| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/22/2013 - 03/25/2013 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 48825 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: ARENA PHARMACEUTICAL
Region: 4
City: SAN DIEGO State: CA
County:
License #: 6434-37
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: DONG HWA PARK | Notification Date: 03/15/2013
Notification Time: 20:43 [ET]
Event Date: 03/06/2013
Event Time: [PDT]
Last Update Date: 03/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DALE POWERS (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED TRITIUM EXIT SIGN
The following information was received from the California Radiologic Health Branch via e-mail:
"[The Radiation Safety Officer] RSO reported that a tritium exit sign (approximately 20 Ci of H-3) was broken when a forklift hit the sign on 3/6/13. The forklift driver did not report the damaged sign to the RSO until 3/13/13. Initial wipe surveys showed contamination up to 130,000 dpm. The area is not routinely occupied and, since being reported, access has been restricted. The forklift is also secured. A consultant will be used to decontaminate the area and the forklift. A urine sample was collected of the forklift driver on 3/14/13."
California Report 031513 |
| Power Reactor | Event Number: 48842 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: CHRIS LAWS
HQ OPS Officer: VINCE KLCO | Notification Date: 03/22/2013
Notification Time: 06:10 [ET]
Event Date: 03/21/2013
Event Time: 22:40 [PDT]
Last Update Date: 03/22/2013 | 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):
RYAN LANTZ (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 MOMENTARY INNER AND OUTER REACTOR BUILDING ACCESS DOORS OPEN SIMULTANEOUSLY
"During performance of surveillance OSP-CONT-M102, secondary containment had been declared inoperable and Technical Specification 3.6.4.1.A had been entered.
"Operations personnel performing the surveillance were holding the inner door open and testing the outer door interlock. When the individual presented his badge to the badge reader and attempted to open the outer door, the door opened. Per the surveillance contingency actions, the individual immediately shut the door. Momentarily, both the inner and outer reactor building access doors were open.
"The surveillance was completed with no further issues. Technical Specification 3.6.4.1.A was exited and secondary containment was declared operable.
"There were no radiological releases associated with this event.
"No safety system actuations or isolations occurred."
The licensee notified the NRC Resident Inspector. |
| Part 21 | Event Number: 48843 | Rep Org: TOPWORX EMERSON PROCESS MANAGEMENT
Licensee: TOPWORX EMERSON PROCESS MANAGEMENT
Region: 1
City: LOUISVILLE State: KY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BRIAN HAMPTON
HQ OPS Officer: PETE SNYDER | Notification Date: 03/22/2013
Notification Time: 16:29 [ET]
Event Date: 03/22/2013
Event Time: [CDT]
Last Update Date: 03/22/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
JAMES TRAPP (R1DO)
DANIEL RICH (R2DO)
DAVE PASSEHL (R3DO)
GREG WERNER (R4DO)
PART 21 REACTORS (EMAI)
| Event Text INCORRECT INSTALLATION INSTRUCTIONS FOR TOPWORX GO SWITCH
"Applicability: This notice applies only to TopWorx GO switch models C7, C8, H7, H8, M7, M8, R7, and SV7.
"Purpose: The purpose on this TopWorx Information Notice (TIN) is to alert users of the GO Switch models listed above, that TopWorx was made aware of a situation which may affect the performance of the aforementioned equipment.
"We are informing you of this circumstance in accordance with Sections 21.21(b) and 50.55 (e) of 10CFR21.
"Discussion: Recently TopWorx has discovered that an incorrect 10M (Instructions & Operations Manual) for the above mentioned switches was available on the TopWorx website. Within that IOM it stated: 'Do not to use excessive force on external threads when installing, (36 in.-Ibs. max).' The correct value is 35 Ibs.-ft. max as stated in the current IOM.
"Actions Required: Verify the torque value used to install the switches is adequate for the application.
"10CFR21 Implications: TopWorx requests that the recipient of this notice review it and take appropriate action in accordance with 10CFR21.
"From:
Brian Hampton
Vice President, Global Operations
TopWorx
3300 Fern Valley Road
Louisville, KY 40213
Fax: (502) 969-7315." |
| Part 21 | Event Number: 48844 | Rep Org: TENNESSEE VALEY AUTHORITY
Licensee: ENGINE SYSTEMS, INC.
Region: 1
City: DECATUR State: AL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: K J POLSON
HQ OPS Officer: PETE SNYDER | Notification Date: 03/22/2013
Notification Time: 17:06 [ET]
Event Date: 03/22/2013
Event Time: [CDT]
Last Update Date: 03/22/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
JAMES TRAPP (R1DO)
DANIEL RICH (R2DO)
DAVE PASSEHL (R3DO)
GREG WERNER (R4DO)
PART 21 REACTORS (EMAI)
| Event Text DIESEL FUEL INJECTORS FAILED A PRESSURE TEST
"The Tennessee Valley Authority (TVA) recently identified that three (3) fuel injectors that were to be used on the 3A Emergency Diesel Generator failed a pressure test. Corrective Action Program documents were written to document the failure of the fuel injectors to pass a pressure test and to require performance of an engineering evaluation of the condition. It was concluded that this condition has the potential to constitute a reportable condition pursuant to Title 10 of the Code of Federal Regulations (CFR), 10 CFR 21, 'Reporting of Defects and Noncompliance,' and, as such, requires additional evaluation.
