NLS2017100, Anchor Darling Double Disc Gate Valve Information and Status

Anchor Darling Double Disc Gate Valve Information and Status

ML18010A069
Person / Time
Site:	Cooper
Issue date:	12/20/2017
From:	Dent J Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2017100
Download: ML18010A069 (3)

Text

Nebraska Public Power District Alwa:ys there when :you need us NLS2017100 December 20, 2017 Attention: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Anchor Darling Double Disc Gate Valve Information and Status Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46

References:

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

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

3) BWROG Topical Report TP16-1-112, Recommendations to Resolve Flowserve 10 CFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failures (Revision 4)

Dear Sir or Madam:

In Reference 1, the Nuclear Energy Institute (NEI) provided the Nuclear Regulatory Commission (NRC) a resolution plan for the U.S. Nuclear Industry to address the known Anchor Darling Double Disc 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 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 Cooper Nuclear Station. -

The attachment to this letter contains the following information for each ADDDGV:

• Plant Name, Unit, and Valve ID;

• System;

• Valve Functional Description;

• Valve Size (inches);

• Active Safety Function (open, close, both);

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

COOPER NUCLEAR STATION P. 0. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com

NLS2017100 Page 2 of2

• Expert Panel Risk Ranking (high, medium, low);

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

• Is the susceptibility evaluation in general conformance with TP16-1-112R4 (Reference 3)

(yes/no);

• Does the susceptibility evaluation rely on thread friction (yes/no)? If yes, was the coefficient of friction (COF) greater than 0.10? For cases where thread-friction was relied upon, information is provided whether the COF was above or below 0.1;

• Was an initial stem-rotation check performed (yes/no)? If yes, include rotation criteria (i.e. :SlO degrees or :S5 degrees);

• Was the diagnostic test data reviewed for failure precursors described in TP16-1-112R4 (Reference 3) (yes/no);

• The valve's repair status (i.e. repaired or not repaired); and

• A repair schedule for each susceptible valve.

This letter contains no regulatory commitments.

Should you have any questions or require additional information, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.

Sincerely,

/;?;;:,~ f(V1)1& /wgo 'Jvv-. BuJJ-vice President - Nuclear and Chief Nuclear Officer

/dv Attachments: Cooper Nuclear Station (CNS) Anchor Darling Double Disc Gate Valve Listing cc: Regional Administrator w/ attachment USNRC - Region IV Cooper Project Manager w/ attachment USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/ attachment USNRC-CNS NPG Distribution w/o attachment CNS Records w/ attachment

NLS2017100 Attachment Page 1 of 1 iI Cooper Nuclear Station (CNS) Anchor Darling Double Disc Gate Valve Listing

!' Is the Does the Was the Are multiple

' susceptibility susceptibility Was an initial stem- diagnostic test design Expert *, Result of Valve Valve Active evaluation in evaluation rely on rotation check data reviewed Plant basis post- Panel susceptibility Valve repair Unit Valve ID System Functional Size Safety general thread friction? performed? for failure Name accident Risk evaluation status

. Description (inches) Function conformance If yes, was the If yes, include precursors strokes Ranking with. TP16 COF greater than rotation criteria described in required?

112R4?<1> 0.10? i TP16-1-112R4?

(Open, (High, (susceptible (No), (No), (repaired Close,. Medium, or (Yes/No) (Yes, >0.10), (Yes, :::;10 deg.), (Yes/ No) or (Yes/No)

Both) Low) not susceptible) (Yes, <0.10) (Yes, <5 deg.) not repaired)

Reactor Recirc  :

. :. Pump A Ye~, ongoing and RR-MOV- Reactor Discharge Yes, Yes periodic, once per CNS 1 M053A Recirculation Isolation 28 Close No Low Susceptible<2> Yes (>0.10, pendingi2) cycle, :S20 degrees< 3) Yes Not repaired<4 )

I Reactor Recirc PumpB yes, ongoing and RR-MOV-- Reactor -Discharge Yes, Yes periodic, once per I , (3)

CNS 1 M053B Recirculation , Isolation 28 Close No Low Susceptible<2

) Yes (>0.10, pendingf) cycle, :S20 degrees Yes Not repaired<4)

(1) Applied Wedge Pin Torque must bound anticipated design basis operating torque requirements and current maximum total torque. '

(2) Weak Link Analysis is currently in development to incorporate the wedge pin subcomponent and will move this to "non-susceptible" status; final acceptance projected January 26, 2018. Exact coefficient of friction (COF) is yet to be determined.

(3) Previous inspections used a :::20 degrees rotation criteria. The susceptible valves will be inspected in RE30 (Fall 2018) to the rotation criteria specified in the current inspection procedure which is :::5 degrees.

(4) CNS has no plans for disassembly/repair 1planned at this time. Completion of evaluation per Note (2) will move this from priority 3b to priority 5 with no inspection required:

The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.)

.. COMMITMENT TYPE COMMITTED DATE OR COMMITMENT ONE-TIME ACTION Programmatic "OUTAGE" (Yes/No) (Yes/No)

None i'

'