ML20039B269
| ML20039B269 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 08/28/1981 |
| From: | Johnson L, Laguardia T, Rau F NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20039B264 | List: |
| References | |
| 8040475, NUDOCS 8112220475 | |
| Download: ML20039B269 (30) | |
Text
'
s.
PROCEDURE NO.
80A0481
SUBJECT:
PIPING WELDS PAGE 1
0F 27 ULTRASONIC EXAMINATION PROCEDURES FOR PIPING BUTT WELDS AND LONGITUDINAL WELDS LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWER STATION UNIT 1 6
CONTROLLED COPY VALID ONLY IF THIS STAMP IS RED i
Prep'd by 0
- A k"lO-77 NES Project
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DATE N E S --
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10/15/77
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12/20/77 QA Mgr.
Date 3
9/1/78 LiLCO bX
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7/11/80 5
1/14/81 Date 6
8/21/81 o
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PROCEDURE NO.
80A0481
SUBJECT:
PIPING WELDS PAGE 2 OF
___2 7 Rev.
P rep.'d No.
Date Description
~
Reason by App'd by 1
10-15 11.3.1: Delete reference NES LILCO to S&W E&DCR -
g A5210.4D 11.3.2: Change "S&W" to "LILC0" p.27, 28, 29: Add sign.
line for
" reviewer".
2
,12-77 Pg. 27: Delete"T/8" y
lfU 7KS 1pfw 3
9-78 5.6.1: Add "Paliographic For clarification Np 7TS datun... to the weld 9/<</7/
5.6.2:
Change to: "If For clarification datun markings. ;..
folloaing manner..
5.6.2:
Change to: (1)
Peorganization
~
5.6.3:
Change to: (2)
,Peorganization 5.6.4:
Change to: (3)
Peor;pnization 5.6.5:
Change to: (4)
Peorganization 5.6.6: Change to: (5)
Peor;ptdzation f
4 7-80 Deleted old Figs. 7,8,9, To reflect new information
- 10. Add new Cal Data Change page no.accordingly.
h-g Dr Sheet.
Fig. 7, 8, & 9.
(h!'
NUCLEAR ENERGY SERVICES, INC.
____m______
PROCEDURE NO.
80A0481
SUBJECT:
PlPlNy WELDS PAGE 3
0F_
77 Rev.
Prep'd No.
Date Description Reason by App'd by i
0-15 p.1
- Add " Level lil" LILCO comments of 10-14-77 NS LILCO Delete "S&W" HARTFORD comments of 10-10-77 M
1.2.2:
Delete "and/or d
- lY'O scan fixtures" i
2.l(6): Delete entirely 5.2.8:
Re-number as 5.2.9 5.2.8:
"All examination weld / areas....
be so recorded."
5.4.2:
Delete entirely, delete "5.4.1" 5.6.2:
Change 1/64" to 1/32"
- 6. l (1) : Add "in compl iance wi th Ref. 2.1 (1)"
6.l(7): Add " thermometer" 6.2 (29) and (30) : Delete, Re-number (31)
(32) (33).
8.l(2): Spell out FSH.
8.3.4 (T > 1") (b):
Correct
" positions" 10.1.3: Add "as indicated in appropriate isometrics."
11.1:
"The data sheets..
... Code Inspector."
6 NUCLEAR ENERGY SERVICES, INC.
- g,
]
_b I
Procedure No.
00A0481
Subject:
pioine teias Page L
of
,3 hu hv.
Prep'd fW.
Date Descrip:1on Reason By App'd by 5
1/14/S:
Para 2.1 (3), (4), (5)
To incorporate FC-3 S. Foote mCO Revised and General Update J
Qf)',
- ff6, Para 6.1 (3) changed size to k" through 1"
)
dia.
Para 6.2 (29) through (32) Added new cal stds Pa:a 7.1.1 changed to show cal s ds Revise Figs 1 through 5 Deleted Tables 1 & 2 CRA 1655 h-n S. Feete cO 77 6
B/21/8 L Revised para. 5.3.1 Incorporate all previou
/'
O T"
field changes.
~
Fig. 6 Revised Step 2 Refer to CRA 2078 Fig. 9 Revised Added Fig. 10 l
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e e
NUCLEAR ENERGY SERVICES. INC.
i
DOCUMENT NO.
80A0481 m
W NUCLEAR ENERGY SERVICES. INC.
ULTRASONIC EXAMINATION PROCEDURES FOR PIPING BUTT WELDS AND LONGITUDINAL WELDS
- 1. SCOPE 1.1 AREA OF EXAMINATION This documen: covers the ultrasonic examination procedures for:
1.
Austenitic stainless steel pipe-to-pipe, pipe-to-fitting, and pipe-to-safeend butt welds and longitudinal welds.
2.
Carbon steel pipe-to-pipe, pipe-to-fitting, and pipe-to-transition piece butt welds.
1.2 TYPE OF EXAMINATION 1.2.1 Volumetric examination shall be performed using ultrasonic pulse echo nominal 450 angle beam shear v. ave and 00 longitudinal straight beam techniques applied to the outside surf aces of the piping.
k 1.2.2 The examination shall be performed using manual search units (transducers).
