ML19309F394

Forwards Summary of Westinghouse,Tva & NRC 800320 Meeting Re Control Rod Guide Tube Support Pins.Affidavit for Withholding & non-proprietary Version Encl

ML19309F394
Person / Time
Site:	Sequoyah
Issue date:	04/23/1980
From:	Anderson T WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP., WESTINGHOUSE ELECTRIC CORP.
To:	Pawlicki S Office of Nuclear Reactor Regulation
References
NS-TMA-2235, NUDOCS 8004290404
Download: ML19309F394 (46)

Text

'

i Y0 y0 042 g ()

Power Systems sex:es Nestinghouse Electric Corporation PinsuurpPemsytvaraa15230 April 23, 1980 NS-TMA-2235 Ref.: a. flS-TMA-2099, 6/11/79

b. ?!S-T'4A-2214, 3/14/80 Hr. Stefan S. Pawlicki, Chief Materials Enoineerino Branch Division of Syster:s Safety ~

Office of fluclear Reactor Reaulation U. S. fluclear Reculatory Commission 7920 florfolk Avenue Bethesda, Maryland 20014

Subject:

Summary of Westinchouse/TVA/ltRC Meetina on March 20, 1980 on Sequoyah Control Rod Guide Tube Support Pins Please find enclosed:

1. One (1) copy of "Sumary of Westinahouse/TVA/*lRC meeting on March 20, 1980 on Sequoyah Control Rod Guide Tube Support Pins" (Proprietary) as

~

Attachment A.

2. One (1) cooy of "Ficures for Backcround and Operatina Plant Experience and flew Support Pin Design for Sequoyah" as Attachment B

3. One (1) copy of "Viewgraphs for Microstructural Evaluation of Alloy Inconel X-750", as Attachment C.

.Also enclosed is: (1) copy of Acolication for Withholding, AW-80-20.

(2) Affidavit AW-77-47, Proprietary The purpose of this letter is to transmit a sumary of the oral presentations made by Westinchouse Water Reactor Division's cersonnel to the flRC Staff on March 20, 1980 on the subject centrol rod cuide tube support pin cracking.

The purpose of that meetino was to present availaole information to the Staff on oin cracking that has been observed in PWR plants operatirio 'in' a foreign country and the relationship of such exoerience to the safety and licensinc of the TVA Sequoyah nuclear plant. This infomation is being transmitted in accordance with your request made at the completion of the March 20, 1980 meeting. dooi U <,

- Reference a. submitted information on ein crackina as of June,1979 which stated Inat no cracks were found in foreicn olants in sucport pins which y_g_.

P had been sucolied by Westinchouse and concluded there was not a safety issue A in domestic coeratina plants. Reference b. also reccrted that the potential pt W for trn ea guide tube support pins due to stress :orrosien cracking was hpP ~

A00 W

t g gq3 MC - -. __

NS-TMA-2235 April 23,1980  !

Page 2 1 reportable to 'IRC, under Title 10CFR21, in that for UHI plants, breakage of a guide tube support ein could .ieopardize the ooeration of the associated control rod. Because Sequoyah is a UHI plant, and the Seouoyah support pins had received a metallurcical heat treatment similar to those pins that had sustained cracking in the foreion olant, Westinohouse recommended the replacement of the existing support pins with new suoport pins manu- )

factured using heat treatment orocesses that would provide extremely low susceptibility to stress corrosion cracking.

l Attachment A, and the associated figures and tables of Attachments B and C, l provide a summary of the technical information describing the foreign operating plant experience related to pin crackina, the information on the Seouoyah replacement pin design and the technical basis for~the selected heat treat-ment to minimize stress corrosion cracking.

It is our conclusion that with the installation in the Seouoyah plant of the newly designed suoport pins which have received the Westinghouse recom-mended solution anneal and single aging heat treatment, the potential for l guide tube misalignment, with the possible restriction of the associated i control rod movement, has been eliminated. We conclude that no unresolved safety cuestion exists with respect to the future performance of the guide I tube pins.

This submittal contains proprietary information of a foreign entity and of Westinghouse Electric Corporation . In conformance with the requirements of 10CFR2.790, as amended, of the Commission's reaulations, we are enclosing with this submittal, an acolication for withholding from public disclosure and an affidavit. The affidavit sets forth the basis on which the inform- l ation may be withheld from public disclosure by the Commission. Correspond-  ;

ente with respect to the affidavit or apolication for withholding should l reference AW-80-20 and should be addressed to R. A. Wiesemann, Manager'of Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, Pennsylvania 15230.

