Event Notification Report for May 05, 2021
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/04/2021 - 05/05/2021
Power Reactor
Event Number: 55239
Facility: North Anna
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Marc Hofmann
HQ OPS Officer: Thomas Kendzia
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Marc Hofmann
HQ OPS Officer: Thomas Kendzia
Notification Date: 05/06/2021
Notification Time: 14:00 [ET]
Event Date: 05/06/2021
Event Time: 12:23 [EDT]
Last Update Date: 05/06/2021
Notification Time: 14:00 [ET]
Event Date: 05/06/2021
Event Time: 12:23 [EDT]
Last Update Date: 05/06/2021
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):
MILLER, MARK (R2)
MILLER, MARK (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 60 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 6/4/2021
EN Revision Text: MANUAL REACTOR TRIP
"On May 6, 2021 at 1223 [EDT], Unit 1 was manually tripped from 60 percent power due to degrading main condenser vacuum. Unit 1 was in the process of decreasing power due to increased secondary sodium levels identified earlier in the day. The Operations crew entered the reactor trip procedure and stabilized Unit 1 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip. This reactor protection actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). Auxiliary Feedwater pumps actuated as designed as a result of the reactor trip and provided makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater pumps is reportable per 10 CFR 50,72(b)(3)(iv)(A) for a valid actuation of an ESF [Engineered Safeguards Features] system. Decay heat is being removed by the condenser steam dump system."
The electrical system is in normal lineup for shutdown conditions. There was no effect on Unit 2 operation. The NRC resident inspector has been notified.
EN Revision Text: MANUAL REACTOR TRIP
"On May 6, 2021 at 1223 [EDT], Unit 1 was manually tripped from 60 percent power due to degrading main condenser vacuum. Unit 1 was in the process of decreasing power due to increased secondary sodium levels identified earlier in the day. The Operations crew entered the reactor trip procedure and stabilized Unit 1 in Mode 3 at normal operating temperature and pressure. All control rods fully inserted into the core following the reactor trip. This reactor protection actuation is reportable per 10 CFR 50.72(b)(2)(iv)(B). Auxiliary Feedwater pumps actuated as designed as a result of the reactor trip and provided makeup flow to the steam generators. The automatic start of the Auxiliary Feedwater pumps is reportable per 10 CFR 50,72(b)(3)(iv)(A) for a valid actuation of an ESF [Engineered Safeguards Features] system. Decay heat is being removed by the condenser steam dump system."
The electrical system is in normal lineup for shutdown conditions. There was no effect on Unit 2 operation. The NRC resident inspector has been notified.
Agreement State
Event Number: 55246
Rep Org: NEW YORK STATE DEPT. OF HEALTH
Licensee: Materials Testing Laboratory, Inc.
Region: 1
City: Bronx State: NY
County:
License #: C2274
Agreement: Y
Docket:
NRC Notified By: Daniel Samson
HQ OPS Officer: Jeffrey Whited
Licensee: Materials Testing Laboratory, Inc.
Region: 1
City: Bronx State: NY
County:
License #: C2274
Agreement: Y
Docket:
NRC Notified By: Daniel Samson
HQ OPS Officer: Jeffrey Whited
Notification Date: 05/10/2021
Notification Time: 15:14 [ET]
Event Date: 05/06/2021
Event Time: 00:00 [EDT]
Last Update Date: 05/10/2021
Notification Time: 15:14 [ET]
Event Date: 05/06/2021
Event Time: 00:00 [EDT]
Last Update Date: 05/10/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
DIMITRIADIS, ANTHONY (R1DO)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
DIMITRIADIS, ANTHONY (R1DO)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
EN Revision Imported Date: 6/10/2021
EN Revision Text: AGREEMENT STATE REPORT - STOLEN AND RETURNED GAUGE
The following was received from the New York State Department of Health (the Department) via email:
"A regional inspector for the Department received an email at 0341 EDT on 5/7/21 from the RSO of a materials testing lab stating that a Troxler model 4640 thin [layer density gauge], serial number 722, containing 40 mCi of Am-241/Be and 11 mCi of Cs-137, was stolen from a job site in Bronx, NY. The operator left the device unattended for a short period of time and returned to find it missing. The device was in its locked position when it was taken. The area was canvassed, and the police were notified.
"On 5/7/21, the licensee received a phone call from [an individual] stating that they had the device and wanted the reward. The licensee paid the reward and the device is back in the possession of the licensee. The device appears to be in good shape, but it will be leak tested before it is put back into operation."
