| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/12/2017 - 09/13/2017 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 52963 | Rep Org: HEMLOCK SEMICONDUCTOR OPERATIONS
Licensee: HEMLOCK SEMICONDUCTOR OPERATIONS
Region: 3
City: HEMLOCK State: MI
County:
License #: 21-32682-01
Agreement: N
Docket:
NRC Notified By: KELLEY DEERING
HQ OPS Officer: JEFF HERRERA | Notification Date: 09/12/2017
Notification Time: 09:46 [ET]
Event Date: 09/11/2017
Event Time: 14:30 [EDT]
Last Update Date: 09/12/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
KENNETH RIEMER (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text SHUTTER STUCK IN THE OPEN POSITION
"License No 21-32682-01
"Fixed Gauge Stuck Shutter-Stuck in the open/normal operating position
No exposures
Vega America Source Holder Model SHLG-2-45
Radionuclide: Cesium-137 5000mCi
Source serial number 1485CO
Source holder serial number 19509171
"At approximately 1430 hrs (EDT) on 9/11/2017 the site RSO attempted to operate the shutter on source holder 10071949 (Hemlock identifier). The shutter operation failed; the shutter is stuck in the open position. There were no exposures as a result of the failed shutter operation. Operating the shutter was part of a field training program for area operations personnel. The source holder is located on site on the HP DPR Tank.
"[The RSO is] in contact with Vega Americas, the manufacturer, to determine a resolution plan. [The RSO] will follow up with a detailed report within 7 days and a complete investigation/resolution report once the gauge manufacturer has performed repairs on the gauge." |
| Power Reactor | Event Number: 52964 | Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [ ] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: EDWARD BURNS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/12/2017
Notification Time: 14:20 [ET]
Event Date: 09/12/2017
Event Time: 11:31 [CDT]
Last Update Date: 09/12/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
KENNETH RIEMER (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 STANDBY LIQUID CONTROL SYSTEM PIPING FAILURE
"On September 12, 2017 at 1131 CDT, both Unit 3 Standby Liquid Control system (SLC) subsystems were declared inoperable for a through wall leak on the common discharge piping. With both subsystems inoperable, the SLC system was unable to fulfill its safety function.
"This event is reportable under 10 CFR 50.72(b)(3)(v)(A) for an event or condition that could have prevented the fulfillment of a safety function of a system that is needed to shut down the reactor and maintain it in a safe shutdown condition and under 10 CFR 50.72(b)(3)(v)(D) for a system that was unavailable for accident mitigation.
"The NRC Resident Inspector has been notified."
With both trains of SLC inoperable, the licensee entered an 8-hr. action statement to restore at least one train to operability. If unable to do so, then the plant will enter a 12-hr. shutdown action statement. |
| Power Reactor | Event Number: 52966 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: JEFFERY KUETHER-ULBERG
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/12/2017
Notification Time: 19:11 [ET]
Event Date: 09/12/2017
Event Time: 12:28 [PDT]
Last Update Date: 09/12/2017 | 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):
JEREMY GROOM (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 SECONDARY CONTAINMENT PRESSURE MOMENTARILY ABOVE TECHNICAL SPECIFICATION LIMIT
"On September 12, 2017, at 1228 PDT, Reactor Building (Secondary Containment) pressure momentarily rose above the Technical Specification (TS) limit. Secondary Containment was declared inoperable and TS Action Statement 3.6.4.1.A was entered. The pressure rise was due to unexpected isolation of the supply and exhaust valves in the Reactor Building ventilation system due to an electrical transient on the power panel feeding the valve operators' solenoid pilot valves during maintenance. The cause of the electrical transient is under investigation.
"The Reactor Building differential pressure controller restored the building pressure to within limits. The Control Room operators reopened the Reactor Building ventilation supply and exhaust valves. Secondary Containment was declared operable at 1228 PDT and TS Action Statement 3.6.4.1.A was exited.
"This condition is being reported under 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D) for an event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material and accident mitigation."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 52967 | Facility: COOK
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RONNIE SIMMONS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 09/13/2017
Notification Time: 01:08 [ET]
Event Date: 09/13/2017
Event Time: 00:47 [EDT]
Last Update Date: 09/13/2017 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
KENNETH RIEMER (R3DO)
BERNARD STAPLETON (IRD)
CYNTHIA PEDERSON (R3RA)
BRIAN HOLIAN (NRR)
CHRIS MILLER (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text UNUSUAL EVENT DUE TO LETDOWN RELIEF VALVE DISCHARGE TO THE PRESSURIZER RELIEF TANK
At 0047 EDT, the licensee declared a notification of unusual event under emergency action level S8 due to actuation of the letdown relief valve which resulted in reactor coolant system leakage to the pressurizer relief tank exceeding 10 gpm.
The plant was in mode 3 at the time making preparations to proceed to cold shutdown to support their refueling outage. Operators were in the process of reducing reactor coolant system letdown from 120 gpm to 45 gpm when the letdown system relief valve lifted. The relief discharged to the pressurizer relief tank at approximately 12 gpm. Operators isolated the letdown line which reduced the leakage to approximately 1 gpm.
Plant staff is in the process of determining where the 1 gpm leakage is from and evaluating the basis for terminating the unusual event.
Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA National Watch Center (email) and Nuclear SSA (email). | |