| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/16/2011 - 11/17/2011 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 47433 | Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: MISTRAS SERVICES
Region: 1
City: ASHLAND State: KY
County:
License #: 20173605
Agreement: Y
Docket:
NRC Notified By: MARISSA VEGA-VELEZ
HQ OPS Officer: CHARLES TEAL | Notification Date: 11/14/2011
Notification Time: 10:07 [ET]
Event Date: 11/13/2011
Event Time: 10:58 [CST]
Last Update Date: 11/14/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GEORGE HOPPER (R2DO)
MICHELE BURGESS (FSME)
| Event Text AGREEMENT STATE REPORT - CABLE DISCONNECTED FROM RADIOGRAPHY SOURCE
The State of Kentucky reported a source containing 39 Curies of Ir-192 disconnect from a QSA model 660A radiography camera during radiography of a boiler. There was no leakage or personnel exposure during this event. The licensee contacted a contractor for retrieval. The source was secured and placed inside the camera. The State will follow up with additional details.
Kentucky Report #: 110008 |
| Power Reactor | Event Number: 47443 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: TOM COBBLEDICK
HQ OPS Officer: JOHN KNOKE | Notification Date: 11/16/2011
Notification Time: 03:04 [ET]
Event Date: 11/16/2011
Event Time: 02:22 [EST]
Last Update Date: 11/16/2011 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
DAVID HILLS (R3DO)
JANE MARSHALL (IRD)
CINDY PEDERSON (RA)
BRUCE BOGER (ET)
JENNIFIER UHLE (DRA)
MICHAEL INZER (DHS)
DAVID BARDON (FEMA)
DANIEL GUNN (DOE)
ART WOOD (USDA)
DANIEL CONNALLY (HHS)
|
| 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 ALERT DUE TO FIRE IN ELECTRICAL BUS AFFECTING SAFETY RELATED EQUIPMENT
At 0222 EST on November 16, 2011, an ALERT was declared due to an electrical fire in the auxiliary building which houses safety related equipment. The apparent cause of the fire was due to an unknown source of water leaking on a breaker, thus causing an arc. The electrical fire is out. The plant was at 0% power and will remain shutdown in Mode 5. There was no impact on core cooling, or emergency power supplies.
The licensee has notified the NRC Resident Inspector and state and local agencies.
* * * UPDATE FROM JANE MALLERNEE TO JOHN KNOKE AT 0449 EST ON 11/16/11 * * *
At 0443 EST on November 16, 2011, Davis Besse, Unit 1 exited their ALERT. The electrical short affected the Control Room Emergency Ventilation Fan #1 Damper.
The licensee has notified the NRC Resident Inspector. Notified R3DO (Hills) and Canada Nuclear Safety Commission (Jim Sandlef). |
| Power Reactor | Event Number: 47444 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVID FASHCHER
HQ OPS Officer: JOHN KNOKE | Notification Date: 11/16/2011
Notification Time: 03:33 [ET]
Event Date: 11/16/2011
Event Time: 03:01 [EST]
Last Update Date: 11/16/2011 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
STEVEN VIAS (R2DO)
JANE MARSHALL (IRD)
VICTOR MCCREE (RA)
BRUCE BOGER (NRR)
MICHAEL INZER (DHS)
DAVID BARDON (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 7 | Power Operation | 0 | Hot Shutdown | Event Text UNUSUAL EVENT DUE TO DRYWELL LEAKAGE GREATER THAN 10 GPM
"On 11/16/11 at 0208 EST, Brunswick Nuclear Plant, Unit 2 calculated a drywall floor drain 42 minute leak rate of 5.88 gpm, following several hours of gradually rising floor drain leakage during a plant startup. Tech Spec 3.4.4 A was entered, requiring floor drain leakage to be restored below 5 gpm within 8 hours. At 0253 EST, a 45 minute leak rate of 10.11 gpm was calculated. At 0301 EST, Unusual Event SU 6.1 was declared for unidentified leakage exceeding 10 gpm, and at 0309 EST, a manual reactor scram was inserted from approximately 7% power [10 CFR 50.72(b)(2)(iv)(B)]. Following the scram, the reactor was depressurized at a maximum cooldown rate of 92.5 deg F/hr, and the unidentified leak rate fell less than 10 gpm within 1 hour and less than 5 gpm within 2 hours. Leak rate at 0614 EST on 11/16/11 is 3.82 gpm with reactor pressure at 228 psig.
"The exact nature of the leak is unknown at this time. The current plan is to continue to depressurize and cool down the reactor to Mode 4, such that a full drywall inspection can commence. At present, Brunswick has not terminated the Unusual Event."
