ML20080K655
| ML20080K655 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 06/01/1983 |
| From: | NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20080K631 | List: |
| References | |
| 80A0475, 80A475, NUDOCS 8309290323 | |
| Download: ML20080K655 (38) | |
Text
-
PROCEDURE NO.
60A0475
SUBJECT:
MANUAL SAFEEND WELD _S j
PAGE 1
0F 38 px u)
MANUAL ULTRASONIC EXAMINATION PROCEDURES FOR VESSEL N0ZZLE SAFEENDS AND CLOSURE HEAD N0ZZLE-FLANGE WELDS LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWER STATION UNIT I l
O Prep'd by 0
30lHRBUIBCBPY Di!LY <F TdlS M.'f 3 E hM,
i NES i2-2.,2 Project Mgr.
Date REV. NO.
DATE NES
.-}
d s/.I//f Mgr.[lS.ILevel I
7 Date ISI Pro
. Level lil
~;z[g[7g he_
0 2-15-78 NES Date NES 2-4-7f QA Mgr.
Date 2
1/16/81 I*
4/~1/~12 3
2/3/81 LILCO e
me u Date fhy 0,l gg y _,, 7,3 4
8/28/81
("y 5
12/11/81 Date 6
2/16/82
-7 6/1/83 g
hD DO PO 0003 2 G
PROCEDURE NO.
80A0475
SUBJECT:
MANUAL SAFEEND WELDS PAGE 2 0F _38 O
Rev.
Prep'd No.
Date Description Reason By
' App'd By 1
7/27/ Changed; 2.l(4) & (5), 5.2.3, General revision to incorporate F. T.
79 5.3.1, 6.1(2) & (3), 7.3.2, latest NES requirements.
Carr Lp 5.2.7, 7.3.3, and Figures 2,5, 6
6, and 7.
Incorporated Field Change I gh/1'/
Deleted; 2.3 Added; 5.1.3 CRA-972
[f[
2 1/16/ Para 1.1 Added Item 6 Update procedure S. L.
81 Foote Para 1.2.1 Revised Para 1.2.3 Added Para 1.4 & 1.5 Changed to Figures 1 through 7 Para 2.1.3, 2.1.4, 2.1.5, Updated Para 5.2 Revised Para 6.1 Revised Para 6.2 Added Item 10 Para 7.1 Revised Para 7.2 Added & renumber-ed accordingly 1
Section 8, 9, 10 Revised Added Fig. 7 Delete Fig. 9, 10, 11, 12.
13, 14, & Table 1 Added new Figs, and numbered accordingly CRA 1670 C
NUCLEAR ENERGY SERVICES. INC.
.--re..
,-,.w,-.
-m,,e-
_,.e.
_-w..-
--~~---wme,,
,,--a
,n
i Procedure No.
80A0475
Subject:
Manual Safeend Welds Page 3
of 38 l
I REV.
PRE'D APPROVED NO.
DATE DESCRIPTION REASON BY BY 3
2/3/F1 Para. 4.1.2 added Customer Comment S. L.
NES LILCO
...Le.el I Trainee Foote g
Para. 4.2.2 changed sub-mitted to available Para. 5.2.1 deleted last sentence Para. 5.3.4 added
...when required Para.'6.l(5) revised q
g Para. 6.l(8) added
...when required Para. 6.2(10) added feedwater Para. 8.2 - typo Para. 8.4.2 revised title Para. 8.4.3 revised title Para. 8.4.4 deleted and revised Para. 10.1. l (l) deleted (as a percent of T)
Para. 10.1.2(4) deleted
... hole representing T Para. 10.1.3 revised Para. 10.1.5 deleted (as a percent of T)
Revised to upstream and downstream 1
NUCLEAR ENERGY SERVICES, INC.
w.
,8 Pcg3 4
of 3 j
.=
(J m
o PRE'D APPROVID
~
BY BY W-orst-'4 TP* TON Pnson NO.
DATI S., L.
