ML20055E050

From kanterella
Jump to navigation Jump to search
Responds to Info Notice 88-085 & NRC Bulletin 89-002 Re Two Anchor/Darling Swing Check Valves.Neither Valve Found to Have Any Svc Induced Cracking of Bolting.Existing Bolting Replaced W/Type 17-4PH Matl (Specification A564-630-1100)
ML20055E050
Person / Time
Site: Maine Yankee
Issue date: 07/02/1990
From: Frizzle C
Maine Yankee
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CDF-90-60, IEB-89-002, IEB-89-2, IEIN-88-085, IEIN-88-85, MN-90-64, NUDOCS 9007100319
Download: ML20055E050 (4)
v • d • e


Text

xg 1

gy-a 3

wg 4 *%

iMaineYankee M

MQi@f?IiiEiruon uAmt swct wit --

- EDISON DRIVE

  • AUGUSTA, MAINE 04336 * (207) 622 4868 -

m i

h.

Y Y

l 7

July 2,1990" MN-90-64
  • CDF-90-60 m

UNITED STATES NUCLEAR REGULATORY COMMISSION.

M iAttention:7 Document Control Desk bx ~, [ W.uashington, DC. ;20555 <

Reference:

J

'(a)- License No. DPR-36 1 Docket No. 50-309) m

.(b) ? NRC Information Notice No. 88-85: Broken Retaining Block Studs'

? y" R

T on Anchor Darling' Cteck Valves, dated October 14, 1988.

g p y,',

(c).. NRC Bulletin 'No. 80-02:J Stress ' Corrosion ' Cracking of _ High -

in-Ch 1,

Hardness Type 410 Stainless Steel InternaT Preloadad Bolting 'of Anchor Darling Model S350W Swing Check Valves or' Valves.

f 3iO b'^f Similar Design, dated July 19, 1989 u

i

, i ':Subjectie Request for Action to Identify, Disassemble and ' Inspect Certain1 Types of' QN/

Anchor Darling Swing Check Valves h[y iGentiemen:1

~

y

w?

.NRC Informatio'n Notice No. 88-85; Reference '(b), alerted licensees to potential Tc J

M problems relating 4to.the7 failure :of retaining block studs on Anchor Darling check N;

i.

valves'and the possible generic implementations. We evaluated the Information Notice 1

4"

' 1through 'our' 0perational: Assessment System and. determined that two-valves similar to C-ithose described in thellnformation Notice are ; installed in;our Primary Component V

(Cooling Water? SystemJ They were evaluated 's; not being ~ subject to the= failure -

a me'chanism;(intergranularastress corrosion cracking of the 410 studs.in a boric' acid.

/

. environment): described in' the Information Notice.

We : took: no further action-in response to.the Information Notice and considered the issue resolved.

s y

f Subsequently,1NRC Bulletin No. 89-02, Reference (c), requested-specificiaction

and? reporting :.regarding o this issue., Specifically,: it was requested that tall:

~,

73 *

,flicensees1 disassemble and inspect all safety-related Anchor Darling Model S350W swing Mi Lcheckivalves supplied with internal retaining block studs' of ASTM specification A193

! Grade 1B61 Type - 410 :SS.c Additionally,-.it was" req'uested that' licensees review the wlV edesign;of other safety-related check valves and:similarly inspect those of similar:

N N design and material; selection.- Finally, a report within-60 days of completion.of.the s

pinspections:wasrequested.

. K hw; hti,i ' 'W M,

[FkN S

oo

; CDF9060.LTR i,

9oo71oost9 9007o2 00 9

Mg, ',

- Poa:.ADOCK 05000309 u

I 4-a W. 2;% :p <

0 PDC U

\\ fl '

w &

k.

e

MaineYankee UNITED STATES NUCLEAR REGULATORY COMMISSION MN-90-64L Attention:l Document Control Desk-Page Two 4

Based on a review of plant records, Maine' Yankee has no ' Anchor Darling Model S350W swing check valves installed in safety class applications. Two Darling swing check valves (PCC-445 & 446) are installed in a safety cicss application with both a similar design-and bolting material as the Model S350W Anchor Darling valve.

In addition, our review concluded that twelve Velan swing check valves have a design similar to the problem Anchor Darling valve but utilize a different bolting material.-

Based on this difference in material, no further action ~was taken with respect to the

,Velan valves.

The two Darling swing check valves were disassembled and inspected during the refueling outage which began = April 7,1990.

Neither valve was found to have any service induced cracking of the bolting. The existing bolting was replaced with Type. 4PH material (Specification A564-630-1100) as recommended by the. valve manufacturer.-

Should you have any questions on this issue, please contact us.