, Very truly yours, e I 2.LMwmwh T. M. Anderson, Manager Nuclear S.afety Department WSB:pj  !

Enclosure cc:NRC,M ivision or Project Management D. L. Lambert, TVA 1

m

@@3 Westinghouse Electric Corporation Power Systems Bcxass PittarctPerrsAaraa15230 April 23, 1980 AW-80-20 Mr. Stefan S. Pawlicki, Chief Materials Engineering Branch Division of Systems Safety Office of Nuclear Reactor Regulation U. S. Nuclear Reaulatory Commission 7920 Norfolk Avenue l Bethesda, Maryland 20014 l APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

SUBJECT:

Sequoyah Control Rod Guide Tube Support Pins - Summary of March 20, 1980 Meeting Between Westinghouse, Tennessee Valley Authority and NRC.

REF.: Westinghouse Letter No. NS-TMA-2235, Anderson to Pawlicki dated April 23, 1980. ,

Dear Mr. Pawlicki:

The proprietary material transmitted by the referenced letter supplements the proprietary material previously submitted concerning properties of fuel and core components materials. Further the affidavit submitted to justify the material previously submitted, AW-7Y-47, is equally applicable to this material. The information designated by the letter (g) is proprietary to a foreign entity.

• Accordingly, withholding the subject information from public disclosure is requested in accordance with the previously submitted proprietary affidavit, AW-77-47, dated October 25, 1977, a copy of which is attached.

Correspondence with respect to this application for withholding or the accompanyino affidavit should reference AW-80-20, and should be addressed to the undersigned.

Very truly yours, l

+hlx IKd4U l Robert A. Wiesemann, Manager ,

Regulatory and Legislative Affairs l

!ai l Attacnment l

l cc: 1. A. Cooke, Esq.

Jffice of the Execu(without attachment) tive Legal Director. NRC

~. ,

s 1!ESTII:GHOUSE PROPRIETARY AFFIDAVIT TO BE WITHHELD FRO.i PU3LIC DISCLOSURE e

e e W

o o

O e

' e e c' O e

7 .. o WESTI!!Gl!0USE PROPRIETARY CLASS 2 AW-77-47 AFFIDAVIT _

00 C'0 !WEALTil 0F PEi!i:SYLVA'!IA:

COU:lTY OF ALLEGHEf;Y:  ! t a Pefore me, the undersigned authority, personclly appeaf ed Robert A. Wiesem. ann, who being duly setorn acccrding to law, deposes and says that he is authorized to execute his Affidavit on behalf of Westinghouse Elt:tric Corporation ("l estinghouse")

and, that the averments of fa;t set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:

1'..itftLc lb '.lbl,'{ IR/G Rober t A.1,'iesenur.n, ::anager

~ ~

Licensing Progra.T.s Sworn to and subscribed before e t.his ./.7 day of A /u L., 197.7.

jf al.uw ,lu'aeI . .

f.otary Public e e l

l l

l l

til:STil:Gl!0USE PROPRIETARY C' LASS 2

. All-77-47 TJtE I!ATUPE OF HIE C0" PETIT!_0'l If; Tile f;Tf EAR Ci!Sl!!ESS Westinghouse's principal competitors in the nucler r steam supply business are Babcock & !!ilcox, Combustion Engineering, and General Elect) (c. The principal U. S. competitors in the nuclear fuel fabrication business are Dabcock & !!ilcox, Cc:du:ticn Engineering, Exxon, ar.d General Liectric.

With the exception of General Electric, these corrpetitors are acw entries in the business with substantially smaller investments in technology.

!!cstinghouse also has cc:rpetition frca foreign fabricators. This c.a.i-petition can drastically affect our ability to obtain contracts in .he international market. Specific competitors inclu.'e ASEA-ATO:4 (Sweden),

Kraftwerk AEG (Germany), Framatome (France), 0:!FL (Great Britain), Enusa (Spain), Mitsubishi (Japan), and Fabrica::icne INcleari (Italy).

Both the nuclear steam supply and the nuclear fuel fabrication businesses involve high technology, and competition is on the basis of that high technology rather than on price. Only if. competition continues based on technology will Westinghouse be able to recover its substantial invest-ments in technology and product development.

