wer Reactor Event Number: 41109
Facility: HOPE CREEK Region: 1 State: NJ Unit:  [ ] [ ] RX Type:  GE-4 NRC Notified By: BILL KOPCHICK HQ OPS Officer: MIKE RIPLEY
Notification Date: 10/10/2004 Notification Time: 21:48 [ET] Event Date: 10/10/2004 Event Time: 18:14 [EDT] Last Update Date: 10/11/2004
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION Person (Organization): RICHARD BARKLEY (R1) CHRISTOPHER GRIMES (NRR) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 M/R Y 69 Power Operation 0 Hot Shutdown
Event Text MANUAL REACTOR SCRAM DUE TO A STEAM LEAK IN THE TURBINE BUILDING "At 1814 [hrs. EDT] on October 10, 2004,
Hope Creek Generating Station was manually scrammed due to a steam leak in the Turbine Building. All Control Rods inserted fully.
Subsequent to the manual actuation of the Reactor Protection System, reactor pressure was reduced to minimize the effects of the steam leak.
Degrading Main Condenser Vacuum following the scram resulted in trips of all operating Reactor Feed Pump Turbines at 10 [inches] HgA. The High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) Systems were manually initiated for reactor level control and the Main Steam Isolation Valves (MSIV's) were closed to isolate the leak - MSIV closure was completed prior to reaching the Main Condenser Vacuum isolation setpoint of 21.5 [inches] HgA.
During plant stabilization, Reactor Water Level lowered below the RPS actuation setpoint of 12.5 inches four separate times. First, following the initial scram.
Second, immediately following initiation of the HPCI and RCIC systems, when the 'A' and 'B' Reactor Water Level channels lowered to -38 inches (Level 2). Level 2 is the HPCI and RCIC actuation setpoint and Primary Containment Isolation actuation setpoint for Groups 2, 7, 8, 9, 12, 13, 14, 17, 18, 19, and 20 valves. Because only two of the four Level 2 instrument channels actuated, the isolation of these systems was channel dependent and occurred as required by the respective isolation logic.
Third, following manual closure of the MSIVs. Finally, Reactor Water Level lowered below 12.5 inches following reset of the original manual scram signal which resulted in an automatic scram signal. RCIC was re-initiated manually to restore Reactor Water Level.
"No personnel were injured during this event. The plant is currently stable in OPCON 3 with reactor pressure at 615 psig. Pressure control (decay heat removal) was transitioned to HPCI in pressure control mode during plant stabilization.
Reactor Water Level is being maintained with the Secondary Condensate Pumps. Two loops of RHR in Suppression Pool Cooling mode are in service with Suppression Pool Temperature at 110 degrees F in compliance with Technical Specification 184.108.40.206 Action b.2.
Actions to determine the cause of the steam leak and effect repairs are in progress." The licensee will inform Lower Alloway Creek Township and has informed the NRC resident inspector.
* * * UPDATE ON 10/11/04 @ 0049 HRS EDT BY BAUER TO GOULD * * * On steam leak investigation, a walk down of the turbine building condenser bay determined the source of the leak to be a failure of an 8 inch moisture separator dump line.
The line break is located approximately one foot from the condenser shell penetration. An additional investigation into the root cause of the failure has commenced.
The NRC Resident Inspector was notified and Lower Alloway Creek Township will be notified.
The Reg 1 RDO (Richard Barkley) and EO (Chris Grimes) were informed.
HOO Note: See Event # 41110
Power Reactor Event Number: 41110
Facility: HOPE CREEK Region: 1 State: NJ Unit:  [ ] [ ] RX Type:  GE-4 NRC Notified By: CLYDE BAUER HQ OPS Officer: CHAUNCEY GOULD Notification Date: 10/11/2004 Notification Time: 00:49 [ET] Event Date: 10/10/2004 Event Time: 21:53 [EDT]
Last Update Date: 10/11/2004 Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION Person (Organization): RICHARD BARKLEY (R1) CHRISTOPHER GRIMES (NRR) Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode 1 N N 0 Hot Shutdown 0 Hot Shutdown
Event Text A RPS ACTUATION SIGNAL OCCURRED DUE TO LOW REACTOR WATER LEVEL WHILE IN MODE 3
At 2153 [hrs. EDT] on October 10, 2004, the Hope Creek Generating Station experienced an automatic reactor scram signal on low reactor level +12.5 inches (Level 3) while cooling down following a manual scram.
As previously reported under Event Notification 41109, the Main Steam Isolation Valves (MSIV's) were closed as the result of a steam leak in the Turbine Building.
The +12.5 inch (Level 3) scram occurred from the manual closure of a Safety Relief Valve (SRV) while it was being manually operated to reduce reactor pressure. The SRV was closed when reactor level was +24 inches, resulting in a reactor level shrink.
Reactor level lowered to +8 inches, and stabilized.
The secondary condensate pumps immediately restored reactor level to its normal band following the scram signal. SRV's were being utilized to assist the plant cool down because the High Pressure Coolant Injection (HPCI) system had been manually taken out of service.
The HPCI vacuum tank vacuum pump tripped on an overload/power failure condition, and use was not desired.
The Reactor Core Isolation Cooling (RCIC) system was out of service because of a high reactor level condition, due to plant cool down.
Also, the Reactor Water Cleanup (RWCU) system was out of service due to the initial manual scram that occurred at 1814 hours which prevented normal reactor level blow down.
The NRC Resident Inspector was notified and Lower Alloway Creek Township will be notified. HOO note: See Event # 41109