Event Notification Report for March 11, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/10/2019 - 03/11/2019
Agreement State
Event Number: 53927
Rep Org: LOUISIANA DEPT OF ENV QUALITY
Licensee: GEORGIA PACIFIC CONSUMER PRODUCTS, LLC
Region: 4
City: ZACHARY State: LA
County:
License #: LA-2162-L01, AI #2617
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: BETHANY CECERE
Licensee: GEORGIA PACIFIC CONSUMER PRODUCTS, LLC
Region: 4
City: ZACHARY State: LA
County:
License #: LA-2162-L01, AI #2617
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: BETHANY CECERE
Notification Date: 03/11/2019
Notification Time: 15:17 [ET]
Event Date: 03/11/2019
Event Time: 13:30 [CDT]
Last Update Date: 03/11/2019
Notification Time: 15:17 [ET]
Event Date: 03/11/2019
Event Time: 13:30 [CDT]
Last Update Date: 03/11/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JEREMY GROOM (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
JEREMY GROOM (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - SHUTTER STUCK IN OPEN POSITION
The following was received by email from the state of Louisiana:
"On 03/11/2019, Georgia Pacific Consumer Products [GA-PAC] Port Hudson Operations was shutting down a process to perform a disposal decommission maintenance. In the process of securing the radiation sources for shipping and disposal, it was then discovered the shutter [on a level density gauge] would not close.
"GA-PAC has called a service contractor, BBP Sales, to evaluate the situation and determine the best course of action to correct the problem. GA-PAC will have BBP Sales determine the proper disposal for this device. The device was manufactured in 1967.
"The sources and device with shutter failure will be sent for disposal and not replaced. GA-PAC is decommissioning this unit. This is not a radiation exposure hazard and does not pose a health and safety situation for the GA-PAC employees or the general public.
"THIS EVENT IS CONSIDERED CLOSED BY LDEQ. This event is being reported to the NRC as required by Regulatory Requirement 10 CFR Part 30.50 (b) (2) & LAC 33:XV341.B."
The Gauge is an OHMART HM8 device/source holder, S/N 6563 with a 100 mCi Cs-137 source.
LA Event Report ID No.: LA-190003
The following was received by email from the state of Louisiana:
"On 03/11/2019, Georgia Pacific Consumer Products [GA-PAC] Port Hudson Operations was shutting down a process to perform a disposal decommission maintenance. In the process of securing the radiation sources for shipping and disposal, it was then discovered the shutter [on a level density gauge] would not close.
"GA-PAC has called a service contractor, BBP Sales, to evaluate the situation and determine the best course of action to correct the problem. GA-PAC will have BBP Sales determine the proper disposal for this device. The device was manufactured in 1967.
"The sources and device with shutter failure will be sent for disposal and not replaced. GA-PAC is decommissioning this unit. This is not a radiation exposure hazard and does not pose a health and safety situation for the GA-PAC employees or the general public.
"THIS EVENT IS CONSIDERED CLOSED BY LDEQ. This event is being reported to the NRC as required by Regulatory Requirement 10 CFR Part 30.50 (b) (2) & LAC 33:XV341.B."
The Gauge is an OHMART HM8 device/source holder, S/N 6563 with a 100 mCi Cs-137 source.
LA Event Report ID No.: LA-190003
Power Reactor
Event Number: 53924
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAN SCHWER
HQ OPS Officer: JEFFREY WHITED
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAN SCHWER
HQ OPS Officer: JEFFREY WHITED
Notification Date: 03/11/2019
Notification Time: 10:00 [ET]
Event Date: 03/11/2019
Event Time: 08:51 [EDT]
Last Update Date: 03/11/2019
Notification Time: 10:00 [ET]
Event Date: 03/11/2019
Event Time: 08:51 [EDT]
Last Update Date: 03/11/2019
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):
FRED BOWER (R1DO)
ERDS (EMAIL)
FRED BOWER (R1DO)
ERDS (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
PLANNED COMMUNICATION SYSTEM MAINTENANCE
"On 03/11/2019 planned maintenance activities will be performed on the Beaver Valley Power Station (BVPS) Unit 2 Digital Radiation Monitoring System's (DRMS) Communications System.
