ML26044A211
| ML26044A211 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/12/2026 |
| From: | Kirkland H Flowserve Corp |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 56612: | |
| Download: ML26044A211 (0) | |
Text
02-12-2026 07:03:41 U.S. Nuclear Regulatory Commission Operations Center Report 1
02-12-2026 07:03:41 U.S. Nuclear Regulatory Commission Operations Center Report Event #:
56612 Event Type:
Power Reactor Site:
Summer Notify Date/Time:
2023-07-07 12:51 (EDT)
Unit:
1 / Region: 2 / State: SC Event Date/Time:
2023-05-11 12:50 (EDT)
Facility:
[1] W-3-LP,[2] W-AP1000,[3]
W-AP1000 Modify Date/Time:
2023-07-10 10:39 Containment Type:
DRY AMB Notified by:
Hank Kirkland Notifications:
Miller, Mark R2DO HOO:
Sam Colvard Part 21/50.55 Reactors, - EMAIL Emergency Class:
Non Emergency 10 CFR Sections:
21.21(d)(3)(i)
Defects And Noncompliance Unit Scram Code Rx Crit Init Power Init RX Mode Curr Power Current RX Mode 1
N No 0
Hot Shutdown 100 Power Operation PART 21 - CAP SCREW IMPROPER LENGTH The following information was provided by the licensee via email:
"This is a non-emergency notification required by 10 CFR 21.21(d)(3)(i). A written notification in accordance with 10 CFR 21.21(d)(3)(ii) will be provided within 30 days. Steam generator emergency feedwater header discharge isolation check valves (XVC01009A-EF, XVC01009B-EF, and XVC01009C-EF) were designed specifically for and supplied to VC Summer Nuclear Station (VCSNS) by Flowserve under purchase order 4500653391 to replace the previous valves in the emergency feedwater system during refueling outage 27. On May 11, 2023, after valve installation, but prior to initial service, the socket head cap screws were identified as being shorter than the required design length. Valve drawings indicate a design length of 1.25" while the socket head cap screws received were 0.875". The correct length cap screws were installed prior to initial service. VCSNS completed a substantial safety hazard evaluation and determined that the improper length of the cap screws constituted a substantial safety hazard. This deviation in cap screw length resulted in a partial engagement of the cap screw to the cylinder rod extension and could potentially affect valve operation.
"The NRC Senior Resident Inspector has been notified."
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