ML17361A073
| 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
Subject:
- 2)
BWROG Topical Report TP16-1-112, Revision 4, "Recommendations to Resolve Flowserve 1 OCFR 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 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. ;.
..
- _EPxapn' eertl.*. ',' Result ot:susceptibjlity evaluation rely ori thread
'. ' rotation check);;
. data reviewed for
/,
. b~sis post7*
evaluatiori in general
\\/alv~*repair.
. acciderif *,
. evaluation coriformarice with.
'. friction? '..
performed?_ ' * '
f~ilure precun;;c;>rs status '
. *NPla~i
- u*nif Valve,*
Active Valve Functional: *., Si~e'.,
Safety*.
Description
- ,
- 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},*
ame (inches)
,Function
- ~ -: -
. " ~-
- (repaired or
.Close,***,,.. (Y iN*.*),.. Medfoin,
. nohusceptib.ie_*).**
- . (Y~s/No).
r*(Yes,>0,10),
JYes,.:S10deg.);**
Both) es o *,
Low)*
... *(Yes; :S0.10)
(Yes, :S5.cteg.).
'(Yes/No),
. no~ repaired}*
Wolf Creek Wolf Creek Wolf Creek Wolf Creek Wolf Creek 1
1 1
Component Cooling EGHV0058 Water Component Cooling EGHV0059 Water Component Cooling EGHV0060 Water Component Cooling EGHV0127 Water Component Cooling EGHV0130 Water CCW TO RCS ISO VL V <CTMT ISO>
CCWRETURN FROM RCS ISO VLV <CTMT ISO>
CCWRETURN FROM RCS ISO VLV <CTMT ISO>
CCW TO RCS HV-58 & HV-71 BYPASS ISO VLV
<CTMT ISO>
RCS CCW RETURN HV-60 BYPASS ISO VLV <CTMT ISO>
2 2
2 2
Close Close Close Close (Passive)
Close (Passive)
No High Susceptible No Susceptible No High Susceptible No High Susceptible<4>
No Hiqh Susceptible<4>
Wolf Cooling HV-59 BYPASS ISO Close Creek 1
EGHV0131 Water VLV <CTMT ISO>
2 (Passive)
No High Susceptible<4>
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.
Yes Yes Yes No<4>
<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.
No No Yes Repaired<1 ><3>
No No Yes Repaired<1><3>
No No Yes
- Repaired<1><3>
No No Yes Repaired<2><3>
No No Yes Repaired<2><3>
No No Yes Repaired<2><3>