ML20076H396

Visual Exam Results of Segment 2,Fort St Vrain Fuel Elements 1-2415,1-0172,2-2693,1-0108 & 5-0801

ML20076H396
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/04/1983
From:	Kettever J GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20076H347	List: A16829, NDE of 54 Fuel & Reflector Elements from Fort St Vrain Core Segment 2 ML20076H345 ML20076H356 ML20076H396
References
906577, PED-81-2200, NUDOCS 8306160560
Download: ML20076H396 (21)

Text

r ok 1485Mtv. tilson (PED-81-2200)

ISSUE

SUMMARY

TITLE: VISUAL EXAMINATION RESULTS OF SEGMENT 2 FSV OR&D 5

APPROVAL LEVEL FUEL ELEMENTS 1-2415, 1-0172, 2-2693, 1-0108 G DV & S AND 5-0801 O DESIGN DISCIPLINE SYSTEM 00C. TYPE PROJECT DOCUMENT NO.

ISSUE N0JLTR.

N 18 RTE 6400 906577

/2 QUALITY ASSURANCE LEVEL i SAFETY CLASSIFICATION SEISMIC CATEGORY ELECT RICAL CLASSIFICATION QAL 1 SC-1 CAT 1 NA k

PPROVAL PREPARED ISSUE ISSUE DATE C

BY DESCRIPTION ENGINEERING OA PROJECT g

/1 J.W.

W..y fel.

rd Initial issue from origi-

@T 0 7199P-Ketterer

%d I

nating project No.

.ll).OTMt49-3t

.p A R.F. TURNER 6415 020 204 StnsIfeW.

W.A.

MON

's.-

u.s 47 2..

Int rface Ass 12rance g

W.I.3., nSch M b

/2 APR 0 4 M S J.W.

ttycoed Minor revisions to text Ketterer 0<N-R.

. Turner of original 004.

t nsfield 4

g' 4 f/53 W

On u -s - t 3 D.J. Kowal w%

n e ss12rance CONTINUE ISSUE

SUMMARY

ON GA FO'RM 1485-1'. ~

'/////3 NEXT INDENTURED DOCUMENTS 906553 REV SH REV SH 29 30 31 32 33 34' 35 36 37 38 39' 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55,56 REV SH 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 8306160560 830602 DR ADOCK 05000 PAGE 1 0F 21

GA Technologies Inc.

G A-14&4 (REV.10/82)

TITLE:

RESULTS OF VISUAL EIAMINATION OF FSV FUEL ELEMENTS S.N. 1-2415,

_p 1-0172, 2-2693, 1-0108, 5-0801 Document No.

906577 Issue /2 TABLE OF CONTENTS E*18 1.

INTRODUCTION AND

SUMMARY

4 2.

PROCEDURE.........................................

4 2.1 Documentation................................

5 2.2 Exceptions to Specification..................

5 3.

VISUAL EIAMINATION RESULTS........................

6 4l 3.1 FSV Fuel Element S/N 1-2415..................

6 E

3.2 FSV Fuel Element S/N 1-0172..................

10 5

3.3 FSV Fuel Element S/N 5-0801..................

12 5

3.4 FSV Fuel Element S/N 1-0108..................

12 3.5 FSV Fuel Element S/N 2-2693..................

15 7

3.6 Stacking Demonstration on Blocks 1-2415 and g

1-0172.......................................

15 2

3.7 Dowel and Socket Dimensions..................

19 3.8 General Features.............................

19 e

i 4.

REFERENCES........................................

20 2m LISI 0F TABLE

.5 5

1.

Postirradiation Measurements on Two FSV Fuel Ele-ments.............................................

20

-}

LIST OF FIGURES

.5 E

1.

Composite photo of crack at top of block 1-2415...

7 9

E 2.

Crack in element 1-2415...........................

8 z

3.

Bottom views of crack in element 1-2415...........

9 4.

Crack in element 1-0172...........................

11 5.

Damage observed on two dowel sockets nearest E face on bottom of element 2-2693..................

13 6.

Control element 2-2693............................

14 l

7.