NTS LILCO J 3
2/3/81 Para. 11.1 changed shall Custcr.er Cdsnent Foote to' cay Para. 11.2 changed exa:niher to NES 4
8/29/
Para. 5.3.4 deleted Where Incorpcrate all previousa G
C
- ?
y.7-d,
a 81 tequired...
field changes i
celeted para. 7.5.5 Renurbered rec.ainder of section Revised para. S.4 i
g Revised para. 10.1.6 i
t Revised Figure 7
{
g Favised Figure 12 Refer to CFA 2086 5
12 Procedure cc:pletely re-To t;gade the examir.atien
$?. 6 E //7 L
81 vised. Due to the exten:
Technique MW[?/
of Technique and For.mt change, previous ?.evisien ntrebers will not be illus-trated en the boarder of the revised paragmphs.
g-6 2/16/
Delete og. 17 and renumber Extra page inserted 3 314e s
82 CRA 235c l
9 NUCLSAA ENERGY SERvtCES. INC.
~
\\j]g REVISION LOG c""T " -
""^" ~
NUCLEAR ENERGY SERVICES, INC.
PAGE 5
OF 38 RE
"^Cf DESCRIPTION APPROVAL DATE yO yg 7
6/1/83 7
Para. 1.4.1, 1.4.2 and 1.5 change figures,
6))
f/7k V llf D
./
1 through 9 to read 1 though 10 Para. 2.10 add Applicable... examinations
- //
(7,
'f" et, m.
9 Para. 5.2.3 Note reworded.
Para. 5.2.8 reworded 21-28 Finures 2.3.5.6.8.9 revised.
.29 Added new Finures 10.
37-38 Added__new Figures __18.,19.
Field changes 1 through 5 were incorporated Refer to CRA No. 3400 0
W i
FORM # NES 2062 60
DOCUMENT NO.
80A0475 NUCLEAR ENERGY SERVICES, INC.
O A
MANUAL ULTRASONIC EXAMINATION PROCEDURES FOR VESSEL NOZZLE SAFE ENDS AND CLOSURE IIEAD NOZZLE-FLANGE WELDS t
- 1. SCOPE 1.1 AREA OF EXAMINATION This document covers the manual ultrasonic examination procedures for:
1.
Mai.1 Steam (N3) nozzle to transition piece welds.
2.
Jet Pump Instrumentation (JP1)(N8) nozzle to safe end piece welds.
3.
Control Rod Drive (CRD) (N9) return nozzle to cap weld.
4.
Core Differential Pressure ( AP)(N10) nozzle to safe end piece weld.
5.
Closure Head Vent (N7) and Instrumentation (N6) nozzle to flange welds.
p 6.
Feedwater (N4) nozzle to safe end welds.
V 7.
Core Spray (NS) nozzle to safe end welds.
8.
Recirculation Outlet (N1) nozzle to safe end piece weld.
9.
Recirculation Inlet (N2) nozzle to safe end piece weld.
1.2 TYPE OF EXAMINATION 1.2.1 Volumetric examination shall be performed using ultrasonic pulse echo nominal 350 or 450 angle beam shear wave, 450 refracted longitudinal wave, and 00 straight beam techniques applied to the outside surfaces of the piping, safe ends transition pieces and flanges.
l 1.2.2 The examination shall be performed manually using contact search units (transducers).
1.2.3 Other beam angles may be used as alternative examination techniques when they facilitate examination or evaluation.
1.3 TIME OF EXAMINATION These procedures shall govern the preservice examination and reexamination of (m
repaired areas of the pipe welds as required by the ASME Boiler and Pressure Vessel Code,Section XI.
FORM # NES 205 2/80
DOCUMENT NO.
80A0475 11 my PAGE 7
OF 38 NUCLEAR ENERGY SERVICES, INC.
=
l l
!5\\
1.4 WELD CONFIGURATION I
k 1.4.1 The nozzle and safe end/ transition piece / flange weld configurations covered by this procedure are shown in Figures 1 through 10.
1.4.2 Nominal weld thicknesses range from 0.28" to 1.844" and are specified in Figures I through 10.
1.5 MATERIALS The nozzles, safe ends and fittings are constructed of austenitic stainless steel, carbon steel, or inconel, as designated in Figures I through 10.
