| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/13/2018 - 04/16/2018 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 53287 | Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOSEPH FRATTASIO
HQ OPS Officer: VINCE KLCO | Notification Date: 03/25/2018
Notification Time: 23:43 [ET]
Event Date: 03/25/2018
Event Time: 16:16 [EDT]
Last Update Date: 04/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
RAY MCKINLEY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text CONTROL ROD DRIVE PIPING POTENTIALLY INOPERABLE
"On March 25, 2018 at 1616 hours [EDT], with the reactor in cold shutdown condition, two control rod drive piping lines were determined to be potentially inoperable in the event of a design basis earthquake due to support defects. The control rod drive piping forms a portion of the reactor coolant pressure boundary and primary containment boundary.
"The supports will be repaired prior to plant startup.
"This event had no impact on the health and/or safety of the public.
"The NRC Resident Inspector has been notified."
The licensee will notify the Commonwealth of Massachusetts.
* * * RETRACTION FROM JOE FRATTASIO TO HOWIE CROUCH AT 1500 EDT ON 4/13/18 * * *
"The purpose of the notification is to retract ENS notification 53287 made on 03/25/18 for Pilgrim Nuclear Power Station. The previous notification reported that control rod drive (CRD) piping could be potentially inoperable in the event of a design basis earthquake, at the time of discovery, due to piping support defects. Subsequent evaluation has demonstrated that the piping was not inoperable.
"Specifically, after an engineering evaluation, it has been determined that the CRD Hydraulic System operability was never lost and the system was operable, although non-conforming, based on the support configuration not conforming to the pipe support drawings. The affected pipe supports have been restored or reworked to the proper design condition in accordance with the design drawings. The CRD System has subsequently been restored to a fully operable status."
Notified R1DO (Jackson) and IRD MOC (Pham). |
| Agreement State | Event Number: 53315 | Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: SIEMENS MEDICAL SOULTIONS
Region: 3
City: HOFFMAN ESTATES State: IL
County:
License #: IL-01130-02
Agreement: Y
Docket:
NRC Notified By: GARY FORSEE
HQ OPS Officer: STEVEN VITTO | Notification Date: 04/05/2018
Notification Time: 15:31 [ET]
Event Date: 04/05/2018
Event Time: 09:04 [CDT]
Last Update Date: 04/10/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
STEVE ORTH (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
GREGORY AHERN (ILTA)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - ABANDONED SOURCE
The following was received from the State of Illinois via email:
"At approximately 0904 [CDT] on 4/5/18, the Agency [Illinois Emergency Management Agency (IEMA)] received a call reporting a radioactive source abandoned near a dumpster in residential Carpentersville, IL. Carpentersville Fire and Hazmat was managing the scene. A patrol with the Carpentersville police department reported finding the source at approximately 0806 [CDT] this morning and utilized the manufacturer label and emergency contact information on the package to notify Siemens Medical Solutions. Police had secured the scene until the fire department had arrived. Siemens' RSO [Radiation Safety Officer] had arrived on scene by 0930 [CDT] and contacted the IEMA radioactive materials section. The RSO confirmed the source to be an improperly abandoned Ge-68 phantom source (model CS-20-1, S/N 11054). Review of the Siemens license confirmed they were authorized for possession of the material and qualified to perform an assessment/transport. After discussion with Fire/Hazmat and IEMA, the RSO took possession of the phantom and the scene was cleared. At 1026 [CDT], the Agency received confirmation of the source being safely placed in Siemens' licensed storage area. Additional leak tests confirmed no contamination and Siemens is tracking down the owner of the source. Preliminary checks show the source was originally shipped to California. Additional details will be provided as they become available.
"The radioactive material recovered was a Ge/Ga-68 epoxy-based reference source utilized in the calibration of PET/CT scanners. The Ge-68 source was contained within its storage packaging and exhibited exposure rates of 0.8 mR/h at one foot and 0.090 mR/h at one meter. Although it originally contained 1.39 mCi of Ge/Ga-68 (assay date of March 31, 2016), the source had decayed to approximately 212 microCuries. However, unshielded contact exposure rate could still be as high as 1100 mR/h on contact. The police officer and fire department personnel established a fifty foot perimeter and never got closer than seven feet to the package. There are no exposure concerns resulting from this incident. The package markings were clearly displayed and no effort was apparent to cover or deface."
