| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/06/2017 - 06/07/2017 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 52774 | Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: MS POWER COMPANY
Region: 4
City: DE KALB State: MS
County:
License #: MS-1062-01
Agreement: Y
Docket:
NRC Notified By: JAYSON MOAK
HQ OPS Officer: JEFF HERRERA | Notification Date: 05/30/2017
Notification Time: 10:19 [ET]
Event Date: 05/28/2017
Event Time: [CDT]
Last Update Date: 05/30/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL OKEEFE (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - STUCK SHUTTER ON A FIXED GAUGE
The following report was received from the Mississippi Department of Health via email:
"Licensee's RSO [Radiation Safety Officer] reported a stuck shutter on a Ronan Model SA8-C10 fixed gauge, Serial No. 1093CP, Source Model CDC.700. This was noticed during preventive maintenance, while performing shutter checks. Licensee notified the manufacturer for service.
"Isotope: Cs-137
Activity: 200 mCi" |
| Agreement State | Event Number: 52776 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: E.I. DUPONT DE NEMOURS AND COMPANY
Region: 1
City: RICHMOND State: VA
County:
License #: 041-313-1
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: JEFF ROTTON | Notification Date: 05/30/2017
Notification Time: 16:23 [ET]
Event Date: 05/30/2017
Event Time: [EDT]
Last Update Date: 05/30/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE - FIXED GAUGE SHUTTER STUCK OPEN
The following information was provided by the Commonwealth of Virginia via email:
"On May 30, 2017, the licensee reported that the shutter of a fixed gauge failed to close during a routine test of the shutter mechanism. The gauge is a Ronan Model SA1, serial number 1093CK, with a 200 millicurie cesium-137 source (effective May 1995). It is used to measure the level of material inside a process vessel. The gauge is located approximately 10 feet from ground level. It is accessible only by a platform which has been restricted by the licensee. The licensee has contacted the manufacturer to repair or replace the gauge."
VA Event Report ID No.: VA-17-007 |
| Power Reactor | Event Number: 52790 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID ALLEN
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/06/2017
Notification Time: 08:30 [ET]
Event Date: 04/28/2017
Event Time: 05:00 [EDT]
Last Update Date: 06/06/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
SCOTT SHAEFFER (R2DO)
|
| 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 60-DAY OPTIONAL TELEPHONIC NOTIFICATION FOR AN INVALID AUXILIARY FEEDWATER ACTUATION
"This 60-day telephone notification is being submitted in accordance with paragraphs 10 CFR 50.73(a)(1) and 50.73(a)(2)(iv)(A) to report an invalid Auxiliary Feedwater (AFW) actuation at Watts Bar Nuclear Plant (WBN) Unit 1.
"On April 28, 2017 at approximately 0500 Eastern Daylight Time (EDT), Unit 1 maintenance personnel were performing 1-IMI-3.005, '18 Month Calibration of Anticipated Transient Without Scram System Actuation Circuitry (AMSAC),' when an AMSAC actuation signal was received. Both Motor Driven Auxiliary Feedwater Pumps (MDAFWPs) were already in service when this actuation occurred. The Turbine Driven Auxiliary Feedwater Pump (TDAFWP) did not start as it had been removed from service. Additionally, steam generator blowdown isolated as required. During this event, AMSAC actuation was complete and equipment functioned as expected by its operating state.
"Upon identification of the AMSAC actuation, maintenance activities were halted and a prompt investigation was initiated. WBN found that the procedure in use for the 18 month calibration had been recently revised. The procedure called for maintenance to connect an analog multi-meter set on resistance to incorrect points during performance of the procedure. When the analog multi-meter was connected to the incorrect points, a relay was energized resulting in an AMSAC actuation. The procedure was revised and the test completed.
"The licensee notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 52791 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: THOMAS WALL
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/06/2017
Notification Time: 15:48 [ET]
Event Date: 06/06/2017
Event Time: 17:51 [EDT]
Last Update Date: 06/06/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
LADONNA SUGGS (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text BOTH STANDBY STEAM GENERATOR FEED PUMPS OUT OF SERVICE FOR PRE-PLANNED MAINTENANCE
"This notification is in accordance with Turkey Point Technical Specification (TS) 3.7.1.6, Action b.1 to report the inoperability of both Standby Steam Generator Feedwater Pumps (SSGFPs) for greater than 24 hours.
"On 6/6/17 at 1751 hours [EDT] both SSGFPs will be inoperable for greater than 24 hours in support of planned valve repairs that require isolation of the common suction and discharge piping. TS 3.7.1.6, Action b.1 requires a report within four hours if both SSGFPs have been inoperable for 24 hours providing the cause of the inoperability and restoration plans. The valve repairs are currently planned for completion on or about 2300 hours on 6/9/17 which will restore the 'A' pump to service and allow TS 3.7.1.6, Action b.1 to be exited. The diesel-driven 'B' pump will remain out of service for radiator repair which is currently planned for completion on or about 0800 hours on 6/14/17.
"The function of the Standby Steam Generator Feedwater System is as a backup to the Auxiliary Feedwater System and is not credited in the safety analysis."
"The NRC Resident Inspector has been notified."
Both pumps were taken out of service at 1751 EDT on 6/5/17. | |