1.3 TIME OF EXAMINATION These procedures shall govern the preservice examination and reexamination of repaired areas of the pipe welds as required by the ASME Boiler and Pressure Vessel Code,Section XI.
1.4 WELD CONFIGURATION 1.4.1 The pipe and safeend weld configurations covered by this procedure are shown in Figues 1, 2, and 3.
1.4.2 Nominal weld thicknesses range from 0.276 inches to 1.781 inches and are specified in the Tables accompanying Figures 1,2, and 3.
1.5 MATERIALS The piping, safeends, and fittings are constructed of austenitic stainless steel or carbon steel.
FORM : NES 2C5 2/60
DOCUMENT NO.
80A0481 PAGE 6
OFJ7 NUCLEAR ENERGY SERVICES. INC.
- 2. REFERENCES 2.1 REFERENCE DOCUMENTS The following documents f orm a part of this examination procedure:
1.
ASME Boiler and Pressure Vessel Code,Section XI,1971 Edition and the Summer of 1972 Addenda.
?.
ASME Boiler and Pressure Vessel Code,Section III,1971 Edition, and the Summer of 1972 Addends.
3 ASNT Recommended Practice, SNT-TC-1 A,1975 Edition.
b 4.
SOA9053; NES Procedure for Ultrasonic Instrument Linearity Verif' cation, (Latest Revision).
5.
SOA906S; NES Procedure for Training and Certification of Nondestructive Examination Personnel (Latest Revision).
2.2 OPERATIONAL MANUALS
/k\\
The equipment operational manua's f or the 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 Pressure Vessel Code,1971 Edition including Summer 1972 Addenda, except where exarNnation coverage is limited by part geometry or access.
- 4. PERSONNEL CERTIFICATION 3.1 PERSONNEL CERTIFICATION REQUIREMENTS 4.1.1 Each person perf orming ultrasonic examination governed by this procedure shall be certified in accordance with References 2.l(1),2.l(3), and 2.l(5).
4.1.2 An examination crew shall consist of one or two members as needed. At least one member of each crew shall have a minimum qualification of Level II in accordance with the above referenced documents.
The remaining member (s) shall have a minimum qualification of Level I.
4.2 PERSONNEL RECORDS 4.2.1 Records of personnel qualification shall be maintained by Examination Contractor.
- COV :NES 205 2.20
DOCUMENT NO.
80A0481 PAGE
' ~7 OF M NUCLEAR ENERGY SERVICES, INC.
4.2.2 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 examinations per this procedure.
- 5. EXAMINATION REQUIREMENTS 3.1 EXAMINATION FREQUENCY 5.1.1 The nominal examination f requency sha!! be 2.25MHz for all straight beam and angle beam examinations.
5.1.2 Other pulse f requenu. shall be used 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 sheets.
5.2 EXAMINATION ANGLES AND COVERAGE 5.2.1 The intent of this procedure is to provide maximum examination coverage in ensure weld integrity. Each weld *all 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 six (6) inches per second.
5.2.3 Each weld and the required volume (WRV) of metal for c :e (1) wall thickness on each side of the weld shall be ultrasonically examined using 450 angle beam techniques applied in two directions perpendicular to the weld axis and in two directions parallel with weld axis and on both sides of the weld where part geometry or access permit.
5.2.4 Straight beam techniques shall be applied, where part geometry permits, to all parent material through which angle beams will pass during angle beam examinations. Indications detected are to be recorded in accordance with paragraph 10.1.1 of this procedure, except in areas where no back echo can be obtained. Indications detected shall be recorded and data used during evaluation of angle beam examination results.
5.2.5 Other beam angles may be used as determined necessary; i.e., for evaluation of reflectors, to compensate for geometric constraints, etc. All information shall be recorded on the data sheets.
5.2.6 In addition, straight beam techniques shall be applied to the weld and required volume where part geometry permits.
Indications shall be recorded in accordance with Section 10.1.2 of this procedure. This shall include straight oeam examination of parent material when no back echo is obtainable.
FO M :NES 205 2/30
DOCUMENT NO.
AGA04R?
NUCLEAR ENERGY SERVICES. INC.
5.2.7 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 arca of non-examination and the particular interfering condition in the space provided on the Weld Scan Data Sheet. In addition, he shall make a sketch of the weld and adjacent pipe and fitting conditions on the reverse side of the same Calibration Data Sheet (Figure 7). Photos will be taken when possible and incorporated as
(
part of the report.
5.2.8 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.
5.2.9 Coverage for the welds specified in this procedure is shown in Figures 1,2 and 3.
5.3 LIQUID COUPLANT 5.3.1 The ultrasonic couplant shall be suitable for use on nuclear plant materials
/h' and be certified not to exceed 50 ppm halogen and 200 ppm sulfer.
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 Where 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 shall be cleaned and free of dirt, weld spatter, etc., or g
any other condition which would interfere with the examination or impair proper transmission of the sound beam.
5.5 WELD IDENTIFICATION Each weld shall be located and identified per appropriate weld maps in the Program Plan Book.
5.6 DATUM POINT 5.6.1 The examiner shall verify that there has been marked a reference datum point on each weld from which ali examination data and reported g
indications shall be referenced. Radiographic datum markings are to be used if they exist on the base material adjacent to the weld.
