ML18255A063

Correction to Wolf Creek Submittal of Anchor Darling Double Disc Gate Valve Information and Status

ML18255A063
Person / Time
Site:	Wolf Creek
Issue date:	09/04/2018
From:	Hafenstine C Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 18-0093
Download: ML18255A063 (3)

Text

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'NUCLEAR OPERATING CORPORATION September 4, 2018 Cynthia R. Hafenstine Manager Nuclear and Regulatory Affairs RA 18-0093 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. Lubinski, USNRC

Subject:

2) 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

3) Letter RA 17-0144, dated December 20, 2017, from C. R. Hafenstine, WCNOC, to USNRC Docket No. 50-482:

Correction to 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 2 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. Reference 3 was intended to provide that information for Wolf Creek Generating Station (WCGS).

Subsequent to that submittal, Wolf Creek Nuclear Operating Corporation (WCNOC) discovered that some valve data was incorrect. The attachment to this letter contains the correct Anchor Darling DDGV information and status.

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

RA 18-0093 Pa~e 2 of 2 It is important to note that while some data submitted was incorrect, all Anchor Darling DDGVs subject to Flowserve's Part 21 Notice in service at WCGS have had all repairs completed. As such, this letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4204.

Sincerely, Cynthia R. Hafenstine CRH/rlt

Attachment:

Corrected Wolf Creek Generation Station Anchor Darling DDGV Information and Status cc:

K. M. Kennedy (NRC), w/a B. K. Singal (NRC), w/a N. H. Taylor (NRC), w/a Senior Resident Inspector (NRC}, w/a

Attachment to RA 18-0093 Page 1 of 1 Corrected Wolf Creek Generating Station Anchor Darling DDGV Information and Status Plan.f.'.

'Name Wolf Creek Wolf Creek Wolf Creek Wolf Creek Wolf Creek Un. it 1

1

,Valve ID

..*.*Syste.61.

Component Cooling EGHV0058 Water Component Cooling EGHV0059 Water Component Cooling EGHV0060 Water Component Cooling EGHV0127 Water Component Cooling EGHV0130 Water

' Valve Act_._i.v_ *e

• Valve Functional *..

• _*.. _oe*.*s**.**c'_**-:r*_*_*1p* t"10** n'* **

Size*

• Safety'<

CCW TO RCS ISO VL V <CTMT ISO>

CCW RETURN FROM RCS ISO VL V <CTMT ISO>

CCW RETURN FROM RCS ISO VL V <CTMT ISO>

CCW TO RCS HV-58 & HV-71 BYPASS ISO VL V

<CTMT ISO>

RCS CCW RETURN HV-60 BYPASS ISO VLV <CTMT ISO>

I*

(in~hesr FLinctiofr L.

12 12 12 12 12 (Open,

.. Close;_..

Both) :

Close Close Close Close

<Passive)

Close (Passive)

Component RCS CCW RETURN Are multiple design*

basis post--*.*,

accident.. :...

'strokes:*

required?

(Yes/N~)\\{

No No No No No Expert Panel Risk /

._.Ranking*.. *

(High, Medium,.*.

. Le>w)*

Low Low Low Low Low 1 Result of susceptibility

,* ei11aluation_.. *

' I (Su~ceptible or.

Not ;susceptible)

Susceptibie(3l Susceptible(3l Susceptible(3l Susceptible(3l Susceptible(3>

Wolf Cooling HV-59 BYPASS ISO Close Creek 1

EGHV0131 Water VLV <CTMT ISO>

12 (Passive)

No Low Susceptible(

3l 1" 1 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 at least 520 ft-lbs which is >125% of any tested or expected actuator torque value.

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

Is the susceptibility -:*_. Does t~e susceptibility evaluation in eneral evaluat10~. r~ry on thread

• • g ;

• fm:t10,n?

~°r;~f:~::;;~4~:;~:> ' If yes, Was,t~~ COF.*

'..*.'*I;:...

greater*.. t~-~IJ _Q.. 10?

<C1-.

('{es/No)*

No(4l No(4l (No),

(Yes, >0:10),

(Yes, ~IJ,10)

No No No No No No Was an initial stem~

Was the di~gnostic test

• rotation check data re{riewed for..

Y

.. a_.. lve repair-***

.. performed? ;;.*.. *failure precursors.

lfy,es; include,rota. tion clescribecl in TP161 > ' i *,

status***...

criteria

• ' }12R.4? * - ~--.*

(No),

• ,. *: (Yes, :S10deg.),

<.- JYes, :ss deg.).-.

No No No No No No (Yes/No)

Yes Yes Yes Yes Yes Yes

• (Repaired or

.. _l\\l<>t Re.paired)

Repaired(1 l(2>

Repaired(1 >(2>

Repaired(1 >(2l Repaired(1 >(2>

Repaired(1 l(2>

Repaired(1 >(2>

(3) All valves applicable to Flowserve's Part 21 were conservatively considered susceptible in accordance with WCNOC's corrective action process.

(4) The resolution concluded and implemented from WCNOC's corrective action process predated access to the BWROG guidance, TP'16-1-112R4, which WCNOC subsequently reviewed and found the initial determination to be bounding.