ML17347A906

Susquehanna Steam Electric Station No Action Safety Function Anchor Darling Double Disc Gate Valves

ML17347A906
Person / Time
Site:	Susquehanna
Issue date:	12/13/2017
From:	Berryman B Susquehanna, Talen Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7665
Download: ML17347A906 (1)

Text

Brad Berryman Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Brad.Berryman@talenenergy.com ENERGY DE C. 1 3 _2 01 7 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 10 CFR 50.4 SUSQUEHANNA STEAM ELECTRIC STATION NO ACTION SAFETY FUNCTION ANCHOR DARLING DOUBLE DISC GATE VALVES UNIT 1 LICENSE NO. NPF-14 Docket No. 50-387 50-388 UNIT 2 LICENSE NO. NFP-22 PLA-7665

References:

I) Letter from Greg Krueg e r (NEJ) to John Lubinski, U.S. Nucl e ar Regulatory Commission , Anchor Darling Double Disc Gate Valve Industry Resolution Plan Update (Proj ec t 689), dated August 4 , 2017 (ML17220A363)

2) L e tt e r from Jo e Pollock (NEI) to Brian Holian, U.S. Nuclear Regulatmy Commission, NSIAC Concurrence on Anchor Darling Double Disc Gate Valv e Industry Response Actions (Proje c t 689), dated October 26, 2017 (ML17303A031)

In Reference 1 , the Nuclear Energy Institute (NEI) provided the NRC a resolution plan for the U.S. Nuclear Industry to address the known Anchor Darling Double Disk Gate Valve (ADDDGV) issues. Reference 2 indicated each utility will provide a listing of their Anchor Darling valve population with active safety functions along with relevant valve infmmation , including the results of susceptibility evaluations, repair status, and a repair schedule for each susceptible valve not yet repaired. Reference 2 also stated that utilities or sites without active safety function Anchor Darling DDGVs would also provide a response.

This letter serves to confirm that Susquehanna Steam Electric Station Unit 1 and 2 does not use Anchor Darling Double Disk Gate Valves with a threaded stem to upper wedge connection that is operated by an actuator that applies torque on the valve stem to suppmi any active safety function.

Should you have any questions regarding this submittal, please contact Mr. Jason Jennings, Manager-Nuclear Regulatory Affairs at (570) 542-3155.

This letter contains no new regulatory commitments.

B. Berryman