- 2. REFERENCES The following documents form a part of this examination procedure:
1.
ASME Boiler and Pressure Vessel Code,Section XI,1971 Edition and Summer of 1972 Addenda 2.
ASME Boiler and Pressure Vessel Code, Section Ill,1971 Edition and Summer of
( )
1972 Addenda 3.
ASNT Recommended Practice, SNT-TC-1 A,1975 Edition 4.
NES Document 80A0482, Preservice Inspection Program Plan, Unit 1 (latest revision) 5.
NES Document 80A0448, Quality Assurance Program Plan for Inservice Inspection Program (latest revision) 6.
NES Document 80A9068, Procedure for Training and Certification of Nondestructive Examination Personnel (latest revision) 7.
NES Document 80A9053, Procedure for Ultrasonic Instrument Linearity Verification (latest revision) as modified in paragraph 7.4.2 of this procedure 8.
NES Document 80A9005, Inservice Inspection Data Review Procedure (latest revision) 9.
NES Document 80A9060, Inservice Inspection Field Change Procedure (latest revision) 10.
Applicable technique sheets attached to the procedure for unique examinations 7~
l
+
l l
I i
l FORM # NES 205 2/80
DOCUMENT NO.
80Ao475 my PAGE 8
OF 3R NUCLEAR ENERGY SERVICES, INC.
l l
- 3. PROCEDURES CERTIFICATION The examination procedures described in this document comply with Section XI of the ASME Boiler and Pressure Vessel Code,1971 Edition, including 1972 Summer Addenda, except where examination coverage is limited by part geometry or access.
- 4. PERSONNEL CERTIFICATION s
'5\\
4.1 PERSONNEL CERTIFICATION REQUIREMENTS 1.
Each person performing ultrascnic examination governed by this procedure shall be certified in accordance with the documents referenced in paragraphs 2.1, 2.3 and 2.6 above.
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 11 in accordance with the above referenced documents.
The remaining member (s) shall have a minimum qualification of Level I or Level 1 Trainee.
4.2 PERSONNEL RECORDS l
I 1.
Records of personnel qualification shall be maintained by the Examination Contractor.
2.
A copy of the examiner's certification summary and a current eye test report as required by SNT-TC-I A shall be filed with each permanent examination record, with a copy available for the Plant Owner, or his Agent, prior to performing examinations per this procedure.
- 5. EXAMINATION REQUIRI.MENTS 5.1 EXAMINATION FREQUENCY 1.
The nominal examination frequency shall be 2.25 MHz for all straight beam and angle beam examinations.
2.
Other pulse fregeencies 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.
l l
3.
5.0 MHz transducer may be required to achieve resolution of the side l
drilled holes in the calibration blocks.
I I
V FORM # NES 205 2/80
DOCUMENT NO.
80A0475 NUCLEAR ENERGY SERVICES, INC.
l 5.2 EXAMINATION ANGLES AND COVERAGE 5m 1.
The intent of this procedure is to provide maximum coverage to ensure weld integrity. Each weld shall be scanned with a minimum of 25% overlap of the transducer element dimensional width (diameter) for each scan pass.
The area to be examined shall be divided into two (2) zones; carbon and stainless steel.
The instrument shall be properly calibrated for examination of each separate zone.
2.
The rate of search unit movement shall not exceed 6" per second.
3.
Each weld and the required volume of metal (WRV) for IT on each side of the weld shall be ultrasonically examined using 350 or 450 shear wave or 450 refracted longitudinal wave angle beam techniques applied in two directions towards the weld and in two directions parallel with the weld, except where restricted by part geometry or access.
Note:
Circumferential scanning performed on safe ends with
/
thickness / diameter (T/D) ratios greater than.15 shall utilize a 350 angle
/73 beam technique and 1/2 vee calibration.
4.
Straight beam techniques shall be applied, where part geometry permits, to all base material through which the angle beams will pass during angle beam examinations. Indications detected are to be recorded in accordance q
g with paragraph 10.1.1 of this procedure.