Illinois Report Number: IL180026
* * * UPDATE ON 04/10/18 AT 1347 EDT FROM GARY FORSEE TO ANDREW WAUGH * * *
The following update was received from the State of Illinois via email regarding two additional missing sources:
"At approximately 0904 [CDT] on 4/5/18, the Agency received a call reporting a radioactive source abandoned near a dumpster in residential Carpentersville, IL. A patrol with the Carpentersville police department reported finding the source at approximately 0806 [CDT] that morning and utilized the manufacturer label and emergency contact information on the package to notify Siemens Medical Solutions. Police had secured the scene until the fire department had arrived. Siemens' RSO had arrived on scene by 0930 [CDT] and contacted the IEMA radioactive materials section. The RSO confirmed the source to be an improperly abandoned Ge-68 phantom source (model CS-20-1, S/N 11054). Review of the Siemens license confirmed they were authorized for possession of the material and qualified to perform an assessment/transport. After discussion with Fire/Hazmat and IEMA, the RSO took possession of the phantom and the scene was cleared. At 1026 [CDT], the Agency received confirmation of the source being safely placed in Siemens' licensed storage area. Additional leak tests confirmed no contamination and the phantom source is pending proper disposal at the manufacturer's Knoxville, TN location. In coordination with Siemens and State of California officials, it was determined the source was originally supplied to Huntington Memorial Hospital in Pasadena, CA. On the evening of 4/5/18, officials with the State of California confirmed Huntington Memorial Hospital's PET/CT unit was serviced and (3) sources shipped for disposal by Zetta Medical (a non-licensed company based out of Lake Zurich, IL). This 11/27/17 servicing by Zetta Medical resulted in the removal and replacement of the following sources: Ge-68 1.14 mCi rod source (S/N 19626), Ge-68 1.14 mCi rod source (S/N 19625), and a Ge-68 1.39 mCi phantom source (S/N 11054). IEMA staff contacted Eckert and Ziegler and confirmed that neither package was received at their company. At this point, IEMA notified first responders and other state and federal partners of the two additional missing sources. IEMA staff dispatched two responders to conduct gamma scintillator surveys of the area where the phantom was found. Extensive searches of the area on the afternoon of 4/6/18, did not result in locating the two missing Ge-68 rod sources.
"IEMA performed an investigation at Zetta Medical on 4/9/18. According to provided FedEx manifests and shipping receipts, Zetta Medical's on site technician, packaged the three sources and transported them to a local FedEx drop off location on 12/7/17. The location of the sources from the time of removal on 11/27/17 until 12/7/17 remains under investigation as well. The shipping manifest was obtained that identifies Zetta Medical as the shipper. The intended recipient was Eckert and Ziegler in California. The shipper/recipient information was inadvertently reversed; resulting in the sources being shipped to Zetta Medical in Lake Zurich. The two packages arrived in Lake Zurich, IL on 12/12/17. On 12/13/17, Zetta Medical attempted to ship the sources back to Eckert and Zeigler in Burbank, CA via Pilot Freight Services. The two packages were consigned as UN2915 for return via air out of O'Hare airport to LAX. The two packages were returned to Zetta Medical on 12/19/17. At this point, the sources were stored in Zetta Medical's warehouse for several months.
"The Zetta Medical employee claims to have packaged and shipped the two packages (containing three Ge-68 sources total) back to Eckert and Zeigler via FedEx on or around 3/12/18. Although electronic shipping records are retained for outgoing shipments, Zetta Medical representatives said this shipment did not have an electronic record. Video surveillance is present in the company. However, the equipment was not recording for the time period of concern. After speaking with FedEx's corporate Radiation Safety Officer and their review of dispatch records over the last four months, FedEx has determined they have no records of a hazmat (radioactive) package being picked up from Zetta Medical. Police found the abandoned phantom source at the dumpster adjacent to the home of the Zetta Medical employee who claims to have shipped the packages.
"It was identified that Zetta Medical has performed unauthorized work with licensed radioactive material. It was also confirmed that representatives of Zetta Medical took possession of at least three Ge-68 sources before losing control of the same. This investigation remains open pending enforcement proceedings and pending paperwork from those entities involved.
