Event Notification Report for September 25, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/24/2012 - 09/25/2012
EVENT NUMBERS
483394834048341483424834348344
Power Reactor
Event Number: 48339
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GLENN GOELZER
HQ OPS Officer: BILL HUFFMAN
Region: 4 State: CA
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GLENN GOELZER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/25/2012
Notification Time: 09:46 [ET]
Event Date: 09/25/2012
Event Time: 05:55 [PDT]
Last Update Date: 09/27/2012
Notification Time: 09:46 [ET]
Event Date: 09/25/2012
Event Time: 05:55 [PDT]
Last Update Date: 09/27/2012
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):
GREG WERNER (R4DO)
GREG WERNER (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 |
TECHNICAL SUPPORT CENTER REMOVED FROM SERVICE FOR MAINTENANCE
"On September 25, 2012, power was removed from various Technical Support Center (TSC) systems to perform planned system preventative maintenance (PM) and corrective maintenance (CM) activities. During these maintenance activities, the normal TSC and Operational Support Center (OSC) are unavailable for use during an emergency. The Plant Data Network (PDN) will not be available to the TSC. This will render the Safety Parameter Display System (SPDS), Emergency Response Facility Display System (ERFDS), Emergency Assessment and Response System (EARS) and the Post LOCA Sampling System in the TSC unavailable. System alarms and data displays will still be available to the plant operators in the Control Room. The expected duration of the power outage is approximately 39 hours.
"As compensatory measures, the backup emergency response facilities will be manned during an emergency. This compensatory measure has been communicated to the emergency response organization. It is expected that appropriate assessment of plant conditions, notifications, and communications could still be made, if required, during the time that the normal TSC and OSC are unavailable. This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. An update message will be provided when the emergency response facilities are restored."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE FROM GOELZER TO KLCO ON 9/27/12 AT 0025 EDT * * *
"This is an update to EN #48339 report on September 25, 2012, where Pacific Gas & Electric company (PG&E) reported that a planned maintenance power outage caused the normal Technical Support Center (TSC) and Operational Support Center (OSC) to be unavailable for use during an emergency.
"PG&E has completed all preventative maintenance (PM) and corrective maintenance (CM) activities that required the power outage to the TSC and OSC and has completed the restoration of these emergency response facilities. Plant personnel have been notified that the normal emergency response facilities have been restored.
"PG&E personnel have informed the NRC Resident Inspector."
Notified the R4DO (Werner).
"On September 25, 2012, power was removed from various Technical Support Center (TSC) systems to perform planned system preventative maintenance (PM) and corrective maintenance (CM) activities. During these maintenance activities, the normal TSC and Operational Support Center (OSC) are unavailable for use during an emergency. The Plant Data Network (PDN) will not be available to the TSC. This will render the Safety Parameter Display System (SPDS), Emergency Response Facility Display System (ERFDS), Emergency Assessment and Response System (EARS) and the Post LOCA Sampling System in the TSC unavailable. System alarms and data displays will still be available to the plant operators in the Control Room. The expected duration of the power outage is approximately 39 hours.
"As compensatory measures, the backup emergency response facilities will be manned during an emergency. This compensatory measure has been communicated to the emergency response organization. It is expected that appropriate assessment of plant conditions, notifications, and communications could still be made, if required, during the time that the normal TSC and OSC are unavailable. This report is being made in accordance with 10 CFR 50.72(b)(3)(xiii), which is any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability. An update message will be provided when the emergency response facilities are restored."
The licensee will notify the NRC Resident Inspector.
* * * UPDATE FROM GOELZER TO KLCO ON 9/27/12 AT 0025 EDT * * *
"This is an update to EN #48339 report on September 25, 2012, where Pacific Gas & Electric company (PG&E) reported that a planned maintenance power outage caused the normal Technical Support Center (TSC) and Operational Support Center (OSC) to be unavailable for use during an emergency.
"PG&E has completed all preventative maintenance (PM) and corrective maintenance (CM) activities that required the power outage to the TSC and OSC and has completed the restoration of these emergency response facilities. Plant personnel have been notified that the normal emergency response facilities have been restored.
"PG&E personnel have informed the NRC Resident Inspector."
Notified the R4DO (Werner).