In addition, straight beam techniques shall be applied to the WRV where part geometry permits.
Indications shall be recorded in accordance with paragraph 10.1.2 of this procedure.
5.
Other beam angles and or longitudinal waves 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.
6.
Where the examination surface, geometry, or other conditions (weld, contour, access, etc.) do not permit a meaninful ultrasonic examination to be performed, the examiner shall record the area of non-examination and the particular interfering condition in the space provided on the Weld Scan Data Sheet. In addition, he may make a sketch of the weld and adjacent pipe and fitting conditions on a separate sheet of paper and attach to the Calibration Data Sheet.
Photos may be taken when possible and incorporated as part of the report.
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.
l l
I 8.
Coverage for the welds specified in this procedure is shown in Figures 1 through 10.
5.3 LIQUID COUPLANT l
l 1.
The ultrasonic couplant shall be suitable for use on nuclear plant materials and be certified not to exceed 50 ppm halogen and 200 ppm sulfur.
/
FORM # NES 205 2/80
DOCUMENT NO.
80A0475 11 mr NUCLEAR ENERGY SER ICES. INC.
PAGR 10 OF 38 e
2.
The couplant shall be supplied in clean containers of sufficient quantity to
/~5i~"
perform the examination.
+
i 3.
The couplant shall _be applied inanually with a brusn or other suitable device.
4.
The examiner shall be responsible for removing couplant frorn the examination surface at the conclusion of the examination, when required.
5.4 SURFACE PREPARATION All examination surfaces shall be clean and free of dirt, weld spatter, etc., or 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 wqld maps in the Program Plan Book.
5.6 DATUM POINT 1.
The examiner shall verify that there has been marked a referenceldatum point on each weld trom which all examination data and reportdd:
(
)
indications shall be referenced.
2.
Datum points shall be' marked by the us'e pf low stress stamps or vibratooling and shall not be deeper than 1/32".
3.
The datum point for all safe er.d/transitica piece welds in horizontal lines shall be located on. the top of the pipe.at weld centerli6e.
s 4.
Closure Head nozzle to flange vceld datum points shall ne on' the weld centerline at Closure Head'00 s
Each weld daum point, along.with respective weld reference points and 5.
t divisions, shall be shown on each examination report.
~
l
- 6. EQUIPMENT REQUIREMENTS l
l 6.1 EXAMINATION CONTRACTOR'S EQUIPMENT The following test equipment, or its equivalent, shall -be: provided by the Examination Contractor (as a minimum) for examination of welds specified in this procedure.
~
1.
Pulse echo ultrasonic instrumsnts.
l I
2.
Search Units,1/4" thru Isl/8" dia., 2.25 MHz,00 3.
Search Units,1/4" thru l-1/8" dia., 5.0 MHz 00 Y
FORT 418 NES 205 2/80
=
DOCUMENT NO.
80A0475 my PAGE 11 OF 39 NUCLEAR ENERGY SERVICES, INC.
l l
4.
Search Units,2.25 MHz (all sizes) for angle beam wedges 5
5.
Wedges: Assorted sizes to accomodate search units 6.
Any additional angle wedges to aid in examination or evaluation 7.
Couplant 8.
450 Dual refracted longitudinal wave for use on material >.750" in thickness, when required 9.
Miniature angle beam verification block 10.
Thermometer 6.2 PLANT OWNER'S EQUIPMENT The Plant Owner, or his Agent, shall provide the following service facilities and equipment as required:
1.
Scaffolding 2.
Water, air, and electricity j
g 3.
Temporary lighting 4.
Crane or lif ting devices 5.
Calibration Block No. STEAM 6.
Calibration Block No. JPI 7.
Calibration Block No. CRD I
8.
Calibration Block No. AP 9.
Calibration Diock No. VENT 10.
Cal;bratien Block No. Later (feedwater) 11.
Calibration Blocks Nos. CS-1-1B, CS-1-1 A, CS-2-A and CS-2-B 12.
Calibration Block No. RC IN 13.
Calibration Block No. RC OUT 14.
