Text

App C to TMI-1 Steam Generator Recovery Program,Task 7, Primary Sys Review,Rcs Insps & Requalification, Exam Results
	ML20063K042
Person / Time
Site:	Three Mile Island
Issue date:	06/25/1982
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20063K013	List: ML20063K020; ML20063K042; ML20064M520;
References
	NUDOCS 8209030158
	Download: ML20063K042 (353)
	v • d • e

_ - - - - - - - - -

I

'I I Nuclear i

I TMl-1 I Steam Generator i Recovery Program l Task 7 g Primary System Review Reactor Coolant System inspections I And Requalification I

l Appendix C g Examination Results I

I g Compiled by N.C.Kazanas

! G. E. Rhedrick l lSA'AS8cfo!S8Sfl; I

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APPENDIX C ll ; Examination Results and Validation 1

1. OTSG stainless clad Dye penetrant and wipe samples of the upper upper and lower head and lower tube sheet and upper and lower head.

'l &

} 2. OTSG inconel clad

,il upper and lower tube l!E sheet

. 3A. Make up nozzle safe end, (3A) Dye Penetrant: Muv-95, Muv-86-A and 86-B,

. B. HPI nozzle safe ends, Visual: Muv-94, Muv-95, Muv-86A and Muv-86B, j C. spray line pressurizer Radiography: Muv-94, Muv-95, Muv-86A, Muv-86B nozzle safe end, surge Ultrasounic: Muv-94, Muv-95 Muv-86A and Muv-86B line pressurizer nozz~e (3B) Radiography: Pressurizer spray nozzle, Ultra-safe end. sonic - pressurizer spray nozzle (3C) Ultrasonic - pressurizer surge nozzle

4. Lead screw Results reported in OTSG failure analysis report Task 1.

5. Reactor _ vessel inner- ---Laboratory metallographic investigation site and o-ring B&W LRC

6. Motor tube Ultrasonic examination of motor tube #63,66 and 68.

ll 7. CRDM end fitting Laboratory metallography investigation, i 8. Hold down bolts of plenum Ultrasonic examination of (6) plenum lifting lift lugs lugs.

l 9. Top of core and control Visual examination of report.

l, component.

's

10A. Fuel assembly & (10A) Visual examination of un-irradiated fuel B. control component (10B) Visual examination of irradiated fuel lt C. reactor internals (10C) Visual examination of baffle region &

l; D. baffle plate region RV internals (10D) Visual examination of control component

11. RNS retainer Laboratory metallographic investigation 4

8

12. Core support shield to Ultrasonic examination of bolts.

a g core barrel bolt.

E 3- Lower bottias rings in visuai examination of Rv internais.

& RV internals and lower t

14. vessel head i

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I i

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1 Appendix C (cont'd)

Examination Results and Variation

, 15. CRDM nozzles to stain- Eddy current examination of motor tube #68.

less flange

16. Plenum assembly Visual examination of structural components.

1

17. Plenum cylinder to Ultrasonic examination of bolts.

plenum cover bolts

18. Vent valves and core Visual and functional examination of valves j support shield I.D. and structrual components.

I 19. Intentionally left blank Deleted inspection.

9 j 20. Low pressure injection Re-schedund for supplementary ISI program. ,

i pipe welds i

i g 21. Incore detectors Functional exam.

i3 22. Incore detector sheath Dye penetrant exam and wipe samples B&W analysis.

Il 23. Vent valve thermocouple Eddy current exam of nozzles.

,E nozzle. '

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j TEST COMPLETION REVIEW SHEET I.

Task #7 Inspection / Test: 1 Inspected Item: OTSG Clad Upper and Lower Head i

! Type of Inspection: Dye Penetrant f

l Inspection and Test Plan: Dye Penetrant Examination of stainless steel weld ,

g deposit cladding. The examination is perfcrmed to verify general conditions f'

g of the cladding and to obtain a data point for PWHT stainless weld deposits. [

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YES N0 f.

y 5 I. Is the work scope in agreement with the B&W $ ,

Engineering Information Record? {

f

2. Was there an approved inspection / test procedure y used for this examination? ! f I

3. Does the results of the examination agree with the I

acceptance criteria called out in the inspection / {

test procedure? ;

I 4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure?

(Accessible quantity inspected Minimum re- j l

! quired .) V ,

8 Note: If any of the. answers to (1), (2), (3), or (4) are

! no, a written explanation must be attached.

s; I 5.

5 Based upon the results of this examination, were there any repairs made to the item (s) being in-spected, or reconmiendations for repairs or re- g l Placements?

6. Does there exist any unresolved discrepancies that have not been (reported) processed for future

resolution?

tl Note: If any of the aesvers to (5) and (6) are yes, E a written description must be attached.

7. B&W EIR No. / /G 2 / O 9-0C i

Task #7 Procedure No. /w1H3-007 k 3 8.

IVES /L PT; l- HP I Reviewer'sSignatureQ/ b '

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E TEST COMPLETION REVIEW SHEET Task #7 Inspection / Test: 2 Inspected Item: OTSG Inconel Clad on Upper and Lower Tube Sheets Type of Inspection: Dye Penetrant Inspection and Test Plan: Dfe Penetrant Examination of inconel weld deposit

g cladding. The examination is performed to verify general conditions of the cladding and to obtain a data point for PWHT Inconel 600 weld deposits.

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. 1. Is the work scope in agreement with the B&W Engineering Information Record?

f f

2. Was there an approved inspection / test procedure f used for this examination? 's 3.

I Does the results of the examination agree with the acceptance criteria called out in the inspection /

test procedure?

I l 4. Does the quantity of items inspected agree with the l minimum requirements called out in the procedure?

l (Accessible quantity inspected Minimum re- ,

j quired .)

Note: If any of the. answers to (1), (2), (3), or (4) are i no, a written explanation must be attached. F

5. Based upon the results of this examination, were ;

, there any repairs made to the item (s) being in- 1 l spected, or recommendations for repairs or re-E placements? _

6. Does there exist any unresolved discrepancies that I have not been (reported) processed for future resolution? [

,l Note: If any of the answers to (5) and (6) are yes,

,E a written description must be attached.

7. B&W EIR No. // 3 2/ 0% CO

8. Task #7 Procedure No. MTZ 6 - OO7 /buf 3

,'l NES /.4 PT- / - NP Reviewer's Signature / h

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DOCUMENT IDENTIFIER 51-1132109-00 ,

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! TITLE OTSG SURFACE SAMPLE AND PT INSPECTION ~ '

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PREPARED BY b ,L u/ D e DATE 2-h-47 i:- REVIEWED BYd DATE 3-s-er_

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REMARKS: -

I This document defines the engineering requirements for collecting surface i film samples and liquid penetrant (PT). examination of'the stainless steel cladding in the OTSG upper and lower heads. The surface film samples

E will provide information on the presence and concentration of contaminarits B in the OTSG. The PT examination shouldreveal any defects in the cladding.

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,k I .' Introduction

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}54- This document defines the engineering requirements for collecting

v surface film samples and liquid penetrant (PT) examination of the

! stainless steel cladding in the OTSG upper and lower heads. The surface film samples will. provide information on the presence and

!h

concentration reveal any defects of contaminants in the cladding. in the OTSG. The PT examination should .

II. Surface Film Samoles

1. !

The samples are to be taken using the " wipe" method. The number and [

' locations of these samples shall be: '

s

a. 2 samples taken above the maximum water level during wet "

a layup, (An elevation equal to mid-span of the upper head

g . .manway).

l b. 2 samples taken at the water line, (Preliminary data indicates +

(

that this is approximately 13-1/2" above the primary face of ,

the upper tubesheet). .

- 4,.

,I c. 2 samplestaken approximately 4" above the primary face of the UTS. I' v

d. 2 samples taken in the lower head. 0 3

.. s c-The highest and lowest samples may be taken from the upper and lower head manway regions provided that they are sufficiently far fr.)m the

.__ _ d (m

openings wip'e area to eliminate should artificial (i'.e.I' be approximately 2 fthuman)

. contamination. The

e i o Wipe samples require that the samole cloths be moistened. The

[

! - sample cloths come pre-moistened'but demineralized waterican

'l- be used to wet the sample cloths if required. Acetone or alcohol f.

i of an acceptable purity may also be used to moisten wipe cloths for sampling. ?*

'lg~ 3. Only pre-cleaned wipe cloths should be used. These will be available through the B&W site office. -

I .

Special care should be taken 'to miniinize inadvertant chemical contamination of the wipes due to handling. For example, ,

rubber gloves should be worn when handling sample cloths and ,

I taking samples from cladding surfaces. The gloves should be thoroughly washed and rinsed with demineralized water prior to use.

I 5.. Samples should be taken by rubbing the wipe cloth over the selected area with the gloved hand. Even pressure should be applied to as much of the area covered as possible. Repeat this process l == one time over the same area to better assure that contaminants

-= are removed by the wipe cloth. An approximate area

^ and location. of sample region that is wiped should be noted on the sample label. (i.e., 2 ft ) 2Samples taken should then be i

resealed in individual sample bags. Acetone or alcohol soaked wipe cloths will collect some types of dirt and greases (if

_ - - - - m

present) which the water wipes may not pick up. If an acetone or alcohol wipe is used, it would be wiped over an area previously wiped with a water wipe. Both acetone and water wipes from the same area should then be placed in the same bag.

h 6. Sample cloth bags should be clearly marked to indicate:

8 Sample number i; O Sample location (elevation and approximate orientation to a~xis) ,

0 Approximate area wiped by sample cloth lE3 8 Date/ Time 0 Water or Acetone / water wipe I Any unusual surface conditions observed or other infomation which may be useful in detemining the condition of the cladding surface should be noted for each sample taken.

jg III. PT Examination

1. A total of four PT examinations shall be performed. A PT shall be

.g perfomed in the upper OTSG head region in an area at an elevation

3 equal to or greater than the centerline of the upper head manway on the stainless clad. A PT shall also be perfomed on the upper and lower a tubesheet on the inconel. clad. A PT shall also be performed on the g lower head stainless clad.

b N. The examination shall be' performed to the requirements of NB-5110 5ectich III of the 1977 thru Summer,1978 Addenda of the ASME Code.

(1 The examined areas shall meet the acceptance standard of NB-5350, -~

U -

S'ection III of the 1977 thru Summer,1978 Addenda of the ASME Code.

3. The stainless clad PT examination shall have a size of an e 3 approximate 6" diameter circle. The specific locations !

g b shall be recorded. ?

E \ 4. l The inconel clad PT examinations shall be performed on the periphery 6- of the tubesheet where an area of approximately 2" by 6" is l 5.

available.

~,

Clad material removal shall, be minimized during preparation of the examination surface.

6. Areas identified as having a defect shall be photographed and' material removed to a depth of approximately .005". The area is I

then to be PT examined again to the requirements of NB-5110 and NB-5350 and if any defects are identified these are to be photographed and reported to B&W.

7. All examination information is to be sent to B&W. Location of the examined areas is to be supplied with the infomation.

== Caution: PT solution shall not be allowed to contaminate tubes.

13 l l Pp dl

s M* -"*N >

a( , . ,

g...-.,.e-~*.-]*3-.....g

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. . . .q ,. ...

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.\ ., m.-5351-NB-5510 .

{ I.

.. (c) Relevant indications are those which result Article 10 of Section V. When vacuum box testing is ,

.,' ./.9 from mechanical discontinuities.. Linear indications used, the soak time shall be a minimum of 10 sec. Any C .T. ~l.

' hree times ' the width. Rounded indications are 'l 1 by t

O indicatiens which are circular or elli Pdeal with th_e..c length less than .three. times..the w.

zi. unacceptable c.o. ndition. h ' . _-

J.idth. W. s ,..jW. .b..M. . . * *. .6.*._ rl,2. .- Y. 'shall be %.ueviden

. *t.. :*')., M, . %... . . -F.%. , S 'M

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'3 E er than W in"(I'6 mm) J sh'all be considered 'relevint: . , ' 'M P . ' ' -N '

N@. ,., .

(b) Unle:is'otherwisis '#h d'l. VESSELS r ."-' " f C -5 45:

NB-5410 , EXAMINATION AFTER NMW the follow. mgre . le.vant . pecified isthis Subsection, i . - - -

'S

.:- md.icatio.ns a. re imaccept.able.:. . . s c.....79 . :' nu. *

,.a.

I"3 ~

(I) anycracksorh.ncar mdications..;

-d:;.5 . ,. c. .g%::-.. , '. .... HYDROSTATIC TES, ,

C T .. //./ .W

, (2) -roundedindications with dimensions $reater 8"'After the hydrostatic or pneumatic test of a vessel, 7.dk (3)in.(4.'8 min);'.Q-$M. 7E/27[.

i than I .

. fos'r'or..more r3tindedisdii:Iations a . d. B,, C, 'and.D, in;$'line'f.jllf' used, to join ferritic(material eldjointsand and' A.::. heat 1 N a e . repair' welds in ferritic material that_ exceed

~ ~

~ '

I Lseparatei1}16rPi gin. (l'.6'Euii)ior less Ed[e, to.eds; 7/ .

(4). '10d, Amore roun[ied indications ineither,3/s iny' 6 sq in. 0.0, nun) or,10% of the 'section thickness @y$

'in. (3870 min:)'ofsurfacewiih the major' dimension of ' n,.*.Schevep leg shall,h mmined when physically @p.,g ~

i this area not to exceed 6 in. (152mm) with the area ' *CC*552E' by.6e magnen,c{ - panicle or, E taken in the most-unfavorablelocation klativ'eto.' tlie3 J. . ant.m,e6o. p.3. .,.h,7g.g.,g,,gjgp

, yp.g . . . . . .

j indications being evaluated. ,e j.,,u ,".. ayg ... e .m: ., . i ..u.. ;.] 0.gr;. ,; . [/;.

W W .

- ; :s z.; m p ; A... . =. d .4;(q $....gn s-. y ._Q cQ5 ' k.& .. -

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9,.~

.NB-5360 .,. VISUAL. ACCEPTANCE .: e..w x,* .v , ~.~ - '

r

.m a -9+ ; .. : -

-- -STANDARDS FOR BRAZED,, :59 3 ~*r9 81 CERTIFICATION O. F..

%pa,w. e . .~d. c .j:'

~q ? . N. . . .

v .

. . . - :.t we.k. a . .. 4.5.,x -

. NONDESTRUCIIVE . , .. ~ . cn?#2.>n - -

.w.,. .W :s.M y.: h i.e

. .. Braze E:rectal JOINTS shall give. evidence-of-luiving-flowed m c., w.:M :p @. -c - '~

~,-~@'t.9...:?p. ' 'M- '

. . EXAM -

NB-551Y r.%-h 4:

i . - -

. t by< the appearanceo< f an .wm,. 0 .cGENERAL c 7-

w. mREQU,IR.EM..E. NTS, '- ~. -bggg.td umformly through a j.otn i . . .; .: .. .

b4?M

cc.m uninterrupted .nar. row visi,bmm leline :of brazing:all,oyst.J.@.w Or ms-g

..s.. .m-

. the end of th. . .-ejomt;.mp g-rr;ggire.c .,g,p;. -

.p mu- gstructive examinations . .

ersonne shall use,p. .e :--;' re w..u.:- ;+FM,:.. ._2;d s.

. and knowledgeable to the degr.ee specified by NBG 4.,.M~fm. G

-..m .-

. -gue. veseptq..n. A.p"sW. &... .,c, _l.5520.'When these services'are subcontracted by'the 94. .M.

@ ;@.w:..:

E y;p N. Aki e.. Cernficate Holder. .or. Quality.. system Cenificate GWfk

~5

~s%' B-53 Dr 'G

. S Nss2iL.J - 4 -~'

qr. u d'h- ; 5 Hofder, E he --

Ashall '.sverify Wthe':,4 - --

qualification of personnel s -

, N. 'BbBBLE " ' # FORMATIdNNg?'to ' .. ..,s.n

- the" requirements of NB-5520. .t' All n

.u.A, W A.W>. M. .:b. E mminatio'ns requ. ire.d by this: Subsection shall be

. .M.4g.FSTING,..a. w . : x For gas, and ' bubble formation . testing, tli,,..dl^.

s etest; performed b and the results evninayd by qualified @dijgf.[

i'

... procedure shall be 'in nondestructive mminationpersonnel.i.. . n@p

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TEST

?

~.

j[ 't 3 i e

I SAFE END NOZZLES

,I

!l ll a

I-1I I

i 1,

!I .

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t i *****~~~____..,~,_.~ ~

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_j Ettter-OKIce Eicmcrcmhtm I Cate March 16,1982 -

y if 2

1mp I b h (-,*g'k.)

Nondestructive Testing of 2h" d-.t-r- M '

I Subject Sch.160 Pressure Injection Nozzle - QC-CL-3 94 and Heat Effective Zone of MUV-94.

g To D. Croneberger Location TMINS Trailers #256/258

3 I. General: .

The assembly is as shown on B & W drawing #160493-E, Rev. 0 '(Modification).

jg The radiographic examination was conducted using the technique data

'E obtained frc= the orisinal examination conpieted on site in 19:3. One (1) .;

film (4'-5) taken on 3/6/82 was found un-acceptable due to covenent of the

film and was discussed. '

l "' II. Scope:

The nondestructive examinations conducted are as follows:

A. Radiographic examination of the safe-end to valve (MUV-94) weld joint.

E. Presence of four (4) werd bea'ds per note #8 on referenced drawing.

C.

j Location of themal sleeve with reference to weld. beads. Decemine possible movement and/or wear of sleeve and weld beads. .

i

'g i D. . Detemine presence of possible clearance between O. D. of thermal i3 sleeve and I. D. of safe-end in the expanded area of the themal sleeve..

E. Liquid penetrant examination of the 0. D. surface starting from the heat affected zone of the nozzle to safe-end weld up to and including 1" of the valve surface adjacent to the valve to safe-end weld. .

F. Visual examination of surface per "E" above.

5

.. G. Ultrasonic examinatio$ of safe-end to nozzle weld, safe-end and safe-end to. valve veld.: .62 6

' ... , --5ifPf.f.j]g1yN!."'

^ .

$.{f"

, :i? ' '

5 -

~

I

I Aoooo648 I --

- .---m- ...e- .-- -.-,--we - . - - . . - - - - .--w - - , * . , . ,. _ _ _

, m.H m -

ww

{ -

Page 2 QC-CL-394' , ,

e I

i III. Evaluation:

II-A.. Radiographs evaluated per acceptance standards of ANSI B31.7

' films (0-1) and (1-2) showed minor tungsten inclusions which were accepted. The film did not reveal any unsatisfactory

~

conditions and the weld was accepted. The technique for

- each exposure was identical however, due to placement of the shims and penetrameters on the film the density was found less than required on several exposures. R sed on acceptable den-sities of exposures (5-6) and (6-0) and exposure techniques j.

being alike for all exposures the film showing low density were "

considered acceptable.

.I N F:t i II-B.' A comparison was made using the original film taken on site E

II-C. 1973 and those taken on 3/6/82. The four (4) beads appeared r

unchanged. The location of the thermal sleeve with reference to the-veld beads appears' unchanged. The radiographs do not

show any wearing away of the welds or thermal sleeve.

l*

II-D. One (1) film (0-1) shows a intercetant line starting at the up stream end of tihe thermal sleeve and extending, down stream approximately 51" in the area of the expanded / rolled portion of the sleeve. _ Evaluation.of the remaining five (5) lI

' - , ~ _

, ' film was~c~ompleted with acceptable results. -

~

II-E.

Liquid penetrant examination revealed three (3) .020 dia.

indications located on the as cast surface of the valve.

{ These indications were documented for information purposes only. No relevant indications appeared on the tested surface.

! II-F.

{

The visual examination was completed with no objectional f

g condition to report. The entire surface was found free from '

J defects.

}

II-G.

i' -

Ultrasonic examination revealed three (3) indications as follows:

1. Low level indication near I. D. surface. Plot shows in- - #

dication in nozzfe clad surface. '

2. Indication,a ears to be a corner.on the I. D. weld prep.

,', surface of_the safe-end.

, , . , - . ..j. :

. . .y

3. Low level indication on safe-end I. D.. surface in the weld

joint area. Appears as slight under cut - safe end to

nozzle veld. -

~ .

I .

Page 3 l QC-CL-394* .

Attachments: 1) Ultrasonic Examination:

I a) Calibrations Sheets (#000173 thru #000175).

~ b) Thickness Date Sheet (1-Sheet).

!g -

c) Limited Scan Report (1-Sheet).

d) Ultrasonic Date Sheets (#000058, page 1 & 2).

e) Request for Evaluation / Recordable Indications t

(sheets 1 thru 4).

i i

2) Visual / Surface Date Sheet (1-Sheet #000155).

3) Visual / Surface Date Sheet (1-Sheet #000154) Dye ?

Penetrant Examination.

= -

4) Radiographic Report dated 3/6/82 (NUS).

1 i

'I, JET /BEB/ejg Attachments - *

' cc: N. Kazanas #2 #-

I B. Ballard *.. J.J.-Tietj en,;.

R. Fsnti -

Mod / Ops Inspect on Supervisor R. Toole

. o z

{ ;

F. Faust (B & W) ,

> QC file (2-) B. E. Bal' lard '

Manager-IMI QA Mod / Ops '

I:

. h .: *b:.

~: .' .: -lj.,- ,

- . <~.

i .

i

!I 4

s a .

---w -- - - .-- , , - - ,, . . - - , - - - - . - - - - , .- - , ,

l: d5e. e;ya Inter-Office Memorandum I. Date March 19, 1982

'3 r'2eo1 Subject TMI Materials Technology Report of tuclear NDE Results - Make up Branch Connection Safe-end/ Welds To D. K. Croneberger Location N. C. Kazanas l

I Materials Technology has completed VT, PT and UT of the subject make-up t

I Piping System /Irr Pipe branch connections. Mod / Ops QC has provided RT contractor support to verify the thermal sleeve position on two(2) branch connections to date. The remaining RT is scheduled for completion 3/20/82.

I I No relevant findings to report. The enclosed NDE record sheets (3-UT reports will be forwarded later) include some ID geometric UT reflectors and a low level cladding UT reflector that are documented for information.

These are not considered revelant. Data sheet No. 058 documents the access I restriction at the reduced "3.5" diameter valve to safe-end weld precluding contact UT of that area. The one(1) inch axial length of the 3.5" diameter region has been reduced to approximately 0.5 inches as-built because of weld reinforcement overlap. The valve to safe-end weld is in the as-welded I condition. The scope and extent of the NDE examinations follow:

NDE METHOD SCOPE AND EXTENT j 1. Visual (VT) - All surfaces including Safe-end/ Attachment welds /

l Buttered weld and one(1) inch (min) of valve and nozzle or Branch connection base material.

2. - Same as VT Liquid Penetrant I (PT)

3. Ultrasonic (UT) - All safe-end areas and one(1) inch of Nozzle base

, g material, excluding the 3.5 inch safe-end reduced lB diameter "ad the va ve to =afe-ead ve d and va ve l base materials.. (Exclusions due to OD geometry

access restrictions). UT included scans for both I

l W

circumferential and axially oriented flaws in the complete thru-thickness volume of the material.

I 4. Radiographic (RT) - The valve to safe-end weld and verification of the Thermal Sleeve location.

Conclusions:

- No relevant findings pending completion of the two(2) remaining RT action items.

l C. D. Cowfer l CDC:bif Manager Materials Technology i

g *Attachmenq jg cc: %

R. Barley J. Tietjen R. Turner pB. Elam

M. Torborg I J.J. Colitz R. Fenti

ISI File

g mc

I .

cc 4wk Inter Office Memorandum Iee Date April 7, 1982 I "

Subject Task #7 Ultrasonic Examination Mudear Results for Spray and Surge Line To N. C. Kazanas Location HQ I Materials Technology has completed the Ultrasonic examination of TMI Unit #1 spray and surge nozzle to safe ends (bi metalic), safe end to elbows and on I the spray line only the first weld after the safe end. The area of inspection and extent was established by B&W per document identifier #51-1132391-00 and

51-1132392-0C. Several reflectors were detected and are outlined below.

All reflectors are geometric in nature and all welds, base metals inspected on the I spray and surge lines are acceptable to ultrasonics. Attached are copies of the data sheets & plots for these welds, also attached are the data sheets & plots for the HPI welds inspected earlier and reported in a letter (MT/2001), dated March 19, 1982 by C. D. Cowfer. Below is a detailed listing of each area inspected.

SPRAY LINE COMPONENT EXAMINATION RESULTS Nozzle to safe end (bi metalic) Resulted : in no reflector being detected.

(Data sheet 000067)

Safe end to elbow Resulted in the detection of several geometric reflectors (data sheet 000068).

A indication plot was drafted to verify reflectors location. A limited scan report I was filled out due to the curvature of the elbow left an area partially inaccessible to U.T. The baseline radiographs were I retrieved and found to contain tooling marks and a poor fit up condition, which is cause I 1st weld after safe end elbow for a U.T. reflector.

. Contained a reflector which was 360 around to elbow weld. I the weld. A indication plot was developed I from the data on (sheet 000069). This data showed the reflector was due to a change in thickness at the ID surface and is classified as geometric. A limited scan report was I completed due to an area that was inaccessible to U.T. at the inside curvature of the elbow.

I I .

I g _ s

N. C. Kazanas Page 2 April 7, 1982 MT/2016 SURGE LINE COMPONENT EXAMINATION RESULTS Nozzle to safe end (bi-metalic) No reflectors detected (data sheet 000066).

A limited scan report was issued due to a large I restraint that was attached to the nozzle's C/S area of interest and U.T. coverage of this area was limited.

Safe end to elbow Detected two(2) 360 reflectors per (data sheet 000065) which were plotted out on the indication plot form. This reaffirmed I that these reflectors were from the counter bores change in thickness section and poor fit up. Both indications are classified geometric.

I

^ Ww I [(Rodne Turner NDE Specialist Approval C. D. Cowfer, Maliefger Materials Technology I RT:bif o Attachments cc:* B. E. Ballard

R. Fenti R. O. Barley J. J. Potter I

J.

D.

J. Colitz K. Croneberger J. Tietjen M. Torborg M. Zeise

B. Elam ISI File i

I I

I

E i

I I

I TEST 3A I

I I

l TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 3A Inspected Item: Make-up Nozzle Safe End (IIPI)

Type of Inspection: R.T.

Inspection and Test Plan: This RT examination shall include areas as required to comply with;

a. The thermal sleeve is tight or has separated from the safe end I b.

thereby revealing a gap between the thermal sleeve and safe end.

The thermal sleeve is in it's "as design axial position within the safe end or has moved axially.

The outboard end weld retainer buttons are in place and not damaged I

c.

or have been damaged or are missing.

Yes No

/

1. Is the work secpc in agreement with the B&W Engineering V Informatian Record?

2. Was there an approved inspection / test procedure used for this examination?

I

~

3. Dose the'results of the examination agree with the acceptance criteria' called out in the inspectien/ test prbcedtire?

4. Does the quantity of items _ inspected agree with the minimum _

requirements called out in the procedure? (Accessible I quantity inspected NOTE:

Minimum recuireo'- .)

If any of the answert to (1),^ (2), (3), or (4) are no, a written explanation must be attached.

I

5. Based upom the results of this e:csination, were there any repairs made to the item (s) being inspected, or recommen-dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not _

been (reported) processed for future resolution?

NOTE: If any of the answere to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. //3 23 9% oo I 8. Task #7 Procedure No. NfS[X b /- /%/M

)

Reviewer's Sigrature /1 I, g.a,ea __

/ /

R I

lE i!

. C _ 7 AESL'?j_*;CI CD: F Cf.TIONS /O-E?>.TIONS

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/r* Y ?) $~~ ibe o* t'i , (~/1* a I , 0 . # ?

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~

Method: Vicual: k' Direct Measurement: Document Review:

E

References:

Other: 5 8* '.r-Titit I .

B W A.)_. (7m.2~FD-dM) Rev. Date y , y. p a.

Var

ied Q s

]~

_Vendcr/Iten Item / Characteristic / Accept / Inspection Identification Activity To Be Reject c-,i n n e.

(as appropriate) Inspected Results/ Sat Tesat NF.

f ?t/ I' 9 0 0 Criteria Readings Ap; R X 2*Wis u T~e d o!!Ar$ AW3/ 8317 1 f

,2y19 Gr G ilCd<ofa ble 1 00' > '

tiiln ;t ?AR& i S~ m e Tichir e n c '

i 49+S 70 t '

t

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.. MO-10S-1 (Rev. 0)

TsA l.201 A.a r.

. :: ,-. C ALT"""i C0!C: 01. PI).'C OSSFECCION ?.E? ORT :

. _ . . . _ - NJ46/)

c. : n . e s . . : , i f.::e : . .nste::. n I :

I . r- : t. crr

.: .f ;:--fr:ci

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I

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l I

l 1 1

I i

i i

I i

l l

l I i .

E. I i -

..-T. I i i I l Mearurine and Test Esuiement Used

[. Identification of Equipoent Serial Calibration Date Dus I .

E/

.. 1 l

No.

I 1

g ;

1 - I I_ - q~ i 1

.3 1 l MNCR Issued: Yes l l No l E" l QDR Issued: Yes l l No lPl id M3CR QD?. No. Date Reason for Issue F.:'.t./ Cendi ,

~

Release

.pd --

Tag Nos.

O !s su ed h?'. -

\ l 1

l I f / /7 l

I tE -

t i /W /1 l I l I l-R . I- 1 I

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Da rth 4 75s ^ &mdbri. red d 71e BM9mpf thdsni1Mi r ~S & M/W i*p.dsisor*wl.s E~~..it '~~~

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.,~[5 ut(dr tr7e via e sad s7H/ PC e d -37~ un.e <%n2 mr -rb simL "s4 m Toec (8av?>i) Ns/Js n not. o r.s . '72s As bss'7%c2 7% e .Vro " dimrtes r/re.

&~

I . * ~~ ed .2% v < *v o MVto) JS o </9H . 7h cer.1srA e,aJ uJ 7L* hdina r sol r udieMs

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w' :7. . .

[55..mA -- c -Q , - . y.m . , ,,.:n........,. ^

,. ..,.,.y,u_,,,_,_.. .;

. .; , e n. yg . .;_,. .,;,_ , . - -

. d: .c . g,u

. p g[. ,, Date: J.pg,2.

- .- .y..... ..t. 2... ., , _

1 I, _ . --Inspected 37 :

g Date:

{' Reviewed and Approved 3y: ,,

E 5:23 Distribution (() Manager Adnin, and Services Uni: j Crig.)

J- ' ( ) QA Mod / Ops Manager

( ) QC Manager (y) Tile ..

[5 L '

Others: ( k') / 72 AVr sfb I (

(

/

)

F # . / ', i s t /Bc/ @

Mo-les-2 (Rev. o)

, i. 4 > . w. Fo p,,' .

G ;.. ,

l 6

l n l ;/w us-.,. y

i I e . :th ,

5-ELTER ACCK ROAD

.E .

E iR t' OtiS C ANBU AY. CONNECTICUT 06810 ptG(m: J A mt p**% om , %9 : \/

I Ps ras F f% O F. **

e-

I e6 e np s* es e=* F '. P* e*" >= 4 4 9=* P a s J % kor t V % # h 5J% b g 6 a 45 6 a V 4% a

~~

. 2 l i A $ ".'.)]

cu90 l o, ?rd 'm C 'EI RADIOGRAPHY RFPORT NO.

'qcc ;do. ACC RU Coo.

REMARKS DATE *f-/ P- Mr

- ' -M ,I t/ cus,~,,e, & Ofj I I s' E / Addr ess W

A d3

' Job Location /M -

l k_'/-[ : th Customer's P.O. No. ud No

~b ? Si a k I JUOU?m t*nd 5fn l tem QtsCF'ption - *

b*

I l

'*$l 51$ bl-IdA f* $A/f 20/[L/ 100% lnsp. W gyn,gn,p,

[A/ 8 Welder Stamo p/#

I- I I Amount WORK

SUMMARY

item Descretion

' T;:a ws i A.M O A te , , _ ,

I _ _ _ , _i I

l l

l Travel Hours Ft.; Plate Weld N P.M. T _

Lunch

n. thk.

P.M. @ _

Standby _

6.,,,,,,,_

I ,,, i. i_

I l

l I

l l I Ea,P..e /e:s

/ Y F.trns, [ L x /U

F .6ms, x

n dia Typc0 Type s < I C.__,

4.,,,_

9_

! ' . h el '. r- a n 'r <1 d m 6f P' # el 'd iD 7 Emoosures i_

_ ' D !] # Slm Ws, e] r Sm IW s**

I_ l.% . o lle L ",-L 4 % b r r*= f $/dru t . /tWS $$

es.___

I Wu F" ',)p !-!? Ai U hMS/A}s rls*[r,,,% , TECHNIGUE DATA I I /tfe-l 4 # b r*v w T Mel[e d i A/<9 /M ov/r't n T inspection Specification N(/ 85'"8Mf*

l . .c -WL t- Us%e*s'oFM hv' Aceep,. nee Standare AM f 1 2247 I l[ ' ..! M 4 m .* h r- i .fb > l RT Procedure No. b /* M I l I

I l

i i

Shooting Sketch (RSSS) Y Physical Source S. sed / Yil# Etfective Focal Spot SF 0 Sou ce toi Ob ect /I, 8 iM I k' '!

