| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
5/4/2018 - 5/7/2018 ** EVENT NUMBERS ** |
| Agreement State | Event Number: 53339 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: GE HEALTHCARE
Region: 3
City: ARLINGTON HEIGHTS State: IL
County:
License #: IL-01109-01
Agreement: Y
Docket:
NRC Notified By: GRAY FORSEE
HQ OPS Officer: STEVEN VITTO | Notification Date: 04/16/2018
Notification Time: 16:36 [ET]
Event Date: 04/16/2018
Event Time: 14:15 [CDT]
Last Update Date: 05/07/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANN MARIE STONE (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ADAM TUCKER (ILTAB) | | This material event contains a 'Less than Cat 3' level of radioactive material. | Event Text AGREEMENT STATE REPORT - TECHNETIUM-99m GENERATOR LOST IN TRANSIT
The following was received from the State of Illinois via E-mail:
"The Agency [Illinois Emergency Management Agency] received a call on 4/16/18 from GE Healthcare (IL-01109-01, Arlington Heights) stating that a Mo/Tc generator in transit to their facility was unaccounted for. The generator was one of eight being returned from pharmacies in Michigan and was shipped as a Yellow-II package through [common carrier]. The Mo-99 activity was estimated to be 10.35 GBq on 4/11/18. GE Healthcare stated the empty packaging for the generator was returned in the shipment with the bottom of the box having been re-taped. [The common carrier] is working to search their hubs (Grand Rapids, Chicago Heights, and Wheeling). The shipping pharmacies have been interviewed and provided signed manifests.
"Details will be provided as they become available. There is currently no reason to believe a deliberate intent to misplace the device [occurred]."
GE Healthcare (Emile Poisson) also notified the NRC Operations Center regarding this event. The package was initially shipped from the Kentwood Michigan GE Healthcare location. The outer package was delivered to the correct location at 1415 CDT.
GE Healthcare Michigan Licensee Number: 21-26707-01MD.
Illinois Item Number: IL180027.
* * * UPDATE FROM EMILE POISSON TO HOWIE CROUCH AT 1752 EDT ON 4/17/18 * * *
GE Healthcare notified the NRC Operations Center that the missing generator had been located. When the shipping box broke, the generator fell into a box of office chairs that was shipping to St. Mary's Hospital in South Dakota. Personnel at the hospital recognized the generator as radioactive material and turned it over to the hospital's radiology department. The radiology department notified GE Healthcare. GE Healthcare is making arrangements to have the generator shipped to its Illinois facility. There were no reported overexposures.
* * * The following additional information was received from the State of Illinois (Foresee) via email:
"On 4/17/18, at approximately 1630 CDT, [GE Healthcare] notified IEMA that the package had been located at St. Mary's Hospital in Pierre, SD. Reportedly, hospital staff opened boxes of steel chairs and the generator had been packaged inside. It is unknown if the chairs/associated packaging has been assessed for removable contamination. GE Healthcare is unsure if the hospital is authorized for possession of the generator. GE Healthcare and IEMA are notifying NRC Region IV staff concurrently. The generator arrived in shrink wrapped boxes, delivered by a secondary carrier. GE Healthcare and [the original common carrier] are retracing the shipment to determine at what point the packages were comingled. Terminals at Kentwood, Ml, Chicago Heights, IL and St. Paul, MN are in question. There is currently no reason to believe a deliberate intent to misplace the device [occurred]. GE Healthcare is working to take possession of the generator at this time. Additional details will be provided as they become available."
Notified R3DO (Riemer), R4DO (O'Keefe), ILTAB (E-mail) and NMSS Events Notification (E-mail).
* * * UPDATE FROM DAN KANE TO STEVEN VITTO AT 1317 EDT ON 4/18/18 * * *
Associates In Medical Physics, LLC notified the NRC on behalf of Avera St. Mary's Hospital, South Dakota, regarding the receipt of the generator. Upon receiving the package the hospital surveyed the device and determined no surface contamination was present. The device was shielded and locked within the hospital's hot lab. Arrangements are being made with GE Healthcare to retrieve the generator.
Notified R3DO (Riemer), R4DO (O'Keefe), ILTAB (E-mail) and NMSS Events Notification (E-mail).
* * * UPDATE FROM EMILE POISSON TO DONG PARK AT 1344 CDT ON 5/7/18 * * *
GE Healthcare has taken possession of the generator.