Test Surface Preparation (cleaning and finishing) 15.
Drawings of each Examination Area 16.
Post-examination cleanup of Test Area v
FORM #NES 205 2/80
DOCUMENT NO.
80A0475 PAGE 12 op 38 NUCLEAR ENERGY SERVICES. INC.
O
' 3\\
- 7. CALIBRATION REQUIREMENTS 7.1 CALIBRATION DATA SHEETS Calibration Data Sheets shall be numbered 475-1, 475-2, 475-3, etc., and shall be signed by the examiner (s) upon completion noting applicable SNT-TC-1 A levels.
7.2 CALIBRATION BLOCKS 1.
The miniature angle beam calibration block designated in 6.1(9) shall be used to establish horizontallinear instrument range.
{
2.
The calibration blocks designated in 6.2 (5) through (13) shall be used for establishing reference sensitivity levels for examination of the specified
- welds, i
3.
Spot thickness checks of the components shall be made prior to preservice l
ext _minations to ensure that the proper calibration block is used.
4.
The identity of the calibration block used for performing calibration shall be recorded on each Calibration Data Sheet.
5.
System calibration shall be performed using the material side which j
corresponds to the material which will be examined; i.e., carbon and
}
carbon; stainless and stainless; of the calibration block, f
6.
The temperature of the calibration block shall be within 250F cf the component temperature. Calibration block and component temperatures shall be recceded on the Calibration Data Sheet.
7.3 REFERENCE SENSITIVITY LEVEL 1.
The reference sensitivi'.y level shn11 be the distanceamplitude curve I
ir.itially obtained directly from the calibration block and shall be the sensitivity level used for evaluating and recording all indi. cations.
j i
2.
Durirg actual weld scanning, the reference sensitivity Iczel shall be a
increased a minimum of 2X (6dB), but not more than 10dB. The actual scan sensitivity shall be recorded on the data sheets.
7.4 TIMES OF CALIBRATION 1.
Basic instrument calibration shall be performed using the appropriate calibration block, search units and instrumentation immediately prior to the examination of the welds specified in this procedure.
2.
h Instrument verticallinearity checks shall be performed at the beginning of each day of examination in accordance with the technique in the procedure referenced in paragraph 2(7) using an angle beam search unit applied to a code calibration block.
V FORM # NES 205 2/80
DOCUMENT NO.
80A0475 11 m
W NUCLEAR ENERGY SERVICES. INC.
O
^\\
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 Level II 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 8.3 and 8.6 of this procedure.
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 plus or minus 20% of that established during basic instrument calibration.
7.5.3 If any point on the Distance Amplitude Correction (DAC) curve is below the 20% limit, the examiner shall:
1.
Mark all Weld Data Sheets since previous calibration " void".
2.
Recalibrate examination system.
{
3.
Reexamine voided areas.
7.5.4 If any point on the DAC curve is above the 20% limit, 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% of the sweep line from its original settings, the examiner shall:
1.
Correct sweep calibration indication data taken since the previous calibration or calibration check and reexamine the applicable area using the corrected sweep.
2.
Void any recorded indication data taken since the previous calibration or calibration check and reexamine the applicable area using the corrected sweep, v
T I
FORM # NES 205 2/80
DOCUMENT NO.
80A0475 1
PAGE 14_O F 38 _
NUCLEAR ENERGY SERVICES. INC.
G 4\\
- 8. EXAMINATION SYSTEM CALIBRATION 8.1 STRAIGIIT BEAM CALIBRATION I'OR BASE MATERIAL Straight beam calibration for all base materisl through which the angle beams will pass shall be performed at a sensitivity level which gives an initial back reflection signal amplitude from the component safe ends of at least 80% FSil.
8.2 STRAIGIIT BEAM CALIBRATION FOR WRV Straight beam sweep calibration and Distance-Amplitude Correction shall be performed as follows for each type of material which will be examined; i.e.,
carbon and carbon; stainless and stainless on the Safe end calibration block.
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 f
on the Calibration Data Sheet.
2.
