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Event Notification Report for April 16, 2015

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
04/15/2015 - 04/16/2015

EVENT NUMBERS
509885098951386

Power Reactor
Event Number: 50988
Facility: BYRON
Region: 3     State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KARI BENNING
HQ OPS Officer: DANIEL MILLS
Notification Date: 04/16/2015
Notification Time: 01:35 [ET]
Event Date: 04/16/2015
Event Time: 05:00 [CDT]
Last Update Date: 04/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
AARON MCCRAW (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
2 N Y 100 Power Operation 100 Power Operation
Event Text
SCHEDULED MAINTENANCE AFFECTING TECHNICAL SUPPORT CENTER HVAC

"On April 16, 2015, Byron Station will remove part of the Technical Support Center (TSC) emergency ventilation system from service to facilitate necessary surveillance work on the fire protection system. This work is expected to last approximately 4 hours. This maintenance affects the ability of the TSC ventilation to maintain adequate habitability during the duration of an emergency. If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. If the TSC becomes uninhabitable, the Station Emergency Director will relocate the TSC staff to an alternate TSC location in accordance with applicable procedures.

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the potential loss of an emergency response facility because of the unavailability of the ventilation system. An update will be provided once the TSC ventilation has been restored to normal operation."

The NRC Resident Inspector has been notified.

* * * UPDATE FROM SHANE HARVEY TO JOHN SHOEMAKER AT 1646 EDT ON 4/16/15 * * *

Maintenance has been completed and the TSC emergency ventilation system was restored to service at 1300 CDT on 4/16/15.

The NRC Resident Inspector will be notified.

Notified the R3DO (McCraw).


Power Reactor
Event Number: 50989
Facility: DUANE ARNOLD
Region: 3     State: IA
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: HANS OLSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/16/2015
Notification Time: 18:06 [ET]
Event Date: 04/16/2015
Event Time: 13:20 [CDT]
Last Update Date: 04/16/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
AARON MCCRAW (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 AIRLOCK DOORS OPEN SIMULTANEOUSLY

"At 1320 CDT, on April 16, 2015, both doors of a Secondary Containment Airlock were reported to be open. The doors being open at the same time caused a failure to meet SR 3.6.4.1.2 to verify that either the outer door(s) or inner door(s) in each Secondary Containment access opening are closed. The identified condition caused Secondary Containment to be considered inoperable per TS LCO 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.

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

"The NRC Resident Inspector has been notified."

The licensee is investigating how the electrical interlock failed to prevent this occurrence.


Part 21
Event Number: 51386
Rep Org: GE-HITACHI NUCLEAR ENERGY
Licensee: GE-HITACHI NUCLEAR ENERGY
Region: 1
City: WILMINGTON   State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DALE E PORTER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/10/2015
Notification Time: 15:50 [ET]
Event Date: 04/16/2015
Event Time: 00:00 [EDT]
Last Update Date: 09/10/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
PATTY PELKE (R3DO)
PART 21/50.55 REACT (EMAI)
Event Text
PART 21 REPORT - POTENTIAL FAILURE OF ELECTROMATIC RELIEF VALVE CUTOUT SWITCHES

The following information was excerpted from an Interim Part 21 Report, received from GE-Hitachi (GEH) via email:

"[This GEH Report #MFN-15-042 R2, is a closure of a Part 21 60-Day Interim Report Notification, containing] information concerning an evaluation of the failure during bench testing of Electromatic Relief Valve Actuators (ERV - GEH Part number 352B2632G001) caused by the failure of a cutout switch to determine applicability to components previously supplied to and accepted by licensees. GEH has performed component testing but has been unable to complete the evaluation to determine if a Reportable Condition, in accordance with 10 CFR 21.21 exists.

"Testing was unable to model plant conditions with sufficient accuracy to draw conclusions based on the results. As such, in accordance with discussions with the sites previously identified as potentially applicable to this concern, GEH will close this 10 CFR Part 21 evaluation with a 10 CFR 21.21(b) Transfer of Information to the Dresden 2 and 3 and Quad Cities 1 and 2 sites."

References
1. 60-Day Interim Report Notification, Titled: Potential Failure of Electromatic Relief Valve Cutout Switch, Numbered: MFN 15-042 R0, Dated: June 12, 2015.
2. 60-Day Interim Report Notification, Titled: Potential Failure of Electromatic Relief Valve Cutout Switch, Numbered: MFN 15-042 R1, Dated: June 22, 2015.

The original notification was reported on June 12, 2015. Because there was a proprietary information disclaimer at the top of that page, GEH revised the original report and submitted that revised letter on June 17, 2015. The revision 1 letter was posted in ADAMS with the following accession numbers as the original report.

- ML15169A007 - Part 21 60-Day Interim Report Notification: Potential Failure of Electromatic Relief Valve Cutout Switch. (2 page(s), 6/17/2015)
- ML15169A008 - Attachment 1 - US Plants Potentially Affected. (1 page(s), 6/18/2015)
- ML15169A009 - Attachment 2 - 60-Day Interim Report Notification Information per 21.21(a)(2). (2 page(s), 6/18/2015)
- ML15169A010 - Enclosure 1 - MFN 15-042 R0 - Description of Evaluation. (6 page(s), 6/18/2015)

If you have any questions, please call;
Dale E. Porter
Safety Evaluation Program Manager
GE-Hitachi Nuclear Energy Americas LLC
Ph: (910) 819-4491.