| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/09/2013 - 08/12/2013 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 49249 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: MARIA POWERS
HQ OPS Officer: BILL HUFFMAN | Notification Date: 08/08/2013
Notification Time: 03:15 [ET]
Event Date: 08/08/2013
Event Time: 03:05 [EDT]
Last Update Date: 08/10/2013 | Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
SCOTT SHAEFFER (R2DO)
SCOTT MORRIS (IRD)
VICTOR McCREE (R2 R)
JENNIFER UHLE (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 92 | Power Operation | Event Text ALERT DECLARED DUE TO A SWITCHGEAR EXPLOSION THAT SUPPLIES SAFE SHUTDOWN EQUIPMENT
The licensee reported that there was an explosion in a non-safety related electrical bus (Bus 1E2). The bus is designated as a safe shut down bus. The licensee has classified this event as an Alert based on an EAL entry condition of "an explosion of sufficient force to damage permanent structures or equipment within the Protected Area." The licensee is still investigating what loads come off this bus but no safety-related loads have been identified at this time. The plant is currently stable at 92% power. Power was reduced due to the loss of moisture separator reheaters on the secondary side as a result of this event. There is no ongoing fire as a result of the bus explosion. No personnel were injured. No damage to other equipment has been identified at this time.
The licensee has notified state and local authorities and the NRC Resident Inspector.
Notified DHS SWO, DOE, FEMA, HHS, DHS NICC, USDA, EPA, FDA and NuclearSSA via email. NRC PAO (Brenner) notified.
* * * UPDATE AT 0404 EDT ON 8/8/13 FROM TYLER HALYE TO MARK ABRAMOVITZ * * *
"Auxiliary bus 1E2 (safe shutdown equipment bus) is de-energized due to the explosion. The Alert was declared due to the explosion affecting safe shutdown equipment." The licensee also noted that the event was initially classified as an Unusual Event at 0234 EDT and then upgraded to an Alert classification at 0305 EDT when the bus was determined to supply safe shutdown equipment.
The licensee has notified the NRC Resident Inspector.
* * * UPDATE AT 0453 EDT ON 8/8/13 FROM TYLER HALYE TO MARK ABRAMOVITZ * * *
No offsite assistance was requested during this event. The licensee verified that there was no fire. It was noted that the licensee is in Technical Specification Action Statement 3.8.1.1 for the "B" Emergency Diesel Generator being out of service. The EDG is out of service due to loss of power to the "C" and "D" air compressors. The licensee was uncertain if the loss of these air compressors was related to the event.
The licensee has notified the NRC Resident Inspector. R2DO (Shaeffer) and NRR EO (Hiland) notified.
* * * UPDATE AT 0546 EDT ON 8/8/13 FROM SHANNON JONES TO MARK ABRAMOVITZ * * *
The licensee terminated the Alert declaration at 0533 EDT based upon no fire at Bus 1E2 and verification that Bus 1E2 is de-energized and disconnected from all electrical systems. The licensee remains at 92% power. The only noted safety related equipment that was impacted is the "1B" Emergency Diesel Generator which has been declared inoperable due to loss of power to associated air compressors "1C-SB" and "1D-SB."
The licensee has notified the NRC Resident Inspector.
R2DO (Shaeffer), NRR EO (Hiland) and IRD MOC (Morris) notified. Notified DHS SWO, DOE, FEMA, HHS, DHS NICC, USDA, EPA, FDA and NuclearSSA via email. NRC PAO (Brenner) notified.
* * * UPDATE FROM TIM ENGLISH TO HOWIE CROUCH AT 1347 EDT ON 8/10/13 * * *
"It has been determined that operability of the 1B Emergency Diesel Generator (EDG) was not affected by the damage to 480 volt auxiliary bus 1E2. The 1C and 1D starting air compressors for 1B EDG did not lose power and thus the 1B EDG was operable.
"The NRC Resident Inspector has been notified."
