ML20039B266

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Manual Ultrasonic Exam Procedures for Reactor Pressure Vessel,Circumferential & Longitudinal Welds
ML20039B266
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 08/31/1981
From: Johnson L, Lance J
NUCLEAR ENERGY SERVICES, INC.
To:
Shared Package
ML20039B264 List:
References
8040462, NUDOCS 8112220472
Download: ML20039B266 (34)


Text

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A, PROCEDURE NO.

8_0A0468

SUBJECT:

FLANGE AND LIGAMENTS PAGE 1

0F 18 ULThASONIC EXAMINATION PROCEDURES FOR REACTOR VESSEL TO FLANGE WELD AND STUD LIGAMENTS LONG lSLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWU. STATION UNIT 1

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-j g g DOCUMENT NO. soAo468 my NUCLEAR ENERGY SERVICES. INC. PAGE 2 OF 18 E C/.TE DESCRIPTION APPROVAL 7 1 S-21-81 3 Para. 1.1 Added... (perpendicular scan). pg[ Added... scan coverage, f[ ],* / fp-y-g[ '/ j 3 Para. 1.2.2. Revised scan angles. 3 Para. 1.4.1. Changed 9/16 to 3/16. 3 Para. 1.4.2. Deleted... and 3. 4 Revised para. 2.1(3), (4), (5). l 5 Revised para. 5.2.3 and 5.2.4. 6 Para. 5.2.6. Revised shall to mr.y. o Deleted... Figure 6. 6 Para. 5.2.8. Deleted...in table 1. 6 Revised para. 5.3.1. 7 Para. 6.1 (2). Added asse=bly number. 9 Para. 8.1. Deleted...as shown in Fig. 5. 9 Revised para. 8.1 (1). 10 Para. 8.l(4). Deleted...as shown in Fig.5. 10 Para. 8.3. Revised scan angles; deleted... as shown in Figure 5. l 10 Revised para. 8.3 (1). 10 Para. 8.3(5). Deleted...as shown in Fig. 5l 11 Para. 10.1.1. Revised ecual to cr creater than to the mathematical symbol. 12 Para. 11.l. Revised authorized code In-pector to Authorized Nuclear Inscector. Deleted Ficures 5 and Table 1. Revised Figures 1-6. Refer to CRA 2079. 4

DOCUMENT NO. 90 ong PAGc 3 18 ~OF NUCLEAR ENERGY SERVICES, I"C. ULTASONIC EXAMINATION PROCEDURES FOR REACTOR VESSEL TO FLANGE WELD AND STUD LIGAMENTS

1. SCOPE 1.1 AREA OF EXAMINATf 0N Thi s document covers the ultrasonic examination procedures for Reactor Pressure Vessel (RPV) to flange weld (perpendicular scan) and RPV stud ligament. Refer to procedure SOA0462 for parallel scan coverare.

A 1.2 TYPE OF EXAMINATION 1.2.1 Volumetric examination of the stud ligament shall be performed using ultrasonic pulse echo 00 straight beam techniques applied to the nonclad upper surfaces of the RPV flange. 1.2.2 Volumetric examination of the flange wc!d shall be pe: formed using ultrasonic pulse echo 00, So and 10.50 refracted longitudinal beam techniques applied to the cladded upper surfaces of the RPV flange. g 1.2.3 The examination shall be performed manually using contact search units (transducers). 1.3 TIME OF EXAMINATION These procedures shall govern the preservice examination and reexamination of repaired areas of the RPV flange weld and stud ligament by the ASME Boiler and Pressure Vessel Code, Section XI. 1.4 WELD CONFIGURATION 1.4.1 The RPV flange weld is 5-7/8" thick. Metal travel depth from examination su-face is 19-5/8" as shown in Figure 1. The stainless steel cladding has a fg' I nominal 3/16" thickness. l.4.2 The stud ligarnent examination area consists of a 9" wide ring, g approximately 8" deep as shown in Figure 2. 1.5 MATERIALS The RPV flange is constructed of low carbon steel (SA-508 CL2) with stainless steel cladding on the ID and partically on the upper surfaces. FCW :NES 205 2/EC

DOCUMENT NO. 80A0468 11 mmr NUCLEAR ENERGY SERVICES. INO. =.

