Event Notification Report for June 11, 2024
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/10/2024 - 06/11/2024
Part 21
Event Number: 57167
Rep Org: Flowserve
Licensee: Flowserve
Region: 2
City: Raleigh State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Aaron G. Goodbar
HQ OPS Officer: Natalie Starfish
Licensee: Flowserve
Region: 2
City: Raleigh State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: Aaron G. Goodbar
HQ OPS Officer: Natalie Starfish
Notification Date: 06/07/2024
Notification Time: 18:30 [ET]
Event Date: 06/07/2024
Event Time: 00:00 [EDT]
Last Update Date: 06/10/2024
Notification Time: 18:30 [ET]
Event Date: 06/07/2024
Event Time: 00:00 [EDT]
Last Update Date: 06/10/2024
Emergency Class: Non Emergency
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
10 CFR Section:
21.21(d)(3)(i) - Defects And Noncompliance
Person (Organization):
Franke, Mark (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
Franke, Mark (R2DO)
Part 21/50.55 Reactors, - (EMAIL)
EN Revision Imported Date: 6/11/2024
EN Revision Text: PART 21 REPORT - CHECK VALVE FAILS BENCH TEST
The following is a synopsis of information received via email:
Flowserve Corporation identified a defect with their 0.5 inch model 1878 piston check valve during bench testing. The piston check valve with adjustable cracking pressure received by Duke Energy Catawba Nuclear Station failed bench test performance for designed cracking pressure with an allowable range of 180 - 220 psig. The valve is used to provide overpressure protection of containment penetration piping due to thermal expansion of fluid trapped between the containment isolation valves when the valves are closed. The valves are required to crack open before the maximum 220 psig setpoint to perform this function. Corrective actions include revising Flowserve's assembly and test procedures for the 0.5 inch model 1878 piston check valve.
Affected known plant: Catawba Nuclear Station
The name and address of the individual reporting this information is:
Aaron G. Goodbar
Nuclear Quality Assurance Manager
Flowserve Corporation
1900 S. Saunders St.
Raleigh, NC 27603
1-888-200-5389
EN Revision Text: PART 21 REPORT - CHECK VALVE FAILS BENCH TEST
The following is a synopsis of information received via email:
Flowserve Corporation identified a defect with their 0.5 inch model 1878 piston check valve during bench testing. The piston check valve with adjustable cracking pressure received by Duke Energy Catawba Nuclear Station failed bench test performance for designed cracking pressure with an allowable range of 180 - 220 psig. The valve is used to provide overpressure protection of containment penetration piping due to thermal expansion of fluid trapped between the containment isolation valves when the valves are closed. The valves are required to crack open before the maximum 220 psig setpoint to perform this function. Corrective actions include revising Flowserve's assembly and test procedures for the 0.5 inch model 1878 piston check valve.
Affected known plant: Catawba Nuclear Station
The name and address of the individual reporting this information is:
Aaron G. Goodbar
Nuclear Quality Assurance Manager
Flowserve Corporation
1900 S. Saunders St.
Raleigh, NC 27603
1-888-200-5389
Fuel Cycle Facility
Event Number: 57162
Facility: Framatome ANP Richland
Region: 2 State: WA
Unit: [] [] []
RX Type: Uranium Fuel Fabrication
Comments: Leu Conversion
Fabrication & Scrap Recovery
Commercial Lwr Fuel
NRC Notified By: Brandon Hanson
HQ OPS Officer: Kerby Scales
Region: 2 State: WA
Unit: [] [] []
RX Type: Uranium Fuel Fabrication
Comments: Leu Conversion
Fabrication & Scrap Recovery
Commercial Lwr Fuel
NRC Notified By: Brandon Hanson
HQ OPS Officer: Kerby Scales
Notification Date: 06/05/2024
Notification Time: 16:06 [ET]
Event Date: 06/05/2024
Event Time: 16:13 [PDT]
Last Update Date: 06/05/2024
Notification Time: 16:06 [ET]
Event Date: 06/05/2024
Event Time: 16:13 [PDT]
Last Update Date: 06/05/2024
Emergency Class: Non Emergency
10 CFR Section:
PART 70 APP A (c) - Offsite Notification/News Rel
10 CFR Section:
PART 70 APP A (c) - Offsite Notification/News Rel
Person (Organization):
Franke, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Franke, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
CONCURRENT REPORT FOR DEGRADED HEPA FILTER
The following information was provided by the licensee via phone and email:
"This concurrent report is being made because a HEPA filter on a scrap recovery line had degraded below the efficiency that would allow it to remain in service (76.85 percent versus 99.95 percent). This condition is reportable to the Washington Department of Health in accordance with Radioactive Air Emissions License (RAEL) 038. The scrap recovery line has been shut down pending further investigation into the cause of the loss of filter efficiency. Investigation has revealed that no limits were exceeded and no additional reporting is required."
The following information was provided by the licensee via phone and email:
"This concurrent report is being made because a HEPA filter on a scrap recovery line had degraded below the efficiency that would allow it to remain in service (76.85 percent versus 99.95 percent). This condition is reportable to the Washington Department of Health in accordance with Radioactive Air Emissions License (RAEL) 038. The scrap recovery line has been shut down pending further investigation into the cause of the loss of filter efficiency. Investigation has revealed that no limits were exceeded and no additional reporting is required."