Very truly yours, Charles D. Frizzle President

.WBD:SJJ

.c:

Mr. Thomas T. Martin Mr. Eric J. Leeds Mr. Richard J. Freudenberger-STATE OF: MAINE Then personally appeared before me, Charles D. Frizzle, who being duly sworn did state that he is President of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing response in the name and on behalf of TMaine Yankee Atomic Power Company,'and that the statements therein are true to the best of his knowledge and belief.

YYniw b an Notary Pfic' '

~

BARBARA J. PADAVtNA MYCoM

[

isNE::anas CDF9060.LTR.

N k'l4

5

' I >: -

(

f gn.'

en - _ _kee MaineYan M

x, u

-u

't g EDISON DRIVE

  • AUousTAiMAINE 04336 + (207) 6224868.

v_

e July 2,1990 MN-90-64 LCDF-90-60 Av%

O UNITED STATES NUCLEAR REGULATORY COMMISSION mjf Attention:e DocumenticontroliDesk j, ' Washington,.DC: ' 20555 o

T

Reference:

(a). License-No. DPR-36 (Docket No. 50-309).

(b) NRC Information Notice No. 88-85: Broken Retaining Block Studs-

- on Anchor-Darling Check Valves, dated 0ctober 14, 1988 (c) :NRCi Bulletin; No. 89-02:

Stress' Corrosion ~ Cracking 'of ' High--

~

Hardness Type 410. Stainless Steel Internal-Preloaded Bolting in

&p.

Anchor = Darling Model S350W Swing. Check' Valves or' Valves : of"

'I Similar Design, dated July:19,1989 Sub' ject:LJRequest for Action,to Identify,. Disassemble and Inspect Certain Types of-Anchor _ Darling Swing Check Valves -

E

Gentlemen

., ':NRC Infobnation Notice No. 88-85, Reference (b), alerted licensees-to potential Tproblemsf relating to the failure of retaining block studs;on ' Anchor Darling check.

i valves and the possible generic implementations.T We evaluated the Information. Notice

through our' Operational
Assessment System and determined that two valves similar:to g4-
those describedcinf the Informatio'n-Notice:are' installed in.oursPrimary Component.

0 Cooling 7 Water System., ' They. were evaluatedt as'.not bbingisubject to thei. failure,

,f a,

lmechanismE(intergranular stress corrosion' cracking of the 410" studs in o' boric acid' environment)E described Jin the Information Notice. - We took no1further at. ion. in;

~

y*

' responseLto'the Information Notice and considered the issue resolved..

' Subsequently,/ RC Bulletin No. 89-02,LReference-(c), requested specific action.

~

N

' andtreporting cregarding Lthist issue.. Specifically, it was requestedi that. all

  • J i Alicensees disassemble and inspect-all safety-related Anchor Darling Model S350W' swing.

? t < - check. valves > supplied with internal retaining block studs 0f ASTM specification A193 4

Grade: B6 ' Type 41.0. SS.

Additionally, Lit.was requested --that licenseesL review the W

fldesignjof other safety-related check valves and similarly inspect those' of similar-Finally design and: material selection.

c,'q pq(i M 4 inspections:was. requested.

v p

,a m

,!W -

[

-CDF9060.LTR E>,

^ ng 3 Tp s'e;;

l$ y.

l IlN N 'iM

t 31aineYankee t

UNITED STATES NUCLEAR REGULATORY COMMISSION MN-90-64 Attention: Document Ct,ntrol Desk, Page Two Based on a review of plant records, Maine Yankee has no Anchor Darling Model

' S350W swing check valves installed in safety class applications'. Two Darling swing check' valves (PCC-44E &'446) are installed in a safety class application.with both a~ similar design and bolting material as the Model S350W Anchor Darling valve.

In addition, our-review concluded that twelve Velan swing check valves have a design similar to the problem Anchor Darling valve but utilize a different bolting material.

-Based on this difference in material, no further action was taken with respect to the Velan valves.

The-two Darling swing check valves were disassembled and inspected during the

-refueling outage which began April 7. 1990.

Neither valve was 'found to have any service induced cracking of the bolting. The existing bolting was replaced with Type 17-4PH material- (Specification A564-630-1100) as-recommended by the valve manufacturer.

Should you have any questions on this issue, please contact us.

Very truly yours, JY Charles D. Frizzle President WBD:SJJ c:

.Mr. Thomas T. Martin Mr. Eric J. Leeds Mr. Richard-J..Freudenberger STATE 0F MAINE Then personally appeared before me, Charles D. Frizzle, who being duly sworn did state that he'is President of Maine Yankee Atomic Power Company, that he. is duly authorized to execute and file the foregoing response.in the name and on behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the-best of his knowledge and belief, w

A m

Notary P%ic

BARBARA J PADtLVtNA

$NkhxOSbNN,17,96 UYcC r

CDF9060.LTR 1

y

_

Retrieved from "https://kanterella.com/w/index.php?title=ML20055E050&oldid=4487005"