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Event Notification Report for March 21, 2015

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
03/20/2015 - 03/21/2015

EVENT NUMBERS
5091450915

Power Reactor
Event Number: 50914
Facility: DUANE ARNOLD
Region: 3     State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MIKE STROPE
HQ OPS Officer: VINCE KLCO
Notification Date: 03/21/2015
Notification Time: 04:15 [ET]
Event Date: 03/21/2015
Event Time: 00:30 [CDT]
Last Update Date: 03/21/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
GREGORY ROACH (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
Event Text
BOTH SECONDARY CONTAINMENT DOORS OPENED SIMULTANEOUSLY

"At 0030 CDT, on March 21, 2015, both doors of a Secondary Containment Airlock were opened concurrently by two separate individuals. The doors being open at the same time caused a failure to meet SR [Surveillance Requirement] 3.6.4.1.2 to verify that either the outer door(s) or the inner door(s) in each Secondary Containment access opening are closed. The identified condition caused Secondary Containment to be considered inoperable per TS LCO [Technical Specification Limiting Condition for Operation] 3.6.4.1. Upon discovery, immediate action was taken to close the doors. The doors were open concurrently for a momentary amount of time. The action to close the door allowed SR 3.6.4.1.2 to be met, and restored Secondary Containment to an operable status.

"This notification is being made pursuant to 10 CFR 50.72(b)(3)(v)(C).

"The NRC Resident Inspector has been notified."


!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 50915
Facility: MONTICELLO
Region: 3     State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: LEE ROY ANDERSON
HQ OPS Officer: JEFF HERRERA
Notification Date: 03/21/2015
Notification Time: 13:55 [ET]
Event Date: 03/21/2015
Event Time: 05:37 [CDT]
Last Update Date: 05/11/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
GREGORY ROACH (R3DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 95 Power Operation 95 Power Operation
Event Text
HIGH PRESSURE COOLANT INJECTION INOPERABLE DUE TO CONDENSATION IN STEAM LINE

"At 0537 CDT on March 21, 2015, following the High Pressure Coolant Injection (HPCI) system quarterly pump and valve surveillance, after HPCI was removed from service, an alarm for the HPCI Turbine Inlet High Drain Pot Level did not reset. This indicated that LS-23-90 (HPCI Steam Supply Drain High Level Bypass) did not reset, which could be an indication that condensate exists in the steam line. The system responded as designed but the alarm did not clear as expected. Without assurance that the condensate has been removed from the HPCI steam line, HPCI remains inoperable for reasons other than the planned surveillance. As a result, this condition is being reported under 10 CFR 50.72(b)(3)(v)(D) as a condition that could have prevented fulfillment of the safety function at the time of discovery.

"The health and safety of the public was maintained as the plant was in a normal condition with no initiating event in progress.

"The NRC Resident Inspector has been notified."

The State of Minnesota will be notified.

* * * RETRACTION FROM RANDY SAND TO DANIEL MILLS AT 1445 EDT ON 5/11/15 * * *

"On March 21, 2015, Northern States Power Minnesota reported a condition that could have prevented the fulfillment of a safety function under 10 CFR 50.72(b)(3)(v)(D). The High Pressure Coolant Injection (HPCI) System was declared inoperable for a reason other than planned maintenance due to the failure of the HPCI Steam Supply Drain Hi Level Bypass Level Switch to clear the high level alarm subsequent to actuation.

"An engineering evaluation was performed and concluded that the function of the primary pathway to remove condensate remained unchallenged by the condition present on the level switch This conclusion was also validated via thermography with the HPCI steam supply pressurized and bypass valve open. The verification that the primary pathway was functional provides reasonable assurance that the HPCI steam supply was always clear of condensate supporting the ability of HPCI to perform its required safety function. Therefore, the condition present on the level switch did not render HPCI inoperable. The conclusions of the engineering evaluation provide the basis for retraction of the ENS report made on March 21.

"The NRC Resident Inspector has been notified."

The licensee will also notify the State of Minnesota.

Notified R3DO (Peterson).