Material ThicknesyM[

Geometric Unsharpness (Ug)

No. cf C.im oet Cassette

>MU#

Type MateriarN I#

Penetrameter /dS+m[h[

Mk.I-I

i l I viemng: Single Pb Screens Front >

Masking or Blocking Used 7 8 ~ Center Superin. posed

~ Back O/A Exposure T me /2 /77/A/ Dev. Trne Yerb ./

Type Source ,-Ef / / a*L Curies // 3 I_ _ 4 DEFECT CODE s .c- 7.n V : e 4 . ;... . . p , pgg . : . Si g ,

Tl - Tgm WM I ' ~. . C '- Crack ~ '~' ' ; BT - Burn Through CV Root Concavity IF - Incomplete Fusion 'OT'- Drop Through Cx Anet Convexity SL - Slag Lmes UC - Undercut O X - Gudation i @ -7 O LEVEL T ECHNICI AN 2 LEVEL

, ig M NICI A N /

j 3.* b e*< ! r' > N. LEVEL %

mC-C_N7mee I , , ,

I t I i !

A A a f ' f 1A.;*/ .

I ' l l 1 .2% ,Y $ S' t? T~0 I .

4.-..........,...,,,.,cu SHELTER ROCK ACAD L e.un,

~

C .M # CO M7CT Of410 p g.-

I

7 .

O .y NC b ,,3I\ I r , i o %

N A L>t U (.7 k.h A ? .-

l' ra I 53"(( j .,.eid . Fism 'C' REMARKS RADIOGRAPHY REP,O, RT NO.

eiEce .a j es. No. ACC R EJ.

Cod' DATE S-6<~

. / s f.,,/2 y-I

- f ' is Customer * .

I/ .?-- / "t7 /)JD r IA/ f g fp # "

Address M i l3 $ f B-/ Job Location I

l

-~ [,~ -

I/ Mefr# ge ss [. ["% Customer's P.O. No. Job No.

I.$ ' O / l stem De'scriptson lb. " S'l h* n O [-O / 100% insp. V Spotinsp.

I l j Welder Stamp Amount MjM WORK

SUMMARY

item Description I I k

O l

Total Hours i Travel Hours N

A.M. O P.M. T Lunch A.'.*._

P.M.@ _

_ Standby _

I in, thk. ('b _

l l i Ft.. Plate Weld

' ! Ea. P pe Weld in . d.a. 4

' ! / Films. O TypeI /I G_,,_

MrN bfM/ 04 **-? 8 [/ f I bh? 87 f"#M Films. x Type G.,,_.

J'*l 6 b/ $ l 51"/m de i c'J**s>f /W ? Y E , posses p_

? Y ~' & t' Mi & Yr4 Pf" n1pl No g*L/l* j p_

T-r s f l !sld/.s'!I ~'7t.)d Nr r/b/? NoNeh hiis /./N^

l //c [8v3 y#8 De /M'I~f . A/o A10 V4*/* *ra f TECHNIQUE DATA j l OJ- d A p* M Ad 8/ NT/ # Mof#d b/ Inspection Specification I O/y*s#> / SC 1/ dd ' b [/*s .I' Acceptance Standard A/d/ 7 I l ~77 b h-1 I 01'If

^ Crb'7b C k}P** At.1Y' Se t' 1"-: km $Nooteng Sketch (RSSS)

RT Procedure No.

b M r r fe*./ N b/re M /r v e[.7//// WT.Md Physical S urce Sue L/ WI /"Ef fecttwe Focal Soot /M N'b M7 W

Ub#

I ! < .f Y/d[ v'h L e e e.. ko i b

/4 N ,

/d# SI#N 8/e# 4)MS di:lPNd 04/

3d estI ./ .M/s d#J d)[M M*-

t'NNr*No-3/l.f. N t' YourI~Y sk SF O Maitrial Thickness ' /

Geometric Unsharpntss (Ug1 Source to Object

[

Type MaterialMN OO S

," ' [' 'f , e f". 4 - 0 Nc. of Falm per Cassett=r S Penetrameter Sher t I

i f/f.

r, c' s 3, s ,,,

4u 7,t on ,-[e /#d er /rene t/7"1. 67?ie[es/4thlViewing: Singie W Supe imposed limo. le5 5 'TGb "T~b # fedriir!d 804ffMeS Pb Screens s ;ront iW$ Center' Back WO ~

/As no ri es/ M; m F Nr5 Cb e % 9/-=t*pm/4"'Maskeng or Biockinq Used

\

l 4l /b a r a r> / ([ r ,., M e e/ '7f* # 4b* Exposure Time O 8/V Dev. Time N*M l jQ U /JY1 or P1 &R la e & Te Ob N* O Le ff sl}M Thoe Source $r* }/% ' Curses $l' 7

'7[, 0 flW e' , 3 (#,l 04 Mr*Y . f [e r [. ' 4,...u

~

-: . -- OEFECT CODE

~

'7Ff p son Tr M/rb #[ MO p d spi [f/m M - brosity [$1 -- SIaYINclusaons Tl - Tungsten inclus.

' BT - Burn Through CV Root Concavity ~

l

f e M , . s IJ/dh 4 d

b O f t*/ fM A/ D#

/D-Crack-

. IF - Incomplete Fusion DT- Drop Through CX Root Convexity w, cy e 4,J,/ #,/J.s <

SL - Slag Lines L;C - Undercut Ox Oxidation I

n ,. /1 .

(, *s W & 5% *

M/Th M/* Ci/ LEVEL _

~

I / 1.

T ECHNICI AN I j l

l 2.

W VE LEVEL 3.

I T ECHNICI AN, INT ERPTpiT E 53

! l l i ..i . i .

f'

- t rn . o pasy

,0 f b( .

- 5 .. .

v l L iu , Ts EiC2.' _.w . aC SHELTER ROCK ROAD FIGURE 4 C '.i."v CONNECTIOUT 06810 I - e miAA, K A vium] APhP'i Ktr v:u r- . j

~ 7 mPmA.N "'"

i l'iDr/. c V J c A, r. , s , RADIOGRAPHY REPORT NO.

SE"hAENj se;d . Fam ACC REJ*

Defect Cooe REMARKS DATE S

20 ** ' -

No.

PiF N NO . No. M O />

/ * /'#c - v; .' -/ i./ ' evste,,,r t

! /' b /

I Address I.

I I-23 / Job Location /#7 I I 3' N / 7M _ Jots No._

-- Customer's P.O. No.

l i I v. ' s - /A (M 'N ---

Item Descr:ption

[ .

I 4b / 100% insp._ V Spot insp.

! b Welder Stamp //

WORK SUMM ARY item Oescription Amount l [

l M@ -

Tota: Hours i_ A.M. { _ 3.M. @ _., _

N P.M. T Standby _

Travel Hours _ Lunch _

I -in. thm. @_

I Ft.. Plate Weld

! I f

' Ea. Pipe We:d

n. dia. @__

l _

g, l f /k Films. I'"5Z. x . M Typeh C

I ! Type _ -@ _

) F ilms.. _x

! l !

I #

7 .Euposures I l bSMGEMIC / h O'#*#d IC @_ _

fri UYnU! l $ N Y N5t/n i / 6' l 1

4) f 5 TECHNIQUE

- AM

' ^ ~

\ L c/-:>r/Q W Ynen & v/ude DATA I

% /* [c /Of W NA*/ Vo Srible 8h del-5=T inspection Specification _ N// 3/MMN l <93"'8 M> BMf"#NI #hM WY S-N* Y

$[5 YC r~s n b d H /PYt' Acceptance Standard I- l N /~ N P t Y rv T 14

$rJN 0 71 M r*/ W n/ RT Procedure No. N b l* N?

I /N Y4 c) I -Ar)

\

Shootog Sketch (RSSS)_ W l n / #X/// Effective Foca Spot i M_

Physical Source S.ze

(( E

/ # Source to Obiect N I

-. SFD Type MateriaMf//fc Material Thickness

/UI r

-NE #

h,:=. Geometre Unsharpness (Ug1 2'

I No. of Film oer Cassette .

S Penetrameter / d Shim I Superimpos J I viewing: Sengle Back'd

, :_.;h .

'* ~ '

Pb Screens Fr'onti / A/O ~ Center _ -- "~ -

.::: g ~ Masking or Blocking Used . - ,

j Expo'sure Time /M MN Dev. Time I/# ^/__

-** - - - * ~~ Type Source JN /9."2 - Cur.es //d

. . OEFECT CODE

'-- T;fl. ,M-

s .m.W M a r,-i'

.g;y Slag inclusions Tig Tungsten

~ ~ ~ ' " '

}m < ..

' .v;d.- c.. N < f *. - .- M':W **C ' p ;,' po,gg-~ii-0. # S

' BT. . Burn Through CV U Root Cor rc C -- Crack : j ,

-.h 4

-w .4, IF L incomplete Fusion DT -- Drop Through Cx i Root Cor

- , . . .p#. : s I g.-] OX Oxidatio-SL- Slag Lines UC - Undercut

... [

[

=::. 1. CWO %.Y!2 /~ V( d f LEVEL Y TECHNICIAN f_

' . gt.

I J

2.

7 LEVEL r . ;. T HNICIAN

5 .. c

" - LEVELC M 1A 3./ 6 % PRETEP T ECHNICI AN. .NT

'~

I j l .. .

l ,

l . . . .

..,.-me_

l

l .

c<. n p-r w

. r. ._ . . .

n?-

w

..- pa } ~, r3 v'j ~

o 3 , . - . .

~ '~

AJO'Jit R EidERGY EERVICES / ~

SMELTER ROCK ROAD D ANS'PY. CO .*.ECTICUT 0S810 I k.e p._ .p. ',. .g ()C D A P,U ym. D C I)ODT m mn. ,

ta, A/f* W Cr (W<j/*

SER AL NO, n y,,,0 p ',* Defect ptECE NO No. No. ACC REJ' Code REMARKS RADIOGRAPHY REP,QRT NO.

DATE T-20 _

, . 'l./ f I 's r - l V TC Customer WN

)E /- d

,2 S V

Yl Address i-

5 _

i l S' . C/ Job Location M-1 l '/d V l' II Customer's P.O. No. /

kt. No" 3*d item Description h2 bdb ((h M-O I/M NON d A/ 100% insp. Spot insp.

k

[

Welder Stamp [M WORK

SUMMARY

E l Amount item Descreption

Total Hours I A.M. O A.M.@ _

U N

P.M. T P.M. @ ,_.

Travel Hours . Lunch Sta'dov _

F t.. P! ate Weld in. thk. @ _ ,_

l l I V-..l. $ iraAt /% ?.pr'Ocl WWh .n. dia. . . . e_

1 1 V.;.Y, A L ~. /.S % d-%n su /et ea. F,,rns.P,pe c' Web-, /sT,,e /~? e1

~

\ \L~lb77 h/ ? - !Yb.t. m o / S/.m 'P . e__

F ems. x Type @

%Vk!s///W -7A*rl R. <- r i h/s eleNeTE ~? esposures e_

d> :d/7de-sif7* de ~leeTe ,/n e_

, . - > . . v n 1. L ,~A'~e 4 I~7I~,o e nr L ' S ! u j e b*/ / 5 - #d h y ..y , ,) yy, lMfi f'm p sys'c g TECHNtGUE DATA k inspection Specification [N// >(/3'7O f I Acceptance Standard YI!' E !'

b RT Procedure No. Kf6 A fr'

'.; Shootmg Sketch (RSSS) V Physical So Sire / [Ye/kf fective Focal Spot /!

5 SFD Source to Obrect / .

W ~

e EM i Material Thickness Type Materia MI Geomete.e Unsracea ss 800 ' N "> 4 f No. of Film per Cassette E Penetrameter. /6 Shem !b h Viewing: Single Superimposed Pb Screens Front /O O Center Back k Masking or'Blockmg Used f

Exposure Time /M 4 / / Dev. Time dM M

~

Type Source [v' /[b Cur.es [//

y. .,_V

[ v ".a-

. f,i <. -

. . -* mp,9 + ' . .. p r ,. r ,-

- DEFECT CODE

( '

'. ~ '

.t'. '

i P - Porosity 1 SI . - Slag inclus.ons Tl - Tungsten inclus C - Crack

BT - Bur. Through CV Aoot Concavity IF - Incomplete Fusion DT - Drop Through CX Root Convexity

's SL - Slag Lines UC - Undercut Ox - Ondteon

1. M#/ /* TCM LEVEL T ECHNiCI AN

2. - LEVEL g

3.

,E _9 ,N,E,, h M ' ~ LEVEL

I f

gps Inter-Office Memorandum Data May 18, 1982 g g{

Reinspection / Radiographic S Technique of 2 " Sch. 160 6111-82-2079 I ubj ct Injection Nozzle.

L ation TMINS Trailers #256/258 To N. C. Kazanas Director-Quality Assurance I. General:

This examination was conducted to provide additional information of the area previously reported (re: QC-CL-394) as an intermittent line 1/2" long as shown on film #0-1.

II. Scope:

Endeavor to reproduce the condition exactly as shown on film #0-1, fron that position point make one (1) additional exposure on each side of that point. The distance / separation I between exposures should be approximately 1/4" using the I.D.

surface of the safe end as a reference.

III. Evaluation:

~~

The re-shot representing the orginial 0-1 position was found to be misaligned approximately 1/16 of an inch. The two (2)

I. additional exposures were found to be approximately 5/16" from either side of the 0-1 re-shot position.

As a result, the area of concern has been exposed to six (6) radiographic evaluations, (i.e., two (2) original exposures taken during construction, one (1) taken on 3/6/82 and three (3) re-exposures taken on 5/12/82.)

With exception to the 1-0 film showing the 1/2" long inter-mittent line the radiographs were found free from any linear I indications and the condition reported is considered non-relevent.

I. JET /ej g

/ 1 ; M *m Q d o tr. Inspecticn Supervisor ra o dated 5/1 /82/MUV-94

~

cc: B.'E. Ballard, Sr. w/o attach.

C. D. Cowfer w/o attach.

J. J. Colitz w/o attach.

I R. F. Fenti QC file w/ attachment CARIRS w/ attachment w/o attach. Soooos4s I .

.. c-___,__ , __ , , ,,- ,

i 11ELag NUCLEAR ENERGY SERVICES I MELTER ROCK ROAD DANBURY, CONNECTICUT 06810 FIGURE 4 RADIOGRAPHY REPORT SE "o^n'"

Weid Feim e Ru D

REMARKS RADIOGRAPHY REPORT NO-No. No. Code gg c=" , n y I PIECE N Y NO bk bd Customer #W

/~da8 Address 011 ,j

~

f/h Z I Job Location Customer's P.O. No. Job No.-

Item Description 8d ' EI //d ## Is t' -

100% Inso. Spot insp.

Weider Stamo /) k WORK

SUMMARY

Amount item Description Total Hours i A.M. O A.M.@ ,_

N P.M. T P.M. @ _

I Travel Hours F t.. Plate Weld Ea, P pe Weld Lunch in. th k.

in. dia.

Standby _ _

O I [ Films.

Films, Y E xposures X

x

[ M T,ype Type r //1 @

b (4 r>r ,a r. erv7* C&U- 6,0 - C L. -3 W e._.

I 'h-WI *1 16- 71.

j l

(1) / C Al/V TECHNIQUE DATA b l t']!*00h5 (OYe M 9$6 0 Nlt Idh b inspectnon Specincation JP tC YT $D D$d &Y fC $$ /bl# l /N' W

/ Acceptance Standard N$l bN' )

M/b/C bbE'N r ?t<J? ? 4 YPY/Ma b bbNi/C RT Procedure No. Y /l I' A/ k

/A/ d 7. D

~

d b 8/d 7, Shooting Sketch (RSSS) b MdB 2 tb A/7" 7 N//* Me A/5" Physical Sourc Size / #M //

Effective Focal Spot i /# "

b . SF O Source to Object / #'

aJ *~ *M d Material Thickness DI Type MaterialbU 'UM I # Geometric Unsharpness (Ug)

No.of Film per Cassette Viewing: Single

' C#' 3 Penetrameter /f Shim /

Superimposed V I Pb Screens Front > SM Masking or Blocking used Exposure Time M /// / /

Center - " ' " Back e OM

Dev. Time IM /**

Tvoe Source If* /#f Curies / J/ -

DE F ECT CODE P - Porosity SI - Slag inclusions Tl - Tungsten inclus.

C - Crack BT - Burn Through CV Root Concavity I IF - Incomplete Fusion OT - Drop Through CX Root Convexity SL - Slag Lines UC - Undercut Ox - Oxidation I ,

1.

2.

I dJ /r TECHNICIAN N/- // D.,/ LEVEL LEVEL CHNICI AN I 3. . 6+ M d T ECH NICI AN, tN T Ef PR E T E R

~ * ' - - ' LEVEL.

I TEST COMPLETI0M REVIEW SHEET I Task #7 Inspection / Test: 3A Inspected Item: Make-up Nozzle Safe End (HPI)

Type of Inspection: U.T.

Inspection and Test Plan: This examination includes the inconel buttering which has been PWHT, the inconel welds on either end of the B-166 safe end, the B-166 safe end and HAZ, and the 304 SS pipe and HAZ.

I Yes No

1. Is the work scope in agreement with the B&W Engineering [

Information Record?

2. Was there an approved inspection / test procedure used for this examination?

[

3. Does the results of the examination agree with the acceptance criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure? (Accessible quantity inspected 4 Minimum required f .)

NOTE: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any [

I repairs made to the item (s) being inspected, or recommen-dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not [

been (reported) processed for future resolution?

NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. N-/[82M d

8. Task #7 Procedure No. /MdS- 407 / .r-do((/Jhs5-d/

Reviewer's Signature %

I I

I Test Completion Review Sheet Comments Task #7/ Test: 3A I Item #1. B&W EIR No. 51-1132394-00 requires an Ultrasonic examination for the entire volume, from 6" outboard of the nozzle safe ends pipe I field weld to the tangent point of the transition radius on the nozzle shoulder inboard of the safe end to nozzle shop weld (see Attachment #1). This type of design / configuration is not I incorporated at TMI Unit #1 site. TMI Unit #1 has a valve welded directly to the safe end (see Attachment #2)/ U.T. examination was limited to the C/S nozzle, C/S to S/S safe end weld and up I to the transition on the safe end. In conjunction with the U.T.

exam a liquid penetrant and a visual examination was performed.

Item #4. Limited accessibility as stated in Item #1 above has affected this item. However, an effort was made to attempt to achieve as much coverage as possible. This typical of all four(4) nozzle safe ends examined.

I I '-

Rodn y Turner ND Specialist I

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gg 33 m M M M M W W E W E E E E E EEjWuef."ar NDE Calibration Sheet Sita: g/2'-/ Inspection ID: Af/j9 ComponentJaPe ced. /"(( Procedurefj)/y'y_ cof #

Rev. [

Examiner: [ d [ A 8 Y g e/C 10 #: /f4f.9 Level: [ Couplant: JogMdfC go Examiner: [ A //j9' ID *:

[/ Level: ///j/ Couplant ID#: g/7f//d Drawing # fft0 (L( [.,'/f' /go(f3f Calibra Block Date:#Aetg(, //

}ry y e: / f'f C Instrument Length 5 in. Type J Typeg gs F ID d- 00 2 Length #

IDa- Oggy OD //- N7- In. Freq. d 2 5 MHZ T///I' O / d Thermometer Linearity Check O Yes o Te p / F ctual '98 Req re nt r '75 o ing)

Reject: oFP - System Calibration Mat'I. Cal.: 2 70 Angle d8 o Cal. Dir.

100 % DAC Plot Delay: O. ,yy Axal uc. O Amplitude Screen Reading 1 2 b Pulse Energy: jfj 90 Reflector % of Full Screen ininches go Coarse Gain in DB: 80 \,

Fine Ga.in in DB: I2 2/8 Node f'd % . T /.I In. 70 3 Nd 6 Fine Gain: 7 Jo % /. 4 Ag in. '\

50 Screen Range: I # '"' 40

- ~ ' ' ~ " ~~ ^~

N de % [ In.

I8Y 2 22 ~

Screen Depth: in. 30 In- 20 C T&R Operation Top Notch % in. 10

(

Opposite Notch I "" "' "" "" "" "" "" "" "" ""

Frequency: 02, g MHZ

% ( In~

O 1 2 3 4 5 6 7 8 9 10 Pulse Rep. Rate 8/R Notch j % \ in.

Damping //1,g Bkr CB / % ), In.

Filter ME8 8kr P d' % V In.

Calibration Confirmation Remarks Time /S.'Y3 Hrs Hrs Mrs _'

, Hrs l Hrs hg j,,, g gjpfe b.S Back Reft. g,/A6 pl/htn. % In. g % in. .- '% in. /)6 in.

Al8 Node [C % ,3/J1n. % in/ % 17 % 'In. [% In.

& 18 Node 20% ,o ez{In. % )b. % /In. % in. l%

in.

18 Node p/f6 g//1n. % j. lIn. %, l In. Q>f% in. _

Top Notch f% [ In. %/f" [ In. [ In. ./% In.[ % in.

,ggf' " -

Opposite Notch [% in. 9d In. / % in.

% In/ % In. Reviewed By: /4 -<*I< - '

M%

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Notch Y In. % % in. % 1rl. % in.

Level Date ~/ 7 b Initials M )

9., cB .aaca aevi,ci i,TF,om Cat Bincke Bhr P (Back Raflectinn from Paren o

e sus amm um uma e um m e met me e uma e e c - tsc ear 000174 NDE Calibration Sheet Site: <I ///

.2~~ / Inspection 10: g/g Component &A.. od #[ Prcesdurejj/jJ.oof Rev.*[ f Exandner: gMfg g.g,jm M T gger 1D #: ///f _ Level: I Couplant: Jogobge y Exam;ner: 0 ,U,hf- ID5: fjff- Level: p{// Couplant 101: f /ffff DrawingMf da ,5Jij/ /gf of'f34'

? l 30 8 Calib nClock C# "' y

,C Date;#)1Atd //lj9)Z Time: //l2 O Search Unit Cable instrument Length 5_. .

In. Type d Typejy//gspf 1D -/3 007. Lersgth / #

,9 , . Offy'2/' OD 'Y'f8 Thicknese . NO In.

In.

Freq.

Size c3.2 t'~

'4 2 MHZ In.

3 , fg acfL Linearity Check G Yes RTio 8 " 9" * ***. ' ***'*

Temp f/ of Actual Required Winter .'75 for piping) .

Heject: o fE -

System Ca!;bration ,

Mat'i. Cal.: /8 _ Anete N o Ca!. Dir.

- 10% DAC Plot De ay- IJy Axial O Circ. I . ,

Pulse Energy: /@N Reffector - % of Full Screen Coarse Gain in 08: , 80 ininche' 80 <

l

. g c2/8 Node #

fB % , 8 7 [ In. 70 ---

Fine Ga.in in DB:

Fine Gain: ~ d *

I"'

50 I I"' ~ ~ ~ ~ ~ " ~~

Screen P.ange: '

40 ;

i Screen Depth: _.___A I7 In.

I % \ In.

30 2

~

- 2 l CT&R -

/

\ % \ In. 20 48 Operation Top Norch % In. 10 i l Opp 5sNe Notch HH IHI IHI HH HH HH HH HH IHi NH Frequency: 'M- 49 e _MHZ ) % [e in . '

O 1 2 3 4 5 6 7 8 9 10 gg Notch /

\/ % V In.

, Pulse Rep. Rate Damping /fhd BkrCB ^

% , f.-(0 in.

Filter oM Bkr P /J/p_. % f>/j p in.

Calibratbn Confirm: tion Ram ks Time / f'; y'd Hrs , Hrs I ffrs l ' His '# ' " N # !

{ks l Back Refl. / //)l6 pifb2. % % ,l In. %

in. h in. gg J df - 4 2.dj, cd-18 Node 70% g/An. %1 /1 4 .

9d in. j %' in. j6 In.

l 18 Node},'96 ,ff4n. ' % l l{. ) In. l .% in. {% in. /'bl hEl ~

           /8 Node         [%          [ In.      %     [ lh. /%                     Igr.'         %               In.         %           in.

Tcp Notch \_% kin. %- [ lq. [% [in. % A - '% In. Reviewed By: /m 4 s '- 7 ' ~ l Opposite Notch 8% ' Min. %[ In. / % [ In. % In. % in. j-Ll4xc8 M -% ,7foin. *) I rf c& In. % in. % in. g, g fdf& h/ 9,, , 3.& Initials 8 / / ' 0 r CB . Rack Reflec'i$n Fiorn Cat Diockl Bhr P fBack Reflection f#om Partl 0o00927 L ___ -

sum uma sus sus aun sua e e saa mai asu aus seu e 'emi Er sus 000175 NDE C:libration Sheet Site: g/f-/ Inspection ID: A'M Components. es/ #yf Procedureg,ooy Rev. 4/ Excminer: [MJ/ 4t p 8 Y,c,ve,q ID#: //g8 Level:[ Couplant: Msgg/'ifg M JO Extminer: 8 ///// ID#: //j7 Level: ,M[ Couplant ID#: f//ff/O DrEwingNf'fa) gJ,,)f'/g effjf"' iD MQ tD j_ MMf en hU ab e / instrument Length I In. Type /- Type /pgfa g ID # 6 40 2. Length / in. Freq. e MHZ ID#: 0/I'V2 # o , Thermometer I#//" O/d I Linearity Check O Yes Erho Te p *F ctual d Requ e i t r '75 or i ing) Reject: 08/ System Calibration Mat'I. Cal.- /d 0 Angle .J2__ o Cal. Dir. 100 % DAC 110t

                .         0, f2,                                                                           Axial jp[r Cire.

2 $ 4 s Pulse Energy: gp Reflector Amplitude Screen Reading go b

                                                                                       % of Full Screen               ininches             80           "
                                                                    /8 Node              ////@'           %           // [ A in.           70 Fine Gain in DB:                                                                                                                   60 g
                                                                    /8 Node                    k          %             [         In.

Fine Gain: 50 Screen Range, . jir /8 Node \ ~% { in. 40 30 :

                                                                    /8 Node                               %            k         in.                      7 Screen Depth:         -

In. 1 In- 20 CT&R Mormal Operation Top Notch / % I in. 10 ijn Ini ny ini ngl lIn In; ini un lHl Frequency: I0 MHZ l- O 1 2 3 4 5 6 7 8 9 10 Pulse Rep. Rate M # '"' Damping irjit) BkrCB }{ i) % ,)lD" V n. i Filter o8k Bkr P /0 % , ye o " In. Calibration Confirmation . Remarks Time //;/f Hrs Hrs , Hts ) Hrs ,/ , Hrs WU='l' Back Rell.I' fc % ,foc in. % lf % frf % In,! W'l In. . _ yg y fp f

       /8 Node       gfjf6 g[gn.               %        /n.         %          [n.        %             [.        ((               In.
       /8 Node        [%           [In.        %      [ In.         %       [ In.         %      /'In. [% [                        in. [4/CT"       ::'         F4l N            ;F~d      [#
                      ?%         f
                                                                                               '                           **'~

18 Node I in. % l In. % l In. W inls %l In. & gwp & f,g*ym y $7~ Top Notch % In. % / In. % [ In. [% jd. "/ In. ,, . Opposite Notch y% In. g in. [ In. [% [In. [4 in. Reviewed By: J .. . Notch f% [ In. [ In. k [% [. %

                                                                                                 / In.              #
                                                                                                                     %             In.

Level P/ f DMe "'l~

-'?

initials @ / y / ./ sh, CB (Back Reflectron From Cal Block) Bkr P (Back Reflection from Partl .40000927

m W W m W m W W W W W W M M M M M M M Nuclear NDE Thickness Data Sheet I Site: I//f-/ Inspection I.D. //g Component:p/v-[f/ Mc cj2 D1scription: ggog e g g' Jg/,e eyd f,)(fg .fn- ys31/c )ff} Cal. Block: pyc o p4& gg] l.D.:pv_/ 94/ ,gg a e g Drawing:Ae /4'dyffy l Procedure:g).oof Re'v. [ Material: /gge/ Thickness: ,go Examiner: [fM A,% g %A= pea = ID # ffdf.8 Level: I Examiner: 8 //g ID # g//A Level: f[gge Position # Drawing Reading in inchea g 1 ,foc 21 41 61 81 101 121 [ 141 - 2 , 22 42 6[j 82 152 122 [ 142 3 . 725 23 43 f3 83 [103 123 [ 143 _g(g 4 24 44 [64 84 [ 104 14[ 144 g ggg/c f 5 25 45 ) 65 85 '[ 105 [25 145 gf 6 26 46 [k 86 [ 106 / 126 146 h 7 27 47 [ 67 87 f 107 [ 127 I47 (( 8 28 48 [ 68 88 f 108 / 128 148 9 29 49 [ 69 89 f 109 [ 129 , 149 K' 10 30 50 [ 70 90 til) 130 (( 150 t 11 31 51

                                                /           71 91/           ljt I)(     /    151 12              32 5[             72 Sf            il2       /  132

[ 152 13 33 [3 73 f3 / 113 / 133 [ 153 14 k 34 [54 74 [94 [ kk114 154 15 ! 35 j 55 75 [ 95 / lif N }35 155 16 36 / 56 76 [ 96 [ [16 [136 156 17 , 37 / 57 77 1f 97 / / 117 137 157 18 [ 58 78 Y 98 / 118 138 158 19 39 [ 59 79 99 b' 119 139 159 20 40 60 80 100 120 140 160 Revi:wed By: ,.8((w[ Date: 7/jgh Page / of / . A0 '20 O G. )

w _- me sup _ sus _ sus e me sum me sus som suas ._ use _ sus au Nuclear 000059 NDE Ultrason.ic Data Sheet Site: g/[-/ Inspection ID: ///9 Component: JAA seld

Description:

gipfe ep/, 64fg g%s/ gj c/V.s .,t, /s/de g' -/-o /dyr/e Cal. Block: 633 1.D.: /// g)-pd fg f .fAFe d Procedure:M f-gof Material:[g ,/ S/J Thickness: , [ff In. Test Surface: 4. 3. No. Positions: / Distance: //A In. Drawing:gfal //dfFf# Cal. Sheet ddd/// Cal. Sheet: ddd/[7 Cal. Sheet: doo //d Beam Direction / Long 2 Shear Limited Exam O No M es Angle: O Angle: g/ # Angle: g.f'8 Examiner:[ ,@--fpy,e ID#:jggy Level:g Time Start: //,*Vf Hr. Time Start:/2.*J9Hr. Time Start: /f f)> Hr. Examiner: U

                                   //A            ID#: g/g         Level: //p-    Time Stop: //.'47 Hr. Time Stop: /2;./J Hr. Time Stop:/d/*/2. Hr.

Notes: Part Temp:/42 c oF Part Temp: /d EO *F Part Temp: /d L 0 "F Date:pt4414 /J'ff/2 Date:ps*<cd /1,'/fJ2. Date: #Aeef/J,'//fL 0* Information Only .. Weld Height N85{ Weld Width I I## Surface One to Surface Two BM Haz @ W eld Haz BM 171 . . Wo . 710 7so_ , 700-LAM LNGTH WIDTH Through Walt Dimension O Minimum Maximum g 2 o

             -p               8      yg            y        y                       Position            Position d      9       e        6      E             G       S      E                   In.                  In.

z e M 4 m ? .9 o r r E e ? 3

                              $      a     E O

E U 1 2 O 1 2

CW' CCW 1 2 CW CCW CW CCW Remarks No Reportable Indicatiorjs Reportable Indications O Non Relevant Indications Revit..ved by: g // Lp,ypj:, g Date: f/yf M Page of NDE Request No. gfy

I Nuclear Limited Scan Report r Data Sheet No.: dd d d-NDE Date:,yg,ggj z Camponent:gsp, gg ,y //ft I No ( Surface 1 g Beam Direction 1 CW X I Limited Scan Surface 2 inches from Reference Point to Beam Direction 2 inches CCW . From Reference Point. inches from Weld Centerline.

    =         For Angles:         O'            45    )(                 60a                Other Due to: $0A?!OJ W'00 Af SAff VY                                       Y                    h< NY Examinergf                                        I.D a- ) f'4]            Level f ^            Dategygfjjjjpg I                           No Surface 1

Beam Direction 1 CW ! Limited Scan Surface 2 Beam Direction 2 CCW i E inches from Reference Point to inches From Reference Point. inches from Weld Centerline. For Angles: 08 45 60a Other I Due to: Examiner l 10. #: l Level: l Date l No 1 1 CW Surface Beam Direction Limited Scan Surface 2 Beam Direction 2 CCW I. Degrees, Inches from Weld Centerline. For Angles: 0o 45* 60' Other Due to: Examiner: I D. s: Level: Date: i a

'                              No                            1                                 1                    CW Surface                     Beam Direction                            -

Limited Scan Surface. 2 Beam Direction 2 CCW Degrees. Inches from Weld Centerline. For Angles: Oa 45' 60' Other i Due to: Examiner- I 10 r ! Level. l Date-1 Reviewed by-l Level- l Date' l Page _ of _ l e-s t A0000930

I I I . I - I I SUPPLEMENTAL EXAMINATIONS I : g . , I l i l I I i I ' I l

I l B

l I i I ,

g g g g g 3 m m m m m M M M M M b F UlNuclear NDE Visual / Surface Data Sheet 000162 Site: Yg- / Inspection ID: //g Component: /#d/f8 ,f',fg[c . & g D:scription: &pg ed_ fg[g cuel arefoCr +

sl4/rT f / A ldzz/t I.D.:fyv p*- f.:r" Js/e hjg Procedure:Mg_ og 7 Material: g/g g J/f Thickness: , g.

