ML20082A457

Results of Exam Performed on 910615 of Radiographic Films Representing Welds in Critical Piping Sys

ML20082A457
Person / Time
Site:	Seabrook
Issue date:	06/15/1991
From:	Thielsch H THIELSCH ENGINEERING ASSOCIATES, INC.
To:
Shared Package
ML20082A347	List: ML20082A344 ML20082A457
References
4762, NUDOCS 9107100334
Download: ML20082A457 (49)

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{{#Wiki_filter:_. THIELSCH ENGINEERING ASSOCIATES,INC. 195 Frances Avenue Cranston, Rhode Island 02910 RESULTS OF EXAMINATION PERFOR.MED ON JUNE 15, 1991 OF RADIOGRAPHIC FILMS REPRESENTING WELDS IN CRITICAL PIPING SYSTEMS SEABROOK NUCLEAR POWER STATION j ,f' (' f / d je i m_ j,5 A.!r L Helmut Thielsch, PE June 16, 1991 Report No. 4762 9107100334 9tO70s ,PDR ADOCK OF,iOOO443 PDR

EXE_CUILVE

SUMMARY

On June 15, 1991, eleven sets of radiographic film were reviewed at the New Hampshire Yankee Seabrook Station. The radiographic film review was directed toward responding to issues raised by an NRC reviewer during May 29, 30, and 31, 1991. The primary issue was the factors used in determining film quality and the remaining issues were technique and weld discontinuities. At no time was there any question that the welds contained defects which would render them rejectable. The ASME Boiler and Pressure Vessel Code, Sections III and V, were used as the governing criteria. It was concluded that the eleven sets of radiographic films reviewed meet the requirements of Sections III and V of the ASME Boiler and Pressure Vessel Code. (1) The original radiographic examinations, including the techniques followed and interpretations

made, were performed in a meaningful manner and in accordance with the requirements of Section III of the ASME Boiler and Pressure Vessel Code.

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l (2) The radiographic film quality reviewed meets the specific requirements of ASME Sections III and V. Of all of the eleven radiographic film sets

examined, not a

single condition was noted

which, in any manner whatsoever, could affect the ability of an interpretation to be made and the weld joint integrity to be evaluated.

(3) The quality of the eleven subject field welds meets the specific acceptance criteria of ASME Section III. The results confirm that all of the radiographic films reviewed meet the requirements of Sections III and V of the ASME Boiler and Pressure Vessel Code. None of the radiographic film exhibited any qualities which would inhibit the ability to interpret the weld to the ASME Boiler and Pressure Vessel Code accept / reject criteria. -b-

4 SCOPE Mat _eLiiLL_Re_v_Lewed Eleven original sets of radiographic film Radiographic Inspection Reports (Appendix A) The unresolved items from the NRC Reviewer's Report NOTE: Digitized films not needed for the review -c-

i INTRODUCTIQH Because of-an ever-increasing concern with the prevention of failures in

piping, the integrity of welds previously accepted has been questioned at various nuclear construction projects.

Consequently, welds in critical piping systems which have been radiographed with film interpretations made ten years

earlier

are, on

occasion, subject to re-examinations or audits.

These audi&s are intended to determine the adequacy of the original intt e;u etations and the training, experience and qualification of the radiographers who were involved in the interpretations of the original radiographic films. This even applies where the original radiographic film interpretations were made by Level II or Level III RT Examiners, and the interpretations which were approved subsequently by the Authorized Inspector, who also has an overall responsibility for the integrity of the welding performed, as well as additional expert film viewers and auditors.

Audits, if performed in a

meaningful and objective

manner, represent an essential feature of quality assurance.

They will help to insure the adequacy of the materials, welding and other aspects associated with the overall quality systems program. Nevertheless, it must be recognized that audits, as applies, also, to the original inspections and interpretations, are made by individuals who are charged with performing their respective responsibilities in a professional, meaningful and responsible manner. Differences in interpretations may occur, even though the general conclusions may be identical with respect to the overall integrity and safety of the welded piping systems, equipment and components involved. As part of an audit on the integrity of the critical piping systems, as associated with thef, original radiographic film interpretations, radiographic films of a number of piping systems installed at the Seabrook Nuclear power Station were