Stacking demonstration with block 1-2415 (top) and 1-0172 (botton) in each photo.....................

16 Page 2

i G A-1484 (REV.10/82)

+

RESULTS OF VISUAL EIAMINATION OF FSV FUEL ELEMENTS S.N. 1-2415, 3-0172, 2-2693, 1-0108, 5-0801 Document No.

I8'"' ' / 2 06577 8.

Stacking demonstration of blocks 1-2415 (top) and 1-0172 (botton) at the B faces showing cracks in both b1ocks.......................................

17 9.

Damage at the top corners of two of the five blocks examined which occurred when the blocks were removed from the FSV shipping cask........................

18

10. Composite photo of C face of element 1-0108 showing vertical scratch seen on all elements examined....

21 4

e 52 22 s?

E e

.b C

E2 0

.e

-5

.5 E

.e 5

5 l

l l

l 1

-o-Pge 3

GA Technologies Inc.

G A-1484 (REV.10/82)

TITLE:

RESULTS OF VISUAL EIAMINATION OF FSV FUEL ELEMENTS S.N. 1-2415, 1-0172, 2-2693, 1-0108, 5-0801 Document No.

906577 Issue /2 1.

INTRODUCI' ION AND

SUMMARY

Five Fort St. Vrain (FSV) fuel elements removed during Segment 2 refuel-ing were shipped from Colorado to General Atomic's (GA) hot cell facility for detailed examination.

One of the elements (1-2415) was discovered to have a cracked web during routine surveillance of 54 fuel and reflector elements at

/2 FSV in April 1982 (Ref. 1).

Another (1-0172) was suspected, based upon later

/2 examination at GA of video tapes made during the surveillance program, of also

/2 having a cracked web.

The presence of this crack was confirmed upon visual

/2 examination of the element in the GA hot cell. Of the other three blocks sent to GA, one (2-2693) was a typical control block, one (1-0108) was from a core position adjacent to element 1-2415, and the last (5-0801) was an element not

=

is f

previously examined but identified by design codes as one of the highest

&g stressed blocks in Segment 2 of the FSV core, fi e

j This report presents the results of the detailed visual examination on the five elements carried out in July 1982 at GA.

The cracked webs in ele-

]

ments 1-2415 and 1-0172 were carefully scrutinized and a stacking demonstra-tion revealed no abnormal interference between the dowels and sockets of these 2

8 two blocks when stacked in their in-core positions. The top, bottom, and side

.t*5 surfaces of all five blocks were visually inspected and photographed.

No e

}

other cracks or damage attributed to the in-pile operation were seen on these blocks. The destructive examination is planned for fiscal year 1983.

Ez

/2 It should be noted that in Figures 1, 2a, 3d, 4, and 8 of this report the

/2 appearance of the cracks has been artificially enhanced. Without enhancement,

/2 the cracks would be difficult to see in the final figure reproductions.

The

/2 resultant figures closely resemble the actual appearance of the cracks.

2.

PROCEDURE A detailed Test Specification (Ref. 2) describing all phases of the visual inspection was adhered to during this work.

Other than minor devia-

/2 tions from the Test Specification (see Para.

2.2),

all examinations were completed and documented as specified.

+

l Page l

is

GA Technologies Inc.

GA-1484 UlEV.10/82)

+

RESULTS OF VISUAL EXAMINATION OF FSV FUEL ELEMENTS S.N.1-2415, 1-0172. 2-2693, 1-0108, 5-0801 Document No.

Issue 906577

/2 2.1 Documentation All observations, measurements and other notes made during the visual inspection were recorded in GA Lab Notebook No. 6637. All photographs taken are filed in the Core Materials Master Photo File in either print or negative form.

In addition, prints of every photo are affixed in Notebook No. 6637 for viewing.

/2 2.2 Exceptions to Test Specification R

E f

/2 Several minor deviations from the Test Specification occurred and are listed herein:

.c 5.

E f

Spec.

jj Exception Section Justification / Resolution E

Q 1.

