| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/20/2018 - 02/21/2018 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 53206 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: E. I. DUPONT
Region: 4
City: ORANGE State: TX
County:
License #: 01819
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/13/2018
Notification Time: 12:57 [ET]
Event Date: 02/09/2018
Event Time: [CST]
Last Update Date: 02/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG WERNER (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED NUCLEAR GAUGE STUCK SHUTTER
The following report was received via e-mail:
"On February 12, 2018, the licensee notified the Agency [Texas Department of State Health Services] that one of its fixed nuclear gauges had a shutter stuck in the closed position. The gauge is an Ohmart-Vega model SH-F1B containing 40 milliCuries of cesium-137. Arrangements have been made with a service company to make repairs. There is no risk of exposure to employees or members of the public. More information will be provided as it is obtained in accordance with SA-300."
Texas Event: I-9540 |
| Agreement State | Event Number: 53207 | Rep Org: SC DIV OF HEALTH & ENV CONTROL
Licensee: INTERNATIONAL PAPER - GEORGETOWN MILL
Region: 1
City: GEORGETOWN State: SC
County:
License #: 060
Agreement: Y
Docket:
NRC Notified By: ANDREW ROXBURGH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/13/2018
Notification Time: 13:28 [ET]
Event Date: 02/12/2018
Event Time: 13:00 [EST]
Last Update Date: 02/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - FIXED GAUGE BROKEN SHUTTER
The following report was received via e-mail:
"The licensee notified the Department [South Carolina Department of Health and Environmental Control] at 1115 [EST] on February 13, 2018, that it had discovered a broken shutter on one of its gauges during the six-month shutter checks on February 12th. The gauge is a Berthold Model LB7440D containing 100 mCi of Cs-137. Source serial number is N-A04538DZ242A and source holder serial number is 2179. The gauge is still in service and a radiation reading of 2 mR/hr was observed on the surface of the gauge. There is no radiation exposure risk to personnel." |
| Agreement State | Event Number: 53208 | Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: JOHNS HOPKINS MEDICAL INSTITUTION
Region: 1
City: BALTIMORE State: MD
County:
License #: MD-07-005-03
Agreement: Y
Docket:
NRC Notified By: ALAN GOLDEY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/13/2018
Notification Time: 16:00 [ET]
Event Date: 02/08/2018
Event Time: [EST]
Last Update Date: 02/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
GRETCHEN RIVERA-CAPE (NMSS)
PATRICIA MILLIGAN (INES)
| Event Text AGREEMENT STATE REPORT - PERSONNEL OVEREXPOSURE
The following report was received from the Maryland Department of the Environment Radiological Health Program via email:
"On February 8, 2018, the Maryland Department of the Environment - Radiological Health Program was contacted by Johns Hopkins Medical Institution (MD-07-005-03) of an incident in which one researcher had received a total effective dose equivalent exceeding 5 Rem and likely an extremity dose exceeding 50 Rem. The licensee received results of a researcher's 4th quarter 2017 radiation badge readings. The researcher was conducting tracer studies using PET isotopes C-11 and F-18 in animals. The researcher has been monitored since February 2012 and has frequently used F-18 in similar studies with no problems. Use of PET isotopes in the lab has been halted pending an investigation by the licensee. The Maryland Radiological Health Program will schedule a reactive investigation.
"The result of the whole-body radiation badge readings (monitoring period Oct 1 - Dec 31, 2017) was:
Deep Dose: 12,818 milliRem
Lens of the Eye: 28,280 milliRem
Shallow Dose: 46,206 milliRem
Beta Dose: 33,388 milliRem
"The researcher's assigned extremity ring badge was not worn during the 4th quarter of 2017.
"The licensee will submit a written report as required within 30 days." |
| Power Reactor | Event Number: 53220 | Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MICHAEL BARTEL
HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/20/2018
Notification Time: 15:35 [ET]
Event Date: 02/20/2018
Event Time: 09:56 [CST]
Last Update Date: 02/20/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
| Person (Organization):
HIRONORI PETERSON (R3DO)
|
| 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 TRANSPORT OF POTENTIALLY CONTAMINATED PERSON TO A MEDICAL FACILITY
"At 0956 CST on 2/20/2018, an employee working in a non-contaminated section of the Radiological Control Area was transported offsite for a personal medical issue. The required radiological survey was not completed prior to the employee being transported offsite by ambulance. A radiological protection technician accompanied the employee and completed a survey during the transfer to the hospital, confirming no contamination of the employee.
"This event is reportable pursuant to 10 CFR 50.72(b)(3)(xii).
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 53221 | Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] [ ]
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: DANIEL MICKINAC
HQ OPS Officer: DAVID AIRD | Notification Date: 02/20/2018
Notification Time: 15:36 [ET]
Event Date: 02/20/2018
Event Time: 09:25 [EST]
Last Update Date: 02/20/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
OMAR LOPEZ (R2DO)
FFD GROUP (EMAI)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Under Construction | 0 | Under Construction | | 4 | N | N | 0 | Under Construction | 0 | Under Construction | Event Text FITNESS FOR DUTY - CONTRACT SUPERVISOR SUBVERTS FITNESS FOR DUTY TEST
"At 0925 [EST] on February 20, 2018, a non-licensed supervisory contractor subverted a random Fitness for Duty test. The contractor's site access has been terminated.
