Alert

The NRC is shutdown due to the lapse in appropriations. Exempted activities to maintain critical health and safety activities and progress on critical activities, including activities outlined in Executive Order 14300, as described in the OMB Approved NRC Lapse Plan will continue.

Event Notification Report for May 22, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/21/2014 - 05/22/2014

** EVENT NUMBERS **

50113

50128

50129

Agreement State	Event Number: 50113
Rep Org: TEXAS DEPARTMENT OF HEALTH Licensee: SEADRIFT COKE LP Region: 4 City: PORT LAVACA State: TX County: License #: LO3432 Agreement: Y Docket: NRC Notified By: KAREN BLANCHARD HQ OPS Officer: PETE SNYDER	Notification Date: 05/14/2014 Notification Time: 15:57 [ET] Event Date: 05/12/2014 Event Time: [CDT] Last Update Date: 05/14/2014
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): VINCENT GADDY (R4DO) FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTER ON A PROCESS GAUGE

"On May 14, 2014, the licensee notified the Agency [Texas Department of Health] that when it was locking out sources on May 12, 2014, for a shutdown it was unable to close the shutter on one of its Ohmart-Vega model SHLG-2 fixed nuclear gauges which contained a 3 curie cesium-137 source. The licensee contacted the manufacturer. A service company came to the licensee's facility on May 14, 2014, and closed the shutter, removed the gauge, and placed it in storage.

"The licensee will send the gauge to the manufacturer for repair. The gauge normally operates with the shutter in the open position. No one received any exposure as a result of this event. Additional information will be provided as it is obtained in accordance with SA-300."

TX # I-9193

Power Reactor	Event Number: 50128
Facility: PEACH BOTTOM Region: 1 State: PA Unit: [2] [3] [ ] RX Type: [2] GE-4,[3] GE-4 NRC Notified By: ADAM FRAIN HQ OPS Officer: DANIEL MILLS	Notification Date: 05/21/2014 Notification Time: 17:39 [ET] Event Date: 05/21/2014 Event Time: 11:00 [EDT] Last Update Date: 05/21/2014
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(B) - UNANALYZED CONDITION	Person (Organization): HAROLD GRAY (R1DO)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
2	N	Y	100	Power Operation	100	Power Operation
3	N	Y	100	Power Operation	100	Power Operation

Event Text

UNANALYZED CONDITION INVOLVING FIRE SAFE SHUTDOWN CAPABILITY

"This notification is to report a condition involving degraded control power wiring that resulted in an adverse impact on the ability to perform Fire Safe Shutdown for a postulated fire in the Main Control Room / Cable Spreading Room (MCR/CSR) complex. Therefore, this notification is being made pursuant to 10CFR 50.72(b)(3)(ii)(B).

"At approximately 1100 hours [EDT], based on inspections being performed as part of an extent-of-condition review, Engineering personnel concluded that a degradation existed involving transfer / isolation switches that potentially impacted the ability to mitigate an Appendix R fire postulated to occur in the MCR/CSR complex. During scheduled maintenance outage windows on March 6, 2014 and May 5, 2014, broken wires were identified and repaired while the associated systems were out of service. Based on completion of the extent of condition walkdowns today, an additional location was identified, raising the potential that this condition existed for a longer period of time. The wiring degradation is limited to the capability of using Shutdown Method 'D' as described in the Peach Bottom Atomic Power Station Fire Protection Program. Shutdown Methods 'A', 'B' and 'C' used for other postulated fire areas were not affected by this condition. The postulated fire would have had to cause the normal control power fuses to fail for the issue to impact the safe shutdown function.

"Compensatory measures have been established until the condition is corrected.

"The NRC Resident Inspector has been informed of this notification."

In the event of fire resulting in a loss of control power, compensatory measures will allow restoration of control power by replacing blown fuses. The compensatory measures are detailed in a temporary change to the MCR/CSR complex fire response procedure. The condition will be repaired during future equipment outages at the earliest opportunity.

Power Reactor	Event Number: 50129
Facility: BROWNS FERRY Region: 2 State: AL Unit: [ ] [2] [ ] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: ERIC STEELE HQ OPS Officer: JEFF ROTTON	Notification Date: 05/22/2014 Notification Time: 02:02 [ET] Event Date: 05/21/2014 Event Time: 17:21 [CDT] Last Update Date: 05/22/2014
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION	Person (Organization): FRANK EHRHARDT (R2DO)

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

STANDBY LIQUID CONTROL INOPERABLE DUE TO TANK INLEAKAGE

"On 5/21/2014 at 1721 CDT, BFN [Browns Ferry Nuclear] U2 declared both trains of standby liquid control (SLC) inoperable due to suspected in-leakage to the U2 SLC tank. Control Room Operators received an alarm for high tank level and corresponding high level on the control room indicator. Personnel were dispatched to check the tank level locally and reported that tank level was high and rising. Based on this report, the SLC tank isolation valve common to both pumps was closed to prevent potentially overflowing the tank. It was subsequently determined that the sensing line had become clogged causing erroneous level indication and the local report of level was incorrect. Sensing lines for the tank level instrumentation were subsequently cleared, indicated tank level then returned to normal, and local check verified that tank level was normal. Operability was restored with tank level being verified normal and isolation valve returned to the open position.

"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D). This is also reportable as a 60-day written report in accordance with 10 CFR 50.73(a)(2)(v)(C) and 10 CFR 50.73(a)(2)(v)(D).

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

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