Visual exam, sequence dif-2.4 Blocks inspected in the order di forent from that specified.

that they were stacked in the

.5 shipping cask because of time and hot cell window burnout f

constraints; order of inspec-E[i tion by block number was:

1-2415, 1-0172, 5-0801, 1-0108,

.s 2-2693.

E j

2.

Operator did not keep daily 2.5 Operator reviewed and signed 5

notes.

off on logbook entries record-2 ed by cognizant engineer.

3.

Standard line card widths 2.7 Limitations in available pen different from that speci-sizesp lines provided were fled.

Judged adequate by Q.A. re-presentative. Line widths in inches on cards used during the visual exam were:

.008,

.013,.014,.017, and.031 on card No. 4,.007,.013,.015,

.018, and.032 on card No. 1.

4.

Individual storage cans for 3.4 Purge cans not available during each element not used, time of visual exam.

a 4>

Page 5

GA Technologies Inc.

G A-1484 (REV.10/82) j TITLE:

RESULTS OF VISUAL EIAMINATION OF FSV FUEL ELEMENTS S.N.1-2415, 1-0172, 2-2693, 1-0108, 5-0801 Document No.

I" 906577

/2 3.

VISUAL EIAMINATION RESULTS Each element was inspected in detail for cracks, blemishes, stains and other markings, and any abnormal features using the in-cell Ko11morgen peris-cope.

Selected areas were photographed through the Ko11morgen and Polaroid prints were made, especially when closeups of certain features were desired.

All end and side surfaces of each block were photographed in composite form through the cell window using a tripod-mounted 35 mm single lens reflex camera.

The visual observations on each block are given separately here fol-f

/2 loved by general observations, special procedures, and measurements. Through-

/2 out this report, references to the different fuel element surfaces are as g

/2 follows:

the top of the block is that end with alignment dowels, the bottom j

/2 is the ena with dowel sockets, and the side faces are identified thusly E"

E 2'.

TOP END VIEW OF FUEL BLOCK E

5e

@ dowels @

.5 D

F E

fuel handling hole f

/2

.5 E

C B dowel A

il e

B 3.1 FSV Fuel Element S/N 1-2415 The crack in this block, which extends down the entire length of the B face, was scrutinized closely in this visual exam.

Figure 1 shows part of a composite photo of the crack with the coolant hole and B dowel visible at the Page 6

906577/2 I

v g.,.

~

m !.

I 4 -

e a

.....+.-7 ab.

.m,1 k,.:'%g..I ', *' ; T -

• y, +

. r '.:.

v ?

v s

a

~3-l' Composite photo

~-

-7,;

4.p.-

4-match lines

~ _ ',;

., <t'.*

' j.. ', _ f...

- ~.

,..'(; $..?

-fil,f h,, '

p

~

e.

' :Af.}.,,,

g,'

. *g q ~.

.,. ~ ' ?

gj...: A,

~

... '][ - l l%.'[

i,-

..,..y4

r,.

n l

h-

_v A*

. e l, " ?$

h

-.,, > y< t.

,9

..., t y;Vf ~ 1.. $..Y

- ? _' ' - l'

'. - ~

2 -; e +

g-

1. ~?

?'{1pl. ' ' i.

~y j.;

(h['f-I, - -

'g f 6+,

p y 5{fc ',% : -

.. 3 _ : :: b.

" M en! s.i :

Fig. 1 Composite photo of crack at top of block 1-2415.

(Appearance of crack on photo enhanced with pen for clarity.)

7 l

,i l

1 dWeP-1 b

y a q g z.:..,

~.,.-

i s., c tc; -

- gtg"

- $$j..Y."

~ * ^

-C,*-

l l

~

i i

t (a)

(b)

I t

Fig. 2 Crack in element 1-2415.

(a) Top view of block near

B dowel showing crack extending across outermost coolant hole to dowel.

(b) Example of use of standard line card for estimation of crack width. Line widths on cards were pre measured. (Appearance of g

crack on photo (a) enhanced with pen for clar1ty.)

~

u N

8 N

PJ

906577/2

~

s..m

. v

},_ Kf-

%pf we

, ':i Js.

' innGL *.-

.'4}

' 4,[

$1e

'y

..g

g..

.., o -..

