Event Notification Report for March 22, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/21/2008 - 03/22/2008
Power Reactor
Event Number: 44087
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RICH KLINEFELTER
HQ OPS Officer: JOHN KNOKE
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RICH KLINEFELTER
HQ OPS Officer: JOHN KNOKE
Notification Date: 03/22/2008
Notification Time: 11:01 [ET]
Event Date: 03/22/2008
Event Time: 10:35 [EDT]
Last Update Date: 03/23/2008
Notification Time: 11:01 [ET]
Event Date: 03/22/2008
Event Time: 10:35 [EDT]
Last Update Date: 03/23/2008
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):
NEIL PERRY (R1)
NEIL PERRY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
LOSS OF SPDS/ERDS COMPUTER SYSTEM GREATER THAN 8 HOURS
"At 1035 hours, on 03/22/2008, the Unit 1 SPDS and ERDS system was removed from service to disconnect and remove a temporary power supply to support a planned maintenance outage on the PICSY computer normal power supply. The disconnection and removal of temporary power is expected to have a duration greater than 8 hours, but less than 24. During this time, control room hardwire indications will be available. An update will be provided when SPDS/ERDS becomes available.
"Since the Unit 1 SPDS/ERDS computer system will be unavailable for greater than 8 hours, this is considered a Loss of Emergency Assessment Capability and reportable under 10 CFR50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector.
* * UPDATE FROM JIM HUFFORD TO JOHN KNOKE AT 0423 EDT ON 3/23/08 * *
"This is a follow-up courtesy notification to EN# 44087. As of 0213 EDT, on 03/23/08, Unit 1 ERDS and PICSY are now fully restored. The planned outage activities are now complete. No further maintenance scheduled."
The licensee notified the NRC Resident Inspector.
"At 1035 hours, on 03/22/2008, the Unit 1 SPDS and ERDS system was removed from service to disconnect and remove a temporary power supply to support a planned maintenance outage on the PICSY computer normal power supply. The disconnection and removal of temporary power is expected to have a duration greater than 8 hours, but less than 24. During this time, control room hardwire indications will be available. An update will be provided when SPDS/ERDS becomes available.
"Since the Unit 1 SPDS/ERDS computer system will be unavailable for greater than 8 hours, this is considered a Loss of Emergency Assessment Capability and reportable under 10 CFR50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector.
* * UPDATE FROM JIM HUFFORD TO JOHN KNOKE AT 0423 EDT ON 3/23/08 * *
"This is a follow-up courtesy notification to EN# 44087. As of 0213 EDT, on 03/23/08, Unit 1 ERDS and PICSY are now fully restored. The planned outage activities are now complete. No further maintenance scheduled."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 44088
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MARK ARNOSKY
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/22/2008
Notification Time: 20:50 [ET]
Event Date: 03/22/2008
Event Time: 19:39 [EDT]
Last Update Date: 03/22/2008
Notification Time: 20:50 [ET]
Event Date: 03/22/2008
Event Time: 19:39 [EDT]
Last Update Date: 03/22/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
NEIL PERRY (R1)
NEIL PERRY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
TURBINE TRIP RESULTING IN A REACTOR SCRAM
"Limerick Unit 1 automatically shutdown from a turbine trip at 1939 hrs on 03/22/08. The cause of the turbine trip is under investigation at this time. All control rods inserted as required. No ECCS [Emergency Core Cooling System] and no RCIC [Reactor Core Isolation Cooling] initiation occurred. No primary or secondary containment isolations were received.
"The plant is currently in Hot Shutdown maintaining normal reactor level with feedwater in service."
Minimum water level after the scram was 5 inches. Level 3 had been reached however all level 3 isolation valves were already shut. No SRVs lifted after the scram. Decay heat is being removed by steam loads with the turbine bypass valves available if needed. The plant is in its normal shutdown electrical lineup.
The licensee will issue a press release and has informed the NRC Resident Inspector.
"Limerick Unit 1 automatically shutdown from a turbine trip at 1939 hrs on 03/22/08. The cause of the turbine trip is under investigation at this time. All control rods inserted as required. No ECCS [Emergency Core Cooling System] and no RCIC [Reactor Core Isolation Cooling] initiation occurred. No primary or secondary containment isolations were received.
"The plant is currently in Hot Shutdown maintaining normal reactor level with feedwater in service."
Minimum water level after the scram was 5 inches. Level 3 had been reached however all level 3 isolation valves were already shut. No SRVs lifted after the scram. Decay heat is being removed by steam loads with the turbine bypass valves available if needed. The plant is in its normal shutdown electrical lineup.
The licensee will issue a press release and has informed the NRC Resident Inspector.