Event Notification Report for December 31, 2013
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/30/2013 - 12/31/2013
Power Reactor
Event Number: 49682
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: CHARLES TEAL
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BUD HINCKLEY
HQ OPS Officer: CHARLES TEAL
Notification Date: 12/31/2013
Notification Time: 10:50 [ET]
Event Date: 12/31/2013
Event Time: 10:50 [EST]
Last Update Date: 12/31/2013
Notification Time: 10:50 [ET]
Event Date: 12/31/2013
Event Time: 10:50 [EST]
Last Update Date: 12/31/2013
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):
MICHAEL KUNOWSKI (R3DO)
MICHAEL KUNOWSKI (R3DO)
| 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 |
UNAVAILABILITY OF TSC VENTILATION SYSTEM DUE TO SCHEDULED MAINTENANCE
"At 1050 EST on Tuesday, December 31, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.
"Under certain accidents conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.
"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 1600 EST on December 31, 2013.
"The licensee has notified the NRC Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the loss of an emergency response facility."
* * * UPDATE ON 12/31/13 AT 1731 EST FROM BUD HINCKLEY TO DONG PARK * * *
The TSC ventilation system maintenance and testing was completed satisfactorily and the system was restored to service at 1730 EST on 12/31/13.
The licensee will notify the NRC Resident Inspector. Notified R3DO (Kunowski)
"At 1050 EST on Tuesday, December 31, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.
"Under certain accidents conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.
"TSC ventilation system maintenance and post maintenance testing is scheduled to be completed by 1600 EST on December 31, 2013.
"The licensee has notified the NRC Resident Inspector.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the loss of an emergency response facility."
* * * UPDATE ON 12/31/13 AT 1731 EST FROM BUD HINCKLEY TO DONG PARK * * *
The TSC ventilation system maintenance and testing was completed satisfactorily and the system was restored to service at 1730 EST on 12/31/13.
The licensee will notify the NRC Resident Inspector. Notified R3DO (Kunowski)
Power Reactor
Event Number: 49684
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MIKE WEISE
HQ OPS Officer: DONG HWA PARK
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MIKE WEISE
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/31/2013
Notification Time: 12:09 [ET]
Event Date: 12/31/2013
Event Time: 11:12 [EST]
Last Update Date: 12/31/2013
Notification Time: 12:09 [ET]
Event Date: 12/31/2013
Event Time: 11:12 [EST]
Last Update Date: 12/31/2013
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):
RAY MCKINLEY (R1DO)
RAY MCKINLEY (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 |
STACK RADIATION MONITOR NON-FUNCTIONAL FOR PRE-PLANNED MAINTENANCE
The Millstone Station Stack Radiation Monitor, RM-8169, was removed from service at 1112 EST for pre-planned maintenance. The expected return to service time is 1400 EST.
The licensee informed the Connecticut Department of Environmental Protection, Waterford Dispatch and the NRC Resident Inspector.
The Millstone Station Stack Radiation Monitor, RM-8169, was removed from service at 1112 EST for pre-planned maintenance. The expected return to service time is 1400 EST.
The licensee informed the Connecticut Department of Environmental Protection, Waterford Dispatch and the NRC Resident Inspector.
Power Reactor
Event Number: 49685
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: JEFF ROTTON
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/31/2013
Notification Time: 14:51 [ET]
Event Date: 12/31/2013
Event Time: 09:33 [CST]
Last Update Date: 01/03/2014
Notification Time: 14:51 [ET]
Event Date: 12/31/2013
Event Time: 09:33 [CST]
Last Update Date: 01/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
MICHAEL KUNOWSKI (R3DO)
MICHAEL KUNOWSKI (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Standby | 0 | Hot Standby |
UNANALYZED CONDITION DUE TO REMOVAL OF MULTIPLE STEAM GENERATOR LATERAL SUPPORT SHIMS AND BUMPERS
"Prairie Island Unit 2 is currently in Mode 3 with RCS [Reactor Coolant System] at Tave 547 degrees and 2235 psig and preparing for reactor startup following steam generator replacement outage 2R28.