Test Surf ace: d.3, , Test Method: A 7~~ No. Positions: / Distance: //M in. Drav<ing://m7//ogf Date: //hfA"d/ ////fZ. ' Extminer:gdqh A .--ri;g" gg 1.D.: //g3 Level: g Notes: Examiner: 6 1.D.: g/A Level: g/p

                                    ///J l                      Magnetic Particle (Ont )                                      Dye Penetrant IOnly)

Particle: Cleaner Batch # [/ O // Wet O Dry O to Penetrant Batch # 4 A dW Visible O Flu esc nt a h/ Developer Batch # p/g o f2 Instrument: ' Method: Method urr nt Visible EdhermometeI#/-8/ L Machine / [ ,A peres Fluorescent O Temp /d/* Distance From

Ind. Size (Inches) $

No. Status (Inches) B Remarks CW CCW 1 2

             $                                                                            fod $g/es/As/f /A/Ws 64 fNA E d A) ,J>t e / c f Al e tt.fc       /som Sc A/e A

No Reportable Indications Reportable indications Non Relevant Indications [ 3eviewed by: g LeveJ//p//f/'Date:_'T[/[f2 - Page lof f NDE Request No. /A /jg

 . \tethod lnd No.        al0199      P.T32OO 399    M.T. 400 599 Other/600-799                                                                       A-   '1925
        .           t.                                                                       ~ . ,

M M M M M M M M M M M M M M M M M h FDlNuclear 000164 NDE Visual / Surface Data Sheet \ Site: fpp2~-/ Inspection ID: stllA Component: fff t).pdf6] ,EM ed Dzscription: 34fg est d , Js4/' c e g / w e / WJ of WA//< stL Af W W D s ld 2 *n;/ \C E 1.D.: ff/g) 3/ .' gg jp gpe g jg Procedure:g'g ,,,o 7 Material: g / {/- Thickness: , 7g , Test Surface: 4. 4 Test Method: [f No. Positions: / Distance: js/jdp in. Drawing:gs* p //od.r- Date: f#44d/ /g /ff 2 Ex miner: /[My__ g T,emg 1.D.: jrff'J Level: g Notes: Examiner: / gjf9 1.D.: g/g Level: j/jff Magnetic Particle (O y) Dye Penetrant (Only) Particle: Cleaner Batch # [/d // Wet O Dry Co r /1 Penetrant Batch # d 4 8 3 f" Visible O Fluor c nt O t / Developer Batch # P/o d C Instrument: Method: p Methc 1 C r t Visible iRThermometer /M -d/E l Machine / ,I/ erek Fluorescent O Temp /d I

Distance From o Ind. Size (Inches) $

No. Status (Inches) 3 Remarks CW CCW 1 2 No Reportable Indications [ Reportable Indications Non Relevant Indications Reviewed by: [g p levely,4y Date: ypf[ff> Page /of / NDE Request No. /

                                                                                                                                           /[/;l-
                                                                                                                                                  .      / N 0925
       *lethod ino No
        .                     eat 0199     P.T 200 399    M.T. 400 599 Other/600 799 w-

g g g g g g g m M M M M M M M W Nuclear NDE Visual / Surface Data Sheet 000185 Site: W/Z"- / Inspection ID: //A Component:.jpr4/-/ f/-g,iS p/c.es(

Description:

pf e - 2p)( JA/-e - Cyd it)t/dJ' -fu /Aff fd/ /dze/t l 1.D.:jsfy.y,gg,g gAfg/ Procedure:MJ- 447 Material: d/g / gg Thickness: . 7,y9 Test Surface: d, 4 l Test Method: jd 7-- No. Positions: Distance: Drawing://e/ge yff/

                                                      /                           j//A In.                          Date: # # d/ /2 /((2.

Enaminer: [ M [p,cser I.D.: / f'/J Level: T Notes: Enaminer: j/// l.D.: //// Level: gg Magneti Particlej(dnly) Dye Penetrant (Only) Particle: Cleaner Batch # //d I! Wet O Dr O C or Penetrant Batch # // d2 Visible O F or see O at / Developer Batch # #/d d instrument: Method: Method ur nt Visible hermometerW/- NE Machi[e , peres' Fluorescent O Temp /dS

Distance From o Ind. Size No. Status Iloches) $

linches) B Remarks CW CCW 1 2 i i No Reportable Indications [ Reportable Indications Non Relevant Indications Reviewed by: gjg Level;gjA- Date:f/h Page foi / NDE Request No. ///g W hodIna No. valOt99 P.T./2OO 399 M T.,400 599 Other/600- 799 #' % 925 _ J J

M M M M M M M M M M M M M M Nuclear NDE Visual / Surface Data Sheet 000181 Site: #p/5 / Inspection ID: MAf Component: /f/dN[0Af ,#. W e ed

Description:

Rf'c dwaf, J'A /'e dw / u>e//.t -/ 4 h/e/t p // Mo s s:,/t*_ l.D.: jj pg.g/.fg.g ggg. c.gg, Procedure:Mh g// Material: gg g p/j Thickness: ,pfe Test Surf ace: c), b, Test Method: //gsg/

                                                     /                                  No. Positions:                      /                                        Distance: //p.               In. Drawing: Aft'd //, ffte Date: /://#/C d4       // /((2_

Examiner:/[Mp M ---TEig~ ec,c 1.D.: / pgy Level: g Notes: Examiner: I g[// l.D.: js//A Level: /# Magnetic Pa le(On Dy'e Penetrant (Only Pcrticle: Cleaner Batch # Wet OD olor A Penetrant Batch # . [/ / Visible Cu r scent Bat / Developer Batch # / /A Instrument: Method: Method Curr t- Visible T r t Machin's ' [ A eres' Fluorescent O Te p Distance From e Ind. Size No. Status (Inches) (Inches) $ B Remarks CW CCW 1 2 Mea 7% 64 ed fx/% cv/ dzo- dood~-o Y

                                                                                                                                                                                             .</aa.u . a e .,r - so .2 k A M - 3 t'r 3 ptd-S fC-'9- Q                   d 73         d'A**

i ( No Reportable Indications Reportable Indications Non Relevant Indications O Reviewed by: Leve g ,. A Date: f/[/2, Page /of / NDE Request No. Method ind No. '6sual/O- 199 P /200 399 M.T./400 599 Otherl600- 799 W ooS25 v U )

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g m m m W M M M M E E E E l FIONuclear 000159 1 NDE Visual / Surface Data Sheet Site: fpt.T~~ / Inspection ID: //A Component:Sg/'e est f gvpf f.r

Description:

GArc.eyg, weff af ofe. ex ;e fafyg ,e' ggf, ep/ rs e /czQg

1. D.: jnv.p pf' Procedure:Ay//J-d//" Material: J/ ,/ h Thickness: ,7$o Test Surf ace: d. A Test Method: t//Sv4/ No. Positions: / Distance: g/g in. Drawing:4!0d//dy'75/ Date: ff/44c/ // /9ff_

E::aminer: gg,6 g -76g' p eg 1.D.: //gf Level: M Notes: Eneminer: I js//4 1.D.: .gM Level: ,// Magnetic Particle (Only) Dye Penetrant (O y) Particle: / Cleaner Batch # Wet O Dry olor Penetrant B # / / Visible O Flu a sce ch Developer at h# /A Instrument: Method: Method I ,u r nt Visi e T r eter Machine / I/ Amperes F orescen O emp-Distance From o Ind. Size No. (Inches) $ Status (Inches) B Remarks CW CCW 1 2 Medfitaind on 4fg edd 42o- ecod*-fe 4(a 222- e s ,t' ~ /* - V l ! 19'f3 Af?t A-/t t x

                                                                                         ~2"W&if h ro.a         sp/0V ff Q           f./2- 73      fse Alo2t/'t Id.
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                                                  ,                                     2 14 /7z V'd                                             _

No Reportable Indications d Reportable Indications Non Relevant Indications M

    .'leviewed by:     g jj                                Levej/[///[ Date: f[/[/h Page / of /                       NDE Request No. jt/[A
 'tethod ind No
  .                      sal 0199    P T./200 399   M.T.!400 599 Other/600 799                                                                       A m 0925

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M M M M M M M M M M M M Nu21 ear 000154 NDE Visual / Surface Data Sheet Site: T%T-l Inspection ID: [O(( Component: ffft/g/'-JP[ f Sff[c w ( ) Description;,ffe cg/ nst// hinh to go st/,. _ f,4ft M 4 s h e casd >#e /A//< l.D.: p w p ( p y e g, g , e g Procedure: M .go7 Y Material: gp g Thickness: //4 Test Surf ace: 4d Test Method:])yg M j .g No. Positions: / Distance: jcfg in. Drawing://o.f ff Date: F[gy["fz Examiner: [Mh u M --y#p,em l.D.: /[/8 Level: /// ~ Notes: 1 Examiner: ///h)[hgj [ IMg 1.D.: Log Level: [ h b(_A ch 6to* M t-

                     ~ Magnetic' 9 d  icle (Only)~         ~~ M                         Dye Penetrant (Only)                  l yd Q & ,j pM Particle:                                                                  Cleaner Batch #        NldII Wet        d;D y           '[A O Color                                Penetrant Batch #         A Molf Visible /C FI ore cert,f) Batch                                       Developer Batch s        T I MT Z.

Instrument- fI Method: Method C arrent Visible kThermometer d Machine Amperes Fluorescent O Temp 7Z# I l Distance From

Ind. Size (Inches) $

No. Status (Inches) B Remarks CW CC,W 1 2 l I Re e.* d 02p" 2.88' W?nd 2- faink an nah enA near noed- _ Z 8eus4 _o'2ff 2.1W 2Zef 2 R Ssa ad .orn' 2.92' .22K 2 .

                                                                                              $ / s d A lo".r
                                                                                                                 / z is Ast'e Nfeeexd4Ae.

A'ee..eded (Y . ave s2/v. / l l l l J hk h/" 00 5 1 No Reportable Indications [ Reportable Indications Non Relevant Indications Reviewed by: Level: Date: Page of NDE Request No. A0000925 Method /Ir 1. Visual /O 199 P.T./200-399 M.T.1400-599 Other/600-799 k y l

M .M M M M M E E E Nuclear NDE VisuaUSurface Data Sheet 000155 Sits: 7#2~ / Inspection ID: //j9 Component:JAfc cad [Wd V-fMeh Drscription:Jppe ed fe forg/c (8M)ap4fg - Me ead AM / Aft ie JAfc CAld Nt// 1.D.:f;pg/_ pf ./ .r:#/e est Procedure: gj*r-o/[ Material: y g ,g /,5- Thickness: //,, Test Surface: d,.b, Test Method: y[ggj/. $f No. Positions: / Distance: //j in. Drawing:/dio y/J, Date: J/f/f z. Extrniner: [M c[_y% 8 Wp,c 1.D.: /fG Level: g[ ' Notes: Extminer: h/h/ ' Ihrg 1.D.: h Level: ,g Particle: Magnetic P/rti e'(O ly) / Dye Penetrant ( nly) [ Cleaner Bate t / Wet O Dry Colo Visible O F1 re ent Ba Penetrant B < h# / /A Developer at :h# /// Instrument: Method: Method ' Cur n Visible her o et r Machine / ,/ Agnper s Fluores nt U Temp Distance From o Ind. Size No. Status (Inches) (Inches) $ ti Remarks CW CCW 1 2 l l

    .                   No Reportable Indications 7                                      Reportable Indications C Non Relevant Indications O Reviewed by:                                                        Level:           Date:
      ,                                                                                                             Page      of     NDE Request No.
      ' *iethod ind No.
        .                              110 199        P. T./2OO- 3 99   M.T. 400 599 Other/600-799                                                                     AOonO925
                                  %s                                                                        -

I I i I I I I I ess, g 3B I I I I I I I I I I

I . TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 3B Inspected Item: Spray Line Nozzle Safe End Type of Inspection: U.T. Inspection and Test Plan: This area includes Inconel 600 weld buttering, B-166 safe end forging and A 376 TP 316 piping. Two circumferential welds are included in the inspection which will involve HAZ of the two different base metals. I Yes .No

1. Is the work scope in agreement with the B6W Engineering Inforination Record?

[

2. Was there an approved inspection / test procedure used for this examination?

[

3. Does the results of the examination agree with the acceptance criteria called out in the inspection / test procedure?

[

4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure? (Accessible quantity inspected / Minimum required / .)

NOTE: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any [

repairs made to the item (s) being inspected, or recommen-I dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not /

been (reported) processed for future resolution? NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. $l~ /023W~ $8

8. Task #7 Procedure No. J- d d [

Reviewer's Signature /Ah 8 I

I I Test Completion Review Sheet Comments, Task #7/ Test:3B, Spray Line Nozzle Safe I Item #1 The volume of the work scope required on B&W EIR tio. 51-1132391-00 was not capable of entirely being ultrasonically inspected. The I- inside radius between the safe end to elbow weld and first elbow to pipe weld after the safe end for a radial distance of 1 1/2" I was encapable of being U.T. examined, due to the curvature of the elbow. A limited scan report was issued. Item #4 The quantity of this Item was limited as reflected above. A best effort was attempted to achieve as much of the required coverage as possible. I / ,= Rodn I Turner NDE Specialist I - I I I

;I I

I I

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Description:

W4 y /drr/c fo JM CW , Cal. Block:$8[fj#ff I.D.:46 fAge/, _f. jgc.o,/ f,g.. cut Procedure:ffyfe de g l Material: [f -fd Thickness: .5/[ In. Test Surface: 0.d. l No. Positions: / Distance: Aj/j/f - In. Drawing:/2f2. /// 7 Cal. Sheet had//2 Cal. Sheet: O c o/f] Cal. Sheet: ddO/k ! Beam Direction " Long Y Shear Limited Exam [iPffo O Yes Angle: [ // Angte: Angle: ff Examiner:[hg g ID#: /7/7 Level:'.//Z. Time Start: ///d Hr. Time Start:/2/2f Hr. Time Start: /.Jlff Hr. ExaminehJh/hy'"f)Jp Lg ID#: A- 3 ')</ Level: 7'/~ Time Stop: /2lo o Hr. Time Stop: /2l3/Hr. Time Stop: /J/ 05 Hr. Notes: d .) Part Temp: f 7 O*F Part Temp: II O'F Part Temp: f7 O'F OAl W 000 Date; p>ygC(3)ff ffz. Date:g/W3fff/2. Date: pppefyjffz . A

O Information Only er

             ,5 w         / '/d E.                                                                                                                      Weld Height MJ4 Weld Width Id
             $+e/         WoY                                                                                                                                                            ^

Surface One to Surface Two BM Haz Q. Weld Haz BM

                                                                                                                                                     . 7z S      .726        . 72S         725         . 72 S LAM             LNGTH WIDTH                                        Through Wall Dimension g           Q                                                              Minimum                     Maximum
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5 0 O 1 .2 y O 1 2 CW CCW 1 2 CW CCW CW CCW Remarks i l

No Reportabfe Indications [ Reportable Inificgions Non Relevant Indications ,j l Reviev>H by: [g / Levg,,g[/ Dat%M Page of NDE Request No. Aj//jd. ) e ngte ind No. O Deg/O-19[45 Deg/200 399 60 Deg!400-599 Othert600-799 " " " "

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gW W W W m M M M W M M M M M M NDE Ultres:nic D:tn Sh ct 0000RR Site: [/1/.2'*-/ Inspection ID:

                                                                                                                                                                                                                                      /[                 Component:                  JgAy                           /fJ. t

Description:

$pf'c .gg .t g f C# fb al o g J 0f.e.s.geirft$ < K. U/Af /sNC                                                                                                                                                                                                            Cal. Block:pey t e/szzjs I.D.:yggy g.ew &/,. yg ,. gg,s Procedure: M.r- co / Y Material: gg- ' Thickness: ,f/[In.                                                                                                                                                                                              Test Surface: OJ.

No. Positions: / Distance: M[//In. Drawing: /2 92 ft E [ Cal. Sheet odo //2 Cal. Sheet: dod/(( Cal. Sheet:J f [ Beam Direction Long Z- Shear Limited Exam O No des Angle: $* Angle: go Angle: [ (( Examiner:[ Mm ID#:/f'/J Level g Time Start: /2lo o Hr. Time Start: /J;4f Hr. Time Sta[tf ((/7 Hr. Examindr'J/Q [j/-($@))/k Lpg ID *:A }'/ t/ Level: 2t - Time stop: /2/d 7 Hr. Time Stop: /J,*gfHr. Time Sybp/ //(( Hr.

Notes: [ Part Temp: f7 O *F Part Temp: 87 O *F Part[mk *F b4fc /h e fAW/0J AAfks' alCldNb.

Date:jt/gd{gfffff'E.- Date:thAle/8fff(( Dath; ff f
Inf rmation OnIy Weld Heig J Weld Width . O Surface One to Surface Two BM Haz Q W eld Haz BM B

                                                                                                                                                                                                                                                         . //S                . 5 50       ,f/o                    , fde     ,fD LAM       LNGTH WIOTH                           Through Walt Dimension g

o Minimum Maximum d

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ti y Position In. Position In. 4 S E z e M E 5 & 3 2 5 s f @ 5 o o a g 3 g e 1 2 g 1 2

                                              #                                                     *

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CW CCW 1 2 CW CCW CW CCW Remarks Roo 96 / 2 /A . f/6 33sc - -

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No Reportable Indications Reportable Indications Non Relevant Indications 7 , Reviewa<1 by: [g/y" Levpd %' Date: g/- Page / of j NDE Request No. //p/

                                                                                                                                                                                                                                                                                                                  /        ,

Angle ind rdo. O Deg/O-19[45 Deg/200-399 60 8 /400-599 9 Other/60N799 ~ A0000926

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Nuclear Limited scan aeport Data Sheet No.: dOO NDE Date:,nse'c(3/lrfft. Component: g4yAior m. md /e e/A,. n o I Surface Beam Direction

                                        ^                                                             '

Limited Scan V Surface 2 Beam Direction 2 V CCW O Inches from Reference Point to /, inches . O /*8 ddd. From Reference Point. inches from Weld Centerline. For Angles: , O' 45* d' 60* Other Due to: #A E d 2 N Examiner: [ ,._ LD. m: j[g y Level ~/// Date g[ /[f z. 0 ' No 1 E Surface Beam Direction 1 CW Limited Scan Surface 2 Beam Direction 2 CCW I inches from Reference Point to From Reference Point. inches _ inches from Weld Centerline. For Angles: Oa 45* 60* Other Due to: Examiner: LD.2: Level: lDate. No 1 Surface 1 CW Beam Direction Limited Scan Surface 2 Beam Direction 2

CCW

Degrees, Inches from Weld Centerline.

For Angles: O' 45' 60* Other t W I Due to: 1 Examiner: LD.#: Level: Date: No 1 CW lE S"" 8'"* "" 1 E Limited Scan Surface 2 Beam Direction 2 CCW Degrees, Inches from Weld Centerline. l For Angles: 0* 45* 60* Other i Due to: Examiner: l 10 m: l Level: l Date-Reviewed by: l Level: l Date: l Pagedof $ s-on AOOOO930

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NDE Ultr:s:nic D:ta Shict 000069 Site: # f/24. / Inspection lD: g[g Component: g/h/ 7 /f),r g

Description:

C/zfoqj Vd #% [d 8//oM Cal. Block:pegea(o2M I.D.: /#ajejf/ 8 W f d - e# d' Procedure:g,,,oof Y Material: M Thickness: g/[ In. Test Surface: d, b, No. Positions: -/ Distance: / /g in. Drawing: js[/Ar- Cal. Sheet g /g2 Cal. Sheet: goo /// Cal. Sheet: / Beam Direction Long & Shear Limited Exam O No Nes Angle: h Mpft '

                                                                                                                          //f*          Angle:         [d                  Angle:              [

Examiner:[ ID#: ///J Levelg g , Time Start: /2lo7 Hr. Time Start: /3,*3SHr. Time Sta,rt:[ [' Hr. Examinei%dk * ~~))fgp he ID#: /37Q Level: '71 ~ Time Stop: /yf3 Hr. Time Stop: /3,*/lHr. Time Sfp/ / ,// Hr. Notes; d ) Part Temp: 87 O *F Part Temp: f7 O*F Part T/n;d:MO *F Date:/qiseC3$3]jfft Date:f)gq1/c[f[jfft., Datf 0* Information 'Only ll l Weld HeightIvfI Weld Width ,

Surface One to Surface Two BM Haz Q W eld Haz BM

                                                                                                                                       , 62 S        . YFo               , 330     . do      ,99b LAM           LNGTH WIOTH                                          Through Walt Dimension g         Q                                                                 Minimum              Maximum g
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9 g .;;; y Position Position e i:i E I S E In. In. z e M 4 e & a e e e , s ? 3 l U E O "- U 5 1 2 y U 1 2-CW l CCW 1 2 CW CCW CW CCW Remarks ho 2 / 2 /fo .sbo 4 . t'w ,pbrfest 3/s

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l No Reportable Indications Reportable Indication,s . Non Relevant Indications [ Reviewad by: [g,// Le g J ff Date: //7/V Page / of S NDE Request No. g[A c Angie ind ivo. O Deg/0199 # 45 Deg/200-399 60 [eg'400-599 Other[600-799 AOnno m

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I Nuclear Limited Scan Report 1 Data Sheet No.: doddI NDE Date:mmel 24 ffrt Component: sg,y,, ,, e/gf. cpg.k No Surface 1 / 1 V CW l 7 Beam Direction r -- Limited Scan Surface 2 / Beam Direction 2 CCW d /. 4 dd O Inches from Reference Point to A .r dd *4nches From Reference Point. inches from Weld Centerkne. For Angles: O' 45' v ' 60* Other Due to: / dd N # Examnnerf fp ID a: / ('j] Level: /// Date JhlfL U No 1 1 CW Surface Beam Direction Limited Scan Surface 2 Beam Direction 2 CCW inches from Reference Point to inches From Referen 9 Point. inches from Weld Centerline. For Angles: 0o 45a 60a Other

Due to

Examiner: l 10 *- l Level- l Date-No 1 1 CW Surface Beam Direction i limited Scan Surface 2 Beam Direction 2 CCW Degrees, Inches from Weld Centerline. For Angles: Oo 45' 60' Other 4 , Due to: Examiner: I D. =: Level: Date. No 1 1 CW Surface Beam Direction Limited Scan Surface 2 Beam Direction 2 CCW I Degrees. Inches from Weld Centerline. 1 i For Angles: 0a 45* 60o Other Due to: Examiner- l10=- l Level l Date-i Reviewed by. l Level l Oate l Page E._ of 2 asi A0000930

TEST COMPLETION REVIEW SHEET II Task 17 Inspection / Test: 3B Inspected Item: Spray Line Nozzle Safe End Type of Inspection: R.T. Inspection and Test Plan: This area includes Inconel 600 weld buttering, B-166 safe end forging and A 376 TP 316 piping. Two circumferential welds are included in the inspection which will involve HAZ of the two different base I metals. I Yes No

1. Is the work scope in agreement with the B&W Engineering Information Record?

2. Was there an cpproved inspection / test procedure used for /

this examination?

3. Does the results of the examination agree with the acceptance /

criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum /

requirements called out in the procedure? (Accessible quantity inspected Minimum required .) NOTE: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upoa the results of this examination, were there any repairs made to the item (s) being inspected, or recommen-I dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not /

been (reported) processed for future resolution? NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No, t 13 M91 - oo I 8. Task #7 Procedure No. NESr /%R-I- NP Reviewer's Signature

                                                                                    /lMW ' kb g                                                                                     /

I

l5 g 2 4 f*2 Inter-Office M3morandum g Date May 18, 1982 c-Nondestructive Examination of > -A S ubject the Pressurizer: 4" Nezzle I To (Spray) and 10" Nozzle (Surge) Lines. - 6111-82-2078 Page 1 of 2. Locatioh TMINS Trailers #256/258 ! N.'C. Kazanas Director-Ouality Assurance I. General: This report covers radiographic examination of the 4" Spray Nozzle. The 10" Surge Nozzle was not shot for the following I reasons: 1) Configuration / excessive wall thickness, 2) No tack welds to use as reference and 3) original radiographs did not show the thermal sleeve. No reference available for comparison. - II. Scope: (4" Sprcy Nozzle) Radiographic exarsination to determine:

a. Location of thermal sleeve as compaired wich original.

film taken during construction. l _

b. Presence of four ~(4) tack weld beads.

   .               c. Location and condition of the tacks.

d. Evidence of possiblh clearance between 0.D. of thermal sleeve and I.D. of 9afe end.

I III. Reference Data: B & W Drawing (129286 Rev. 5. l i ANSI B31.7 l RT Procedure XR-1-NP , , PIR #WE/43128/82

NES Radiographic Report, dated 3/31/82, Vald'Nur.ber l (I.D.) RC-54 5

1 !I g _ ... I . .

I I 6111-82-2078 (continued) Page 2 of 2. Nondestructive Examination of the Pressurizer: 4" Nozzle (Spray) and 10" Nozzle (Surge) Lines. IV. Evaluation: II-a . A comparison was made between the original film and the film taken on 3/31/82. There appears to be no I change of position and/or physical condition of the thermal sleeve. ' l I II-b- c . The four (4) tack welds were apparent and there does not appear to be evidence of wear and/or change of position between the weld (s) and thermal sleeve end. II- d . Evaluation of the radiographs did not reveal any gaps / clearance between the O.D. of the thermal sleeve and I.D. of the safe end. l Radiographic examination has not provided any evidence of move- ! ment of the thermal sleeve and shows no wearing away of the ! welds or sleeve. Evaluation of all five (5) radiographs was completed with acceptable results. I JET /ejg / J / E. Tietfen attachments (2) QC Mod /Corhtruction Inspection lI PIR fWE/43128/82 Supervisor l Radiographic Report, dated 3/31/82 for item #RC-54 cc: B. E. Ballard, Sr. w/o attach. I C. D. Cowfer w/o attach. J. J. Colitz w/o attach. R. F. Fenti w/o attach. F. Faust (B&W) w/o attach. I QC file w/ attachment l CARIRS w/ attachment 'I I I

    . .       ..        .. - . . ..        . u .... _ .... _    ,

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    /                                              11ELag;.                                                         s_

NUCLEAR ENERG'I SERVICES [ M MS' %37 P2 I . SMLTt*R ROCK ROAD DANBUFlY. CONNECTICUT C6610 RADIOGRAPHY REPORT p gggp,4 1 R. e. w pSEQl AL NO,

30

                                           ^          '

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          -                  S O -/                                                        Customer
                                    /*                                                     Address
                                    ,2 - 7   /

I SY Y* d. l Job Locatson Customer's P.O. No. item Description

                                                                                                                           '# N Job No, 100% Insp.                                         Spotinsp.

[W Welder Stamo MM 3 WORK

SUMMARY

 !                                                                                         Amount                                item Descriptioft A.M. O               A.M.@ _,,,_

W Teral Hours I j N P.M. T P.M. 9 _,,,,,. Trawl Hours Lunch Standby.,_ Ft. Plate Weld in. th k. 9_ l f Ea. Pipe 'ep in. dia. 9__ d, Films, k' A x /d Ty @_

                                                 >                                                          Filens.             x           Type                       9._,

J iras < dedio m oLt i,u n 5 E , ,o,u,,, ,_ Ce,hs ps) d 51, 72' rx - /.-ia~,,/ ,_ 1 R /51 % de'7~o rinihr '~"n j 'fr-.k itWS S W. i 87- % t Pf, p ym3 /_ . ff,, m, , M ,' ~f/ TECHNIQUE DATA Y NS L abd Ps. wi Ade W, ;- -t, . ,n,,ee,.on Spee,,ica,,on . AYO h.0r.? A i- en"7"* cfod9We Y- Accootance Sgandeed $bl UN= 7 _5 bM MCY4)n 'a E! Y C Y '"7No e n, ./ <*/g .o ud RT Procedure No. 5Y~# 'V' ?" 5 NE tt/o Te d l} r

Ocr .s , r ** e J e- - Shoot,nq Sketen (RS$$1

                                                     !                                      Physical S               a Size */      '/       Effective Focal Spot      '

W SF D 37 to Obiect ,,

   '                                                                                        Materia 6 Thickness                                , g Material i                                                                                            Geometric Unsk.woness (Ug) -                                       g                &

No. of Film per Casset Penetrameter Shy - i Viewmg: Singis Superimp.p.sid , g, g

Pb Screens Front Center Back f.; Wsking or Blocking gdy Exposare Time j7 Dev. Time 7j 2 Tvoe Source Curies '

DEFE CT CODE j .5 P - Porosity $1 - Slag inclusions T1 - Tungsten incia C - Crack 87 - Burn Through CV Root Concavit IF - Incomo;ete Fusion DT - Orop Through CX Root Convema-SL - Slag Lines UC - Undercut Ox - Oxidation

                                                                                                   % =/c/ Jechc~< _                                                             a.

TECHNICIAN

2. ^ O LEVEL Y e s.e n

3. 7 LEVEL TECHNICI ANilN TE RPRETER

Pega',1,cf _"5 QUALITY ASSURANCE MODIFICATIONS /0PERATIONS

QUALITY CONTROL FURT INSPECTION REPORT Unit No. I Inspector Dere.a /c! [DChCo%# PIR No/M VJ/M[PJ l Inspection Descr.ip, tion $2borr*20fv d /2.d. SufiQ m 4/ # $ f. Or of b n.S fresta rt vo- * ' / ' '

l

I Visual: # Direct Measurement: -

                                                                        " Document Review:                  Other:             A IM3thod:        '

R.T R3ferences: Title Rev. Date Verffied I X A /- N/ '

                                                                                     /       g.3a ?s       Q%L I     Vandor/ Item                 Item / Characteristic /.       Accept /          Inspection           e m H ,ne, l         Identification              Activity To Be                  Reject            Results/         Sat     Unsat          Not l

(cs appropriate) Inspected Criteria Readings Applic. veil fle r</ a a? /,t 1.4M Ago dro nee Os# l su t:- - a s 21, wn s u 6 ~ ~ ~ rs , I ll l l .c g I I . I . i l1 1I -

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MO-lo8-1 (Rev. O) TMI 201 6 80 M ' 6 - --

Paga ,2,, of 1 g5ALITY CONTROL PLANT INS 7ECTION REPORT PIR Na # G '/?' Y / - Vendor /Ite:n Ites/ Characteristic / Accept / Inspection Identification Activity To Be Reject Results/ Sat Unsat Not B (as acerocriate) Insoected Readings Criteria l Acolic. I

                                                                       \
                                                                                                                         \

M essuring and Test Eculocent Used I Identification of Equipment Serial Calibration No. Date Due A l 11 l

                                     /V//                                                                           l l                                                                                                                l l

MNCR Isabed: Yes l No Xl QDR Issued: Yes l l No # l MNCR QDR No. Date Reason for Issue Hold /Condit. Release Tag Nos. i Issued I , I i f A/ # t l l I l 1 l l l 1 Co=nents/Other Infor:ation: RsNe penols esm on e ret is77, c er eNp/ idr oorw}r

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A/o wsoner v7"* de facts ha en al, coer A em o orr we s. nl a e meve m wY ed %rn e / r/e e ve 2 r o/dTeem sw/ l lI j Inspected By:

02of - n - nate: < . 2/- e;- Reviewed'and Approved By: ,, /J W m m Dai:e: N/[ 72 \ . -

                                                                           /              l                             .

l Distribution ( X') Manager Admin and Services UnitN (Orig.) ( ) QA Mod / Ops Manager

'(

I Others: ( Y)

( Jr ) QC Manager File M.//,s'#/# ( ) ( ) MO-108-2 (Rev. 0) ( ) ,

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I TEST 4 i I 3C l I 1 I I l I I !.I 1 l,I 1I . l 4 l t . J i i I i il . _ _ . . - , _ _ _ _ - _ _ _ _ _ . _ _ _ - _ _ - _ _ _

I TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 3C Inspected Item: Pressurizer Surge Line Nozzle Safe End Type of Inspection: R.T. Inspection and Test Plan: This inspection includes the safe end made of AS 336 CL F8M material and the connecting welds to the SA 182 TP 316 surge pipe and Inconel 600 buttering. , C. /y)Q W , ,

     @             (CfA<A.55                     -

N U" n t & b a- J/e ' Yes 3o

1. Is the work scope in agreement with the B&W Engineering I Information Record?

2. Was there an approved inspection / test procedure used for this examination?

3. Does the results of the examination agree with the acceptance criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure? (Accessible quantity inspected Minimum required .)

NOTE: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any repairs made to the item (s) being inspected, or recommen-I dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not been (reported) processe' for future resolution?

NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. //3 2 3 h2 - b

8. Task #7 Procedure No.

Reviewer's Signature

                                                           !           M ~~

, / I

I TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 3C Inspected Item: Pressurizer Surge Line Nozzle Safe End Type of Inspection: U.T. E Inspection and Test Plan: This inspection includes the safe end made of AS 336 CL F8M material and the connecting welds to the SA 182 TP 316 surge pipe and Inconel 600 buttering. I I I Yes M

1. Is the work scope in agreement with the B&W Engineering [

Information Record? .

2. Was there an approved inspection / test procedure used for this examination?

[

3. Does the results of the examination agree with the acceptance [

criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum [

requirements called out in the procedure? (Accessible I quantity inspected / Minimum required / .) NOTE: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any [

repairs made to the item (s) being inspected, or recommen-dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not been (reported) processed for future resolution?

[ NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. 8/-/O2872"' dd

8. Task #7 Procedure No. ///dS - d O [

Reviewer's Signature N V I I

I I Test Completion Review Sheet Comments, Task #7, Test: 3C Surge Line Nozzle Safe End. Item #1. B&W's required work scope (area of examination) as stated on B&W EIR 51-1132392-00 was not capable of completely being examined. The area limited to examination was the C/S portion I of the nozzle. This area for 360 was inaccessible because a main restraint was attached directly in this area, and removal would have caused numerous hardships. A limited scan report was issued. Itep #2. The quantity of this item was reduced due to the attached I restraint as mentioned above. All other areas were examined. A best effort scan was performed on the nozzle's C/S portion. Refer to Attachment #1. I f-Rodney urner l NDE S cialist I I I

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NDE Ultrcs nic Dita Sh:It 000065 Site: [ //ZZ'. / Inspection ID: [g Component: Joggd //p C

Description:

fp;ppgo, CW ~/~O C/b e.<) J-c/[ Cal. Block:,qqe{. mast I.D.gg g,g ,3-A.ej((If grocedure:fjyfu.aot Y Material: [g Thickness: //dein. Test Surface: dJ, No. Positions: / Distance: //h/ In. Drawing: /2 92 ffs T Cal. Sheet d O O/[0 Cal. Sheet: g} co/// Cal. Sheet: (( Beam Direction Long 7- Shear Limited Exam B'60 0 Yes Angle: go Angte: fgf'O Angle: (( Examiner:[dM,. Mg ID#://t,3 LevelFj//7 Time Start: /[2 2- Hr. Time Start:g//l$ ExaminerF))!da/kg,b 77Jp 3;cf ID#: g3 jy Time St/rt[ / / fir. d Level: [ Time Stop: //.*,J Z. Hr. Time Stop: //.*eSHr. Time [o/:/ / / Hr. Notes: ) Part Temp: N O 'F Part Temp: f 7 O 'F

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No Reportable Indications O Reportable Indications Non Relevant Indications [ ,, Reviewed by: g ,,-;[ ,. Leyejd/p/7/'Date: ((43, Page/ of 2 NDE Request No. //[j(l

 - Angtei . .' No. O Deg/O-199       5 Deg/200 399                                             '

60 Deh400-599 Other/6CU-799 AOOOO926

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Description:

Joeec ,l/c z't-/t fa &fe [4 a)e/GC Cal. Blockg.gg2d 1.D.:8 0 & M ar.c/r w ,e/d o g g A M Procedure: M }def$# Material: %g g_ Thickness: //do in. Test Surface: d.3. l Distance: g[g in. Drawing: /2 fE' /// Cal. Sheet doo/f0 No. Positions: / Beam Direction Long 2. Shear Limited Exam 0 No des Cal. Sheet: 000/f/ Cal. Sheet: , /[ Angle: 8* Angle: 4',f

Angle: [ ((j Examiner:[M_,_. _ My ID#: /[/J Time Start: / M Hr. Time Start: / ggtHr. Time Sta/t: [

ExaminsfF/f2dkf 7,L_y/'d{ 2,;rc ID#: /)3') / Level: C Leveti ///. Time Stop: AV'2e Hr. Time Stop: / g*/f Hr. Time pop [/[Hr.

                                                                                                                                                                                         / //[ Hr.

Notes: d ./ Part Temp: P7 O 'F Part Temp: O 'F Part[emp: O 'F 09Ce ll6 t k b a' CA W k sd *l l b $ ~ W A Date:))AWdd 3d /ff2. Date:pW$d,/ffL Date: /l i l3 -de au c/c( 47fk/t 2C 1lt* .5 Aft - C'Ad & Cll04

0* nformation Oniy or g pg Weld Height 'UI Weld Width Od Surface One to Surface Two BM ljaz (Weld Haz BM

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No Reportable indicatio,ns @ Reportable Indication 3 Non Relevant Indications Reviewed by: [gyg Lef f i### Date: J/C/[f*

                                                                                                              /                  Page /of        /       NDE Request No.      //[g Anglek. No. O Deg/O-199        Deg '200-399     60 Deg/400-599      Other/kiUof799                                                                  A0000926

l 2 Nuclear Limited scan neport Data Sheet No.: 400d/( NDE Date:imedge pyyz Component: g ugge y,4_g 34_,4 Surface Beam Direction Limited Scan Surface 2 Beam Direction 2 V CCW d Inches from Reference Point to - 6 From Reference Point. inches from Weld Centerline. For Angles: ' O' 45' v 60* Other Due to: $h dN W-<W NC of XWt* Examiner (( 1.D.*: / f / f Level.' g g DateJ[ #[f2. I g No Surface 1 Beam Direction 1

CW Limited Scan Surface 2 Beam Direction 2 CCW Inches from Reference Point to inches From Reference Point. I For Angles: O* inches from Weld Centerline. 45* 60* Other Due to: Examiner-l 1.D. *: l Level: l Date-No 1 1 CW Surface Beam Direction Limited Scan Surface 2 Beam Direction 2 CCW Degrees, Ir.ches from Weld Centerline. For Angles: 0* 45* 60* Other I Due to: Examiner: 1.D. v: Level: Date: I No 1 1 CW Surface - Beam Direction - Limited Scan Surface 2 Beam Direction 2 CCW Degrees. Inches from Weld Centerline. I '-^"" Due to: Ex aminer- lIDa: l Level lDate. ee... . _ i Leve, ie.... i .. ,. _ , _ g . cooono

                                                    . - = _ . .      -. _.  . _ _ -

l lI i i 4 t i 1 1 i i l i i l .i TEST i 4 4 l l l RESULTS REPORTED BY FAILURE ANALYSIS GROUP TASK 1 i I 1 i iI !i l. 4 1 I 1 i 4 1

_m - - -" - d " -" I I I :

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I g I ess, s , 2, eu g g ossesoc,Ivs exAmIuA,Ioss WIPE SAMPLs ANALYSIS I I 1 I I I I I

TEST COMPLETION REVIEW SHEET & TI Q - U .- Task #7 Inspection / Test: 5 IS 21$32 Inspected Item: Reactor Vessel Inner 0-Ring - J, h Type of Inspection: Destructive Examination Inspection and Test Plan: The RV 0-Ring is made of Inconel 718. It has i been highly stressed due to the pre-load induced 1y the closure head. This examination of fers a confirmatory check on the crachine or 1.ac' c" cracking in a highly stressed area plus a check for contaninant concen-tration. YES NO I 1. Is the work scope in agreement with the B&W Engineering Information Record? X

2. Was there an approved inspection / test procedure use AN,d x

              / for this examination?

AiBEG+rw~' JV/ N W ~/077 s5bw/ &# M

3. Does the results of the examination agree with the acceptance criteria called out in the inspection /

test procedure? )(

4. Doem the quantity of items inspected agree with the minimum requirements called out in the procedure?

(Accessible quantity inspected Minimum re-quired .) )( Note: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any repairs made to the item (s) being in-I spected, or recommendations for repairs or re-placements? C I 6. Does there exist any unresolved discrepancies that have not been (reported) processed for future resolution? Y Note: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. #/ -//JJ.$~e'f/- S/

8. Task #7 Procedure No. M7~J~ /# 7 7. //

A'$.,onde.s-<.<-' z W s y 7s*).Z W ff YW d e s Signature -

I TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 7 Inspected Item: CRDM Closure Insert Type of Inspection: Destr'ictive Examination Inspection and Test Plan: This insert is made of SA 182 GR F 304. It is in the "as-ordered" condition. The purpose of this examination was to obtain a data I point for general attack to annealed F 304. I YES NO

1. Is the work scope in agreement with the B&W B Engineering Information Record? X 2.

I Was there an approved inspection / test proce ure us=d for this examination? 89 / M 6' .

')[

3. Does the results of the examination agree with the I acceptance criteria called out in the inspection /

test procedure? Y 4. I Does the quantity of items inspected agree with the minimum requirements called out in the procedure? (Accessible quantity inspected Minimum re-quired .) X Note: If any of the answers to (1), (2), (3), or (4) are no,,a written explanation must be attached.

5. Based upon the results of this ev==ination, were there any repairs made to the item (s) being in-spected, or recommendations for repairs or re-placements? ,,

X_

6. Does there exist any unresolved discrepancies that I have not been (reported) processed .for future resolution? -

E Note: If any of the answers to (5) and (6) are yes, I a written description must be attached.

7. B&W EIR No. [/-/M.2 ed77-d/

3. Task #7 Procedure No.

I ie.er.s Siena re p a d A > I .

TEST COMPLETION REVIEW SHEET Task #7 Inspection / Test: 11 ( Inspected Item: RNS Retainer l l l Type of Inspection: Destructive Examination Inspection and Test Plan: Was examined in detail for evidence of sulfur assisted I intergranular corrosion cracking. The retainer assembly includes a spring made of Inconel X-750 and high stress areas of SS-304 load arm. YES NO

1. Is the work scope in agreement with the B&W Engineering Information Record? Y I 2. Was there an approved inspection / test procedure used for this examination? M/4/ effjf5' N

3. Does the results of the examination agree with the I acceptance criteria called out in the inspection /

test procedure? _

                                                                                ,Y I       4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure?

(Accessible quantity inspected Minimum re-quired .)

N Note: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached. I 5. Based upon the results of this examination, were there any repairs made to the item (s) being in-I spected, or recommendations for repairs or re-placements? (

6. Does there exist any unresolved discrepancies that I have. not been (reported) processed for future resolution? ; -

I Note: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. [ h // M [ #8 ~ 8 8 __

8. Task #7 Procedure No.

Reviewer's Signature E

I E a_ g< Inter Office Memorandum 8 April 13, 1982 ISI/NDE M82017 ect Removal, Ultrasonically Locating Weld and Sectioning of Inner 0-Ring (Task #7 Test 5) N. C. Kazanas Location Parsippany I A maintenance crew of four (4) men entered the head stand on I April 13, 1982 and before cutting was started each sector was marked to its proper coordinates. The inner 0-Ring was cut at clips 1, 4, 7, and 10. At this time water from the inside of the Ring was attempted g to be collected. The 0-Ring contained no water therefore, this was 5 unable to be performed. The four (4) Sections were laid out and prepped for UT inspection. UT inspection was performed and revealed two welds. These welds were cut at a distance of 6" on both sides of the weld and I labled #1 and #2. They were bagged in a lay flat, tagged for B & W L.R.C., and placed in the B & W shipping box. Sample #1 came from Quad 'X' 'Y' axis, sample #2 came from 'Y' I 'Z' to axis. Both samples were visually examined on the I.D. to verify the _ _ samples contained a weld. Two..(2)_other 12" samples were labled #3 and to

            #4, bagged for B & W, and placed in their shipping box. Sample #3 was taken from Quad   'Z' to 'W' axis and sample #4 was taken from Quad 'W'

I to 'X' axis. Two additional samples were cut, these were for GPUN's use and were bagged in a lay flat.

i GPUN samples were removed in accordance with procedure 1504-9 and were , delivered to the Decon Room (R. Campbell). One (1) sample was from "W' ! to 'Y' axis and the other from 'Y' to 'Z' axis (as depicted in procedure). l The only exception to the procedure is two weld samples (#1 and #2) which were included instead of only one weld sample. This completes the in-

volvement required on my part.

l ' 'g dw-Rodney Turryg l NDE SpeciaYist l Materials Technology l RT:ef lh l5 cc: C. Cowfer J. Potter l C. Rhedrick lg ~ R. Toole i5 M zei=e acocosas lE

I cr eel g_. -

    ~
       ~ ~

l Inter-Oiffice Memorandum a ttAY e '^M" " April 30, 1982 y pts (MTI.1086) . f [ hubject Bend Testing Strips from TMI-l R.V. m Head 0-ring o J. J. POTTER Location Reading Introduction On April 23, 1982, the writer visited TMI-l Nuclear Station for the following purposes: (1) Oversee the sectioning of two reactor vessel head 0-ring pieces into longitudinal strips and the bend testing of these strips in accordance with the attached memo (MTI.1077). (2) Examine the tensioned surface of the bend specimens for trans-verse cracks. Testing i Two 0-ring pieces, marked W-X axis and Y-Z axis, were each split longi-tudinally into four sections. Subsequently, bend testing was performed on these strips. Specifically, three of the four strips from each 0-ring piece, numbered 1, 2 and 3, were bent around a 1" diameter rod so as to place the I.D.

surface in tension. The remaining strip from each 0-ring piece, numbered 4, .I was bent putting the 0.D. surface in tension. I Post test examination consisted of inspecting the entire tensioned surface of each strip under the stereo microscope at magnifications up to 70X.

        ' Observations

1. The O.D. surface of each 0-ring strip was shiny while the I.D.

surface was discolored and had a black appearance.

2. No cracking was observed on the tensioned surface of any strip.

I wwnR. L. MILLER RLM;brk cc: C. D. Cowfer i F. S. Giacobbe R. R. Harper N. C. Kazanas H. L. Wilson I AOOOO648

I I Inter-Office Memorandum E Date March 29, 1982 y (MTI.1077) T Qj g(h hh[ Subject Examination of TMI #1 R.V. Head 0-Ring I To J. POTTER Location Reading The examination of the Inconel 718 0-ring from the reactor vessel head to shell flange shall be conducted in the following manner.

1. If fluid is contained within the central annulus of the 0-ring plans need to be formulated to collect this fluid for future analysis.

Mr. Jim Tangen should be contacted regarding sample containers, sample size and analytical laboratory.

2. The analysis of the fluid should include the following:

PH B Conductivity Na S Li i C1

3. Once the water sample is collected, a- three (3) inch section of I O-ring shall be removed from two (2) locations 180 degrees from each other.

Note: Record the locations from which the samples were removed with I reference to the R.V.

4. These two sections shall each be split into four (4) longitudinal strips as shown.

g

                                                                 ,QCut
                                                    \

I . <

                                                      \ 1y 4 / 2
                                                    /3\

R.V. flange face

                                                           \
                                           /                    Cut The quadrants shall be numbered 1 to 4 as shown.

5. All longitudinal strips except one (1) shall be completely bent around a 1.00" diameter rod putting the I.D. surface in tension. The remaining section shall be bent putting the 0.D. surface in tension (a number 2 or 4 section shall be used for this).

Note: When bending the sample, the longitudinal axis of the sample shall be transverse to the longitudinal axis of the rod. AOOOo648 I

3 , g J. POTTER March 29, 1982 Y I I 6. After the sections are bent, they shall be examined on-site using a stereo microscope. This examination to be performed by GPUN Materials Technology. A clean area shall be prepared in the hot machine shop I or hot instrument shop for this examination. A 2' X 3' area is sufficient.

7. A report shall be prepared describing the visual examination.

8. If defects are discovered which require further investigation, preparation shall be made to ship the samples to B&W Lynchburg Research Center.

Please give me a call if you have any questions. As we discussed, you are writing the site procedure to accomplish this work.

                                                               . cott Giacobbe ailure Analysis Task Force I     cc:  J. J. Colitz R. L. Long N. C. Kazanas I          D. G. Slear J. Tangen J. Sipp I

I I . I I I I

I~ , I .. .. . .... inter Office Memorandum g Nff 2419PF Date May 17, 1982 I k re uacDear Fy Subject Visit to B&W Lynchburg Research Center (LRC) on May 6,1982 (GP.0128) To Location Reading On the subject date, the writer visited B&W LRC and met with Messrs. Baker, I McInteer, Garner, Piascik, Behnke, Mathens, Baty and Clevenger. The purpose of this meeting was to review the status of each of the following metallurgical I examina tions : (1) Regenerative Neutron Source (RNS) Retainer I (2) CRDM Closure Insert (3) Reactor Vessel 0-ring (4) Waste Gas System Header Pipe These examinations, except for item #4, are being conducted in support of the TMI-1 Reactor Coolant System (RCS) Review Tests (Task 7) which were estab-lished to identify any corrosion dcmage to the RCS internals as a result of sulfur contamination of the reactor coolant. . Summary The on-going metallurgical analyses of selected DiI-l RCS parts have revealed no evidence of corrosion damage. These parts are representative of RCS materials of construction. During service they were highly stressed and were exposed to I one of the following environmental conditions: continuous immersion or liquid-vapor interface. I From the current metallurgical results, it can be deduced that the stress assisted intergranular corrosion mechanism which was responsible for the OTSG

             . tube. failures has not occurred elsewhere in the DiI-l RCS. Also, it is evident I            that theientire.RCS 1.s contaminated.with sulfur compounds.

Analysis of RNS Retainer This part is composed of two Type 304ss arms, a Type 304ss can with a Type

 ~I           308ss closure weld on each end and an Inconel X750 internal spring.

iI Findings of this metallurgical examination were: (1) Low magnification microscopy revealed several patches of yellow deposits on the arms. Also, both black and white crystalline deposits, normally ,i present on RCS parts, were observed on all surfaces of the retainer. Constituents of the yellow deposits were sulfur, silicon, chlorine, m yaesium and potassium. The black deposits were composed of iron, I chromium, nickel and silicon and the white deposits were identified as boron. I AOOOO646

N. C. KAZANAS May 17, 1982 I.

I (2) Both bend testing and metallography revealed no degradation of retainer material. (3) Chemical analysis of wipe samples measured the following chloride and sulfur levels: 8 ppm Cl- maximum and 33 ppm S maximum. (4) Load deflection tests on the Inconel X750 spring and subsequent comparison of this test data to design base data indicated no noticeable change in the spring constant. In summary, this metallurgical examination has shown that there was neither I apparent degradation of the mechanical properties of the spring nor corrosion damage to any retainer material. Also, it identified that sulfur compounds were present on the interior and exterior of this part although reduced sulfur species were confined to the exterior only. The last item that needs to be completed to finish this examination is chemical analysis of wipe samples which were taken from the retainer surfaces at Three Mile Island Station. Analysis of CRDM Insert T45 [ 7 A sketch of this Type 304ss part is shown in Figure 1. Findings of this metallurgical examination were: (1) Eddy current examination from the exterior of this part revealed no indications. --- - ~ ~ ~ (2) Low magnification light microscopy revealed possible intergranular corrosion on some inner surf aces of the CRDM insert as shown in Figure 1. ,l W (3) Metallographic examination of the suspect defect at the interior of the CRDM insert revealed no intergranular attack, suggesting I that the microscopic observation identified in item (2) was probably oxide cracking. In short, this metallurgical analysis has revealed no metal deterioration via intergranular corrosion. Items that need to be completed to finish this examination are: (1) metallog-I raphy to further substantiate that there was no corrosion damage to the CRDM insert material (2) Kevex energy dispersive X-ray analysis of deposition and ASTMA-262 Practice A for sensitization. RV 0-ring [/[ 3 [ f Four sections of the RV 0-ring were submitted for metallurgical analysis. l I A circumferential weld was present at the midpoint of two of the four sections. Ihe 0-ring was made of Inconel 718 and was coated on its exterior with ~2.5 mils of silver. 1E

.r

N. U. IM4ANA3 !

                                           .3 -                      tiny 1/, lyc4 I~

I Findings of this metallurgical analysis were: 8 (1) Radiography has revealed a few rounded indications in one sample. These indications were confined to one side of the closure weld but at some distance from the weld. On the same sample there appeared I to be a band of circumferential linear indications on the other side of the weld but once again at some distance from the weld. (2) Eddy current testing from the exterior of each sample revealed no indications. (3) Scanning Electron Microscopy identified the rounded indications as small cracks on the exterior of the ring. One of these cracks was I broken open and its fracture surface examined in the SEM. This SEM examination revealed a dimpled structure which is characteristic of I ductile rupture; however, it was unable to determine if the crack extended through the silver plating. This microscopic observation indicates that these cracks were not produced by the stress assisted intergranular corrosion mechanism which was responsible for the OTSG tube failure since it is recognized by intergranular fracture. To date this metallurgical examination has revealed no evidence of inter-3 granular corrosion or cracking. 5 Remaining metallurgical tests include: (1) bend tests and weld bend tests and (2) metallography and fractography (if necessary) of tested bend specimens. Analysis of WGS Cracked Pipe I This failed pipe was a four inch long, 2" sch 40 Type 304ss pipe with a socket weld on each end. one socket weld. It contained a thru wall circumferential crack adjacent to This metallurgical examination is in its preliminary stages with receipt inspection and radiography completed. Radiography has revealed that the thru wall crack was ~3/16" from the toe of the socket weld. Also, it revealed another I small branched circumferential indication about 1/4 inch from the toe of the other socket weld. - R. L. Miller RLM/ds cc: J. J. Colitz C. D. Cowfer I D. K. Croneberger F. S. Giacobbe H. D. Hukill R. L. Long I D. G. Slear I I r.

                       '                                                                                                                                '     I
                                               ..}__.___.______..__.
                                                                                                                                                                                             ._ _ l l                                                                                                                                l                                             !

t l Figure.l._ Sketch of_CRDM Insert. ' E,

                                                                                                                                                       '      I

[. l l } _a L i~ 3 1 i , E F f I

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                                                                                                \ ', .xm
                                                                                    \

l surfacepontaining, au pect defects "--k-

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W Fara LRC-139 Rasserc% and Osvcisemisst Divisise tVNCitBURG RESEARCH CENTER g Babcock &Wilcox tyNCatuno, vinomix i To R. S. PIASCIK. FUEL ENGINEERING, NPCD E-- y From D. L. BATY NUCLEAR HATERIALS T N 1 6 - * ~*"-- - Cust. CPU ^ File No. w Reh RDD:83:5490/5491:01 Ml* EXAMINATION OF THI-1 REACTOR VESSEL Date HAY 25, 1982-0-RING AND CRDM CLOSURE INSERT l Tun s es , se es.* e d i.bi 4 - - -- f

SUMMARY

I -* This report outlines the results of the metallurgical examinations performed on THI-1 reactor vessel 0-ring sections (silver placed alloys 718) and a CRDM closure insert (type 304 stainless steell. These.. sections were potentially -- l exposed to sulphur ontaminated primary coolant. This examination was to

determine whether any intergranular attack.had occurred.in these componente as a result of this potencial exposure.. - -

The examination of both components consisted of visual ar==in= tion. 'non-j [. destructive evaluation, surface examination by stereo light microscopy. - - - - - - - g -- scanning electron microscopy (SEM) Karex. energy.dispetalve.x-ray spectro- . - - scopy. metallography, and bend testing and examination with SEM. The results have shown that neither component suffered any intergranular i I* attack although the presence of sulphur was detected. The 0-ring contained some shallow cracks prior to becding and some sections fractured as a result l of bending. However, fracture surface avamin= tion revealed all cracking to be transgranular _ ductile .ruitpieZ.~Ihii CRDli.c,lasure . insert did noe contain . . . any cracka prior to or as a ress1r of bend testing. i

                                         . A subsequent report is in prophancion-which--will..eentaiar appropriate--Mguesav-
                                                                                                                                                . . = -

and tablas to doctment the micrcotructurek ex==f nation. . ' . . ~ ~ ' ~

                                                                                                                           -N   6 I

I I . I I I I

g 1 i !I

1 .lI t NOTE M W makes no warranty 'or representation,.- expressed or implied. o relative to the accuracy, completeness, or usefulness j of the information contained in this report; e or that the use of any informat. ion, apparatus, method. !W 4 or process disclosed in this n port may not infringe privately owned rights. I MW sesumes no liability relative to .the.use.cf. or for damages resulting from the use of e any information, apparatus, method or process disclosed in this report ' e or any experimental apparatus turnished with , . . - this report. E ee o

   .I I

I I I I

I BABCOCK & WII.COX RDD:83:5490/5491:01 PAGF. 1 I 1. INTRODJCTION This report contains a summary of the results obtained from the metallurgical examination of the Three Mile Island Unit-L (TMI-1) reactor vessel 0-ring and a control rod drive mechanism (CRDM) closure insert. These components were examined to determine if the metal had undargone any intergranular attack as a result of sulphur contamination in the primary coolant. The entire exami-nation was performed at the Lynchburg Rese2rch. Center.(LRC).of the. Babcock & Wilcox Company. 1.1 Component Description 1.1.1 0-Ring The reactor vessel 0-ring examined was- the inner of two- 0-rings. Four (4) - approximately 12-inch long sections were s'. tipped to the LRC. These sections were identified as follows: I Sample #1: contained circumferential weld; from X to Y quadrant: Sample #2: contained a circumferential weld.

                                                                      .~    .    .

Sample #3: taken from Z to W quadrant. - - -. - Sample #4: taken from end of W to X quadrant.. As seen from above two specimens contained a circumferential weld. ~~ The inner 0-ring is fabricated from alloy 718 tubing which is typically solu-tion annealed at 1950 !'25*F for '30 minutes maximum a'nd precipitation hardened I at 1350 25'F for 3-6 hours, air cooled.. The outer surface of this ring has been plated with silver. The tube outer diameter prior to plating is 0.500" 000 with a nominal wall thickness of 0.050". The silver plate has a thick-ness of 0.004" to 0.006". The mean diameter of the inner 0-ring is 169.750" m. 1.1.2 CRDM Closure Insert A single closure insert was sent for examination. This component forms a high elevation primary boundary in the upper part of the control rod drive mechanism. I I

I I BABCOCK & Wii.COX RDD:83:5490/5491:01

PACE 2 I

As such, the lower portion of this component comes into contact with the pri-mary coolant. The component is machined and assembled from type 304 stainless steel in the annealed condition. I IE 1 I I iI i !l

I 4 {

jI . !I . I il I .

BABCOCK & WII.COX RDD:83:5490/5491:01 PAGE 3

2. EXAMINATION PLAN .

Based upon the request for examination by OPU and discussions with NPCD, a work scope was proposed in Reference 1. This workscope was agreed upon with some modifications as identified in Reference 2. The tasks performed on cach component and a brief description of the procedures used is given below. _2.1 0-Ring The examination of the 0-ring consisted of the following tasks. ~ ~ ~ 2.1.1 Receipt Inspection The four 0-ring specimens were visually ex.2 mined and-photographed at low magnification to document any unusual appe.irance. O-ring outer diameter measurements were taken at O' and 90* with dial calipers to document the t ellipticity of the 0-ring tube's cross seccion. I 2.1.2 Nondestructive Examination The 0-ring specimens were examined using tiro eddy current techniques. An annular differential encircling coil was uaed with a 400 kHz and 900 kHz mix to suppress the effects of wobble. The other~ technique used a radial abso-i lute pencil probe with the same frequency nix. to suppress the effects of i lift-off. This examination was used to identify surface defects both on the OD and ID of the O-ring tube. _2.1.3 Radiography Radiographs at three orientations were performed on'the four 0-ring sections using a Norelco 150 KV industrial x-ray unit. The following operating para-meters were used: 140 KV 12 MA, 48" source to film distance, 3/4" to 3-3/8" collimator at source. Type M film was used with 45 second exposure time. 2.1.4 Surface Examination Stereo light microscopy and scanning electron microscopy (SEM) were used to ' I examine the ID and OD surfaces for evidence of any surface cracking and unusual I . 3 .

I BABCOCK & WII.COX RDD:83:5490 /5491:01 PAGE 4 _ I deposits. Kevex. energy dispersive x-ray spectroscopy was utilized to examine these surfaces for the qualitative composition of deposits. Samples 1, 2, and I. 4 received complete ID and OD examinations. Sample 3 was held in reserve and was not sectioned for ID examination; howe /er, the OD was examined by light microscopy. _2.1.5 Metallography Based upon the examinations above, locations for metallographic examination I were selected from samples 1, 2, and 4. S.imple #3 was~not destructively examined. Sectioning was performed with either a diamond saw, band saw, or hack saw. No water or cutting lubricant w.is used during sectioning. Samples were mounted in "Epimet" for excellent edge retention and processed with nor-mal metallographic specimen preparation procedurec. All specimens were exam-ined ir.itially in the unetched condition on an Olympus metallurgical micro-scope. Photographs were taken to document both' typical and unusual condi-tions. Examination of all specimens was performed _at,. magnific,ations frpm . 50X to 1000X in bright field illumination. A total of ten (10) metallo-

graphic sections were prepared and examined; four (4) were axial. sections, six (6) were transverse sections. Two (2) transverse sections and one-(1) -

axial section were examined af ter bending. 2.1.6 Bend Testing l Based upon the nondestructive examinations, both. axial and circumferential bend test specimens were selected. The axial bend specimens were approxi.- mately 2-1/2" long x 1/4" wide (circumference). These specimens were bent over a 1/2" diameter steel rod using a bench vise. Tests were performed which put either the ID or OD in tension. The circumferential bends were performed or. %3/8" long half cross section or "C" specimens. Again tests were performed to put either the ID or OD in' ten- " sion. The OD tension tests were performed by flattening the "C" section with a pair of vise grips. The ID tension specimens were pressed into a flat strip t I with a bench vise. A total of six (6) axit.1 bends were performed, three (3) in l I l I

I BA13 COCK & WII.COX RDD : 83 : 5490 /5491:01. PAGE.5 1D tension. Nine (9) transverse bend specimens were performed; five (5) in OD tension, fo 2r (4) in ID tension. I 2.2 CRDM Closure Insert . 2.2.1 Receipt Inspection The CRDM closure insert was visually examined and photographed at low-magnifi -- cation to document unusual or suspicious features. 2.2.2 Nondestructive Examination Eddy current examination was performed or the* outer surface exposed to .the I primary coolant. A radial absolute pencil probe was used to scan the entire surface. A frequency mix of 200 }diz and 900 kHs was used to reduce the re- - - sponse to lift-off. 2.2.3 Surface Examination . -

                                                                         ~  '     '

Low magnification stereo light microsco'py it$i~d' low to'h"igh' magnification scan - - ning electron microscopy was performed on nurfaces suspected of containing I defects based on the previous examinations. Kevex energy dispersive.x-ray-spectroscopy was performed to obtain qualitative. analysis of deposits.on surfaces in contact with primary coolant. 2.2.4 Metallography

      'IVo (2) metallographic sections were prepared. These sections we.re taken from two different surfaces in contact with primary. coolant.. Both,were mounted in "Epimet" to preserve,the specimen edges . The samples were pre-                    .

pared using standard metallographic technicues and examined in the unecched !ga condition. The examination was performed cn an Olympus metallurgical micro-scope at magnifications ranging from 50X to 1000X in bright ficid. Subse-quently, one specimen was prepared and examined in accordance with Practice A of ASTM-A262. Detecting Susceptibility to Intergranular Attack in Stainless l Steels. 'I . I i

I I BABCOCK & WU.COX _ RDD:83:5490/5491:01 PAGM 6 2.2.5 Bend Testing lg A total of eight bend specimens were prepared from two different surfaces 5 exposed to primary coolant. The specimens were machined strips removed from the insert so that the tensile surface had been exposed to the primary coolant. Specimen dimensions were either 7/8" or 1-1/8" long x 1/4" wide x 1/16" thick. The specimens were bent over a 1/4" diameter secel bar using a bench vise. Due to the curvature of the surfaces being tested the specimens did not have a flat surface in the tensile bend side. "he surfaces were either slightly I convex in the width direction with a radiun .of 1-1/4" or concave in the width direction with a radius of 7/8". During all handling and sectioning the specimens from both components were kept from.any liquid contamination and handled with latex gloves and poly-ethylene bags. The 0-ring specimens had a.'. ready been marked on the OD sur-face. with a black ink marker. I _ . - I I I I I I g -. I I

l . I !I !!AllCOCK & Wil.COX RDD:83:549_0/5491:01 PAGE 7.

3. RESULTS I 3.1 0-Ring Examination

_3.1.1 Receipt Insrection All four (4) 0-ring sections had a light silver appearance except for bronze colored stains associated with the seating flats on the top, bottom, and out-er diameter of the 0-ring. The inside dianeter of the 0-ring was free of I .hese stains. Associated with the brenze stain were y,rayish-black stains covering a much smaller area and located at the interface of the smeared flat seat and undisturbed surface. These ironze and grayish-black. stains were usually elongated in the tube axis direction. At high eagnification these stains could. be seen to be cracked and fleking-off in certairr areas. 'I Visual examination of these stained areas uith the.Nikon stereo light micro-g scope indicated that some axially aligned cracks may be prese..c in these 5 stained areas particularly near the interface betw'een'the flat seating and the smooth surface. I Dimensions taken at the major and minor axis of the now' approximate 1y'ellip-t tical cross section showed dimensions ranging from 0.501" to 0.504" at the major axis to 0.424" to 0.431" on the minor axis. 3.1.2 Eddy Current l'.xamination No defect indications were found on the ID or OD of' any of the four 's'ainple's. I 3.1.3 Radiographic Examination No indication of cracking was"found in any of the four (4) samples. Some broad circumferential bands were observed c.n all four samples; however, the location of these bands varied between oric ntations on the same sample and 8 the band was missing altogether in some oricatations. This is believed to be an artifact and had no bearing on tube integrity._ Subsequent examina-tions in these areas revealed nothing which would correlate with these marks. A porosity-like structure was seen on all four sections at specific I I

I BABCOCK & WII.COX RDD:83:5490/5491:01 _PAGE 8 . locations and orientations. No pattern appeared to be present and this pat-tern was not related to the welds. Roughness in the silver plate layer may account for this effect or it is an artifa:t. 3.1.4 Surface Examination Results Samples 1, 2, and 4 were each sectioned. axially yielding two 12" half sec-tions. Each half section was cut into three (3) approximately 3-inch I sections yielding six (6) specimens per sa ople or 18 specimens in all. The

results of visual, low magnification light microsco'py SEM, and Kevex indi-cated that some shallow cracking was present on both the ID and OD-of some - specimens, but not all specimens, and that sulphur was present on the OD.of the 0-ring and possibly on the ID in some . Locations. The ID cracking was contained ~1n regions'under the' top an'd' bottom seating flat'of the 0-ring. This is an area which is put in tension by bending during loading. Simi-larly, the CD cracking ,was found . adjacent ,:o. the cut.er di,ameter seating ,

   ,   flat, also.an. area.put.in. tension from. bending..during. loading.._-.        ... . . - --

Other than S and the--major elements in alloy 718 Ti, Zr, A1, Si and Cl 'were occasionally observed in random ID deposits. .The Ti and Zr seemed.particu . . larly noticeable in deposits near the weld in. sample 1 . Typically the.0D contained only Ag with a minor amount of Si. The bronze and grayish-black - areas observed frequently are areas rich in Fe, Cr, and N1. In the grayish-black deposits, Fe is the major component with some Cr and even smaller I amounts of Ni; in the bronze areas Fe .Cr, and Ni are found in approximately i equal amounts but much lower quantity. S was occasionally found associated with these deposits. Other elements occasionally found on the OD.in. adherent - deposits were minor amounts of Ti and C1. 1 . I I . I .