4 4 re-examined by a Level III radiographic examiner employed by the Nuclear Regulatory Commission. The major issue raised by the recent NRC review of these eleven film sets of eleven pipe weld joints involved the radiographic technique and overall film quality. It should be noted that there was no NRC determination of unacceptable quality of the eleven welds, which is the ultimate intent of the ASME Codes governing the construction of these welds and their adequacy for service. RADIOGRAPHIC FIL.M INTERPRETATIONC My interpretations of the radiographic films were made on the basis of my over 35 years of experience with the examination and interpretations of pipe welds subject to the requirements of Sections III and V of the ASME Boiler and Pressure Vessel Code. Additional personal-experience factors involve extensive sectioning of welds containing weld defects which had been questioned on the basis of compliance considerations with specific requirements of the ASME Boiler and pressure Vessel Code, or the ASPZ/ ANSI Code for pressure Piping Standards. My interpretations are also based on the prior evaluations of various test welds which had been produced with all of the major defects intentionally included, to determine the detectability and interpretability of a specific discontinuity or defect condition in pipe welds subject to the

_4_ inspection requirements of Section III of the ASME Boiler and pressure Vessel Code. My interpretations are also based in part on the results of extensive litigation experiences, where specific welds were subject to legal interpretations with respect to Code compliance. These welds subsequently had been sectioned and evaluated further to establish their compliance to specific sections of the ASME Boiler and Pressure Vessel Code. At no time did these interpretations rely on the review of the eleven radiographic film sets performed previously by New Hampshire Yankee personnel (Reference Appendix A). Moreover, the review of the eleven radiographic film sets was performed without the benefit of " enhancement" of those film sets involving digitization. The film quality was such that the 4T penetrameter was clearly visible, obviating the need for enhancement. The-results of the evaluations performed on June 15, L

1991, are detailed in Appendix B.

This re-evaluation particularly involved those issues raised by the NRC Level III l ' Reviewer during the May 29, 30, and 31, 1991, radiographic film review.. Our (myself and my associate, William Weseman) examina-l- tions of the . radiographic films involved the following considerations: (1) Acceptance of radiographic films in accordance with the ASME Boiler and Pressure Vessel Code, Section III.

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,4 . a_. (2) Acceptance-of the original ~ radiographic film segments _ ori 'an -audit ' basis with respect to reasonable interpretations of-the. acceptance - limits of Section III of. the ASME --Boiler-and Pressure Vessel Code. (3)'- Acceptance of the radiographic _ inspection techniqu'es followed by the original -radiog'rapher technicians-as applicable _ to the requirements of Sections III,- V,.and XI, _ ' of the ' ASME Power and Pressure" Vessel

Code, and in'suring that: the = weld and penetrameter images on - the radiographic films are, in fact, acceptable.

(4)i Acceptances' which would involve - estimating shadows and sizes of' indications as associated with-film. quality. L(5)- -In the event-of non-compliance with-Section -III of ' the ASME - Boiler and Pressure ' Vessel Code, we-are prepared _ to reject the : weld.- Even though such welds are borderline

with respect to acceptance. criteria, they: represent-adequate _ workmanship; and would not be subject to service-f ailurer: because of the minor. significance of the issues so noted.

Such welds would normally contain" ~ adequate wall. thickness, and meet the inherent design requirements applicable. 4 (6) These considerations include the techniques employed that result ~ in echieving a level of film quality where the weldment-can be evaluated to ASME Boiler and Pressure

y

., " Vessel-Code requirement's.

This level of film quality is evaluated' on - the - basis of being able to visualize the penetrameter' representing - 2% of the material thickness and a_ hole representing 4X the penetrameter thickness on - the finished radiographic films. Additionally, evaluations of densities in the areas of interest and geometric unsharpness compliance were considered -(.uring this review. At the beginning of any radiographic inspection l job,-the radiographers will interface with a reviewer not involved directly with exposures; and this reviewer will impose _ his/her specific requirements _ for - film evaluation-based upon the allowable ranges of the

ASME-Boiler and Pressure Vestal Code.

This can be- ~ preferred -densities and~ a particular film' based upon graininess.- It is-from this point on that-anyone J . reviewing-the film'-later will' have-to arrive at conclusions using - these Code-allowable criteria, whether - they feel comfortable or uncomfortable with the final a radiographic'~f11m. This-degree of. comfort for the reviewer has a pronounced' effect on his/her film- - evaluation _ responses. .For.this reason- -the reviewer -should-- be experienced enough to be able to evaluate across the entire range allowed by the ASME ' Boiler and - pressure Vessel Code' : without going ' to the extent -that - he/she becomes more stringent because of his/her degree of comfort. This will insure that the degree of comfort

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. l which a reviewer foels will not have an adverse effect on his/her ability to evaluate radiographic films with respect to radiographic techniques, film quality, weld discontinuities and weld defects. DISfUSS10N The basic intent of all major construction codes is to insure that the erectea piping systems are of adequate quality, and are not subject to

failures, particularly involving conditions associated with potentially catastrophic failures.

