ML17361A073

Submittal of Anchor Darling Double Disc Gate Valve Information and Status

ML17361A073
Person / Time
Site:	Wolf Creek
Issue date:	12/20/2017
From:	Hafenstine C Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 17-0144
Download: ML17361A073 (3)

Text

Cynthia R. Hafenstine Manager Nuclear and Regulatory Affairs December 20, 2017 RA 17-0144 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Reference:

1) Letter dated August 4, 2017, "Anchor Darling Double Disc Gate Valve Industry Resolution Plan Update (Project 689)," from G. A. Krueger, NEI, to J. Lubin.ski, USNRC

2) BWROG Topical Report TP16-1-112, Revision 4, "Recommendations to Resolve Flowserve 10CFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failures," dated August 2017

3) Letter dated October 26, 2017, "NSIAC Concurrence on Anchor Darling Double Disc Gate Valve Industry Response Actions (Project 689)," from J.E. Pollock, NEI, to B. E. Holian, USNRC

Subject:

Docket No. 50-482: Wolf Creek Submittal of Anchor Darling Double Disc Gate Valve Information and Status To Whom It May Concern:

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 Valves (DDGV) issues. Reference 3 indicated each utility will provide a listing of their Anchor Darling DDGV 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 information was requested to be submitted by December 31, 2017. This submittal transmits that information for Wolf Creek Generating Station (WCGS).

The Attachment to this letter contains the following information for each Anchor Darling DDGV:

• Plant Name, Unit, and Valve ID

• System

• Valve Functional Description

• Valve Size

• Active Safety Function (open, close, both)

P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET

RA 17-0144 Page 2 of 2

• 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 TP16-1-112R4 (Reference 2)?

• Does the susceptibility evaluation rely on thread friction? If yes, was the coefficient of friction greater than 0.1 O?

• Was an initial stem-rotation check performed? If yes, include rotation criteria (i.e. s; 10 degrees ors; 5 degrees)

• Was the diagnostic test data reviewed for failure precursors described in TP16-1-112R4 (Reference 2)?

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

• A repair schedule for each susceptible valve.

As all Anchor Darling DDGVs subject to Flowserve's Part 21 Notice in service at WCGS have had repairs completed, this letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4204.

Sincerely, t;~e~

Cynthia R. Hafenstine CRH/rlt

Attachment:

Wolf Creek Generating Station Anchor Darling DDGV Information and Status cc: K. M. Kennedy (NRC), w/a G. A. Krueger (NEI), w/a B. K. Singal (NRC), w/a N. H. Taylor (NRC), w/a Senior Resident Inspector (NRC), w/a

Attachment to RA 17-0144

/

..Page 1 of 1 Wolf Creek Generating Station Anchor Darling DDGV Information and Status Are.multiple. * * * ".Y * ., ., ,.. ,*, .*, * . * ** ** *. ,._ ~--****I'.. ; * *

• • design * .* *** Is the susceptibility. D'<:>esthe,susceptibility Was an initial stem~ Was the cJiagn<>,sti~fost . ;.

Valve ,* Active .

• _EPxapn'eertl.*. ' ,' Result ot:susceptibjlity ' evaluation rely ori thread '. ' rotation check);; . data reviewed for /, '

.*NPla~i

• u*nif Valve Functional: * . , Si~e'. , Safety* . . b~sis post * * * * *

• evaluatiori in general * , * * ** * * * .** * * \/alv~*repair.

Description . * . acciderif7 *, . , . evaluation ' ,, coriformarice with . ' ' ' . friction? ' ..  ; performed?_ ' * ' f~ilure precun;;c;>rs status '

ame .*. ,*

(inches) ,Function ,'  ;,

• Risk ,, . 1

• • TP1's* 1*1*2R4'.?'(A)

• lfyes,wastheCOF lfye~.inclu,derotation -:de~cribE!dJri"TP1f:i-f~

- ~ -: - . " ~- . ., " ' *' . strokes . Ranking,:_: *. . ** ** * * .. .-:. * * * * **

'required? .. . *.. ,:.~ * , ** "* * ._., '-* *,great~r.than MO?,  : criteria ,: , , ;: . .112R4? * *

'. (Open,  ;. '(High,  : (susceptible*or * " >. (No), * * (No},* * * * ,  : (repaired or

_; ., *. .Close,***,,.. (Y iN*.*), . . Medfoin, . nohusceptib.ie_*).** .* **. (Y~s/No). ' r*(Yes,>0,10), JYes,.:S10deg.);** '(Yes/No),

Both) ., es o *, ' Low)* , .. . * * ** ' ...*(Yes; :S0.10) * (Yes, :S5.cteg.) . . no~ repaired}*

Component Wolf Cooling CCW TO RCS ISO Creek EGHV0058 Water VLV <CTMT ISO> 2 Close No High Susceptible Yes No No Yes Repaired< 1><3>

Component CCWRETURN Wolf Cooling FROM RCS ISO Creek 1 EGHV0059 Water VLV <CTMT ISO> 2 Close No Susceptible Yes No No Yes Repaired< 1><3>

Component CCWRETURN Wolf Cooling FROM RCS ISO Creek 1 EGHV0060 Water VLV <CTMT ISO> 2 Close No High Susceptible Yes No No Yes

• Repaired< 1><3 >

CCW TO RCS HV-Component 58 & HV-71 Wolf Cooling BYPASS ISO VLV Close Creek 1 EGHV0127 Water <CTMT ISO> 2 (Passive) No High Susceptible< >

4 No<4> No No Yes Repaired<2><3>

Component RCS CCW RETURN Wolf Cooling HV-60 BYPASS ISO Close Creek EGHV0130 Water VLV <CTMT ISO> 2 (Passive) No Hiqh Susceptible< >

4 No No Yes Repaired< 2>< 3>

Component RCS CCW RETURN Wolf Cooling HV-59 BYPASS ISO Close Creek 1 EGHV0131 Water VLV <CTMT ISO> 2 (Passive) No High Susceptible< >

4 No No Yes Repaired<2><3>

lAJ Applied Wedge Pin Torque must bound anticipated design basis operating torque requirements and current maximum total torque.

1

< >The repair included torqueing the stem/wedge connection to 170% of the anticipated design basis operating torque, 520 ft-lbs.

2

< >The repair included torqueing the stem/wedge connection to 150% of the anticipated design basis operating torque, 520 ft-lbs.

3

< >The maximum allowable stem torque is 695 ft-lbs for the installed 2-piece stems, per Flowserve.

4

< >Under the TP16-1-112R4 guidance these valves would not be considered susceptible as they are passive valves, however our Part 21 action plan predated access to the BWROG guidance.