Event Notification Report for June 06, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/05/2012 - 06/06/2012
EVENT NUMBERS
47997479984799948000
Power Reactor
Event Number: 47997
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: JOE O'HARA
Region: 1 State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: DAVID NOYES
HQ OPS Officer: JOE O'HARA
Notification Date: 06/06/2012
Notification Time: 00:47 [ET]
Event Date: 06/06/2012
Event Time: 00:45 [EDT]
Last Update Date: 06/06/2012
Notification Time: 00:47 [ET]
Event Date: 06/06/2012
Event Time: 00:45 [EDT]
Last Update Date: 06/06/2012
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):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION REGARDING LABOR NEGOTIATIONS
"On June 6, 2012, at 0045 EDT hours and the reactor at 100% core thermal power the following press release being issued by Entergy Nuclear regarding the status of the ongoing labor negotiations.
"Plymouth, Mass. - Entergy Nuclear, the company that owns and operates the Pilgrim Nuclear Power Station is
implementing a contingency staffing plan after weeks of negotiations between the Company and the Utility Workers Union of America Local 369 leadership were unsuccessful in reaching an agreement for a new union contract.
"Local 369 has stated flatly that while its members are not on strike, they reserve the right to walk off the job at any time, without any notice, and leave the nuclear power plant critically understaffed and in violation of the plant's operating license. This disregard for public safety is unacceptable. Accordingly, the company's contingency plan is being implemented.
"The contingency plan for temporary alternate staffing is consistent with Nuclear Regulatory Commission regulations and is in the interest of safety and maintaining formal organizational controls on the plant site. Highly qualified individuals from within Pilgrim's management team as well as the Entergy nuclear fleet will be filling the necessary positions.
"The NRC Resident Inspector staff has been informed of this press release and notification.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi)."
The licensee will be notifying the Massachusetts Emergency Management Agency.
"On June 6, 2012, at 0045 EDT hours and the reactor at 100% core thermal power the following press release being issued by Entergy Nuclear regarding the status of the ongoing labor negotiations.
"Plymouth, Mass. - Entergy Nuclear, the company that owns and operates the Pilgrim Nuclear Power Station is
implementing a contingency staffing plan after weeks of negotiations between the Company and the Utility Workers Union of America Local 369 leadership were unsuccessful in reaching an agreement for a new union contract.
"Local 369 has stated flatly that while its members are not on strike, they reserve the right to walk off the job at any time, without any notice, and leave the nuclear power plant critically understaffed and in violation of the plant's operating license. This disregard for public safety is unacceptable. Accordingly, the company's contingency plan is being implemented.
"The contingency plan for temporary alternate staffing is consistent with Nuclear Regulatory Commission regulations and is in the interest of safety and maintaining formal organizational controls on the plant site. Highly qualified individuals from within Pilgrim's management team as well as the Entergy nuclear fleet will be filling the necessary positions.
"The NRC Resident Inspector staff has been informed of this press release and notification.
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi)."
The licensee will be notifying the Massachusetts Emergency Management Agency.
Power Reactor
Event Number: 47998
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: WARREN BRANDT
HQ OPS Officer: DONG HWA PARK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: WARREN BRANDT
HQ OPS Officer: DONG HWA PARK
Notification Date: 06/06/2012
Notification Time: 05:19 [ET]
Event Date: 06/06/2012
Event Time: 03:27 [CDT]
Last Update Date: 06/06/2012
Notification Time: 05:19 [ET]
Event Date: 06/06/2012
Event Time: 03:27 [CDT]
Last Update Date: 06/06/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
HEATHER GEPFORD (R4DO)
HEATHER GEPFORD (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 |
INADEQUATE COOLING AVAILABLE TO SUPPORT ELECTRICAL POWER SYSTEMS
"Wolf Creek commenced a nuclear plant shutdown in accordance with Technical Specifications. Engineering analysis has determined that with one non-functional Class IE A/C unit, there is inadequate cooling available to support electrical power systems required by Technical Specifications (TS) 3.8.4, 3.8.7, 3.8.9, during all postulated conditions. Actions are currently underway to restore the non-functional Class IE A/C unit to a functional status."
The non-functional Class IE A/C unit had a clogged oil pump strainer. Per TS 3.0.3, Wolf Creek began reducing power and was at 89% power at the time of the report.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM WARREN BRANDT TO DONG PARK AT 0700 EDT ON 06/06/12 * * *
"The A Class IE A/C unit was restored to functional at 6/6/2012 0505 CDT. The plant shutdown was terminated at 87 percent power. Actions are underway to restore the unit to 100 percent power."
Notified R4DO (Gepford).
"Wolf Creek commenced a nuclear plant shutdown in accordance with Technical Specifications. Engineering analysis has determined that with one non-functional Class IE A/C unit, there is inadequate cooling available to support electrical power systems required by Technical Specifications (TS) 3.8.4, 3.8.7, 3.8.9, during all postulated conditions. Actions are currently underway to restore the non-functional Class IE A/C unit to a functional status."
The non-functional Class IE A/C unit had a clogged oil pump strainer. Per TS 3.0.3, Wolf Creek began reducing power and was at 89% power at the time of the report.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM WARREN BRANDT TO DONG PARK AT 0700 EDT ON 06/06/12 * * *
"The A Class IE A/C unit was restored to functional at 6/6/2012 0505 CDT. The plant shutdown was terminated at 87 percent power. Actions are underway to restore the unit to 100 percent power."
Notified R4DO (Gepford).
