Event Notification Report for September 03, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/02/2016 - 09/03/2016
Power Reactor
Event Number: 52221
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ZACH HYDE
HQ OPS Officer: DANIEL MILLS
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ZACH HYDE
HQ OPS Officer: DANIEL MILLS
Notification Date: 09/03/2016
Notification Time: 08:44 [ET]
Event Date: 09/03/2016
Event Time: 07:10 [CDT]
Last Update Date: 09/03/2016
Notification Time: 08:44 [ET]
Event Date: 09/03/2016
Event Time: 07:10 [CDT]
Last Update Date: 09/03/2016
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GREG WARNICK (R4DO)
CHRIS MILLER (NRR)
BRIAN McDERMOTT (NRR)
KRISS KENNEDY (R4RA)
BERNARD STAPLETON (IRD)
GREG WARNICK (R4DO)
CHRIS MILLER (NRR)
BRIAN McDERMOTT (NRR)
KRISS KENNEDY (R4RA)
BERNARD STAPLETON (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 93 | Power Operation | 93 | Power Operation |
UNUSUAL EVENT DECLARED DUE TO SEISMIC EVENT ALARM
At 0710 CDT, Cooper Nuclear Station declared a Notification of Unusual Event under EAL HU1.1 due to the station seismic event alarm registering a response to an earthquake (epicenter near Pawnee, OK). The reactor was not affected by the earthquake and remains at 93 percent power. The licensee is performing walkdowns of structures and equipment to verify that the site is unaffected.
Notified the DHS SWO, FEMA Ops Center, DHS NICC, FEMA National Watch Center (E-mail) and Nuclear SSA (E-mail).
* * * UPDATE FROM ZACH HYDE TO STEVEN VITTO AT 1704 EDT ON 9/3/2016 * * *
At 1547 CDT, Cooper Nuclear Station terminated the Notice of Unusual Event. All inspections and walkdowns of the plant have been completed. No damage or injuries were reported. The seismic event caused no impact to the plant.
The Licensee has notified the NRC Resident Inspector.
Notified R1DO (Warnick), NRR EO (Miller), IRDMOC (Stapleton), DHS SWO, FEMA Ops Center, DHS NICC, FEMA National Watch Center (E-mail) and Nuclear SSA (E-mail).
At 0710 CDT, Cooper Nuclear Station declared a Notification of Unusual Event under EAL HU1.1 due to the station seismic event alarm registering a response to an earthquake (epicenter near Pawnee, OK). The reactor was not affected by the earthquake and remains at 93 percent power. The licensee is performing walkdowns of structures and equipment to verify that the site is unaffected.
Notified the DHS SWO, FEMA Ops Center, DHS NICC, FEMA National Watch Center (E-mail) and Nuclear SSA (E-mail).
* * * UPDATE FROM ZACH HYDE TO STEVEN VITTO AT 1704 EDT ON 9/3/2016 * * *
At 1547 CDT, Cooper Nuclear Station terminated the Notice of Unusual Event. All inspections and walkdowns of the plant have been completed. No damage or injuries were reported. The seismic event caused no impact to the plant.
The Licensee has notified the NRC Resident Inspector.
Notified R1DO (Warnick), NRR EO (Miller), IRDMOC (Stapleton), DHS SWO, FEMA Ops Center, DHS NICC, FEMA National Watch Center (E-mail) and Nuclear SSA (E-mail).