.).

q::r.;. f. '.

.-y., r

- ~

p J. ':y;

',7,

%#R'/.9

e,p+,

y,+; g....

. ~ -

m.

... u, p.. y 4

..:g.-

g

.-. e.. _

.a:.-,..

a

.s. n s

-)

'e

&. yhh.

1 ll*

r

s

. g. ;:

..[

/

tlv.

w.

.r -

..,w (a)

(b)

-f r. e:4,q;, : '

.s Ti,*\\ ;,v

.. g.1 1

a_,

e' Ar 5; : 4 '.o i

?, *y y

M"

. ;?h 'g: A k k$,$$${h,,. ;)-[g4

..z=;y,. x q'4 a

.v.;

,a-g,

. 'o y<

3lf!f

f

_f p$;" -)

]

?

l

' ' $ 'O y

~

y s.,

(

v.

~~

'f ? '.

. ' +

,p 9

,'y.

67.J[\\ ;, ~* n,

.q7 sp.

t s~

.~.g..--,

.,rpj-q g ~6-7p i t:

u.a.

r

~

, -4 ;,

g.

,l, s-

/.Q4, (k_,%q;p !

.w.

~~ '.! '.-

1' y f,.

,4 t

s

..l,).s".,.

iD S.1 n

n n

2.

.,..<. L.:

, y '; L'y

L. ;-*;, ; _.U.Q. re..

s y

G Y

• ai.

f.

, y,., e>4; &y'

• yc.-+u$., m g.l1...l M i,7.:lf.:p, '

t w,g,j X

y.

y 'n. 4 y

~ > c :3 p-w h

l l*

g,

2. -C:$

(c)

(d)

Fig. 3 Bottom views of crack in element 1-2415.

(a) Bottom of

B face (b) Standard line card used to gauge crack width (c) crack crossed outermost coolant hole into dowel socket (d) crack continued into dowel socket up to but not across coolant hole in the dowel socket.

(Appearance of crack on photo (d) enhanced with pen for clarity.)

(

9 l

l

NS NCO GA-1484 (REV.10/82)

TITLE:

+

RESULTS OF VISUAL EXAMINATION OF FSV FUEL ELEMENTS S.N. 1-2435, 1-0172, 2-2693, 1-0108, 5-0801 Document No.

906577

/2 top of the block.

The crack extends across the coolant hole and up to the B dowel as shown in Figure 2a.

However, it was not possible to determine at the top of the element whether the crack extended further without removal of the dowel, which is not possible without block disassembly.

The crack did not reappear on the far side of the dowel. Figure 2b shows the use of one of the standard line cards placed near the crack at the top of this blockp the crack width at this point was estimated to be.008 to.010 in. (.20 to.25 mm).

At the bottom of block 1-2415 (Fig. 3a) the crack appeared slightly wider

.)

and was estimated to be.011 to.012 in. (.28 to.30 mm) wide at this point (Fig. 3b).

The crack also crossed the outermost coolant hole (Fig. 3c) and j

extended into the dowel socket and up to but not across the coolant hole in h

the dowel socket (Fig. 3d). The direction of the crack into the block at both c=

E the top and bottom is perpendicular to the B face on a line which, if exten-5 g

ded, would intersect the fuel handling hole approximately through the middle.

i Assuming that this line of the crack holds true along the entire block length, 2y it would appear that no fuel holes were intersected by the crack.

This as-o

.E sumption should be confirmed in the destructive phase of block examination, i

-5

._[

No other cracks were observed anywhere on block 1-2415.

Numerous f

scratches and scrapes were seen that would be easy to mistake for cracks, but l

h which are clearly not so when viewed through the Ko11morgen. Where there was any doubt, the alcohol evaporation test (see Ref. 2 section 4.2.1(c)) was 2

employed.

Face E showed some light rub marks approximately 2/3 of the way up from the bottom which appeared to be from an adjacent offset block. This face was indeed adj acent to the offset control block column in region 8.

All dowels and sockets on this block were in excellent condition, with only some light wear marks apparent on the B dowel.