5.6.2 If Da:um markings do not exist, the examine: shall mark the pipe in the following manner:
FCW = NES 205 2/80
DOCUMENT NO.
80A0481 H E_%
NUCLEAR ENERGY SERVICES. INC.
PAGE 9
O F_ _2"/
1.
Datum points shall be marked by the use of low stress stamps or vibratooling and sha!! not be deeper than 1/32".
2.
The datum point for all pipe butt welds in horizontal lines shall be located on the top of the pipe at weld centerline.
3.
The datum point for all pipe butt welds in vertical lines shall be at the most visible portion of the pipe at weld center'ine.
4.
Longitudinal weld datum points shall be located at the weld centerline at the intersection with the circumferential weld nearest the reactor vessel.
5.
Each weld datum point, along with respective weld reference points and divisions, shall be shown on each examination report.
- 6. EQUIPMENT REQUIREMENTS 6.1 EXAMINATION CONTRACTOR'S EQUIPMENT The following test equipm ent, or its equiv: Gent, shall be provided by the Examination Contractor for examination of weic, specified in this procedure.
1.
Pulse echo ultrasonic instrument (in compliance with Ref. 2.1 (1)).
b 2.
Wedge, 450 3.
Search urnts,00,1/4" through 1" Dia.; 2.25 MHz.
b 4.
Search units,2.25MHz angle beam of a suitable size.
5.
Couplant.
6.
Camera.
k 7.
Thermometer.
6.2 PLANT OWNER'S EQUIPMENT The Plant Owner, or his Agent, shall provide the following service facilities and equipment as requ:. red:
1.
2.
Water, Air, and Electricity.
3.
Adequate Temporary Lighting.
=c='.s = NES 205 2/80
DOCUMENT NO.
9 nan 191 my E
M OF M NUCLEAR ENERGY SERVICES. INC.
4.
Crane or Lif ting Devices 5.
Calibration Standard No. 2S-XXI-SS.
6.
Calibration Standard No. 24-305-55.
7.
Calibration Standard No. 22-080-55.
S.
Calibration Standard F s. 20-80S-55.
9.
Calibration Standard No.12-XXI-SS.
10.
Calibration Standard No.10-S05-SS.
11.
Calibration Standard No. 04-805-SS.
12.
Calibration Standard No. 24-080-CS.
13.
Calibratioi.
andard No. 20-080-CS.
14.
Calibration Standard No. 20-100-CS.
15.
Calibration Standard No. 20-120-CS.
16.
Calibration Standard No.18-100-CS.
17.
Calibration Standard No. IS-160-CS.
18.
Calibration Standard No.14-100-CS.
19.
Calibration Standard No.12-100-CS.
20.
Calibration Standard No.10-080-CS.
21.
Calibration Standard No. OS-100-CS.
22.
Calibration Standard No. 06-160-CS.
23.
Calibration Standard No. 06-080-CS.
24.
Calibration Standard No. 04-160-CS.
25.
Calibration Standard No. 04-080-CS.
26.
Calibration Standard No. 03-OS0-CS.
27.
Calibration Standard No. 03-160-CS.
28.
Calibration Standard No. 2.5-080-CS.
70A?. =!.Es 2:5 2/83
DOCUMENT NO.
80A0481 NG9 11 OF 27 NUCLEAR ENERGY SERVICES, INC.
29.
Calibration Standard No. 06-120-CS d[
30.
Calibration Standard No. 02-160-CS 31.
Calibration Standard No.10-100-CS 32.
Calibration Standard No.16-100-CS 33.
Test Surf ace Preparation (cleaning and finishing).
34 Drawings of each Examination Area.
35.
Post-examination Cleanup of Test Area.
- 7. CALIBRATION REQUIREMENTS 7.1 CAllBRATION STANDARDS 7.1.1 The calibration standards designed in 6.2 (5) through (32) shall be used for k
basic instrument calibration and for establishing ref erence sensitivity levels f or examination of the piping welds specified in this procedure.
Figures 1 through 5 provide a cross-ref erence between the welds to be examined and the applicable standard.
7.1.2 The appropriate calibration standard corresponding to each respective weld thickness shall be recorded on each Calibration Data Sheet. Figure 7 is an example of the Calibration Data Sheet to be used with this procedure.
7.1.3 Calibration Data Sheets shall be numbered 481-1, 481-2, 481-3, etc., at the time of calibration and shall be signed by the examiner (s) upon completion.
7.1.4 Calibration procedures shall be performed using the OD surface of the calibration standard.
7.1.5 The temperature of the calibration standard shall be within 250F of the pipe weld temperature. Calibration standard and component temperature shall be recorded on the Calibration Data Sheet.
7.2 REFERENCE SENSITIVITY '.14 EL 7.2.1 The reference sensitivity level shall be the c!istance amplitude curve initially obtained direct;y from the calibration standard and shall be the sensitivity level used for evaluating and recording all indications.
7.2.2 During actual weld scanning, the reference sensitivity level shall be increased at least 2X (6dB).
FORM NES 205 2/60
DOCUMENT NO.
80iO4A1 PAGE 12 O F_.21 NUCLEAR ENERGY SERVICES. INC.
7.3 TIMES OF CALIBRATION 7.3.1 Basic instrument calibration sh'all be performed using the appropriate calibration standard, search units, and instrumentation immediately prior to the examination of the piping welds specified in this procedure.