Event Report ID No.: NYDOH-21-02
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
EN Revision Text: AGREEMENT STATE REPORT - STOLEN AND RETURNED GAUGE
The following was received from the New York State Department of Health (the Department) via email:
"A regional inspector for the Department received an email at 0341 EDT on 5/7/21 from the RSO of a materials testing lab stating that a Troxler model 4640 thin [layer density gauge], serial number 722, containing 40 mCi of Am-241/Be and 11 mCi of Cs-137, was stolen from a job site in Bronx, NY. The operator left the device unattended for a short period of time and returned to find it missing. The device was in its locked position when it was taken. The area was canvassed, and the police were notified.
"On 5/7/21, the licensee received a phone call from [an individual] stating that they had the device and wanted the reward. The licensee paid the reward and the device is back in the possession of the licensee. The device appears to be in good shape, but it will be leak tested before it is put back into operation."
Event Report ID No.: NYDOH-21-02
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
Agreement State
Event Number: 55237
Rep Org: NORTH CAROLINA DIV OF RAD PROTECTIO
Licensee: NV5 Engineers and Consultants, Inc.
Region: 1
City: Durham State: NC
County:
License #: 092-0898-1
Agreement: Y
Docket:
NRC Notified By: Travis Cartoski
HQ OPS Officer: Thomas Herrity
Licensee: NV5 Engineers and Consultants, Inc.
Region: 1
City: Durham State: NC
County:
License #: 092-0898-1
Agreement: Y
Docket:
NRC Notified By: Travis Cartoski
HQ OPS Officer: Thomas Herrity
Notification Date: 05/06/2021
Notification Time: 13:01 [ET]
Event Date: 05/06/2021
Event Time: 00:00 [EDT]
Last Update Date: 05/06/2021
Notification Time: 13:01 [ET]
Event Date: 05/06/2021
Event Time: 00:00 [EDT]
Last Update Date: 05/06/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
YOUNG, MATT (R1DO)
ILTAB, (EMAIL)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
HARRINGTON, HOLLY (PAO)
YOUNG, MATT (R1DO)
ILTAB, (EMAIL)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
HARRINGTON, HOLLY (PAO)
EN Revision Imported Date: 6/4/2021
EN Revision Text: AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE
The following notice was received from the State of North Carolina Radioactive Materials Branch (RMB), via email:
"A portable nuclear density gauge was reported stolen out of a licensee's flatbed truck, sometime during the evening of May 5th. The gauge was reported as secured from unauthorized removal by two independent means and padlocked in its transportation case. The truck was parked in front of the personal residence of one of the licensee's authorized users overnight. The morning of May 6th, the authorized user noticed the gauge case missing with locks and chains broken. The authorized user immediately called 911 and notified the licensee's Radiation Safety Officer immediately, who in turn, notified the RMB who responded to the scene of the theft the morning of [May] 6th. RMB is preparing a press release in an effort to recover the gauge and its investigation is ongoing."
Durham Police Department was notified.
Gauge Information:
Manufacturer: Troxler; Model: 3430P; S/N: 71890
Sources Information:
CS-137 0.300 GBq, 8.0 mCi; Am-241 BE, 40.0 mCi
North Carolina Tracking Number: 210006
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
EN Revision Text: AGREEMENT STATE REPORT - STOLEN TROXLER GAUGE
The following notice was received from the State of North Carolina Radioactive Materials Branch (RMB), via email:
"A portable nuclear density gauge was reported stolen out of a licensee's flatbed truck, sometime during the evening of May 5th. The gauge was reported as secured from unauthorized removal by two independent means and padlocked in its transportation case. The truck was parked in front of the personal residence of one of the licensee's authorized users overnight. The morning of May 6th, the authorized user noticed the gauge case missing with locks and chains broken. The authorized user immediately called 911 and notified the licensee's Radiation Safety Officer immediately, who in turn, notified the RMB who responded to the scene of the theft the morning of [May] 6th. RMB is preparing a press release in an effort to recover the gauge and its investigation is ongoing."
Durham Police Department was notified.