Notified R3DO (Kozak), R4DO (Haire), ILTAB (E-mail) and NMSS Events Notification (E-mail).
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 |
| !!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 53356 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JUSTIN GALLAGHER
HQ OPS Officer: DAVID AIRD | Notification Date: 04/22/2018
Notification Time: 04:28 [ET]
Event Date: 04/22/2018
Event Time: 02:22 [EDT]
Last Update Date: 05/04/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
ALAN BLAMEY (R2DO) | | 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 BOTH TRAINS OF RESIDUAL HEAT REMOVAL INOPERABLE
"On April 22, 2018 at 0222 EDT, Watts Bar Nuclear Plant (WBN) Unit 2 entered TS [Technical Specifications] LCO [Limiting Condition for Operation] 3.0.3 due to both trains of the Residual Heat Removal System (RHRS) becoming inoperable. During surveillance testing, the gas void values on Emergency Core Cooling System (ECCS) piping common to both trains did not meet acceptance criteria. This caused both RHRS trains to become inoperable. Operations subsequently vented the RHRS to meet the acceptance criteria and exited TS LCO 3.0.3 at 0227 EDT. More frequent surveillances will be conducted to monitor gas void volumes while additional analysis is being performed to determine corrective actions."
The NRC Resident Inspector has been notified.
* * * RETRACTION FROM TONY PATE TO HOWIE CROUCH ON 5/4/18 AT 1455 EDT * * *
"This event is being retracted. The initial report was based on a conservative acceptance criteria for gas accumulation adopted on April 19, 2018 when it was determined that the previously used acceptance criteria for gas accumulation in the ECCS was non-conservative. Additional analysis has subsequently been performed and determined that a higher gas accumulation acceptance criteria does not challenge operability. With a void of less than the acceptance criteria, in the event of ECCS actuation, the system piping support loads will remain within structural limits and the piping system will remain operable. Therefore, both trains of Unit 2 RHRS were operable and the previously reported 10 CFR 50.72(b)(3)(v)(B) event is being retracted.
"The NRC Resident Inspector staff has been informed of this event retraction."
Notified R2DO (Desai) of this retraction. |
| Agreement State | Event Number: 53363 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: ALBEMARLE CORPORATION
Region: 4
City: MAGNOLIA State: AR
County:
License #: ARK-0717-03120
Agreement: Y
Docket:
NRC Notified By: DAVID STEPHENS
HQ OPS Officer: STEVEN VITTO | Notification Date: 04/26/2018
Notification Time: 10:31 [ET]
Event Date: 04/24/2018
Event Time: 14:00 [CDT]
Last Update Date: 04/26/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text AGREEMENT STATE REPORT - STUCK SHUTTERS
The following was received from the State of Arkansas via email:
"At approximately 1400 [CDT] on 4/24/2018 the Arkansas Department of Heath Radioactive Materials Program received a phone call from the licensee stating that during routine shutter tests two fixed gauge shutters were not functioning properly; one had a stuck shutter and the other was stiff and might become stuck. The gauges are Thermo MeasureTech Model 7063S, source serial numbers S97D2112 (stuck shutter) and S97D2109 (stiff shutter), each originally containing 2 Ci of Cs137.
"Discussion with the licensee indicates that the gauges are mounted on a reactor, outside of normal employee traffic. It is normally open during operations and is only closed during maintenance of the reactor, which is not planned. Cautionary signage is already present. The licensee representative stated that the staff will be made aware of the situation. Licensee maintenance is assessing the situation and will advise the ADH Radioactive Materials program of the plan for handling this situation.
"The State of Arkansas is awaiting a written report from the licensee and final disposition information for the gauge. The State's event number is AR-2018-004." |
| Agreement State | Event Number: 53364 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: BLUE CUBE OPERATIONS LLC
Region: 4
City: FREEPORT State: TX
County:
License #: L 06926
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BETHANY CECERE | Notification Date: 04/26/2018
Notification Time: 17:36 [ET]
Event Date: 04/26/2018
Event Time: 00:00 [CDT]
Last Update Date: 04/26/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text AGREEMENT STATE REPORT - STUCK SHUTTER
The following was received from the state of Texas via email:
"On April 26, 2018, the Agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer (RSO) that while performing routine testing of an Ohmart Vega model SH-F1 gauge containing a 5 milliCurie cesium - 137 source, the shutter would not fully close. The RSO stated open is the normal operating condition for the gauge and it does not create an exposure risk to any individual. The gauge is used for level indication. The RSO stated they have contacted a service company and they will be on site on April 27, 2018, to inspect the gauge. Additional information will be provided as it is received in accordance with - SA-300."
