| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/24/2016 - 08/25/2016 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 52185 | Rep Org: NIST
Licensee: NIST
Region: 1
City: GAITHERSBURG State: MD
County: MONTGOMERY
License #: SNM-362
Agreement: Y
Docket:
NRC Notified By: TOM OBRIEN
HQ OPS Officer: VINCE KLCO | Notification Date: 08/16/2016
Notification Time: 15:50 [ET]
Event Date: 08/15/2016
Event Time: 16:15 [EDT]
Last Update Date: 08/16/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
DON JACKSON (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text IRRADIATOR SAFETY EQUIPMENT FAILURE
The NIST (National Institute of Standards and Technology) irradiator has several Cs-137 sources used to calibrate instruments. During a calibration process, a 3.6 Ci source did not return to its shielded position. The event occurred in a portion of the building where such events are expected, therefore there were no health or safety consequences to employees, public or the environment. Licensee corrective actions include manually installing a lead plug into the beam port (opening) of the irradiator. The licensee is contacting the manufacturer in order to assist with troubleshooting and repairs. The irradiator (Model 81-12; JL Shepherd; S/N 7132) is currently in a safe and stable configuration. It is noted that the irradiator is NOT a Part 36 irradiator. |
| Agreement State | Event Number: 52186 | Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: BL ENGLAND GENERATING STATION
Region: 1
City: MARMORA State: NJ
County:
License #: 444566
Agreement: Y
Docket:
NRC Notified By: JOE POWER
HQ OPS Officer: VINCE KLCO | Notification Date: 08/16/2016
Notification Time: 15:49 [ET]
Event Date: 08/15/2016
Event Time: 21:00 [EDT]
Last Update Date: 08/16/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DON JACKSON (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - DAMAGED FIXED GAUGE
The following information was received from the State of New Jersey by email:
"Event Narrative: During a walkthrough of the facility, the night shift RSO [Radiation Safety Officer] discovered that an ABB Industrial Systems, Ltd model LS100 fixed measuring gauge had fallen off of a coal feeder to which it was attached. The area, which is not normally accessed by staff, was cordoned. Readings were taken directly on top of the device, and measured 0.5 to 1.0 mR/h. The device does not have a shutter mechanism. The direct beam was surrounded with lead that was available for shielding.
"Root cause(s) and contributing factors: Vibration from coal feeder caused the metal mounting bracket to shear. Semiannual preventative maintenance did not identify the issue. Scaffolding is required to reach the gauge for maintenance, which makes it difficult to do more regularly.
"Isotope and activity; manufacturer, model and serial number: Ra-226, 0.5 mCi, ABB Industrial Systems, Ltd model LS100, serial number R868."
New Jersey Incident Number: C612607 |
| Power Reactor | Event Number: 52195 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: STEVEN KIRSHBERGER
HQ OPS Officer: JEFF HERRERA | Notification Date: 08/24/2016
Notification Time: 12:15 [ET]
Event Date: 08/24/2016
Event Time: 08:41 [CDT]
Last Update Date: 08/24/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
RAY KELLAR (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 UNANALYZED CONDITION ASSOCIATED WITH DAMAGING EFFECTS OF TORNADOS
"During performance of an extent of condition evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornados, Arkansas Nuclear One, Unit 1, identified non-conforming conditions in the plant design such that specific TS equipment on Unit 1 is considered to not be adequately protected from tornado missiles. The reportable condition is postulated by tornado missiles entering the Unit 1 Cable Spreading Room through penetrating the hollow metal door or potentially from spalling of the block wall separating Room 96 and 97. A tornado could generate multiple missiles capable of striking the Unit 1 Cable Spreading Room and rendering both safety related electrical trains inoperable.
"This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) for any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety, and per 10 CFR 50.72(b)(3)(v) for any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to (A) Shut down the reactor and maintain it in a safe shutdown condition, (B) Remove residual heat, or (D) Mitigate the consequences of an accident.
"This condition was identified as part of an on-going extent of condition review of potential tornado missile related site impacts. Licensee Event Report (LER) 50-313/2016-002-00 was recently submitted addressing previously identified tornado missile vulnerabilities at the Unit 1 plant.
"Enforcement discretion per Enforcement Guidance Memorandum EGM 15-002 has been implemented and required actions taken. Corrective actions will be documented in a follow-on licensee event report.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 52198 | Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: JOSEPH RHODES
HQ OPS Officer: JEFF HERRERA | Notification Date: 08/24/2016
Notification Time: 16:55 [ET]
Event Date: 08/24/2016
Event Time: 13:38 [EDT]
Last Update Date: 08/24/2016 | 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):
ERIC MICHEL (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text REACTOR TRIP DUE AUTOMATIC TURBINE TRIP FROM 100 PERCENT POWER
"At 1338 [EDT] on 08/24/2016, a turbine trip, and a subsequent reactor trip occurred. The cause is under investigation. Following the reactor trip, the Auxiliary Feedwater System actuated as expected on low steam generator level. At the time of the trip, the plant was in Mode 1. As of 1643 [EDT], the Plant is in Mode 3. The current RCS [Reactor Coolant System] Temperature is 548 degrees F (Average), and the Steam Generator Levels are in the range of 40 to 45% (normal range) with levels controlled by the Main Feedwater System. All systems and equipment operated as expected.
"Due to the automatic actuation of the Reactor Protection System, this event is being reported as a 4 hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B). Due to the valid actuation of Auxiliary Feedwater System, this event is also being reported as an 8 hour Non-Emergency per 10 CFR 50.72(b)(3)(iv)(A)(B)(6). At no time during this occurrence was the public or plant staff at risk as a result of this event.
"The NRC Resident Inspector has been notified." | |