| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/13/2011 - 05/16/2011 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 46674 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: JOHN KNOKE | Notification Date: 03/15/2011
Notification Time: 16:25 [ET]
Event Date: 03/15/2011
Event Time: 14:56 [CST]
Last Update Date: 05/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
CHUCK CAIN (R4DO)
|
| 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 FLOOD BARRIER PENETRATION NOT SEALED
"During investigations of flood barrier penetrations, a 4 inch conduit has been identified that is not sealed. This conduit penetrates the South wall of the auxiliary building near the transformers into room 19. Flooding through the penetrations could have impacted the ability of the station's auxiliary feedwater (AFW) pumps to perform their design accident mitigation functions.
"This eight-hour notification is being made pursuant to 10 CFR 50.72 (b)(3)(v).
"The penetration is at an elevation of 1007'-8". The river level has been less than 995 feet Mean Sea Level (MSL) since prior to December 1, 2010. The AFW pumps are operable. There are not any indications of conditions that might result in a flood. Actions are in progress to plug the penetration."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION FROM ERICK MATZKE TO DONG PARK ON 5/13/11 AT 1709 EDT* * *
Further investigation has determined that the penetration is adequately sealed inside of the affected structure. Therefore this notification is being retracted.
The licensee will notify the NRC Resident Inspector. Notified R4DO (Walker). |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Part 21 | Event Number: 46760 | Rep Org: ENGINE SYSTEMS, INC
Licensee: ENGINE SYSTEMS, INC
Region: 1
City: ROCKY MOUNT State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TOM HORNER
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/15/2011
Notification Time: 17:29 [ET]
Event Date: 04/15/2011
Event Time: [EDT]
Last Update Date: 05/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
STEVE ORTH (R3DO)
PART 21 GROUP email ()
| Event Text POTENTIAL DEFECT IN MAGNETROL LEVEL SWITCH FROM ENGINE SYSTEMS INCORPORATED
"Engine Systems, Incorporated (ESI) began an evaluation of a level switch on February 16, 2011. Monticello Nuclear Plant returned a level switch for failure evaluation. The reported condition was that the switch mechanism would not actuate throughout the entire level range. ESI supplied the level switch in July, 2008. The switch was functionally tested prior to shipment and it worked properly at that time. It remained in customer inventory until recently when it was tested and the problem was identified.
"This level switch is used in the fuel oil day tank of some EMD 999 emergency diesel generators and controls the fuel transfer pump. Malfunctioning of this switch could prevent the fuel transfer pump from operating and therefore the diesel generator could shut down due to insufficient fuel supply; thus preventing the diesel generator from performing its safety related function. The EMD 999 fuel system also incorporates a backup fuel transfer pump that is controlled by the level alarm switch within the day tank. The backup transfer pump turns on when the low level alarm is actuated and turns off when the high level alarm actuates.
"ESI has been conducting tests and inspections of the returned level switch and will be coordinating with the manufacturer (Magnetrol) to complete our evaluation. To date, no other similar failures with this Magnetrol level switch have been reported to ESI."
Component: Magnetrol level switch, ESI P/N: 8277780-ESI, Magnetrol type A10
Report No: 10CFR21-0101-INT
* * * RETRACTION FROM TOM HORNER TO DONG PARK ON 5/13/11 AT 1146 * * *
The following information was received by facsimile:
"COMPONENT: Magnetrol level switch
ESI P/N: 8277780-ESI
Magnetrol type A 10
"PURPOSE: This report is a follow-up to an interim report (10CFR21-0101-INT) issued by Engine Systems, Inc. (ESI) on 04/15/11 which identified a deviation with a Magnetrol level switch. The interim report was issued because ESI was not able to complete the evaluation within the 60 day requirement of 10CFR21.
"SUMMARY: Evaluation of the level switch failure at Monticello was completed on 5/12/11 and it has been determined that the deviation is not a reportable defect as by defined by 10CFR21. Based on the data collected by ESI and through evaluation by and discussion with Magnetrol (manufacturer of the level switch), it is ESI's conclusion that the level switch was delivered to the customer in working order and that it must have been damaged subsequent to ESI's involvement. Furthermore, within the fuel oil system in which the level switch is installed, there is an inherent redundancy whereby the high/low level alarm switch will actuate to turn on or turn off a secondary fuel transfer pump in the event this level switch (or its associated fuel transfer pump) does not function properly. Therefore, ESI does not consider this as a reportable defect.