7.3.2 Instrument vertical linearity checks shall be performed at the beginning of each day of examination in accordance with the the procedure referenced in paragraph 2.l(4) using an angle beam search unit.
7.3.3 Examination system calibration checks shall be performed at least at the beginning and at the completion of each four (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.
7.4 CALIBRATION RESPONSE 7.4.1 Calibration response shall be checked at the primary reference sensitivity level.
7.4.2 Signal response obtained during calibration check shall be within plus or minus 20% of that established during basic instrument calibration.
7.4.3 If any point on the Distance Amplitude Correction (D AC) curve is below the 20% limit, the examiner shall:
1.
Mark all data sheets since previous calibration void.
2.
Recalibrate examination sys tem.
3.
Reexamine voided areas.
7.4.0 If any paint on the DAC curve is above the 20% limit, the examiner shall:
1.
Recalibrate examination system.
2.
Re-evaluate all indications recorded since the previous calibration check at the corrected sensitivity level.
7.4.5 If any point on the DAC curve has moved horizontally more than 5% of the sweep line from its original settings, the examiner shall:
1.
Correct the sweep calibration and note it on the Calibration Data Sheet.
2.
Void any data sheets made since the previous calibration check which have recorded indications and reexamine those areas.
FOW.' = t.ES 2
- 5 2 E 3
1 DOCUMENT NO.
80A0481 PAGE 1'
OF 77 NUCLEAR ENERGY SERVICES. INO.
- 8. EXAMINATION SYSTEM CALIBRATION 3.1 STRAIGHT BEAM CALIBRATION Straight beam calibration shall be performed as follows and as shown in Figure 6.
1.
Adjust the instrument sweep controls so that the examination area is displayed on the CRT screen.
Mark the horizontal screen positions selected for the hole or holes directly on the CRT screen and on the chart on the Calibration Data Sheet.
2.
Position search unit to obtain maximum response from the side drilled (1/4T if > T 1" or 1/2T if T <
1") calibration hole. Adjust sensitivity h
control to provide a signal amplitude of 80% of Full Screen Height (FSH)+
and mark location and amplitude on CRT screen.
3.
This is the primary reference sensitivity. Record all sensitivity control settings on the appropriate Calibration Data Sheet.
L.
This completes calibration for thicknesses of under one (1) inch. (No DAC is necessary for weld thicknesses under one (1) inch or less).
5.
For weld thicknesses one (1) inch and greater a distance amplitude correction (DAC) curse shall be established as follows and as shown in Figure 6.
A.
Without changing the sensitivity obtained in (2) above, position the search unit for maximum response from the 3/4T note and mark amplitude on the CRT screen.
B.
If the instrument is equipped with an electronic DAC device, the primary reference response shall be equalized at 80% of FSH over the distance range to be employed in the examination.
C.
Plot a DAC curve by connecting the two signal response positions with a continuous line extending over full examination range.
6.
Record all data and instrument settings on tne Calibration Data Sheet, and sign and date upon completion.
7.
Repeat steps (1) through (6) for eacn diff erent weld thickness just prior to examination.
- Full Screen Height rc=v = t.ES 2:5 2E
DOCUMENT NO.
on e o, aw PAGT 14 OF 27 NUCLEAR ENERGY SERVICES. INC.
S.2 STRAIGHT BEAM CALIBRATION CHECK Straight beam calibraion check as required by Section 7.3.3 shall be performed as follows:
1.
Adjust the sensitivity control settings to those recorded f or the calibrated reference sensitivity. (See Section S.1 (2)).
2.
Reposition search unit at each respective test hole and observe maxium signal response amplitudes.
3.
See Section 7.4 f or signal response requirements during calibration check.
3.3 ANGLE BEAM C/.LIBRATION Angle beam calibration shall be perf ormed as follows and as shown in Figure 6:
1.
Adjust the instrument sweep controls so that the examination area is displayed on the CRT screen.
Mark the horizontal screen positions selected for the hole or holes directly on the CRT screen and on the chart on the Calibration Data Sheet.
2.
Position search unit to obtain maximum response f rcm the calibration hole 3/4T if T > 1" or 1 - 1/2T if T < 1"). Adjust sensitivity control to provide a signal amplitude of SO% of FSH and mark location and amplitude on CRT screen.
3.
This is the primary ref erence sensitivity. Record all sensitivity control settings on the appropriate Calibration Data Sheet.
4.
DAC curves f or angle beam examinations shall be established as f ollows and as shown in Figure 6:
Weld Thickness Less than One (1) Inch A.
Position the earch unit f or maximum response f rom the calibration hole at the 1 - 1/2T position.
Adjust the instrument sensitivity controls to provide a signal amplitude of S0% of FSH and mark location and amplitude on the CRT screen. (See S.3(2)).
B.
Wittout changing sensitivity, position the search unit for maximum respanses f rom the calibration hole at 1/2T, 2 - 1/2T and 3 - 1/2T positions respectively and mark location and amplitudes on the CRT screen.
C.
If the instrument is equipped with an electronic DAC device, the primary reference response shall be equalized at 80% of FSH over the distance range to be employed in the examination.
FC:*. :NES 205 2.50
DOCUMENT NO.
