| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/06/2011 - 10/07/2011 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 47318 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: J. YANG AND ASSOCIATE
Region: 4
City: SAN RAMON State: CA
County:
License #: 3694-34
Agreement: Y
Docket:
NRC Notified By: KENT PRENDERGAST
HQ OPS Officer: JOE O'HARA | Notification Date: 10/03/2011
Notification Time: 18:48 [ET]
Event Date: 09/27/2011
Event Time: 09:00 [PDT]
Last Update Date: 10/03/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JACK WHITTEN (R4DO)
DUNCAN WHITE (FSME)
| Event Text AGREEMENT STATE REPORT - LICENSEE FAILED TO TURN IN THEIR NUCLEAR GAUGE AFTER LICENSE WAS TERMINATED
The following was received from the state via e-mail:
"On September 27, 2011, RHB [Radiologic Health Branch] was informed by Pacific Nuclear Technology (PNT) that they collected a moisture density gauge that was left on the adjacent office porch of the BSK & Associate office. The gauge was discovered by BSK & Associate's employee, and according to PNT service records, the gauge belonged to J. Yang and Associates. The gauge was delivered to CDPH-RHB on 09/27/11 by PNT. RHB will investigate to determine how the gauge was lost. Mr. Yang terminated his CA License in 2008, but apparently did not relinquish all of his licensed materials."
CA 5010 Number: 092711 |
| Fuel Cycle Facility | Event Number: 47325 | Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: PHILLIP OLLIS
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/06/2011
Notification Time: 13:16 [ET]
Event Date: 10/05/2011
Event Time: 14:00 [EDT]
Last Update Date: 10/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
| Person (Organization):
STEVEN VIAS (R2DO)
MICHELE SAMPSON (NMSS)
| Event Text ITEM RELIED ON FOR SAFETY NOT AS DESCRIBED IN THE INTEGRATED SAFETY ANALYSIS
"During a review of the Integrated Safety Analysis (ISA) for a 3-gallon can elevator used in the Dry Scrap Recycle (DSR) area, it was determined that the ISA incorrectly describes the IROFS used to control movement of SNM. The system is composed of two sequential can elevators that are used to move SNM to different floors. A Fuel Business System (FBS) automated control and associated gate controls are designated as one of the Items Relied On For Safety (IROFS). In the ISA, this IROFS is incorrectly attributed to the 2nd can elevator instead of the 1st can elevator. Based on a review of this condition, determined at approximately 1400 on October 5, 2011, it was determined that the system was different than analyzed in the ISA and resulted in a failure to meet performance requirements.
"The FBS and associated gate control were in place at all times on the 1st can elevator, was operating correctly, and supported by management measures. No unsafe condition existed. The ISA and associated documentation are being updated to designate the correct can elevator and associated controls.
"Operation of the equipment has been suspended pending additional review and implementation of corrective actions. Additional corrective actions and extent of condition are being evaluated.
"This event is being reported pursuant to the reporting requirements of 10CFR70 Appendix A (b)(1) within 24 hours of discovery."
The licensee will notify NRC Region 2 and State and local authorities. |
| Part 21 | Event Number: 47326 | Rep Org: ATC NUCLEAR
Licensee: MOORE CONTROLLERS
Region: 1
City: OAK RIDGE State: TN
County:
License #:
Agreement: Y
Docket:
NRC Notified By: GREG HOTT
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/06/2011
Notification Time: 13:35 [ET]
Event Date: 10/06/2011
Event Time: [EDT]
Last Update Date: 10/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
MONTE PHILLIPS (R3DO)
PART 21 GROUP (E-MA)
| Event Text PART 21 NOTIFICATION CONCERNING MOORE PROCESS CONTROLLERS
The following information was received from ATC Nuclear via facsimile:
"This notification is in accordance with U.S. Nuclear Regulatory Regulation 10 CFR 21.21(a)(3)(ii)(b).
"Exelon Corporation Clinton and LaSalle Stations have identified common mode failures associated with Moore 535 Controllers (Part Number 535-000000HOST-SSTRV) provided through ATC Nuclear Tennessee. These items were provided as safety related components to Exelon under Clinton Purchase Order 00461980 and LaSalle Purchase Order 00462363. All safety related failures to date appear to originate from these specific purchase orders. The failures have been evaluated with the original equipment manufacturer and appear to be isolated to controllers containing a main processor board containing "Revision F" labeling manufactured in early 2010 (Date Code 1310). These items all passed an extended burn-in during testing. The failures may manifest themselves as process variable (PV) drift, controller reset with loss of controller function, or create nuisance alarm conditions after a relatively short period (less than 1 year) following installation.