I BA11 COCK & WILCOX RDD:83: 5490 /5491 :01 PACE 9 3.1.5 Meta 11ographic Examination . A total of ten (10) metallographic specimens were examined. These sections came from samples 1, 2, and 4. Six (6) of these were transverse sections, two (2) of which were examined af ter bending. One axial specimen which had broken into two pieces was examined after hending. The examination results indicated that any cracking which had been observed in the surface exams was extremely shallow and,. in some cases, .:ould not be detected in the metal- -- lographic occtions. The deepest OD cracking observed was found af ter bending and it was 0.001" deep, entirely wit; 4.n then silver plate. One transverse I specimen contained a region of observable .ID cracking with the largest being 0.0016" deep. Etching in this structure revealed the crack to probably be , transgranular. Three (3) of the axial seccions examined contained welds.and other than one which broke during bending, no evidence of cracking was observed in, the weld zones. The specimen which broke had been examined on the SEM for fracture mode and- is. discussed in.the-next section. I .. . 3.1.6 Bend Testing Of the 16 bend specimens tested and examined, ten -(10) contained evidence of I cracking on either the ID or OD. Cracking ranged from shallow surface crack-ing to through-wall fracture. In all cases, however, the fracture features contained cusps and voids, or shear parabolas all indicative of a ductile rupture mechanism. ' There were_ no indications of any. intergranular . cracking. This was true near the surface in tension, where such cracks might act as initiation sites for f'urther propagation by ductile means, as well as deeper I into the fracture where active crack propagation was occurring. - 3.2 CRDM Closure Insert Examination 3.2.1 Receipt Inspection Visual examination indicated the prewnce of a grayish-black film on the I inside surface which had been in contact wf.th primary coolant. The outer surfaces which were also in contact with primary coolant did not contain this film. In general, the part appeared :.n very good condition except I . I .

BABCOCK & WILCOX RDD:83:549075491:01 PAG E .10 . I for the film. Small amounts of a white crystal were observed in the vent hole and these are believed to be boric acid crystals. 3.2.2 Nondestructive Examination Results from the eddy current pencil probe examination of the outer surfaces in contact with the primary coolant showed no indication of cracking. Eddy current examination on the inside surfaces was delayed and eventually not performed due to the need to confirm whether intergranular attack was occur-ring by examination on the SEM and subsequent metallography. 3.2.3 Surface Examination Examination of the inside surface film with stereo light microscopy revealed

                                     *                                        ~

a pattern which resembled intergranular at ack. The closure insert was sec-tioned dry using a band saw and milling machine to gain-access to this sur-face for examinat. ion.on the.SEM. .SEM.exanination. revealed that the suspected intergranular attack.was basically a film 1thich had-formed on the surface in - a pattern resembling a grain boundary network. This network was clearly I raised and could be readily smeared. Keve:: energy dispersive x-ray spectro-scopy revealed a large amount of Si to be present in the film with some S present also.

3.2.4 Meta 11ographic Examination l Two (2) metallographic sections were prepa: ed to examine the inside and out--

i side surfaces. No evidence of intergranular attack or cracking of any kind was found in and away from areas containing the surface. film.. One-section was further examined for susceptibility to intergranular attack and was t found to have an acceptable microstructure. lgl 3.2.5 Bend Testing Eight (8) bend specimens were prepared frou both inside and outside surfaces at 90' intervals around the insert. All bends were made without any obvious cracking. Further. examination of the maximum tensile strain areas on the SEM showed no signs of cracking. ,I i l _ _

BAllCOCK & WII.COX Run:83:5490/5491:01 . . . PACE 11... I 4. CONCLU'3 IONS Although the presence of S was detected on both the reactor vessel 0-ring and CRDM closure insert, no intergranular attack was found. Cracking which was found on the 0-ring surfaces before and af ter bending was ductile rupture and not intergranular. The closure insere contained no evidence of cracking before or af ter bend testing. lI I _ I . . . g . .. . . I I lI i 'I I 'I iI

      !!AllCOCK & WII.COX                                                                  RDD: 83 : 5490,'5491:01        l' AGE 12 -

i

5. REFER 124CES -

I 1 D. L. Baty to L. J. Stanck, " Proposed Work Scopes for Reactor. Vessel 0-Ring, and CRDM Closure Insert Examinations," March 31, 1982. 2 D. L. Baty to L. J. Stanek, '" Additions to Work Scope of TMI-l Reactor Vessel 0-Ring and CRDM Closure Insert Examinations," April 20, 1982. I I . e *- I I I . I en I I I I . I

TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 11 Inspected Item

RNS Retainer Type of Inspection: Destructive Examination Inspection and Tcat Plan: The retainer assembly includes a spring made of X-750 material which is under load in the cold condition. It also includes 304 SS material which is welded and is under load.

I I YES NO

1. Is the work scope in agreement with the B&W Engineering Information Record? i[

2. Was there an approved inspection / test procedure j used for this examination? V I 3. Does the results of the examination agree with the acceptance criteria called out in the inspection /

test procedure?

4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure?

I (Accessible quantity inspected quired l .)

                                                                       /   Minimum re-I  Note: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. I Based upon the results of this examination, were there any repairs made to the item (s) being in-spected, or recommendations for repairs or re-placements?

6. Does there exist any unresolved discrepancies that have not been,(reported) processed for future

resolution? V Note: If any of the answers to (5) and (6) are yes, a written description must be atte.ched.

7. B&W EIR No. T /- // %03-CD

    .. Tash ,,      ,r...d.r.                            No. + w . , n _ . ,

g Reviewer's Signature *% I I

I I OTSG Task 7 Inspection Area #11

Title:

RNS Retainer Exam Type of Inspection: Remote Visual / Local Visual / Met Lab Equipment Used: Westinghouse 1250 w/St. Lens I Procedure: Final Report Prep: G. R. Bond /E. D. Shoua - Visual Exam B&W LRC - Met Lab Exam I This inspection was performed in accordance with B&W EIR 51-1132403-00 and GPU Nuclear Fuels Memo NF-2620. The following individuals were directly involved with the examination on-site. E. D. Shoua - GPU Nuclear Fuels J. R. Stair - Nuclear Engineer, TMI-l Both retainers were examined using remote video and were found to be free of any discernable defects. The retainer in core location "P-4" (RNS I Retainer L106) was selected due to its slightly darker shading. A hands on examination was done and revealed no material degradation. Wipe samples were taken as requested and the entire retainer sent to LRC for Met Lab exam. I I I I I I

I NF 2628 ,

                                 .                                              Inter-Office Memorandum File:   701.2/4003.2 Data Subject April 27, 1982 TASK 7 PRIMARY SYSTEM REVIEW:                              -

MNuclear SUBTASK 11 RNS RETAINER INSPECTION To N. C. KAZANAS Location Three Mile Island DIRECTOR, QUALITY ASSURANCE I

Reference:

1. J. D. McCarthy to N. C. Kazanas, "TMI-l Task 7 Fuel Inspection Plan" dated April 16, 1982 Memo No. NF 2620; 2. B&W Engineering Information Record #51-1132401-00 "TMI-l RNS Retainer Examination", dated March 25, 1982
I In accordance with the above two references, the two retainers in the I core were examined by means of a video camera. The first retainer had a shiny appearance while the second retainer exhibited a uniform light brown discoloration over its entire surface. The video clos.eup of both retainers

'g                 revealed no visible degradation i.e. no visible corrosion cracks at velds, g             load arms or inconnel X-750 springs. In addition no visible signs of crud buildup was evident in either retainers and neither load arms were displaced
,                  from their norzal unloaded position.

l Itwasthereforedecidedtopulloutthediscoldredretainerfromcore location P-4 (Retainer No. R00006) for hands-on examination. As soon as it ! was removed from the water, the H.P. took a vipe sample from the outer surface of the can housing of the retainer, and a wet soak wipe sample of the coolant water. The RNS retainer exhibited about 25 mR/hr activity and conseque'ntly was brought up for hands on exasination. The hands on examination which consisted of a visual of the welds and spring showed no visible sign of material degradation; in addition, the load arm was depressed one/two inches four consecutive times with no sign of damage or permanent set to the spring. I ' I - 3

                                ?             .                                            .

I N. C. KAZANAS April 27, 1982 I Poloroid photographs were taken of the inspected retainer to document the condition of the wclds, the spring and the load arms. Subsequently, the inspected RNS retainer and the wipes were packaged for shipment to BW LRC as per Reference 2. A new retainer was installed'on the RNS in location P-4. , Mk E. David Shoua . Nuclear Analysis & Fuels EDS/ dss

I cc: G. R. Bond, Nuclear Analysis & Fuels Director J. J. C611tz, Plant Engineering Director, TMI-l I R. W. Keaten, Director, Systems Engineering J. D. Luoma, Manager, TMI Fuels Projects J. D. McCarthy, Fuels Project Engineer OA Engineer III Mechanical l'I J. R. Stair, Engineer II Nuclear, TMI-l D. G. Slear, TMI-l Project Engineering Manager W. S. Wilkerson, Lead Nuclear Engineer, TMI-l I .

I ~ I 4 I .

g . .

I

rm LRC-139 Rosoorch and Development Division LYNCHBURG RESEARCH CENTER gbCOCk & W.lCOX i tyNCHauRo, m oisiA J. E. MATHESON, FUEL ENGINEERING, NPGD cm - IRRADIATED MATERIALS TECHNOLOGY, LRC Ef. File No. GPUN or Ref. RDD:83:5489:01 8 hj. THI-l RECOVERY - RNS RETAINER EXAMLNATION Date - MAY 20, 1982 m.1.w.r *. , .me.=., d hi e ly.

SUMMARY

As part of the TMI-1 recovery effort, a RNS retainer was examined at the LRC Hot Cell Facility. Although it was unirradiated, the retainer had been installed I in-core since the EOC-4 outage in late 1973. Detailed testing of the retainer and its component parts included: e visual ====4n=tions a spring load-deflection and full-compression tests

sodium aside spot tests .
liquid penetrant checks bend tests metallography and SEM arm =4 nations I .

chemical analysis of surface wipe camples I While sulfur compounds were found on the external retainer surfaces, there was no evidence of mechanical property degradation or sulfur assisted intergranular attack. I I I

I . I I g # c. MW makes no warranty or representation, expressed or implied:

              . with respect to the accuracy, completeness, or usefulness of the information contained in this report that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights.

MW assumes no liability with respect to the use of, or for damages resulting from the use of: any information, apparatus, method, or process disclosed in this report

              . experimental apparatus furnished with this report.

1 I I I

I BABCOCK & WILCOX RDD:83:5489:01 Page 2

1. INTRODUCTION Analysis of cracked tubes from both A and B steam generators at TMI-l indicated I the failure y de was intergranular stresu corrosion cracking with a reduced '

form of sulfur most likely acting as the corrosive agent.1 Since the tube cracks were initiated from the ID surface, the presence of sulfur contaminents in the primary system implies the potent:.al for material degradation of other RCS components. . I A detailed examination of a regenerative neutron source (RNS) retainer from the TMI-l core was conducted at B&W's Lynchburg Research Center as part of an effort to assess potential damage to various core components.2 Although the retainer was unirradiated, it had been installed during the end-of-cycle four outage, and the retainer spring and load legs had been in a stressed condition while exposed to the RCS environmenc. A RNS retainer was selected for exami-nation, since it contained materials reptesentative of a wide range of core components (304 SS, 308 SS weld metal, ar.d Inconel X750). After receipt at the LRC, the retainer (fL106) was visually examined and load-deflection tests of the spring were performed. The retainer was then dis-assembled and the following tests were conducted on the components: e detailed visual examination 6 e spring compression test a sodium azide spot tests e liquid penetrant checks e bend tests e metallography

           . SEM examinations i

Chemical analyses were also performed on cloth wipe samples from the retainer components and on samples obtained at the reactor site. Wipe samples taken at TMI-l were from the north face of a new f uel assembly (NJ0132) and from the retainer, prior to shipment. I I

BABCOCK & WILCOX RDD:33:5489:01 Page 3 ' , This letter report presents results from the examination of the retainer at the i LRC and the chemical analysis of the cloth wipe samples. E + .. i t I I l I _ .- - ~ i g ' I I I I y __ I I I

I BABCOCK & WILCOX RDD:83:5489:01 Page 4

2. EXAMINATIONS AND RESULTS3 s 4 I 2.1 Visual Examinations i

l I 2.1.1 Method Visual examination of the retainer and its component parts was conducted at magnifications up to 60X with a stereo microscope. Photographic records of visual observations were taken with a 4X5 camera attached to the microscope. Macrophotographs of the retainer were taken with a MP-3 copy camera.

l i 2.1.2 Results A visual inspection of the tstainer, prior to disassembly, showed no cracks in the weld, knee, or foot regions of the retainer legs. A schematic view of a retainer identifying its various components is shown in Figure 1. Typical macrophotos of the leg weld, knee, and foot regions are shown in Figure 2. l Virtually no crud was observed on the outside surface. Overall views of the

 . _ _ __ retainer are shown in Figures 3 and 4.          _        _

After disassembly all retainer components were examined in detail. Disassem-bly consisted of cutting the top fitting off the can and cutting the numbered leg from the hub through the weld area. Examination of the retainer legs showed no cracks or evidence of sulfur assisted attack of the surfaces. Sev-eral areas of black and white deposits and two small areas of yellow deposits were noted. The black areas are most likely crud and the white areas appear to be boron crystals from the coolant. The previously reported SEM/EDX analy-sis of the yellow deposits 4 was incorrectly based on a contaminated sample. Other EDX analyses on similar deposits found on the reactor vessel o-ring in-dicate the composition is mostly Fe with some Cr.5 The spring surface was a uniform dark gray with localized areas of black and white deposits (see Figure 5). Two small areas also had yellow deposits similar to those found on the retainer leg. Examination of the retainer can showed no signs of surface deg-radation. The outside of the can had a thin, black oxide layer with a blue tint. The inside of the can had a dark, powdery crud layer with several areas of localized crud deposits. I I

!I BABCOCK & WILCOX RDD:83:5489:01 Page 5 ! 2.2 Spring Load-Deflection Tests 2.2.1 Method Prior to disassembly the X750 spring was tested for preload and spring rate using a load-deflection test rig previously used for irradiated retainers from - Oconee 3.6 'The retainer spring was compressed using known weights of up to ! 100 pounds, while spring deflection was measured with two dial indicators accurate to 0.001 inch. Ig 2.2.2 Results

E t

Three load-deflection curves were recorded and are shown in Figure 6. Measured I spring preloads ranged from 40 to 41 pounds and spring rates from 48-50 pounds per inch. These values are considered normal and agree with other retainer data. 2.3 Spring Compre.9sion Test ] 2.3.1 Method After the retainer was disassembled, the spring was compressed to its solid spring height using five lead bricks. Eack brick weighed a nominal 26 pounds. Relaxed spring height was measured before and after full compression with dial calipers accurate to 0.001 inch. 2.3.2 Results .I Relaxed spring height before and after full compression was 4.00 inch, indicat-ing no plastic deformation occurred during testing. After testing, the outer surface of the spring was visually examined at 10X magnification with a st.ereo 1 i microscope. No cracks or other forms of damage were observed. ,I'

     . 2. 4 Sodium Azide Spot Tests f

2.4.1 Method 7 Sodium azide spot tests for the presence of reduced forms of sulfur were con-ducted by placing drops of test solution on surfaces of interest (spring, leg,

!I

g

BABCOCK & WILCOX RDD:83:5489:01 Page 6 weld area, inner and outer can surfaces). The areas where the drops were placed i were then ' observed through the stereo microscope. Bubbles from the solution indicate the presence of reduced forms of sulfur (sulfide, thiosulfate, etc.). The basis for the test is the catalytic neceleration of the iodine-azide re-action by r$duced forms of sulfur. This reaction evolves free nitrogen gas tof - produce bubbles and will detect reduced forms of sulfur at concentrations less than one ppm. E

E 2.4.2 Results Outside surfaces of the retainer components showed positive reactions to the sodium azide spot test. The inner surface of the can and the retainer spring showed negative reactions. Results of the tests are summarized below:

Retainer Comoonent Run Spring g Leg-Weld Can (outside) Can (inside) 1 neg. pos. neg. pos, neg. 2 neg. pos. pos. pos. neg. g Tests indicated the presence of reduced sulfur on outer surfaces of the retain-WI er. The inside of the can and the Inconel X750 spring showed no evidence of a reduced sulfur, but results may have been affected by crud deposits. 2.5 Liquid Penetrant Tests , 2.5.1 Method Liquid penetrant tests were conducted on the retainer leg and hub and on the spring using the procedure specified in Reference 6. The pieces were ultra-sonically degreased'with tichloroethylene, cleaned with Spotcheck Cleaner / Remover, and dried with clean cloths. The parts were sprayed with Spoccheck

       . Penetrant and kept thoroughly wetted for 20 minutes. The spring was tested while under compression to open any cracks that may have been present. After removing excess penetrant, the parts were uniformly covered with Spotcheck developer and visually inspected.

I i I I

I . BABCOCK & WILCOX RDD:83:54H9:01 Page 7 1 2.5.2 Results No indications of cracks were observed in either the leg, weld area, or spring. l The only positive indications observed were from elongated surface inclusions , on the sides of the leg. l I 2.6 4 Bend Tests b 2.6.1 Method Bend tests were performed on the leg / hub weld region and a 1-1/2 inch piece from the middle coil of the spring. The parts were clamped in a vise and bent to open any cracks which may have been present. 2.6.2 Results The leg weld was bent through approximately 45 degrees with no visible crack initiation, indicating a sound weld. The spring sample was bent and fractured. The fracture surface was examined with an SEM to characterize the mode of failure. The SEM examination showed the fracture surface was new and failure was 100 percent ductile. Examples of the appearance of the fracture surface are shown in Figure 7. No evidence of intergranular cracking was observed. 2.7 Meta 11ography 2.7.1 Method Samples from the leg, knee, weld area, and the active evil and contact region of the spring were mounted in Buehler Epomet. The samples were ground flat on silicon carbide through 600 grit and polished with alumina. Final polishing

,  I  was done with 0.05 micron alumina. The samples were then metallographically examined at 400X magnification for evidence of intergranular attack. The samples were examined in both polished and etched conditions. The Inconel
     'X750 spring material was etched with copper regia and the 304 and 308 stainless
 ;    steel samples with glycerol regia.

I I

BABCOCK & WILCOX RDD:83:5489:01 Page 8 2.7.2 Results i The microstructure of all the samples appeared normal and no evidence of inter-granular attack was observed. Figure 8 e, hows typical etched microstructures of the 304 SS base metal, 308 SS weld metal, and X750 spring. The weld area and I heat-affecthdzoneareshownat50XinFJgure9. b 2.8 Chemical Analysis of Surface Wipe Samples 2.8.1 Method cloth wipe samples were taken from the RNS retainer and a new fuel assembly, NJ0132, at TMI-1 prior to shipment of the retainer to the LRC. The retainer wipe covered 15.5 square-inches of the leg area. The fuel assembly wipes covered one face of a grid and across 15 rods just below a grid. Wipe samples I were taken from the retainer after disassembly at the LRC. Samples were ob-tained from one retainer leg, two coils of the spring, and the inner and outer surfaces of the can. ,I Wipe _ samples from the disassembled retairer were analyzed for chlorine content I by a LRC procedure similar to ASTM D512. " Tests for Chloride Ion in Water and Waste Water " and for sulfur content by a procedure similar to ASTM D516. " Tests for Sulfate Ion in Water and Waste Water." Since the chloride ion results were low (8 pg total or less) and used half the wipe sample, wipe samples from TMI-1 i were only tested for sulfate content. 2.8.2 Results Chloride and sulfate ion contents of wipe samples from the retainer parts were low, < 5 to 8 pg total Cl and < 20 to 50 pg total S02 . When the back- ' ground from the cloth samples was subtracted, only the sample from the spring showed any removable sulfur. Results of the sulfate analysis of wipe samples are given below: I 1 I ,I 1 1

l BABCOCK & WILCOX RDD:83:54~39:01 Page 9 LRC Wipe Sample Results (cloth batch 67) RNS Total Less Total

Wipe Component Removable SO A , pg Blank Sample S, pg Area, in2 Sulfur, pg/in2 d'

blank 18 5.~~ ! blank 15 Avg <20 Leg <20 - -- 20 - g Spring 50 >30 >20 9 N2

'W        Can                25            >5             >3        28               -

(outside) Can <20 -- -- I (inside) I

on a whole cloth bas-is Cloth wipe samples taken from the retainer after it was removed from the core and from the fuel assembly grid and rods showed slightly higher levels of re-movable sulfur, in the range of three to five ug/in2 Results of the sulfate analysis are given below:

TMI-1 Wipe Sample Results Cloth Total Less Total Wipe Batch Sample Removable SO4, pg Blank Sulfur, pg Area, in2 Sulfur, ug/in2 75 blank 30 blank < 10 Avg <20 Zr Fuel 50 >30 > 10 2.7 N4 Rods - Inconel 90 >70 >23 8.1 N3 Grid 71 blank <10 blank 20 Avg <15 Cloth 20 >5 >1.7 ' l Dipped

I in core Retainer 243 228 76 15.5 NS

i l BABCOCK & WILCOX RDD:83:54119:01 5 Page 10

3. CONCLUSIONS

!n.E J While reduced forms of sulfur were detected on the retainer components, there was no evigace of mechanical property degradation or intergranular attack. h, !I " lI l8 , !I 1 I . I 1 I I .t. I I I I I

I BABCOCK & WILCOX RDD:83:54119:01 Page 11 I

4. REFERI:NCES

1. M. A. Rigdon and E. B. S. Pardue, " Evaluation of Tube Samples from TMI Final Report," RDD:83:5390-03:01, Babcock & Wilcox, Lynchburg, Virginia, April k982.

2. C. G. Dideon to D. G. Culberson, Memorandum, "TMI-1 Recovery - Core Exami-nation' Task," FPO-82-41, March 24, 1982.

3. W. A. McInteer and G. M. Bain to Distribution, Memorandum. TMI Core Re-covery - Initial Retainer Exam," April 30, 1982.

4. W. A. McInteer to C. G. Dideon, Memorandum, "TMI Core Recovery - RNS Re-tainer Detailed Exam," May 6, 1982.

5. D. L. Baty " Examination of TMI-2 Reactor Vessel 0-Ring and CRDM Closure Insert," RDD:83:5490/5491:01, Babcock & Wilcox, Lynchburg, Virginia, May 25, 1982.

6. E. B. S. Pardue, " Examination of Oconee 3 RNS Retainers," LRC 9085, Babcock

                                      & Wilcox, Lynchburg, Virginia, February 1982.

7. F. Feigl Laboratory Manual of Spot Tests, p. 163-166 Academic Press, New York, 1943.

I I I l I ; c<;. lI ,I .I l I 1I

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I t I , i 1 1 4 'l TEST i 6 i I I : I I I I I I I

I TEST COMPLETION REVIE'4 SHEET Task #7 Inspection / Test: 6 Inspected Item: Potor Tube Extension (3) Type of Inspection: Ultrasonic Inspection and Test Plan: These motor tubes are made of SA312 GR TP 304. Included in the examination is one weld seam on each motor tube which is in the as welded" condition. This examination will include heat affected zone and stainless filler metal. Two of these tubes were reworked prior to installation to remove flaws induced by the hot drawing process. There-fore, they may have had small initial flaws which would make them more susceptible to corrosion attack. YES NO I 1. i Is the work scope in agreement with the B&W Engineering Information Record? y 7

2. Was there an approved inspection / test procedure used for this examination?

I 3. Does the results of the examination agree with the acceptance criteria called out in the inspection / test procedure? //

                                                                              /            N'O l     4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure?

N4f ry19#0 j7 (Accessible quantity inspected :7 Minimum re-

quired S .) [

Note: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were l there any repairs made to the item (s) being in-I spected, or recommendations for repairs or re-i l

placements? [

6. Does there exist any unresolved discrepancies that have not been (reported) processed for future l

1 resolution? [ Note: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. I/- //82 -d!

8. Task #7 Procedure No. M A /. f2- 6 0 8 Reviewer's Signature /

l d

I J l I . Test Completion Review Sheet Comments, Task #7 Test #6, Motor Tube Extension (3) I Item #3 The ultrasonic examinations for APSR #63 and 66 were examined

.               inplace atop of the reactor head. This exam did not reveal any indication which exceeded the acceptance criteria. The ultrasonic examination of APSR #68 was performed after it was iI removed from the reactor head.      An ultrasonic reflector was detected, this reflector exceeded both amplitude and length of that stated in the acceptance criteria. At this time, this reflector is only being classified as a suspected indication.

further investigation is on-going to determine the nature of this reflector and until that is established APSR #68, connection , weld remains an open item. Rodney urner NDE Specialist !I lI l lI I

cr . 4 h g Inter Office Memorandum April 26, 1982 late ISI/M82020 bject Ultrasonic Examination of the CRDM Motor Tubes APSR #63 and #66 (Task #7 Test #6 Partial) T3 N. C. Kazanas Location Parsippany An ultrasonic examination was performed on the motor tubes APSR

              #63 and #66 on April 15, 1982 by Materials Technology personnel. Both APSR's were found to be acceptable.

These two (2) APSR's were still bolted in place on the Reactor Vessel Head during this examination causing access problems which were overcome I with some difficulty. The connecting veld, 1" above and 18" below this weld was the area subject to this inspection. An ultrasonic reflector was detected and reported in the connecting weld area on both APSR's. These reflectors were recorded on data sheets 000070 and 000071 (attached) APSR

              #63 and #66 respectively. These reflectors were plotted on the indication plot form (attached) and found to be attributed from a change in thickness on the I.D. A longitudinal beam test was performed prior to plotting which verified that this condition exists in both APSR's.

APSR #63 revealed this reflector 360 intermittently while APSR #66 showed this reflector continuously for 3600 This falls into the guidelines I that APSR #63 change in thickness is not as severe as APSR #66. This change in thickness is cuased by a honing process which was employed on the I.D. surface to remove hot tears, which developed during fabrication of the motor tube. Limited scan reports were issued to denote that 100% scanning was not obtainable due to the stator and thermocouple connections which caused inter-I ference. The exam was performed in accordance with procedure MTIS-008, Rev. 4, FCA TMI-1-005 and STP-1-82-0015. The acceptance criteria employed was taken from B&W E.I.R. document 51-113-2496-01. This test is only partially I completed. The examination of APSR #68 is still open, and can not be per-formed at this time. The Plant is still attempting to remove this APSR from the Head due to the fact that this APSR requires a greater extent of ultra-sonic inspection which is inaccessible when attached to the Head. A follow up report will be issued upon completion of the ultrasonic examination of APSR #68. I

                                                  #AA-RodneyTuger NDE SpecMlist RT:ef cc:   C. Cowfer                                                              acocosas I                 J. Potter G. Rhedrick M. Zeise

M - M M M M M M M M M M M l' L 21 Nuclear NDE Ultr: sonic D:ta She:t 000070 Site: ffffy- / Inspection ID: pjj// Component: Leg)g/ /A/en* Age

Description:

stjjf.*g feje dgaxcflac usto// ,/ ff f ag; .t,,f g y' / "M$ce/t ddAlaittY dC M/r//, Cal. Block:,,yggenfot/ 1.D.:A/e/s.e /afe ##f/2 84M Procedure:jfff:.,af /h// Material: E/f Thickness: , J g. In. Test Surface: g,3 No. Positions: / Distance: p//A In. Drawing: /[/;F Cal. Sheet ggp//g Cal. Sheet: god /// Cal. Sheet: [ [ Beam Direction Long 2 Shear Limited Exam O No f#ies Angle: gar'd ff' # Angle: Angle: f [ / Examiner:[Ah g gg ID#: /p/g Level:g Time Start://*/d Hr. Time Start: /f'// Hr. Time f[t irt:/ / jr. Examinerpfgdhg gjf p L;ye ID#: A3?y Level: F Time Stop: /g,*/p/ H r. Time Stop: /yyy Hr. Timej!stM / //Hr. Notes: ' O Part Temp: 72 0 *F Part Temp: 7/' O *F Parfe[p:,/,/ *F Date:f$ // /ffz hte: ll l Date:j.fffe 'ffgjffz, r 0* Information'Only << Weld HeightM*J/ Weld Width 28d Surface One to Surface Two BM Haz Q W eld Haz BM

                                                                                                                  .3So         .3/S        . 1/3     . 3/* . 3c S LAM       LNGTH WIDTH                I        Through Walt Dimension g        Q                                            Minimum               Maximum
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A/ o/'AntseoJ Ap/)$teofef No Reportable Indications Reportable Indications Q Non Relevant Indications [

Revie. I by: gk[ y Lg gDate:/[j, 'h Page / of [3 NDE Request No. /[4

                                                                                                                                                   /
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Annlednd Nn O Den /n-199 45 Deo/2OO-399 6[Deo/400-599 Other/600-799 ar. , , AOOOO926

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J Nuclear I NDE Date:pge,ysf tyrz Limited scan neport Data Sheet No.: 0000/d Component: com sei..e +0s e spx #G No ' CW v # 1 1 V Surface Beam Direction Limited Scan V Surface 2 V Beam Direction 2 V CCW [ Inches from Referenc 72 inches ,ge From Reference Point./7N Yo di'yinches Point from to W .d L -L p o/* d#DM bd s For Angles: O' 45' V 60* Other Due to: SYAb A ; YbA#0 $dWE $0N MYe Examiner: [ l D. n: /[/8 Level: {///_ l Date: f.g g2. y No 1 1 CW Surface Beam Direction Limited Scan Surface 2 Beam Direction 2 CCW Inches from Reference Point to inches From Reference Point. inches from Weld Centerline. For Angles: O' 45* 60* Other Due to: Examiner: l 1.D. #: l Level: l Date: No 1 CW l Surface 1 Beam Direction Limited Scan Surface 2 Beam Direction 2 CCW Degrees, Inches from Weld Centerline. For Angles: 0a 45* 60* Other Due to: Examiner: 1.D. * : Level: Date: No 1 1 CW Surface Beam Direction - Limited Scan Surface 2 Beam Direction 2 CCW Degrees. Inches from Weld Centerline. For Angles: Oa 45' 60* Other Due to: Examiner: l LD. #: l Level l Date. Reviewed by: l Level: l Date; l Page d ofI s-e t A0000930

m M Nuclear NDE Ultrasonic Data Sheet 000071 Site: W,yff / Inspection ID: //// Component: dLpgj fyjefog .,4sje

Description:

p)pofore faf g gappeef}ap gug-fg fo 64,4, f "A fear e ,p p d / / " j e fear fjh goe,fr Cal. Block:g_enf.et/ 1.D.:A e /o f /dd e /9/afg Yd Procedure:gfg.o f4h/[ Material: d] f Thickness: , go In. Test Surface: d.d. No. Positions: / Distance: je//fst in. Drawing: p/gr

                                                                         /             Cal. Sheet 840 /fg          Cal. Sheet: ddd/// Cal. Sheet:                          /

Beam Direction Long N Shear Limited Exam O No l Wyes Angle: $ Angle: W Angle: J (( Examiner:/Qg $ Tgger ID#: /g/3 Level: g Time Start: //;f7Hr. Time Start: //.-(f Hr. Time %rp/ / [Hr. Examiner $g[hh .:pJJA L;ge ID#: f)37y Level: Y Time Stop: /4.* 2/Hr. Time Stop: JZ*ef Hr. Timp/ S kp:[ (( Hr. Notes: 8 / Part Temp: 72

O *F Part Temp: 78 "O *F O 'F P[ Te'n/: '

Date:jffje.'/ /f, fff 7. Date:jffk4'/fffffL bate:l}l O' information nly Weld Height MJ/ Weld Width 2I* Surface Onc to Surface Two BM Haz @ Weld Haz BM

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s No Reportable Indications O Reportable Indications Non Relevant Indications d Revi; 'd by: gj , Lev g g Date: fi/g '-}- Page / of 3 NDE Request No.gg , Angle /ind. No. O Deo/O-199 Deo/200-399 60 da/400-599 OEer/60h799 AOOOO928

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          !            Inches from Referenc                  [        inches    //ML From Reference Point /7M"r* Pf'yinches    Point tofrom "!dd C;.,,cione        @p og gRD#/

For Angles: O' 45' V 60* Other Due to: SN - "th'2A0 $ddAl* $dNM0b A [ff/~2. Examiner:[M LD.*: ///3 Level. ~/// Date: J <I No Surface 1 1 CW Beam Direction Limited Scan Surface 2 Beam Direction 2 CCW Inches from Reference Point to inches ' From Reference Point. inches from Weld Centerline. I For Angles: O* 45* 60a Other Due to: Examiner: l l D. e: - l Level: l Date. 'S i5 No 1 1 CW Surface Beam Direction Limited Scan Surface 2 Beam Direction 2 CCW <I Degrees, inches from Weld Centerline. For Angles: Oa 45* 60' Other Due to: Examiner: I D. #: Level: Date: I No Limited Scan Surface Surface 2 1 Beam Direction Beam Direction 2 1 CW CCW Degrees, Inches from Weld Centerline. For Angles: Oo 45* 60* Other Due to: I Examiner: Reviewed by: llD=: l Level: l Level. l Date: l Date: lPage1of2 g .. *oooosso

E'8 EEIR 15 8 EEER W umst m aus um nas aim aus em unre aus gun uma sum Nuclear 000186 NDE Calibration Sheet Sits: [///f / Inspection ID: /V/j;f Componentqbfyy . Agfg f,g ProcedureMg.jof Rev. / Ex: miner: [dgy M %gg ID#: /[/8 Level: ~~7//~ Couplant: Jojs/o-ffdAdc k o Ex: ming,7,] hQ gjg7 Z g ; y ,,,,, ID#: A 3 ')/ Level: [ Couplant ID#: g/ff//d Drawing # ' g[j/ j ) Calibrat on Bloc ID# /7/c'f-a8'- 8 'p Crystal ID# 4 25//9 Date:4/F//.f ////_ Time: /-/,*f( Search Unit Cable Instrument Length 7/I," In. Type ZJ Typepffg A AerID W .,do 7 Length 4 ' pffggg OD F in. Freq. # 2# MHZ ID#- Thermometer YA/ 9 Linearity Check O Yes &ffo Te p al$ ctual W "' ' ' Required t r '75 or i ing) Reject: o 43 A System Calibration Mat't. Cal.: 2. 2/ Angle gle Cal. Dir. DAC Plot 100 % Delay: I.7g al V Grc.O j pfg' Amplitude Screen Reading go 1 2 5 4 s Pulse Energy: Reflector % of FullScreen ininches 80 " Coarse Gain in DB: 20 R2 t/8 Node /d % * (2f In. 70 Fine Gain in DB:

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Fine Ga,n: i /M /* % . pyf in. ; 50 Screen Range: 2. I /* '"' 40

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I M* / de g/A % gg in. I Screen Depth: In. 30 2 " '- " - - I I' I -I OT&R In- 20 Operation Top Notch [ % f In. 10 Opposite Notch \ % In.