TX Incident #: 9564 |
| Non-Agreement State | Event Number: 53367 | Rep Org: DESERT NDT LLC DBA SHAWCOR
Licensee: DESERT NDT LLC DBA SHAWCOR
Region: 4
City: ABILENE State: TX
County:
License #: 42-35224-01
Agreement: Y
Docket:
NRC Notified By: LANE WATTS
HQ OPS Officer: BETHANY CECERE | Notification Date: 04/27/2018
Notification Time: 12:48 [ET]
Event Date: 04/26/2018
Event Time: 12:30 [CDT]
Last Update Date: 04/27/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
DAVE WERKHEISER (R1DO)
MICHAEL VASQUEZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text UNABLE TO RETRACT SOURCE DUE TO GUIDE TUBE DAMAGE
The following report was excerpted using information provided via email:
"On Thursday, April 26, 2018, a crew was performing radiographic operations. At approximately 12:30 p.m. (CST), the crew experienced an incident wherein a 2-inch diameter, 8-foot long pipe rolled off a 2-1/2-foot tall table, resulting in the guide tube being used by the crew to be smashed [under the] pipe. The dent in the guide tube prevented the source from being returned to the fully shielded position.
"Exact Location of Event: Pennsboro, WV
"Licensed Material Involved:
SPEC-150 Exposure Device (s/n 2056)
SPEC G-60 Source (s/n ZA0905)
lr-192
45 curies
"Corrective Action Taken/Planned:
To immediately correct the problem and retrieve the source, allowing it to be returned to the fully shielded position, the black sheathing on the outside of the guide tube was removed in the damaged area. Using a hammer, the damaged area was rounded out enough to allow the source to be returned to the fully shielded position.
"The guide tube involved in this incident has been removed from service and will be destroyed as to prevent it from being reused.
"Retraining on these types of situations will be provided to all employees, and this incident specifically, will be discussed during this quarter's safety meetings within all company locations.
"To prevent a reoccurrence of an incident of this type, we have made plans with the company for whom we were providing radiography for to stage and brace piping moving forward.
"Extent of Exposure:
The personnel responsible for performing source retrieval recorded a total dose of 60 mR during the retrieval.
"As soon as this event occurred, the crew performing radiographic operations immediately reassessed and set up appropriate 2 mR/hr boundaries, notified their Site RSO [Radiation Safety Officer] and Branch Manager, and maintained constant visual surveillance until source retrieval personnel arrived at the jobsite. At no time were any unmonitored employees in any immediate danger of being overexposed, nor were any of our company personnel, all of whom were utilizing proper radiation detection equipment." |
| Agreement State | Event Number: 53368 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: ALPHA TEST INCORPORATED
Region: 4
City: DALLAS State: TX
County:
License #: L 03411
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BETHANY CECERE | Notification Date: 04/28/2018
Notification Time: 15:18 [ET]
Event Date: 04/28/2018
Event Time: 00:00 [CDT]
Last Update Date: 04/28/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
ILTAB (EMAIL)
NMSS_EVENTS_NOTIFICATION (EMAIL)
CNSNS (MEXICO) (EMAIL) | | 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 obtained from the state of Texas via email:
"On April 28, 2018, the Agency was notified by the licensee's radiation safety officer (RSO) that a Troxler model 3430 moisture/density gauge had been stolen from a company truck [in Houston, TX]. The gauge contains a 40 milliCurie cesium - 137 source and an 8 milliCurie americium source. The gauge was not in the transport case. The RSO did not know if the source rod was locked in the shielded position. The technician who had checked the gauge out had taken the gauge to his apartment (against company policy) and had placed it in the front seat of the truck to recharge it. When the technician came down the next morning to leave, they found a front window of the truck broken and the gauge gone. Local law enforcement has been notified of the theft. Additional information will be provided as it is received in accordance with SA-300."
