| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
12/08/2017 - 12/11/2017 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 53078 | Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: SIGNET TESTING LABORATORY
Region: 4
City: HAYWARD State: CA
County:
License #: 2943-01
Agreement: Y
Docket:
NRC Notified By: K. ARUNIKA HEWADIKARAM
HQ OPS Officer: STEVE SANDIN | Notification Date: 11/18/2017
Notification Time: 01:06 [ET]
Event Date: 11/17/2017
Event Time: 00:00 [PST]
Last Update Date: 11/18/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JASON KOZAL (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ILTAB (EMAI)
CNSNS (MEXICO) (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE
The following information was received from the State of California via email:
"On 11/17/17, the RSO [Radiation Safety Officer] contacted RHB [CA Radiologic Health Branch] to report a stolen moisture density gauge. The stolen gauge is a CPN Model MC-1DR, S/N MD90209216, containing 10 mCi of Cs-137 and 50 mCi of Am-241. The user had taken the gauge home and left it secured in the back of his truck. The truck was parked at his residence . . .. According to the user, most likely between midnight and 5 AM of 11/17/17, the chain locking the gauge to the truck bed was removed and the case was dragged behind a building where the locks on the box were broken and the gauge was removed. The box was recovered without the gauge. [The] RSO had notified San Jose Police Department of this incident (Event # P173210429). RHB will be following up on this investigation.
"5010 NUMBER (Date Notified): 111717"
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Agreement State | Event Number: 53097 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: INTERTECK ASSET INTEGRITY MANAGEMENT, INC.
Region: 4
City: LONGVIEW State: TX
County:
License #: 06801
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/30/2017
Notification Time: 08:49 [ET]
Event Date: 11/28/2017
Event Time: [CST]
Last Update Date: 11/30/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL OKEEFE (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
PATRICIA MILLIGAN (INES)
| Event Text AGREEMENT STATE REPORT - RADIOGRAPHY TRAINEE OVEREXPOSURE
The following report was received via e-mail:
"On November 28, 2017, the Agency [Texas Department of State Health Services] was contacted by the licensee's Radiation Safety Officer (RSO) who reported that on November 28, 2017, they were notified by their dosimetry processor that one of their radiographer trainee's exposure badges was reported to read 62 Rem. The RSO stated the trainee was returning to the Longview office from West Texas to be interviewed. The badge reading was for the month of October 2017. The RSO stated the trainee had operated the radiography camera crank out device, but had not changed out any film. It is believed the dose is to the badge only. The RSO stated they had not observed any adverse health effects in the trainee. On November 29, 2017, the Agency contacted the RSO and requested additional information. The RSO stated the trainee stated that they had not dropped their dosimeter and accidently exposed it. The trainee had stated that they had been wearing an alarming rate meter and it had never alarmed. The trainee's daily exposure record did not indicate any abnormal exposures. The radiographer supervising the trainee did not recall any abnormal operations while supervising the trainee. The RSO stated the trainee had not received any type of medical treatments during the exposure period. The RSO stated they were considering sending blood samples to REAC/TS for analysis. The RSO stated the dosimetry processor reported the exposure to the badge was angular. The RSO stated the trainee has been assigned duties that would not give them any additional exposure.
"The licensee will provide the Agency [Texas Department of State Health Services] any information gathered in the interview with the trainee. The RSO cannot state with certainty that the exposure is not real, therefore the Agency is providing this report to the Nuclear Regulatory Commission. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9523 |
| Agreement State | Event Number: 53100 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: EXXONMOBIL OIL CORPORATION
Region: 4
City: BEAUMONT State: TX
County:
License #: 00603
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: DAVID AIRD | Notification Date: 11/30/2017
Notification Time: 18:14 [ET]
Event Date: 11/28/2017
Event Time: [CST]
Last Update Date: 12/01/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
NEIL OKEEFE (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - TWO NUCLEAR GAUGES INVOLVED IN FIRE
The following report was received via E-mail:
"On November 30, 2017, the Agency [Texas Department of State Health Services] was notified by the licensee's consultant that two nuclear gauges were involved in a fire on November 28, 2017. The consultant stated they could not gain access to the gauges until this date. The gauges are Thermo Fisher model 5203 gauges containing a two (2) curie (original activity) cesium-137 source. The consultant stated the dose rate on one of the gauges was reading 180 millirem an hour on a preliminary radiation survey. This dose rate appears to be higher than normal. A contamination survey was performed in the area of the gauges, but the results were not available at the time of the report. The gauges are located 20 - 30 feet above the ground and do not create an exposure risk to any individuals. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-9524
* * * UPDATE AT 0740 EST ON 12/1/2017 FROM ART TUCKER TO MARK ABRAMOVITZ * * *
The following information was received via E-mail:
"The licensee has provided the following additional information:
"The source holders are visibly intact, however they are black with soot. Both of the gauges were surveyed. For B-1228 the readings are normal but B-1227 has a localized spot on the lower left-hand location of the shield where the readings are 180 mR/hr at contact and 14 mR/hr at 1 ft. Additional shielding has been attached to the lower left hand location of the shield to reduce the dose rate to 3 mR/hr at 1 ft. Sealed Source leak tests have been performed and the results will be communicated as soon as they are assayed. No personnel (member of the general public or radiation workers) have been within 5 feet of either source due to the unsafe structural conditions due to the fire. Additional information will be provided as it is received in accordance with SA-300."