Agreement State
Event Number: 48340
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: SOUTH STATE INC
Region: 1
City: BRIDGETON State: NJ
County:
License #: RAD110001-507
Agreement: Y
Docket:
NRC Notified By: PATRICIA GARDNER
HQ OPS Officer: BILL HUFFMAN
Licensee: SOUTH STATE INC
Region: 1
City: BRIDGETON State: NJ
County:
License #: RAD110001-507
Agreement: Y
Docket:
NRC Notified By: PATRICIA GARDNER
HQ OPS Officer: BILL HUFFMAN
Notification Date: 09/25/2012
Notification Time: 10:10 [ET]
Event Date: 09/25/2012
Event Time: 01:00 [EDT]
Last Update Date: 09/26/2012
Notification Time: 10:10 [ET]
Event Date: 09/25/2012
Event Time: 01:00 [EDT]
Last Update Date: 09/26/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RONALD BELLAMY (R1DO)
FSME EVENT RESOURCE (E-MA)
D. JOHNSON VIA EMAIL (ILTA)
RONALD BELLAMY (R1DO)
FSME EVENT RESOURCE (E-MA)
D. JOHNSON VIA EMAIL (ILTA)
AGREEMENT STATE REPORT - LOST HUMBOLDT DENSITY GAUGE
The following report was received from the NJ Department of Environmental Protection Bureau of Environmental Radiation via facsimile:
"Licensee: South State Inc.
"Event date and time: September 25, 2012 at 01:00 am
"Event location: NJ Turnpike Interchanges 1-3 N-S
"Event type: Lost density gauge - Humboldt Model 5001EZ Serial No. 2872 (Am-241 44 mCi and Cs-137 11 mCi)
"Notifications: NJDEP BER and NJDEP Hotline
"Event Description: South State Inc. reported a missing density gauge on September 25, 2012 at 01:29 am. South State was working on the NJ Turnpike. South State reported that the gauge was lost somewhere between exits 1 and 3 on the north or south bound lanes of the turnpike. Additionally, South State is looking along the route that was taken from their office on 202 Reeves St in Bridgeton, NJ and the turnpike.
"As of 9:00 am this morning, the gauge has not been recovered and the search continues.
"Media attention: None
"NJ Event Report ID No: 12-09-25-0129-19"
* * * UPDATE ON 9/26/12 AT 1239 EDT FROM PATRICIA GARDNER TO DONG PARK * * *
The following report was received from the NJ Department of Environmental Protection Bureau of Environmental Radiation via email:
"The Humboldt Model 5001EZ Serial No. 2872 has been recovered. The gauge is back at the licensee's (South State Inc.) facility. There is no observable damage to the transportation case and/or the gauge. The NJ State Police assisted with the recovery. Details of the event are being summarized and the NMED event report will be updated when completed."
Notified R1DO (Bellamy), FSME, and ILTAB (Johnson) 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 report was received from the NJ Department of Environmental Protection Bureau of Environmental Radiation via facsimile:
"Licensee: South State Inc.
"Event date and time: September 25, 2012 at 01:00 am
"Event location: NJ Turnpike Interchanges 1-3 N-S
"Event type: Lost density gauge - Humboldt Model 5001EZ Serial No. 2872 (Am-241 44 mCi and Cs-137 11 mCi)
"Notifications: NJDEP BER and NJDEP Hotline
"Event Description: South State Inc. reported a missing density gauge on September 25, 2012 at 01:29 am. South State was working on the NJ Turnpike. South State reported that the gauge was lost somewhere between exits 1 and 3 on the north or south bound lanes of the turnpike. Additionally, South State is looking along the route that was taken from their office on 202 Reeves St in Bridgeton, NJ and the turnpike.
"As of 9:00 am this morning, the gauge has not been recovered and the search continues.
"Media attention: None
"NJ Event Report ID No: 12-09-25-0129-19"
* * * UPDATE ON 9/26/12 AT 1239 EDT FROM PATRICIA GARDNER TO DONG PARK * * *
The following report was received from the NJ Department of Environmental Protection Bureau of Environmental Radiation via email:
"The Humboldt Model 5001EZ Serial No. 2872 has been recovered. The gauge is back at the licensee's (South State Inc.) facility. There is no observable damage to the transportation case and/or the gauge. The NJ State Police assisted with the recovery. Details of the event are being summarized and the NMED event report will be updated when completed."
Notified R1DO (Bellamy), FSME, and ILTAB (Johnson) 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
Power Reactor
Event Number: 48341
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: BEN COOK
HQ OPS Officer: DONG HWA PARK
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: BEN COOK
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/25/2012
Notification Time: 15:11 [ET]
Event Date: 09/25/2012
Event Time: 10:44 [CDT]
Last Update Date: 09/25/2012
Notification Time: 15:11 [ET]
Event Date: 09/25/2012
Event Time: 10:44 [CDT]
Last Update Date: 09/25/2012
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):
MARK RING (R3DO)
MARK RING (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DURING MAINTENANCE ON 4160V BUS 12 AMMETER
"During maintenance on 4160V Bus 12 ammeter, a Bus 12 lockout occurred. The station power was from 1R Reserve transformer for work on the 2R Auxiliary transformer. Net effect was Bus 12 locked out, removing power from 12 Reactor Feed Pump and 12 Reactor Recirculation pump. Reactor level lowered to +23 inches then began to rise. With both Main Feed Reg Valves in AUTO, the level transient reached +48 inches, the Reactor Water Level Hi Hi setpoint. The Main Turbine and 11 Reactor Feed Pump tripped as designed, and a Reactor SCRAM occurred. Reactor water level began to drop, and C.4.A Abnormal Procedure for SCRAM was used to restart 11 Reactor Feed Pump and recover water level. Minimum water level reached was -26 inches. Reactor Low Level SCRAM signal and Group 2 Primary Containment isolation occurred at +9 inches as designed, No Safety Relief valves lifted during this transient. High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) did not receive an initiation signal due to not reaching their setpoints. There were no Emergency Core Cooling Systems initiation setpoints reached. Prior to the event, both divisions of Standby Liquid Control were inoperable as part of planned maintenance."