Level control is currently being maintained with control rod drives (CRD). The MSIVs were manually closed to control cooldown. The maximum cooldown was observed to be 92.5 F/hour. The plant plans to reopen MISIVs and depressurized to condensate booster pump injection pressure of 350 psig. The plan is to achieve Mode 4 for a leak inspection.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM DAVID FASHCHER TO CHARLES TEAL AT 0550 EST ON 11/16/11 * * *
The leakage rate is currently 3.73 gpm. The decrease is due to lower pressure which is currently at 258 psig. There are no additional changes. The leakage source is not identified at this time. The licensee has notified the NRC Resident Inspector.
Notified R2DO (Vias).
* * * UPDATE FROM DUSTIN LUPTON TO JOHN SHOEMAKER AT 0648 EST ON 11/16/11 * * *
The leakage rate is currently below the T.S. limit due to lower pressure which is currently at 210 psig. There are no additional changes. The plant will remain in an Unusual Event (UE) until further notice. The licensee has notified the NRC Resident Inspector.
Notified R2DO (Vias).
* * * UPDATE FROM DUSTIN LUPTON TO CHARLES TEAL AT 0749 EST ON 11/16/11 * * *
The leakage rate is stable. The leak rate is calculated at 3.04 gpm at 183 psig at 0708 EST. The current reactor pressure is 162 psig. The licensee has notified the NRC Resident Inspector.
Notified R2DO (Vias).
* * * UPDATE FROM DUSTIN LUPTON TO JOHN KNOKE AT 0832 EST ON 11/16/11 * * *
The licensee terminated from their Unusual Event at 0815 EST. The leakage is still unidentified.
The licensee has notified the NRC Resident Inspector.
Notified R2DO (Vias). |
| Power Reactor | Event Number: 47446 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [3] [ ] [ ]
RX Type: (3) M-4-LP, (4) M-4-LP
NRC Notified By: JOSEPH HEGNER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/16/2011
Notification Time: 11:35 [ET]
Event Date: 09/13/2011
Event Time: 09:00 [EST]
Last Update Date: 11/16/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
STEVEN VIAS (R2DO)
PART 21 GROUP ()
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Under Construction | 0 | Under Construction | Event Text EARLY SITE PERMIT POSTULATED SEISMIC ACCELERATION IS LESS THAN PROJECTED BASED ON NEW INFORMATION
"On August 23, 2011, an earthquake occurred with an epicenter 11 miles from the North Anna Unit 3 site. Instruments recorded earthquake data at the North Anna Unit 1 containment structure base mat. Certified data regarding the earthquake was received on September 13, 2011 and a Condition Report was initiated. This best available earthquake data exceeded at low frequencies the Safe-Shutdown Earthquake (SSE) response spectra established in the North Anna Early Site Permit (ESP-003). The event data also exceeded the site 250 foot elevation Ground Motion Response Spectra (GMRS) and the hard rock SSE developed for the North Anna Unit 3 Combined Operating License Application (COLA) based on the ESP SSE spectra.
"The US-APWR standard plant (i.e., Reactor Building Complex and Power Source Building) Certified Seismic Design Response Spectra (CSDRS) envelops the actual seismic response recorded on August 23, 2011. However, the site-specific Seismic Category I Ultimate Heat Sink Related Structures, Essential Service Water Pipe Tunnel and Power Source Fuel Storage Vault use design inputs presented in the ESP. The recorded seismic response on August 23, 2011 exceeded the seismic design spectra presented in the ESP and COLA.
"As defined in 10 CFR 21, this condition represents a 'deviation' in the seismic design information contained in the ESP and a 'defect' in that it involves a 'basic component' that could result in a major design deficiency that has safety implications, if it were to remain uncorrected. Therefore, NRC notification of this condition is required pursuant to 10 CFR 21.21(d)(1). The basis for this conclusion is discussed in the following paragraph.
"In August 2007, the NRC amended the regulations applicable to the licensing and approval processes for nuclear power plants (e.g., ESP, COLA) to clarify various requirements, and made conforming amendments to other related regulations, including 10 CFR21. The discussion of changes to 10 CFR 21 (Federal Register / Vol. 72, No. 166, Page 49424) states that: 'services that are required to support an early site permit application (e.g., geologic or seismic analyses, etc.) that are safety-related and could be relied upon in the siting, design, and construction of a nuclear power plant, are to be treated as basic components as defined in part 21.' The discussion also states: 'if the ESP holder becomes aware of a significant safety concern with respect to its site (e.g., that the specified site characteristics for seismic acceleration is less than the projected acceleration due to new information), the concern should be reported to the NRC so that it may be considered in the review of any future application referencing the ESP.' Based on these statements of consideration, the analyses supporting the seismic design information in the ESP would be considered a 'basic component' and the recorded response data from the August 23, 2011 seismic event represents new information that impacts the seismic analyses.
"This defect resulted from new data, not an error in the performance of the seismic analyses for the ESP. While there was no error in the performance of the seismic analyses, Dominion is assessing whether any changes should be made to the North Anna Unit 3 COLA."