Notified R2DO (Shaeffer). |
| Power Reactor | Event Number: 49253 | Facility: SUMMER
Region: 2 State: SC
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: JUSTIN BOUKNIGHT
HQ OPS Officer: BILL HUFFMAN | Notification Date: 08/09/2013
Notification Time: 08:21 [ET]
Event Date: 08/08/2013
Event Time: 19:53 [EDT]
Last Update Date: 08/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Under Construction | 0 | Under Construction | | 3 | N | N | 0 | Under Construction | 0 | Under Construction | Event Text VIOLATION OF THE FITNESS FOR DUTY PROGRAM
A contractor supervisor tested positive for alcohol on a follow-up fitness for duty screening. The individual's construction site access was revoked.
The Unit 2/3 Resident Inspector has been notified. |
| Research Reactor | Event Number: 49257 | Facility: NATIONAL INST OF STANDARDS & TECH
RX Type: 20000 KW TEST
Comments:
Region: 1
City: GAITHERSBURG State: MD
County: MONTGOMERY
License #: TR-5
Agreement: Y
Docket: 05000184
NRC Notified By: SEAN O'KELLY
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/09/2013
Notification Time: 14:29 [ET]
Event Date: 08/08/2013
Event Time: 14:30 [EDT]
Last Update Date: 08/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
ALEXANDER ADAMS (PRLB)
XIAOSONG YIN (PM)
PATRICK ISAAC (IR L)
| Event Text TECHNICAL SPECIFICATION VIOLATION DURING CORE RELOAD
While the reactor was shut down for planned maintenance, the licensee was performing a core reload in accordance with procedure. This procedure requires control rods elements to be withdrawn to get a count rate. As expected, the reactor became critical at some point.
It was noted on 8/8/13 that this criticality was a violation of Technical Specification (TS) 3.1.3 which prohibits operating the reactor with any grid position empty.
This procedure has been used multiple times in the past. A core reload is performed approximately every 4 years.
The licensee plans on either modifying their procedure or TS to prevent this in the future. |
| Power Reactor | Event Number: 49259 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MARK LOOSBROCK
HQ OPS Officer: CHARLES TEAL | Notification Date: 08/09/2013
Notification Time: 17:01 [ET]
Event Date: 08/09/2013
Event Time: 10:00 [CDT]
Last Update Date: 08/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JULIO LARA (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 | | 2 | N | Y | 80 | Power Operation | 80 | Power Operation | Event Text RADIATION MONITOR OUT OF SERVICE
"During the performance of SP [Surveillance Procedure] 1027.2A, NMC Radiation Monitor Train A Calibration, Radiation Monitor R-21, Circulating Water Discharge Radiation Detector failed the source test point three times and was removed from service.
"R-21 has an emergency response function to provide indication of gaseous or liquid effluent release to the environment. This monitor has no compensatory measure that will allow timely classification of two NUE [Notification of Unusual Event] and Alert classifications when out of service.
"This is a priority 1 activity to repair the monitor. The repair activity is continuous and is in progress.
"There are not radioactive leaks that impact the Circulating Water System.
"The NRC Resident Inspector was notified." |
| Power Reactor | Event Number: 49260 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MICHEL CICCONE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 08/09/2013
Notification Time: 22:27 [ET]
Event Date: 08/09/2013
Event Time: 21:19 [EDT]
Last Update Date: 08/09/2013 | 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 | | 3 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL
The loss of a non-vital 480v bus resulted in a feedwater transient that caused steam generator water level to lower below the automatic reactor trip setpoint. The reactor trip and plant response was uncomplicated with all rods being inserted into the core.
The auxiliary feedwater system automatically actuated and is currently being to used to feed the steam generators. Decay heat is being removed via the steam dumps to the condenser. No relief valves or safeties lifted during the transient. The plant is currently stable in Mode 3 at normal operating pressure and temperature and is in its normal shutdown electrical lineup. There was no impact on Unit 2 which is currently operating at 100% power.