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 52222
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE BRUMMITT
HQ OPS Officer: STEVEN VITTO
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE BRUMMITT
HQ OPS Officer: STEVEN VITTO
Notification Date: 09/03/2016
Notification Time: 12:47 [ET]
Event Date: 09/03/2016
Event Time: 09:02 [EDT]
Last Update Date: 11/02/2016
Notification Time: 12:47 [ET]
Event Date: 09/03/2016
Event Time: 09:02 [EDT]
Last Update Date: 11/02/2016
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):
RAY POWELL (R1DO)
RAY POWELL (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 60 | Power Operation | 60 | Power Operation |
UNIDENTIFIED LEAKAGE GREATER THAN TECHNICAL SPECIFICATIONS
"At 0902 EDT, on September 3, 2016, a leak developed from 13 Charging Pump seals that resulted in an unidentified leak rate of 1.3 gpm. Salem Unit 1 entered Technical Specification 3.4.6.2.b for unidentified leakage greater than 1 gpm. The Technical Specification requires the leak rate to be restored to below 1 gpm in a 4 hour period or place the Unit in Hot Standby in the next 6 hours and Cold Shutdown within the following 30 hours. In addition there is an allowable total ECCS leakage outside of Containment value of 0.45 gpm associated with Control Room habitability to comply with GDC-19 [General Design Criteria] limits. 12 Charging Pump was placed in service and 13 Charging Pump was removed from service and isolated. The unidentified leak rate lowered to below the 0.45gpm requirement for the total ECCS leakage outside of containment and the Technical Specification value of 1 gpm.
"This event is being reported under the requirements of 10CFR50.72(b)(3)(ii)(B) as 'the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety' for exceeding the 0.45gpm total ECCS leakage allowable in accordance with GDC-19 limitations.
"The Licensee has notified the NRC Resident and the Lower Alloways Creek Township."
* * * RETRACTION FROM MATT MOG TO STEVEN VITTO ON 11/02/2016 AT 0916 EDT * * *
"The purpose of this notification is to retract event report number 52222 made on 09/03/2016 at 1247 (EDT). Previously PSEG reported that Salem Unit 1 was in an unanalyzed condition due to a leak from the 13 Charging Pump seals exceeding the 0.45 gpm limit for total ECCS leakage outside containment associated with the Control Room Habitability analysis.
"A subsequent engineering evaluation determined that the post-accident ECCS leak rate from the 13 Charging Pump seals that would have existed is 0.33 gpm. This is within the limits of the existing Control Room Habitability analysis and no unanalyzed condition existed.
"Therefore, PSEG is retracting the notification made under 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector was notified of this retraction by the licensee."
Notified R1DO (Schroeder).
"At 0902 EDT, on September 3, 2016, a leak developed from 13 Charging Pump seals that resulted in an unidentified leak rate of 1.3 gpm. Salem Unit 1 entered Technical Specification 3.4.6.2.b for unidentified leakage greater than 1 gpm. The Technical Specification requires the leak rate to be restored to below 1 gpm in a 4 hour period or place the Unit in Hot Standby in the next 6 hours and Cold Shutdown within the following 30 hours. In addition there is an allowable total ECCS leakage outside of Containment value of 0.45 gpm associated with Control Room habitability to comply with GDC-19 [General Design Criteria] limits. 12 Charging Pump was placed in service and 13 Charging Pump was removed from service and isolated. The unidentified leak rate lowered to below the 0.45gpm requirement for the total ECCS leakage outside of containment and the Technical Specification value of 1 gpm.
"This event is being reported under the requirements of 10CFR50.72(b)(3)(ii)(B) as 'the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety' for exceeding the 0.45gpm total ECCS leakage allowable in accordance with GDC-19 limitations.
"The Licensee has notified the NRC Resident and the Lower Alloways Creek Township."
* * * RETRACTION FROM MATT MOG TO STEVEN VITTO ON 11/02/2016 AT 0916 EDT * * *
"The purpose of this notification is to retract event report number 52222 made on 09/03/2016 at 1247 (EDT). Previously PSEG reported that Salem Unit 1 was in an unanalyzed condition due to a leak from the 13 Charging Pump seals exceeding the 0.45 gpm limit for total ECCS leakage outside containment associated with the Control Room Habitability analysis.
"A subsequent engineering evaluation determined that the post-accident ECCS leak rate from the 13 Charging Pump seals that would have existed is 0.33 gpm. This is within the limits of the existing Control Room Habitability analysis and no unanalyzed condition existed.
"Therefore, PSEG is retracting the notification made under 10 CFR 50.72(b)(3)(ii)(B).
"The NRC Resident Inspector was notified of this retraction by the licensee."
Notified R1DO (Schroeder).