80A0481 PAGE 15 OF_27 NUCLEAR ENERGY SERVICES, INC.
D.
Plot a DAC curve by connecting the signal response positions with a continuous line extending over the full examination range.
E.
Note position and amplitude of ID and OD notch responses through 3T calibration range (ID atlT and 3T, OD at 2T).
Weld Thickness One (1) Inch and Greater A.
Position the search unit for maximum response f rom the calibration hole at the 3/4T position. Adjust the instrument sensitivity controls to provide a signal amplitude of 80% of FSH and mark location and amplitude on the CRT screen (See 8.3(2)).
B.
Without changing sensitivity, position the search unit for maximum h
responses from the calibration hole at the 1/4T,1 - 1/4T and 1 - 3/4T positions respectively and mark location and emplitudes on the CRT screen.
C.
If the instrument is equipped with an electronic DAC device, the primary reference response shall be equalized at 80% of FSH over the distance range to be employed in the examination.
D.
Plot a DAC curve by connecting the signal response positions with a continuous line extending over the full examination range.
E.
Note position and amplitude of ID and OD and notch responses through 2T calibration range (ID at IT, OD at 2T).
5.
Record all data and instrument settings on the Calibration Data Sheet and sign upon completion.
6.
Repeat steps (1) through (3) for each diff erent weld thickness just prior to examination.
8.4 ANGLE BEAM CALIBRATION CHECK Angle beam calibration check as required by Section 7.3.3 shall be performed as follows:
1.
Adjust the sensitivity control settings to those recorded for the calibrated reference sensitivity (See Sectica 8.3(2)).
2.
Reposition search unit at each respective test hole and observe signal response amplitudes.
3.
See Section 7.6 for signal response requirements during calibration check.
FORM : NES 205 2,60
DOCUMENT NO.
80A0481 m
NUCLEAR ENERGY SERVICES. INC.
- 9. EXAMINATION PROCEDURES 9.1 STRAIGHT BEAM EXAMINATION OF BASE MATERIAL FOR LAMINATIONS Straight beam examinations of all base material through which the angle beams will pass during angle beam examination shall be performed at a sensitivity level which give a minimum back reflection signal amplitude of 80% of FSH.
9.2 STRAIGHT ANGLE BEAM EXAMINATION OF THE WELD AND REQUIRED VOLUME (WRV) 9.2.)
All straight and angle beam examinations of the WRV shall be performed at a scanning sensitivity level 2X (6dB) greater than the calibrated reference sensitivity level.
9.2.2 The search unit shall be swivelled to ensure maximum coverage as it is moved along a rectilinear scan pattern allowing a minimum of 25% overlap of the transducer element width (diameter).
9.2.3 See Figures 1, 2 and 3 for examination summary and scan path distances.
Refer to the Preservice Inspection Program Plan for detailed weld locations and identifications.
9.2.4 Continue scanning sequences until all base material has been examined.
Examination shall not be considered complete until all recordable indications have been evaluated per Section 10.1.1.
- 10. EVALUATION CRITERIA 10.1 RECORDING OF INDICATIONS 10.1.1 For straight beam examinations of base metal for laminations, all areas giving indications equal to or greater than the remaining back reflection shall be recorded on the appropriate data sheet prior to angle beam examination of the wcid and reauired volume.
1.
Each recorded area shall be identified as to distance from surf ace, length and position relative to the weld 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).
10.1.2 For straight beam and angle beam examinations of weld and heat affected zone, all indications showing a signal amplitude response equal to or greater than 50% of the ref erence response shall be recorded on the appropriate data sheet at the time of weld examinatien and prior to removing equipment.
FORM = NES 205 2,80
DOCUMENT NO.
90A0481 m
PAGE 17 OF~27 NUCLEAR ENERGY SERVICES. INC.
l.
Each recorded indication shall be identified as to depth (as percent of t hickness), distance f rom surf ace, length, signal amplitude and location relative to the weld 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).
10.1.3 Indications from all welds shall be reported in inches upstream or downstream of the weld centerline and in inches CW or CCW f rom the weld datum point when looking with direction of flow as indicated in appropriate isom etric.
10.2 EVALUATION OF INDICATIONS 10.2.1 Evaluation of all indications 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 11 or Level 111 examiner.
10.2.2 Results of this evaluation shall 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 t
11.1 CERTIFICATION OF RECORDS The Examiner shall complete and sign all data sheets immediately upon the h
completion of each weld examination. The data :;heets may be reviewed by the authorized Code 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 SNT-TC-1 A.
11.3 PROCEDURE CORRECTIONS AND ADDITIONS 11.3.! All procedure corrections and/or additions required during the preservice h
examinations shall be made in accordance with requirements of NES QA Program Plan No. NES 80A0448.
11.3.2 The examiner shall contact the LILCO representative on site to initiate all changes.
All changes shall be documented in the record of revisions section of this procedure.
FCW:NES 205 2/50
DOCUMENT NO.
80A0481 mer PAGE 18 0 F.__2 7 NUCLEAR ENERGY SERVICES. !NO.
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y i
SCAN LEGEND NOTE:
All scan paths rounded - up to nearest.25"
.L Perpendicular to Weld Parallel tio Weld
=
WRV Weld and required volume W Weld Width
- Base Material NOM.