The licensee will be notifying the NRC Resident Inspector. |
| General Information | Event Number: 47447 | Rep Org: NASA GODDARD
Licensee: NASA GODDARD
Region: 1
City: GREENBELT State: MD
County:
License #: 19-05748-03
Agreement: Y
Docket:
NRC Notified By: DAN SIMPSON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/16/2011
Notification Time: 16:37 [ET]
Event Date: 11/16/2011
Event Time: 11:09 [EST]
Last Update Date: 11/16/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
36.83(a)(1) - UNSHIELD STUCK SOURCE
| Person (Organization):
JOHN CARUSO (R1DO)
BILL VON TILL (FSME)
JANE MARSHALL (IRD)
| Event Text IRRADIATOR SOURCE STUCK IN UNSHIELDED POSITION
On November 16, 2011 at 1637 EST, the licensee's Radiation Safety Officer called the NRC Operations Center, as required by 10 CFR 36.83, to report a source not being able to be returned to its normal down position inside a J.L. Shepherd Model 81-24Q Beam Irradiator.
At approximately 1109 EST on November 16, 2011 the source, located inside the right side of the irradiator, was not able to be returned to the down position. An emergency shutter built into the system was deployed, which reduced the radiation intensity surrounding the irradiator, permitting access into the irradiator room. Upon entering the room, it was noted that the source position indicator found on the operating tower mounted on the top of the irradiator showed that the source was about halfway up from its normal down position. A radiation survey taken around the irradiator found one point in front of the emergency shutter to be less than 10 mR/hr at one foot from the irradiator. Further shielding was added at this point which reduced it down to about 0.3 mR/hr.
Contact was made to J. L. Shepherd and arrangements are being made to have a representative come onsite to help return the source to its normal down position.
The location of the event was in the irradiator room inside the Radiation Effects Facility of Building 22 at the NASA Goddard Space Flight Center. 8800 Greenbelt Road, Greenbelt, MI 20771. |
| Power Reactor | Event Number: 47448 | Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: KEVIN HUBER
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/16/2011
Notification Time: 19:04 [ET]
Event Date: 11/16/2011
Event Time: 16:22 [CST]
Last Update Date: 11/16/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
DAVID HILLS (R3DO)
|
| 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 RHR CAPABILITY AFFECTED DUE TO BOTH TRAINS OF RIVER WATER SUPPLY HVAC SYSTEMS INOPERABLE
"At 1622 [CST] on November 16, 2011, NextEra Energy Duane Arnold declared the 'A' River Water Supply inoperable following discovery that the HVAC damper controller was installed in reverse. This would have closed the HVAC intake dampers on high temperature instead of opening them. At this time, the 'B' River Water Supply system was already inoperable for HVAC damper maintenance. This resulted in entering TS 3.7.2 Condition B for both River Water Supply systems inoperable [required action to restore a train or be shutdown in 12 hours]. Both trains of River Water Supply inoperability potentially affect the plant capability to remove residual heat. Therefore, this event is being reported pursuant to the requirements of 10CFR 50.72(b)(3)(v)(B).
"At 1735 [CST] on November 16, 2011 Post Maintenance testing on the 'B' River Water Supply HVAC Dampers was completed and 'B' River Water Supply was declared operable, restoring the capability to remove residual heat.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 47449 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: KEN GOODALL
HQ OPS Officer: BILL HUFFMAN | Notification Date: 11/16/2011
Notification Time: 23:16 [ET]
Event Date: 11/16/2011
Event Time: 17:00 [EST]
Last Update Date: 11/16/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JOHN CARUSO (R1DO)
|
| 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 HPCI DECLARED INOPERABLE DUE TO DUAL POSITION INDICATION ON CLOSED STEAM ADMISSION ISOLATION VALVE
"On November 16, 2011, at 1600 hours [EST], with the reactor at 100% core thermal power and steady state conditions, the High Pressure Coolant Injection (HPCI) system was removed from service for planned testing and the appropriate Limiting Condition for Operation was entered (14 days per TS 3.5.C.2). At 1700 hours during restoration from the testing, the normally closed HPCI steam admission isolation valve (HPCI-2301-3) displayed dual indication (not full closed). The HPCI-2301-3 is a motor-operated valve (MOV) whose safety function is to open upon a HPCI injection/actuation signal.
"The Limiting Condition for Operation (LCO) that had been entered in a planned manner was continued as of 1700 hours due to the apparent degraded performance of the HPCI-2301-3 valve. Currently, troubleshooting into the cause of the anomalous dual indication on HPCI-2301-3 is in progress. However, it is projected that the troubleshooting will not be complete within reportability assessment requirements. Therefore, in accordance with 50.72(b)(3)(v)(D), Pilgrim Nuclear Power Station is providing an 8 hour non-emergency notification that the HPCI System is inoperable.
"This event had no impact on the health and/or safety of the public.
"The NRC Resident Inspector has been notified." | |