However, even leaks are considered extremely undesirable. With reference to pipe welds, this would mean that the welds must represent levels of adequate quality, which will not become subject to cracking, crack progression, or rupture under normal, or even faulted (severe) service conditions. To insure that the welds meet adequate levels of quality, the ASME Boiler and Pressure Vessel Code has established specific requirements with respect to weld defect or disc ontinuity conditions.

Moreover, to insute that those weld defects which could affect the integrity of pipe velds are deiected, the ASME Boiler and Pressure Vessel Code has established specific criteria that are intended to verify that the inspection techniques provide adequate sensitivity to insure detection of the major defect conditions which could represent hazards to the integrity of the weld joints involved.

giu,w,w,y . l With respect to radiographic examinations, a sensitivity of 24 is normally established to insure detectability of those wold defects considered to be of significance. The purposo of audits is to determine the overall proficiency, adequacy and experience of the personnel involved in the respective nondestructive examinations.

Thus, all of these factors must be taken into consideration when performing a meaningful audit.

On the basis of the examinations performed and covered by this report, it is concluded that the original radiographic film interpreters complied with the intended requirements of Section III of the ASME Boiler and pressure Vessel Code. On an overall basis, it is my opinion that nondestructive examinations, the quality assurance programs applied to radiographic examinations of piping at Seabrook Station during the 1979 t i 1985 period were tighter than required or actually desirable. Responsible and responsive exarai nations and interpreta-tions of radiographic films means that they should be interpreted to the requirements of Sections III and V of the ASME Boiler and pressure Vessel Code. Interpretations should not be made tighter than the limits established, or looser than the limits established. Nevertheless, the established limits represent extremely " conservative *

levels, far beyond the adequacy limits which normally should apply to pipe and pressure vessel welds subject to the service conditions applicable to nuclear power plants.

. It should also be recognized, if several

trained, experienced and qualified Level II or Level III Examiners review the same group of radiographic

films, that some disagreements in the interpretation will occur.

Normally, if 4,100 radiographic film sections are evaluated, agreement would be expected on about 90% of the films.

Disagreements would involvs approximately 10% of the radiographic films involving interpretations of the types of defect (or discontinuity) conditions noted and the respective levels of acceptance (or rejection). An additional 5 to 10% of the films would involve disagreements with respect to the acceptability or rejections j of the specific interpretations involved. These disagreements would involve size, type or location of the specific defect conditions identified or interpreted. For the films that we reviewed for Seabrook, we would say that their program was much tighter than the norm and therefore, their percentages would come out much better than p 1 I the norm. CONCLUSIONS . Eleven radiographic film sets which had been produced in the period from 1979 to 1985 were examined to resolve is ues i raised by an NRC Level III during an audit on May 29, 30, and 1 31, 1991. The following conclusions were reached: l

, ~ i (1) The original radiographic examinations, including the techniques followed and interpretations

made, were performed in a meaningful manner and in accordance with the requirements of Section III of the ASME Boiler and pressuro Vessel code (2)

The radiographic. film quality reviewed meets the specific accepance criteria of ASME Sections III and V. Of all of the eleven radiographic film sets examined, not a single condition was noted

which, in any manner whatsoever, could affect the ability of an interpretation to be made and the wold joint integrity to be evaluated.

(3) The quality of the eleven field welds meets the intent and specific acceptance criteria of ASME Section III. As a result of tne examination of a total of eleven film sections, the following results were obtained Accentable Reinc_ table 1-CBS-1201-01-F0103 X 1-CS-355-05-F0501 X 1-CS-355-01-F0109 X i l 1-CS-355-01-F0104 X 1-CS-360-02-F0206 X 1-CS-432-02-F0203 X l l 1-CS-355-08-F0801 X l l' "--f +-Mf* 9 7-'P r ? y-m w esm-- et ww--e**vram-