2. REFERENCES 2.1 REFERENCE DOCUMENTS The following documents form a part of this examination pro ~ dure:

1. ASME Boiler and Pressure Vessel Code, Section XI,1971 Edition and the Summer of 1972 Addenda 2. ASME Boiler and Pressure Vessel Code, Section III,1971 Edition and the Summer of 1972 Addenda 3. ASNT Recommended Practice, SNT-TC-1 A,1975 Edition /I\\ 4. NES Document 80A906S; Procedure for Training and Certification of Nondestructive Examination Personnel (Latest Revision) 5. NES Document SOA9053; Procedure for Ultrasonic Instrument Linearity Verification (Latest Revision). 2.2 APPLICABLE DRAWING 5 / The following drawings are part of this procedure: 1. CE Assembly Dwg. E-234-237 2. CE Assembly Dwg. E-234-4SI 2.3 OPERATIONAL M ANUALS The equipment operational manuals for particular ultrasonic instruments used form a part of this procedure.

3. PROCEDURE CERTIFICATION The examination procedures described in this document comply with Section XI of the ASME Boiler and Prenure Vessel Code,1971 Edition including Summer 1972 Addenda, except where examination coverage is limited by part geometry or access.
4. PERSONNEL CERTIFICATION 4.1 CERTIFICATION REQUIREMENTS 4.1.1 Each person performing ultrasonic examination governed by this procedure sha!! be certified in accordance with References 2.l(1,3, and 4).

FC4'." = NES 2:5 2/50

DOCUMENT NO. soAo468 11 NUCLEAR ENERGY SERVICES. INC. 4.1.2 An examination crew shall consist of one or two members as needed. At least one member of each :rew shall have a minimum qualification of Level II in accordance witn the above referenced documents. The remaining member shall ho ee a minimum qualification of Level I. 4.2 PERSONNEL RECORDS 4.2.1 Recc ds of personnel qualification shall be maintained by the Examination Contractor. u.2.2 A copy of the examiner's certification summary and a current eye test as required by SNT-TC-1 A shall be filed with each permanent examination record, with a copy submitted to the Plant Owner or his Agent, prior to performing examination per this procedure.

5. EXAMINATION REQUIREMENTS 5.1 EXAMINATION FREQUENCY 5.1.1 The nominal examination frequency shall be 2.25 MHz for all straight beam and angle beam examination.

5.1.2 During preservice examination, other pulse frequencies shall be used only if such variables as material attenuation, grain structure, etc., necessitate their use to achieve penetration or resolution. This information shall be recorded on the data sheet. 5.2 EXAMINATION ANGLES AND COVERAGE 5.2.1 The intent of this procedure is to provide maximum examination coverage to ensure weld /part integrity. Each weld /part shall be scanned with minimum 25% overlap of the transducer width (diameter) for each scan pass. 5.2.2 The rate of search unit movement shall not exceed 6" per second. 5.2.3 The RPV to flange weld shall be ultrasonically examined using 00,50 and [1h 10.50 refracted longitudinal beam techniques applied in one direction perpendicular to the flange weld, except where restricted by part geometry or access. 5.2.4 The flange ligament area shall be ultrasonically examined using 00 straight beam techniques applied in one direction around and between each stad hole, except where restricted by part geometry or access. 5.2.5 Other angles may be used if required for aid in evaluation of reflectors or to accomodate geometric restrictions and limited access. All information shall be recorded on the data sheets. FCW.* = NES 2 5 2:83

DOCUMENT NO. 80A0468 PAGE 6 OF 18 NUCLEAR ENERGY SERVICES. IN.:. 5.2.6 Where examination surface, geometry or other conditions (weld, contour, access, etc.) do not permit a meaningful ultrasonic examination to be performed, the examiner shall record the area of nonexamination and the b particular inurfering condition in the space provided on the Calibration Data Sheet. In addition, he may make a sketch of the weld and aujacent conditions on the reverse side or the calibration data sheet. 5.2.7 All examination weld / areas shall be entered in the space provided on the Calibration Data Sheet. If there are no recordable indications, it shall be so recorded. 5.2.8 Coverage for the welds / parts specified is shown in Figures I,2, and 3. M 5.3 LIQUID COUPLANT 5.3.1 The ultrasonic couplant shall be suitable for use on nuclear plant material k and be certified not to exceed 50 ppm halogen and 200 ppm sulfur. 5.3.2 The couplant shall be supplied in clean containers of sufficient quantity to perform the examination. 5.3.3 The couplant shall be applied manually with a brush or other suitable device. 5.3.4 A nt.re required, the examiner shall be responsible for removing couplant from the examination surface at the conclusion of the examination. 5.4 SURFACE PREPARATION All examination surfaces should be clean and free of dirt, weld spatter, or any other condition that would interfere with the examination-by impairing proper transmission of the sound beam, or by preventing free movement of the search unit along the examination surface. 5.5 WELD IDENTIFICATION s-Each weld and examination area shall be located and identified per the appropriate map located in the Program Plan Book. 5.6 DATUM POINT 5.6.1 The examiaer shall verify that each weld has been marked with a reference datum point from which all data and reported indications shaji be referenced. 5.6.2 Datum points shall be marked by the use of low stress stamps or vibratooling and shall not be deeper than 1/32". 5.6.3 The flange weld datum point shall be located at vessel 00, Et the highest point on the flange OD surface. l FCCV = NES 205 2E