Gauge Information:
Manufacturer: Troxler; Model: 3430P; S/N: 71890
Sources Information:
CS-137 0.300 GBq, 8.0 mCi; Am-241 BE, 40.0 mCi
North Carolina Tracking Number: 210006
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
Agreement State
Event Number: 55238
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: Ascend Performance Materials
Region: 1
City: Cantonment State: FL
County: Escambia
License #: 4145-2
Agreement: Y
Docket:
NRC Notified By: David Pieski
HQ OPS Officer: Thomas Herrity
Licensee: Ascend Performance Materials
Region: 1
City: Cantonment State: FL
County: Escambia
License #: 4145-2
Agreement: Y
Docket:
NRC Notified By: David Pieski
HQ OPS Officer: Thomas Herrity
Notification Date: 05/06/2021
Notification Time: 13:59 [ET]
Event Date: 05/05/2021
Event Time: 00:00 [EDT]
Last Update Date: 05/06/2021
Notification Time: 13:59 [ET]
Event Date: 05/05/2021
Event Time: 00:00 [EDT]
Last Update Date: 05/06/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
YOUNG, MATT (R1DO)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
RIVERA-CAPELLA, GRETCHEN (NMSS DAY)
YOUNG, MATT (R1DO)
NMSS_EVENTS_NOTIFICATION, (EMAIL)
RIVERA-CAPELLA, GRETCHEN (NMSS DAY)
EN Revision Imported Date: 6/4/2021
EN Revision Text: AGREEMENT STATE REPORT - FIRE DAMAGE PREVENTS LEVEL GAUGE RETRACTION
The following was reported by the State of Florida via email:
"On 5/5/21 a fire occurred on the same floor as the nylon finishing line using a nuclear gauge (level switch). Fire extinguished by in-house [personnel] on-site as well as Escambia County fire depts. After a structural review was completed and entrance safety assured, continued property examination on 5/6 revealed the nuclear gauge could not be shuttered. No injuries were reported. No exposures were reported. Exclusion zones have been marked on the finishing line floor as well as adjacent floor. At the time of this report, Ascend [Performance Material] is evaluating contractor availability for gauge assessment concerning repair and/or removal. Plant contact person reported the 1500 milliCurie source was purchased in 1962."
Florida Incident Number: FL21-060.
EN Revision Text: AGREEMENT STATE REPORT - FIRE DAMAGE PREVENTS LEVEL GAUGE RETRACTION
The following was reported by the State of Florida via email:
"On 5/5/21 a fire occurred on the same floor as the nylon finishing line using a nuclear gauge (level switch). Fire extinguished by in-house [personnel] on-site as well as Escambia County fire depts. After a structural review was completed and entrance safety assured, continued property examination on 5/6 revealed the nuclear gauge could not be shuttered. No injuries were reported. No exposures were reported. Exclusion zones have been marked on the finishing line floor as well as adjacent floor. At the time of this report, Ascend [Performance Material] is evaluating contractor availability for gauge assessment concerning repair and/or removal. Plant contact person reported the 1500 milliCurie source was purchased in 1962."
Florida Incident Number: FL21-060.
Power Reactor
Event Number: 55244
Facility: Monticello
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: Gustavo Hernandez
HQ OPS Officer: Bethany Cecere
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: Gustavo Hernandez
HQ OPS Officer: Bethany Cecere
Notification Date: 05/07/2021
Notification Time: 17:21 [ET]
Event Date: 05/05/2021
Event Time: 00:00 [CDT]
Last Update Date: 05/07/2021
Notification Time: 17:21 [ET]
Event Date: 05/05/2021
Event Time: 00:00 [CDT]
Last Update Date: 05/07/2021
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):
ORLIKOWSKI, ROBERT (R3)
PART 21/50.55 REACTORS, - (EMAIL)
ORLIKOWSKI, ROBERT (R3)
PART 21/50.55 REACTORS, - (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
EN Revision Imported Date: 6/7/2021
EN Revision Text: PART 21 - POWER RANGE NEUTRON MONITOR SYSTEM DEFECT
The following is a summary of information received via email from Monticello Nuclear Generating Plant (MNGP):
On March 9, 2021, GE Hitachi (GEH) issued Safety Communication SC 21-02 for PRC 21-02, Transfer of Information, Revision 0, pursuant to 10 CFR 21.21(b). Monticello Nuclear Generating Plant (MNGP) was listed as a potentially affected plant. This is a deviation from the Power Range Nuclear Monitor (PRNM) Licensing Topical Report, NEDC 32410P-A.
On May 5, 2021, MNGP completed an evaluation of this deviation and concluded this condition represents a substantial safety hazard in that the condition could result in an Average Power Range Monitoring (APRM) flux reading either below or above the Technical Specification (plus/minus) 2% band. The condition is a defect that is reportable pursuant to 10 CFR 21.21(d)(4).
The GEH NUMAC PRNMS was installed in 2009 with System Part No. 299X739NF.
Name and Address of the Individual or Individuals Informing the Commission:
Thomas A. Conboy,
Site Vice President
Monticello Nuclear Generating Plant
Northern States Power Company - Minnesota
2807 West County Road 75
Monticello, MN 55362
The licensee notified the NRC Resident Inspector.