"Because the end-use application of each item is not known by ATC Nuclear, the safety hazard evaluation has been deferred to the customer. The Licensees above have been formally notified of the defect." |
| Power Reactor | Event Number: 47327 | Facility: SEABROOK
Region: 1 State: NH
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: BARRY BRADBURY
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/06/2011
Notification Time: 15:17 [ET]
Event Date: 10/06/2011
Event Time: 12:26 [EDT]
Last Update Date: 10/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
MEL GRAY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO LOW STEAM GENERATOR WATER LEVEL
"At 1226 [EDT] today, Seabrook experienced an automatic reactor trip on low steam generator water levels. The low steam generator levels resulted following a trip of one of the two operating main feed pumps. Main feed pump 'A' tripped on low suction pressure while a condensate pump was being returned to service following maintenance on the pump. The emergency feedwater system actuated automatically and recovered steam generator levels. All systems actuated and functioned as designed. The wide range level indication on steam generator 'C' indicated erratically and was declared Inoperable. The plant is stable and being maintained in Mode 3. The station plans to cool the plant to Mode 5 for a previously planned forced outage.
"This notification provides a four-hour report for an actuation of the reactor protection system while the reactor is critical and an eight-hour report for a valid actuation of the emergency feedwater system."
All rods fully inserted. Emergency feedwater has been secured and placed in standby and startup feedwater is supplying the steam generators. Decay heat is being removed to the condenser via the turbine bypass valves. Electrical systems are in a normal shutdown alignment. There is nothing unusual or not understood and all systems functioned as required.
The licensee has notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 47328 | Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVE BORGER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 10/06/2011
Notification Time: 16:47 [ET]
Event Date: 10/06/2011
Event Time: 11:40 [EDT]
Last Update Date: 10/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
MEL GRAY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 99 | Power Operation | 99 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECTION SYSTEM INOPERABLE
"On 10/06/2011 the control room was notified of an oscillation occurring on the output of Unit 2 High Pressure Coolant Injection (HPCI) pump electronic governor. These oscillations are occurring while the system is in standby and is an early indication of potential governor failure. The governor oscillations were discovered on 10/06/2011 at 1140 EDT by the system engineer while performing system trending analysis via plant computer points.
"HPCI was declared inoperable and LCO 3.5.1 was entered at 1140 EDT on 10/06/2011.
"An investigation is in progress. Unit 1 HPCI and both Unit 1 and Unit 2 RCIC (Reactor Core Isolation Cooling) systems are unaffected as the electronic governor outputs for this equipment is stable and trending as expected.
"This is being reported as a loss of an entire safety function condition in accordance with 10CFR50.72(b)(3)(V)(D)."
The licensee notified the NRC Resident Inspector. |
| Fuel Cycle Facility | Event Number: 47329 | 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: ROBERT STOKES
HQ OPS Officer: BILL HUFFMAN | Notification Date: 10/06/2011
Notification Time: 17:34 [ET]
Event Date: 10/06/2011
Event Time: 11:25 [CDT]
Last Update Date: 10/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
40.60(b)(3) - MED TREAT INVOLVING CONTAM
| Person (Organization):
STEVEN VIAS (R2DO)
MICHELE SAMPSON (NMSS)
| Event Text MEDICAL TREATMENT OF EMPLOYEES WITH CONTAMINATION ON CLOTHING
"Two maintenance employees were exposed to anhydrous hydrogen fluoride while working on a chemical storage tank. The two employees were taken to the plant dispensary for first aid treatment. Both employees were treated and released to return to work. Radiological surveys of the employees in the dispensary showed contamination on both of the employees work shoes and one of the employee coveralls.
"[The contamination was from] U3O8 Uranium Ore Concentrate, Natural Uranium.
"[This event is reportable under] 40.60(b)(3) - Unplanned Medical Treatment at a Medical Facility of an individual with spreadable contamination."
The licensee has notified appropriate local authorities and NRC Region 2. | |