EFFECT OF RELEASE OF !! FORIMTION ON NESTI: GHOUSE COI PETITIVE POSITIO t If, as a natter of general practice, cost or price information or infor-mation about the basis on which !!cstinghouse makes its business judge-ment's were made publicly available, it would have the general effect of altering the nature of competition from a technology base to a price .

base. This tould change the entire coc.plexion of the business and drive it toward a low investment-low technology development business. Under ,

such circumstances, those in the business with heavy unrecovered invest-cents in technology such as Westinghouse would have difficulty competing successfully with those who have made relatively small investments since D *

• lD D '3' Y h nJAA .

r-WESTII:CIIOUSE PROPRIETARY Cl. ASS 2 All-77-47 business could tend to go to the lowest qualified bidder. The general public would also suffer "a that they would be deprived of the benefits of technological developr:ents that would most likely far exceed any short-term benefits derived frca lower prices. Likewise, a general practice of making publicly available information obtained from invest-ments in technology would enable competitors to benefit without having to take comr.ensurate investments. This would stifle the incentive for  ;

further invest.7ents in technology and drive the business to price-based competition instead of competiticn on the basis,0f technology with the same end results as in the case of disclosure of cost or price infor-mation. . .

Wi!AT tlESTIt!GHOUSE SEEKS TO PP.OTECT Westinghouse seeks to protect its abili'ty to recover its investments in:

(1) Basic data resulting from research and development. -

~

- '(2) Analytical methods and models.

(3) Details of our, designs including margins, tolerances, etc.

(4) The knowledge of what data to present and how to present the ,

data to satisfy tiRC licensing requirements. fl0TE: In the -

current licensing environment, the capability to obtain ,

licensing approval has become very important in the market-place.

p

)

fh '

. 33G Gig '

1

• e. - me w,em . + e ew , .. e ** em e-- ,e . e, w es .

• o .

WESTIRG!!00".E PROP.710 A!n' CLF.SS 2 AW-77-47 The above identificd information is of considerabl. cc.mercial advantage

.tc the coepetitors of Westinghouse to the extent t'ut it climinates the need for sitailar investments in technology.

RELATIOl; SHIP GF I!:F02:'.iTI,0.*: SC'J7HT TO CE WITHHELD Tj'.C: PUCLIC DISCLOSURE TO WIMT IS SOUGHT TO BE PROTECTE'O II;FORiGT,1,0;! SOUGHT TO CE UITHi: eld The information sought to to '<ithheld in this repcrt includes conclusions regarding thermal, physical, chemical and mccPanical properties of fuel and ccre component matcrials based upon Westing".our.e experiment:1 data and an extensive literafGre survey and data reduction program. The ,

report also contains Westir.ghotse material specifications. The release '

of this information would retuit in the following competitor benefits:

POTEliTIAL AD'!A:!TAGES TO COMPETITORS

1. It would allow competitors to verify their material propc-ty design values by mere reference to the Westinghouse Report without having to expend the time, resources and funding otherwise necessary.

2. For the materials listed in the report, the data presented would cnabic competitors to determir.e to a close approximation soma of the final heat treatments , processes, densitics , etc. , used by Westinghouse.

3. Krowledge of the materials prcperties presented, or the implied .

specifications may permit competitors to either relax their material specifications ,,or reduce design margins, either of which circum-stances could lead to saics advantages detricental to the Westinghouse marketing position.

, 4 ,

5694

i , }!ESTil!Gl!OUSE PROPRIETARY C'. ASS 2 N! A 7 IllVESTf4EliT BY WESTII G!iOUSE IN WHAT IS SOUGHT TO BE PROTECTED It is estimated that fcur to five man-years of engincering and one man-year of technician effcrt, amounting to apprcximately $500,000 was expended to perform the literature surscy, obtain lestinghouse experi-mental data, perform detailed tr.alysis of selected data and to derive acceptable design c:;u_tiens and values.

Competitors could cbtain the equivalent information, with difficulty, by investin0 a similar sum of money and provided ,they had the appropriate resources available and the requisite experience.

$ 1EfiTIAL

[ llARi4 TO WESTIIGHOUSE .

Ele believe there is a likelihood of substantial harm to the ccapetitive position of Westinghouse if the information sought to be withheld is publicly discl'osed, v;hich could result in a icss of revenue to ;-lesting-house of approximately $10,E00,000 in potential first-core and $7,000,000

- in potential reload fuel business.

Further the deponent sayeth not.