PIPE ACTUAL CALIBRATION PIPE DIA SCHEDUI "
T" 0.D."
A" B"
STANDARD STAINLESS STEEL 4
l 80s
.337 ! 4.5 W+1.25
'U+.75 04-80S-SS 10 80S
.500 '10.75 W+1.5 W+1.0 10-80s-SS 12 snecial
.607 12.75
'W+2.0 W+1.25 12-XXI-SS 20 80s 1.031 20 W+3.25 W+2.25 20-80S-SS 22 80 1.125 22 ku3.5 W+2.25 22-080-SS 24 RSS 1.219 24 WA3.75 k42.5 24-80S-SS 28 wecial 1.20C 28 kw3.75 W+2.5 28-XX1-SS CARBON STEEL 160
.143 0.175 TM1.25 WA.75 02-160-CS 2.5 80
.276 2.5 p 1,g g,75 7,q_ngg_gg 3
160 438
'.5 W 1.5 W+1.0 03-160-CS 1
80
.300 1.5 1M1.0 k4.75 03-0A0-c5 6
160
.511 4R tut 75 141.'5 05-160 rc 04-080-CS 6
90 177 6.5 tu1.95 N*.75 06-080-CS A
pn tu c Aos vui c tut n 6
120
.562 6.625 W+1.75 W+1.25 06-120-CS FIGURE 1.
'JLTRASONIC EXAMINATION SCAN PATHS A
FORM NES 205 2/80
DOC,UMENT NO.
80A0481 11 av PAGE.__19 O F._ 27 NUCLEAR ENERGY SERVICES. INO.
A l --
A B
1-l r
x a
I l
so o
u 45 11 o,
= 45
<( l. 45 1
O I
o I
8 0
/ ]i SCAN LEGEND NCTIE:
All scan paths rounded-up to
.L Perpendicular to Weld nearest
.25".
?arallel to Weld
=
WFN Weld and Required Volume W Weld Width
- Base Material NOC-Pipe Actual Calibration ype,,
Schedule T"
O.D."
A" B"
Standard 6
160
.719 6.625
'a + 2.25 w+ 1.5 06-160-CS 8
l 100
.594 l 8.625 h + 2.0 w + 1.25 08-100-CS 10 l
80
.594 (10.75 w + 2.0 ha+ 1.25 10-080-CS
! 100 2.25ha+
10
.718 10.75 a+
1.5 10-100-Cs
.844l12.75 a + 2. 75 w+
1.75.
12-100-CS
__ 12 100 14 100
.938l14 a+ ?.0 ha+ 2.0 14-100-CS 16 l 100 1.03d16 h+3.25he+2.25 16-100-CS 18 100 1.156l18 a + 3.5 w+ 2.5 18-100-CS 18 160 1.781l18 w + 5. 5 w+
3.75 18-160-CS 20 120 1.5 l 20 e+ 4.5 lw + 3. 0 20-120-CS 20 100 1.281l20 w + 4. 0
!w + 2.75 20-100-CS 20 80 1.031l20 w + 3.75 w + 2.5 20-080-CS 24 80 1.21d24 w + 3.75 w + 2.25 24-080-CS FIGUFZ 2 ULTPASCNIC EXA*4INATION SCAN PATHS FC:W 7 NES 205 2/S0
DOCUMENT NO.
80A0481 my PAGE 20 OF 27 _
NUCLEAR ENERGY SERVIC$S. INC.
A
^
A
'f
\\
IW 'l'
/
i l
o, 45 "o
o 45 145 45_L
%WRV N gyy I
l 0*
I 0*
SCAN LEGEND Perpendicular to Weld T
Parallel to Weld
=
WRV Weld and required volume W Weld width N
- Base Material NOM.
PIPE ACTUAL l
CALIBRATION PIPE DIA. SCHEDULE T"
O.D."
A" B"
STANDARD 12 special
.607 12.75 W+2.25 W+1.25 12-XX1-SS 22 80 1.125 22 W+4.0 U+2.25 22-080-SS 24 80 1.219 24 W+4.5 m25 24-080-CS 28 i special 1.2 28 W+4.25 W+2.5 28-XX1-SS l
NOTE: ALL SCAN PATHS ROUNDED-UP TO NEAREST.25" FIGURE 3.
ULTRASONIC EXAMINATION SCAN PATH FORM # NES 205 2/80
DOCUMENT NO.
80A0481 NUCLEAR ENERGY SERVICES. INO.
PAGE 91 O F _.2 7 e
O c:::::
'~
~ ~ ~ ~.,
~
,.W
'O e
Circ. Scan
$\\
Calibration Hole
',\\
II Axial Scan Calibration Hole Calibration Hole Hole IIole Standard O.D."
T" Dia."
Location Iangth" i
14-100-c9 14
.938
.094 T
1.5 min 19-ino ce 19.7m
.o44 1
l 10-100-CS 10.75
.718 10-080-CS 10.75
.594 08-100-CF 8.625
.594 oc-Oon-ce 6.A?;
.432 06-120-CS 6.625
.562 06-160-CS 6.625
.719 l04-080-CS 4.5
.337 04-160-CS 4.5
.531 03-080-CS 3.5
.300 03-160 ce 1.c
.43c l
15-080-CS 2.5
.276 l
nn 1cn_ce n_,7c
_,a, 12-XX1-SS 12.75
.607 10 cn9-SS 10.75
.500 04-805-SS 4.5
.337 I
I Figure 4.