The licensee has notified state and local authorities and the NRC Resident Inspector. |
| Power Reactor | Event Number: 49261 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MATTHEW BIRKEL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/10/2013
Notification Time: 01:21 [ET]
Event Date: 08/09/2013
Event Time: 20:28 [CDT]
Last Update Date: 08/10/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
JULIO LARA (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 | | 2 | N | Y | 80 | Power Operation | 80 | Power Operation | Event Text INOPERABLE CONTROL ROOM ENVELOPE
"In 2010, Control Room Envelope testing was conducted to satisfy SR 3.7.10.5 (this surveillance testing is required each 6 years). At that time, as a prerequisite, the surveillance procedure contained a step to add water to two floor drain loop seals that penetrated the Control Room Envelope; this practice was determined to be unacceptable preconditioning. Because the 2010 surveillance test was the first performance of this surveillance, the unacceptable preconditioning resulted in the following: a never-performed surveillance, failure to meet the associated surveillance requirement, and an inoperable Control Room Envelope. At 2028 CDT the station entered LCO 3.7.10, Condition B.
"The station has taken action to periodically add water to the loop seals; this practice validates the loop seals will remain full of water. This action ensures, through Engineering judgment, that the loop seals will perform their function and the Control Room Envelope will provide adequate protection to the plant operators.
"The NRC Resident Inspector was notified."
The floor drains are located inside the control room envelope near the control room chillers. Prior to this report, filling the loop seal was performed sporadically. The loop seal is now filled daily. |
| Power Reactor | Event Number: 49262 | Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES MORGAN
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/10/2013
Notification Time: 10:38 [ET]
Event Date: 08/10/2013
Event Time: 07:11 [EDT]
Last Update Date: 08/10/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
MEL GRAY (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION DUE TO INADVERTENT SINGLE EMERGENCY SIREN ACTIVATION
"Calvert Cliffs was notified at 0711 [EDT] by Calvert Control Center that a siren in the Calvert County Area was activated. [It was] determined to be Siren C15 on Lloyd Bowen Road.
"Per CNG-NL-1.01-1004 this is a verbal report to Calvert Control Center.
"This event is reportable as a 4-hour non-emergency notification [under] 10CFR50.72(b)(2)(xi) as 'Any event resulting in notification to other government agencies that has or will be made.'"
The licensee informed the NRC Resident Inspector. |
| Independent Spent Fuel Storage Installation | Event Number: 49263 | Rep Org: SUSQUEHANNA
Licensee: PPL SUSQUEHANNA LLC
Region: 1
City: ALLENTOWN State: PA
County: LUZERNE
License #: GL
Agreement: Y
Docket: 72-28
NRC Notified By: DOUG LAMARCA
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/10/2013
Notification Time: 10:58 [ET]
Event Date: 08/10/2013
Event Time: 04:30 [EST]
Last Update Date: 08/10/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
72.75(c )(2) - SPENT FUEL, HLW OR RX-REL GTCC RED. EFECT
72.75(d)(1) - SFTY EQUIP. DISABLED OR FAILS TO FUNCTION
| Person (Organization):
MEL GRAY (R1DO)
HO NIEH (NRR)
SCOTT MORRIS (IRD)
| Event Text DEGRADED NEUTRON SHIELDING FOR A SPENT FUEL CASK
"PPL Susquehanna, LLC became aware of a reduction in the effectiveness of a spent fuel confinement system at 0430 [EDT] on Saturday August 10, 2013. One of the safety barriers in a spent fuel cask is the water filled volume of the cask which provides neutron shielding. This volume is normally filled with approximately 670 gal of demineralized water. It has been determined that the neutron shielding volume was not completely filled. The cask neutron shield volume is currently being filled. The loaded spent fuel canister is currently located in the reactor building on the refuel floor and has been located there for the duration of the event. Investigation is currently in progress concerning personnel radiation exposure. The lack of neutron shielding represents a significant reduction in the effectiveness of a spent fuel storage cask confinement system which is an 8 hour reportable condition under 10CFR72.75(c)(2). This also represents a dry fuel storage safety system that was disabled or failed to function which is a 24 hour reportable condition under 10CFR72.75(d)(1)."
The cask was a TransNuclear NUHOMS-61BTH. Personnel on the refuel floor were equipped with neutron dosimetry.
The licensee notified the NRC Resident Inspector and will notify the Commonwealth of Pennsylvania. | |