D -

9 w 't d

l ATTACHMENT A

SUMMARY

OF WESTINGHOUSE /TVA/NRC MEETING ON 3/20/80 ON SEQUOYAH CONTROL R0D GUIDE TUBE SUPPORT PINS I

1 I. Background and Operating Plant Exoerience  !

Guide tube support pins align the lower guide tube to the upper core plate. ,

(Figures 1, 2, 3, 4) There are two support pins per guide tube. (Figures '

5,6) This same basic design has been used in all Westinghouse PWR plants since Southern California Edison (SCE). The material is Inconel X-750, heat treated and age hardened.

- -(g)

-~(g)

In the unlikely event that a pin leaf were to break off, there may be some small potential for a loose part to adversely affect control rod operation.

The possibility of this is remote because of the torturous path the loose part would have to traverse plus the preferential orientation and location

, -, that would be required. (Figures 9 and 10) If the succort pins were completely broken at the shank to shoulder juncture, the loose part is too large to

. enter any clearance space to adversely affect control rod operation.

For an Upper Head Injection (UHI) plant, such as Sequoyah, if the guide tube support pin should break in the present design, the guide tube align-

. ment with the support plate would not be maintained under all conditions, because of the clearance between the bottom of the guide tube flange and .

. the upper core plate. (Figure 11) Such guide tube misalignmen could jeopardize the operation of the associated control rod. It was noted that for non-UHI plants, the clearance between the guide tube flange and upper core plate is smaller, and misalignment could not occur in the event of a broken support pin.

II. New Support Pin Design for Seouovah To eliminate the potential for guide tube-upper core plate misalignment, a new support pin has been designed for replacement of the original pins in the Sequoyah plant. The new design includes tne following features :

(a.c) mm em

(a,c)

- (a,c) 11 1. Microstructural Evaluation of Alloy Inconel X-750 (a)

(g) t a

1

.- 79) -

t 1

1

~

l

_ 1 __?.:~ _ _

(a)

The results of both the SCC tests in primary coolant and pure water, and the microstructural evaluations indicated that a high temperature heat treatment (>1800*F) would provide the desired microstructure. Because i

.o j 1

• 3, (a,-

. ~l Testing of full size pins in both primary ecolant and pure water did not result in any failures (cracking). (Viewgraph15) -- ( a , ;

I

~

~

IV. Safety Evaluation and Cenclusiens

- (a,c t

2. The replacement pins are of a new mechanical design, such that even if failure occurrec in the shank or leaf of the pin, the alignment of the guide tube / upper core plate is not lost for all conditions that require centrol red operation. ,

3. The potential for a 1cose part resulting frem a broken pin leaf to adversely affect centrol red oceration is extremely remote. ;eeanage of a pin leaf due to stress corrosion cracking is highly unlikely

- because of the heat treatment process received by the replacament pins.

Even if such a 1cose part was created, and transported to a locatien so as to interfere with control red coveMent, such circumstance is

. not an unresolved safety cuestion. Accicent analyses have rnown that the reactor can be safely snutdown with one control ro1 stuck ~

in the fully withdrawn position.

O G

a t

mm 4

e.

_ _ _ _ _ ___ _ _ . . _ _ _ . . . _ . _ - . . ~ _ - ._ _ - _ . . _ - - . . . _ _ _ _ . - - -

a 4

i i

i i

4

ATTACHMENT B 4

1 1

i i

i Figures for Background and Operating Plant Experience and

! New Support Pin Design for Sequoyah.

b l

d i

i i

I i

1 i

i j

l

^

i i i i

if e

l l

l s

l i i 1

i i

r

$ h 6

I

b. ah,..--n!!,

,. I g -

Iuv_ g amau2.

tecaten or

'pm}gylfilIW,,

y .r5gf p u??a culos imE V

h .

i M nrm n --

1 g 9 (t $, kNT T. .

J$li 9p i b e

%,%id.Ln.&,

%  % 9%h p

k.,:s.

4; x. ~ipe ..

... a, c, r y

I;;n .z :.. 1,M : ):. l6 T..

p .U j d!!;;;' .s7p. :,

n. . ,

. ~ , , . .

i r.

y ;}3.,7rrp}- -(

[ p}.-

r s :rr E }-

,+'

lk f

=

4

- [-}- - M p g 0 Cl,2 09, s

==

- l'h f O . .- Ls

g. m . , u.. .G.. - .,. . : .. L o < . . e.. g . gg warL C '.;df's::O O! 'D:@:.;:.. Q ' Ch ..'.- 1 -

N 3./;h:

c$6.ftY.%;.%,,\,..O,.

'm , .w i?.'.<; , ! .'r.9 o O.

