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Event Notification Report for November 19, 2011

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
11/18/2011 - 11/19/2011

EVENT NUMBERS
4745947460

!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 47459
Facility: PALO VERDE
Region: 4     State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: AMADO FERNANDEZ
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/19/2011
Notification Time: 16:48 [ET]
Event Date: 11/19/2011
Event Time: 08:28 [MST]
Last Update Date: 12/15/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BLAIR SPITZBERG (R4DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Standby 0 Hot Standby
Event Text
THE LOW PRESSURE SAFETY INJECTION SYSTEM WAS SUBJECTED TO HIGH PRESSURE RESULTING IN BOTH TRAINS BEING DECLARED INOPERABLE

"On November 19, 2011, Unit 1 was in Mode 3. Boration of the four reactor coolant system (RCS) cold leg injection lines was in progress using High Pressure Safety Injection pump 'A'.

"During this activity, 'SI CHK VLV Leak Pressure Hi' alarms were received at 0828 [MST]. The 'A' and 'B' Low Pressure Safety Injection (LPSI) subsystems were declared inoperable because the pressure downstream of the motor operated LPSI injection valves was above 1525 psia. This elevated pressure potentially impacts the ability of the LPSI RCS loop injection valves to open. The high differential pressure may exceed the capability of the motor operator. All four injection line pressures were found above 1525 psia and LCO 3.0.3 was entered due to both trains of LPSI being inoperable. At 0839 [MST], pressure in the 'A' train injection lines was lowered below 1525 psia and 'A' LPSI subsystem was declared operable and LCO 3.0.3 was exited. At 0842 [MST], pressure was reduced below 1525 psia on the 'B' train injection lines and the 'B' LPSI subsystem was declared operable and LCO 3.5.3 condition A was exited.

"This call is being made to report a condition that could have prevented the fulfillment of a safety function required to mitigate the consequences of an accident and unanalyzed condition that existed for 11 minutes while both LPSI subsystems were inoperable.

"The NRC Resident Inspector has been notified."

* * * RETRACTION RECEIVED FROM DANIEL HAUTALA TO CHARLES TEAL AT 1546 EST ON 12/15/11 * * *

"The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via ENS or under the reporting requirements of 10CFR50.73.

"This notification is a retraction of ENS 47459 which was made by Arizona Public Service to report a condition that could have prevented the fulfillment of a safety function required to mitigate the consequences of an accident and an unanalyzed condition that existed for 11 minutes while both LPSI subsystems were declared inoperable when pressure downstream of the motor operated injection valves for safety injection subsystem were declared inoperable. An engineering review of the motor operated valves thrust and torque calculations determined that the affected valves would have been fully capable of performing their intended safety function at the time of the pressure excursion.

"The NRC Resident Inspector has been notified of this retraction."


Power Reactor
Event Number: 47460
Facility: MONTICELLO
Region: 3     State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: MARK IHLENFELDT
HQ OPS Officer: VINCE KLCO
Notification Date: 11/20/2011
Notification Time: 02:10 [ET]
Event Date: 11/19/2011
Event Time: 23:12 [CST]
Last Update Date: 11/20/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID HILLS (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 90 Power Operation 0 Hot Shutdown
Event Text
AUTOMATIC REACTOR SCRAM WHILE PERFORMING TURBINE BYPASS VALVE TESTING

"While performing a regularly scheduled Turbine Bypass Valve surveillance, prior to Turbine Bypass Valve movement, a 'B' half scram [signal] was received. Operators immediately suspended testing. Approximately 10 seconds later, a full Reactor Protection System actuation occurred. Following the reactor scram, reactor water level lowered below the Group II isolation initiation setpoint of +9 inches, [resulting in containment valve isolations]. There were no radioactive releases associated with this event.

"No other alarms were received prior to the RPS actuation. The cause of the reactor scram is under investigation at this time.

"Also, due to the reactor scram, discharge canal temperature rate of change exceeded plant requirements. As a result, the State of Minnesota, and appropriate local agencies will be notified."

All control rods inserted and the scram is considered uncomplicated. The plant is in a normal shutdown electrical configuration.

The licensee notified the NRC Resident Inspector.