3.2 FSV Fuel Element S/N 1-0172 Element 1-0172 was cracked down the center of the B face similar to block 1-2415, but the crack was narrower and hard to see in some places, even

+

Page 10

l l

i 906577/2

__,1

. p'* 'h..*'*

.i d

4..., va

/

. g,

' WQ?.. -

4.

%V[. L -

~

[ % %[$N,.9,

,.5

.. #.Q

,NE p'~

q.

k...

[t f m' Y [., ( t 1 " - j,'p9 i

..y

. g i

'pc J Q Q,i'i O d

. _ + -

a.

ljji'l

,4.,,

- g.

.. r;- -

w j-J:

s

.p.

m,,

g.,.

g.

,[:l :

,s

v...

rn y % gy

y3 f, f ' i n*

('9p;j yt t< i 0o

.a.

m y

.!i '

i;'.w p.r..

f

'_ ; W.. g.

. ~

M.

l i

?,A ;?'Q'Y

$$...$4*,h-l..

5.,

,f..

9 1h

^

.- ~E \\_ t. m.... q.,h<.,a,

, g q.

,,.o i

+

3 7, ; n 1 gg/

,,-f+ag--

- y> -

..i; g ;,..,-

s e

..c.

& b h.l.f ] 5{

?,.

wg..

'f l

~ %..,. s-. :~.. :.

7 f.6 4, i

4

?%{%. f.l...

,..

.4 i; m./

I

~

O

,,e JJ qw,. ' ;... \\.

^,,

y 5 4.9

.f p

2 r

c.

..n!.

r.

(a)

Fig. 4 Crack in element 1-0172.

(a) View at top of

B face (b) Top of s

block near

B dowel showing crack crossing outermost coolant hole to dowel. (Appearance of cracks on photos enhanced with pen for clarity.)

11

GA Technologies Inc.

G A-14B4 (REV.10/82)

TITLE:

RESULTS OF VISUAL EIAMINATION OF FSV FUEL ELEMENTS S.H. 1-2415, 1-0172, 2-2693, 1-0108, 5-0801 Document No.

906577 Isme /2 through the Ko11morgen.

Figure 4a shows the crack appearance at the top of the block and partway down the B face.

Figure 4b shows that the crack goes across the outermost coolant hole at the top and up to the dowel. Crack width at the top of the block was estimated to be.005 to.006 in. (.13 to.15 mm).

On the bottom of the block, the crack was so thin that it did not show up even in close-up pictures.

It was apparent, however, that unlike block 1-2415, this crack did not cross the outermost coolant hole on the bottom end, and did not extend into the B dowel socket.

Alcohol was used to verify this visual observatson. The crack width at the bottom of this block between the side and j

the outermost coolant hole was estimated to be.002 to.003 in. (.05 to.08 E

e mm).

8

.o E2 No other cracks were observed on any other surfaces of block 1-0172.

Mg Many scratches and other marks, all of a minor nature, were seen on all sides a6 and on the top and bottom ends.

Many of these marks can be attributed to e2 handling, both at FSV and during the present examination at GA.

5 23 jg 3.3 FSV Fuel Element S/N 5-0801 e

5 3

This block had not previously been examined and was the least marked and j

scratched of the five examined at GA.

No cracks were observed anywhere on this block though it was predicted to have experienced high stresses during e

3 irradiation. The E f ace showed the imprint of an adjacent, offset block in 2y the region 25 contr"t eclumn.

Its handling hole was slightly chipped.

A handprint was obO 2ve, on the E face.

3.4 FSV Fuel f.lement S/N 1-0108 This element was very clean similar to S/N 5-0801 with a minimum of scrapes and scratches.

The dowel socket edges were particularly sharp and distinct compared to some of the other Alocks.

No cracks were seen anywhere on this block; several scratches were closely examined and checked with alco-Page 12

's

,t 906577/2 Wa. k.y,.-

~

?

$1 ~

..f $

'~

TJ W>

\\ '

f. k 'n M);J

\\

I 9

.7yw I*kt[;s[I*E l

$ t;l?

h$b'?'*f6 e, $

y.,

k{QL N(Cr,.

i i,V#iti l N i[ Y N k i

l tj( Q 7 V l

< dHW '

'~W i

l t.: - y *.g ; -

. c57 y g:, --

..+

...-i_f...s ? % x 5'. q, j :'q..

