NRC Resident Inspector. Notified R1 RA (Dean), R1DO (Powell), NRR DIR(Leeds) NRR EO (Evans) and NSIR IRD (Marshall).
Notified DHS SWO, FEMA, USDA, HHS, DOE, DHS NICC, EPA, and NuclearSSA via email.
Part 21
Event Number: 49576
Rep Org: CB&I LAKE CHARLES
Licensee: CB&I LAKE CHARLES
Region: 4
City: LAKE CHARLES State: LA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KEVIN WALSH
HQ OPS Officer: STEVE SANDIN
Licensee: CB&I LAKE CHARLES
Region: 4
City: LAKE CHARLES State: LA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KEVIN WALSH
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/24/2013
Notification Time: 18:23 [ET]
Event Date: 02/08/2013
Event Time: 00:00 [CST]
Last Update Date: 11/24/2013
Notification Time: 18:23 [ET]
Event Date: 02/08/2013
Event Time: 00:00 [CST]
Last Update Date: 11/24/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
DAVID PROULX (R4DO)
FRANK EHRHARDT (R2DO)
PART 21 GROUP (EMAI)
DAVID PROULX (R4DO)
FRANK EHRHARDT (R2DO)
PART 21 GROUP (EMAI)
INTERIM PART 21 REPORT REGARDING DEVIATIONS OF SUPPLIED MATERIALS FOR MODULE ASSEMBLY
The following is a summary of a fax updating a report initially submitted to the Document Control Desk on February 8, 2013:
"CBI Lake Charles (CBI-LC) provided an interim report to the NRC regarding the ongoing 10 CFR Part 21 evaluation that could not be completed within 60-days from discovery of the deviation. This deviation is related to Mechanical Splices delivered to AP1000 Projects, Vogtle Unit 3 and V.C. Summer Unit 2.
"CBI-LC executed the test plan and submitted the results to the Design Authority for evaluation. The 'Use-As-Is' disposition by the design authority was contingent upon additional qualification testing performed by the manufacturer. During the review of the testing by the manufacturer, there were some minor administrative errors identified. Therefore, upon the Design Authority approval of these minor error corrections, the evaluation to determine if this deviation is reportable per Part 21.21, could not be completed with the 60-days. Hence, this updated interim report is being provided. CBI Lake Charles expects the Design Authority approval of the test results by January 31, 2014."
The following is a summary of a fax updating a report initially submitted to the Document Control Desk on February 8, 2013:
"CBI Lake Charles (CBI-LC) provided an interim report to the NRC regarding the ongoing 10 CFR Part 21 evaluation that could not be completed within 60-days from discovery of the deviation. This deviation is related to Mechanical Splices delivered to AP1000 Projects, Vogtle Unit 3 and V.C. Summer Unit 2.
"CBI-LC executed the test plan and submitted the results to the Design Authority for evaluation. The 'Use-As-Is' disposition by the design authority was contingent upon additional qualification testing performed by the manufacturer. During the review of the testing by the manufacturer, there were some minor administrative errors identified. Therefore, upon the Design Authority approval of these minor error corrections, the evaluation to determine if this deviation is reportable per Part 21.21, could not be completed with the 60-days. Hence, this updated interim report is being provided. CBI Lake Charles expects the Design Authority approval of the test results by January 31, 2014."