"The radioactive material recovered was a Ge/Ga-68 epoxy-based reference source utilized in the calibration of PET/CT scanners. Ge-68 has a 271 day half-life, with gamma exposure from the Ga-68 daughter in equilibrium. The recovered Ge-68 source exhibited exposure rates of 0.8 mR/h at one foot and 0.090 mR/h at one meter. Although it originally contained 1.39 mCi of Ge/Ga-68 (assay date of 3/31/16), the source had decayed to approximately 212 microCi. Leak tests were taken on scene and confirmed to not have removable contamination. The police officer and fire department personnel established a fifty foot perimeter and never got closer than seven feet to the package. There are no exposure concerns resulting from this portion of the incident. The package markings were clearly displayed and no effort was apparent to cover or deface.
"The two remaining, missing Ge-68 rod sources were originally assayed with 1.14 mCi of activity each. They now each contain approximately 0.2 mCi of Ge-68 and are sealed in a 0.25" x 11" steel rod. There should be no airborne hazard due to the internal matrix unless immersed in fire. Data made available from the manufacturer states if the sources are removed from their shielding, the exposure rate would be approximately 1 mR/h at one foot and 100 microR/h at one meter. There are no exposure concerns reported from this incident; however, efforts to recover the remaining two sources are still ongoing."
Notified R3DO (Stone), ILTAB DO (Ahern), and NMSS Events Notification (email).
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: 53316 | Rep Org: NORTH DAKOTA DEPARTMENT OF HEALTH
Licensee: AMERICAN CRYSTAL SUGAR COMPANY
Region: 4
City: HILLSBORO State: ND
County:
License #: ND33-05208-01
Agreement: Y
Docket:
NRC Notified By: DAVID STRADINGER
HQ OPS Officer: STEVEN VITTO | Notification Date: 04/05/2018
Notification Time: 17:40 [ET]
Event Date: 04/05/2018
Event Time: [MDT]
Last Update Date: 04/05/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DRAKE (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - STUCK SOURCE
The following was received from the State of North Dakota via email:
"American Crystal Sugar Company experienced a stuck sealed source (Berthold Technologies U.S.A., LLC Model SSC-100, 60 milliCuries [Co-60] at calibration) in a source tube located inside a vessel during a routine shutter check at their Hillsboro, ND location. The sealed source is fixed to a cable which allows the source to be lowered through a source tube which is located inside a vessel. Upon attempting to retract the source into the shielded gauge housing (Berthold Technologies U.S.A., LLC Model LB 8120-01) to perform the shutter check, the source did not budge. The licensee contacted Berthold Technologies U.S.A., LLC (manufacturer) regarding the stuck source. Berthold personnel instructed the licensee to apply a penetrating oil to the source tube in an attempt to break it loose. As of the notification time, the source remained lodged in the source tube in its normal operating position. The five detectors associated with this source continue to read radiation levels as expected. The licensee will continue to apply the penetrating oil and attempt to pull it back into the shielded gauge housing and provide an update in the morning. More information will be provided as received."
ND Incident Report # ND180001 |
| Non-Agreement State | Event Number: 53320 | Rep Org: MCLAREN GREATER LANSING HOSPITAL
Licensee: MCLAREN GREATER LANSING HOSPITAL
Region: 3
City: LANCING State: MI
County:
License #: 2104073-01
Agreement: N
Docket:
NRC Notified By: KIM GROVE
HQ OPS Officer: STEVEN VITTO | Notification Date: 04/08/2018
Notification Time: 12:20 [ET]
Event Date: 04/08/2018
Event Time: 07:00 [EDT]
Last Update Date: 04/08/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
| Person (Organization):
STEVE ORTH (R3DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text SURFACE CONTAMINATION ON OUTSIDE OF PACKAGE EXCEEDING NRC REPORTING LIMITS
McLaren Greater Lansing Hospital is reporting receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits.
The package was received on 4/8/18 around 0700 EDT. Wipe tests performed on the external surface of the package indicated a removable contamination level of 8,427 dpm/300 cm2. Radiation levels of the package measured 0.02 millirem at the surface.
