Event Notification Report for October 08, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/07/2009 - 10/08/2009
EVENT NUMBERS
45421
Power Reactor
Event Number: 45421
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVID MANKIN
HQ OPS Officer: CHARLES TEAL
Region: 3 State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: DAVID MANKIN
HQ OPS Officer: CHARLES TEAL
Notification Date: 10/08/2009
Notification Time: 18:06 [ET]
Event Date: 10/08/2009
Event Time: 14:20 [CDT]
Last Update Date: 10/08/2009
Notification Time: 18:06 [ET]
Event Date: 10/08/2009
Event Time: 14:20 [CDT]
Last Update Date: 10/08/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ANN MARIE STONE (R3DO)
ANN MARIE STONE (R3DO)
| 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 |
AUTOMATIC REACTOR SCRAM DURING TESTING
"This report is being made under CFR 50.72(b)(2(iv)(B) for a automatic reactor scram which is preliminarily believed to have been caused while restoring reactor pressure vessel level/pressure instrumentation to service during performance of surveillance test 3.3.3.2-09 Reactor Water Level and Pressure Instruments Calibration .
"In addition, this report is being made under CRF 50.72(b)(3)(iv)(A) due to PCIS (Primary Containment Isolation System) Groups 2, 3 and 4 being received when reactor water level dropped below 170 due to the expected level shrink immediately following a reactor scram. All isolations went to completion. Reactor water level was recovered to normal vessel level as expected under post scram conditions.
"The following Technical Specification LCOs (Limiting Conditions of Operation) were in affect at the time of the reactor scram:
"TS 3.7.5, Required Action A.1, 30 day completion time for 'B' Control Building Chiller;
TS 3.7.2, Required Action A.1, 7 day completion time for 'B' River Water Supply loop;
TS 3.3.3.1, Function 6, Required Action A.1, 30 day completion time for position indication of MO-1949B, 'B' Residual Heat Removal Heat Exchanger Vent;
TS 3.7.1, Required Action A.1, 30 day completion time for 1P22D, 'D' Residual Heat Removal Service Water Pump.
"All rods fully inserted during the scram. The plant is in a normal shutdown electrical lineup with offsite sources powering the safety busses. No safety or relief valves lifted during the transient. Decay heat is being removed via the steam bypass [valves to the] condenser.
"The licensee notified the NRC Resident Inspector."
"This report is being made under CFR 50.72(b)(2(iv)(B) for a automatic reactor scram which is preliminarily believed to have been caused while restoring reactor pressure vessel level/pressure instrumentation to service during performance of surveillance test 3.3.3.2-09 Reactor Water Level and Pressure Instruments Calibration .
"In addition, this report is being made under CRF 50.72(b)(3)(iv)(A) due to PCIS (Primary Containment Isolation System) Groups 2, 3 and 4 being received when reactor water level dropped below 170 due to the expected level shrink immediately following a reactor scram. All isolations went to completion. Reactor water level was recovered to normal vessel level as expected under post scram conditions.
"The following Technical Specification LCOs (Limiting Conditions of Operation) were in affect at the time of the reactor scram:
"TS 3.7.5, Required Action A.1, 30 day completion time for 'B' Control Building Chiller;
TS 3.7.2, Required Action A.1, 7 day completion time for 'B' River Water Supply loop;
TS 3.3.3.1, Function 6, Required Action A.1, 30 day completion time for position indication of MO-1949B, 'B' Residual Heat Removal Heat Exchanger Vent;
TS 3.7.1, Required Action A.1, 30 day completion time for 1P22D, 'D' Residual Heat Removal Service Water Pump.
"All rods fully inserted during the scram. The plant is in a normal shutdown electrical lineup with offsite sources powering the safety busses. No safety or relief valves lifted during the transient. Decay heat is being removed via the steam bypass [valves to the] condenser.
"The licensee notified the NRC Resident Inspector."