"The NRC Resident Inspector was notified." |
| Non-Power Reactor | Event Number: 53222 | Facility: UNIV OF FLORIDA
RX Type: 100 KW ARGONAUT
Comments:
Region: 0
City: GAINESVILLE State: FL
County: ALACHUA
License #: R-56
Agreement: Y
Docket: 05000083
NRC Notified By: DAN CRONIN
HQ OPS Officer: DAVID AIRD | Notification Date: 02/20/2018
Notification Time: 16:45 [ET]
Event Date: 02/16/2018
Event Time: 08:55 [EST]
Last Update Date: 02/20/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
| Person (Organization):
DUANE HARDESTY (NRR)
ELIZABETH REED (NRR)
| Event Text TECHNICAL SPECIFICATIONS VIOLATION DUE TO INCORRECTLY CALIBRATED REACTOR TRIP INSTRUMENTATION
"On 2/16/18, the calorimetric portion of Surveillance Requirement (SR) 3.2.3.3 for Limiting Condition for Operations (LCO) 3.2.3.1 was performed in accordance with University of Florida Test Reactor (UFTR) procedures. Reactor power was stabilized at an indicated power of approximately 94 percent with actual thermal power (calculated by heat balance) at approximately 98kW (98 percent RTP) [rated thermal power]. Indicated power was then adjusted to approximately 99 percent to ensure adequate margin to the license limit of 100kW thermal steady-state (100 percent RTP). At no time was actual reactor power allowed to exceed the license limit. The reactor was then shutdown and secured to perform post-calorimetric verifications. SR 3.2.2.1 and 3.2.3.1 were performed satisfactorily just prior to operation to verify the High Reactor Power trip function and setpoint. Reactor Power Channel 1 was set to actuate at 110 percent and Reactor Power Channel 2 was set to actuate at 108 percent.
"At about 1400 on 2/19/18, during review of surveillance parameters and discussion with the operators, UFTR management determined that Limited Safety System Setting 2.2.1 and LCO 3.2.2.1 had been violated. The Technical Specifications allowable value for the automatic High Reactor Power trip function is less than or equal to 110 percent RTP. There was a period of approximately 5 hours of operation prior to adjustment of the power channels, however, during which actual thermal power was greater than indicated power (but less than 100kW thermal). During this period, if a power excursion had occurred, the High Reactor Power trip would have actuated at approximately 114 percent RTP. This condition is reportable in accordance with Sections 6.7.2.a.3 and 6.7.2.a.4 of the UFTR Technical Specifications. As described above, this condition was corrected by adjusting indicated power on both reactor power channels to greater than actual thermal power.
"The NRC Project Manager, assigned inspector, and Non-Power Reactor Licensing Branch Chief (acting) have been notified." |
| Power Reactor | Event Number: 53223 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: BRYAN PARKER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/20/2018
Notification Time: 18:46 [ET]
Event Date: 02/20/2018
Event Time: 12:25 [CST]
Last Update Date: 02/20/2018 | 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):
GREG PICK (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 ALL THREE AUXILIARY FEEDWATER PUMPS INOPERABLE DUE TO HELB DOOR BEING OPEN
"At 1225 CST, all three Auxiliary Feedwater [AFW] pumps were declared inoperable at the Callaway Plant upon discovery that a door (DSK13311) credited for protection of equipment from the effects of a high-energy line break (HELB) hazard had come partially open due to vibration harmonics from the running turbine-driven Auxiliary Feedwater pump (TDAFP). Immediate investigation identified that play in the mechanism that holds the door closed had rendered it susceptible to movement from the vibration harmonics.
"The affected HELB door specifically protects safety-related instruments that provide a swap-over signal upon detection of a low suction pressure condition for the AFW pumps and thereby automatically effect a suction transfer for the AFW pumps from the condensate storage tank (normal/standby source) to the Essential Service Water (ESW) system (credited safety-related source).
"All of the AFW pump suction transfer instrument channels were declared inoperable. Per Technical Specifications (TS) 3.3.2, 'Engineered Safety Feature Actuation System (ESFAS) Instrumentation,' the applicable Condition(s) and Required Action(s) for inoperable AFW pump suction transfer instrumentation only addresses a single channel being inoperable. Thus, the condition of having all three instrument channels inoperable required entry into TS Limiting Condition for Operation (LCO) 3.0.3. At the same time, however, with the automatic suction transfer capability rendered inoperable, all three AFW pumps, i.e., the TDAFP and the 'A' and 'B' motor-driven AFW pumps, were declared inoperable. Although LCO 3.0.3 was applicable, entry into the Required Actions of LCO 3.0.3 was suspended per the Note attached to Required Action E.1 of TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' which states, 'LCO 3.0.3 and all other LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.'
"At 1336 CST, Operations took actions to prevent the TDAFP from running, so the remaining [AFW Pumps] could be returned to Operable status. Operations then declared the affected instrumentation and the 'A' and 'B' motor-driven AFW pumps Operable. This allowed LCO 3.0.3 and Conditions A, B, D, and E under TS 3.7.5 to be exited. With only the TDAFP inoperable, TS 3.7.5 Condition C and its Required Actions remain in effect.
"Due to the degraded HELB door rendering all three AFW pumps inoperable, the unidentified condition is being reported as an unanalyzed condition that significantly degraded plant safety [per 10 CFR 50.72(b)(3)(ii)(B)] as well as a condition that could have prevented the fulfillment of the safety functions of structures or systems that are needed to shut down the reactor and maintain it in a safe shutdown condition, remove residual heat, and mitigate the consequences of an accident [per 10 CFR 50.72(b)(3)(v)(A), (B), and (D), respectively].
"The NRC Senior Resident Inspector has been notified." | |