Event Notification Report for May 11, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/10/2008 - 05/11/2008
EVENT NUMBERS
44200
Power Reactor
Event Number: 44200
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVID DEES
HQ OPS Officer: BILL HUFFMAN
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: DAVID DEES
HQ OPS Officer: BILL HUFFMAN
Notification Date: 05/11/2008
Notification Time: 06:36 [ET]
Event Date: 05/11/2008
Event Time: 03:00 [CDT]
Last Update Date: 05/11/2008
Notification Time: 06:36 [ET]
Event Date: 05/11/2008
Event Time: 03:00 [CDT]
Last Update Date: 05/11/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
BLAIR SPITZBERG (R4)
BLAIR SPITZBERG (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Standby |
LOSS OF SAFETY FUNCTION DUE TO BOTH RHR TRAINS BEING INOPERABLE DURING MODE 3
"On 05/11/2008, at 0300 CDT, Technical Specification 3.0.3 was entered when excessive leakage was identified on EJ8842 RHR to hot leg injection relief valve. Due to the location in the system this leak adversely affected the operability of both RHR trains. EJHV8716A and EJHV8716B RHR Hot Leg Injection cross tie valves were closed to isolate the leak path. Technical Specification 3.5.2 does not have a CONDITION statement that addresses both RHR trains being out of service in Mode 3.
"At the time of discovery the RCS was being heated towards NOP/NOT. RCS pressure was 1340 psig and temperature 504F.
"The Unit is being cooled down to reenter Mode 4 at this time. When the Unit enters Mode 4 Technical Specification 3.5.3 will be in effect. Technical Specification 3.5.3 requires one Emergency Core Cooling System (ECCS) Train to be operable while in Mode 4. An operable ECCS train includes both an RHR Subsystem, and a Centrifugal Charging Pump (CCP) subsystem. The requirement to have EJHV8716A and EJHV8716B open is not applicable to Technical Specification 3.5.3.
"The Unit will remain in Mode 4 until EJ8842 is restored to Operable status.
"The Resident Inspector has been notified."
"On 05/11/2008, at 0300 CDT, Technical Specification 3.0.3 was entered when excessive leakage was identified on EJ8842 RHR to hot leg injection relief valve. Due to the location in the system this leak adversely affected the operability of both RHR trains. EJHV8716A and EJHV8716B RHR Hot Leg Injection cross tie valves were closed to isolate the leak path. Technical Specification 3.5.2 does not have a CONDITION statement that addresses both RHR trains being out of service in Mode 3.
"At the time of discovery the RCS was being heated towards NOP/NOT. RCS pressure was 1340 psig and temperature 504F.
"The Unit is being cooled down to reenter Mode 4 at this time. When the Unit enters Mode 4 Technical Specification 3.5.3 will be in effect. Technical Specification 3.5.3 requires one Emergency Core Cooling System (ECCS) Train to be operable while in Mode 4. An operable ECCS train includes both an RHR Subsystem, and a Centrifugal Charging Pump (CCP) subsystem. The requirement to have EJHV8716A and EJHV8716B open is not applicable to Technical Specification 3.5.3.
"The Unit will remain in Mode 4 until EJ8842 is restored to Operable status.
"The Resident Inspector has been notified."