Position search unit to obtain maximum response from the side drilled f'
(1/4T if T > 1" or 1/2T if T < 1") calibration hole. Adjust sensitivity control i
i to provide a signal amplitude of 80% of FSII and mark location and j
amplitude on CRT screen.
3.
This is the reference sensitivity level.
Record all sensitivity control settings on the appropriate Calibration Data Sheet.
j 4.
This completes calibration for thicknesses < 1". No DAC is necessary.
i 5.
For weld thickricsses > 1" DAC curve shall be established as follows:
A, Without changing the sensitivity obtained in (2) above, position the scarch unit fcr maximum response from the 3/4T hole and mark amplitude on the CRT screen.
B.
Plot a DAC curve by connecting the two signal response positions j
with a continuous line extending over the full examination range.
6.
Upon completion of calibrativn, ensure that all data and instrument settings are recorded on the Calibration Data Sheet. The examiner (s) shall sign the l
completed data sheet, noting applicable SNT-TC-1 A levels.
l l
l 7.
Repeat steps (1) thru (6) for each different weld thickness just prior to I
examination.
(v
\\
I FORM 2 NES 205 2/80
DOCUMENT NO.
80A0475 11 NUCLEAR ENERGY SERVICES, INC.
p V
3.3 STRAIGHT BEAM CALIBRATION CHECK Straight beam calibration check as required by paragraph 7.4.3 shall be performed as follows:
1.
Position the search unit on the material side, i.e., carbon or stainless and adjust the sensitivity control settings to match those recorded in paragraph 8.2(6).
2.
Reposition search unit at each respective test hole and observe maximum signal response amplitudes, and horizontal screen positions.
3.
Position the search unit on the other material side of the safe end calibration block and repeat step (2).
4.
See Section 7.5 for signal response requirements during calibration check.
8.4 ANGLE BEAM CALIBRATION NOZZLE SIDE EX AMINATIONS (Where ID conditions have no stainless steel cladding the technique outlined in Section 8.5 shall be utilized.)
C
'v 1.
Adjust the instrument sweep and delay controls so that the entire calibration presentation for 1/2 vee path is displayed on the CRT (see Figure 10 for the appropriate metal path calibration).
2.
From the OD surface of the calibration block, position the search unit to obtain maximum response from the hole which gives the highest amplitude signal. Adjust the sensitivity control to provide a signal amplitude of 80% full screen hei ht (FSH) and mark location d
and amplitude peak on CRT.
3.
Without changing sensitivity, position the scarch unit respectively on the remaining hole and mark signal location and amplitude on the CRT.
4.
Plot a DAC curve connecting the locations marked on the CRT 'vith a continuous line extended to cover the full examination range (OD to ID).
i 5.
Repeat steps I through 4 for each different weld thickness just prior j
to examination.
v FORM # NES 205 2/80
DOCUMENT NO.
80A0475 16 PAGE OF 38-NUCLEAR ENERGY SERVICES. INC.
/5\\
g 6.
Record all data and instrument settings on the Calibration Data Sheet and sign upon completion, noting applicable SNT-TC-1 A certification level (s).
8.5 ANGLE BEAM CALIBRATION SAFE END SIDE EXAMINATIONS (Where ID conditions have stainless steel cladding, the technique outlined in Section 8.4 shall be utilized.)
1.
Adjust the instrument sweep and delay controls so that the entire
'l calibration presentation for one full vee path is displayed on the CRT (see Figure 10 for the appropriate metal calibration).
l 2.
From the OD surface of the calibration block, position the search unit to l
obtain maximum response from the hole which gives the highest amplitude signal. Adjust the sensitivity control to provide a signal amplitude of 80%
FSH and mark location and amplitude peak on CRT.
3.
Without changing sensitivity, position the search unit respectively on the remaining holes and mark signal location and amplitude on the CRT.
4.
Plot a DAC curve connecting the locations marked on the CRT with a continuous line extended to cover the full examination range. (OD to ID to e
OD) 5.
Repeat steps 1 through 4 for each different weld thickness just prior to examination.
6.
