Event Notification Report for April 12, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/11/2010 - 04/12/2010
EVENT NUMBERS
45831458324583345834
Power Reactor
Event Number: 45831
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BRUCK
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BRUCK
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/12/2010
Notification Time: 03:01 [ET]
Event Date: 04/12/2010
Event Time: 04:00 [EDT]
Last Update Date: 04/12/2010
Notification Time: 03:01 [ET]
Event Date: 04/12/2010
Event Time: 04:00 [EDT]
Last Update Date: 04/12/2010
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):
HIRONORI PETERSON (R3DO)
HIRONORI PETERSON (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 92 | Power Operation | 92 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
SCHEDULED MAINTENANCE ON THE TECHNICAL SUPPORT CENTER VENTILATION SYSTEM
"At 04:00 on Monday, April 12, 2010, 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 accident 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 is scheduled to be completed by 22:00 on Monday, April 12, 2010.
"The licensee has notified the NRC Senior 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 FROM SCOTT SCHNEIDER TO CHARLES TEAL AT 1545 EDT ON 4/12/2010 * * *
"The TSC ventilation system maintenance was completed satisfactorily and the system was restored to service at 1415."
The NRC resident inspector has been informed.
Notified R3DO (Orth).
"At 04:00 on Monday, April 12, 2010, 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 accident 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 is scheduled to be completed by 22:00 on Monday, April 12, 2010.
"The licensee has notified the NRC Senior 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 FROM SCOTT SCHNEIDER TO CHARLES TEAL AT 1545 EDT ON 4/12/2010 * * *
"The TSC ventilation system maintenance was completed satisfactorily and the system was restored to service at 1415."
The NRC resident inspector has been informed.
Notified R3DO (Orth).
Power Reactor
Event Number: 45832
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: CHRIS SMOLINSKI
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: CHRIS SMOLINSKI
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/12/2010
Notification Time: 04:49 [ET]
Event Date: 04/12/2010
Event Time: 05:00 [EDT]
Last Update Date: 04/12/2010
Notification Time: 04:49 [ET]
Event Date: 04/12/2010
Event Time: 05:00 [EDT]
Last Update Date: 04/12/2010
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):
JAMES TRAPP (R1DO)
JAMES TRAPP (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 92 | Power Operation | 92 | Power Operation |
PLANNED MODIFICATIONS AFFECTING TECHNICAL SUPPORT CENTER VENTILATION
"A planned modification at the James A. Fitzpatrick (JAF) Nuclear Power Plant will replace an air conditioning chiller unit located in the old administration building. The electrical isolations necessary to safely perform the modification will require tagging out a booster fan common to the chiller unit and the Technical Support Center (TSC) ventilation system. Therefore, the TSC ventilation system will be rendered non-functional during the course of the work activities. The TSC ventilation is expected to be out of service for approximately 12 hours.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the station Emergency Plant Manager will relocate the TSC staff to an alternate TSC location in accordance with applicable site procedures giving first consideration to the Control Room. TSC facility leads have been made aware of this contingency.
"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the potential loss of an emergency response facility (ERF). An update will be provided once the TSC ventilation has been restored to normal operation. The NRC Resident Inspector has been notified."
* * * UPDATE FROM CHRIS SMOLINSKI TO CHARLES TEAL ON 1857 EDT 4/12/10 * * *
Maintenance on the TSC is complete. The TSC has been returned to service.
The licensee has informed the NRC Resident Inspector. Notified R1DO (Gray).
"A planned modification at the James A. Fitzpatrick (JAF) Nuclear Power Plant will replace an air conditioning chiller unit located in the old administration building. The electrical isolations necessary to safely perform the modification will require tagging out a booster fan common to the chiller unit and the Technical Support Center (TSC) ventilation system. Therefore, the TSC ventilation system will be rendered non-functional during the course of the work activities. The TSC ventilation is expected to be out of service for approximately 12 hours.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the station Emergency Plant Manager will relocate the TSC staff to an alternate TSC location in accordance with applicable site procedures giving first consideration to the Control Room. TSC facility leads have been made aware of this contingency.
"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the potential loss of an emergency response facility (ERF). An update will be provided once the TSC ventilation has been restored to normal operation. The NRC Resident Inspector has been notified."
* * * UPDATE FROM CHRIS SMOLINSKI TO CHARLES TEAL ON 1857 EDT 4/12/10 * * *
Maintenance on the TSC is complete. The TSC has been returned to service.
The licensee has informed the NRC Resident Inspector. Notified R1DO (Gray).
