Event Notification Report for August 18, 2020
|
U.S. Nuclear Regulatory Commission Event Reports For ** EVENT NUMBERS ** |
| 54806 | 54823 | 54839 |
| !!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!! | |
| Power Reactor | Event Number: 54806 |
| Facility: Callaway Region: 4 State: MO Unit: [1] [] [] RX Type: [1] W-4-LP NRC Notified By: Josh Copeland HQ OPS Officer: Thomas Kendzia |
Notification Date: 07/30/2020 Notification Time: 11:59 [ET] Event Date: 07/30/2020 Event Time: 08:15 [CDT] Last Update Date: 08/17/2020 |
| Emergency Class: Non Emergency 10 CFR Section: 50.72(b)(3)(ii)(B) - Unanalyzed Condition |
Person (Organization): HEATHER GEPFORD (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
EN Revision Imported Date : 8/18/2020 EN Revision Text: EMERGENCY PROCEDURE ERROR POTENTIALLY PREVENTING TIMELY COMPLETION OF EMERGENCY CORE COOLING SYSTEM RECIRCULATION ALIGNMENT "At 0815 CDT on 7/30/2020, it was determined that a procedural error in emergency procedure ES1.3, Transfer to Cold Leg Recirculation, could delay realignment from emergency core cooling system (ECCS) injection phase to recirculation phase under lower plant operational modes. It is noted this scenario is postulated to occur only when the boron dilution mitigation system is operable in lower modes of operation as per Technical Specification 3.3.9 (required operable in Mode 2 [below P-6], 3, 4 and 5). Current plant conditions require this feature nonfunctional so this issue does not impact current plant conditions. This condition is not bounded by existing design and licensing documents; however, it poses no current impact to the health and safety of the public or plant personnel. Therefore, this event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(B). "The NRC Resident Inspector has been notified." * * * RETRACTION ON 8/17/2020 AT 1603 EDT FROM JOSH COPELAND TO KERBY SCALES * * * "Event Notification (EN) 54806, made on 7/30/2020, is being retracted because re-evaluation performed subsequent to the notification has demonstrated that the error in Emergency Operating Procedure ES1.3 would not have resulted in a condition outside of the current licensing basis analyses of record for the Callaway Plant. This re-evaluation addressed core effects, containment pressure-temperature and radiological consequences analyses, documented in the plant's corrective action program. "The re-evaluation has led to the conclusion that the procedural error in ES1.3 would not have prevented any system required to be OPERABLE by the Technical Specifications from performing its specified safety functions. With all systems capable of performing their specified safety functions, the current licensing basis analyses of record for Callaway Plant remain valid and bounding. Based on these considerations, it has been determined that the condition reported in EN 54806 did not result in the plant being in an unanalyzed condition that significantly degraded plant safety. Consequently the condition did not meet the criteria for an 8-hour notification per 10 CFR 50.72(b)(3)(ii)(B) for an unanalyzed condition that significantly degrades safety. "The NRC Resident Inspector has been notified of this Event Notification retraction. " Notified R4DO (Taylor) |
| Agreement State | Event Number: 54823 |
| Rep Org: TENNESSEE DIV OF RAD HEALTH Licensee: World Testing, Inc. Region: 1 City: Mount Juliet State: TN County: License #: R-95009 Agreement: Y Docket: NRC Notified By: Andrew Holcomb HQ OPS Officer: Ossy Font |
Notification Date: 08/07/2020 Notification Time: 16:59 [ET] Event Date: 08/06/2020 Event Time: 15:30 [EDT] Last Update Date: 08/07/2020 |
| Emergency Class: Non Emergency 10 CFR Section: Agreement State |
Person (Organization): FRANK ARNER (R1DO) NMSS_EVENTS_NOTIFICATION (EMAIL) |
Event Text
| AGREEMENT STATE REPORT - RADIOGRAPHY CAMERA GUIDE TUBE DENTED The following was received from the Tennessee Division of Radiological Health via email: "On August 6, 2020, World Testing radiographers were radiographing at Matrix Drilling in Lewisburg, Tennessee. They were radiographing pipes and one of the pipes (weighing approximately 1000 pounds) rolled onto the guide tube, denting it. They could not crank the source back in. They called the RSO [(Radiation Safety Officer)]. The guide tube was curled and making it more difficult to get the source back into the camera. They pulled on the crank to straighten out the guide tube and with enough pressure they were able to get the source past the dent and back into the exposure device. They placed lead on the collimator for additional shielding while working with it. The camera was a Sentinel, Model 880D, Serial number D-1120. The [Ir-192] source serial number was 96522G, with an activity of 44Ci. The source was exposed for approximately 4 hours. All personnel involved were wearing dosimetry. There were no overexposures." Tennessee Event Report ID No.: TN-20-114 |
| Power Reactor | Event Number: 54839 |
| Facility: Turkey Point Region: 2 State: FL Unit: [3] [] [] RX Type: [3] W-3-LP,[4] W-3-LP NRC Notified By: Art Alvarez HQ OPS Officer: Thomas Herrity |
Notification Date: 08/18/2020 Notification Time: 00:08 [ET] Event Date: 08/17/2020 Event Time: 21:13 [EDT] Last Update Date: 08/18/2020 |
| 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): MARK MILLER (R2DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 3 | M/R | Y | 92 | Power Operation | 0 | Hot Standby |
Event Text
| MANUAL REACTOR TRIP DUE TO RISING STEAM GENERATOR LEVEL "On 08/17/20 at 2113 EDT, with Unit 3 in Mode 1 at approximately 92% [Rated Thermal Power] RTP, the reactor was manually tripped. This was due to a turbine runback caused by CV-3-2011, Low Pressure Feedwater Heater Bypass Control Valve, failing open, followed by rising Steam Generator (S/G) levels. Unit 3 reactor was tripped manually when the 3C S/G Level reached 78% narrow range. Unit 3 Main Steam Isolation Valves were closed manually in accordance with Emergency Operating Procedure (EOP) network due to 38 MSR Main Steam Stop valve position indication lost. All other systems operated normally. Auxiliary Feedwater initiated as designed to provide S/G water level control. EOPs have been exited and General Operating Procedures (GOPs) were entered. Unit 3 is stable in Mode 3 at normal operating temperature and pressure. "This event is being reported pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). "The NRC Resident Inspector has been notified." All rods are inserted, decay heat is being removed via S/G through normal secondary systems. The plant is in normal electrical line up. Lightning strike is believed to be the initial cause of the runback. |
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021