ULNRC-06402, Anchor Darling Double Disc Gate Valve Information and Status

Anchor Darling Double Disc Gate Valve Information and Status

ML17348A558
Person / Time
Site:	Callaway
Issue date:	12/14/2017
From:	Wink R Ameren Missouri, Union Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-06402
Download: ML17348A558 (5)

Text

Ame MISSOURI ren CaI1aav Plant December 14. 2017 ULNRC-06402 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington. DC 20555-0001 Ladies and Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.

RENEWED FACILITY OPERATING LICENSE NPf-30 ANCHOR DARLING DOUBLE DISC GATE VALVE INFORMATION AND STATUS

References:

1) Letter from Greg Krueger (NEI) to John Lubinski (U.S. Nuclear Regulatory Commission). Anchor Darling Double-Disc Gate Valve Indtistry Resolution Plan Update (Project 689), dated August 4. 2017

2) Letter from Joe Pollock (NEI) to Brian Holian (U.S. Nuclear Regulatory Commission). NSIAC Concurrence on Anchor Darling Double-Disc Gate Valve Industry Response Actions (Project 689), dated October 26. 2017

3) BWROG Topical Report TP-16-l-1 12. Revision 4. Recommendations to Resotve Ftowserve 10 CFR Part 21 Notification Affecting Anchor Darling Double-Disc Gate Valve Wedge Pin Failure 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 fttnctions along with relevant valve information, including the results of susceptibility evaluations, repair status, and a repair schedule for each susceptible valve not yet repaired. This letter serves to provide this information for the Callaway Plant.

P.O. Box 620 Fulton, MO 65251  : AmerenMissouri.com

ULNRC-06402 December 14. 2017 Page 2 of 1 The Attachment to this letter contains the following information for each ADDDGV.

• Plant name. unit. and valve ID.

• System.

• Valve functional description.

• Valve size.

• Active safety function (open. close, both).

• Are multiple design basis post-accident strokes required (yes/no)?

• Expert Panel risk ranking (high. medium, low).

• Result of susceptibility evaluation (susceptible or not susceptible).

• Is the susceptibility evaluation in general conformance with TP-16-l-1 12 R4 (Reference 3)?

• Does the susceptibility evaluation rely on thread friction? If yes, was the COF greater than

0. 1 0? For cases where thread-friction was relied upon, information is provided on whether the coefficient of friction was above or below 0.1.

• Was an initial stem-rotation check performed? If yes, rotation criteria (i.e.. 10 degrees or < 5 degrees) are included.

• Was the diagnostic test data reviewed for faiLure precursors described in TP-16-1-112 R4 (Reference 3)?

• The valves repair status (i.e. repaired or not repaired).

• A repair schedule for each susceptible valve.

This Letter does not contain new commitments.

Shocild you have any questions or require additional information, please contact me at (573) 310-7025 or Terry Becker, Supervising Engineer at (573) 659-6068.

Sincerely, 2

Roger Wink Manager, Regulatory Affairs

Attachment:

Callaway Plant ADDDGV Valve Listing

ULNRC-06402 December 14, 2017 Page 3 of 4 cc: Mr. Kriss M. Kennedy Regional Administrator U. S. Nuclear Reaulatory Commission Region IV 1600 East Lamar Boulevard Arlington. TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman. MO 65077 Mr. L. John Kios Project Manager, Callaway Plant Office of Nticlear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 081-14 Washington. DC 20555-000 1

ULN RC-06402 December 14. 2017 Page 4 of 4 Index anti send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 6100 Western Place. Suite 1050 Fort Worth, TX 76107 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disctosed.)

Electronic distribtttion for the following can be macic via Responses and Reports Distribution:

F. M. Diya I. E. Herrmaim B. L. Cox S. P. Banker I. C. Olson R. C. Wink T. B. Eiwood Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. Jay Silberg (Pillsbury Winthrop Shaw Pittman LLP)

Attachment 1 to ULNRC-06402 December 14, 2017 Page 1 of 1 Callaway Plant ADDDGV Valve Listing Plant Callaway Callaway Callaway Unit Unit 1 Unit 1 Unit 1 Valve ID EGHVOO58 EGHVOO59 EGHVOO6O Component Cooling Component Cooling Component Cooling Water System Water (CCW) Water (CCW) (CCW)

CCW from Reactor Coolant CCW to Containment CCW from Containment System from Containment Valve Functional Description Outer Isolation Outer Isolation Inner Isolation Valve Size 12, 150 pressure class 12, 150 pressure class 12, 150 pressure class Active Safety Function Close Close Close Multiple Design Basis Post-Accident Strokes Required? No No No Risk Ranking Low Low Low Result of Susceptibility Evaluation Susceptible Susceptible Susceptible Yes, Priority 1C (stem/disc Yes, Priority 3B (Low risk Yes, Priority 3B (Low risk connection was assembled safety related valve with safety related valve with by plant maintenance, no no evidence of no evidence of record of adequate stem Susceptibility Evaluation lAW TP16 separation); pressed on separation); pressed on pre-torque); pressed on 112R4? stem collar stem collar stem collar Yes, thread friction (COF=O.42l was credited in evaluation showing that torque applied during a 2010 stall event was not adequate to fail the pin. However, the evaluation remains SAT if COF=0.1 is used.

Additionally, the pins shear torque excluding thread friction has 80%

Susceptibility Evaluation Reliant on margin over design basis Thread Friction? No torque No Initial Stem Rotation Check Completed SAT; rotation Completed SAT; rotation Completed SAT; rotation Performed? criteria 5 degrees criteria 5 degrees criteria 5 degrees Diagnostic Test Data Reviewed for Test data reviewed SAT; Test data reviewed SAT; Failure Precursors lAW TP16 No failure precursors No failure precursors Test data reviewed SAT; No 112R4? observed observed failure precursors observed Repair Status Not repaired Not repaired Not repaired Repairs tentatively Repairs tentatively planned for next Repairs tentatively planned planned for next refueling refueling outage in for next refueling oLitage in Repair Schedule outage in Spring 2019. Spring 2019. Spring 2019.