"At 0933 December 31, 2013 it was discovered that multiple upper lateral support shims and bumpers were removed from both 21 and 22 steam generators. This resulted in both loops being declared inoperable and entry into Tech. Spec. [Technical Specification] LCO [Limiting Condition of Operation] 3.4.5 Condition D. It also placed the Unit 2 Reactor Coolant System in an unanalyzed condition for Seismic and LOCA analyses and required this 8 hour report under 10 CFR 50.72(b)(3)(ii)(B).
"During this condition both reactor coolant loops were in operation, adequately removing decay heat and keeping Prairie Island in a safe condition.
"Tech Spec [LCO] 3.4.5 Condition D requires 3 immediate actions: 1. Place the rod control system in a condition incapable of rod withdrawal; action is completed. 2. Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet shutdown margin; action is completed. 3. Initiate action to restore one RCS loop to operable status and operation; action was immediately initiated.
"Actions have been initiated to reinstall all shims and bumpers in both steam generators. Once these actions are completed and verified the unanalyzed condition will be corrected and Technical Specification [LCO] 3.4.5 Condition D will be exited. These actions are expected to be completed by 1600 on December 31, 2013."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1653 EST ON 1/3/2014 FROM TERRY BACON TO MARK ABRAMOVITZ * * *
"Technical Specification 3.4.5 Condition D was exited on December 31, 2013 at 1728 [CST], when 21 and 22 Steam Generator Upper Lateral Supports were restored to the proper configuration to meet seismic acceptance criteria. Additionally, based on further analysis, it was determined that with both Reactor Coolant Loops inoperable that this condition is a loss of safety function and reportable under 50.72(b)(3)(v)(B).
"The licensee has notified the NRC Resident Inspector."
Notified the R3DO (Kunowski).
"Prairie Island Unit 2 is currently in Mode 3 with RCS [Reactor Coolant System] at Tave 547 degrees and 2235 psig and preparing for reactor startup following steam generator replacement outage 2R28.
"At 0933 December 31, 2013 it was discovered that multiple upper lateral support shims and bumpers were removed from both 21 and 22 steam generators. This resulted in both loops being declared inoperable and entry into Tech. Spec. [Technical Specification] LCO [Limiting Condition of Operation] 3.4.5 Condition D. It also placed the Unit 2 Reactor Coolant System in an unanalyzed condition for Seismic and LOCA analyses and required this 8 hour report under 10 CFR 50.72(b)(3)(ii)(B).
"During this condition both reactor coolant loops were in operation, adequately removing decay heat and keeping Prairie Island in a safe condition.
"Tech Spec [LCO] 3.4.5 Condition D requires 3 immediate actions: 1. Place the rod control system in a condition incapable of rod withdrawal; action is completed. 2. Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet shutdown margin; action is completed. 3. Initiate action to restore one RCS loop to operable status and operation; action was immediately initiated.
"Actions have been initiated to reinstall all shims and bumpers in both steam generators. Once these actions are completed and verified the unanalyzed condition will be corrected and Technical Specification [LCO] 3.4.5 Condition D will be exited. These actions are expected to be completed by 1600 on December 31, 2013."
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1653 EST ON 1/3/2014 FROM TERRY BACON TO MARK ABRAMOVITZ * * *
"Technical Specification 3.4.5 Condition D was exited on December 31, 2013 at 1728 [CST], when 21 and 22 Steam Generator Upper Lateral Supports were restored to the proper configuration to meet seismic acceptance criteria. Additionally, based on further analysis, it was determined that with both Reactor Coolant Loops inoperable that this condition is a loss of safety function and reportable under 50.72(b)(3)(v)(B).
"The licensee has notified the NRC Resident Inspector."
Notified the R3DO (Kunowski).