Event Notification Report for September 08, 2019
|
U.S. Nuclear Regulatory Commission Event Reports For ** EVENT NUMBERS ** |
| 54215 | 54245 | 54257 | 54262 | 54263 |
| Part 21 | Event Number: 54215 |
| Rep Org: FLOWSERVE Licensee: FLOWSERVE FLOW CONTROL DIVISION Region: 1 City: RALEIGH State: NC County: License #: Agreement: Y Docket: NRC Notified By: KEVIN WORTH HQ OPS Officer: CATY NOLAN |
Notification Date: 08/12/2019 Notification Time: 17:47 [ET] Event Date: 08/12/2019 Event Time: 00:00 [EDT] Last Update Date: 09/06/2019 |
| Emergency Class: NON EMERGENCY 10 CFR Section: 21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE |
Person (Organization): JONATHAN GREIVES (R1DO) GERALD MCCOY (R2DO) HIRONORI PETERSON (R3DO) RAY KELLAR (R4DO) - PART 21/50.55 REACTORS (EMAIL) |
Event Text
| PART 21 - NON-DESTRUCTIVE EXAMINATION PERFORMANCE OF COMPONENTS BY AN UNQUALIFIED EMPLOYEE The following is a summary of the information received from Flowserve via facsimile: Contrary to the requirements of ASME Section III & ASME NQA-1 Requirement 2, an employee of Flowserve was found to have performed Non-Destructive Examinations (Liquid Penetrant Testing - PTs) without the required certificate in accordance with ASNT SNT-TC-1A, and Flowserve's written practice. The employee was trained and tested in accordance with the written practice and ASNT requirements. Although the individual section scores were found to pass the (70 percent) minimum, the composite test requirements failed to meet the minimum 80 percent requirement. Actual composite score achieved was 79.176 percent. The extent of exposure to this condition was on examinations completed between 10/22/18 and 11/21/18. There were ten examinations, totaling 22 pieces that were completed by the employee without oversight/signature by another certified individual. The scope of impacted valves/components encompasses body, stem, cover, yoke, pin wedge, and disk. Licensees affected include Exelon Company, Pinnacle West Capital Corp, Bruce Power, Xcel Energy, Alabama Power, Entergy Nuclear Operations Inc., and FirstEnergy. Flowserve issues a corrective action, and is currently in the process of determining the root cause and prevention action measures. This will include identifying the affected valves via communications with affected customers. * * * UPDATE ON 09/06/2019 AT 1345 EDT FROM KEVIN WORTH TO JEFFREY WHITED * * * The following is a synopsis of a letter received from Flowserve: On 09/06/19, Flowserve issued its Final Report for the Part 21, noting the scope of the valves/components affected by the issue described above. Flowserve also noted the corrective actions that were taken to address the issue and detailed the specific actions taken for the individual components. Notified R1DO (Carfang), R2DO (Shaeffer), R3DO(Edwards), R4DO(O'Keefe), and Part 21/50.55 Reactors Group (e-mail). |
| Agreement State | Event Number: 54245 |
| Rep Org: OK DEQ RAD MANAGEMENT Licensee: HOLLYFRONTIER TULSA REFINING Region: 4 City: TULSA State: OK County: TULSA License #: GLD0027 Agreement: Y Docket: NRC Notified By: KEVIN SAMPSON HQ OPS Officer: BRIAN LIN |
Notification Date: 08/29/2019 Notification Time: 17:18 [ET] Event Date: 08/28/2019 Event Time: 00:00 [CDT] Last Update Date: 08/29/2019 |
| Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE |
Person (Organization): RAY AZUA (R4DO) NMSS_EVENTS_NOTIFICATION (EMAIL) |
Event Text
| AGREEMENT STATE REPORT - SHUTTER FAILURE The following was received from the Oklahoma Department of Environmental Quality via email: "The State of Oklahoma reported that a generally-licensed Ronan Model SA-F37 fixed gauge (S/N M2265) containing 1.5 Ci of Cs-137 experienced a shutter failure during routine maintenance. The source holder is being removed from service and will be stored pending disposal." |
| Power Reactor | Event Number: 54257 |
| Facility: SOUTH TEXAS Region: 4 State: TX Unit: [] [2] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: MICHAEL CHANDLER HQ OPS Officer: CATY NOLAN |
Notification Date: 09/06/2019 Notification Time: 02:47 [ET] Event Date: 09/05/2019 Event Time: 21:15 [CDT] Last Update Date: 09/06/2019 |
| Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION |
Person (Organization): NEIL O'KEEFE (R4DO) |
| 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
| CONTAINMENT PENETRATION DISCOVERED NOT ISOLATED "At 2115 CDT on 9/5/2019, an inside containment test connection and inoperable outside containment isolation valve were discovered to be open for a containment air sample penetration. This resulted in the containment penetration not being isolated. The inside containment test connection was closed at 2322 CDT on 9/5/2019. "This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and (D) and 10 CFR 50.72(b)(3)(ii)(B). "There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. " |
| Power Reactor | Event Number: 54262 |
| Facility: SAINT LUCIE Region: 2 State: FL Unit: [1] [] [] RX Type: [1] CE,[2] CE NRC Notified By: REESE KILIAN HQ OPS Officer: ANDREW WAUGH |
Notification Date: 09/07/2019 Notification Time: 12:01 [ET] Event Date: 09/07/2019 Event Time: 08:24 [EDT] Last Update Date: 09/07/2019 |
| Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL |
Person (Organization): SCOTT SHAEFFER (R2DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
Event Text
| AUTOMATIC REACTOR TRIP "On September 09, 2019 at 0824 EDT, with St. Lucie Unit 1 in Mode 1 at 100 percent power, the reactor automatically tripped on Low Reactor Coolant System Flow due to a trip of the 1A1 reactor coolant pump. The trip was uncomplicated with all systems responding normally post-trip. Operators responded and stabilized the plant in Mode 3. The cause of the loss of the 1A1 reactor coolant pump is currently under investigation. "St. Lucie Unit 2 was unaffected and remains in Mode 1 at 100 percent power. "This report is submitted in accordance with 10 CFR 50.72(b)(2)(iv)(B) for the reactor trip." Decay heat removal is being accomplished by main feed water and the main condenser using the turbine steam bypass valves. The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 54263 |
| Facility: DAVIS BESSE Region: 3 State: OH Unit: [1] [] [] RX Type: [1] B&W-R-LP NRC Notified By: TIM THOMPSON HQ OPS Officer: ANDREW WAUGH |
Notification Date: 09/07/2019 Notification Time: 15:53 [ET] Event Date: 09/07/2019 Event Time: 13:09 [EDT] Last Update Date: 09/07/2019 |
| Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL |
Person (Organization): ANN MARIE STONE (R3DO) |
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | |||||||
| 1 | A/R | Y | 95 | Power Operation | 0 | Hot Standby |
Event Text
| AUTOMATIC REACTOR TRIP "At 1309 EDT on September 7, 2019, with the unit in Mode 1 at approximately 95 percent power, the reactor automatically tripped during main turbine valve testing. The trip was not complex with all systems responding normally post-trip. "Operations responded and stabilized the plant. Decay heat is being removed by the turbine bypass valves discharging steam to the main condenser. "Due to the reactor protection system actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). The cause of the reactor protection system actuation is under evaluation. "There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified." |
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021