Notified R2DO (Guthrie), R3DO (Passehl), and Part 21 group via email. |
| Agreement State | Event Number: 46834 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: METCO
Region: 4
City: HOUSTON State: TX
County:
License #: 03018
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/10/2011
Notification Time: 12:16 [ET]
Event Date: 04/19/2011
Event Time: [CDT]
Last Update Date: 05/10/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE WALKER (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - STUCK RADIOGRAPHY CAMERA SOURCE
The following information was received via facsimile:
"On May 10, 2011, the Agency [Texas Department of Health] received written notification from a licensee that on April 19, 2011, at approximately 12:45 p.m. while performing radiographic operations on a tank, a radiographer found he was unable to retract a 58.6 Curie Iridium (Ir) -192 source into to a QSA Model 880D radiography camera. The radiographers working with the camera immediately repositioned the restricted area barricade to ensure that the barricade was set at less than 2 millirem per hour. The radiographers contacted their office and two source retrieval supervisors immediately proceeded to the jobsite. The Site Radiation Safety Officer was contacted and went to the location.
"The source retrieval team arrived at the secured barricaded area at 1:40 p.m. The radiographers maintained visual surveillance to ensure no members of the public had entered the area. The exposure device was adjacent to the tank's exterior; secured by a magnetic plate lifter, and located approximately 40 feet above ground. The exposure device was removed from the tank using a JLG lift and lowered to the ground. The guide tube was removed from the front of the camera and it was discovered that the source pigtail was sticking out of the front of the camera about one and a half inches. The source was manually retracted to the shielded position and locked in place. A radiation survey of the camera found the readings to be normal. No one exceeded any exposure limits and there was no exposure to any member of the general public. The camera was transported to the licensee's facility and inspected. The camera has been returned to the manufacturer for inspection and repair. The investigation into this event is on going. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident # I-8843. |
| Agreement State | Event Number: 46835 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: TEAM INDUSTRIAL SERVICE INC.
Region: 4
City: ALVIN State: TX
County:
License #: L00087
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: PETE SNYDER | Notification Date: 05/10/2011
Notification Time: 12:43 [ET]
Event Date: 05/10/2011
Event Time: [CDT]
Last Update Date: 05/10/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WAYNE WALKER (R4DO)
GLENDA VILLAMAR (FSME)
| Event Text AGREEMENT STATE REPORT - STUCK RADIOGRAPHY CAMERA SOURCE
"On May 10, 2011, the Agency [Texas Department of Health] was notified by a licensee that while conducting radiography operations at a temporary job site, a pipe fell on the guide tube of a QSA Model 880D camera. The pipe damaged the guide tube preventing the radiographer from retracting the 34.1 curie Iridium (Ir) -192 source into the camera. The radiographer contacted his supervisor and a source recovery team was sent to the location.
"The recovery team was able to repair the guide tube enough to retract the source into the camera. The camera was returned to the licensee's facility for inspection. There was no exposure to a member of the general public and the highest exposure to a member of the recovery team was 28 millirem for the event.
"The investigation into this event is ongoing. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident No. I-8844 |
| Agreement State | Event Number: 46836 | Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: GEORGIA PACIFIC
Region: 3
City: GREEN BAY State: WI
County:
License #: 009-1106-01
Agreement: Y
Docket:
NRC Notified By: MARK PAULSON
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/10/2011
Notification Time: 14:28 [ET]
Event Date: 05/05/2011
Event Time: [CDT]
Last Update Date: 05/10/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVE PASSEHL (R3DO)
GLENDA VILLAMAR (FSME)
| Event Text AGREEMENT STATE REPORT - STUCK FIXED GAUGE SHUTTER MECHANISM
The following information was received via facsimile:
"On May 5, 2011, the Licensee's Radiation Safety Officer reported via phone message that the shutter mechanism on an installed fix gauge failed to close. The gauge is an Ohmart model SHRM-3 with a 500 mCi Cesium-137 source. This malfunction was discovered during routine maintenance testing. No persons were exposed to radiation as a result of the malfunction. The Licensee has restricted access to the area and has scheduled repairs to be done by the manufacturer. DHS plans to perform a follow up inspection within the next 6 months."