"The TVA is working with Engine Systems, Inc., to determine the cause of failure of the fuel injectors. At this time, the evaluation is not expected to be complete until May 31, 2013. Pursuant to the reporting requirements of 10 CFR 21.21(a)(2), if the evaluation of the deviation or failure to comply potentially associated with a substantial safety hazard cannot be completed within 60 days (i.e. by March 23, 2013), an interim report must be submitted to the NRC.
"Name and Address of the Individual Making the Interim Report:
Mr. K. J. Polson
Vice President
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Post Office Box 2000
Decatur, Alabama 35609-2000.
"Identification of the firm supplying the basic component which fails to comply or contains a defect (under evaluation):
Engine Systems, Inc (ESI)
175 Freight Road
Rocky Mount, North Carolina 27804." |
| Power Reactor | Event Number: 48845 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [ ] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: PATRICK HAARHOFF
HQ OPS Officer: PETE SNYDER | Notification Date: 03/22/2013
Notification Time: 19:58 [ET]
Event Date: 11/19/2012
Event Time: 19:00 [CDT]
Last Update Date: 03/22/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
DAVE PASSEHL (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text CONTROL ROD DRIVE CHECK VALVE IN SERVICE LEAK TEST FAILURE
"Control Rod Drive (CRD) Check valves 3-0399-593 and 3-0399-594 are installed on the CRD supply header inside the reactor building to prevent unfiltered radiological release from primary containment past secondary containment through the CRD supply header. The DBA LOCA dose analysis does not postulate the CRD supply piping as a release path. These valves were added in response to NRC IN 90-78. Their function is described in the Dresden UFSAR section 4.6.4.6.
"Control Rod Drive (CRD) check valves 3-0399-593 and 3-0399-594 failed their as found In Service Testing (IST) seat leakage test during refuel outage D3R22.
"Based on the condition of as-found failed seat leakage tests, Engineering determined that CRD check valves 3-0399-593 and 3-0399-594 would not have been able to perform their design functions as described in the UFSAR to maintain the offsite dose and control room dose within regulatory limits.
"The valves were repaired in D3R22 and successfully retested."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 48846 | Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: HARVEY ANDERSON
HQ OPS Officer: VINCE KLCO | Notification Date: 03/24/2013
Notification Time: 09:54 [ET]
Event Date: 03/24/2013
Event Time: 04:58 [EDT]
Last Update Date: 03/24/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
DANIEL RICH (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text AUTOMATIC START OF AN EMERGENCY DIESEL GENERATOR DUE TO A LIGHTNING STRIKE
"At 0458 [EDT], a lightning strike caused a voltage disturbance on the 115 KV offsite power source and resulted in the automatic start of the 'A' emergency diesel generator on an undervoltage relay actuation. The 'A' emergency diesel generator came up to rated frequency and voltage. The voltage disturbance [duration] was not long enough to cause the normal incoming breaker to the 'A' train 7.2 KV safety related bus (XSW1DA) to open or the 'A' emergency diesel generator output breaker to close.
"The voltage disturbance caused the 'A' safety related chiller and some ventilation fans to trip. These loads were subsequently restarted with no issue.
"The 'A' emergency diesel generator was secured and made ready for autostart at 0520 [EDT].
"The station is in Mode 5 for a mid cycle outage to repair a reactor coolant pump seal.
"This notification is being made per 10CFR50.72(b)(3)(iv)(A) as a valid actuation of an emergency diesel generator."
The unit is in a normal electrical shutdown plant configuration.
The licensee notified the NRC Resident Inspector and will notify the State and Local authorities. |
| Power Reactor | Event Number: 48847 | Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ANDREW WISNIEWSKI
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/24/2013
Notification Time: 13:16 [ET]
Event Date: 03/23/2013
Event Time: 23:18 [EDT]
Last Update Date: 03/24/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JAMES TRAPP (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text SWITCHGEAR ROOM DEGRADED FLOOD SEALS
"On 3/23/13 it was identified that a conduit flood seal between an outside manhole and the switchgear rooms is displaced. This degraded flood seal compromises the flooding design of both the East and West Switchgear Rooms.
"Compensatory measures were implemented for the flood seal in accordance with the plants barrier control process. Repairs of the seal are in progress."
Per the licensee these switchgear rooms contain both normal and safety related 4kV and 480 V electrical boards. Compensatory measures implemented include: Plant Maintenance personnel will take actions to seal any leak within 24 hours of a flooding event and also provide sump pumps to remove any water that has leaked in.
The licensee notified the NRC Resident Inspector and the Vermont State Liaison. | |