Power Reactor
Event Number: 45833
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PAT MINAHAN
HQ OPS Officer: BILL HUFFMAN
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: PAT MINAHAN
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/12/2010
Notification Time: 10:00 [ET]
Event Date: 04/12/2010
Event Time: 07:21 [CDT]
Last Update Date: 04/12/2010
Notification Time: 10:00 [ET]
Event Date: 04/12/2010
Event Time: 07:21 [CDT]
Last Update Date: 04/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BLAIR SPITZBERG (R4DO)
BLAIR SPITZBERG (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
ACTUATION OF BLACKOUT SEQUENCERS DUE TO LOSS OF ONE OFFSITE POWER SOURCE
"At 0721 [CDT] on 4/12/10 the Comanche Peak Nuclear Power Plant experienced a loss of 138 KV transformer XST1 due to a failed transmission line insulator. Unit 1 is currently defueled per 1RF14 refueling outage schedule. Unit 2 was subjected to actuation of both blackout sequencers causing an automatic start of both motor driven Aux Feedwater (AFW) pumps as well as the turbine driven AFW pump.
"No emergency diesel generator started as per design.
"Train B and the turbine driven AFW pumps have been returned to automatic. Train A AFW pump has been removed from service due to damaged pump packing.
"Unit 2 is currently operating in Technical Specification (TS) 3.8.1, Condition A, for one required source of offsite power inoperable and in TS 3.7.5, Condition B, for one train of AFW inoperable.
"With the exception of Train A AFW on Unit 2, all other safety systems functioned per design.
"The licensee has notified the NRC Resident Inspector."
The loss of power to 138 KV transformer XST1 resulted in loss of power to both safeguards busses on Unit 2. The busses performed a load-shed and slow transfer to power supplied from 138 KV transformer XST2 as designed and were re-energized and loads sequenced back onto the busses. The emergency diesel generators are not required to start unless the busses are not re-energized by the alternate offsite transformer. All electrical power related actuations functioned as designed. During this event, the A train AFW pump on Unit 2 started as expected but had to be removed from service due to a pump packing leak. There was no impact on Unit 1 because of its defueled condition.
* * * UPDATE FROM PAT MINAHAN TO DONG PARK ON 1840 EDT 4/12/10 * * *
"The faulted 138 KV [line] insulator has been repaired, and the Unit 2 safeguard busses have been transferred back to their normal power supplies. The 2-01 motor driven AFW pump has been successfully surveillance tested and is available. Unit 2 remains in TS 3.7.5 condition B pending the close out of an engineering evaluation. No further update notifications are planned."
The licensee has informed the NRC Resident Inspector. Notified R4DO (Spitzberg).
"At 0721 [CDT] on 4/12/10 the Comanche Peak Nuclear Power Plant experienced a loss of 138 KV transformer XST1 due to a failed transmission line insulator. Unit 1 is currently defueled per 1RF14 refueling outage schedule. Unit 2 was subjected to actuation of both blackout sequencers causing an automatic start of both motor driven Aux Feedwater (AFW) pumps as well as the turbine driven AFW pump.
"No emergency diesel generator started as per design.
"Train B and the turbine driven AFW pumps have been returned to automatic. Train A AFW pump has been removed from service due to damaged pump packing.
"Unit 2 is currently operating in Technical Specification (TS) 3.8.1, Condition A, for one required source of offsite power inoperable and in TS 3.7.5, Condition B, for one train of AFW inoperable.
"With the exception of Train A AFW on Unit 2, all other safety systems functioned per design.
"The licensee has notified the NRC Resident Inspector."
The loss of power to 138 KV transformer XST1 resulted in loss of power to both safeguards busses on Unit 2. The busses performed a load-shed and slow transfer to power supplied from 138 KV transformer XST2 as designed and were re-energized and loads sequenced back onto the busses. The emergency diesel generators are not required to start unless the busses are not re-energized by the alternate offsite transformer. All electrical power related actuations functioned as designed. During this event, the A train AFW pump on Unit 2 started as expected but had to be removed from service due to a pump packing leak. There was no impact on Unit 1 because of its defueled condition.
* * * UPDATE FROM PAT MINAHAN TO DONG PARK ON 1840 EDT 4/12/10 * * *
"The faulted 138 KV [line] insulator has been repaired, and the Unit 2 safeguard busses have been transferred back to their normal power supplies. The 2-01 motor driven AFW pump has been successfully surveillance tested and is available. Unit 2 remains in TS 3.7.5 condition B pending the close out of an engineering evaluation. No further update notifications are planned."
The licensee has informed the NRC Resident Inspector. Notified R4DO (Spitzberg).
Power Reactor
Event Number: 45834
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RAUL MARTINEZ
HQ OPS Officer: CHARLES TEAL
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RAUL MARTINEZ
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/12/2010
Notification Time: 21:38 [ET]
Event Date: 04/12/2010
Event Time: 19:20 [CDT]
Last Update Date: 04/12/2010
Notification Time: 21:38 [ET]
Event Date: 04/12/2010
Event Time: 19:20 [CDT]
Last Update Date: 04/12/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
BLAIR SPITZBERG (R4DO)
BLAIR SPITZBERG (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY REPORT
"A licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details."
The licensee notified the NRC Resident Inspector.
"A licensed employee supervisor had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details."
The licensee notified the NRC Resident Inspector.