Ultrasonic Examination Calibration Standards less than 1".
FCAM t,ES 205 2/80
{
DOCUMENT NO.
80A0481 PAGE _ 22 OF_ 27 NUCLEAR ENERGY SERVICES,INC.
Circ. Scan
[ ~_ _ ~_ T)
(
)
(_ _ ~_ _ ~, ; Calibration Holes X
~
h
,m O
v e
il
.)m Illl AXIAL
\\\\
\\
CALIBRATION HOLES CALIBRATIO'i HOLE HOLE HOLE STANDARD 0.D."
T" DIA."
LOCATION LENGTH 24-080-CS 24 1.219
.125 1/4T-3/4 1.5 min.
i
_ -080-CS 20 1.031 20 20-100-CS 20 1.281 20-120-CS 20 1.5 18-100-CS 18 1.156 l
!18-160-CS 18 1.781 16-100-CS 16 1.031 28-XXI-99 28
!.?
24-80S-SS 24 1 ?10 l22-080-SS 22 1.125 l20-80S-SS 20 1.031 y
y j
i l
l t
I I.
FIGURE 5.
ULTRASONIC EW11 NATION CALIBRATION STANDARDS EQUAL TO OR GREATER THAN 1".
FORM: NES 205 2/80
DOCUMENT NO.
80A0481
= "
NUCLEAR ENERGY SERVICES, INC.
1 2
_3 Primary Reference T
I Response set at 80%
1 2
3 4
l 4 of full screen.
~{2 f
l c.6, ~ ' g <~Vv v/
ll li I
x,-
II ll 0
l fl; ll q
If For Thickness of 1 inch or less T
1T 2kT 3T 1
I FT
~"~ ' Primary Reference 2
Response cct at 80% of I
I b
h l
Full Screen
^ '
t g
, /,, ,,I ll l
4 3/4T j
y' s_ /,-
l f;
[
t l
For Thickness over 1 inch I
ll l-l Il
!i i
C.
$T 3/4T lkT 1 3f'4 f SEARCH UNIT LOCATIONS & DI.p CURVES FOR ANGLE BFAM CALIB'JATION-g Primary Reference Response T
1 r -,
T 1T p
y4 4
4
/ Set at 80% of Ful_ Screen b-2T b'-
b-
?
L i
/
l_T 3
3 4
4 SEARCH UNIT LOCATIONS & DAC CURVE _ TOR STRAIGHT SEAM ' CALIBRATION, NOTE: For straight beam calibration on we1Lt under l',' thick, use :T hole enl'r, r.o DAC Neg' !.
STEP 1 - Adjust sweep controls so that the entire examination $ea is displayed on CRT screen
~
STEP 2 - Adjust sensitivity to provide 80LFS! indication from the appropriate hole giving maximum response as referenced in paragraphs 8.1 or 8.3.
Mark position on screen.
.r.
STEP 3 - Position search unit for maxinam respojisc' from remaining holes'.
Mark positicn on screen.
STEP 4 - Plot DAC by connecting points marked' on screen wien line extended to cover entire examination range.
STEP 5 - Record all sweep and sensitivity control settings en respective data sheets.
FIGURE 6 - REFERENCE SENSITIVITY A!O DAC CALIBRATION PROCEDL*RES FOR ULTRASONIC EXAMINATION OF WELDS.
FORM : NES 205 2/80
n PROC 5 DURE NO SOA0481 m
EE E
Page
,a of 27 Plant / Unit Data Shi.tet No.
comp / System CALIBRATION DATA SHEET Procedure No. a n. ni o r i
' ISO Loop
Subject:
~~~~~
Rev/ Change No.
INSTRUMENT SE~ TINGS 3EARCH UNIT Calibration Block No.
Mf 1/P.odel No. -
Scan Angle:
Mode:
Surface Serial No.
Fixturing (if any):
Block Temp
_' F Comp. Temp
- F 3 weep'Lencth Style or Type No. :
Thickness Size & Shape.
CRT Calibrated in Sweep'Delty Pulse Lencth/ Damping:
Freq.2ency Frec.
Rep. Rate:
Serial No/ Brand :
Fil$er:
Video:
Jack:
Measured Angle DEC/ Gate Switch:
Range:
Cable Type & Length:
i bde Select:
Reject:
Couplant Brand:
hain Iccarse):
(fine):
Counlant Batch:
e
~
Scan Sensitivity DAC PLOT 10 0 %
1.o.n.
2.. nam 2 cm..
2 90l l
1 j
2 j
3 l
4 l
5 SCAN Ann.
A plitu'de l
l 1
l l
l l
l l
l no gpy l Hic. l Low l l High l Low I
I I
I I
I I
I I
I 7ol l
l l
l l
l l
I oo ug,3 1l l
l5l l
60
_L g
j j
j j
To Weld S
2 I
Jel l
- i. l + 1 +
1 +
l + 1 -
=
10 v,1d 40, 2
g,
l 7I l
2 3
=
Calibration 30l l
l l
l l
l l
l 4l
-l lel 2Oj g
l Axial 10[. )
lip.),itiltie l I ilititlp ylit tiliitt Cire AMPL. CONTROL LINEAn!TY O 1 2 3 4 5 6 7 8 9 10 Initial l l d3 l Result 80 l
-6 80 l -12 l
EXAh! NATION
- S?'
