Event Notification Report for August 20, 2020
U.S. Nuclear Regulatory Commission Event Reports For ** EVENT NUMBERS ** |
54816 | 54830 | 54831 | 54833 | 54844 |
!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!! | |
Power Reactor | Event Number: 54816 |
Facility: Millstone Region: 1 State: CT Unit: [] [2] [] RX Type: [1] GE-3,[2] CE,[3] W-4-LP NRC Notified By: Michael Watson HQ OPS Officer: Andrew Waugh |
Notification Date: 08/04/2020 Notification Time: 22:43 [ET] Event Date: 08/04/2020 Event Time: 17:45 [EDT] Last Update Date: 08/19/2020 |
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): FRANK ARNER (R1DO) |
Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
2 | N | Y | 100 | Power Operation | 75 | Power Operation |
Event Text
EN Revision Imported Date : 8/20/2020 EN Revision Text: BOTH SERVICE WATER HEADERS DECLARED INOPERABLE On 8/4/20, at 1745 EDT, Millstone Unit 2 entered technical specification (TS) 3.0.3 due to both service water headers being declared inoperable because strainer differential pressures (D/Ps) were greater than 9 psid. The high service water strainer D/P was the result of heavy debris impingement caused by tropical storm Isaias. To reduce heat loads and service water flow, Unit 2 reduced power to 75 percent. One service water header was restored to operable at 1816 EDT, at which time TS 3.0.3 was exited. At 1843 EDT both service water headers were declared operable. The NRC Resident Inspector has been notified. * * * RETRACTION ON 8/19/2020 AT 1141 EDT FROM ERIC DONCH TO KIRBY SCALES * * * "The purpose of this call is to retract a report made on August 4, 2020, NRC Event Number EN 54816 describes a condition at Millstone Power Station Unit 2 (MPS2) in which both trains of service headers were declared inoperable due to service water strainer differential pressures greater than 9 psid. "The condition was reported to the NRC pursuant to 10 CFR 50.72(b)(3)(v)(A), (B) and (D) via an 8 hour prompt report as an 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 shutdown the reactor and maintain it in a safe shutdown condition, remove residual heat and mitigate the consequences of an accident. "Upon further review, MPS2 determined that there was no loss of safety function. An engineering evaluation supports the conclusion that a strainer differential pressure of 16 psid would not challenge the system flow distribution during worst case conditions. The evaluation also demonstrates that flowrates on both headers were observed to be unaffected during the timeframe of the high strainer differential pressure conditions. Therefore, both service water headers would have provided the required flows to perform their safety function. "Therefore, this condition is not reportable and NRC Event Number EN 54816 is being retracted. "The basis for this conclusion has been provided to the NRC Resident Inspector." Notified R1DO (Greives). |
Agreement State | Event Number: 54830 |
Rep Org: SC DEPT OF HEALTH & ENV CONTROL Licensee: Sullivan & Associates, Inc. Region: 1 City: Sumter State: SC County: License #: 383 Agreement: Y Docket: NRC Notified By: Andrew Roxburgh HQ OPS Officer: Brian Lin |
Notification Date: 08/12/2020 Notification Time: 07:54 [ET] Event Date: 08/10/2020 Event Time: 17:30 [EDT] Last Update Date: 08/12/2020 |
Emergency Class: Non Emergency 10 CFR Section: Agreement State |
Person (Organization): MEL GRAY (R1DO) DAVID PROULX (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) |
Event Text
AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA DRIVE CABLE FAILURE This was received from the South Carolina Department of Health and Environmental Control via email: "On August 11, 2020, at 1500 (EDT), the Department (SC Department of Health and Environmental Control) was notified by the licensee that a drive cable used to crank out a source on a Spec 150 camera failed to function as designed. The radiographer was performing the initial source crank out of the source to check the 2 mR in any one hour boundary when he realized that the drive cable was not functioning properly and quickly retracted the source to the shielded position. The radiographer then contacted the Radiation Safety Officer (RSO) to provide him with the details. The RSO then cancelled the job for the night until the drive cable could be replaced. The RSO stated that there were no overexposures that occurred as a result of this incident. The RSO was informed by the Department's on-call duty officer that a 30-day written report will be required detailing the incident." The event occurred on Shaw Air Force Base. South Carolina Incident No: 54830 |
Agreement State | Event Number: 54831 |
Rep Org: TENNESSEE DIV OF RAD HEALTH Licensee: Energy Solutions Region: 1 City: Oak Ridge State: TN County: License #: R-73016 Agreement: Y Docket: NRC Notified By: Andrew Holcomb HQ OPS Officer: Brian Lin |