All control rods fully inserted. Decay heat is being removed through the turbine bypass to the main condenser. The plant is in a normal shutdown electrical lineup and stable in Mode 3.
The licensee has notified the NRC Resident Inspector and will notify the State and local governments.
"During maintenance on 4160V Bus 12 ammeter, a Bus 12 lockout occurred. The station power was from 1R Reserve transformer for work on the 2R Auxiliary transformer. Net effect was Bus 12 locked out, removing power from 12 Reactor Feed Pump and 12 Reactor Recirculation pump. Reactor level lowered to +23 inches then began to rise. With both Main Feed Reg Valves in AUTO, the level transient reached +48 inches, the Reactor Water Level Hi Hi setpoint. The Main Turbine and 11 Reactor Feed Pump tripped as designed, and a Reactor SCRAM occurred. Reactor water level began to drop, and C.4.A Abnormal Procedure for SCRAM was used to restart 11 Reactor Feed Pump and recover water level. Minimum water level reached was -26 inches. Reactor Low Level SCRAM signal and Group 2 Primary Containment isolation occurred at +9 inches as designed, No Safety Relief valves lifted during this transient. High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) did not receive an initiation signal due to not reaching their setpoints. There were no Emergency Core Cooling Systems initiation setpoints reached. Prior to the event, both divisions of Standby Liquid Control were inoperable as part of planned maintenance."
All control rods fully inserted. Decay heat is being removed through the turbine bypass to the main condenser. The plant is in a normal shutdown electrical lineup and stable in Mode 3.
The licensee has notified the NRC Resident Inspector and will notify the State and local governments.
Power Reactor
Event Number: 48342
Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: THOMAS D. OLIVER
HQ OPS Officer: DONG HWA PARK
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: THOMAS D. OLIVER
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/25/2012
Notification Time: 18:07 [ET]
Event Date: 09/25/2012
Event Time: 15:30 [EDT]
Last Update Date: 09/25/2012
Notification Time: 18:07 [ET]
Event Date: 09/25/2012
Event Time: 15:30 [EDT]
Last Update Date: 09/25/2012
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):
REBECCA NEASE (R2DO)
REBECCA NEASE (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 |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION DUE TO TRITIUM IN OVERFLOW
"At 1215 hours on September 24, 2012, Surry Power Station personnel confirmed the presence of tritium at a level of 1,450 picoCuries/Liter (pCi/L) in a Unit 2 Turbine Building heating steam drain receiver (HSDR) tank. This tank collects condensate from steam which is used to heat buildings. A sample of the condensate was analyzed following failure of the pump (used to control level) which resulted in the tank overflowing to a drain line on September 17 and 23. The sample was taken because the drain line was degraded and the overflow resulted in a release to the environment.
"The normal inputs into this drain line had been isolated from use in August when the degraded pipe was discovered. Currently, the tank contents are being diverted to a sump until repairs to the drain line and pump are complete. These are expected to complete in the next couple of weeks.
"Both releases were estimated to be greater than 100 gallons. The location of the leak was within the Protected Area of Surry Power Station. There has been no tritium detected in any monitoring wells in the vicinity of the degraded drain line, nor in any monitoring wells outside the Protected Area. Because the leak remained onsite, no offsite impact to ground water is expected. Furthermore, the leak posed no threat to employees or the public.
"Because there was a detectable amount of licensed material in the water, Surry implemented communication to offsite agencies as part of [licensee] commitment to the Nuclear Energy Institute (NEI) Ground Water Protection Initiative.
"This notification is being transmitted due to Notification of Other Government Agencies under 10CFR50.72(b)(2)(xi). The Virginia Department of Environmental Quality, Virginia Department of Health, Virginia Department of Emergency Management, NRC Senior Resident Inspector and Surry County Administrator were notified."