TX Incident #: 9565
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 |
| Power Reactor | Event Number: 53381 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: BILL RAYBURN
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/04/2018
Notification Time: 12:50 [ET]
Event Date: 03/08/2018
Event Time: 13:23 [EST]
Last Update Date: 05/04/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
| Person (Organization):
BILLY DICKSON (R3DO)
BO PHAM (IRD) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text 60-DAY OPTIONAL TELEPHONIC NOTIFICATION FOR AN INVALID EDG START DURING OUTAGE TESTING
"On March 8, 2018, an invalid system actuation occurred while preparations were underway to perform Safety Features Actuation System (SFAS) integrated response time surveillance testing during the recent Davis Besse Nuclear Power Station refueling outage. Several minutes after connecting a data recorder to monitor the Emergency Diesel Generator (EDG) 1 start signal, at 1323 hours [EST], the EDG started with no valid actuation signals or test inputs present. The EDG successfully came up to speed and voltage as expected. The associated essential 4160 volt electrical bus remained energized from the normal power supply, therefore, the EDG output breaker did not close to supply power to the bus. Troubleshooting determined the inadvertent actuation was due to a short in the test lead wires at the recorder connection caused by a faulty test lead. The test lead was replaced and the SFAS surveillance testing completed satisfactorily.
"This event is being reported as an invalid system actuation per 10 CFR 50.73(a)(2)(iv)(A); this 60-day optional telephone notification is being made per 10 CFR 50.73(a)(i) in lieu of submitting a written Licensee Event Report.
"The NRC Resident Inspector was notified of the inadvertent EDG start at the time of the event and has been notified of this invalid specified system actuation notification." |
| Power Reactor | Event Number: 53382 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MIKE BRANSCUM
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/04/2018
Notification Time: 13:50 [ET]
Event Date: 05/04/2018
Event Time: 11:29 [CDT]
Last Update Date: 05/04/2018 | 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):
RAY AZUA (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, River Bend Station identified non-conforming conditions in the plant design such that specific TS equipment is considered to not be adequately protected from tornado missiles. The reportable condition is postulated by tornado missiles entering the Diesel Generator Building through conduit and pipe penetrations. A tornado could generate multiple missiles capable of striking Division 1, Division 2, and Division 3 Diesel Generator support equipment rendering all Safety Related Diesel Generators 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.
"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: 53385 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: CHRISTOPHER ROBINSON
HQ OPS Officer: DONG HWA PARK | Notification Date: 05/04/2018
Notification Time: 16:20 [ET]
Event Date: 05/04/2018
Event Time: 14:12 [EDT]
Last Update Date: 05/04/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
BILLY DICKSON (R3DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text OFFSITE NOTIFICATION
"At 1412 EDT, a portable chemical toilet was found tipped over. Approximately 1 gallon of contents spilled to gravel only. A notification to the Michigan Department of Environmental Quality and local health department is required, as well as a press release.
"This event is being reported pursuant to 10CFR50.72(b)(2)(xi)."
The licensee will notify the NRC Resident Inspector. |
| Power Reactor | Event Number: 53386 | Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATT MOG
HQ OPS Officer: STEVEN VITTO | Notification Date: 05/07/2018
Notification Time: 05:23 [ET]
Event Date: 05/07/2018
Event Time: 03:25 [EDT]
Last Update Date: 05/07/2018 | 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):
MATT YOUNG (R1DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP
"This 4 and 8 hour notification is being made to report that Salem Unit 2 initiated a manual reactor trip and subsequent automatic Auxiliary Feedwater system actuation. The trip was initiated due to a 21 Reactor Coolant Pump reaching its procedural limit for motor winding temperature of 302F.
"Salem Unit 2 is currently stable in Mode 3. Reactor Coolant system pressure is 2235 PSIG and Reactor Coolant System temperature is 547 F with decay heat removal via the Main Steam Dump and Auxiliary Feedwater Systems. Unit 2 has no active shutdown technical specification action statements in effect. All control rods inserted on the reactor trip. All ECCS [emergency core cooling systems] and ESF [emergency safety function] systems functioned as expected.
"No safety related equipment or major secondary equipment was tagged for maintenance prior to this event. No personnel were injured during this event."