Notification Date: 08/12/2020 Notification Time: 10:57 [ET] Event Date: 08/11/2020 Event Time: 11:30 [EDT] Last Update Date: 08/12/2020 |
Emergency Class: Non Emergency 10 CFR Section: Agreement State |
Person (Organization): MEL GRAY (R1DO) GRETCHEN RIVERA-CAPELLA (NMSS DAY) NMSS_EVENTS_NOTIFICATION (EMAIL) |
Event Text
FIRE INVOLVING A CONTAINER POSSESSING LICENSED MATERIAL The following information was received from the state of Tennessee via email: "An incident took place while processing a liner with water filters and Dry Active Waste (DAW) in it during filter shredding operation in the Filter Shredding area of the Radioactive Material Solutions (RMS) Building on site. The container contained mixed fission and activation products with Co-60 as a primary contaminant. A fire was observed in the steel Final Form Container (FFC) liner through the remote observation. The size of the fire was limited to the container itself. The FFC is a steel liner where the material accumulates and is contained in preparation for sealing for disposal. The filter processing room was accessed via a hatch and a crane was used to seal the FFC. The fire suppression system was activated to cool down the FFC liner. The Oak Ridge Fire Department responded to the site. Since the fire was contained to the FFC liner, the Oak Ridge Fire Department did not enter the building. The area radiation and air effluent stack monitors did not alarm. Samples from air samplers are being analyzed for airborne material. Staff that remained in the building will undergo a bioassay to assess for potential uptake. A follow-up report will be submitted within 30 days." TN Incident No.: TN-20-116 |
Agreement State | Event Number: 54833 |
Rep Org: OR DEPT OF HEALTH RAD PROTECTION Licensee: Goodwill Industries Region: 4 City: Eugene State: OR County: License #: N/A Agreement: Y Docket: NRC Notified By: Richard Went HQ OPS Officer: Brian P. Smith |
Notification Date: 08/12/2020 Notification Time: 14:48 [ET] Event Date: 08/10/2020 Event Time: 00:00 [PDT] Last Update Date: 08/12/2020 |
Emergency Class: Non Emergency 10 CFR Section: Agreement State |
Person (Organization): DAVID PROULX (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) ILTAB (EMAIL) |
This material event contains a "Less than Cat 3" level of radioactive material. |
Event Text
AGREEMENT STATE REPORT - ABANDONED TRITIUM SIGN The following information was received via a letter from Goodwill Industries to the Oregon Department of Health Radiation Protection: "Goodwill Industries of Lane and South Coast Counties found an abandoned exit sign (Tritium) in their inventory. The exit sign was sent to SRB Technologies, INC. at 2580 Landmark Drive, Winston-Salem, NC 27103 (NC Radioactive Materials License# 034-0534-2) for proper disposal. One sign was sent. The sign had been manufactured by lsolite Safety Light Corp. Bloomberg, PA/ Model Number 2040. Serial Number 0412499. Date of Manufacture 12-84. Life rating/ Curies of 10 years 9.8ci. The device was never registered or installed at any of our sites as it was abandoned here. "The Oregon Department of Health Radiation Protection will attempt to find the original owner based on the serial number. Since the light has been disposed of properly and reporting is now entered per SA300, Oregon is requesting that this event be marked as complete and request closure of this event." 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: 54844 |
Facility: Turkey Point Region: 2 State: FL Unit: [3] [] [] RX Type: [3] W-3-LP,[4] W-3-LP NRC Notified By: Steve Corrigan HQ OPS Officer: Michael Bloodgood |
Notification Date: 08/19/2020 Notification Time: 15:57 [ET] Event Date: 08/19/2020 Event Time: 13:25 [EDT] Last Update Date: 08/19/2020 |
Emergency Class: Non Emergency 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS Actuation - Critical |
Person (Organization): MARK MILLER (R2DO) |
Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
3 | N | N | 0 | Startup | 0 | Hot Standby |
Event Text
AUTOMATIC REACTOR TRIP DURING STARTUP "On 08/19/20 at 1325 EDT, during Unit 3 startup at approximately 0 percent rated thermal power, the reactor automatically tripped. The trip was automatically initiated from the Source Range Nuclear Power Instrumentation. All other systems operated normally. Operations stabilized the plant in Mode 3. Decay heat is being removed by Steam Dumps. Unit 4 is not affected. "This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B). "The NRC Resident Inspector has been notified." The cause of the Source Range Nuclear Power Instrumentation trip is under investigation. |
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021