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Event Notification Report for April 06, 2011

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
04/05/2011 - 04/06/2011

EVENT NUMBERS
4673846735467364673346731

Research Reactor
Event Number: 46738
Rep Org: OREGON STATE UNIVERSITY
Licensee: OREGON STATE UNIVERSITY
Region: 4
City: CORVALLIS   State: OR
County: BENTON
License #: R-106
Agreement: Y
Docket: 05000243
NRC Notified By: STEVE REESE
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/07/2011
Notification Time: 15:25 [ET]
Event Date: 04/06/2011
Event Time: 00:00 [PDT]
Last Update Date: 04/07/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
NEIL OKEEFE (R4DO)
AL ADAMS (NRR)
Event Text
VIOLATION OF LIMITING CONDITION OF OPERATION 3.8.1, REACTIVITY LIMITS

"Summary of Events:

"The Oregon State University TRIGA« Reactor (OSTR) staff is designing a new experiment which will utilize reactivity oscillation to measure reactor parameters. During attempts to measure the maximum worth of the oscillating absorber on Wednesday, April 6, it was determined that the worth of the preliminary test absorber is $0.60 at the mid-plane of the core. Technical Specification 3.8.1, Reactivity Limits states in part that 'The absolute value of the reactivity worth of any single unsecured experiment shall be less than $0.50.' Measurements were taken in a manner such that the apparatus qualifies as a movable experiment, and moveable experiments are taken to be a subcategory of unsecured experiments.

"A neutron absorber was fabricated by crushing an existing ¢ inch segment of B4C absorber and placing 29.8 grams of the material in a sealed aluminum TRIGA« tube. The reactivity of the absorber was not formally calculated, but it was believed that the worth of the absorber would be less than $0.20. This was based on the fact that a full length control rod absorber (15 inch) is worth about $2.00, depending on position in the core. Past experience has also shown that several grams of Cadmium, a very strong thermal neutron absorber, have a reactivity worth of ~$0.20 in the B-1 position where the absorber was being tested.

"To characterize the worth of the absorber, the reactor was first taken critical with the In-Core-Irradiation-Tube (ICIT) installed in the B-1 position. Critical rod heights were measured and core excess was calculated. The reactor remained critical at 15 watts in automatic mode. The absorber was then manually lowered to the bottom of the ICIT by an operator using a length of nylon line. The regulating rod was observed to behave as anticipated, automatically withdrawing until some maximum worth position near core center was reached by the absorber, and then automatically inserting as the absorber was lowered to the bottom of the core. The worth of the absorber when resting at the bottom of the core was estimated to be less than $0.07.

"When power and reg rod position were stable, the absorber was slowly withdrawn 7.5 inches to the geometric center of the core. The reg rod automatically withdrew to compensate. The difference between reg rod position with no absorber present and reg rod position with the absorber at core center indicated that the worth of the absorber at core center was $0.60. As soon as absorber worth was determined, the reactor was shut down and the absorber was withdrawn from the ICIT. Although oscillatory operation was not planned, the fact that the absorber was moved while the reactor was critical qualified the experiment as a moveable experiment. Since $0.60 is in excess of L.C.O. 3.8.1, reactor operation was secured in accordance with Technical Specification 6.6.2.a."


!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 46735
Facility: GINNA
Region: 1     State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: MIKE SLABY
HQ OPS Officer: PETE SNYDER
Notification Date: 04/06/2011
Notification Time: 21:20 [ET]
Event Date: 04/06/2011
Event Time: 15:30 [EDT]
Last Update Date: 04/07/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
JOHN CARUSO (R1DO)
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
DEGRADED FIRE BARRIER

"During walk downs for a planned site modification on April 6, 2011 at 1530 EDT, two degraded fire barrier seals were identified in the wall between the Auxiliary Building Basement and the Charging Pump Room. The wall is listed as an Appendix R wall between Fire Area (FA) ABBM and FA CHG. The wall separates redundant safe shutdown equipment.

"Two cylindrical six inch penetrations through the wall did not contain the required material to conform to a 3-hour fire rated barrier. This has been identified as a missing fire barrier such that the required degree of separation for redundant safe shutdown trains is lacking.

"A fire watch was established as a compensatory measure on 4/6/11. The discovery of this non-compliance is being reported as an unanalyzed condition as defined by 10 CFR 50.72(b)(3)(ii)(B).

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

* * * RETRACTION FROM ALAN MODZELEWSKI TO JOE O'HARA AT 1628 EDT ON 4/7/11 * * *

"The purpose of this report is to retract the event discussed in Emergency Notification System report #46735 submitted on April 6th, 2011. The ENS notification reported an inadequate fire barrier penetration seal discovered on April 6th, 2011 when maintenance inspected the penetration in preparation for a modification. Initial investigation concluded that the fire barrier penetration seal between the Charging Pump room and Auxiliary Building Basement was inoperable because there was inadequate seal material to provide the required three hour barrier rating. It appeared that when looking in the penetration sleeve that a fire board from the opposite room was visible and no foam material was present.

