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Event Notification Report for June 11, 2014

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
06/10/2014 - 06/11/2014

EVENT NUMBERS
5018950190

!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 50189
Facility: BRAIDWOOD
Region: 3     State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOEY TRUDEAU
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 06/11/2014
Notification Time: 22:42 [ET]
Event Date: 06/11/2014
Event Time: 14:34 [CDT]
Last Update Date: 06/13/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ROBERT DALEY (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
ONE CONTAINMENT SPRAY TRAIN CHEMICAL ADDITIVE FLOW OUT OF SPECIFICATIONS

"At 1434 [CDT] on 06/11/14, the 1A Containment Spray chemical additive flow was found out of tolerance low during surveillance testing. This resulted in an unanalyzed condition in that insufficient chemical additive flow might have resulted in lower than assumed containment spray Ph values during past periods. The impact of the unanalyzed condition has not been fully evaluated. Based on the above, this is being reported in accordance with 10CFR50.72(b)(3)(ii)(B). Engineering analyses are in progress to evaluate the past condition. Actions are in progress to restore the 1A Containment Spray chemical additive flow to within tolerance. The 1B Containment Spray system is operable per Tech Spec 3.6.6 and is capable of providing required chemical additive flow."

The required flow is 30 to 63 gpm. Measured flow was 27 gpm. The last measurement was six years ago.

The licensee notified the NRC Resident Inspector.

* * * RETRACTION PROVIDED BY JOHN LOGAN TO JEFF ROTTON AT 1803 EDT ON 06/13/2014 * * *

"The purpose of this report is to retract EN report #50189 (June 11, 2014). This EN report was made for the 1A Containment Spray chemical additive flow which was found out of tolerance low during surveillance testing. At the time of reporting, it was concluded that this was an unanalyzed condition in that insufficient chemical additive flow may have resulted in lower than assumed containment spray pH values during past periods. This was reported in accordance with 10CFR50.72(b)(3)(ii)(B) as an unanalyzed condition that significantly degrades plant safety.

"At approximately 1700 CDT on Thursday, June 12, 2014, Braidwood Generating Station concluded that the prior EN notification could be retracted based on the completion of Engineering Change 398472, 'Evaluation of As-Found Results for 1A Containment Spray NaOH Additive Flow.'

"The Engineering Change concluded that the approval of the alternate source term (AST) license amendment resulted in the elimination of a minimum containment spray (CS) spray pH value. The current containment release analysis does not credit the addition of sodium hydroxide (NaOH) to CS spray for fission product removal from the containment atmosphere. The long-term retention of captured fission products in the sump water assumes the sump water pH is greater than 7. This is established by the transfer of the containment spray additive tank (CSAT) contents to the sump during CS system operation. To transfer the maximum CSAT inventory to the sump within 8 hours, a minimum NaOH eductor flow of approximately 10 gpm is required. The minimum NaOH injection flow for the 1A CS eductor system (27.0 ' as-found' and 27.7 'as-left' gpm) exceeded 10 gpm so the eductor injection flows meet the criteria to transfer CSAT inventory to the containment recirculation sump within the expected minimum CS system operating time. The out of tolerance flow values recorded at the time of the initial notification are acceptable.

"The licensee has notified the NRC Resident Inspector."

Notified R3DO (Daley).


Power Reactor
Event Number: 50190
Facility: COMANCHE PEAK
Region: 4     State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RAMON VALDEZ
HQ OPS Officer: JEFF ROTTON
Notification Date: 06/11/2014
Notification Time: 23:17 [ET]
Event Date: 06/11/2014
Event Time: 21:40 [CDT]
Last Update Date: 06/11/2014
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
GREG WERNER (R4DO)
JENNIFER UHLE (NRR)
JEFFERY GRANT (IRD)
MARC DAPAS (RA)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
Event Text
UNUSUAL EVENT DECLARED DUE TO HALON GAS RELEASE IN UNIT 2 CABLE SPREADING ROOM

"Release of Halon into the Unit 2 Cable Spreading Room. No indication of fire in the area.

"HU3.1 (Toxic, corrosive, asphyxiant or flammable gases in amounts that have or could adversely affect normal plant operations) was declared at 2154 CDT due to Halon release and Oxygen levels below safe habitability conditions (19% oxygen). Ability still exists to maintain safe operations and safely shut down the reactor.

"No adverse plant response or control board alarms indicated. No smoke or fire in the room and access is provided with SCBA.

"Escalation criteria would be if not able to maintain safe operations or safely shut down the reactor.

"Exit criteria would be when normal oxygen levels are restored to Unit 2 Cable Spreading Room.

"Local NRC resident notified at 2223 CDT."

Unit 2 is stable at 100% power. Unit 1 was not affected and remains stable at 100% power.

The licensee notified the State of Texas, the local counties, and the NRC Resident Inspector.

Notified DHS, FEMA, and NICC. FEMA NWC and Nuclear SSA were notified via email.

* * * UPDATE FROM SCOTT HARVEY TO CHARLES TEAL AT 1642 EDT ON 6/12/14 * * *

At 0330 CDT the Unusual Event was terminated.

The licensee notified the NRC Resident Inspector.

Notified R4DO (Werner), NRR (Uhle), IRD (Grant), DHS, FEMA, and NICC. FEMA NWC and Nuclear SSA were notified via email.