The package contained Technetium-99m and was shipped by Cardinal Radiopharmacy of Jenison, MI. No damage to the package was observed. The hospital employee receiving the package immediately notified the shipper about the contaminated package. Surveys were performed in the package receipt area to ensure that contamination was not spread beyond the area. No additional contamination was found in the package receipt area. |
| Power Reactor | Event Number: 53329 | Facility: OCONEE
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: JOE FRAVEL
HQ OPS Officer: BETHANY CECERE | Notification Date: 04/13/2018
Notification Time: 06:07 [ET]
Event Date: 04/13/2018
Event Time: 02:27 [EDT]
Last Update Date: 04/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
MARVIN SYKES (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 24 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP FOLLOWING MAIN FEEDWATER CONTROL PROBLEM
"On 4/13/2018 at 0227 [EDT], the Oconee Unit 1 Reactor was manually tripped from 24 percent power due to the inability to control main feedwater flow through the Main Feedwater Control Valves using the Integrated Control System. Due to the RPS actuation while critical, this event is being reported as a 4-hour Non-Emergency per 10 CFR 50.72(b)(2)(iv)(B).
"Following the reactor trip, multiple Main Steam Relief Valves failed to reseat at the expected pressure. Using procedure guidance, Main Steam Pressure was lowered by 115 psig, resulting in the closing of all Main Steam Relief Valves. All other post-trip conditions are normal and all other systems performed as expected. Unit 1 is currently in Mode 3 and stable."
Decay heat is being removed by the steam generators discharging steam to the main condenser using the turbine bypass valves. Units 2 and 3 are not affected by the Unit 1 reactor trip.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 53334 | Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD HARRIS
HQ OPS Officer: DAVID AIRD | Notification Date: 04/13/2018
Notification Time: 20:01 [ET]
Event Date: 04/13/2018
Event Time: 15:55 [EDT]
Last Update Date: 04/13/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
ANN MARIE STONE (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Defueled | 0 | Defueled | Event Text VALID EMERGENCY DIESEL GENERATOR START DURING TESTING
"At 1555 EDT, the Unit 2 'CD' Emergency Diesel Generator (EDG) automatically started and loaded to 4kV Safeguards bus T21C. Testing was in-progress and the start was unplanned. Unit 2 is currently defueled. Unit 1 remains stable at 100 percent power.
"The South Spent Fuel Pit Cooling Train lost power due to a load shed. The South Spent Fuel Pit Cooling Pump was restarted on 2 'CD' EDG at 1614 EDT. The North Spent Fuel Pit Cooling Train remained in-service the entire time. There was no observable change in Spent Fuel Pool temperature.
"This event is reportable under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of an emergency diesel generator, as an eight (8) hour report."
The NRC Resident Inspector has been notified. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 53335 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: BRANDON STARNES
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/13/2018
Notification Time: 21:04 [ET]
Event Date: 04/13/2018
Event Time: 12:08 [CDT]
Last Update Date: 04/15/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
RAY KELLAR (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text TWO CRACKS IDENTIFIED AT THE FEED WATER LINE 'B' CONTAINMENT CONCRETE PENETRATION
"At 1208 CDT on April 13, 2018, GGNS [Grand Gulf Nuclear Station] identified cracks in the primary containment concrete penetration [outer wall] around feed water line 'B'. There are no available dimensions for crack width or depth until further inspections are performed.
"In accordance with NUREG 1022, Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73, Section 3.2.4, any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded, requires that when a principal safety barrier is declared inoperable the condition must be reported under 10 CFR 50.72 (b)(3)(ii)."
The licensee has notified the NRC Resident Inspector.
* * * RETRACTION FROM GERRY ELLIS TO HOWIE CROUCH AT 2012 EDT ON 4/15/18 * * *
"Grand Gulf Nuclear Station (GGNS) personnel performed an inspection of the wall around feed water line 'B'. This inspection included the protective coating in the identified area and a partial inspection of the underlying concrete. The inspection of the protective coating found a collection of non-linear anomalies, chipping, and flaking. The inspection found non-significant linear indications in the concrete.