F s' ).. .p . : , . d*Nj;  % .. ,:; w. .~ y,.c:o. 7. t.,.,.e ,.g h'. . . S ..

, ,.c.!. u e: ..

.O  ;, . <.,

w w...o p. s.n ..w... . u ,,.:.s.,~ s f:7-LCt.ATlCn C7 JVi w LCL'I2 C'JlC2 ,

~-C:Hs yiQg@F*.

,12

u. [ ' jGy .q. l5 .; 9 +3 3; : w e O . t %a;;;Lht:';'?:'rE.3 :?2?! ! O f t .T.-l-(lt'a;'d -

• g g e g c,y xt- - ~

r x C py s "

• ~

.. yEh...y 01 - s O W';;n'.=,=,.u:.'..+..@~.'M t. .* . -

g

'a"-. . ,. !

O. ..

Cr , , ;: :7.v.; ?g/ O *

' iG,"! O .* O .  ;

. d'l {. I ' .,,di rai9 O ,

M g;.% Wyw? D; / ,; .~. sp

• O O ' w.I .e ' g ..

stand.:bj9,dN1 tt-N,.pi:.- O )O g 0 Cl99 00 r

G m..... m:..s m__ -

. ,. t b.y.,.2.w.r..s-m. ,p. w.. . ..g

g. . -

..h,.....

[ gn im igr w n niniu, d _i.i!

m. k'7. d . .

i p: _E m_

d ...

Mkr.-: - !=sexN - -

s t! f. il ti 9

n u

t r * .- s

{

f.] & l A:&j .

+ If '

1I -

1 1

REACTC2 VESSEL GENE :AL ASSEM5LY l Figure 1

l I

l l

l 1

FLEXURES TK JW4

,wi 9a%

.a.

l l '\

, a ,'

s -

.Y p o 's n

• =C 46 sai l

eav -

As-h ka!

db.h). 1 SUPPORT PI!is

. GUIDE TUCE ASS [i.CLY Figure 2 ,

abee

• l

• ~ ~ ~

p OO OO D E T.

N 6 f///// / A , / ; .i L.)

-- k[ /w Whq. '

f. . .

.e o- ..

w l

,g,

.e

.e y _._

~

1 .

l - -

=

e ai; t ;g

. E['**. -_.

.? E .

l- {l

. i =~

j e .! 11 Si ..

.! E* .. . .. M "

gj j 8 4

m

'_ g 1 . -

- ., 2

- ~ f _'

i

~ . ., . . s>

I -G

. y-

- ' .* 6 J ,p

'.I q

• C W

uo ,

i fvl g

~

,w.) p- . t

'- -i i g H I i , . _,

• 1

-, -l }

a u

,.a .

m . c  ;~-

a -

g l .,-

, ^. i 2=s._ _- .. _.m et,.i

,~

"i . -

p m._;

4, y; i  :- .:

.: 3 .i .

.; o j , i[Ip - .

t .. .. .. ..  ;: ;y ,

/

p.

.- ybe< / / / .s s sM -

n i

w . .I i

-* 11 gt/ .

1 m- m f

s gI e -

Af

// n

'////// .

• • . . < L }

. . . . . . . . .- . .. . . . . .S

• 9 v-9 9\gM

(a.C) l Q g g i ..

9 l  %

\ _ ..--

g %

.g. - -

g .

Soo (r.S.zi] C'^*E "

i 147 (as.si) .

O *c*1A.cccolooo:J ro. coos to.o? 2j duideT4be$pportPin M ~'

h *T 'T AWM .

• F1gure,4 l g

4 ,

e e

-- i - - , , - - w= - w= m - ' =

u w "

"6"

l

\

l (8,C) l 1

I

)

1

\

i l

1

.jl

. SUPPORT PIN ASSE!"JLY !!! LOUER CUIOE TUDE (15 x15) Gulot Tust

• Figure 5 0

GUIDE TUBE SUPPORT PINS

SUMMARY

- _(9)

- a

~

(9)

(9)

. . . -(g) l

- WESTINGHOUSE SUPPLIED PINS IN 1 OUT OF 4 PLANTS WERE CRACKED. i 1

l l

- NO BROKEN PINS IN DOMESTIC PLANTS BASED ON VISUAL EXAMINATION.

l l

l Figure 7 i .

h 4 WESTINGH,0USE NUCLEAR EQUIP!JENT CIVISIONS

'a ,,, -

PdesME 6 5 , w TsuG s Gass WA er sasweaav .ba r.

m _4.c,

(-,y ( .- -

r _

g

• lf jg ..