Wisconsin Event Report # WI-110004. |
| Power Reactor | Event Number: 46847 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [ ] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RICKY GIVENS
HQ OPS Officer: JOHN KNOKE | Notification Date: 05/13/2011
Notification Time: 01:53 [ET]
Event Date: 05/12/2011
Event Time: 18:25 [CDT]
Last Update Date: 05/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
EUGENE GUTHRIE (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text LOSS OF SHUTDOWN COOLING
"At 1825 CDT on 05/12/2011, with Browns Ferry Nuclear Plant Unit 3 in Mode 4, Browns Ferry Nuclear Plant PCIS [Primary Containment Isolation System] relay maintenance activities for a Group 1 PCIS relay inadvertently interrupted the neutral for a Group 2 PCIS relay and a Group 2 PCIS isolation occurred resulting in a loss of Shutdown Cooling. Relays were reset and Shutdown Cooling was restored at 1905 CDT. Moderator temperature prior to the event was 112.5 degrees F and the highest moderator temperature recorded during the loss of Shutdown Cooling was 122 degrees F.
"This condition is reportable under 10CFR50.72(b)(3)(v) - Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: B.) Remove residual heat.
"This is also reportable as a 60 day written report IAW 10CFR 50.73(a)(2)(v).
"The NRC Resident Inspector has been notified of this event.
"This event was entered into the licensee's Corrective Action Program as SR# 368205". |
| Power Reactor | Event Number: 46852 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: MICHAEL MCDONNELL
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/14/2011
Notification Time: 04:32 [ET]
Event Date: 05/14/2011
Event Time: 02:45 [EDT]
Last Update Date: 05/14/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
| Person (Organization):
ANNE DEFRANCISCO (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 14 | Power Operation | 14 | Power Operation | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO INABILITY TO MAINTAIN SPECIFIED DIFFERENTIAL PRESSURE BETWEEN DRYWELL AND SUPPRESSION CHAMBER
"Following startup from RFO [Refueling Outage] 18, at approximately 14% reactor power, PNPS [Pilgrim Nuclear Power Station] was unable to set the conditions required to demonstrate the drywell to suppression chamber decay rate is less than 25% of the differential pressure decay rate for the maximum allowable bypass area of 0.2 ft2 [as required by] TS [Technical Specification] 3.7.A.4(b).
"Prior to exceeding 15% power, PNPS Technical Specifications require differential pressure between the drywell and suppression chamber to be greater than 1.17 psid. The licensee was not able to achieve this delta pressure and initiated troubleshooting to determine the cause. A plant shutdown is being initiated to continue this effort.
"The plant is in a stable condition. Investigation is continuing into the failure to establish test conditions. There is no threat to the health and safety of the public as a result of this condition."
The licensee suspects leakby in the Drywell to Torus vacuum breaker but will not be able to verify until the plant is shutdown.
The licensee has notified the NRC Resident Inspector and will be notifying the State of Massachusetts. |
| Fuel Cycle Facility | Event Number: 46853 | Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: DEREK WARFORD
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/15/2011
Notification Time: 21:39 [ET]
Event Date: 05/15/2011
Event Time: 12:54 [CDT]
Last Update Date: 05/15/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
EUGENE GUTHRIE (R2DO)
BRITTAIN HILL (NMSS)
| Event Text PORTION OF HIGH PRESSURE FIRE WATER SYSTEM DECLARED INOPERABLE
"At 1254 CDT, on 05/15/2011, the Plant Shift Superintendent was notified that the C-333 High Pressure Fire Water (HPFW) Sprinkler System C-14 had been inspected by Fire Services and eleven sprinkler heads had visible corrosion on them. The system configuration was evaluated using EN-C-822-99-047, 'Effects of Impaired Sprinkler Heads on System Operability' and determined that with these heads potentially impaired, a portion of the building would not have sufficient sprinkler coverage. The HPFW system is required to be operable according to TSR LCO 2.4.4.5. HPFW system C-14 was declared inoperable and TSR LCO 2.4.4.5 Required Action B was implemented for the area without sprinkler coverage. Based on past testing results, there is a possibility that the heads would have been able to perform their specified safety function. Once the heads are removed from the system, testing will be performed to determine the actual affect on operability.
"This event is reportable under 10 CFR 76.120(c)(2) as an event in which equipment required by the TSR is disabled or fails to function as designed.
"The NRC Senior Resident Inspector has been notified of this event.
"PGDP [Paducah Gaseous Diffusion Plant] Assessment and Tracking Report No. ATR-11-1192; PGDP Event Report No. PAD-2011-08; Responsible Division: Operations
"An hourly fire patrol is being conducted in the affected area. [Licensee] estimated correction date: 5/20/2011." | |