The NRC Resident Inspector was notified. The Lower Alloways Creek Township will be notified. |
| Power Reactor | Event Number: 53387 | Facility: COOK
Region: 3 State: MI
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JIM HABLIK
HQ OPS Officer: JEFF HERRERA | Notification Date: 05/07/2018
Notification Time: 06:42 [ET]
Event Date: 05/07/2018
Event Time: 03:36 [EDT]
Last Update Date: 05/07/2018 | 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):
BILLY DICKSON (R3DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 30 | Power Operation | 0 | Hot Standby | Event Text MANUAL RX TRIP DUE TO HIGH-HIGH LEVEL IN MOISTURE SEPARATOR DRAIN TANK
"On May 7, 2018 at 0336 [EDT], DC Cook Unit 2 Reactor was manually tripped due to a high-high level experienced in the East Moisture Separator Drain Tank (MSDT) of the Moisture Separator Reheater (MSR).
"This notification is being made in accordance with 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The NRC Resident Inspector has been notified.
"Unit 2 is being supplied by offsite power. All control rods fully inserted. All Aux Feedwater Pumps started properly. Decay heat is being removed via the Steam Generator Power Operated Relief Valves following Main Steam Stop Valve closure at 0431 due to a slow RCS [Reactor Coolant System] cooldown. Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip. DC Cook Unit 2 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event." |
| Power Reactor | Event Number: 53388 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: JEREMY MORTON
HQ OPS Officer: DAN LIVERMORE | Notification Date: 05/07/2018
Notification Time: 16:31 [ET]
Event Date: 05/07/2018
Event Time: 13:35 [CDT]
Last Update Date: 05/07/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
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):
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 DISCOVERY OF A CONDITION THAT COULD HAVE PREVENTED FULFILLMENT OF A SAFETY FUNCTION
"On May 7, 2018, during an engineering review of mission time requirements for Technical Specification related equipment, a deficiency was discovered regarding the Emergency Operating Procedure (EOP) guidance for natural circulation cooldown with a stagnant loop. This condition could be the result of a postulated Main Steam Line Break with a loss of offsite power.
"During a natural circulation cooldown with a faulted steam generator, flow in the stagnant reactor coolant system (RCS) loop associated with the isolated faulted steam generator (SG) could stagnate and result in elevated temperatures in that loop. This becomes an issue when RCS depressurization to residual heat removal system (RHR) entry conditions is attempted. The liquid in the stagnant loop will flash to steam and prevent RCS depressurization. In this condition, the time required to complete the cooldown would be sufficiently long that the nitrogen accumulators associated with Callaway's atmospheric steam dumps and turbine driven auxiliary feedwater pump flow control valves would be exhausted. The atmospheric steam dumps and turbine driven auxiliary feedwater pump would not be capable of performing their specified safety functions of cooling the plant to entry conditions for RHR operation. This issue has been analyzed by Westinghouse in WCAP-16632-P. This WCAP determined that to prevent loop stagnation, the RCS cooldown rate in these conditions should be limited to a rate dependent on the temperature differential present in the active loops.
"The WCAP analysis was used to support a revision to the generic Emergency Response Guideline (ERG) for ES-0.2 "Natural Circulation Cooldown." Figure 1 in ES-0.2 provides a curve of the maximum allowable cooldown rate as a function of active loop temperature differential which is directly proportional to the level of core decay heat. At the time of discovery of this condition, Callaway's EOP structure did not ensure that the ES-0.2 guidance would be implemented for a natural circulation cooldown with a stagnant loop.
"Callaway has issued interim guidance to the on-shift personnel regarding this concern and is in the process of revising the applicable EOPs.
"This condition is reportable 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) Shutdown the reactor and maintain it in a safe shutdown condition, (B) Remove residual heat, or (D) mitigate the consequences of an accident."
The licensee notified the NRC Resident Inspector of this condition. |
| Power Reactor | Event Number: 53389 | Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: ARVEL HALL
HQ OPS Officer: RICHARD SMITH | Notification Date: 05/07/2018
Notification Time: 17:40 [ET]
Event Date: 05/07/2018
Event Time: 10:22 [CDT]
Last Update Date: 05/07/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
MARK HAIRE (R4DO)
FFD GROUP (EMAIL) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FITNESS FOR DUTY - NON-LICENSED SUPERVISOR CONFIRMED POSITIVE FOR ALCOHOL
"A non-licensed supervisor had a confirmed positive result for alcohol during a random fitness for duty test. The employee's access to the plant has been terminated.
"The NRC Resident Inspector has been notified." | |