CCFy.ENTS/ REASON FOR 40 l
46 l
WELD /APIA INCOMPLE*ED SCAN (S)
YeslNo l Geom 20 l +12 l
l l
1 1
I l
CHECF5l TII'.E l
C:1!ERATIO::
Init al Cal.
l l
l Intermediate l
1 l
l e
i Inter ediate I
l Interrediate Final Cal.
l l
ADDITICNAL SHEET 5? (CHECK BOX)
EXAMINERS 1 Date Letel Continua t ion l l Beam Plot l 2
Date Level Supplements l lNcne l
y..,..,..r...
Date
.-.a..
NUCLEAR ENERGY SERVICES M,.
FIGURE 7
~.,s PROCEDURE NO."f0A0481-~
Plant /, Unit A
ATA SHEET Data SheetNo, CONTINUATION SHEET Comp / System Procedure No. 80A0481 Subj ec t Recordable Examina t t'on
. ~ Indication COMMENTS / REASON FOR
'w' e l d / A r e a '= ~
~-
OBSTRUCTIONS YES NO GE0M Incompleted Scan (s)
\\%
+
i I
T_
I Additional Sheets?(Check Box) Examiners 1.
Date Level 2.
Date Level Continuation Reviewer Date Supplements auctsna t~tacv scavicts ac FIGURE 8
NUCLEAR ENERGY SERVICES, INC.
I'roject No.
Site L tocation Date: (Day /Mo/Yr) g Item idenLIfIcallon l.ocation Pap,e of S
o Enaminer:
TC-1A Level Angle 0"
45".L 4 5"=
Attached Cal. Data Sheet J-~~~
~ ~ ~ ~ ~
'[~
~
'- 7
""I
\\;'-[./
Thickness Exam i ner : TC-1A Level
- cann ing
_r-
~ x_
I
,i n Diameter (nom.)
MP Metal Path W max Distance frem g to S.U. at maximum response.
Y RBR Remaining Back Reflection W
Distance from weld g' at 50% of DAC (backward) at 50% of DAC (fwd) 1--
L Distance from Datum 0 W
Distance from weld C c,
j l
Ind.
FWD BACKWARD L
L RBR S.U.
W MAX 507 DAC 50%
DAC l -
j
[1; i
a-w of lc-W MP W
MP W
MP 50%
max 50%
amp Loc.
-67 J 2
No.
DAC DAC DAC RDiARKS DRAW FULL SCALE PLOT IIERE:
'o tf M
Sd
=
REVIEWER DATE
-O REVIEWER DATE S
coo i
REVIEWER DATE o
E>
FIGURE 9 f--
t vi
!!P Unli:t um h
!!!!h!;: C h
'"3 d ' rn '
7 1
DOCUMENT NO.
80A0491 1
M NUCLEAR ENERGY SERVICES, INC.
METAL PATH CALIBRATION TABLE 1&l/2 VEE SCAN PATH EXAMINATION Metal Path Calibration Material Thickness Range Recommended 45 60 70 2.5 "
< 0.5"
< 0.4" N/A 5.0 "
> 0.5"
_< l.0"
> 0.4"
_< 0.8"
_ 0.5" 10.0"
> 1.0"
_< 2.0"
> 0.8"
_< l. 6"
> 0.5"
_< l.0" 20.0"
> 2.0"
_< 4.5" 1.6"
_< 3.3"
> 1.0"
_< 2.2" FULL VEE SCAN PATH EXAMINATION Metal Path Calibration Material Thickness Range Recommended 45 60 70 2.5 "
_ 0. 8"
_ 0.6"
_ 0.4" 5.0 "
> 0.8"
_< l.7"
> 0.6"
_< l.2"
> 0.4"
_< 0.S" 10.0 "
> 1.7"
_< 3.5"
> 1.2"
_< 2.5"
> 0.8"
.< l.6" 20.0"
> 3.5"
_< 7.0"
> 2.5"
_< 5.0"
> 1.G"
.< 3.3" 1/2 VEE SCAN PATH EXAMINATION Metal Path Calibration Material Thickness Range Recommended 45 60 70 2.5 "
_ l.7"
_ l.2"
_ 0.S" 5.0 "
> 1.7"
_< 3.5"
> 1.2"
_< 2.5"
> 0.8"
_< l.6" 10.0"
> 3.5"
_< 7.0"
> 2.5"
_< 5. 0"
> 1.6"
_< 3.3" 20.0 "
> 7.0"
_< 14.0"
> 5.0"
_< 1 C.0"
> 3.3"
_< 6.6" INSTRUCTIONS: The Vee Path and the examination angh are given in the specific procedure.
Using the appropriate Vee Path Examination Chart (1/2 Vee, Full Vee, and 1-1/2 Vee Paths) and the appropriate examination angle column, find the thickness range that encompasses the thickness of the material being examined.
FIGURE 10 I
A FCa'A = NES 2C5 2 E3
_ _ _ _ _ _