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                                                                                                                                        , Crystal
                                                                                                                                        / Pf//f Date: A4t','//4 /7/E- Time: /t.' *//

Search Unit Cable Instrument Length 7 M In. Type M Typeps/us b,/ ID --/ zf.oo P Length / ID#: 2// of0 OD #" In. Freq. M& MHZ M7 Thermometer Linenity Check O Yes LVNo Te p 2 *F ctual I " 488 eu d tr'75 o i ing Reject: System Calibration Mat'l. Cal.: d. ES Angle R o Cal. Dir. DAC Plot Delay: d 7 Z- Axial O Cire. Y- 100% pfj Amplitude Screen Reading go Pulse Energy: Reflector % of Full Screen ininches 80 " Coarse Gain in DB: 2O - -- - -- - - - Fine Gain in DB: 2 d /8 Node f0 % , 8 2 / In. 70

                                                                                                                                                        '"'     60 Fine Gain:                     M/A                                                                                      '

50 Screen Range: 2. / !* '"' 40

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Screen Depth: 2 75~O in.

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                                                                                                                            /       In.       h         in. g,y,yjg##g Date initit             h                     /                                  [        /                  /[                    \                       '[            '#'

Bkr CB (Back Reflecton From Cat. Block) Bkr P (Back Reflection from Part) A0000927

B Inter Office Memorandum Date June 2, 1982 MT/2049 - g Evaluation of APSR #68 Ultrasonic M0d Indication. Task #7 Test 6 (Completion) I Ta N. C. Kazanas On April 26, 1982 an Ultrasonic Reflector was detected and plotted out. This signal was believed to be originating from an indication that was developed during original construction and not caused during service such as IGSCC. The signal was plotted out on thq plot form (attached) and found to be located at approximately .075" from the outside surface. The indication had a length of 8.550" which equates to 230 degrees and produced a general amplitude I of 100% of DAC. A review of the original (Base line) Radiographs was conducted. This I review revealed that a grain boundary existed in the base metal adjacent to the weld in the motor tube extension. This condition was noted on the film in one (1) area, however, the report made no mention of this condition what so ever. A review of the Ultrasonic indication plot against the Radiographs dis-closed that the Reflector found Ultrasonically was possibly the same condition found Radiographically (Grain Boundary). A Radiographic examination was I conducted on the APSR in the area of the Ultrasonic Reflector to verify that a defect did not exist and that the Reflector was from the Crain Boundary of the weld to HAZ of the base metal. Two (2) areas were exposed and in both cases no indications were detected, the Grain Boundary could not be observed due to the use of a higher source (IR192) of power employed, this fell into our thinking prior to exposure. The APSR #68 was re-evaluated and found to be acceptable as is. The Ultrasonic Reflector was caused by Grain Boundary in the HAZ of the cap connection weld. No other further work or testing is required. i I /n dney rner NDE Sp ialist RT:bif Attachment cc: C. D. Cowfer J. Potter G. Rhedrick M. Zeise I AOOOo648

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ggg m m ma W W G W W M M M W M M NDE Ultr=cnic Dzt: Shret 000072 Site: M /_Z'~ . / Inspection ID: je//j;r Component: ddd#1 ff/d/a4 -fv8c -

Description:

fyjg-fs,( -/' o b e dAjd tsJ e/d honeds'at tack fa Mo*fese '7'Jbt* erNAC/o d Cal. Block:,gg,gjf I.D.:p[" *,[,[jh,f #f,"[f[y, f yy Procedure:ffff;,s.oof fa/p/ Material: J[g Thickness: . Jfo in. Test Surface: g,J, No. Positions: / Distance: g/A In. Drawing: /[g Cal. Sheet ggg/g/ Cal. Sheet: ggo/g7 Cal. Sheet:[ [ j! Beam Direction #/d Leng 2- Shear Limited Exam L3fTio O Yes Angle: g* Angle: sy [' O Angle: [/ ((f Examiner:[ @ fs,,,4 10#: jf/J Level:g Time Start: /./'ff /Hr. Time Start: ///7 Hr. Time S;drtf ((((Hr. Examiner: 6 je///J ID #: N/sv [ Level: Time Stop: /f*ff Hr. Time Stop: //.'.f2 Hr. Timejstol[:// / [ Hr. Notes: Part Temp: 18__ O F Part Temp: /.5 0 F Pay [Temhl/ , F fcfe/edCR //N 4. 3 fart /40' $*l E/ U0 lo 0l/ C # Date:gyf' gg /ff2 Dateg}Qff /ffz fte: fl

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44 //[ Crew 4 [/ ifs 4 <t , ' O* Information bnly ., Weld Height '/fd Weld Width m2fd Surface One to Surface Two BM Haz Q_ Weld Haz BM

                                                                                                                                 . Sfo       Sfo            . 5 90   .335 . 3f6 LAM        LNGTH     WIOTH                                  Through Wall Dimension g        j                                                         Minimum                  Maximum

[o) y y Position Position g 9 e 6 E E S E In. In. 2 e g < r & .e o r r e ? I n 5 U E O E 1 2 E O 1 2 CW CCW 1 2 CW CCW CW CCW Remarks 200 ff 2 / fyf)f .73/ f37[ ~ 8Sb -

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No Reportable indications Reportable Indications ~ Non Relevant , Indications [ Reviewed by: [j [ - Levekf[g.g/7Date: f'//g PageJ of$ / NDE Request No./j angiMno N.. } O Deg/O 199 45 Deg'200 399 60 Deg/400-599 Other < 60L f9 lAOOOO926

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ucTear sus sua en aus uma una use en se Emu um mun aus W Eum mim 000188 NDE C librati::n Sh:et Site: gg-/ Inspection ID: gj,/4 Componentgo,, frfs/g -/*J7/c Procedurefff;j- do p Rev. / Examiner: I [M g ffpeg ID#: /gg3 Level: _. g Couplant: 8di/ die ~d/de 4 q Examiner: g/jp ID#: gj[// Level: gj/A Couplant ID#: g/7,9//d Drawing # g , Calibrat on Blo ID M / set-ed a //ck l0 g Cr J. 2.ystal S*// Date://Nlf/Zt, /ffz Time: //V7 Search Unst Cable Instrument Length 7M~ In. Type- 4S Typefp/gfoJoe I WC.d49 Length g # pfgfo OD # In. Freq. 2 2.$~ MHZ Thickness ,MO In. Size .25e sC in. Thermometer YN N Linearity Check do (Required Summer '73 for Vessels O Yes Temp /2 F Actual II Required Winter '75 for piping) Reject: d[8 System Calibration - Mat'l. Cal, d. 9J Angle ff_ Cal. Dir. 100% DAC Plot el y: - j Axial F# Cire. O Amplitude Screen Reading go 2 3 4 5 Pulse Energy: Reflector

                                                                                                                                                                 % of Full Screen                 ininches                                     x-Coarse Gain in DB:                                 Ed                                                                                                                                                           80 Fine Gain in DB:                                   22
                                                                                                                                               /8 Node                    g/)         %        . ,$~ 2 5 In.              70
                                                                                                                                            /o/8 Node                                                                     60
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                                                                                                                                            /*/18 Node                  2f
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Screen Depth: /.760 In.

                                                                                                                                               /8 Node               p/4               %           g/A        In.

30 : - T '- _ : : ::\~ - " - "~ g O T&R Operation

                                                                                                                                               /8 Node                /                 %          [          In.        20
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Top Notch ( % k in. 10 Opposite Notch ) Frequency: 2.I MHZ i

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In. Top Notch ys/4% jf/Aln. %[ Irf [% in. [% iga 7- In. Opposite Notch [% fin. 9/ lj. /% / % /In. % I In. Reviewed By: Notch h% hin. [ lb.,/ % [ In. % j/ In. % ( in. Level ///eM"/![/' Date [ BL < CR (Back Rs.. crion From Cal Block) 8kr P (Back Reflec on from Part) AOOOo m 1

M M M M M M M M M M M M. - W M M NDE Calibration Sheet Site: fg / Inspection ID: /[4 Componentg/3rn #ade %4c Procedure fyffI'- d Rev. . Examiner: [d M gwg ID#: ffgJ Level: g Couplant: Sd4st~ff/d'c #Jd ' Enaminer: [g ID #: gA Level: f[/A Couplant ID#: g/7f//B

                                                               ' * "9 #

ID# - / ID # /2 / S at hU abi instrument Length 7N In. Type 4S Type />NM 2e f ID 76- dd 9 Length g ID#: EN '* ****' Th ckness . FI'd ze 4 4 n . Linearity Check O Yes Edo Temp /2 F Actual Mf~ ' R t r '75 or i g Reject: 688 . System Calibration Mat'l. Cal. /. /4 Angle d o Cal. Dir. DAC Plot Axial O Cire. ( 100% Delay: l 7g Pulse Energy: g Amplitude Screen Reading go 1 2 3 4 s

                                                                                                                                                                                                                       ~ Regector               % of Full Screen               ininches            80--

Coarse Gain in DB: __/o

                                                                                                                                                                                                                    @f/8 Node                                fo %             . 52f In.            70
                                                                                                                                                                                                                                                                                                                        \

Fine Gain in DB: 2/ 60 -2 *- Fine Gain: j/"/. /a /8 Node _ fa% . g7f In. 50 [

                                                                                                                                                                                                                                                                                                                                                              ?
                                                                                                                                                                                                                     'Y ' "

Screen' Range: ?.S - U * *IES '"' 40

                                                                                                                                                                                                                                                                                                      ~   " " "                   "        ~ ~ ~~

Screen Depth: __. / 780 in. Node 4/A % p/g in. 30 2 ' ~

                                                                                                                                                                                                                                                                                                                        ~ ~" ~                    ~ ~~

O T&R In- 20 Operatica Top Notch ( % [ In. 10 \ Opposite Notch "' "" '" "' '" " Frequency: 2I MHZ ) % \ In' O 1 2 3 4 5 6 7 8 9 10 Pulse Rep. Rate M/p tch Yo } In Damping goff Bkr CB j % [ In. Filter M/A Bkr P [ % p/- In. Calibration Confirmation , Remarks Hb Fffs Time /[*:r2/ Hrs Hrp/ Hrs f / Back Ref t. f/a% g/4 In.

                                                                                                                                                                                /                   %l     /!  ! n.      %     ['in.                 %         [ in. [          16          In.

4/8 Node [o % ,42 fin. % [ fn. 96[ In. %,[ In.[ % In.

                                                           /0 /8 Node                                                                                                          /0 % . g/ fin.       %[         In.       */             In.         [                jd.        'o          (n.

In. /%

                                                       /e//8 Node                                                                                                         Jo % /,yzfin.             %j         In.      [o                   '

[In. ' 4 in. Top Notch 4 [46 d[A ln. - 9)I In. [% 17 % h 6 in. Opposite Notch h (In. [o n. [% / n. i % [ In. "6 In. Reviewed By: __an< _ Notch h% h In. [% h.j % [ In. f In. ' 6 In. Leve' d _ Date# [M Initials g [ f [ [ , BW CB (Back R=.. coon From Cat. Block) Bkr P (Back Reflect on from Part) AOOOO927

I . .s ,

                                  & : 'R      Inter-Offico Momerandum                     i I

Date May 25, 1982 g g[ RT Examination of CRDM

            #APSR-68 Grid Location subject                                       6111-82-2083 4

D-10, Mfg. Ser. #R72-003 Weld Location g TMINS Trailers #256/258 I N. C. Kazanas Director-Quality Assurance The above referenced CRDM has been radiographic examined per RT Procedure #XR-1-NP (N.E.S.) and results evaluated per ANSI N31.7. Per the attached radiographic report, the two (2) exposures were found acceptable with no apparent defects. I : JET /ej g i

D f GP P # k3171/82 Q b d o . Inspection Supervisor

2) Radiographic Report, dated 5/21/82 !

cc: R. F. Fenti i B. E. Ballard, Sr. t CARIRS QC file l i I II I B I , I I I -, I

page 1 of J3 QUALITY ASSU M NCE MODIFICATIONS /0PERATXONS QUALITY CONTROL PLANT INSPECTION REPORT Unit No._ . S Inspector .Ded2/) Scfs~c~1/ PIR No.tJf f3/7///2- l Inspection Description Ypt/,,,.! 79r ,/c'# /E ('f D h /?/e7Es- Nbe 7?; re, -,p- e *E~ ZS.I' __//. T Evem M r7~oa Method: Visual: X Direct Measurement: ' Document Review: Other: A'

References:

A'. T Title Rev. Date if4ed 1 ,YA-/- NP _) 4 - J o s c) Vg&de

                                                                                                     %L 7 4 I    Vendor / Item         Item / Characteristic /        Accept /

Inspection Cc slience I Activity To Be Reject Results/ Sat Unsat Not I (dentification as appropriate) Inspected Criter ia Readings Applic. R 79 co3 l},77 !Je/d At/2 83t.7 dec -r/o a; neur Coy ~ I fRnhr A?se- 6,9 6PS 7s 8./.h'sl De l. ett I i I i I . I l E '- , I I I l 1 I , I

~
/

l - f 1 I

l I . i I I

MD-108-1 (Rev. 0) TMi 201 6-80 f

Page 2_ of .3 OUALITY CONTROL PI. ANT INS?ECTION REPORT ?IR Noi? '?/J//fL ' Ia Vendor / Item Identification (as appropriate) Ice =/ Characteristic / Activity To Ee Inspected Accept / Reject Inspection Results/ 1 3at Unsa: Not Criteria Readings Acclic. I i i i l l i I l 1 I i I I l l I I l I l 1 i i 1 I I i l i I I I i l i i 1 6 I I I I I I I i i Measuring and Test Ecuitment Used Identification of Equipment Serial Calibration No. Date Due A / /J l l I / if o I l I I I MNCR Issued: Yes l l No l [l QDR Issued: Yes l l No l 4' l MSCR QDR No. Date Reason for Issue Hold /Condit. I Release Tag Nos. I l 1 A

/, l J- J I

Issued t j'/ I'. l l 1 I I Cc:::ents/Other Information: . . - . I Inspected Ey: ) _ ,/ o , m /] f Date: f L VP' Reviewed and Approved By: .L /y; Date: 6- 2.S~- M

                                                                        /             /
                                                                      /             /

Distribution ( '>/) Manager Admin. and Services Unit S (Orig.) I ( ( (X)

                                 )
                                 )

QA Mod / Ops Manager QC Manager File 'g Others: (<) / t, MNd 5 3 ( ) MO-108-2 (Rev. 0) ( ) e s

                                                                                                                              ...,"t               Q ,f:.'.".af C.lT                                                                         -

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                                                                                                                             ?~                    %Q                                                       ; G[?} 2             JC~ .:-

L- E : lC T.YD{.*O - , I Ur.rCLEAR Sn~0i~.GY GERVICES SHELTER ROCK ROAD D ANSU AY. CONNECTICUT 06810 t %-- T I (p l v%C-~ 9 .'

                                                                                                                                                                                                                                              ,, - / ,

glGURE 4

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I Fm/m Awyra RADIOGRAPHY REPORT V.eiu Film R ADIOGR APHY REP _OQT NO. I SERIALNO OR PIECE PO dO- 40-ACC R E J. C "' REMARKS DATE IN-#^ ( f. D j% Y ($ Customer Y$ 8*O /r!S1 ') S r' **#

                .<'d .Y                                                                                                                                                            Address I / f h*((                    /* $  V                                                                                lb0 k ?%r /// bS $/Ch Jeb location I                                                                                                                                                                                 Customer's P.O. No.

Item Description 100*6 Insp.

                                                                                                                                                                                                                                         / b/I Spot insp.

Job No.

                                                                                                                                                                                                                                                       'M
                                                                                                                                                                                                                /M8 I

Welder Stamp WORK

SUMMARY

Amount item Description I Tctal Hours 1 Travel Hours N A.M. O P.M. T Lunch U AM@_ P M . @ _,,_ _ _ Standby _ in. th k. @_ I F t . Plate Weld Ea. Pipe Weld in. dia. @.,,,,,,.

                             !                                                                                                                                                            h        Films, I      .x    /) Type              (    j'T       @_

Films. x Type '@_._ S Exposures @ _. tJ /P -VM I Inspection Specification Acceptance Standard TECHNtOUE DATA

                                                                                                                                                                                                                     /2! I/             .W/7 I                    -

RT Procedure No. Shooting Sketch (RSSSI Pnysical Source Sue / M M - / ' /1/ YI V Ef fective Focal Sr at // b Y. (h ? sin rin/ &r'd (*S 'l l:lflk Yr' Y~" l l Y r'f . .$ ? l!5 .5'?>rs ;+/? Y$~/. SF D !N Maternal Theckness Geoma ric Unsharpness (Ug) Source to Obrect .

7 IO

                                                                                                                                                                                                                             ./   Md V Type Mawr al      b*$/ A Y} /*) D) lYV O $L/rC: fa)('s

C / P N.*./ No og y,lm per Cassette A Penetrameter N Shim )

uhe %$ ,bh *.N N N/$!S ($/8rk E " b e" 0 $ hJl f!!h ! 2^s2 h E / O! [ $) y ,e w ,n q Single pu Screens Fran, /C /0 " Superimposed Back / [IO "

                         .-                                                                                                                                                                                                   Center I'l h /e f     ,/          TI e                                                             [//T/C rd W/                                                     Masking or Blocking Used
                               , .D  '[                               (-N                                                                                                          E =posure Time _ S . M M/                          Dev. T.me -'    /?? b o                            /')                                            e                                                         Type Source           [r* /[ #.                  Curias     43 k.*./c ?-                              /q h 4%                                                        [d f/* (f A                                                         DEF ECT CODE I

f/ r P - Poros ty SI - S!ag inclusions T1 Tungsten inclus. C - Crack BT - Burn Through CV Root Concavity IF - Incomplete Fusion DT - Drop Through CX Root Conve uity SL - S>ao Lines UC - Undercut Ox O= dat.on

1. ^6/I L O LEVEL I 2 T E CHNICI AN TcC NICI AN A LEVEL I' !. W

l ' " M EVEL~

I

3. ~

T ECHNICI AN INT c.PP% T EH

                           .               _________.._._________.m_.                                                          _ _ . _ _ _ _ _           _ _ ___                 m             .._u_m                                 m                     .am_.._m _  a. __

I I I I I I I I I TEST 8 I I

I '

I j I I I I I I '

TEST COMPLETION REVIEU 3HEET I Task #7 Inspection / Test: 8 Inspected Item: Fold-down Bolts of Plenum Lift Lug Type of Inspection: Ultrasonic Inspection and Test Plan: These bolts are made of A-193 B8 and have a nominal strees of 23 KSI. This material and pre-load is typical of the 1 stainless steel bolts used in the RV internals. { i YES NO 1 i

1. Is the work scope in agreement with the B&W Engineering Information Record? [

t 2. Was there an approved inspection / test procedure I used for this examination? [ I 3. Does the results of the examination agree with the acceptance criteria called out in the inspection / test procedure? l l

4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure?

(Accessible quantity inspected 6 Minimum re-1 I quired 4 .) i Note: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any repairs made to the item (s) being in-spected, or recommendations for repairs or re-placements? [

6. Does there exist any unresolved discrepancies that i have not been (reported) processed for future j resolution? V Note: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. 8/-//J2"//I-0 0

8. Task #7 Procedure I'c. J[/ /-[2- Cd/2.

I -

                                                                        # if Reviewer's  .-3 nature /        bCtah l

l

 ,g      -

a a &" l Inter Office Memorandum ate April 13, 1982 ISI/NDE M82016

. Subirct  Ultrasonic Examination of the Plenum Lifting Lug Bolts (Task #7 Test 8)

To N. C. Kazanas Location Parsippany iI i l An ultrasonic examination on the six (6' plenum lifting bolts was

                                                          ,                                  l performed on April 13, 1982 by two (2) B & W pe;aonnel and Material               )

'g , Technology representative, Mike Zeise. ' f l The examination was performed in accordance with Procedure B & W l j l l ISI 166, Rev. O, STP 1-82-0012. No recordable indications were detected, l Il all six (6) lifting bolts are acceptable and meet the criteria set forth jW in B & W Document 51-1132418-00. During this examination a visual I

!          inspection of the plenum cylinder cover bo] ting was performed which lg          revealed an inadequate surface for UT examination due to normal sludge 1

3 build-up on the bolting end surfaces. Maintenance personnel, at this time, cleaned the bolts involved. i Attached are the B & W Data Sheets which I have reviewed and with which I am in concurrence. This completed test 8 of Task #7. RodneyTyfner , NDE Specialist i Materials Technology I APPROVAL s j C. D. Cowfer f r' RT:ef l I cc: J. Potter G. Rhedrick M. Zeise ISI File Acocosas

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TEST COMPLETION REVIEN 9HEET Task #7 Inspection / Test: 9 Inspected Item: Top of Core Type of Inspection: Video Examination Inspection and Test Plan: This examination is intended to confirm the " normal" appearance and condition of the core componets prior to conducting other inspections. Emphasis is placed on confirming no failed or defective parts are present and no sulfur assisted corrosion is observed. I I YES NO

1. Is the work scope in agreement with the B&W Engineering Information Record? v/

[

2. Was there an approved inspection / test procedure used for this examination?

w/ I 3. Docs.the results of the examination agree with the acceptance criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure?

(Accessible quantity inspected /CS Minimum re-quired (O.) Note: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any repairs made to the item (s) being in-spected, or rec:nmendations for repairs or re-placements? , _

6. Dooa* there exist any unresolved discrepancies that have not been (reported) processed for future resolution?

Note: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. ((-ll3140[~O[

8. Task #7 Procedure No. 59 / - R- 008

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                                             .e qw                  Inter 'Effice Memorandum g

Date May 25, 1982 subject OTSG Task 7 Area #9 Muclear

                           " Top of Core Video" To                                .m
                           ", C.                                         Location Three Mile Island Director - Qua,il ty Assurance I                                    Ref:     (1) GPUN Memo NF-2620, J. D. McCarthy to N. C. Kazanas, April 16, 1982 A remote video inspection of the top of the TMI-l Cycle 5 core was completed I     on April 23, 1982.                   The scope of the actual inspection exceeded the minimum requirements of the program specified by the GPUN TMI Fuel Projects group

( Re f. 1 ) . All conditions observed were determined to be normal with no indication of IGSCC. GPUN Till Fuel Projects, TMI-l Nuclear Engineering, TMI-l QC Piping /NDE In-spection, and to a small extent B&W Fuels Engineering, were all involved in the Area #9 inspections. Individual reports for each GPU group have been written and are attached. As responsible Task Leader for this inspection I have reviewed these reports, and concur that all Task 7 Area 9 requirements have been met. The B&W involvement was limited to technical input to TMI Fuel Projects to assist in the program development, and a brief review of the inspection video tapes. In view of the fact that there has been some inconsistency in the material list for the fuel assembly components provided by B&W,a thorough review was I performed by Till Fuel Projects. should be used in the Task 7 material evaluation. The resultant material list is attached and [c El W W. S. Wilkerson Lead Nuclear Engineer, TMI-l Attachments WSW/sf cc: J. J. Colitz, Plant Engineering Director, TMI-l I W. L. Kimmick, NDE/ Piping Insp. Lead QA J. D. McCarthy, Engineer, TMI Fuels Project G. R. Bond, Nuclear Analysis & Fuels Director I J. R. Stair, Nuclear Engineer, TMI-l J. D. Luoma, Manager TMI Fuels Projects I _a g

May 18,1982 OTSG Task 7 Inspection Area #9

Title:

Top of Core Type of Inspection: Remote Video Equipment Used: Diamond ST-5 Procedure: STP l-82-0023 Report Prep: W. S. Wilkerson I This inspection was performed on April 22 and April 23, 1982 and was done in accordance with the inspection plan outlined by the GPU Nuclear Fuels Memo I NF-2620 (Summary attached) . the actual exam: The following people were directly involved in I J. D. McCarthy - GPU Nuclear Fuels C. C. Mehta - GPU Nuclear Fuels R. M. Rama - GPU Nuclear Fuels E. D. Shoua - GPU Nuclear Fuels I J. R. Stair - Nuclear Engineer, TMI-l W. S. Wilkerson - Lead Nuclear Engineer, TMI-l I The video tapes were reviewed by W. L. Kimmick, Lead QC Piping /NDE Inspection, after completion of the examination. A summary of this review was provided. Using the Table nomenclature from NF-2620 the results are listed below. Item A.1 " General Conditions / loose parts" A complete video scan of the entire top of the core was done. There was no obious deterioration of any type noted and in general the conditions were found to be excellent. No loose parts were identi-fied although there were loose flakes of material typical of those broken loose by the head removal evolution and CRDM uncoupling which were generally small (less than 1/16 inch in diameter). Item A.3 " Fuel Assembly Holddown Springs" A video exam was made of all 177 fuel assembly holddown springs with-I out lifting any control components. On the 106 assemblies without control components 85 to 100% of the spring was viewed. The remaining 71 springs received less coverage with approximately 15 to 25% of each I spring being accessible for the exam. A 100% inspection does not in-dicate that 100% of +he entire spring surface was examined. A crack in I

i l Top of Core Page 2 of 2 I this highly stressed magerial would propagate thru the spring material and be present as a 360 indication. Therefore, an inspection of the I entire inner diameter or outer diameter would reveal this condition. A 100% inspection indicates that the entire inner or outer diameter, or an equivalent combination of bcth was examined. In all cases there was no excessive relocation or cracking observed. Item A.4.a "Holddown Spring Retaining Spider" I As in Item A.3 above the coverage varied due to the presence of control components with almost 100% coverage on the 106 without i l I CCA's to 15 to 255 on those with CCA's. No visible cracks, relocation, or tilt was seen in any case. l l Item A.4.b " Guide Tube Nuts" ) During the holddown spring inspection, approximately 12-16 guide tube nuts were visible in the assemblies without CCA's The number of nuts examined well exceeded that required by the program outline. ' Again there were no unusual conditions (cracks, crud, missing quts) identi fied. Item A.4.c "Latchup Weld" Although a specific exam of this weld was not performed a large number I (106) of latchups were seen during the holddown spring inspection

v. % no sign of cracks or other irregularities.

I I I I

                                                             "                                            XCLE FRtM'-2E          M (11-    I; '

ps s 7 y, ACCEL'TA!1CE CRITERIA JtISTIFICATIO!![ REMARKS INSPECTI0t1 IlUMIIER / I.0 CATI 0tl ITElf Top of Core whole top of core - !!o obvioun - Early indication of

1. Cencral condition / - video scan deterioration; degradation loose parts - No loose parts. - Assure no loose part s

                                                                                                         - Documentation             ,

2. Intentionally Left Blank All 177 springs tio visible cracks or - liighest vulnerable Fue'l assembly holddown - video closeup 3.

(without lifting excessive relocation material: Inconel X-750 springs CCAs) (Itef. IEW recommen- - Former NRC concern over dations) spring breaks at other plants.

                                                                                                         - Number of springs in-
                                                                 -/                                         spected in detail to be determined by inspecting engineers.

I .

EXCERPT FRott NF-2620 OTSG TASK 7 AREA # 9 " TOP OF CORE'" ACCEPTANCE CRITERIA JUSTIFICATION /RDIARKS INSPECTION llUMBER / LOCATIO!! ITDI

4. F.A. Upper End Fittings

                                     - video closeup     Fresh F.A. in C-4    - No visibic cracks  - Stressed CF-3t! material a) lloiddown spring                                                                      - Indication of. spring retalning spider                         natch 5 F.A. in        at load arms C-3                  - No relocation or      integrity.

tilt (NOTE: Inspections b and c are not first priority. They should be per-formed if visibility allown.)

                                     - video closeup     Same two F.A.s in    - nuts in place      - weld between SS304 and b) Guide tube nuts                                                  - No visible cracks     CF-3tl.

(and welds) (a) above. 2 to 4 nuts In each F.A. In welds Same two F.A.s in - No visible cracks - Fillet veld . c) Latchcup weld - video closeup (a) above. Visible or irregularities portion of circum- - Latchcup subject to CRA ference impact. Locates CRs in core. G 8

I Attachment W. S. Wilkerson to ,I N. C. Kazanas May 25, 1982 Area #9 Top of Core Inspection Material List l

Item Description ' Material Condition ** Stress A.1 Upper End Fitting 316L S.S. Casting As ordered / Low

                                       & Plate              welded A.3         Holddown Spring        Inconel X-750       drawn wire    High A.4a        Holddown Spring       316L S.S.            As ordered    Moderate Retaining Spider       CF3M Casting iI i

A.4b Guide Tube Nuts 304 S.S. As ordered / Low welded A.4c Latcheup 304 S.S. As ordered / Low 2 m Cas ting welded - I !i i

Item number as outlined by GPUN memo NF-2620, 4/16/82 4

      ** Stress in the cold condition I

I I I I i

I inter-Office Memorandum NF-2635 File: 701.2/4003.2 Date May 3, 1982 Q +f' Subject Task 7: Item 9, Top of the Core Inspection To N Location Headquarters (1) IOM NF-2620, J.D. McCarthy to N.C. Kazanas, "TMI-l Task 7 Fuel Inspection IRefs.: Plan", April 16, 1982. (2) B&W EIR 51-1132401-01, "TMI-1 Top of Core Video Examination", April 16, 1982. E (3) IOM NF-2628, E.D. Shoua to N.C. Kazanas, " Task 7: Subtask 11, RNS Retainer Inspection", April 27, 1982. (4) Task 7 Procedure No. STP 1-82-0023. On April 22nd and 23rd TMI Fuel Projects and Plant Engineering personnel inspected the top of the TMI-l core in accordance with the Task 7 require-ments specified in References 1, 2, and 4. The inspections consisted of video scans and closeups of representative top of the core components. No anomalous I materials or mechanical conditions were observed for the upper fuel and control components examined. The examinations also served to verify that no loose parts or general materials deterioration were present. Camera and lighting equipment were suspended from the auxiliary fuel handling bridge and maneuvered manually. The video image was monitored both on the bridge by the equipment handlers and remotely by the inspecting engineers with 1 voice-over comments from the latter. All inspections were video-taped for documentation and any necessary further evaluations. Every core location was examined at least to a detail consistent with the inspection requirements. I Actually, due to the excellent picture clarity and visibility of most components, many more specific closeup exams were obtained than originally required. In addition to observing for general conditions, inspections included F.A. hold-down springs, spring retaining spiders (and load arms), guide tube nuts (and welds), and latchcups. At control element (CCA) locations the CCA spiders, rod nuts and rod nut welds were examined. Viewing conditions allowed clear closeup inspection of all visibly accessible components. Special attention was paid to the Inconel X-750 F.A. holddown springs in the 106 core locations without a CCA inserted. These included three springs from the B&W heat 64G5XS that recently had several breaks at other plants. Also, partial views of spring coils beneath almost every CCA were obtained. No corrosion, cracking, coil relocation, or excessive crud were seen for any spring. A further indication of the integrity of all holddown springs was I that no spring retainers exhibited tilt. I The CF-3M spring retaining spiders also showed no excessive crud buildup, corrosion, or indications of cracking at the load arms. All of the SS304 guide tube nuts inspected were in place with no visible degradation to their welds. The circumferential latchcup welds were not visible at the camera angle used I (angle was chosen for best holddown spring views); however, the tops of all latchcups in the 106 non-CCA locations were in good condition and show no relo-cations. No significant debris was evident on the upper end fitting grill plates. A0000648

I I N. C. Kazanas 1 i Overall conditions were typical for all components; i.e., the older F.A.s and CCAs with more exposure were darkened with varying amounts of crud buildup, while fresh components were brighter and clean. Inspection of the RNS/ ORA mechanical retainer was reported earlier in Reference 3. I Therefore, based on these inspection results, the top of the core fuel and control components examined showed no indications of anomalous materials or mechanical conditions. Test Completion Review Sheet is attached. I g/ h.D.McCarthy l JI Fuel Project's JDMc:rmc Attach. cc: G.R. Bond I J.J. Colitz (TMI) R.W-. Keaten J.D. Luoma I C.B. Mehta R.M. Rama G.E. Rhedrick (w/ attach.) E.D. Shoua D.G. Slear J.R. Stair (TMI) W.S. Wilkerson (TMI) I I I I I

I I i % inter-Office Memorandum Data "7 ' Remote Visual Examination Q %[ g s W :ct (Task 7, Inspection (9) Top of 6111-82-2073 3 Fuel and Core Components. Location TMINS Trailers #256/258 To W. S. Wilkerson Lead Nuclear Engineer-Unit I Ref: GPU Nuclear Fuels Memo #NF-2620 Reviewed five (5) reels of reel to reel video tape of the top i portion of the fuel and core components. The review was in accordance with Inspection #9, Task 7. The review took place after the actual inspection had been performed. The area appeared to be in good shape and the film sensitivity was such I that the identification number of each assembly was easily dis-cernible. There was white shiny particles app 3 rent throughout the entire area. These particles were most of the assemblies. Inspection #9 outlined the areas of interest and the following was noted:

1) A.l. of inspection outline: No metal degredation and no loose parts were noted.

