Event Notification Report for December 02, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/01/2009 - 12/02/2009
Power Reactor
Event Number: 45535
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MARK JANKIN
HQ OPS Officer: DONG HWA PARK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: MARK JANKIN
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/02/2009
Notification Time: 17:09 [ET]
Event Date: 12/02/2009
Event Time: 13:45 [CST]
Last Update Date: 12/02/2009
Notification Time: 17:09 [ET]
Event Date: 12/02/2009
Event Time: 13:45 [CST]
Last Update Date: 12/02/2009
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):
RICK DEESE (R4DO)
RICK DEESE (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 |
NOTIFICATION TO KANSAS DEPARTMENT OF HEALTH
"Notification to State agency due to sample exceeding limits.
"On 12/2/09, Wolf Creek received lab results for Wastewater Treatment Basin samples. The sample taken on 11/14/09 exceeded the National Pollutant Discharge Elimination System (NPDES) daily limit of 15 parts per million (ppm) for oil and grease. The result was 18.3 ppm. Exceeding this limit required notification to the State. The Kansas Department of Health and Environment, Bureau of Water was notified on 12/2/2009 that our NPDES limit was exceeded."
The licensee notified the NRC Resident Inspector.
"Notification to State agency due to sample exceeding limits.
"On 12/2/09, Wolf Creek received lab results for Wastewater Treatment Basin samples. The sample taken on 11/14/09 exceeded the National Pollutant Discharge Elimination System (NPDES) daily limit of 15 parts per million (ppm) for oil and grease. The result was 18.3 ppm. Exceeding this limit required notification to the State. The Kansas Department of Health and Environment, Bureau of Water was notified on 12/2/2009 that our NPDES limit was exceeded."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 45536
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVID HALL
HQ OPS Officer: DONG HWA PARK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVID HALL
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/02/2009
Notification Time: 17:25 [ET]
Event Date: 12/02/2009
Event Time: 13:41 [EST]
Last Update Date: 12/02/2009
Notification Time: 17:25 [ET]
Event Date: 12/02/2009
Event Time: 13:41 [EST]
Last Update Date: 12/02/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DANIEL HOLODY (R1DO)
DANIEL HOLODY (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 |
POTENTIAL FIRE PREVENTING REDUNDANT CHILL WATER PUMP FROM OPERATING
"During reconstitution of the post fire safe shutdown analysis, it was noted that conditions exist whereby the requirements of the Hope Creek fire protection program (BTP CMEB 9.5-1) for the required degree of separation for redundant safe shutdown trains may not be met.
"A postulated fire in one of the reactor building fire zones (RB1 or RB2) may affect the ability to operate a required chilled water circulating pump due to the logic interrelationships between the cooling fans and their associated chilled water pump. Specifically, a fire in one area may affect cooling fans from each division and the fan failures could either trip or prevent the redundant chilled water pump from operating. This has the effect of removing the fire barrier between redundant safe shutdown trains. As such, this event is reportable under 10CFR50.72(b)(3)(ii)(B) for the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.
"Fire watches have been implemented in accordance with our approved fire protection program as an interim compensatory measure. All required safe shutdown systems remain operable. No systems or safety-related equipment actuations occurred or were required or expected as a result of this condition. All systems and safety-related equipment affected by this condition remain operable and functional. Nothing has been noted as unusual or not understood. The only system affected is the chill water system. There were no actuations or initiating signals, nor effects of the event on the plant. No personnel have been injured."
The NRC Resident Inspector will be notified.
"During reconstitution of the post fire safe shutdown analysis, it was noted that conditions exist whereby the requirements of the Hope Creek fire protection program (BTP CMEB 9.5-1) for the required degree of separation for redundant safe shutdown trains may not be met.
"A postulated fire in one of the reactor building fire zones (RB1 or RB2) may affect the ability to operate a required chilled water circulating pump due to the logic interrelationships between the cooling fans and their associated chilled water pump. Specifically, a fire in one area may affect cooling fans from each division and the fan failures could either trip or prevent the redundant chilled water pump from operating. This has the effect of removing the fire barrier between redundant safe shutdown trains. As such, this event is reportable under 10CFR50.72(b)(3)(ii)(B) for the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.
"Fire watches have been implemented in accordance with our approved fire protection program as an interim compensatory measure. All required safe shutdown systems remain operable. No systems or safety-related equipment actuations occurred or were required or expected as a result of this condition. All systems and safety-related equipment affected by this condition remain operable and functional. Nothing has been noted as unusual or not understood. The only system affected is the chill water system. There were no actuations or initiating signals, nor effects of the event on the plant. No personnel have been injured."
The NRC Resident Inspector will be notified.