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Event Notification Report for May 5, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/02/2014 - 05/05/2014

** EVENT NUMBERS **


50057 50080 50081 50083 50084 50085

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Agreement State Event Number: 50057
Rep Org: COLORADO DEPT OF HEALTH
Licensee: ANALYTICAL INSTRUMENT RECYCLE, INC.
Region: 4
City: GOLDEN State: CO
County:
License #: CO License No
Agreement: Y
Docket:
NRC Notified By: JAMES JARVIS
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 04/24/2014
Notification Time: 16:38 [ET]
Event Date: 02/05/2014
Event Time: [MDT]
Last Update Date: 04/24/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY AZUA (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - LEAKING GENERALLY LICENSED SOURCES

The following was received from the state of Colorado via email:

"On or after February 05, 2014, while working on a license renewal action, the Colorado Radiation Program was informed by the licensee that it had three (3) generally licensed electron capture detectors (ECDs), containing ~15-18 mCi of Ni-63 (each), that [leak tests] indicated contamination in excess of regulatory limits. The devices were determined to be manufactured by Hewlett-Packard and Agilent Technologies (model number verification is pending).

"The licensee reported that upon discovery, the devices were contained to minimize potential contamination spread. The area where gauges were used/handled was surveyed and determined to be free of contamination. The licensee indicated that the manufacturer was notified and the devices have been returned to the manufacturer for disposal.

"Further investigation by the Colorado Radiation Program is pending."

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Power Reactor Event Number: 50080
Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN SELLERS
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/01/2014
Notification Time: 22:33 [ET]
Event Date: 05/01/2014
Event Time: 20:45 [EDT]
Last Update Date: 05/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID AYRES (R2DO)

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

LOSS OF HPCI OPERABILITY DUE TO WATER ACCUMULATION IN THE HPCI TURBINE

"While investigating a Unit 1 high pressure coolant injection (HPCI) room instrument sump level high alarm, condensation was observed dripping out around the HPCI turbine shaft gland seals. A steady stream of water was also observed coming out of the governor end gland seal along with a slight leak coming from the coupling end. Observation revealed that leakage through the 'closed' steam admission valve (1E41-F001) was apparently resulting in water accumulation in the HPCI turbine. A blown fuse that prevented the associated HPCI exhaust drain pot from draining in conjunction with the leakage by the steam admission valve was determined to be sufficient to impact HPCI operability. Required actions were taken in accordance with the Technical Specifications.

"Efforts are underway to determine the actions needed to restore the HPCI system to operable status."

The licensee has notified the NRC Resident Inspector.

* * * UPDATE FROM JOHN SELLERS TO CHARLES TEAL AT 0154 EDT ON 5/2/14 * * *

"HPCI has been restored to an Operable but degraded nonconforming condition. Fuses replaced and automatic functions restored. Leakage confirmed to not be excessive for this condition. Compensatory actions established. Restoration time 2345 EDT 5/1/14."

The licensee will notify the NRC Resident Inspector.

Notified R2DO (Ayers).

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Fuel Cycle Facility Event Number: 50081
Facility: HONEYWELL INTERNATIONAL, INC.
RX Type: URANIUM HEXAFLUORIDE PRODUCTION
Comments: UF6 CONVERSION (DRY PROCESS)
Region: 2
City: METROPOLIS State: IL
County: MASSAC
License #: SUB-526
Agreement: Y
Docket: 04003392
NRC Notified By: ROSS LINDBERG
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/02/2014
Notification Time: 13:43 [ET]
Event Date: 05/02/2014
Event Time: 11:25 [CDT]
Last Update Date: 05/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
Person (Organization):
DAVID AYRES (R2DO)
MIKE FRANOVICH (NMSS)

Event Text

ON-SITE MEDICAL TREATMENT OF A CONTAMINATED INDIVIDUAL

"An employee with a foreign body in his left eye reported to the on-site dispensary this morning. The plant nurse administered first aid and then released the employee to an off-site medical facility for further evaluation. A whole body survey of the employee in his plant clothing was performed. The maximum amount of contamination present was on the employee's boots, 370,667 dpm/100cm2. Prior to leaving the Restricted Area, the employee removed all plant clothing, changed into his personal clothing, and was whole body frisked out of the plant. The employee was free of contamination upon release."

Licensee notified NRC Region II Division of Fuel Facility Inspection personnel.

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Part 21 Event Number: 50083
Rep Org: FLOWSERVE US INC.
Licensee: FLOWSERVE US INC., FLOW CONTROL DIVISION
Region: 1
City: RALEIGH State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAMES MCGEEHIN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/02/2014
Notification Time: 16:48 [ET]
Event Date: 05/02/2014
Event Time: [EDT]
Last Update Date: 05/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
DAVID AYRES (R2DO)
MARK HAIRE (R4DO)
PART 21 GROUP (EMAI)

Event Text

PART 21 REPORT - CHECK VALVES WITH MISSING JAM NUTS

The following is a synopsis of information received via facsimile from Flowserve:

Jam nuts were found to be missing on size 4, pressure class 600, normally open, in-line check valves per Flowserve drawing no. 07-45546-01. The valves are used in saturated steam service and must close with a reverse flow of less than 7000 lbs/hr steam at 95 and 1085 psig. The valve operating parts are identified as safety related.

These valves were supplied to both Diablo Canyon and Sequoyah nuclear power plants. Flowserve recommends that all in-service valves be inspected for proper torque and that dual thread staking be provided per revised Flowserve drawings.

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Power Reactor Event Number: 50084
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: NICHOLAS RULLMAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/03/2014
Notification Time: 03:42 [ET]
Event Date: 05/02/2014
Event Time: 19:20 [PDT]
Last Update Date: 05/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARK HAIRE (R4DO)

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

REACTOR BUILDING STACK RADIATION MONITOR FAILURE

"This notification is being made due to a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). At 1920 (PDT), on 05/02/2014, PRM-RE-18, Reactor Building Stack Monitor - Intermediate Range Detector, failed downscale. PRM-RE-1A and PRM-RE-1C, the Reactor Building Stack Monitor - Low and High Range Detectors, both remain operable and fully functional. Compensatory measures are being implemented per plant procedures at this time.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 50085
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: JOSHUA PICKETT
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/03/2014
Notification Time: 15:15 [ET]
Event Date: 05/03/2014
Event Time: 12:09 [CDT]
Last Update Date: 05/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
ANN MARIE STONE (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM DUE TO GENERATOR/TURBINE LOAD MISMATCH

"At 1209 CDT on 3 May 2014, Dresden Unit 2 automatically scrammed on a Generator-Turbine Load Mismatch signal following a main generator trip. All rods inserted to their full in positions.

"All systems operated as expected. Reactor vessel inventory and pressure are being maintained in automatic.

"The cause of the scram was due to a main generator trip that occurred during a voltage regulator channel transfer. Troubleshooting is in progress to determine the exact cause of the generator trip.

"This condition is being reported pursuant to 10CFR50.72(b)(2)(iv)(B), any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical."

The plant is in a normal shutdown electrical lineup. Main feedwater is being used to maintain reactor vessel level and decay heat is being removed by the main condenser via the turbine bypass valves. There was no impact on Unit 3 which remains stable at 100 percent power.

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Wednesday, May 14, 2014
Wednesday, May 14, 2014