Power Reactor
Event Number: 47999
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: VINCENT DeCLEMENTE
HQ OPS Officer: STEVE SANDIN
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: VINCENT DeCLEMENTE
HQ OPS Officer: STEVE SANDIN
Notification Date: 06/06/2012
Notification Time: 09:38 [ET]
Event Date: 06/06/2012
Event Time: 06:12 [EDT]
Last Update Date: 06/06/2012
Notification Time: 09:38 [ET]
Event Date: 06/06/2012
Event Time: 06:12 [EDT]
Last Update Date: 06/06/2012
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):
CHRISTOPHER CAHILL (R1DO)
CHRISTOPHER CAHILL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP ON TURBINE MAIN GENERATOR TRIP
"On June 6, 2012, at approximately 0612 hours, Indian Point Unit 2 reactor automatically tripped from 100% steady state power due to a turbine-main generator electrical trip. All rods fully inserted. Investigation into the generator trip is in progress. All systems responded as expected. The Auxiliary Feedwater system actuated and responded as expected and is maintaining steam generator levels. Decay heat removal is via the steam generators to the main condenser. Offsite power and plant electrical lineups are normal. No primary or secondary code safety relief valves lifted. The reactor is in Mode 3 and stable. Unit 3 was unaffected and remains at 100% power."
The NRC Resident Inspector has been notified, and the licensee issued a press release.
"On June 6, 2012, at approximately 0612 hours, Indian Point Unit 2 reactor automatically tripped from 100% steady state power due to a turbine-main generator electrical trip. All rods fully inserted. Investigation into the generator trip is in progress. All systems responded as expected. The Auxiliary Feedwater system actuated and responded as expected and is maintaining steam generator levels. Decay heat removal is via the steam generators to the main condenser. Offsite power and plant electrical lineups are normal. No primary or secondary code safety relief valves lifted. The reactor is in Mode 3 and stable. Unit 3 was unaffected and remains at 100% power."
The NRC Resident Inspector has been notified, and the licensee issued a press release.
Power Reactor
Event Number: 48000
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: ERIC HORVATH
HQ OPS Officer: DONG HWA PARK
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: ERIC HORVATH
HQ OPS Officer: DONG HWA PARK
Notification Date: 06/07/2012
Notification Time: 02:39 [ET]
Event Date: 06/06/2012
Event Time: 19:56 [EDT]
Last Update Date: 06/07/2012
Notification Time: 02:39 [ET]
Event Date: 06/06/2012
Event Time: 19:56 [EDT]
Last Update Date: 06/07/2012
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
DAVE PASSEHL (R3DO)
DAVE PASSEHL (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Standby |
DEGRADED CONDITION DUE TO DISCOVERY OF PRESSURE BOUNDARY LEAKAGE
"On June 6, 2012, at 1956 EDT, with the Unit shutdown for refueling, leakage was identified from a 3/4-inch weld during Reactor Coolant System (RCS) walkdown inspections. The leakage amount was approximately 0.1 gpm pinhole spray.
"During the performance of MODE 3 engineering walkdown inspections in accordance with procedure DB-PF-03010 (ASME Section III, Class 1 and 2), with the RCS at Normal Operating Temperature and Pressure, a pressure boundary leak was identified on the Reactor Coolant Pump (RCP) 1-2 1st seal cavity vent line upstream weld of 3/4 inch small bore pipe socketweld at a 90 degree elbow between the RCP pump and valve RC-407 (1st Seal Cavity Vent Isolation). The plant was in MODE 3 at Normal Operating Pressure and Normal Operating Temperature (NOP/NOT) for the inspections.
"The plant entered Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.13, 'RCS Operational Leakage,' Condition B and procedure DB-OP-02522. 'Small RCS Leaks,' abnormal operating procedure. Plant cooldown to comply with LCO 3.4.13, Condition B, Required Action B.2 is in progress. The cause and resolution are under evaluation.
"This event is reportable within 8 hours under 10CFR50.72(b)(3)(ii)(A).
"The NRC Resident Inspector has been notified. This condition has been documented in the Davis-Besse Corrective Action program as Condition Report 2012-09381."
The plant is required to be in MODE 5 within 36 hours.
"On June 6, 2012, at 1956 EDT, with the Unit shutdown for refueling, leakage was identified from a 3/4-inch weld during Reactor Coolant System (RCS) walkdown inspections. The leakage amount was approximately 0.1 gpm pinhole spray.
"During the performance of MODE 3 engineering walkdown inspections in accordance with procedure DB-PF-03010 (ASME Section III, Class 1 and 2), with the RCS at Normal Operating Temperature and Pressure, a pressure boundary leak was identified on the Reactor Coolant Pump (RCP) 1-2 1st seal cavity vent line upstream weld of 3/4 inch small bore pipe socketweld at a 90 degree elbow between the RCP pump and valve RC-407 (1st Seal Cavity Vent Isolation). The plant was in MODE 3 at Normal Operating Pressure and Normal Operating Temperature (NOP/NOT) for the inspections.
"The plant entered Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.13, 'RCS Operational Leakage,' Condition B and procedure DB-OP-02522. 'Small RCS Leaks,' abnormal operating procedure. Plant cooldown to comply with LCO 3.4.13, Condition B, Required Action B.2 is in progress. The cause and resolution are under evaluation.
"This event is reportable within 8 hours under 10CFR50.72(b)(3)(ii)(A).
"The NRC Resident Inspector has been notified. This condition has been documented in the Davis-Besse Corrective Action program as Condition Report 2012-09381."
The plant is required to be in MODE 5 within 36 hours.