Notified the R4DO (O'Keefe) and NMSS Events Notification (via e-mail).
* * * UPDATE FROM ART TUCKER TO DONALD NORWOOD AT 1511 EST ON 12/1/2017 * * *
The following information was received via E-mail:
"The licensee reported that the results of the leak test performed on the two gauges indicated the sources were not leaking (less than 0.0001 microCi). Additional information will be provided as it is received in accordance with SA-300."
Notified the R4DO (O'Keefe) and NMSS Events Notification (via e-mail). |
| Power Reactor | Event Number: 53108 | Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RACHEL HEATH
HQ OPS Officer: VINCE KLCO | Notification Date: 12/08/2017
Notification Time: 17:25 [ET]
Event Date: 12/08/2017
Event Time: 13:10 [EST]
Last Update Date: 12/08/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
CHRISTOPHER CAHILL (R1DO)
|
| 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 HIGH PRESSURE COOLANT INJECTION INOPERABLE DUE TO A LEAKING CHECK VALVE
"U/2 HPCI [Unit 2/High Pressure Coolant Injection] was declared inoperable due to leak by of the pump discharge check valve after pump shutdown from flow testing. This resulted in cycling of the minimum flow valve. The discharge valve was closed to prevent the continued cycling of the minimum flow valve. This condition was identified during normal surveillance testing."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 53110 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DALE SHELTON
HQ OPS Officer: STEVE SANDIN | Notification Date: 12/09/2017
Notification Time: 18:42 [ET]
Event Date: 12/09/2017
Event Time: 13:48 [CST]
Last Update Date: 12/10/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
ANN MARIE STONE (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 98 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO LOSS OF DIVISION 1 AC POWER TO NUMEROUS COMPONENTS
"At approximately 1347 [CST] on 12/09/17, the Main Control Room received annunciators that indicated a trip of the 4160 V 1A1 breaker 1AP07EJ, 480V XFMR 1A and A1 breaker. Numerous Division 1 components lost power (powered from unit subs 1A and A1). The Division 1 containment Instrument Air isolation valves had failed closed by design due to the loss of power. Due to the loss of containment instrument air, several control rods began to drift into the core as expected and, by procedure, the reactor mode switch was placed in the shutdown position at 1353 [CST]. All control rods fully inserted.
"Also due to the loss of power, the Fuel Building ventilation dampers failed closed by design. With the normal ventilation system secured, secondary containment differential pressure rose to slightly greater than 0 inches water gauge which exceeded the Technical Specification requirement of greater than 0.25 inches vacuum water gauge at 1348 [CST]. The Control Room entered EOP-8, Secondary Containment Control. Secondary Containment differential pressure was restored within Technical Specification requirements at 1351 [CST] by starting the Division 2 Standby Gas Treatment system.
"This event is being reported as a manual actuation of the Reactor Protection System (RPS) and as a Condition that Could Have Prevented Fulfillment of a Safety Function.
"The cause is currently under investigation. The NRC Resident has been notified."
The licensee informed the NRC Resident Inspector.
* * * UPDATE FROM DALE SHELTON TO VINCE KLCO AT 1658 EST ON 12/10/2017 * * *
"During a review of plant logs it was identified that the primary to secondary containment differential pressure was identified to be outside of Technical Specification 3.6.1.4 limits of 0 plus or minus 0.25 psid at 2009 on 12/9/17 due to the primary containment ventilation system dampers closing as a result of the loss of power. This parameter is an initial safety analysis assumption to ensure that primary containment pressures remain within the design values during a Loss of Coolant Accident (LOCA). As a result, this condition is reportable as an unanalyzed condition that significantly degrades plant safety.
"The NRC Senior Resident Inspector has been notified."
Notified the R3DO (Stone). |
| Power Reactor | Event Number: 53111 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: JEFF NOLTE
HQ OPS Officer: ANDREW WAUGH | Notification Date: 12/11/2017
Notification Time: 00:35 [ET]
Event Date: 12/10/2017
Event Time: 23:50 [EST]
Last Update Date: 12/11/2017 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
SHAKUR WALKER (R2DO)
BO PHAM (IRD)
CATHERINE HANEY (R2 R)
BRIAN HOLIAN (NRR)
|
| 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 UNUSUAL EVENT DUE TO A SMOKE DETECTOR ALARM RECEIVED INSIDE CONTAINMENT
"St. Lucie Unit 1 declared an Unusual Event due to a smoke detector alarm received in the Unit 1 Containment Building that was unable to be confirmed within 15 minutes. A Containment entry was completed and no evidence of fire was found. The Unusual Event was terminated at 00:26 on 12/11/17.
"State and local officials have been notified by the licensee.
"The NRC Resident Inspector has been notified of this by licensee."
Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), and DHS Nuclear SSA (email). | |