.. ~

' 'W w

t s.

sk,.g _ _

[ j';

_%f.

l

./

--4

. ;t.,,..

• l '

5, s

=

'N'.

J

)

t A

$^

&.si i

s'

,g

.s.~..

p^'

4

.;Nt2

,;n, ce+t s

s

~

.Shh MN[jf s

w ^

-M N%. M.A.ma. M M %&.L% a u ' '

l Fig. 5 Damage observed on two dowel sockets nearest "E" face on bottom of element 2-2693. See text Section 3.5.

13

4 a

-. 4 -.-..

a

6

- =

906577/2

~-

n,

"" 7 9

g Tg;ig..,.ri?g:te

~

y7-

-b n 009 *.

.-,.,.-9

- wa q

L..

. -;i.,

a.

'... b 3,,

s g-

<5 g

,,g E.

+t y. y.7-3 N

a (a)

-> g y.- '

vi 1-c.

, ag[ ~. '

y.

1 s.,

.,,c

~Ss s*j.7 c?.~j y

n...

.p

.. v.

i.

.3-

i.._-:,

. c. -c.

y.,, ' -

f

. sh, % p

.M ;?q;9'.4 ',

Tp,,*

,d p%.(T

$.7"

, m:g

~

...3 e,

.. [,

-l

~

,8

,,. c.-'

. m.g

13.. ' ~

gk -

(b)

Fig. 6 Control element 2-2693 (a) Overall top end view (b) Closeup of control rod penetration showing light, vertical scratches attributed to control rod movement.

14

6. ;. _

• L. ;'. ' '.. ' '. -

~ ';-

+ ". *;- ).. ; ' a.

.,...4'.

. +'..'...

,1 e '. * ; '-

c, > '

v'

+

.~

IOS InC.

GA-1484 (REV.10/82)

+

RESULTS OF VISUAL EXAMINATION OF FSV FUEL ELEMENTS S.N.1-2415, 1-0172, 2-2693, 1-0108, 5-0801 Document No.

Issue 906577

/2 hol to verify that they were not cracks. The E face showed the imprint of the adj acent of fset control column in region 8.

I 3.5 FSV Fuel Element S/N 2-2693 This block was a control element, having two control rod channels and one poison channel in addition to fuel and coolant holes.

The most notable fea-1 ture observed on this block was slight damage to two of the dowel sockets on the bottom end, shown in Figure 5.

This damage is tentatively being attri-buted to placement dowels on the bottom plate of the FSV shipping cask which prevent undue movement of the blocks during shipment.

E

.c g

Imprint marks of adj acent, offset blocks were seen on almost all faces since this control block was surrounded by standard fuel element columns in the reactor.

All other marks on the block surfaces were minor scratches and a

.E E

scrapes typical of those seen on the other blocks examined.

The insides of the control and poison channels were inspected with the j

aid of a small in-cell spotlight.

No cracks were observed in any of these O

[

holes.

Shallow vertical scrape marks as shown in Fig. 6b, probably due to

.i~=

control rod movement, were seen in the two control red channels.

c.e 3

3.6 Stacking Demonstration on Blocks 1-2415 and 1-0172 2

As called for in section 4.2.3 of the Test Specification (Ref. 2), block 1-2415 was stacked on block 1-0172 in their irradiation positions to investi-gate the fit of the dowels and sockets.

This procedure is shown in sequence in Figure 7.

The blocks stacked together easily with no apparent mismatch or interference.

In fact, with the blocks stacked together but the weight of the top block supported by the overhead crane, there was noticeable lateral clear-ance, particularly at the B face dowel and socket location.

This is shown in Figure 8.

Figure 8a shows the view of the B faces just before finally lower-ing block 1-2415 onto 1-0172 ; the larger crack size in block 1-2415 is appar-t ent.

Figure 8b is a double exposure made by moving the top block to the two

+

Page 15

y, -~m,m pra,.

ry. :.,

s.