DOCUMENT NO. 80A0469 my 1" 7 18 PAV OF NUCLEAR ENERGY SERVICES, INC. 5.6.4 The datum point for each ligament area around uJd holes shall be on the highest point on the fic..,ge OD surface at the inter ection of an imaginary line from the center of the reactor through the stud hole center. 5.6.5 E ch weld datum point, along with respective weld reference points and divisions, shall be shown on each e>:smination report.

6. EQUIPMENT REQUIREMENTS 6.1 EXAMINATION CONTRACTOR'S EQUIPMENT The following test equipment or its equivalvent shall be provided by the Examination Contractor (as a minimum) for examination of the vessel flange weld and stud ligaments:

1. Pulse Echo Ultrasonic Instrument (in compliance with Reference 2.l(1)) 2. Sled Assembly SOD 0437 /i\\ 3. Search Units, 3/4" to 1-1/2" Dia., 2.25 MHz, 00 4. Couplant 5. Camera 6. Thermometer. 6.2 PLANT OWNER'S EQUIPMENT Tne Plant Owner or his Agent shall provide the following service facilities and ( equipment as required: 1. Scaffolding 2. Water. air and electricity 3. Temporary lighting 4. Crane or lif ting device 5. Calibration Standard No. FL/LIG 6. Test surface preparation (cleaning and finishing) 7. Drawings of each examination area S. Post-examination cleanup of test area. i ec=v = NES 205 2/80

DOCUMENT NO. 90A0469 11 my PAGE 8 OF= _ U NUCLEAR ENERGY SERVICES, INC.

7. CALIBRATION REQUIREMENTS 7.1 CALIBRATION DATA SHEETS Calibration Data Sheets shall be nurabered 468-1, 468-2, 468-3, etc., at the time of calibration and shall be signed by the examiner (s) upon completion. Figure 5 is an example of the Calibration Da a Sneet to be used with this procedure.

7.2 CALIBRATION STANDARDS 7.2.1 The calibration standard designated in paragraph 6.2(5) shall be used for basic instrument calibration and for establishing reference sensitivity levels for examination of the specified parts (see Figure 4). 7.2.2 The identity of the calibration standard used for performing calibration shall be recorded on each Calibration Data Sheet. 7.2.3 Calibration procedures for the examination shall be performed using the cladded upper surface of the referenced standard for the flange weld examination, and unciadded upper surface for the stud ligament examination. 7.2.4 The temperature of the calibration standard shall be within 25o of the component temperature. Calibration standard and component temperatures shall be recorded on the Calibration Data Sheet. 7.3 REFERENCE SENSITIVITY LEVEL 7.3.1 The reference sensitivity level shall be the distance-amplitude curve initially obtained directly from the calibration standard and shall be the sensitivity level used for evaluating and recording all indications. 7.3.2 During actual parts scanning, the reference sensitivity level shall be increased a minimum of 2x(6dB). 7.4 TIME OF CALIBRATION 7.4.1 Basic instrument calibration shall be performed using the appropriate calibration standard, search units, and instrumentation immediately prior to the examination of the flange weld and stud ligaments. 7.4.2 Instrument vertical linearity checks shall be performed at the beginning of each day of examination in accordance with Reference 2.l(5), using an angle beam search unit applied to the code calibration standard. 7.4.3 Examination system calibration checks shall be performed at least at the beginning and at the completion of each 4-hour period of examination. and/or at the change of examination personnel, equipment, search units, coupler shoes, etc., and at the completion of the examination of each similar series of welds, in accordance with Sections 8.2 and 8.4 of this procedure. FORM:NES 22 2<S0