I 2) A.3. of inspection outline: Springs don't appear to have any excessive relocation and none appear to be cracked. I Note: A.P.S.R. and C.R. 25% of spring visible, on all others 707. to 80% of spring is visible.

3) A.4.a. of inspection outline: Retainer Load Arms not broken I (four (4) places). Note: A.P.S.R. and C.R. only two (2)

Load Arms were visible. I 4) A.4.a. of inspection outline: All hold-down Spring Retaining Spiders were in place and not askew.

5) A.4.b. of inspection outline: Guide tube nuts were in place.

a) A.P.S.R. and C.R.; only four (4) to six (6) nuts out of sixteen (16) were visible. I b) All other assemblies; eight (8) to twelve (12) nuts out of l sixteen (16) were visible. l The above items are the only items on the inspection list which I were visually accessible and discernible. It should be noted j that nine (9) of the fuel assemblies are not covered on the video j i tapes. 1

1 I I 9

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I I - I TEST 1 l FUEL INSPECTION l 'I I I I II lI i 'E I

Inter-Office Memorandum NF-2646 I T'" File: 701.2/4003.2 Date May 10, 1982 I Subject Task 7, Fuel and Control Assembly ' 7 e Nuclear Inspection Results: Items 10A,10B,10D I To .N Location Headquarters Refs.: 1. IOM NF-2620, J.D. McCarthy to N.C. Kazanas, "TMI-l Task 7 Fuel I Inspection Plan", April 16, 1982. 2. I 3. B&W EIR 51-1132404-01, "TMI-1 Recovery: Fuel Assembly Inspection", April 16, 1982. B&W EIR 51-1132412-01, "TMI-l Recovery: Control Component Inspection", April 16, 1982 5 4. Task 7 Procedure No. TCN 1-82-0051.

5. Task 7 Procedure No. STP l-82-0027.

I As part of Task 7 of the OTSG Recovery Program, inspections were completed on BlI-l fuel assemblies and control component assemblies in accordance with the requirements specified in References 1 to 5. The inspections-were performed by TMI Fuel Projects and Plant Engineering personnel; B&W I fuels engineers also participated. Inspections consisted of video scans and close-ups of two fresh fuel assemblies pulled from the core, four irradiated FAs and one fresh FA in the core, two control components (one I CRA and one APSRA) , and a portion of the core baffle. Several faces of the pulled fresh FAs were also inspected by direct visual exar.luation. Special attention was paid to materials potentially vulnerable to sulfur-induced corrosion, to potential weld-sensitized areas, and to areas of higher stress. Results showed no anomalous materials conditions on any I of the fuel or control components examined. I Results of the baffle inspection will be reported independently by Plant QA (W. Kimmick). Item 10A - Unirradiated Fuel i Fresh fuel assemblies NJ0132 and NJ01BM were pulled from core locations h C-4 and H-15, respectively, using the main fuel handling bridge and moved fg over the deep end of the fuel canal. A Diamond ST-5 video camera with 3 zoom lens on pan and tilt was situated on the canal floor about 3 feet from the assembly. Appropriate stationary lighting was provided. Viewing was in air and the video system provided extremely clear black and white I remote monitor pictures. Left-right field ranged from the full width of the FA face at about 1X to a 4-5X magnification of any detailed area on the face. Video tapes were recorded on Betamax cassettes with voice-I annotation by the inspecting engineer. Video inspection included the N, S, E and W faces of FA 132 and the N and S faces of FA 1 BM. In addition, the B&W fuels engineers performed direct visual examinations of the S face of 132 and the N, W and E faces of 1 BM. I A COOC 64

N. C. Kazanas I Page 2 May 10, 1982 I Inspections consisted of a full vertical scan of each FA face as the assembly was raised or lowered past the camera (or the direct-visual I inspector). Specific examinations included: the holddown spring retaining spider plugs, the horizontal structural welds connecting the end fitting grill and plenum, the welds connecting the end fitting grill to the skirted end spacer grids, the outer ribs cf all spacer grids, and I the outer fuel rods. Due to the excellent picture clarity and smoothness of operations, many more detailed examinationslwer'e performed than specified in the requirements. Each FA has two holddown spring retaining spider plugs (304SS) at 180 welded between two upper end fitting locating fingers (CF3M-SS) to I contain the spider. Although it was necessary to view the plugs through cutouts in the FA grappling tool lifting arms, all four plugs were clearly visible, in place, and the tack welds to the fingers were in good condition. The retaining spider load arms beneath the plug were properly oriented (no tilt) and flush against the plug. ' The outer surfaces of the CF3M-SS upper and lower end fittings were smooth and clean in all cases. All of the horizontal structural welds joining the CF3M grill and the CF3M plenum to form the upper and lower end fitting assemblies were I inspected on both FAs. For the six FA faces examined using the video zoom this included individual inspections of the 48 welds at about 3-4X. No indications of any cracking or veld deterioration were observed. Nor were any anomalies seen on the remaining 16 welds inspected by direct-visual. Axially adjacent to each plenum-to-grill weld there is a large (5/8-inch diameter) button weld joining the end fitting grill to the Inconel-718 skirted end spacer grids. These welds were also examined at 3-4X and I all showed no indications of defects or corrosive attack. I The outer ribs of all Inconel-718 spacer grids on both FAs were closely inspected. Welds and other detail areas (e.g., hard-stop indentations) were viewed at 3-5X on the 6 videoed faces. All spot welds'on the end I spacer grid skirt weldments were in good condition. Rib surfaces were smooth and clean. Occasional darker patches or light scratches showing on the video image of the ribs were interpreted as post-welding grind marks or rub marks due to fuel handling. No corrosive damage was detected. This was verified by the direct-visual inspections. Special attention was given to the stamped hard-stop depression areas on I the ribs and to the rib intersection welds. No cracks or evidence of corrosive damage were seen. Although viewing conditions did not permit a fully-lighted image within the peripheral fuel rod cells, the adjacent rib springs were seen to be in place and against the rods. Corners of I the grids were examined, and in several cases turned directly into the camera, with no signs of deterioration. I I

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I I N. C. Kazanas Page 3 May 10, 1982 I According to the B&W inspectors who performed the direct-visuals, I several grid strap surfaces exhibited a light yellow discoloration. A wipe sample was taken across one such rib and the colored material was easily removed. No corrosion or other anomalous material conditions were I associated with the discoloration. The wipe sample will be chemically analyzed at B&W LRC. The full view of each intermediate spacer grid showed that all were properly oriented relative to the fuel rods. The Zircaloy-4 fuel rods were scanned vertically in each span between I grids. Views were full-width of an FA at about 1X and, in several instances, 3 or 4 adjacent rods at 4-5X. All rods were free of adhering crud and in excellent condition. I At several spacer locations the rods exhibited small elliptical swirl marks of a whitish-gray color immediately below (and sometimes also above) the grid. The pattern of the marks seemed to be symmetrical about the I middle fuel rod in the outer row. A wipe sample was taken across the rods at one location and sent to B&W LRC for chemical analysis. No indications of corrosion were associated with these markings. During the inspections several irregularly-shaped bright marks were seen on the rods or grid straps. These were determined by direct-visual exam-ination to be debris from the deep end water and did not adhere to the FA components. As part of the in-core inspections described below under Item 10B, an additional face of a fresh fuel assembly was inspected (FA NJ01BL, I Location B-4, West face). Although camera and lighting equipment were different, good pictures were obtained. Results were the same as for the removed fresh assemblies, i.e., a uniformly clean assembly with no indi-cations of any corrosion or other material degradation. Several 35mm color slides were taken of FA 132 during the inspections. I The pictures verify the good condition of all components on the assembly. A close-up shot of one spacer grid area shows both the swirl marks on tha fuel rods and a light yellowish-orange discoloration on portions of the outer strap. Again, no materials degradation is associated with these markings. Inspections of the bottom of the lower end fittings were not performed I (Items 8 and 9 of Reference 1). These exams were optional in the inspection plan and were omitted because camera angles did not permit viewing. Direct visual examination would have created an unjustified risk. The GPUN and B&W inspecting engineers agreed that the good condition of the other FA I components made it unlikely that the LEF deposits, or that the guide tube nuts or contained any excessive crud guide bars were damaged. I I

I N. C. Kazanas Page 4 May 10, 1982 I Item 10B - Irradiated Fuel Irradiated fuel ass emblies were ins,ected in place in the core. The following were examined: Fuel Core Insertion Face _Ajsembly Location Batch Inspected NJO OMG H-14 6 S NJO 13A C-5 6 N NJO OLT C-3 5 S NJO OB1 D-4 4B E A Westinghouse-1250 video camera with a right-angle lens was suspended from the auxiliary fuel handling bridge into the empty core locations (C-4, H-15) created by removal of the two fresh assemblies. A supplementary I light source was also provided. Both camera and light vare manually maneuvered from the bridge. Viewing was in water and the ideo system provided clear black and white remote monitor pictures. Left-to-right I field ranged frca about ene-third the width of an assembly (4-5 rods) at about 1-2X to a magaification of 6-8X of any detailed area on the FA face. Bet. wax cassette video tapes were taken for all inspections with voice-over by the inspecting engineer. In addition to the irradiated assemblies, the West face of fresh FA NJ01BL was also examined by the above method. Results are described above under Item 10A. ! Inspections consisted of a full vertical scan of each FA face by raising l g or louering the camera. Specific examinations included: holddown spring i g retaining spider plugs, structural welds between the end fitting grill I and plenum, welds between the end fittings and spacer grid skirts, outer grid straps, and outer fuel rods. Special attention was given to end l l fitting and spacer grid components and welds which were examined completely [W on each FA face. Coverage of fuel rods was detailed but representative, t with full horizontal scans across all rods at elevations with distinctive crud patterns. Because of assembly orientations the holddown spring retaining spider I plug (304SS) was visible only on the Batch 4B FA. The plug was in place and the tack welds to the UEF locating fingers (CF3M) showed no degradation. The plug and welds exhibited a typical amount of crud deposition for an assembly with three cycles of exposure. The retalaing spider load arms in the 4B,and all tnree other irradiated FAs, were properly oriented. 1 I I

I - N. C. Kazanas Page 5 May 10, 1982 I The outer surfaces of the CF3M end fittings on each FA were all in good condition with crud deposits typical for their respective exposures. (The Batch 6 assemblies were particularly clean after one cycle.) Each structural weld joining the end fitting CF3M grill and plenum was I inspected on each FA face (total of 32 welds). Magnification was about 5X. No cracks or weld degradation were observed. Each adjacent button weld joining the CF3M grill to the Inconel-718 end spacer grids was similarly inspected (total of 32 welds) . No deterioration was seen on any weld. The outer ribs of all Inconel-718 spacer grids on the face of each irradiated FA were closely examined. The spacers showed varying amounts I of crud deposits typical for their dif ferent operating times. Welds and other detail areas were viewed at 6-7X across each grid strap. Spot welds on the end spacer skirt weldments appeared in good condition. Various minor markings and shadings were identified as due to fabrication grinding, I fuel handling, or irregular crud patterns. No indications of corrosive material damage was observed. I Special attention was paid to all rib intersection welds and the hard-stop depression locations. No cracks or other material deterioration were seen. Lighting conditions afforded many good views into the outer fuel rod cells. Adjacent rib springs were in place and against the rods. Visible portions I of the grid corners were also intact. Although a full view of a grid could not be obtained, the partial views I indicated that all were properly oriented relative to the fuel rods. The top few spacers on the older Batch 4B FA showed some axial misalignments (h." to I") s relative to grids on adjacent lower burnup assemblies. This is expected due to irradiation-induced assembly growth. Minor grid damage, unrelated to Task 7 concerns, was observed on the upper end spacer of the Batch 5 assembly. The bottom edge of the outer rib is I bent upward (or torn of f) to a height of about one quarter inch across two adjacent fuel rod cells near the SE corner of the grid. However, all the rib intersection welds appeared intact and the grid structu' rally g sound. Also, there was no difficulty removing the adjacent fresh assembly E from location C-4. The B&W fuel engineers concurred that such damage was of minor concern. The Zircaloy-4 fuel rods were vertically scanned in each inter-grid span. Views were of 4 or 5 rods at 1-2X. At elevations of particular interest (e.g. , distinctive crud patterns) full horizontal pans were made across I the assembly at 6-7X. The two Batch 6 assemblies appeared very clean with a uniform lustre. The Batch 5 FA had some moderately heavy crud patterns at the upper spans, becoming uniform at mid-assembly to the bottom. The Batch 4B FA exhibited heavier crud deposits in the top spans with a very mottled light and dark pattern. This also became more unifrom toward the I I

I N. C. Kazanas Page 6 May 10, 1982 I bottom of the assembly. None of these crud patterns were considared I atypical or excessive for the relative burnups of the FAs; this was concurred with by the B&W LRC engineer. No indications of defects or chemical degradation were observed. Item 10D - Control Components Two control component assemblies (CCA) were selected for inspection: Control Rod Assembly (CRA) #C10 from core location E-3; and Axial Power Shaping Rod Assembly (APSRA) #A03 from location F-4. The CCAs were partially lifted out of the fuel assemblies from the main fuel bridge I using the manual CCA handling tool suspended from the bridge hoist. Removal was limited to a height of about 2h feet based on minimization of both personnel exposure and mechanical damage risks. Viewing equipment was the same as for the irradiated fuel inspections (Item 10B above): Westinghouse 1250 video camera with right-angle lens and a separate supplementary light source. Both were suspended from the I bridge and maneuvered manually. Monitoring was also the same as described for irradiated fuel, with a magnification capability of 6-8X of detailed areas. Betamax video tapes with voice-over were recorded. Inspections consisted of scans and/or close-ups, as appropriate, of spider assemblies, rod nut welds, retainer pin welds, upper end plug to cladding welds, and CR cladding. As for the other fuel-related examinations, I good picture quality and relative ease of operations allowed more inspections to be performed than called for in the requirements. I Both CF-3M spider assemblies were in good condition with no excessive crud buildup or observable corrosion. This confirmed the results of the top of the core inspection which showed these and other CCA spiders to be free of materials damage. I Six to eight SS304 rod nuts and welds on each CCA were examined at about 7X with no missing nuts and no signs of weld cracks or other deterioration. I At least two retainer pin and the stop pin area welds were inspected on the SS304 female coupling hub of each CCA and were also in good condition. Again, these confirmed the top of the core results. t Special attention was paid to the circumferential welds joining the upper end plugs (SS 304/308) to the SS304 CR cladding. About 10 welds were examined on each CCA at about 6X. For the CRA, all of the welds were I in excellent condition: smooth with no indications of cracking or corrosion. For the APSRA, several of the welds had a rougher appearance indicating some circumferential ridging. One weld contained a grooved indication between the bottom of the fusion area and the cladding that warranted I further evaluation. This concern was alleviated by closer examination of the video tape using freeze-frames of the weld which indicated that no separation existed at the groove. The concern was fully resolved by .I lI

N. C. Kazanas Page 7 May 10, 1982 I I inspection of the same weld on several rods of an inventory APSRA. The as-fabricated welds, examined at about 2-3X, showed similar circumferential grooves in the fusion area, but no indications of separation or cracking. These evaluations provided sufficient evidence to judge the weld acceptable. I A more detailed report on this concern will be prepared by Plant QA (W. Kimmick). I The SS304 cladding was inspected at about 3-4X for a length of 15 to 20 inches below the end plug weid. Eight to ten rods were examined on each CCA. All had light, mostly uniform crud deposits judged to be typical for rods in their exposure range. This was concurred with by the B&W LRC engineer. No defects, irregularities, or corrosion were observed. Summary The purpose of Task 7 inspection Items 10A, 10B, and 10D was to assess the general appearance and overall structural integrity of the Cycle 5 fuel I assemblies and control components for abnormal crud deposits, anomalous surface textures, and indications of sulfur-induced corrosion. As described in the above sections, detailed examinations of representative I unirradiated and irradiated fuel assemblies and control assemblies has been completed. Particular interest was focused on potentially vulnerable materials, possibly sensitized weld areas, and areas of higher stress. I Results show that the core components examined exhibit no atypical conditions and no visually-observable materials or mechanical degradation. Test Completion Review Sheets for inspection Items 10A, 10B, and 10D are attached. he J.D.McCarth] I . E. D. Shoua Nuclear Analysis & Fuels Group = Att. I cc: G.R. Bond J.J. Colitz (TMI) R.W. Keaten R.M. Rama G.E. Rhedrick (w/att.) D.C. Slear W.L. Kimmick (TMI) J.R. Stair (TMI) J.D. Luoma W.S. Wilkerson (TMI) C.B. Mehta I

I f.' I m 14 m/ M- PJ Babcock & Wilcox ~ uu i.., po.., o.n.r. tion oiv.3 ion I a McDermott company May 10, 1982 3315 Old Forest Road P.O. Box 1260 irgwa 24 sos

                                                                          $"[$"/0;[3 GPU-82 122

<I Mr. D. G. Sl edr TMI-1 Project Engineering Manager I GPU ttuclear 100 Interpace Parxway Parsippany, NJ 07054 Suoject; GPUtl (TMI-1) Master Services Contract, Effective Date June 1, 1977 Reference Nos: B&W 582-7105, GPUN M77120 Task 182-Task 7 RCS Inspection

Reference:

Gregory E. Rhedrick to J. F. Pearson , " Validation of TMI-1 Fuel Assembly Inspection," dated April 29, 1982, QA/d2-005.

Attachment:

Trip Report J. E. Matneson to Distribution, dated May 3,19d2. Trip Report J. T. Mayer to Distribution, dated May 4,1982 Attention: M

Dear Mr. Slear:

The attached information was provided directly to Mr. Kazanas. It is being formally transmitted for record purposes. The attacned information provides results of inspections of fuel in tne TMI-1 core, both new fuel and irradiated fuel in the vicinity of tne new fuel . The inspection results for control components and axial power shaping rod assemblies are also reported. I The general conclusion from the visual inspections was that no significant degradation of these assemblies or components has occurred. The only anomaly noted was the presence of a lignt yellow suostance on and near the fuel assemoly I grids. The nature of this material is presently being investigated at the Lynchburg Research Center. Should you have any questions or comments regarding tnis information please contact me at 804-385-2611 in Lyncnburg. Very tr, yours, G. L. J. Stanek I /dmr Engineering Product Manager Attacnment 'g cc: R. L. Long J. J. Colitz M. J. Graham D. W. Uemers W H. D. Hukill R. A. Knief J. A. Mann R. J. Tool e U. S. Bhachu L. R. Allen F. R. Fai st R. E. Kosiba

I da0 COCK &tVdCOX Nuctorr Pccer GcncratiN Division DISTRIBUTION i s w .2o55 w .an c......, I Sayes, J. E. MATHESON, FUEL MECHANICAL ENGINEERING, 3433 g o,, FSA-82-30 TRIP REPORT - TMI-l FUEL INSPECTION, APRIL 26-30, 1982 MAY 3, 1982 l DISTRIBUTION K0 STEIN JB ANDREWS RV DEMARS MH FISH CG DIDE0N I DG CULBERSON l JT MAYER (LRC) RJ BAKER GL GARNER RS PIASCIK I The purpose of this trip was to inspect two new fuel assemblies and the top of two components at the TMI-l site. This inspection was intended to detennine whether the sulphur-contaminated primary coolant had any deleterious effects on fuel ass'emblies and components. The two assemblies to be inspected were NJ01BM and NJ0132. The control components were ASPRA S/N A02 and Control Component S/N C10. A thorough visual examination was conducted on the fuel using remote video - I equipment. The camera was set up on.the drained canal floor and was capable of panning the fuel assembly while it was raised and lowered into the water in the deep end. While inspecting assembly NJ01BM, an anomaly - I was observed on one of the fuel rods. The nature of this could not be determined from the video picture, so I went down on the canal floor for a visual examination. The problem was determined to be a wetted flake of a boron which had floated on to the fuel from the plenum which was stored g in the deep end. Wnile down there, I observed a light yellow deposit on the grids-which was I concentrated about the soft stops and above and below the grids on the fuel rods. Wipes of this substance were taken by J. T. Mayer (LRC) when the second fuel assembly was inspected. For that inspection, I remained on the canal floor during the entire procedure. A report form was filled-I out for each face of each fuel assembly which was visually inspected. These forms were submitted to Joe McCarthy (GPU). Copies are attached to this report. In general, no significant degradation of the fuel assemblies was noted. The CRA and APSRA were pulled up far enough to view the end plug / tube weld I area, using underwater video equipment suspended from the fuel handling bridge. During this inspection, an incomplete weld zone was noted on one of the rods. Further investigation proved this to be acceptable, since zones of this type occur in the welding process. No other anomalies were I noted. at TMI-1. This inspection completed the inspection of the RCS components

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e ' ILaCFt.m't38 Rosoorch and Dev slopment Division LYNCHBURG RESEARCH CENTER pabcock a cox LYNCHBURG, VIRGINIA i gTo DISTRIBUTION From J. T. MAYER, IRRADIATED MATER!a'.3 TE""0 LOGY, LRC m hust. File No. or Ref. TRIP REPORT, TMI SITE, APRIL 26-30, 1982 MAY 4, 1982

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Distribution I G. M. Bain

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D. L. Baty D. G. Culberson, NPGD H. H. Davis R. V. DeMars S. C. Inman J. E. Mathes'on, NPGD W. A. McInteer I P. C. Childress, NPGD G. S. Clevinger C. G. Dideon F. R. Faist, TMI Site L. J. Stanek, NPGD K. O. 'tein, S NPGD Summary John Matheson and I participated in the. visual examination of fuel and control components conducted by GPU as part of the TMI-l recovery effort. The examina-tion included two unirradiated fuel assemblies, one face each from four irradi-ated assemblies, and the upper portion of two control components .(see attached core map). I personally concentrated on the irradiated components, and saw nothing out of the ordinary (except for an anomoly on the APSRA, described in more detail below). At GPU's request, I draf ted a brief statement summarizing my observations (see attachment). I took two wipe samples from one of the un-

           ' irradiated fuel assemblies; John Matheson covered the visual examination of these.

Examination Procedure I . Two independent video systems were set up in the Unit 1 reactor building for viewing in-core and out-of-core. The new fuel assemblies were pulled from the core and examined while the bridge lowered and raised the assembly at the edge l of the deep end of the canal. An ST-5 camera with =com and pan / tilt had been ' l set up at the canal edge for this purpose, along with two fluorescent lights. l The monitoring and recording equipment were up at the walkway level near the l southwest corner of the canal. Co=munication to the bridge was done using head- ! phones. I While the new fuel assembly was being examined, a Westinghouse 1250 camera was lowered into the cavity (from the auxiliary bridge) for examination of the irradiated fuel. An additional set of monitoring equipment and headphones were-set up at the southwest corner for this exam. The two examinations were done concurrently. The CRA exam was done with the Westinghouse camera after with-drawing the component with a manual tool.

o D'istribution Mmy 4, 1982 I ' l Joe McCarthy (GPU General Offices) directed the examination of the new fuel I assemblies NJ0132 and IBM. The site people were reluctant at.first to allow anyone down on the canal floor during this exam, but were finally persuaded to I give permission. John Matheson was down for the last part of the visual on 132, and the entire visual on IBM. I was down for the first part of the 132 exam and took two wipe samples (batch #75) from the north (A) face. The first cover-ed the entire outer strap on grid 4, and the second was taken on the first iner I or so of all fuel rods just below grid 3. These wipes were taken to characterize a yellowish-looking coating on the assemblies. The coating appeared to be re-moved by the wiping, and the wipes were noticeably blackened. I ' Dave Shoua (also General Office) directed the irradiated fuel exam. The Westing-house camera was operated by either Scott Wilkerson (the site coordinator for the entire exam) or Jim Stair, one of Wilkerson's engineers. Bill Kimik, a site Q/C representative, was the responsible CPU man for the control rod exams, espe-cially the weld areas. In general, all exams were thorough and the image quality good; however, the advantages of close-proximity direct inspection of the unir-radiated fuel were ob.vious once this was allowed. Results The general appearance of the irradiated components is adequately described in the attached write-up. The one item not mentioned is the " anomaly" on one of the rods from APSRA A03. The lower edge of the end cap / cladding weld region had a thin dark circumferential line that had all the appearances of a crack. Subsequent discussions and review of the videotape were not sufficient to deter-~ mine just what the anomaly was. After examining several weld areas on some new

   , components being stored onsite, Kimik was , satisfied that the mark was merely discoloration, and the issue was dropped. Kimik indicated that several new welds actually looked worse than the one on A03.

I lkw I Attachments

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FUCL I.D.(0AX & 03X-Ostch 4; OLX,0.H & OUX-Catch 5; Datch 6-ttnderlinedt Il . Con t rol Rnd i .D. (CXX-CT.A; AXX-APSRA) or Re tainer 1.D.(LXXX) 13X, 14X, IDX & IC.V JJtch ?) Source I . D . ( r.NCX-S econda ry) - gg,g.'6-01 l NOTC: fa)0 Prefixes All F.A. l.D. Ilumbers. Poge *. of 2 l l . l ' \

ll RESULTS OF TMI-l FUEL EXAM The writer was present during a visual examination (using CCTV) of irradiated The following areas were observed: fuel in the TMI-l core on 4-27-82. I Fuel Assembly ID 3atch Face Examined South NJ00LT 5 I 031 13A 4 6 6 East North South OMG-I Inspections were generally done at close range; left-to-right field of view was 3 inches or less. Although full 100% coverage of each face was not accomplished, During the viewing, I rspresentative areas of all components were covered inNodetail.psreic spacer grid welds), stress areas on the grids, and fuel rod crud patterns. Fuel I cracks or corroded areas were seen at any of the weld or stress regio regions in the upper portion of higher-burned fuel, to unifor= lustrous areasAll of the patt covering entire spans between grids. Nothing could be seen that I observed on irradiated fuel from other B&W reactors. would be called atypical, and none of the examinations revealed any evidence of significant chemical degradation to materials. On 4-29-82, the writer also observed the CCTV visual exa=ination.of The cladding two crudpartially deposits withdrawn (% lb feet)' control components, A03 and C10. reflective and uniform for the most part, and typical of other CRAs I were light, from B&W plants.

ll

                                                        . .  .M, W John T. May          I
                                   .      B&W R&D Dis sion Lynchburg Research Center I        JTM/ dss I                                                                                             S e

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i lI 4 t 1 i, d 4 i i il i l TEST i .i j 10A I : 1 1 !I 4 1, d i i e !,II l i b l

I TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 10A Inspected Item: Un-irradiated Fuel Assembly Type of Inspection: Video Inspection and Test Plan: To assess the general appearance and overall structural integrity of the un-irradiated fuel assemblies in the core for idications of abnormal surface deposits (crud), abnormal surface texture, and sulfur-induced corrosion. A general check o! the zircaloy. Inconel 718. I Yes _No

1. Is the work scope in agreement with the B&W Engineering Information Record?

2. Was there an approved inspection / test procedure used for this examination?

3. Dogs the results of the examination agree with the acceptance criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum requirements called o in the procedure? (Acegssible I quantity inspected f NOTE:

                                   ,p d F. A . & &

Minimum required d h r.)

                                                        **eA. fd]'=

If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any repairs made to the item (s) being inspected, or recommen-dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not v been (reported) processed for future resolution?

NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. h - /O Y0 h - O (

8. Task #7 Procedure No. Ibd/ / ~ h2- 00[/

Reviewer's Signature mv .

                                                           }v                  s I GD c fa- A

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p,{ acurr,U g @ )(sR%d h a e.a. am) P, L in -cove S VEL w Ey =

I OTSG Task 7 Inspection Area #10A Ti tle : Un-irradiated Fuel Assemblies I Type of Inspection: Equipment Used: Remoge Video / Local Visual Diamond ST-5 with Zoom on Pan & Tilt Procedure: RP 1507-12, TCN 1-82-0051 Final Report Prep: G. R. Bond /J. D. McCarthy These inspections were performed on April 20, 1982 and were done in accordance with the inspection plan outlined by the GPU Nuclear Fuels Memo NF-2620. The following people were involved in the actual exam: T. Mayer - B&W R&D Division E. Matheson - B&W Fuel Engineering J. D. McCarthy - GPU Nuclear Fuels W. S. Wilkerson - Lead Nuclear Engineer, TMI-l Using the Table nomenclature from NF-2620 the results are listed below. Item C.1 "F. A. Wipe Samples" Two wipe samples were taken on F.A. #NJ OlBM removed from core location "H-15". Item C.2 "Holddown Spring Retainer Plug" The two plugs in each assembly examined, NJ 0132 and NJ01BM, were I viewed. All four plugs were found in place with no sign of cracking or degradation. Item C.3 " Upper End Fitting Plenum to Grill Weld" I All faces on both assemblies were viewed either thru remote monitoring equipment or a local visual examination. No degradation or cracking was observed. Item C.4 " Upper End Spacer Grid to UEF Grill Weld" The same exam and results as noted for Item C.3 above. Item C.5 "Overall F. A. Grids and Rods" All faces on both assemblies were viewed by remote monitoring or local visual. All rods and grids appeared normal for a new assembly. Local visual exam revealed that debris noted during video exam was being picked up off the water surface in the deep end and were not representa-tive of the core conditions. The yellow deposits noted by the B&W representatives on NJ0132 were not seen by the GPU individual nor are they apparent on the color slides taken at the time. I

64 4 lll i, l t i Un-irradiated Fuel Assemblies Page 2 of 2 } 1 l11 ) Item C.6 " Lower End Spacer Grid to LEF Grill Weld" i Inspection performed with same results as noted in Item C.3 above. Item C.7 " Lower End Fitting Plenum to Grill Weld" jll j Inspection performed with same results as noted in Item C.3 above.

l Items C.8 and C.9 "LEF Grill and LEF Nuts" l Inspections not performed.

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i l I i i l TEST 10B ' i a n J i i i { i l 4 4 4 l 4 0

o I TEST COMPLETION REVIEW SEEET Task #7 Inspection / Test: 10B Inspected Item: Irradiated Fuel Assembly Type of Inspection: Video I Inspection and Test Plan: To assess the general appearance and overall structural integrity of the irradiated fuel assemblies in the core for indications of abnormal surface deposits (crud), abnormal surface texture, and sulfur-induced corrosion. A general check of the zircaloy. Inconel 718. Yes .No i

1. Is the work scope in agreement with the B&W Engineering t/

Information Record?

2. Was there an approved inspection / test procedere used for this examination?

I 3. Does the results of the examination agree with the acceptance n/ criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum requirements called out in the procedure? (Accessible quantity inspected ! Eico Minimum required ,f Eteo.)

I NOTE: F 3,fM b t ddfk If any of the answers to (1), (2), (3), or (4F are no, a written explanation must be attached. I S. Based upon the results of this examination, were there any repairs made to the item (s) being inspected, or recommen-l! i dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not been (reported) processed for future resolution?

NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. N ~ (( t b4 - 0[

l 8. Task #7 Procedure No. l\! d / ' N - d b [/

                                                             %?          [

! sh c0 et Reviewer's Signature C W'[ 6 [ M 'O , ole e ut of l lBL

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I TSG Task 7 Inspection Area #10B

Title:

Irradiated Fuel Examination Type of Inspection: Remote Video Equipment Used: Westinghouse 1250 TV Camera w/Rt Angle Lens. Procedure: RP 1507-12, TCN 1-82-0051 Final Report Prep: G. R. Bond /E. D. Shoua I These irpections were performed in accordance with the GPU Nuclear Fuels in-spection plan outlined in Memo NF-2620 on April 20, 1982. The following people were directly involved with the examination: J. T. Mayer - B&W R&D Division C. B. Mehta - GPU Nuclear Fuels R. M. Rama - GPU Nuclear Fuels E. D. Shoua - GPU Nuclear Fuels J. R. Stair - Nuclear Engineer, TMI-l W. S. Wilkerson - Lead Nuclear Engineer, TMI-l Using the Table nomenclature of GPU Memo NF-2620 the results are listed below. Item 0 " Irradiated Fuel Assemblies" I The south face of F. A. NJ 00LT (Batch 5), the east face of F.A. NJ0031 (Batch 4B), the north face of F. A. NJ013A (Batch 6), and the south face of F. A. NJ 00MG (Batch 6) were examined. The areas of particular interest for Task 7 were weld areas on the upper and lower end fittings, the intermediate spacer grids, the holddown retainer plugs, and the upper and lower spacer grids. All of these areas as well as a general view of the individual fuel rods were seen during the inspection with no weld cracking or metal degradation identified. Apart from the Task 7 concerns was the identification of some minor I spacer grid damage due to fuel handling on one assembly, and some variable rod crud patterns on F. A. NJ 00B1. Neither of these items is unusual in nature from that which has been observed previously at TMI or other B&W units. I

V I d i l r i k i i i TrsT I I

v I TEST COMPLETION REVIEW SHEET Task #7 Inspection / Test: 10C Inspected Item: Baffle Plate and Lower Grid Type of Inspection: Video Inspection and Test Plan: This examination will chect: for damage to the submerged 304 stainless steel shells and plates. Particular attention vill be paid to locking welds and HAZ's of welds. Bolts made of A193-B8 and X-750 material will also be included in this inspection. I Yes No

1. Is the work scope in agreement with the B&W Engineering Information Record?

[

2. Was there an approved inspection / test procedure used for /

this examination?

3. Does the results of the examination agree with the acceptance criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum /

requirements called out in the procedure? (Accessible quantity inspected Minimum required .) NOTE: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any repairs made to the item (s) being inspected, or recommen-

[ dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not been (reported) processed for future resolution?

[ NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. 51 - 113 2<-110 - Cro

8. Task #7 Procedure No. U 1 EU)-Q TC A3 1-82-006l Reviewer's Signature h. tJ L. lag N I

I l

m I Attachment A Test Completion Review Sheet Area #10C Item 1 & Item 4 The following exceptions were taken to the B&W EIR: - a) Insp. 2.1.1, the entire vertical length of baffle plate was not inspected. The visual conditions of the baffle toward the lower portion of the baffle were insufficient for examina-tion. b) Insp. 2.1.3, none accessible. c) Insp. 2.1.4, tne two attachment welds on each bolt's locking pin were not visible in all cases, therefore they were not inspected. I d) Insp. 2.1.6, none accessible. I e) Insp. 3.1.1, 3.1.2, 3.1.3 and 3.1.4. These areas were not inspected due to the visual conditions in this area (which prevented meaningful examination) and camera constraints. I

I I

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DMDLULis & WILLUX - fiFbD ' l[# I ENGINEERING INFORMATION RECORD , ,3 .x .

      ;                                                                                                        e 5                                                                          '

DOCUMENT IDENTIFIER 51-II32410-00 I TITLE VIDEO INSPECTION PROCEDURE-BAFFLE PLATES AND LOWER GRID i j PREPARED BY Em/ e~ Yv4, DATE Abe/< < -r

                                                                                     /VA 2, l                                         '
    . REVIEWED BY M              .//,

DATE F 24-F& . g Cto Cem A slo TN4clem 3-2 w z i REMARKS: a 1. 0 Purcose *

l As part of the inspections to evaluate the reactor coolant system', ' l! . two different peripheral fuel assemblies located adjacent to baffle plate a::semblies will be removed from the core. A video inspection will then be perfomed on the accessible, visible baffle plates and the lower grid assembly. Inspections shall be video taped. . { [ I I({2.0 a - Baffle Plate Insoection

h" 3 1. j s$

g Inspect the accessible vertical baffle plates in each 27037F I location for weid cracks and any other corrosion damage. I Areas of special. consideration are: I

1. Inspect the entire vertical length of each baffle plate. [

i 2 I Inspect the flow holes and flow slots (if visible).

3. Inspect the vertical gap (only if visible) between the baffle plates. !

4. Inspect all baffle plate to former bolts, each i h 'b g

bolt's locking pin and each pin'.s two attachment 27037F Detail F welds . gf This excludes the 'fifth horizontal row i down from the top of each baffle plate. i l l 5. Inspect the baffle plate to former bolts located oa the fifth horizontal row down from the top of each 27037F Detail J baffle plate. ! Inspect the single locking weld which i secures the 1/8 inch locking dowel. G. If visible, inspect the corner baffle to baffle 27037 F d- bolts, each bolt's crimp wire and the crimp wire E locking weld. Detail H 3 Page 1 of 2

Page 2 of 2

e. '

3.0 Lower Grid -Insoection

1. Inspect the accessible sections of the lower grid for weld cracks and any other corrosion damage. Areas of special consideration are:

1. . Inspect the accessible lower grid pads and the .1/8 . 27042 F inch fillet weld at each grid pad's ends. Section V - V

'I -

143533 E

2. Inspect on each grid pad the two 3/8 inch diameter 27042 F dowels and 1/16" fillet 30wel locking welds Section V - V

3. Inspect on'each grid pad the 1/2 inch diameter 27042 F socket head cap screw and its two locking welds. Section V - V

.,I 4. 'Inspedt any visible section of the lower grid 27042 F top rib section. 143527 E I I i . i . I ~ l E N - I I I .

I - Inter-Office Memorandum Date May 21, 1982 M 261982 l Sut:iect OTSG Task 7 Area #10C k r.A Nuclear

                 " Core Baffle Inspection" To       N. C, Kazanas                             Location Three Mile Island Director - Quality Assurance I

A remote visual inspection of the core baffle plate area adjacent to core location "H-15" was completed on April 27, 1982. The examination was performed in accordance with TMI-l Procedure )lB RP 1507-12 (TCN 1-82-0051). All of the inspected areas were found to l be acceptable with no indication of weld cracking or corrosion damage. l The completed report on Area #10C including the evaluations by W. L. 4 Kimmick, R. Ostrowski, and F. S. Giacobbe, the Test Completion Review ! Sheet, and B&W EIR 51-1132410-00 is attached. } CTCe W& iQ W. S. Wilkerson 1 i 3 Lead Nuclear Engineer, TMI-l i Enclosures WSW/sf cc: J. J. Colitz, Plant Engineering Director, TMI-l W. L. Kimmick, NDE/ Piping Insp. Lead QA I F. S. Giacobbe, Welding & Materials Manager G. E. Rhedrick QA Engineer III Mechanical R. Ostrowski, $upervisor Inservice Inspection, OC ,li. I il it i I il A0000648 i _.-m - ,---

I I OTSG Task 7 Inspection Area #10C Page 1 of 2 Tif.e: Eaffle Plate and Lower Grid Type of Inspection: Remote Video Equipment Used: Westinghouse 1250 w/Rt. Angle Lens Procedure: RP 1507-12, TCri 1-82-0051 Report Preparation: W. S. Wilkerson I These inspections were performed in accordance with B&W EIR-51-ll32410-00 I on April 27, 1982. actual examination: The following people were directly involved with the I W. Kimmick - GPUf4 QA, TMI-l W. S. Wilkerson - Lead Nuclear Engineer, TMI-l The video tape made during this exam was subsequently viewed by other GPU I individuals to help resolve one indication (discussed in Item 2.1.4 below). This included but is not limited to: J. Potter - GPUt1 QA, TMI-l 1 R. Ostrowski - GPU'1 QA, Oyster Creek F. S. Giacobbe - GPUtl System Labs, Materials & Welding Manager Using the nomenclature of the B&W ElR the results are listed below. Item 2.1.1 " Entire Length of Baffle Plate" A closeup view of the baffle adjacent to core location "H-15" was obtained for approximately 50-60% of the baffle. Camera I handling and the tight confines of the F. A. hole made per-forming a verifiable 100f, baffle inspection extremely diffi-cul t. Additionally, the surface texture and visual conditions I toward the bottom of the baffle made continued visual in-spection less meaningful. fio sign of material cracking or degradation was noted in the general baffle plate. Item 2 1.2 " Flow Holes & Flow Slots" Only Flow holes were visible and these were examined. No weld cracks or corrosion damage was found. Item 2.1.4 " Baffle Plate to Former Bolts" Twenty-one of these bolts were visible, however both locking pin attachment welds were not visible in all twenty-one cases. All visible bolts and welds were found to be free of weld cracking or other corrosion damage. I I

'l' Baffle Plate and Lower Grid Page 2 of 2 l Underneath the center bolt of the first row down from the top l was a dark line in the baffle plate which could not be resolved at the time of inspection. The tape of this indication was sent out for processing. Viewing of the enhanced video tape lead to I the conclusion that the indication was not related to the OTSG Stress-Corrosion cracking problem. (See attached F. S. Giacobbe memo for more details) . Item 2.1.5 " Baffle to Former Bolts, Fifth Row" Three of these were visible. Again, no weld cracking or other corrosion damage was noted. Item 2.1.6 " Corner Baffle Crimp" None visible. Item 3.0 " Lower Grid Inspection" The shading, crud buildup, and surface texture toward the bottom of the baffle plate made the satisfactory performance of these I inspections improbable. Due to thic fact, TV camera constraints, ar.d concerns over getting the camera stuck and/or damaging adjacent fuel asse:ablies during camera positioning these inspections were not i performed. I I I I ' E I . t I . 1 l

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I inter-Offico Momerandum I Date May 19, 1982 g gy Remote Visual Examination subge: Task 7 Inspection 10C Core 6111-82-2072 t Baffle Plate "B" (Area of Fuel Assembly H-15) Location TMINS Trailers #256/258 I W. S. Wilkerson Lead Nuclear Engineer-TMI 1 A visual examination using video recording equipment was performed I. on Core Baffle Plate "B" with twenty-one.(21) bolts and welded keepers and three (3) slotted screws with one (1) tack weld as a retainer. The examination performed was a visual inspection of the Baffle Plate, the bolts with keepers and tack walds. I Approximately 40". of the entire length of the Baffle Plate was examined along with the bolts, keepers and tack. welds in the accessible area behind fuel assembly H-15. During the inspection process of the plate, ic was noted that an indication, linear in nature, extended downward from the center - bolt hole of the upper first row of bolts. This linear indication extended from the bolt hole down curving away from the center. The appearance of the line was irregular and darker than the adjacent surface. The video film was reviewed extensively. Final determination of whether the indication was relevant or non-relevant was unattainable. The video film was then sent out for image inhancement. When the results of this process are received, a final de~ termination on the relevancy of the indication will be made by GPU metallurgist.

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k WLK/ej g ! / 5 7. L. imm2.ck attachment Lead Piping /NDE Inspection cc: J. Potter R. Fenti J. Tietj en N. Kazanas i QC file w/ attachment CARIRS w/ attachment a _. I

M M M M M M M M M MM .M M M M :H M, M M P rJINuclear NDE VisuaySurface Data Sheet 001187 Site: 7/J'J.Z' / _ inspection ID: Mf 7 M /Ov_, Component: //ge j M g /gffgg4

Description:

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Procedure: [g [/ #* Material: 6/3 Thickness: 3g" T(st Surf ace:gmjg' Test Method /f32,s/[jfpo No. Positions: ,()/ D,i; stance: gj in. Drawing: f743'7-f Date: //-4~7-82.

Examiner:

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Level: Z 7 Notes: kN d;t37sr?MJfrhe.d Examiner: f7 1.D.:

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Cleaner Bate # Wet O Dry Color Penetra ac 4 / Visible O Flu sc n Batch Devel r Instrument: Method: Method , Current Visible O Thermometer Machine Amperes Fluorescent OTemp Distance From o Ind. Size (Inches) $ No. Status (Inches) B Remarks CW CCW 1 2 k e d' 7 2sr>/??2 *rhax) M/ syy aas ow 6,ee .desh 24 ss." 2f 4h>/h aDdeoe/de'd keepe<s 4 74; de# As/e 9l' 6 x@ .?s 4 de 4bak, 7 s<s'ob]k% s0Y di7stol> .S 46/o y'r(*l) Meso $ CN//llJYb 49,. /$aA06 Ab4 23~deArk Ae/ c:e.edtQ /,ss e,ee- a.uvs e swi6o dooAadox).*

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i No Reportable Indications Reportable Indications & Non Relevant Indications O Hevicwed by:[gd ghu Lovel:'[ Date://sfy4 ff/t Paue /of / NDE Request No. Me th.,.l.'inet fJo. Vr.uallo 1 1 P.T./200 399 M.T./400 599 Other/600 799 ^UUUO M

1 I ! I' Et iIW Inter-Office Memorandum I Date May 14, 1982 (MT1 1094) (Rev. 1) I Subject Visual Observation of the Dil Unit Reactor Vessel Baffle Plate 1 To N. C. KAZANAS Location Reading i Ref.: Black and White Video tape of north baffle plate center bolt, top row. i Core location H15 B&W ElR-51-1132410-00

!                      Inspection area 10C On May 6, 1982, the writers reviewed the above video tape including the I         Aptech computer enhanced tape. This tape revealed a linear indication located near the baf fle plate bolt hole.

{ The indication was approxim tely 1.0"-2.0" in length with a slight curvature. l The major observations which were made are as follows:

1. The indication came up to the bolt hole but did not penetrate the hole I.D. surface.

2. The indication appears to make an abrupt acute angle change at the bolt hole.

3. In the vicinity of this indication there are numerous grinding marks which pass over the indication.

4. Other faint linear indications exist in the vicinity of the main indications, l

however, resolution is not sufficient to assess their characteristics.

5. The indication has a ragged edge appearance.

i

6. A depth assessment could not be made.

7. There were no other indications of this type on any other bolt hole i examined.

8. There were no deposits or scale observed associated with the indication.

 ,                  9. In this area the metal appeared bright with a metallic lustre while the
;g                       indication was dark obviously indicating either depth due to shadowing
 ;3                      or staining.

1 Conclusions

l. The fact that the indication is so near the bolt hole yet does not penetrate jl it suggests that the indication is not due to applied or residual stresses.

Stress would be maximum on the bolt hole I.D. surface and thus initiate cracks from that region. 35 AOOOO648

N. C. KAZANAS May 14, 1982 I

2. In the absence of a stress related phenomenon, environmentally induced s cracking can be ruled out as a possible cause for the linear indication.

3. This indication is believed to be a surface anomalf associated with the plate and/or baffle manufacturing history. The fact that grinding was

 ;                done in this area would suggest an attempt to remove such an indication during manufacturing.

Recommendation:

.              1. During the next refueling outage, it is recommended that this area be re-examined to determine if any changes have occurred to the indication shape.                                                7 S

45 - //

                                                        .& Q ;/ ) cac'/-N
                                                              'F. E. ' Giacobbe Materials & 'elding Manager

[ R. Ostrowski cc: B. E. Ballard W J. J. Colitz C. D. Cowfer i J. J. Potter

            .D. G. Slear S. Wilkenson i

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I . Inter-Office Memorandum Date May 28, 1982 ; (MTI 1105) ![ k d ( ( h-[ Subject Visual Observation of the TMI Unit 1 Mrcr-72 373 Reactor Vessel Saffle Plate To N. C. KAZANAS Location Rsading Ref.: MT1 1094 dated May 14, 1982. I I Please note that in conclusion 1 the word " crack" has been changed to

             " indication". The use of the word crack was incorrect and was an oversight i           on the part of the writers.

t ,l,c aY- -l . : c.c. c~.aw . . F. Scott Giacobbe I FSG/ds Manager Materials Engineering

                                                                                   & Failure Analysis I

l 4p:9a"%o 8 i J G 1982 % ig i. f,e.inr [rrcn 8 g 3 4. e e) 3 -w I I 1 8 i y

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'I I I s I I i 1 1 TEST 10D 8 I , g , I I I 1 i s 8

I TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 10D Inspected Item: Control component Type of Inspection: Video I Inspection and Test Plan: One control rod assembly (CRA) and one axial power shaping rod assembly (APSRA) will be partially withdrawn in their core position and visually inspected to verify their normal condition. I I Yes No

1. Is the work scope in agreement with the B&W Engineering Information Record?

2. Was there an approved inspection / test procedure used for this examination?

3. Do # the results of the examination agree with the acceptance criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum requirements called gut in the procedure? (Acpessible I h quantity ins eted4ful Minimum r

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NOTE: ocL If M ocfA ie. vah.a answers to w1),

                                              $%dp(L tuA&equired               4 fe,(..)

(2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any repairs made to the item (s) being inspected, or recommen-I I 6.

dations for repairs or replacements? Does there exist any unresolved discrepancies that have not v been (reported) processed for future resolution? 8' NOTE: If any of the answers to (5) and (6) are yes, a written description must i be attached.

7. B&W EIR No. d - II 3 24/ 2. - 01

8. Task #7 Procedure No. STP 1 - T2. - 0 02 7 Reviewer's Signature . ,

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Title:

Control Component Examination Type of Inspection: Remote Video I Equipment Used: Westinghouse 1250 w/Rt. Angle Lens Procedu re: STP l-82-0027 Final Report Prep: G. R. Bond /J. D. ficCarthy - General Conditions I W. Kimmick - Detail on End Plug to Tube Weld I The inspections were performed in accordance with the GPU Nuclear Fuels Memo NF-2620 on April 22, 1982. The following people were directly involved in the actual examinations: W. Kimmick - GPUN QA, TMI-1 J. E. Matheson - B&W Fuel Engineering J. T. Mayer - B&W R&D Division J. D. McCarthy - GPU Nuclear Fuels E. D. Shoua - GPU Nuclear Fuels I J. R. Stair - Nuclear Engineering, TMI-l W. S. Wilkerson - Lead Nuclear Engineer, TMI-1 As in inspection #10C additional GPU individuals reviewed the video tape. i Using the nomenclature from NF-2620 the results are listed below. Item B.1 "CCA Spider" Various spider assemblies were examined during the holddown spring inspection and this inspection. No unusual conditions were found. Item B.2 " Rod Nut Weld" Rod nut welds on the APSR A03 and C10, additionally some of these welds

I were examined during the top of core inspection. All nuts were present and no material cracking or corrosion noted.

Item B.3 " Retainer Pin Welds" A video closeup on some of these welds was performed on A03 and C10, additionally some of these welds were examined during the top of core inspection. No weld cracking or corrosion was found.

I it I

5

o lI i Control Component Examination Page 2 of i 48 Item B.4 " Upper End Plug to Cladding Weld" Approximately 8 to 10 of these welds were examined close up on each CCA. There were some initial concerns with one weld which i were subsequently found to be typical of the as-manufactured condition. Overall, no material cracking or corrosion was found. l Item B.5 " Cladding" A video closeup of 4 to 8 rods on each CCA was performed over approxima tely 15-20 inches . No clad irregularities were iden-ti fied .

In addition to Items B.1 thru B.4 a general overview was obtaine'd of each CCA. Both looked typical for their age and service.

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Enter-Office Memorandum l Date May 11, 1982 Remote Visual Examination (( M#'*

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subject Task 7, Inspection 10D Control Rod Inspection (Axial Power 6111-82-2075 I Shaping Rod A.P.S.R.) TMINS railers !256/258 To Location t I W. S. Wilkerson Lead Nuclear Engineer-TMI-l Aon visual examination using video recording equipment was performed F-4. Axial Power Shaping Rod (A.S.P.R.) #A03 located in the Core at The end examination performed plugs to the tube welds.was visual weld inspection of the upper assembly with one (1) weld perThere rod. are sixteen (16) rods in the Rods examined were only those I rods which were accessible with the camera. During the inspection process of the welds it was noted that one (1) 8 *onweldthehad tubea side. dark linier indication running along the toe of the weld The area was looked at for a considerable period of closetimeaswith adjusted possible, lighting which is and withtoabe estimated view taken as physicclly about I (3) inches with a good focus for a short period of two time.(2) er three I When the film was reviewed, the area of concern was frozen on the screen which allowed a close and extended examination. It was noted that this dark linier indication ran at the toe of the weld. The indication was noticeably darker than areas adjacent and ran the same contour of the weld bead. 3 One view of the weld was a profile of the joint. At this point there 3 was an abrupt chnage at the edge of the weld metal with a minute de-pressed area between slight transition' it and form the the base metal of the tube which had a weld. I It was determined from B & W Engineering, Lynchburg, Virginia, that these welds were welded using an automatic TIG process, with no filler metal added, which is buffed after completion. This process is per-formed to acquire the proper O.D. It was felt that to get a true propective of what was being seen a first hand look at one of these assemblies and welds was necessar,y. I It was determined that new assemblies were available on site. g __ I

v I Page 2 6111-82-2075 Remote Visual Examination 4 Task 7, Inspection 10D Control Rod Inspection (Axial Power Shaping Rod A.P.S.R.) I (continued) After looking at the new assembly on site and talking to the B & W 5 Engineering people, I have determined that the indication is of a non-relevant nature. This appearance is a result of the as welded I condition of the weld and is enhanced by the conditions resulting from four (4) cycles of operation. I *The exact location of the rod in the assembly was not determined. The reason for this was the inability of the camera operator to see exactly where the camera was positioned.

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W. L. Kimmick attachment Lead QC Piping /NDE Inspection I cc: J. Potter R. Fenti J. Tietj en

CARIRS (1) I I 1 I I I I

W W W W W 5W M M S W W W W W W M M M Pkr Nuclear NDE ' Visual / Surface Data Sheet Site: //777 ,/ Inspection 10:72</7 % /op Component: (Lfg sd/JE,y, Description;&y/4/ &%gc./7& f/b68llSv?st- c6/)SMth$ N ~A04S-b l.D.: [ [ ;6 [ //d3 Procedure:yg/gf.m77 Material: y/g Test Methodyd[j Thickness: ,y/" Test Surface du/[ ( pfh No. Positions: M Dis nce:y[ In. Drawing://fd/4 /g Date: [g-R Examiner: ,,y ' { _ h ,rjy ,yy Y r I.D.: //-(N/ Level: Examiner:

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_f2 Notes: g3 qapps'7;gr}ssu Level: Particle: Magnetic Particle (Only) Dye Penetrant (Only)

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I t '" ' inter-Offics Memorandum l' Date May 11, 1982 e-twAwa

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Remote Visual Examination f$ Subject Control Rod Inspection (C.R.A.) 6111-82-2074 ask 7, Inspection 100 5 T Bo W. S. Wilkerson - - Lead Nuclear Engineer-TMI-l A visual examination usfng video recording equipment was performed on Control Rod Assembly (C.R.A.) Number C-10, located in the Core at E-3. The examination performed was a visual weld inspection of the upper end plug to tube welds. There are sixteen (16) rods in the assembly im with one (1) weld per rod. Rods examined were only those rods which lE were accessible with the camera. 1 The assembly was found to be acceptable.

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                                                                  /   /~              /

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                      .                                   W .' L . Kimmick
;             attachment                                  Lead QC Piping /NDE Inspection
!             cc:     J. Potter R. Fenti

E J. Tietj en 5 _--

QC file (1) CARIRS (1) .I I I il ,I l AOOOO648 5

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I !I 8 1 l l I t . 1 I t I lI lI P I 'I I TEST 12 I I i l 1 I I . I I .I -I I I

TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 12 Inspected Item: Core Barrel Bolt Type of Inspection: Ultrasonic Inspection and Test Plan: Determine if cracking has occurred on the bolts or screws of the reactor internals. I I Yes o No

1. Is the work scope in agreement with the B6W Engineering Information Record?

2. Was there an approved inspection / test procedure used for this examination?

[

3. Does the results of the examination agree with the acceptance criteria called out in the inspection / test procedure?

[

4. Does the quantity of items inspected agree with the minimum

~ requirements called out in the procedure? (Accessible [ quantity inspected fd Minimum required 87 . ) NOTE: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any /

repairs made to the item (s) being inspected, or recommen-dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not been (reported) processed for future resolution?

[ NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. 5/- //32rfo- 4 o g 8. Task g7 Procedure No. s/-/- r2- 40/2 m -

5 Reviewer's Signature 8///M6 m l I i

O I 3ntr-Sffice Memorandum I Date April 30, 1982 Suctect Remote Ultrasonic Examination of Core Barrel Bolting. Task #7 Test # 12

h'A - & '&,

l To N. C. Kazanas q

An Ultrasonic examination of the Core barrel bolting on Unit l 's reac to r was completed. This examination could only be performed on 96 of the 120 g bolts securing the Core barrel. Interferences such as loca bumpers, vent g valv.es and jack screws limited this inspection from doing 100% of the bolts.

This meets and exceeds B&W's requirements which only required 88 Core barrel bolts as a minimum to be examined. In performance of the 96 bolts, no ,I reflectors were detected and it is considered that all the bolting which was inspected is acceptable. g On April 26, 1982 two(2) B&W personnel commenced the i.ltrasonic examination with 5 one(1) T.V. camera operat r (B&W), while under Materials Technology surveillance. During the lotted time, 60 bolts were attemped to be examined. Only 49 of the Core barrel bolts could be examined, the remaining 11 bolts had interferences 'W l which created an inadequat'e exam on these 11 bolts (refer to Attachments). This examination was performed entirely from the fuel handling bridge using along (approx 40') reach rod with the aide of video. At approximately 22:00 hours the exam was terminated due to the plant had to prepare for fuel handling for f the next day. Bolts #1 thru 60 (Y to W axis) were completed for the exact identification of the bolting which was examined, refer to B&W Volumetric data sheet attached. Re-entry was made on April 28, 1982 to complete the examination of the re-maining 60 Core barrel bolts. During this exam it was also revealed that out

E of the remaining 60 botts to be examinea, only 47 were accessible to u.T.

and 13 were inaccessible. This is depicted on Volumetric data sheets attached. l3 The test was completed and found acceptable. This exam exceeded the requirements set forth by B&W on Document 51-1132420-00, which requires that a minimum of 88 out of the 120 bolts be inspected. This exam accomplished 96 out of 120 Core barrel bolts requiring U.T. and was performed in accordance with B&W ISI 166 R/0 and STP-1-82-0012.

                                                      ,           /n - -

Rodney urner NDE S cialist RT:bif cc: C. D. Cowfer

J. Potter aM. meer

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I ' i l l l l l l l I TEST I 13, & 14 I I l I 1 I I I F a----w, ,--na-, - --- - - - --- ww - - - - - - - - - - * ~~ '-w=

I TEST COMPLETION REVIEW SHEET I Task #7 Inspection / Test: 13 and 14 Inspected Item: Annulus Between CSA and RV Type of Inspection: Video Inspection and Test Plan: This exanination shall check the annulus between the reactor vessel inside diameter and the core support shield (CSS) and thermal shield, the outside of the flow distributor and the region below it. Yes tjo

1. Is the work scope in agreement with the B&W Engineering X Information Record?

2. Was there an approved inspection / test procedure used for )(

this examination?

3. Does the results of the examination agree with the acceptance X criteria called out in the inspection / test procedure?

4. Does the quantity of items inspected agree with the minimum Y requirements called out in the procedure? (Accessible quantity inspected X Minimum required .)

NOTE: If any of the answers to (1), (2), (3), or (4) are no, a written explanation must be attached.

5. Based upon the results of this examination, were there any X repairs made to the item (s) being inspected, or recommen-dations for repairs or replacements?

6. Does there exist any unresolved discrepancies that have not X been (reported) processed for future resolution?

NOTE: If any of the answers to (5) and (6) are yes, a written description must be attached.

7. B&W EIR No. 6/- //33 S 9 7- OO I S. Task #7 Procedure No. l - 6 2 CO / '-[

Reviewer's Signature "

l CONFIRETION COPY Inter-Office iMemorandum I Date May 17, 1982 ,r ..

Subject Task #7 Inspections 13,14 (Annulus j'[ h .

                                                                                  -h h [

Area Between Core Support Assembly and I To Reactor Vessel),16 (Plenum Assembly) N. C. Kazanas Location Parsippany I Remote visual inspections using viceo tape equipment were performed on the subject areas in accordance with GPUN Procedure STP l-82-0014. There were no recordable indications as a result of these examina-tions. The following data sheets were generated to document the examina-I tions. 4 Inspection 13 & 14 000176 000177 W Inspection 16 000170

.. 000174

!g 000175 5 000179 000180 000181 000193 000194 1 pt W R. Ostrowski l Supervisor, Inservice Inspection RO/dg cc: G. Rhedrick w/ attachment l t I ! l l

I ~ I ANNULUS IlETWEEN CSA and RV

                                . Core Support Shield Annulus A  360 Weld OD Upper Flange & Shield Cylinder          (15%) Accessible & completed B  360 Weld OD Lower Flange & Shield Cylinder          (15%) Accessible 6 completed C  OD Surf ace Shield Cylinder, Upper & Lower          (15%) Accessible & completed Flange D   360 Weld OD Between (2) Outlet Nozzles and Shield Cylinder                                    Non-accessible (0%)

E (4) Flow Deflectors & Attachment Welds Non-accessible (0%) F Surveillance Tube Assemblies Non-accessible (0%) Thermal Shield Annulus _ A 360 Weld OD Between Upper & Lower Cylinder (10%) Section of Thermal Shield B OD Surface of Thermal Shield Performed - % undetermined C (20) Block Ass'y [(3) Bolts & Welds] (2/20) Accessible & completed I D (120) Lower Crid Sheet to Thermal Shield (74/120) Accessible & completed Bolts Clocking Clips & Welds 3 E (108) Lower Grid Shell to Core Barrel Bolts (72/108) Accessible & completed Clocking Clips & Welds] I I I I I I I

m: m m m O M M M M MM M M' M M M M M M YAswI.D.: is s is - i' TN 3PECTioN ic.l4 ECM, Lt ST - -

                                                                                                                                                                                                                     .          THect - i e-f 8 Ens ow eestieds                                               '

i j3 l

 ;                                                          IN Fo 72Eco R D:        51-1i32399-00                   i TtT't.E *,                         Anny3 y, tpety,,n n g 3,3             yfygg,,    y,,,,,,,,,

d ! AREA To S6 TTEM TRAwiaJa RteuintmC JT" r RCm Anse s ag mg eu rb SJa. Nu m S f( - 2.1 Core Support --- --

                                                                                                                  ,                    inspec,    e for evidence of weld dracks 14ote it Access to perform the inspec-Shield assembly out-                                     .

and corrosion damage.- See specific tion of the annulus region between side diameter region See Note 1 under gl item for additional requiremerts. the reactor vessel inside diameter vall

                                                        -Rema r k s.                             l g
                                                                                                                 ..I g                                                  ;                        and the core support shield is through the eight (3) .3 1/8 diameter vent g ; gII                                                                                    ,
                                                                                                                                                                                             ~

valvd exercise holes in the core support

                                                                                                 ,               ;                                                                                 sliteld flange.
                                                                                                 .               L                                                                                        !  .

n . 3600 circumferential 2.1.1 27039R -- Inspect accessible outside suifaces weld (weld has been 8 14660!E of detectable parts for . weld cracks blended) between '27d40) and corrosion damage. *

the core support -Detall-D '

                                                                                                                                                                                           .                 I shield upper flange                                                                                                   8 and the shield                                .

e cylinder. . g , 'I e I i 36') circumferentia: 2.1.2 270379 Inspect accessible outside su faces weld (weld has been 14660hE ofEdetectable parts for veld dracks blended) between 27040# 1 and corrosion damages . i the core support

shield lower flange Detall-E{
and the shield 4 '

cylinder. t . [ l ,

                                                                                                                       !                                    l                        l                                                                      .

l..

                                                                                                      !            ..i                                                              !

t i i i t u, -,0 , I e.

e a

W W M M mM M MM MM M mM M M M m m

TAsx2.0,: ns 'IN 3PECTioN C H Ecid Li ST Enewscamo y, I suerr 2 _ ..ga '

                                                                                                                              ;}                               ,                  i                   l IN Fo RECO R. D

51-132199-no T WLE
Annulus between CSA and MV/ Video Inspection d

AREA To SE MEm T R e anaja Rteutat m Cast ~ p r4 m esu r O Me . Nu m 6 f R, i RCatMr.1

1. Core support 2.1.3 27039F Inspect accessible outside surfaces shield cylinder i

2. Upper flange for veld cracks / corrosion damage. ,

1

3. Lower flange

                                                                          %0 weld between        2.1.4            27040F._         ,                    inspect accessible outside sur aces e.sch of the two (2)                     Detail F                              for veld cracks and corrosion amagt outlet nozzles and

the core support ,

i , g shield cylinder. i

i Four (4) flow 2.1.5 27039 Inspect accessible areas for Id -

i deflectors and view J rracks and corrosion damage. l attactunent welds to 2 7040F' core support shield j Vlev 0-C ' j cylinder. 1 I I 5 Surveillance tube 2.1.6 Inspec't accessible areas' for crac'ks, assemblies on core support shield.

                                                                                                                ,---l{.

corrosion damage. l ; l I i ' . i l

.b

I I :' i I

I Te% A-

e m M M M M m amm m mmM m M M m m m m TAswI.v.: 13 a 14 i IN SPECTioN c14 E'ck LI ST TH e" ) _e t EnaweemNs ; rN p:o 52Etto R. D: 51-1i32199-00 l

     ,                                                                                                             i                  "F WLE :             Annulus netween CSA and RV/ Video inspection 5

3 AM To GE ITEM 'T)R Aw tasa RteutAE m CsJT" i RCMAAki EX s9 mi su rO Me. Nu m 6 ER,, ! . I 3.1 Thermal shield -- 2703SF' . Inspect for weld cracks and other assembly outside . I corrosion damsge. See specific diameter area. l tten for additional requiremedts.

                                                                                                                 . ;                                                ?
                                                                                                          .     ! :                                I'               1 160 circumferentia;                 3.1.1           '14153 dis                  ins'pect acces ible outside su faces weld (weld has been                                           . - -}}

ML20063K042

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