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. Acc.catable Reiccinhin 1-CS-355-01-F0102 X 1-CS-303-03-F0301-X 1-CS-302-04-F0404 X 1-CS-318-02-F0202 X The results confirm that all of the radicgraphic films reviewed meet the requirements of Section III of the ASME Boiler and Prossure Vessel Code. None of the radiographic film exhibited any_ qualities whhh would inhibit the ability to interpret the wold to the ASME Boiler and Pressure Vessel Code accept / reject criteria. t I yr w ,,wrr ->w- - wew ye,- w -y y -r--yyyy.,g-y --ny 3 r- -d's--+-" ey-g w .?yp- ='CT-

L APPENDIX A= COPIES OF ORIGINAL READER SHEETS DY PULLMAN POWER PRODUCTS FOR SEABROOK STATION l 1 e h l t i I 5 m...n--- -a

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• 55 REPORT

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APPENDIX B i FINAL INTERPRETATIONS OF RADIOGRAPHIC FILMS ON JUNE 15, 1991 BY HELMUT THIELSCH, P.E. LEVEL III EXAMI!!ER i %'M w -v r-w- evmwwg.,,- wv-emerww we-w -*. met m w r.sww, v g m +-*, e--e.+ - - *s=-*w+ +.

Radiog-Re-Radiog-NRC Weld' Film raphy graph Issue Identification hnl . Sire Date Date Synoosis Comments 1-{85-1201-01-F0103 0-1 12" 12-26-79 Internal Undercut-Centerline shrinkage and slight concav-E 405 Severe possible lack ity which represent acceptable condi-1-2 of per.etration and/or tions. severe root concasity 2-3 3-0 1-CS-355-05-F0501 0 3" 09-28-81 12-01-81 YAEC accepted the weld Slight root penetration which is accept-0.463 radiography before the able. 90 0* section was re-shot Artifact on film which is acceptable. 1-CS-355-Ol-F0109 0 3* 08-17-81 09-17-81 4T hole obscured by Slight centerline concavity in root 0.433 source fixture which represents acceptable conditions. j 1 The film did show the image of the 4T hole. 2 e 1-CS-355-01-F0104 0-1 3" 04-15-81 Flash I.D. eliminated. The original image of the identification 0.438 Grease pencil I.D. label was dark. However, the identifi-1-2 not permanent cation could be read by viewing the flim 2-3 against the light, which revealed the identification image. In addition, the identifications had been originally applied with a was pencil and had been re-applied with ink on 6/4/91. The [ original weld was radiographed on 4/15/81. The film reader sheet also y showed the date of the esposure as y j April 15 1981. This represented g i acceptable practice followed and also is acceptable. O The 4T penetrameter hola was visible. i i I

m-Radiog-Re-Radiog-NRC Weld Film raphy graph Issue Identification Seg_ntn1 _Siig_ __J2 AIL Date Synopsis Coweents This weld essentially represanted a 1-CS-360-02-F0206 b 3" 05-27-82 06-09-82 straight-thru shot. The weld itself was 1 0.438 2 Repair radingraphs read;1y interpretable on the O' view. results not consistent The penetrameter hole was visible. The wif'. eader sheet weld was set up for single wall viewing listed technique of and the weld was interpretable. The 0-1 1-2 06-19-84 double wall eccentric film dated 6/9/82 was photographed. This weld was re-radiographed on 6/19/84. 2-3 01-05-85 On 6/19/84, this weld had been re-radio-graphed for single viewing. This film was taken with four esposures. On the film section dated 6/19/84, fila 3-4 E5 segment 3 to 4 was rejected because of a 4 single inclusion measuring 3/8" in 4-0 length. A repair was subsequently made. This film section was photographed. The area was rejected for a grind mark. The weld was subsequently re-radio-graphed on 1/10/85, af ter some addi-tional contour (seooth) grinding had been done. The radiographic esposure was dated 1-CS-412-02-F0203 0-1 3" 07-18-85 7/18/85. Film section 1 to 2 was re-0.216 Back scatter evident jected (see Report). The NRC issue was I-2 back scatter. The change in density ap-2-3 pears to be due to film overlap. 3-4 Back scatter evident g 4-0 impinging on weld Section I to 2 was photographed. On 4 E section 1 to 2, defects were not appar-area ent. The penetramettr hole was visible. 3 >c 1 Film section 2 to 3 was not questioned, l te even though it has considerable varia-I n i tions it: density. This section was also v I photographed. I. i