DOCUMENT NO. 80A0468 mr a NUC '. EAR ENERGY SERVICES. INC. 7.5 CALIBRATION RESPONSE 7.5.1 Calibration response shall be checked at the primary reference sensitivity level. 7.5.2 Signal response obtained during calibration check shall be within 120% of that established during basic system calibration. 7.5.3 If any point on the Distance-Amplitude Correction (DAC) curve has decreased by more than 20% of it:; amplitude, the examiner shall: 1. Mark all weld data sheets void since previous calibration 2. Recalibrate examination system 3. Reexamine voided areas. 7.5.4 If any point on the DAC curve has increased by more than 20% of its amplitude, the examiner shall: 1. Recalibrate examination system 2. Reevaluate all indications ~ recorded since the previous calibration at the corrected sensitivity level. 7.5.5 If any point on the DAC curve has moved horizontally more than 5% cf the sweep line f rom its original settings, the examiner shall: 1. Correct the sweep calibration and note it on the Calibration Data Sheet 2. Void any data sheets with recorded indications made since the previous calibration and reexamine those areas.

8. EXAMINATION SYSTEM CALIBRATION 8.1 STRAIGHT BEAM CALIBRATION FOR LIGAMENT Straight beam sweep calibration and DAC shall be performed as follows:

/$\\ 1. Using the unclad end of the calibration block, adjust the instrument sweep controls so that the signal responses from calibration holes E, D, C, and B k occur at the 2nd,4th,6th and 8th horizontal screen positions respectively. 2. Position search unit to obtain maximum response from the hole which gives the highest amplitude signal. Adjust sensitivity control to provide a signal amplitude of 80% of Full Screen Height (FSH) and mark location and amplitude on the CRT. FCw = NES 2:5 2a j

I DOCUMENT NO. 80A0468 PAGE 10 op 18 NUCLEAR ENERGY SERVICES, INC. 3. Without changing sensitivity, pesition the search unit respectively on the remaining holes and mark signal amplitudes and locations on the CRT. 4. Plot a DAC curve by connecting the locations (marked on the CRT) with e d continuous line extended to cover the full examination range. 5. This is the primary reference sensitivity. Record all sensitivity control settings on the appropriate Calibraiton Data Sheet. S.2 STRAIGHT BEAM CALIBRATION CHECK Straight beam calibration check as required by paragraph 7.4.3 shall be performed as follows-1. Adjust the sensitivity control settings to those recorded for the calibrated reference sensitivity (see paragraph S.l(2)). 2. Reposition search unit at each respective test hole and observe maximum signal response amplitudes and horizontal screens positions. 3. See paragraph 7.5 for signal response requirements during calibration check. 3.3 ANGLE BEAM CALIBRATION FOR RPV FLANGE WELD Angle beam sweep calibration and DAC for each angle (Oo, 50, 10.50) shall be ^4 performed as follows: 1. Using the clad end of the calibration block, adjust the instrument swt.ep controls so that the signal responses from the B, C, and D hole are evenly '1z displayed on the horizontal screen axis. I 2. Position search unit to obtain maximum response from the hole which gives the highest amplitude signal Adjust sensitivity control to provide a signal amplitude of 80% of FSH and mark location and amplitude on CRT. 3. Without changing sensitivity, position search unit respectively on the remaining angle beam calibration holes and mark signal amplitudes and locations on CRT,. 4. If the instrument is equipped with an electronic DAC device, the primary reference response shall be equalized at 80% FSH over ti.e. distance range to be employed in the examination. 5. Plot a DAC curve by connecting the locations (marked on the CRT) with a M continuous line extended to cover the full examiantion range. 6. This is the primary reference sensitivity. Record all sensitivity control settings on the appropriate Calibration Data Sheet. 7. Report all data and instrument setting on the Calibration Data Sheet. FCO'.1 = NES 2 ^5 2:63

DOCUMENT NO. 80AN 68 m PAGE 11 _OF 18 NUCLEAR ENERGY SERVICES, INC. S.4 ANGLE BEAM CALIBRATION CHECK Angle beam calibration check as required by paragraph 7.4.3 shall be performed as f ollows: 1. Adjust the sensitivity control setting to those recorded for the calibrated reference sensitivity (see paragraph S.3(2)). 2. Reposition search unit at each respective test hole and observe signal response amplitudes and horizontal screen positions. 3. See paragraph 7.5 for signal response requirements during calibration check.