{ g i ,

s l'

4. ..

n' '

i_

g, s  :. -

s  :

(

e -i .

L v l .h l

Ol ,

IFG\7n{h

.~

~ ~

l f.( l \llt

• / - -(a,C),

~ ~ ~ ~ ' ~~

88 -

4-(a6C)

_8,C)1

( }

I< .

qu-. -

\

/ <. ,-l. . g ',.' j c'.  %,4.' < *

} .(

l T _r3 I

--N' -M -.-%-MOl ,J,

- - Pin Orientation (Typical)

s. ./'.'

< '7 'g ( #)3

. (17 x 17 Guide Tube)

O Figure 6

.- sk.y s. ,e '

_7 a -

r-- ---

i 1- -

O e

S

. ** g v

[ l s  !

Oe l

E 1 0 1 m

b u

W Ch.

M E

E E eC =

sh. O. g CD

' Cn H r=4 c:

E C *

• Q. _

Ch. ac

= '-] a: e M < &

W z C E

4 W ,

J CC

& 2 F

s g

. .W W W C3 4 -

e:  ::3 W c I A

O IA.

• C M

D

. b

• M l

'l

• i 1

. i 9

l e

l b

t -

6\ l gD 9 ,

~

g f f . .A I A~ t -

(a\ m\ l

.\ .[

g e

i l

f?..IN}A D 'i ( #

I I:

we I O lli 6li i

yc.3.x

,,,e

.% Whip.A E. LC C A""1 ON 4 ll OF LOCGE*O

'd LEAS P AG. T".

Y l N .

1 a  : e -

I Q .,

'cl / l

% l

\ l u _ viv

,fi ag l ] cofot. "tua1ii -

,G' m # C'

'N g i m/- . I e

s j / y u

vlv

~

L 1

uff])

"e '

i . 1  !.

lI i, pl.

OppE7 c c C E. Pt.A."T E

~E..

. /

-Q4di .. . .. cn -

M //s3Lt* V <;q v / / n \ ,

r ' -

ag ,, met %M <

kF'ER To %r l l F6GuCE /d 7 C2 A v t=' s. o C "t:C.cWEw I YbR Suppoc r giu/C.oc.E pTE LEkF PAfD' mi s. .s. L

/}* \ Route of Pin Leaf in the Event of Pin Fracture

( Figure 9

-v g I

9 l

l l

L .

a l

e@ s dM pM F

l S*// W ' f,

• /g; e w

- . =- esa (6AI

~ u (a,C) ir

~

Fersera 6 .

__ / $ [ u WF M _

~

./ ll -cd '

, ' Y *** h e ,i A. ll r 3 t y -

,r.u n f =}iJJf ., i i

gn

/

• jj \ [/#d

, Interface. Detail of Guide Tube.

. . tipper Core Plate end Fuel i

. Figure 10 l

l I

e S

i N

e==

O C

m M

ee ame O

m M

==

9 m

O

.R.

M O

2 9

• F3 M

m M

M 2

H d e.

US e

3 O

==

N oo -

o C.

.Z.

N P

2 w

W9 l .  ;

n O

. w

'"w-= " = - - , -- u---- - - - .,, , _ , , _ , , ,, ,, ,

(a,c) 1 i

Figure 12 Modified Support ?in Sequoyah

ATTACHMENT C l

i I

1 l

Viewgraphs for Microstructural Evaluation of Alloy l

Inconel X-750 l d

e e

. i mr

LIST OF VIEWGRAPHS

1. Environmental Exposures

2. Specimens

3. Schematic of Semi-Static Autoclave System for SCC Tests

4. Inconel X-750 Starting Materials for SCC Test Program

5. Composition (W/0) of Inconel X-750 SCC Test Materials

6. SCC Incidence: Pin Mat ri 1 U-Bends -[ _ .

7. SCC Incidence: Pi M terial U-Bends - RCS Exposures,[

8. SCC Incidence: Pin Material U ends -[

~

9. SCC Incidence: Stock U-Bends -[ . _

. ](9)

~ '

10. SCC Incidence: Stock U-Bends - RCS Exposures,[ ~ ~ ~ ](9) 650*F (343*C)

- - ~~

11. SCC Incidence: Stock.U-fs -[ _ .

12. Effect of Pre-Age Thermal Treatment on SCC of Stock U-Bends -[ ~ .]9

.13. Effect of Pre-Age Thermal Treatment on Stock U-Bends -[

. .]9

~ ~

14. SCC Incidence: Stock & Pin U g}ds-[ _ .

15. Full Size Torqued Pins in SCC Tests ~

16. Analyses of Graphite-Base Lubricants Used On Torqued Pins '

In SCC Tests 8

l l .

l l __

FOOTNOTES FOR VIEWGRAPHS e FOOTNOTES FOR VIEWGRAPH 6 (a)

Note 1 -

Note 2 -

Note 3 -

8 FOOTNOTES FOR VIEWGRAPH 7

. Note 1 - Further identification appears in Viewgraph 4.