"The work includes upgrades to the DRMS hardware, software and computer peripherals. Components to be upgraded under this planned maintenance include: Redundant Servers, Operator Console, Health Physics Office Console/Workstation, Printers and Portable Mass Storage/Backup and Computer peripherals necessary to interface with the computer system. This planned upgrade on the Unit 2 DRMS Communications System will result in the loss of Unit 2 radiological monitoring capability in the Control Room and on the Plant Computer System (PCS). Neither the Emergency Response Facilities nor the Emergency Response Data System (ERDS) will receive radiological data. No actual radiation monitors are affected. The scheduled work duration is approximately three weeks.
"When the DRMS is out of service for the upgrade, compensatory actions will be in place. Radiation monitors will be continuously monitored for any increases in radiation levels. The Unit 2 Shift Manager will be notified of any increase in radiation monitor readings, including exceeding Emergency Action Levels (EAL).
"This is an eight-hour, non-emergency notification for a Loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the upgrade to the DRMS Communications System will result in the loss of the Unit 2 radiological monitoring capability in the Control Room and to the Unit 2 Plant Computer System that affects the functionality of an Emergency Response Facility.
"There is no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The licensee is currently in a Technical Specification Action Statement, Limiting Condition for Operation for spent fuel pool radiation monitor and leakage rate monitor.
"On 03/11/2019 planned maintenance activities will be performed on the Beaver Valley Power Station (BVPS) Unit 2 Digital Radiation Monitoring System's (DRMS) Communications System.
"The work includes upgrades to the DRMS hardware, software and computer peripherals. Components to be upgraded under this planned maintenance include: Redundant Servers, Operator Console, Health Physics Office Console/Workstation, Printers and Portable Mass Storage/Backup and Computer peripherals necessary to interface with the computer system. This planned upgrade on the Unit 2 DRMS Communications System will result in the loss of Unit 2 radiological monitoring capability in the Control Room and on the Plant Computer System (PCS). Neither the Emergency Response Facilities nor the Emergency Response Data System (ERDS) will receive radiological data. No actual radiation monitors are affected. The scheduled work duration is approximately three weeks.
"When the DRMS is out of service for the upgrade, compensatory actions will be in place. Radiation monitors will be continuously monitored for any increases in radiation levels. The Unit 2 Shift Manager will be notified of any increase in radiation monitor readings, including exceeding Emergency Action Levels (EAL).
"This is an eight-hour, non-emergency notification for a Loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the upgrade to the DRMS Communications System will result in the loss of the Unit 2 radiological monitoring capability in the Control Room and to the Unit 2 Plant Computer System that affects the functionality of an Emergency Response Facility.
"There is no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The licensee is currently in a Technical Specification Action Statement, Limiting Condition for Operation for spent fuel pool radiation monitor and leakage rate monitor.
Power Reactor
Event Number: 53929
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: WAYNE GRIFFIN
HQ OPS Officer: JEFFREY WHITED
Region: 1 State: NY
Unit: [2] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: WAYNE GRIFFIN
HQ OPS Officer: JEFFREY WHITED
Notification Date: 03/12/2019
Notification Time: 11:21 [ET]
Event Date: 03/11/2019
Event Time: 12:35 [EDT]
Last Update Date: 03/12/2019
Notification Time: 11:21 [ET]
Event Date: 03/11/2019
Event Time: 12:35 [EDT]
Last Update Date: 03/12/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
FRED BOWER (R1DO)
FFD GROUP (EMAIL)
FRED BOWER (R1DO)
FFD GROUP (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY REPORT - EMPLOYEE FAILED TO REPORT FOR TESTING
A contract employee failed to report for a random fitness for duty test. The contractor's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector and the NY Public Service Commission.
A contract employee failed to report for a random fitness for duty test. The contractor's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector and the NY Public Service Commission.