9. EXAMINATION PROCEDURES 9.1 STRAIGHT AND ANGLE BEAM EXAMINATION 1.

Straight and angle besm examination of ligament area and flange weld and required volume respectively shall be performed at a scanning sensitivity level at least 2x(6dB) greater than the calibrated referer.ce sensitivity level. 2. A suitable scan pattern shall be used for all examinations. 3. For the location and the numbers of the examination areas, ref er to the Program Plan. Examination shall not be considered complete until all recordable indications have been evaluated.

10. EVALUATION CPITERIA s

10.1 RECORDING OF INDICATIONS 10.1.1 For examination of the RPV flange weld and ligaments, all indications /$\\ showing a signal amplitude res;cnse > 50% of the reference response shall be recorded on the appropriate data sheet at the time of examination. 1. Each recorded indication shall be identified as to depth, distance from ID surface, length, signal amplitude and location relative to the datum point. 2. Recorded data shall be taken on each parallel scan pass at increments not to exceed that permitted by the 25% overlap of transducer element diameter (width). 3. The end points of recorded indications shall be determined by 50% DAC amplitude points. FORM:NES 205 2 83

DOCUMENT NO. ROA0469 m OF 13 NUCLEAR ENERGY SERVICES. INC. 15.1.2 Indications f rom the RPV to flange weld shall be reported in inches below the examination surface, in degrees (or inches) CW or CCW from the weld datum point when looking down upon the top of the vessel, and in inches outboard f rom the flange ID towards the vessel OD. 10.1.3 Indications from the ligament areas shall be reported in inches below the examination surf ace, in degrees (or inches) CW or CCW from the nearest stud hole datum point and in inches outboard from the flange T towards the vessel OD. 10.2 EVALUATION OF INDICA ?!ONS 10.2.1 Evaluation of all inacations shall be made at the reference sensitivity and in accordance with the requirements of the ASME Boiler and Pressure Vessel Code, Section XI,15-300. All evaluations shall be perf ormed by a Level II or Level III. 10.2.2 Results of this evaluation sha!! be reported to the Plant Owner or his Agent in accordance with the requirements of the ASME Boiler and Pressure Vessel Code, Section XI,15-600. Disposition of evaluation results shall be made in accordance with the Owner's plant procedures.

11. EXAMINATION RECORDS 11.1 CERTIFICATION OF RECORDS The examiner shall complete and sign all data sheets immediately upon the s

completion of each weld examination. The data sheets may be reviewed by the l\\ Authorized Nuclear Inspector. 11.2 FILING OF RECORDS The examiner shall be responsible f or submitting to the Plant Owner or his Agent a completely documented set of examination records including certification of personnel qualifications (with a current eye test report) in accordance with Reference 2.l(3). 11.3 PROCEDURE COP.RECTIONS AND ADDITIONS 11.3.1 All procedure corrections and/or additions required during the preservice examinations shall be made in accordance with requirements of NES Document 80A0448, QA Program Plan. 11.3.2 The examiner will contact the LILCO representative on site to initiate all such changes. All changes shall be documented in the record of revisions. FC.Y:NES 2 5 2 23

DOCUMENT NO. 80A0468

  • AGE 13 OF 18 NUCLEAR ENERGY SERVICES, INC.

Clad 9/16" Scan Surface Y [ l / p I l I l, 1 I I l l J l 0* I I I l 5'

10. 5' l l

1 I 19 5/8" l l i l l l I 1 3/8" 1 l ~ I t F __ l I 5/16" p 5 7/8" r l Cladding l A j FIGURE 1. ULTRASONIC EXAMINATION OF REACTOR VESSEL TO FLANGE WELD FCAM :NES 205 2/80

6 / DOCUMENT NO. 80A0468 PAGE 14 OF 19 NUCLEAR ENERGY SERVICES. INC. 4" 7 1/16" 2 3/16" __ ~ _ Scan Path (Note 1) t c -s i l i t i I 8 I I l l 8 1/4" l I l l O* Straight l Bean i i l 1 F Note: See Figure 3 for Plan View of Scan Path s / l J b y-l l l FIGURE 2. ULTRASONIC EXAMINATION OF RPV STUD LIGAMENT AREAS l FCRM :NES 205 2/80