Note 2 - AR = As Received (See Viewgraph 4) (g) we '"'

m ,. ee a 69 9

9 om " _ _ ,

e FOOTNOTES FOR VIEWGRAPHS

. 2 8 FOOTNOTES FOR VIE'i'.RAPH 9 Note 1 - Further identification appears in Viewgraph 4.

Note 2 - AR = As Received (See Viewgraph 4) -

(9)

(9) 3 Note 3 - SCC * =[" ,

Note 4 -[. ,

.]I9) 9 FOOTNOTES FOR VIE'JGRAPHl0 (9)

Note 1 -

_ .. .e .e -

, ~

m

$ o l

-, . m yr .,*

, mm-r._ a..- - -- - -a - _ -- .

e*e e

9 e

VIEWGRAPH No. 1 ENVIRONMENTAL EXPOSURES

~

- (9)

I I

f

~~

O e

4 I

l I

l l - -,

e*

' I 8 g *

• I VIEWGRAPH NO. 2

$PECIMENS M - - -

M O

e

~ -

M M

e. '

j a .

1 s

4 1

i l

-a w.-

I i

e+

1 r -- --- - -

M --'

way. savsn,a I  !

i t

t 1 -

' E

-Schematic of semi-static autoclave system for SCC tests.

F

=

VIEWGRAPH NO. 3 d

2 I

D i

VIEWGRAPH NO. 4 INCONEL X75b STARTING MATERIALS FOR SCC TEST PROGRAM Haterial Heat No. or Source (A-D) Thermal Treatment in As-Received Condition i

Type Identification & Producer (SourceInformation ~

~

I

[

e i

,\ ,-

L I g

V e

4 O

O e

k.W.

W W

>=

r M

W

>=

U .

U M

' O an N

M

.J W

Z SD O U -

. 2 O M E

2 Lt.

O. C .

g Og C

N w

> M Z

O w

-W e

Y O

a.

. u5 ,

I e

e I

I e

M S

e

• W e aeeeeWSWe9 W ee esame eeee. , ,

-7 _

w gue'm i

VIEWGRAPH NO. 6 STRESS-CORROSION CRACKING (SCC) INCIDENCE: PIN MATERIAL U-BENDS f

INCONEL X-750 HEAT CONDITION SAMPLE RESULT EXPOSURE PREVIOUS INSPECTIONS

~

PIN (Note 1) (Note 2) NUMBER (Note 3) (Days) (Days)

A B

E F

J K

4 4

L M

Q R ,

h T

85

.o

. . m 9

..  ?

\f19 ==e t p ng ( (

VIEWGRAPd* sNO. 7 , . -

• ,,493 g .* g e -** J t;e - ga  ?

.  !; ' ' 4 STRESS-CORROSION CRACKING (SCC) INCIDENCE: PIN MATERIAL U-BENDS D .

](a)

'INCONEL X-750 HEAT CONDITION SAMPLE EXPOSURE PREVIOUS INSPECTIONS (Note 2) NUMBER RESULT (Days) (Days) (

} PIN (Note 1) ,

[ A 1

B -

e E

F 1

L M

a S

> T ,p

~

85 -

l

'I . .. ,. .

~

VIEWGRAPil NO. 8 .

STRESS-CORROSION CRACKING INCIDENCE (SCC): PIN MATERIAL U-BENDS,9)

{ .

INCONEL X-750 .

. 's HEAT CONDITION SAMPLE EXPOSURE PREVIOUS INSPECTIONS PIN (Note 1) (Note 2) NUM11ER RESULT (Days) (Days)

~

I I g

B E

F J

K L

H i Q ,

S.

T 85' i

I I 2

w 4

! 4 VIEWGRAPH NO. 9 -

l STRESS-CORROSIONCRACkiNC(SCC) INCIDENCE: STOCK U-BENDS

~

C l [ J9) .