"Subsequently, an engineering review of the penetration has been completed. The review determined that a minimum of 8 inches of foam is required to maintain a 3-hour rating. Engineering identified that the design also requires a fire board on each side of the foam. Upon measurement it was confirmed that at least 11 inches of the penetration was filled, with a fire board on each side. Based on these measurements, the fire barrier met design requirements and was operable. The individuals performing the initial investigation did not recognize the thickness of the wall. On April 7th, Maintenance proceeded to penetrate the fire barrier for the modification and it was confirmed that foam was behind the fire board. With a 24 inch thick wall, a large portion at the penetration sleeve can be void of material and still meet the 3 hour rating. As such, the April 6th, 2011 event is being retracted.

"The licensee notified the NRC Resident Inspector."

Notified the R1DO (Caruso)


Fuel Cycle Facility
Event Number: 46736
Facility: HONEYWELL INTERNATIONAL, INC.
Region: 2     State: IL
Unit: [] [] []
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
NRC Notified By: MICHAEL GREENO
HQ OPS Officer: JOE O'HARA
Notification Date: 04/07/2011
Notification Time: 11:26 [ET]
Event Date: 04/06/2011
Event Time: 12:05 [CDT]
Last Update Date: 04/07/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
Person (Organization):
BRIAN BONSER (R2DO)
ABY MOHSENI (NMSS)
Event Text
CONTAMINATED WORKER TREATED AT DISPENSARY

"A Honeywell employee (Senior Process Control Engineer) entered the Dispensary at 1205 on 04/06/11 and reported he had foreign material in his right eye. He was on the 1st floor of the FMB (Feeds Material Building) by the glycol heat exchanger closing a valve with a wrench (lazy rod). The wrench struck another pipe and knocked rust off and into his eye. The rust was removed with simple irrigation and a swab. The employee was sent back to work with no additional issues. He was monitored by HP (Health Physics) in the Dispensary and was found to have 5300 dpm/100cm2 (beta, gamma) on his boots and 280 dpm/100cm2 on his coveralls. The individual was not transported offsite. Reported IAW 10CFR40.60 b(3).

"NRC Region II (Richard Gibson) was also informed of this occurrence"


Agreement State
Event Number: 46733
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TICONA POLYMERS INC
Region: 4
City: BISHOP   State: TX
County:
License #: 02441
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOE O'HARA
Notification Date: 04/06/2011
Notification Time: 16:34 [ET]
Event Date: 04/06/2011
Event Time: 00:00 [CDT]
Last Update Date: 04/06/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
NEIL OKEEFE (R4DO)
PAUL MICHALAK (FSME)
Event Text
AGREEMENT STATE REPORT - STUCK SHUTTER ON OHMART MODEL SH-F1 GAUGE

"On April 6, 2011 the Agency [State of Texas] was informed by the licensee that on April 6, 2011, while conducting shutter operational checks, the shutter on an Ohmart Model SH-F1 containing 60 millicuries of Cesium (Cs) -137 was found to be stuck in the open position. The licensee stated that this is the normal operating position for the gauge and because of its location it does not create an exposure risk to any individuals. The licensee has contacted a contractor to repair the gauge. The cause for the failure is under investigation. Additional information will be provided as it is received in accordance with SA - 300."

Texas Incident Number I-8832


Power Reactor
Event Number: 46731
Facility: COOK
Region: 3     State: MI
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JAMES SHAW
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/06/2011
Notification Time: 02:44 [ET]
Event Date: 04/06/2011
Event Time: 04:00 [EDT]
Last Update Date: 04/06/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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
2 N Y 100 Power Operation 100 Power Operation
Event Text
TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE DUE TO PLANNED MAINTENANCE

"At 0400 EDT on Wednesday, April 6, 2011, the Cook Nuclear Plant (CNP) Technical Support Center (TSC) air conditioning and charcoal filtration systems will be removed from service for scheduled maintenance.

"Under certain accident conditions the TSC may become unavailable due to the inability of the air conditioning and charcoal filtration systems to maintain a habitable atmosphere. Compensatory measures exist to relocate TSC personnel to the unaffected unit's control room if necessary.

"TSC ventilation system maintenance is scheduled to be completed by 1600 EDT on Wednesday, April 6, 2011.

"The licensee has notified the NRC Resident Inspector.

"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the loss of an emergency response facility."

* * * UPDATE FROM DEAN BRUCK TO DONG PARK ON 4/6/11 AT 1514 EDT * * *

"The TSC ventilation system maintenance was completed satisfactorily and the system was restored to service at 1455 EDT."

Notified R3DO (Daley).