| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
03/18/2016 - 03/21/2016 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51690 | Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: CHEVRON USA PRODUCTS COMPANY
Region: 4
City: PASCAGOULA State: MS
County:
License #: MS-413-01
Agreement: Y
Docket:
NRC Notified By: ROBERT SIMS
HQ OPS Officer: STEVEN VITTO | Notification Date: 01/28/2016
Notification Time: 09:33 [ET]
Event Date: 09/18/2015
Event Time: [CST]
Last Update Date: 03/18/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED GAUGE OPEN/STUCK SHUTTER
The following was received from the State of Mississippi via email:
"During Fall shutter checks and inventory, on 9/18/2015, an Ohmart-Vega fixed gauge, DEA-2102, device model no. SHLM-BR1, (housing serial no. 13530993) (source serial no. 8533CN), was discovered to have an open/stuck shutter, the source disconnected, and was unable to be moved into the closed position. The RSO [Radiation Safety Officer] contacted the manufacturer and arrangements for repair are in motion. DRH [Mississippi Division of Radiological Health] was notified on 1/15/2016 and recommended that RSO take surveys with a survey measurement of the source. On 1/22/2016, [the] RSO provided readings that did not exceed 0.02 mR/hr at the surface of the steel drum that encloses the gauge and the source. The gauge and source is sealed in the steel drum and is only accessible by the manufacturer. The source is not in a designated work area, and is not causing exposure limits beyond the limits for radiation control to the general public and occupational workers."
Isotope: Cs-137
Activity: 40mCi
Mississippi report # MS-16001
* * * UPDATE FROM ROBERT SIMS TO DANIEL MILLS AT 1724 EDT ON 03/18/16 * * *
The following was received from the State of Mississippi via email:
"DRH [Department of Radiological Health] received vendor's field service update on 3/17/2016, from RSO. Report states that shutter failure was due to fatigue and the harsh environment to the roll pin that holds the two rods together. The source holder was repaired and leak test performed. DRH forwarded updated report to NRC on 3/17/2016. All Updated information on the source repair, the cause of the failure and all corrective action was forwarded the HOO on 3/18/2016.
"Violation issued for failure to report event to Mississippi State Department of Radiological Health within 24 hours."
Notified R4DO (Haire) and NMSS Events Notification (email). |
| Agreement State | Event Number: 51786 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: FROEHLING & ROBERTSON
Region: 1
City: KNIGHTSDALE State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: LEE COX
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 03/11/2016
Notification Time: 19:50 [ET]
Event Date: 03/11/2016
Event Time: 15:34 [EST]
Last Update Date: 03/11/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE
The following report was received via e-mail:
"A private company reported a soil density meter was damaged and an increase in background radiation was detected due to possible shielding damage.
"Event terminated. Gauge has been safely transported back to the manufacturer, Instrotek at 1905 [EST]. Radiation surveys at the scene indicated sources were intact and not leaking. Swipes on the source rod, device and equipment confirmed no contamination at the scene. Scene has been released for general public use.
"Radioactive Material Licensee: Froehling & Robertson
Incident Location: 1202 Redwood Valley Lane, Knightdale, NC
Gauge: Instrotek 3500
Radioactive Material: 10 mCi Cesium 137; 40 mCi Americium 241, Beryllium
"Summary:
Radiation Protection Staff arrived on site at 1720 [EST].
Gauge housing was found to be damaged along with a bent source rod.
When staff approached the gauge, at 5 feet, the readings were 5mR/hr (milliRem per hour) indicating that sources were not properly shielded.
When staff surveyed the bottom of the gauge at the shutter, the source rod fell out backwards from the top of the device.
All items were moved to survey the area around where the accident occurred to see if the sources had fallen out in the compacted soil. They had not.
Readings were background for the area of 25 to 30 uR/hr (microRem per hour) indicating the sources were still in the source rod.
Staff put the source rod back in the gauge housing.
Readings at the bottom of the device with the source rod in place, showed readings of 150 to 200 mR/hr. This confirmed the sources were in the rod, but indicated the shutter shielding the sources was not functioning properly.
The reassembled gauge was placed back in the certified DOT shipping container and properly blocked and braced in the licensee's (Froehling & Robertson) truck.
Staff followed the licensee to Instrotek where the device was safely stored until the manufacturer can assess the damage.
US Nuclear Regulatory Commission notified via this email
Radiation Protection Section will continue its compliance investigation of why this event occurred.
Radiation Protection Section will update the National Material Event Database.
Pictures to be uploaded into event reporting.