EN Revision Text: PART 21 - POWER RANGE NEUTRON MONITOR SYSTEM DEFECT
The following is a summary of information received via email from Monticello Nuclear Generating Plant (MNGP):
On March 9, 2021, GE Hitachi (GEH) issued Safety Communication SC 21-02 for PRC 21-02, Transfer of Information, Revision 0, pursuant to 10 CFR 21.21(b). Monticello Nuclear Generating Plant (MNGP) was listed as a potentially affected plant. This is a deviation from the Power Range Nuclear Monitor (PRNM) Licensing Topical Report, NEDC 32410P-A.
On May 5, 2021, MNGP completed an evaluation of this deviation and concluded this condition represents a substantial safety hazard in that the condition could result in an Average Power Range Monitoring (APRM) flux reading either below or above the Technical Specification (plus/minus) 2% band. The condition is a defect that is reportable pursuant to 10 CFR 21.21(d)(4).
The GEH NUMAC PRNMS was installed in 2009 with System Part No. 299X739NF.
Name and Address of the Individual or Individuals Informing the Commission:
Thomas A. Conboy,
Site Vice President
Monticello Nuclear Generating Plant
Northern States Power Company - Minnesota
2807 West County Road 75
Monticello, MN 55362
The licensee notified the NRC Resident Inspector.
Part 21
Event Number: 56920
Rep Org: V. C. Summer
Licensee: V. C. Summer
Region: 2
City: Jenkinsville State: SC
County: Fairfield
License #:
Agreement: Y
Docket:
NRC Notified By: Justin Bouknight
HQ OPS Officer: Thomas Herrity
Licensee: V. C. Summer
Region: 2
City: Jenkinsville State: SC
County: Fairfield
License #:
Agreement: Y
Docket:
NRC Notified By: Justin Bouknight
HQ OPS Officer: Thomas Herrity
Notification Date: 01/10/2024
Notification Time: 08:18 [ET]
Event Date: 05/05/2021
Event Time: 00:00 [EST]
Last Update Date: 01/17/2024
Notification Time: 08:18 [ET]
Event Date: 05/05/2021
Event Time: 00:00 [EST]
Last Update Date: 01/17/2024
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):
Miller, Mark (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
Miller, Mark (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
EN Revision Imported Date: 1/18/2024
EN Revision Text: PART 21 - GOULD FIELD FLASH RELAY ON EMERGENCY DIESEL FAILED
The following information was provided by the licensee via email and phone call:
"On January 9, 2024, VC Summer Nuclear Station (VCSNS) determined a manufacturing defect affecting a field flash contactor (K2) relay on its 'B' emergency diesel generator (EDG) was reportable under Part 21.
"During testing on May 5, 2021, the 'B' EDG was rendered inoperable when its K2 relay coil switch exhibited intermittent binding due to insufficient clearances of the switch actuator from the protective case and plastic switch molding. The inadequate clearances resulted in accelerated loss of graphite lubrication at these locations, which led to mechanical binding. VCSNS replaced the affected relay and restored operability of its 'B' EDG.
"Manufacturer/Model: Gould F10NOCLD1 DC coil switch
"A written notification in accordance with 10 CFR 21.21(d)(3)(ii) will be provided within 30 days. The NRC Senior Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The licensee did not notify the intellectual property owner because the manufacturer is no longer operating or in business. They are not aware of other plants that utilize this coil switch.
EN Revision Text: PART 21 - GOULD FIELD FLASH RELAY ON EMERGENCY DIESEL FAILED
The following information was provided by the licensee via email and phone call:
"On January 9, 2024, VC Summer Nuclear Station (VCSNS) determined a manufacturing defect affecting a field flash contactor (K2) relay on its 'B' emergency diesel generator (EDG) was reportable under Part 21.
"During testing on May 5, 2021, the 'B' EDG was rendered inoperable when its K2 relay coil switch exhibited intermittent binding due to insufficient clearances of the switch actuator from the protective case and plastic switch molding. The inadequate clearances resulted in accelerated loss of graphite lubrication at these locations, which led to mechanical binding. VCSNS replaced the affected relay and restored operability of its 'B' EDG.
"Manufacturer/Model: Gould F10NOCLD1 DC coil switch
"A written notification in accordance with 10 CFR 21.21(d)(3)(ii) will be provided within 30 days. The NRC Senior Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The licensee did not notify the intellectual property owner because the manufacturer is no longer operating or in business. They are not aware of other plants that utilize this coil switch.