"Grand Gulf Nuclear Station determined that the collection of non-significant coating imperfections and non-significant indications in the concrete do not constitute serious degradation of primary containment. The indications do not adversely impact the operability, mission time, or safety-function (as described per Technical Specification 3.6.1.1, Primary Containment) of the containment structure. The as-found conditions have been entered into the GGNS corrective action program for final disposition.
"The containment structure is operable, therefore, GGNS is retracting this event notification."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Kellar). |
| Power Reactor | Event Number: 53336 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JEFF MYERS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/14/2018
Notification Time: 14:34 [ET]
Event Date: 04/14/2018
Event Time: 10:40 [EDT]
Last Update Date: 04/15/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ANN MARIE STONE (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION
"At 1040 EDT, Fermi 2 automatically scrammed on RPV [Reactor Pressure Vessel] Level 3 following a loss of the Division 1 Station System Transformer (SST) #64. All control rods fully inserted. HPCI [High Pressure Coolant Injection] and RCIC [Reactor Core Isolation Cooling] automatically started as designed on Reactor Water Level (RWL) 2 and restored RWL. The lowest RWL reached was 101.8 inches [above Top of Active Fuel]. HPCI injected for approximately 35 seconds. RWL is currently being maintained in the normal level band with RCIC. No Safety Relief Valves (SRVs) actuated. All isolations and actuations for RWL 3 and 2 occurred as expected. Investigation into loss of SST #64 continues. At the time of the scram, all Emergency Core Cooling Systems (ECCS) and Emergency Diesel Generators (EDGs) were operable, and no safety related equipment was out of service.
"This report is being made in accordance with 10CFR50.72(b)(2)(iv)(A), any event that results in ECCS discharge into the reactor coolant system as a result of a valid signal and 10CFR50.72(b)(2)(iv)(B), any event that results in the actuation of the Reactor Protection System (RPS) when the reactor is critical. Following the loss of power and reactor scram, the Division 2 EECW [Emergency Equipment Cooling Water] Temperature Control Valve (TCV) controller was in Emergency Manual and maintaining max cooling. Operators placed the controller in Auto and the TCV is controlling normally.
"The NRC Senior Resident has been notified."
Decay heat is being removed via Division 2 steam dumps to the condenser. The plant is in a modified shutdown electric lineup with offsite power available and stable. Emergency diesel generators did automatically start and load.
* * * UPDATE ON 4/14/2018 AT 1838 EDT FROM JEFF MYERS TO HOWIE CROUCH * * *
"This update provides additional clarification of the applicable reporting criteria for this event associated with Primary Containment Isolation Actuations.
"All isolations and actuations for RWL (Groups 4, 13, and 15) and RWL 2 (Groups 2, 10, 11, 12, 14, 16, 17, and 18) occurred as expected.
"This report is also being made in accordance with 10CFR50.72(b)(3)(iv)(A), any event or condition that results in valid actuation of any systems listed in paragraph (b)(3)(iv)(B): RPS, HPCI, and RCIC.
"RPV pressure is being maintained by the bypass valves to the main condenser."
All actuations that occurred were fully completed and restored.
The licensee notified the NRC Resident Inspector.
Notified R3DO (Stone).
* * * UPDATE ON 4/15/2018 AT 1950 EDT FROM KELLEY BELENKY TO DAVID AIRD * * *
"This update provides additional information regarding the specified system actuations and an additional applicable reporting criteria.
"The loss of Division 1 Station System Transformer (SST) #64 at 1040 EDT on 4/14/2018 resulted in the automatic initiation of Emergency Diesel Generators (EDG) 11 and 12. The EDGs started as expected and continue to supply their associated busses. This is reportable pursuant to 10CFR50.72(b)(3)(iv)(A), as an event or condition that resulted in a valid actuation of any system listed in paragraph (b)(3)(iv)(B), including EDGs.
"In addition, the loss of the Division 1 SST #64 resulted in the expected transfer from the normal to alternate power source for the Low Pressure Coolant Injection (LPCI) swing bus, rendering LPCI loop select inoperable. The alternate power source continued to energize the LPCI swing bus throughout the event until the system was realigned to the normal power source at 1239 EDT on 4/14/2018. This condition is reportable pursuant to 10CFR50.72(b)(3)(v)(D)."
The licensee notified the NRC Resident Inspector.
Notified R3DO (Stone). | |