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Event Notification Report for July 29, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/28/2015 - 07/29/2015

** EVENT NUMBERS **


51245 51272 51274

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Agreement State Event Number: 51245
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: STERIGENICS US, LLC
Region: 4
City: HAYWARD State: CA
County:
License #: 6268-01
Agreement: Y
Docket:
NRC Notified By: KENT PENDERGAST
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 07/21/2015
Notification Time: 20:06 [ET]
Event Date: 07/21/2015
Event Time: 00:11 [PDT]
Last Update Date: 07/21/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
HEATHER GEPFORD (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - SOURCE RACK PNEUMATIC CYLINDER FAILURE

The following report was received from the State of California via email:

"On 07/21/15, the Sterigenics Corporate RSO [Radiation Safety Officer] contacted [California - Radiologic Health Branch] RHB-Sacramento office, via an email and telephone, to report the following event in accordance with [10CFR]36.83(a)(4). [The licensee's] email stated the following:

"Last night, at approximately [0011] PDT, at the Sterigenics Hayward Facility (Radioactive materials License 6268-1), the pneumatic cylinder used to raise one of the two source racks (Hoist #1) failed to function as designed. The failure did not cause a stuck source, nor was there any risk of exposure to any individual as a result of this failure. The source did return to the down position in the pool as designed, however, the pneumatic cylinder experienced a failure and a broken flange and is not operable.

"[The licensee] will review, in detail, the cause of this failure and implement appropriate corrective action including any necessary changes in maintenance and equipment and report these changes to [the State of California] in writing, within 30 days, as required by 10CFR36.83(b).

"In the interim, the facility will not commence operations until repairs are completed to the hoist and approval to commence operations is granted by the Corporate RSO and Corporate Engineering.

"[The licensee RSO] further stated that there is no emergency or current issue. A corporate engineer will arrive in San Francisco by [1400 PDT] on 7/21/15, to work on the irradiator. The facility is staffed 24/7 and will notify RHB before resuming any operations.

"[California] RHB will be following up with the licensee."

The irradiator is in safe mode and the licensee will be investigating the reason for the failure.

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Power Reactor Event Number: 51272
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: NATE CLEVELAND
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/28/2015
Notification Time: 01:08 [ET]
Event Date: 07/27/2015
Event Time: 17:30 [CDT]
Last Update Date: 07/28/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CHRISTINE LIPA (R3DO)

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

CONTROL ROOM EMERGENCY VENTILATION SYSTEM INOPERABLE

"On July 27, 2015, at 1730 hours [CDT], the Control Room Emergency Ventilation (CREV) system was declared inoperable due to the 'B' Air Filtration Unit (AFU) Booster Fan discharge damper stuck open in mid-position. In this condition, the CREV system cannot be guaranteed to achieve required design flow rate. As a result, Technical Specification 3.7.4, Condition A, was entered.

"The CREV system maintains a habitable control room environment and ensures the operability of components in the control room emergency zone during accident conditions as well as protection of the operators from a high dose environment assumed during a design basis accident.

"This notification is being made in accordance with 10 CFR 50.72(b)(3)(v)(D) because the CREV system is a single train system, and loss of the CREV system could impact the plant's ability to mitigate the consequences of an accident as stated in Chapter 6 of the UFSAR [Updated Final Safety Analysis Report]. This event is also reportable under 10 CFR 50.72(b)(3)(xiii) since this condition also impacts the control room as an Emergency Response Facility.

"The NRC Resident Inspector has been notified."

Both units are in a seven day technical specification for troubleshooting and repairs. If the control room became uninhabitable, procedure "Complete Loss of Control Room HVAC" would be entered.

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Power Reactor Event Number: 51274
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MARIAZ DAVIS
HQ OPS Officer: JEFF ROTTON
Notification Date: 07/28/2015
Notification Time: 18:55 [ET]
Event Date: 07/28/2015
Event Time: 13:58 [EDT]
Last Update Date: 07/28/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
RAY MCKINLEY (R1DO)

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

DISCOVERED ONE INCH DIAMETER HOLE BETWEEN REACTOR BUILDING AND AUXILIARY BUILDING

"At 1358 [EDT] on July 28, 2015, a 1 inch diameter hole was discovered in the secondary containment wall, between the Reactor Building and the Auxiliary Building, causing the Secondary Containment to become inoperable under Technical Specification 3.6.5.1. Reactor Building pressure was maintained at a negative pressure as required by Technical Specification 3.6.5.1 with the Reactor Building ventilation system in service before and after discovery of the hole. In addition, the Filtration, Recirculation and Ventilation system remained fully operable and remained in standby. The hole was sealed at 1600 and technical specification 3.6.5.1 was exited. Plant operation was not impacted by the event and was operating at 100% power. No personnel injuries resulted from this event."

The hole was discovered by plant personnel that were walking past the wall. Due to the discovery of the hole, the plant is performing an extent of condition inspection.

The licensee notified the NRC Resident Inspector and the Lower Alloways Creek Dispatch.

Page Last Reviewed/Updated Wednesday, July 29, 2015
Wednesday, July 29, 2015