INCONEL X-750 SAMPLE EXPOSURE PREVIOUS INSPECTIONS ANNEALING ACE (Days)

NUMBER RESULT (Days)

TtMP (Note 1) (Note 2) IIEAT .. _ _ _ _

__ __ .- y y

O e

= = _ _ _ _ _-

j3 __

t VIEWGRAPH NO. 10 STRESS-CORROSION CRACKING (SCC) INCIDENCE: STOCK U-B RCSEXPOSURES(Li,B,ll)'[ 2

'] -

INCONEL X-750 SAMPLE EXPOSURE PREVIOUS INSPECTIONS ANNEALING ACE s

NUMllER RESULT (Days) (Days) l TEMP (Note 1) (Note 2) HEAT I

• ! I 1

f -

!7 l

- - - _ _ _ - - - __- - - - - _ _ _ _ _ ' _ _ _ _ _ - _- _= __.-.-

_ _ _ _ __ _=_._.=__ _____ __ _ _ _ _ _- _

i.i.i,...,,,,. .

, VIEWCRAPH NO. 11 i - '

l .. -~,.. , , ,, , ,

l STOCK U-BENDS '

STR?.SS-CORRO$10N CRACKING (SCC) INCIDENCE:

.i ^

[

INCONEL X-750 . ....

t i 1

ACE ' SAMPLE ,,,' EXPOSURE PREVIOUS INSPECTIONS ~

ANNEALING RESULT (Days) (Days)

(Note 2) HEAT NUMBER TDiP (Note 1)

I I

i h

I, I

i 6 i

I' I

1 I *

^

o v

VIEWGRAPH f40.12

. EFFECT OF PRE-AGE THERMAL TREATMEllT Gil SCC OF STOCK U-Bell 0S*

SINGLE AGE Mumber of U's Failed /fturber of U's Tested .

Heat I fjegluge-fta!_P,gs digiu[iEYd29 I9$$1I9)

T re

_.em er _

~-

l

- l l

l eumas .

• Various exposure perieds in tests (see Viewgraphs 9 and 10) l

. i . ..

t VIEWGRAPH NO. 13 EFFECT OF PRE-AGE THERMAL TREATMEt(T Off SCC OF STOCK U-BENDS *

~

. DOUBLE AGE Pre-Age Numbar of U's FailedR u-ber of O's Tested Heat i Temperature , , ,

(g)

O Various_ exposure periods in tests (see Viewgraphs 9 and 10) e

. 1

j VIEWGRAPH Np.,14,, , ,

; .l l f ,. .

l .

STOCK & PIN U-BErlDS_ '

STRESS-CORROS10tl CRACKIflG (SCC) IllCIDEllCE: .. .. (g) ,

I SAMPLE EXPOSJRE (HOURS) i AGE IIEAT RES T ( lote 2)

AtitlEALING  : litJimER ,

s TEMP.(1 HR) (flote 1) (Table 1) l I I

9 f

1 I .

i I

i

, i i

1 . .

e.

VIEWGRAPil NO. 14 (Continu:d)

STRESS-CORROSION CRACKillG (SCC) IllCIDENCE: STOCK & PJilgg-BEllDS SAMPLE EXPOSURE (ll00RS)

AtillEALIllG AGE IIEAT RESUt.T tiUttBER (flote 2) .

TEt1P.(1IIR) (flote1) . (Table 1) 1 .

l t

1 I I

a 1

? -

a e.

u cn umr ., . . . . . ,

FULL-SIZE TORQUED PItls IN SCC TESTS * .

(/ = One Pin per Test)

. - (9)

Pin Torque (Table 1) See Below A 1  !

E 2 1

F 2 l I 3 l

J 1 l K 2

. ~ Torque Values (acolied with torcue wrench):  ;~ -

-(a,c,g)

I,1=  ; .-

l 2= '

3=

• The torque values and the special stressing a;:paratus (nuts, blocks, -

and caps) were furnished by Westingnouse Pensacola. ., , , ,

1 e

m

.l l

VIEWGRAPH NO. 16 ANALYSES OF GRAPP.ITE-BASE LUBRICA!!TS USED Ofl TORQUEB PIfS Ill SCC TESTS j (EmissionSpectroscopy; Values = 2 3x Esticates Shown)

I i

Concentration (ccm) (g)

Element en A-f l

li I

O i

f I <

I i

. i . )

1 l

. l 1

.__ l 1

__ y _