.J 3~.c99.., d E.: (

't...

y, s.

y f

ff L 2

~

g.,,

3 o+

3 1

P Y

1 l

3 l

i l

{;

}

'i 1

1.

[

l i

ip l

6 -

p (a)

(b)

+.q,s g

q y 2.3

'j

[

b,.,

4 .

i

.l

.o P

w

.i s

I;

/s

').

[,

g i -

(c)

(d)

Fig. 7 Stacking demonstration with block 1-2415 (top) and 1-0172 (bottom) in each photo. (a) Blocks approximately 6 inches apart (b) dowels about to engage sockets (c) dowels engaged (d) fully seated.

D D

16

i.

I 4

i i

i l

i s

l l

I I

[

l I

r W9

.. s

t. '

=

i t

I b ' [j/E..~ #

'S

,j.

v*

,7 i

i s

y t

6 -

i 5

4 4

~

e j

(a)

(b)

I i

j Fig. 8 Stacking demonstration of blocks 1-2415 (top) and 1-0172 (bottom) at the "B" faces showing cracks in both blocks. (a) Just before fully engaged (b) fully engaged; double exposure showing lateral move-e ment possible at "B" dowel and socket. (Appearance of cracks on g

photos enhanced with pen for clarity.)

d i

N N

i 17 w

i i

I

906577/2

+-

x; i

d ;.>,

fi

. ss

. ~....

i..

L &:.., ; n..l&. c

,.? WT%.

n. ~, U

'-4 ',

'a,

'n_ 4-

,t

,~

h

'f

-.' Qg L*'

o.

'_,g'

? W z.de h

-5, : ;; "., ^gj.Qx

. ~*

3Q_

g%p ;;%u,,.

m'

~ q

o.

y M;.;5,

y,c a.

a w.

a

+. p, e:s

' ' ; y,, jgfg

• • g

    s' q v[it:a=

Q e,e-s w

lg

~

, %', N pf,-

y :: :. :

w

. rg ;y gwcq'

s*f.';,*;; y %*3:

y

.g Q.{+.ts..;---4i

-y yg g : t;; y n.

, >' > n ;+8- =

,,v.

c ~Ti l < ;p l;;[$6 h,j e'-Q,^[c,%

' ^ ^

V4 f%)

l;>

i?N '

q l5Ch j[ v@Wg," lifJe gp\\@e VRty'Q-:':,g R'h 6,

N V'; s r 3

s 3 KQ;.y.

n n.G E.:'m ;- M id L i s idi,i d d;u;',.-lid ' #

L.

(a) e r

4 9

N r

y

A

• t.'

i e

9 y.\\

(b)

Fig. 9 Damage at the top corners of two of the five blocks examined which occurred when the blocks were removed from the FSV chipping cask; (a) block 1-2415 (b) block 1-0172.

i 18

ISS If1C.

GA-1484 (REV.10/82)

+

RESULTS OF VISUAL EXAMINATION OF FSV FUEL ELEMENTS S.N. 1-2415, 1-0172, 2-2693, 1-0108, 5-0801 Document No.

Issue 906577

/2 extreme positions allowed by the lateral clearance.

From this exercise the relative movement and thus the diametral clearance at this point was estimated to be.040 to.050 in. (1.02 to 1.27 mm).

The nominal design clearance is

.040 in.

3.7 Dowel and Socket Dimensions Although it was not called for in the visual exam procedure, several cur-4 sory dimensions of the dowels and sockets on blocks 1-2415 and 1-0172 were E

taken. A dial caliper was c:ed to obtain these measurements, and no standards were employed.

Table 1 gives the data.

The O.D. measurements on the dowels j

seem satisfactory in that the percent shrinkage calculated by comparison with g

the nominal preirradiation dimensions agrees well with values determined pre-f viously in the surveillance characterization at FSV (Ref. 1).

The socket measurements are probably in error, however, because the shrinkage determined

.c f rom them is roughly 4 to 5 times the block average determined previously and E

because of the dowel to socket clearance determined indirectly during the

(-

stacking procedure (see Section 3.6).