Radiog-Re-Radiog-NRC Weld Film raphy graph Issue i Corments Identification _ iegment lilR_ lig_ Date Synopl s Film section 0 to 4 was photographed. 1-CS-432-02-F0203 The NRC issue was back scatter image, which is not considered possible. The two density patterns are of uniform density on both sides of the separa-tion. One is slightly more dense than the other. The weld certainly is interpretable and shows an acceptable weld fully in cenpliance w-ith the requirements of Sections III and V of the ASME Boiler and Pressure Vessel Code. Film section 4 to 0 was also photo-graphed. Conditions that sometimes can cause two densities on a film are film overlap, screen size, water in pipe. None of these conditions seem to apply. However, back scatter also does not seem to apply. In any case, the weld on both side, nf the separation is readily interpretable and is acceptable. 1-CS-355-08-F0801 0 3" 07-17-82 Pene on code tag Film section 0 had a code nameplate on 0.438 No 4T hole the outside which showed the *N" Stamp 1 Pene on code tag symbol irpression on the nameplate at No 4T hole the same location at which the shim 2 Pene on code tag penetrametcr was placed. The fils. did Nc 4T hole show the image of the 4T hole. This g section also was photographed.

• c I then photcgraphed view 1.

E tr View 2 shows the two 12 penetrameters g on the right of the weld and the 15 penetreeters to the left. View 2 was ^w also photographed. The penetrameter v hole was apparent on the 15 penstrameter and on the 12 penetrameter.

r Radiog-Re-Radiog-NRC Weld Film' raphy graph Issue Identification legngni Sire .Date Date Synopsis Coannents ' 1-CS-355-01-F0102 0 3" 08-17-81 08-24-81 Source not aligned weld F0102 shows tungsten inclusions in 0.438 Flash ID on pene-the weld. trameter A second view was taken where the pene-1 Flash ID on pene-trameter image was covered up by the trameter identification label. Obviously,~since 2 No 4T hoie on weld this represeited triple loading, the-metal penetrameter same penetrameters were used on this image as had been apparent on the other two images. The same tungsten inclusion defect pattern was also apparent. I also photographed view I which showed tungsten inclusions in the weld represented by this view. A second weld, apparently representing a separate

exposure, was also apparent. This second weld appeared to contain porosity.

On the lighter film, the 4T hole is apparent. View No. 2 was also photographed. The 4T hole was apparent on the penetrameter representing the base metal thickness. Slight concavity was apparent in the weld root. ~ d a ti,

Radiog-R e-P.ad i og-NRC Weld Film raphy graph Issue Identific gion $ggngni Sirg_ J ate Date Synopsis Connents 1-CS-303-03-F0301 0 3" Code tag in the way This weld was radiographed on 2/22/82. 0.216 02-22-82 The critique of this weld states that 90 Sensitivity margin-there's a Nuclear Code Stamp plate mask-ally acceptable ing the location of the penetrameters. Neither the 0* view nor the 90* view shows the existence of a Code Stamp plate that match the penetrameter. The 4T holes are apparent on the penetraeeters on the 0* view and the 90* view. The weld also is readily discernable and interpretable. It represents an acceptable weld. The 90* view was photographed. The penetrameter holes are visible on the penetraceters. 1-CS-302-04-F0404 0 3" Code tag in the way Weld F0404 had been radi.;raphed with a 1 0.216 02-22-8? 07 23--82 No 4T hole for weld double film technique. On one 'ilm, the 2 metal penetrameter di hole on the penetrameter representing the weld thickness was readily apparent. It was also apparent on the second pene-trameter representing the base eietal thickness. This weld was photographed. View 1 was photographed tw;ce. The second view had the identi fications also applied by ink. Image 2 was also photographed and the y penetrawter holes were readily visible m' an the image. The veld was also E readily interpretable. 3 x te h

Radiog-Re-Radiog-NRC Veld Film raphy graph Issue Identification Sgurant Sirg_ _Date_ Date Svnoosis Comnents 1-CS-318-02-F0202 0 3" 10-29-81 Eccentric sbbt The artifact reported by the NRC viewers 0.438 No 4T hole artifact was wiped off eechanically from the ii. weld film. 1 No 4T hole These films were viewed as double films. Eccentric shot On double 'ilm viewing, the 4T hole 2 Shot elliptical image was apparent. The view shows two Not contact welds. The weld that is being reviewed is the concentric weld opposite to the location where the station marker was identified. On film section 1 the penetrameter 4T hole image is considered apparent on one film, but not on the duplicate film. The weld is interpretable and is considered acceptable upon double film viewing. The weld itself shows a good penetration weld of uniform penetration to the ID and is typicC J a weld made by a properly qualified and highly enperienced welder. o Sx te b