No further updates will be given." |
| Power Reactor | Event Number: 51806 | Facility: BYRON
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN LEWIN
HQ OPS Officer: STEVEN VITTO | Notification Date: 03/18/2016
Notification Time: 16:37 [ET]
Event Date: 03/18/2016
Event Time: 09:37 [CDT]
Last Update Date: 03/18/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
ROBERT ORLIKOWSKI (R3DO)
FFD GROUP (EMAI)
|
| 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 FITNESS FOR DUTY - CONFIRMED POSITIVE TEST FOR ALCOHOL
"In accordance with 10 CFR 26.719(b)(2)(ii), this notification reports a non-licensed contracted employee supervisor had a confirmed positive for alcohol during a random fitness for duty test. The employee's access to the plant has been suspended.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 51807 | Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: JUSTIN WIEMER
HQ OPS Officer: DANIEL MILLS | Notification Date: 03/18/2016
Notification Time: 18:43 [ET]
Event Date: 03/18/2016
Event Time: 11:28 [CDT]
Last Update Date: 03/18/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
MARK HAIRE (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 SHUTDOWN COOLING PIPE VOID
"During a scheduled surveillance test on 3/18/2016 at 1128 [CDT], Fort Calhoun ultrasonic testing technicians discovered a void on the common shutdown cooling heat exchanger discharge piping. This piping is normally isolated during power operation, and the void does not adversely affect the Containment Spray function, Low Pressure Safety Injection function, or High Pressure Safety Injection function.
"This isolated piping with the void is placed in service only during shutdown cooling operation. The fluid height measured was 10.8 inches, compared to the required height of 11.7 inches for the surveillance test. The void could potentially complicate the initiation of shutdown cooling in the required mode of operation.
"This piping was last tested satisfactory on 12/31/2015. The source of the void is still under investigation.
"Fort Calhoun maintenance was successful in venting the void on 3/18/2016 at 1704 CDT."
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 51808 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [2] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: RODRICK JOHNSON
HQ OPS Officer: STEVEN VITTO | Notification Date: 03/19/2016
Notification Time: 22:51 [ET]
Event Date: 03/19/2016
Event Time: 17:10 [CDT]
Last Update Date: 03/19/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
MARK HAIRE (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNANALYZED CONDITION THAT COULD CHALLENGE RHR EQUIPMENT DURING FLOOD CONDITIONS
"Two (2) potentially degraded flood barriers at penetrations 0073-01-0034 and 0073-01-0063 were identified in the area between the Unit 1 Turbine Building and Auxiliary Building. The deficient barriers are a 'blockout section' of the floor designed to house multiple penetrations that transition from the Turbine Building to the Auxiliary Building. Attempts have been made to investigate the status of the flood barrier with no definitive results. Investigations and additional evaluations are continuing, however, it is currently unknown if the aggregate of these two flood barriers could potentially overwhelm and flood the Auxiliary Building which would challenge equipment necessary to remove residual heat and constitute an unanalyzed condition.
"Based on current conditions (i.e., no forecast flooding conditions), this condition does not present an immediate safety concern.
"This condition has been determined to be reportable per 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(B). This condition is a non-emergency condition. This condition has been entered into the Corrective Action Program.
"Compensatory measures have been prepared to allow placement of a seal over the identified deficient barriers. If required these seals can be installed well in advance of forecast flood conditions. Permanent repairs are currently being designed for installation."
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 51809 | Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: JOHN HARKINS
HQ OPS Officer: VINCE KLCO | Notification Date: 03/20/2016
Notification Time: 23:51 [ET]
Event Date: 03/20/2016
Event Time: 21:54 [EDT]
Last Update Date: 03/21/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
JAMES NOGGLE (R1DO)
SCOTT MORRIS (NRR)
BERNARD STAPLETON (IRD)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 15 | Power Operation | 15 | Power Operation | Event Text TECHNICAL SPECIFICATION (TS) REQUIRED SHUTDOWN DUE TO PRESSURE BOUNDARY LEAKAGE
"During a planned Unit 1 shutdown for a refueling outage, a 0.5 gpm 'pressure boundary leak' was identified on a 1 inch pipe connected to the '1A' RHR-Shutdown Cooling return line by the drywell leak inspection team during a drywell inspection at approximately 15% power. The leak exceeded the TS 3.4.3.2 'Operational Leakage' LCO of no pressure boundary leakage. TS action 'a' was entered which requires to be in at least Hot Shutdown within 12 hours and Cold Shutdown within the next 24 hours. Therefore, the event is reportable within 4 hours per 10CFR50.72(b)(2)(i) due to the initiation of a plant shutdown required by the plant's TS.
"The event is also reportable within 8 hours per 10CFR50.72(b)(3)(ii) due to an event that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
"TS 1.28 defines Pressure Boundary Leakage as leakage through a nonisolable fault in a reactor coolant system component body, pipe wall or vessel wall; therefore, the leak is a 'pressure boundary leak' as defined in TS."
The licensee notified the NRC resident Inspector. | |