The dimensions shown in Table 1 indi-Ea cate only.010 in. (.25 mm) diametral clearance between the B socket of block O

1-2415 and the B dowel of block 1-0172, while the clearance apparent in Figure

.c

}

8b was estimated to be.040 to.050 in. (1.02 to 1.27 mm).

Since the stacking experiment was considered conclusive, no further measurements were made.

l 0

3.8 General Features Figure 9 shows deep gashes at the tops of the first two blocks examined (S/N's 1-2415 and 1-0172).

The source of these has been traced to a pro-trading index bracket on the shipping cask that gouged the blocks as they were removed for this examination.

This damage was avoided on the other three blocks after the problem had been identified.

A feature seen on all the blocks examined is shown in Figure 10.

A long, vertical scrape or scratch down the center of the C face, and sometimes near i

Page 19 i

198 lDC.

GA-1484 (REV.10/82)

TITLE:

-p, RESULTS OF VISUAL EIAMINATION OF FSV FUEL ELEMENTS S.N. 1-2415, 1-0172, 2-2693, 1-0108, 5-0801 Document No.

luue /2 906577 the right hand edge of the D face was observed.

The source of these marks is

/2 not known but it has been speculated that fuel handling in the fuel storage

/2 wells at the reactor site may be the cause.

4.

REFERENCES 1.

SAURWEIN, J.

J.,

Nondestructive Examination of FSV Fuel Element 1-2415, General Atomic Company, Document No. 906505, Issue A, May 17, 1982.

E 5

2.

DONCK, H.

A.,

Test Specification for Nondestructive Examination of FSV Fuel elements S/N 1-24153 1-0172 2-2693: 1-0108; 5-0801,

General 4

5 Atomic Company, Document No. 906553, Issue A, July 1, 1982.

8 fi E

i 2

8j Table 1 POSTIRRADIATION MEASUREMENTS ON 'IVO FSV FUEL ELEMENTS 11 Nominal y

Preirra-E Mean Dimen-

/diation 5

Block sion(*)

Dimension j

Number Item Measurement in.(mm) in.(mm) 1-2415 B dowel outside diameter 1.7458(44.3433) 1.750(44.450) 1-0172 B dowel (c) outside diameter 1.7484(44.4094) 1.750(44.450) 1-2415 B socket (b),(c) inside diameter 1.7588(44.6735) 1.790(45.466) 1-0172 B socket (b) inside diameter 1.7469(44.3713) 1.790(45.466) 1-2415 E face dowel outside diameter 1.4981(38.0517) 1.500(38.100) 1-2415 E face dowel outside diameter 1.4979(38.0467) 1.500(38.100)

(*) Average of three measurements taken at 0, 450 and 900 orientations.

0 (b)See text, Section 3.7, concerning these measurements.

(c)The dowel and socket engaged during the stacking demonstration, See text, Section 3.6.

-D*

Page 20

s n

g

yyt nyc14.Jimannamar72, j

3v y q

7:a yi a 906577/2

,yn,.~. we,yety, r-,;n

-: e

. s, y.,9..:, _ -

P v

u.

4

.,s,

, ~

n.;

2 1- 0 fp.,

a g,l 7

Q,

~-

+

.x-

.c t

e.

1 Mr c~

.w l llh s 7, $-

3

?-;

f, tp.

a,. s

~ sf : :

i.? :e.

%fM

,...x. !/. :. J4 gg r. f :. '. M? r--

rq'.;. ",,0, 7 j

.~,(.

(> w g

--a

_5

. ~f ?^

,_ h!'f'f$*;

.a_ y.- -;

5-p l

IC E_C-n-..

1 FoY i

sy i

>Eg v-

[,

i,

-j*

--'" o l

I-(

R._._

_?*

Composite photo

--p-match lines N

l

=

e y

'h.

I k

E-t o.

+=

d a

e*

4 l

m h,

cd

s ca

• A y

w.

l Fig. 10 Composite photo of

C face of element 1-0108 showing vertical scratch seen in same location on all elements examined.

See text.

Section 3.8. (scale in inches).

21

.