"At 1215 hours on September 24, 2012, Surry Power Station personnel confirmed the presence of tritium at a level of 1,450 picoCuries/Liter (pCi/L) in a Unit 2 Turbine Building heating steam drain receiver (HSDR) tank. This tank collects condensate from steam which is used to heat buildings. A sample of the condensate was analyzed following failure of the pump (used to control level) which resulted in the tank overflowing to a drain line on September 17 and 23. The sample was taken because the drain line was degraded and the overflow resulted in a release to the environment.
"The normal inputs into this drain line had been isolated from use in August when the degraded pipe was discovered. Currently, the tank contents are being diverted to a sump until repairs to the drain line and pump are complete. These are expected to complete in the next couple of weeks.
"Both releases were estimated to be greater than 100 gallons. The location of the leak was within the Protected Area of Surry Power Station. There has been no tritium detected in any monitoring wells in the vicinity of the degraded drain line, nor in any monitoring wells outside the Protected Area. Because the leak remained onsite, no offsite impact to ground water is expected. Furthermore, the leak posed no threat to employees or the public.
"Because there was a detectable amount of licensed material in the water, Surry implemented communication to offsite agencies as part of [licensee] commitment to the Nuclear Energy Institute (NEI) Ground Water Protection Initiative.
"This notification is being transmitted due to Notification of Other Government Agencies under 10CFR50.72(b)(2)(xi). The Virginia Department of Environmental Quality, Virginia Department of Health, Virginia Department of Emergency Management, NRC Senior Resident Inspector and Surry County Administrator were notified."
Power Reactor
Event Number: 48343
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JERRY STOCKHAM
HQ OPS Officer: DONG HWA PARK
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: JERRY STOCKHAM
HQ OPS Officer: DONG HWA PARK
Notification Date: 09/25/2012
Notification Time: 18:23 [ET]
Event Date: 09/25/2012
Event Time: 15:00 [CDT]
Last Update Date: 09/25/2012
Notification Time: 18:23 [ET]
Event Date: 09/25/2012
Event Time: 15:00 [CDT]
Last Update Date: 09/25/2012
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):
MARK RING (R3DO)
MARK RING (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
OFFSITE NOTIFICATION DUE TO HYDRAULIC LEAK
"On September 25, 2012 at 1055 CDT, a road grader developed a hydraulic leak on a steering hose. This resulted in a light mist of approximately 20 gallons of oil being sprayed for a quarter mile. Three hundred feet of that was on gravel and the rest on blacktop. There is no actual or potential impact to the environment.
"There is no impact to plant operation. At 1500 CDT, [the licensee was] notified by Xcel Energy Environmental Services that the State has been notified."
The licensee has notified the NRC Resident Inspector.
"On September 25, 2012 at 1055 CDT, a road grader developed a hydraulic leak on a steering hose. This resulted in a light mist of approximately 20 gallons of oil being sprayed for a quarter mile. Three hundred feet of that was on gravel and the rest on blacktop. There is no actual or potential impact to the environment.
"There is no impact to plant operation. At 1500 CDT, [the licensee was] notified by Xcel Energy Environmental Services that the State has been notified."
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 48344
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: CHUCK HAIDAR
HQ OPS Officer: JOHN KNOKE
Region: 4 State: CA
Unit: [] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: CHUCK HAIDAR
HQ OPS Officer: JOHN KNOKE
Notification Date: 09/25/2012
Notification Time: 22:50 [ET]
Event Date: 09/25/2012
Event Time: 17:07 [PDT]
Last Update Date: 09/25/2012
Notification Time: 22:50 [ET]
Event Date: 09/25/2012
Event Time: 17:07 [PDT]
Last Update Date: 09/25/2012
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):
GREG WERNER (R4DO)
GREG WERNER (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
| 3 | N | N | 0 | Refueling | 0 | Refueling |
OFFSITE NOTIFICATION DUE TO A FREON LEAK FROM BUILDING AIR CONDITIONER
"The control room was notified by the Environmental Protection Group that 43 lbs of Freon was released [from an air conditioning unit] at the Administration Warehouse Supply/Shop, not in the Protected Area, and that it was reported to the California Emergency Management Agency at 17:19 PDT and San Diego County at 17:12 PDT, per lAW procedure SO123-XV-17.3, 'Spill Contingency Plan'.
"There is no longer a Freon release in progress."
The licensee has notified the NRC Resident Inspector.
"The control room was notified by the Environmental Protection Group that 43 lbs of Freon was released [from an air conditioning unit] at the Administration Warehouse Supply/Shop, not in the Protected Area, and that it was reported to the California Emergency Management Agency at 17:19 PDT and San Diego County at 17:12 PDT, per lAW procedure SO123-XV-17.3, 'Spill Contingency Plan'.
"There is no longer a Freon release in progress."
The licensee has notified the NRC Resident Inspector.