<,3 New ilampshire Yankee - July 8,1991-ATTACHMENT C -) d I

New Hampshire l N Memorandum 1 5 Subject CS-355-05, F0501, (4T SENSITIVITY ISSUE) From R. C. Julian Date July 3, 1991 To File P.eference NRC Inspection Report 50-443/91-12 raises an additional issue not originally presented in the NRC Synopsis of Radiographic Review at Seabrook Station 5/29 to 5/30. The inspection report stated that "when a rereview of the radiographs [for weld 1-CS-355-05-F0501] was performed on June 20, 1991 ft was determined that the radiographs did not have sufficient 4T sensitivity." NHY has rereviewed the radiographs for Pullman-Higgins field weld 1-CS-355-05-F0501 and has determined that 4T sensitivity was achieved and is discernible. Therefore, weld 1-CS-355-05-F0501 complies with ASME Section 11: for Weld quality and its radiographs comply with ASME Section V for film quality. (M C Richard C. Julian NHY RT Level 11 RCJ/ caw File: 19.13 file: (2) New Hampshire Yankee Divis;on of Public Service Company of New Hampshire P.O. Box 300

• Seabrook, NH 03874
• Telephone (603) 474 9521

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,

New Ilampshire Yarkee July 8,1991 - - ATTACHMENT D i

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New Hampshire OO Memorandum

1. 1 hf6 Subject 1-CS-360-02, F0206 - RESPONSE TO UNRESOLVED ITEM From R. C-Julian Date July 3, 1991 To File Reference Attached is the response of the weld radiograph issue 1-C5-360-02, F0206

" Tangent Wall". NHY hes presented and demonstrated to Mr. M.C. Modes NRC that the technique stated on the RIR dated 1-10-85 station 3-4 was the technique used. The attached report documents how this demonstration was accomplished. Mr. Modes acknowledged verbally his acceptance of NHY's demonstration of technique results and indicated that a written response would be required. .0 0 C Richard C. Julian NHY RT Level II RtJ/ caw Attachment File: 19.13 File: (2) New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300

• Seabrook, NH 03874
• Telephone (603) 474-9521

Response to Unresolved Item 1-C5-360-02, F0206 The concern as stated by Mr. Modes: The repair radiographs were not taken consistent with the technique stated on the radiographic reader sheet since the tangent wall of the pipe and weld are clearly visible. The stated technique was double wall eccentric from the 0.0. The only way that the tangent wall can be revealed in a radiograph is if the source is positioned away from the pipe wall. FHY Response: The technique used to radiograph this weld was double wall contact, single wall viewing. This is the technique stated on the radiographic inspection report. With this technique, the source is placed on the outside diameter of the pipe wall while the film is, wrapped around the lower portion of the pipe extending film coverage to more than 180*. With this technique, it is possible for the film to capture the tangent wall of the pipe and the weld. Re-review of the radiographs for this weld indicates that the area on either side of the weld area of interest appears eccentric. This is due to the weld transition from the pipe to the valve and the wrapping of the film tightly around the weld. The following remarks and demonstration was presented to Mr. M.C. Modes, Chief, Mobile NDE Laboratory, ED, DRS. This demonstration consisted of a sketch depicting a 3" schedule 160 piping cross section. This sketch illustrated the actual dimensions on 3.5" 0.D. with.438 wall thickness. The cross section was divided into five (5) equal film stations 0-1 through 4-0 as originally radiographed, with a source to film distance of 4" (collimated). The source was positioned at station #1, to repr^sent the original radiographic technique set-up. Additionally, a clear overlay from the original film station 3-4 was produced with all the pertinent information, station 3,4,0 and cross section of tangent wall at station 0 illustratcd. This represents the actual weld profile of the questioned radiograph. To further demonstrate the acceptability of this technique and setup, the overlay was wrapped, conforming to the profile of the 31/2 0 D. piping sketch. This demonstrated that the tangent wall was present and that the station markers 3,4 and 0 on the overlay were aligned with tne 3,4 and 0 station of the sketch. The tangent wall configuration was demonstrated, and provides that the technique and setup used for CS-360-02, F0206 station 3-4 was correct and the NRC unresolved issue for this weld does not exist. At the conclusion of this demonstration, Mr. Modes indicated that NHY had successfully demonstrated the acceptability of the technique used for radiography for 1-CS-360-02, F0206 station 3-4 dated 1-10-85.}}