O DOCUMENT NO. 80A0468 air PAGE 15 OF 18 NUCLEAR ENERGY SERVICES, INC. Examination Surface 7 . ~ / N N OD of Clad </\\ j ID of Flange _f \\ ^ / Datu:n . #j f ' I Point jj To RPV I x \\ l / x _,/ Shaded Area Shows Examination g Surface to be Sca:med [ l I l l l 9". I i "l F/ } l l s~ l-I V ( 1 1 l 1 FIGURE 3. ULTRASGNIC E)' AMINATION OF RPV STUD LIGAMENT AREA, PLAN VIEW FC:.'.i :NES 205 2/80 t

DOCUMENT NO. 80A0468 PAGE 16 op 18 NUCLEAR ENERGY SERVICES, INC. Calibration Surface for Flange Weld Examinations L 1 1 6. 1 O O 16" 18" 20" 26" 22" i A c f 8 O C -e e o y 1r D 8" O f E ~O 4" l l 2" l I y 9 v l / 1 / Calibration Surface for I l ( Ligament Examination l l f\\ !1 FIGURE 4. ULTRASCNIC CALIBRATION BLOCK FLANGE / LIGAMENT i l FCRM :NES 205 2/80

A Plant / Unit FIGURE 5 Page 17 of 18 Comp / System CALIBRATION DATA SHEET Data Sheet No. ISO Loop Procedure No. 00A0468

Subject:

TNcTR!mrvT srTTTxcq granen imTT Rev/ Change No. 1 Calibration Mfc/Model No.: Scan Ancle: Mode: Block No. rixturine (if any): Fabrication No. Serial No. Surface Sweep Leneth - Style or Tyne Nn. - Block Temp [F Size & Shnee, Comp. Temp Sween Delav Thickness Pulse Lencth/Darrine: rreenancv CRT Calibrated in Frec.* Ren. Rate-Ser4n1 Nn/Brnnar Filter: Video: Jack: Men eured Aaal e DFC/Cate Svf*che Pnecat rnklo Tma A Tn-y - Mode Select: Re4ert rnn; 1 nn. n-n-a. Cnin (cnneenT. (#4-n). Counlant Estch 1 sc2e g n n = 4 - 4. 4... 1007 DAC PLOT 0 WRV l 1 ? 1 I, I 5 INSTR. LINEARITY CAL. 0 "'" ' 80 Amnlitude 70

== To Weld Hich Law Hich low l 1 To Weld l 1 s 40 [s enlikenrinn f 20 3-A 4,3 i' - i 10 8 lilllll!! fil! lil ! Iffl ll!! lil!lIlli llll Circ I t + A}mT] _rnmni-T"FAnTTv Initial dB Re sult__ Recordable EXAMINATION Indications C0101ENTS/ REASON FOR 80 -6 WELD / AREA Yes No l Geon. INCOMPLETED SCAN ('O 80 -12 40 +6 20 +12 I CALIBRATION CHECK! TIME Initial Cal. Intermediate Intermediate Intermediate EXAMIN':Es 1 Date Level Final Cal. l ~ 2 Me W ADDITIONAL SHEETS? CHECK BOX REVIEWERS 1 Date Continuation Fan-Pine 2 Date Sunnicurts Nnna 3 Date s a + l

1 o. DOCUMENT NO. 80A0468 PAGE 15 OF 18 NUCLEAR ENERGY SERVICES, INC. Y E { \\ CCW X [ INDICATION REPORT SHEET l FIR:GE WELD AND LIGAMENTS O I l to RPV ~ - G I o Procedure No._ _ CW Subject Y2 - Yy, Part No. L -] Datum or Page of l [ RPV Oo Attached to Cal. I Data Sheet No. D Notes: P (1) X-axis increments not to exceed I allowable scan increments (2) End points shall be: 50% of DAC l (6db) FORWARD BACK 7.DI-(1) MAX Y @ PAX (f) (f) % DAC % DAC ENDPOINT ENDPOINT NO. DATUM (idb) (2) (2) Y1 Y2 COMMENTS: EXAMINEFS 1. Date Level 2. Date Level REVIEWER Date / FIGUFI 6 FORY :NES 205 2.50

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