Record all data and instrument settings on the Calibration Data Sheet and sign upon completion, noting applicable SNT-TC-1 A certification level (s).
8.6 ANGLE BEAM CALIBRATION CHECK Angle beam calibration check as required by paragraph 7.4.3 shall be performed as fcilows:
1.
Adjust the sensitivity control settings to match those recorded for the calibrated reference sensitivity.
I 2.
Reposition search unit at each respective test hole and observe signal response amplitudes and horizontal screen positions.
3.
See Section 7.5 for signal response requirements during' calibration check.
y O
FORM 2 NES 205 2/90
DOCUMENT NO.
80A0475 mr 1
NUCLEAR ENERGY SERVICES, INC.
O A
- 9. EXAMINATION PROCEDURES 9.1 STRAIGHT BEAM EXAMINATION FOR BASE MATERIAL Straight beam examinations to detect laminar reflectors which might affect the interpretation of angle beam results shall be performed at a sensitivity level giving a back reflection from the component of at least 80% FSII as nc((d in Section 8.1.
9.2 STRAIGHT AND ANGLE BEAM EXAMINATION OF WRV 9.2.1 All straight and angle beam examination of weld and required volume shall be performed at a scanning sensitivity level, a minimum of 2X (6dB) but no more than 10dB greater than the calibrated reference sensitivity level. All scanning sensitivity levels shall be recorded on the Examination Data Sheets.
9.2.2 For straight beam examinations, a rectilinear scan pattern shall be used.
9.2.3 For angle beam examinations, the search unit shall be swivelled to ensure maximum coverage as it is moved along a rectilinear scan pattern.
Ob 9.2.4 For the location and numbers of the welds, refer to the Program Plan.
Examinations shall not be considered complete until all recordable indications have been evaluated.
- 10. EVALUATION CRITERIA 10.1 RECORDING OF INDICATIONS 10.1.1 For straight beam examinations of base metal for laminations, all areas presenting 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 weld and required volume.
i 1.
Each recorded area shall be identified as to distance from surface, length and position relative to the weld datum point.
2.
Pertinent recorded data shall be taken on each parallel scan pass at increments not to exceed that permitted by the 25% overlap of transducer element (width).
l (v?
)
l FORM 2 NES 205 2/80
DOCUMENT NO.
80A0475 18 38 PAGE OF NUCLEAR ENERGY SERVICES. INC.
C
./S\\
v 10.1.2 For straight baam examinations of weld and required volume, and angle beam examinations, all nongeometric indications showing a signal amplitude response equal to or greater than 50% of the reference response shall be recorded on the appropriate data sheet at the time of weld examination.
I 1.
Each recorded nongeometric indication shall be identified as to depth, distance from surface, 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).
4 3.
The end points of recorded indications shall be determined by 50%
DAC amplitude points.
4.
Planar indications at or near the far surface shall be compared directly with the amplitude obtained from the notch if available.
10.1.3 Geometric indications shall be recorded at one location and noted as geometric caused by thickness change, ID geometry, etc.
l 10.1.4 Nongeometric Indications for straight beam examinations of weld and required volume and angle beam examinations, all indications showing a signal amplitude response equal to or greater than 50% of the reference response shall be recorded on the appropriate data sheet at the time of examinations.
4 10.1.5 Each recorded indication shall be identified ~ as to depth, length, signal amplitude, and location relative to the weld datum point.
10.1.6 Indication: from all welds shall be recorded in inches upstream or downstream in relation to the flow from the weld center line, and iii inches CW or CCW from the datum point.
)
10.2 EVALUATION OF INDICATIONS 10.2.1 Evaluation of all indications shall be made at the reference sensitivity level and in accordance with the requirements of the referenced ASME Boiler and Pressure Vessel Code,Section XI, IS-300. All evaluations shall be performed by a Level II or Level III examiner.
10.2.2 Results of this evaluation shall be reported to the Plant Owner, or his l
Agent, in accordance with the requirements of the ASME Boiler and l
Pressure Vessel Code,Section XI, IS-600. Disposition of evaluation results shall be made in accordance with the Owner's Plant Procedures.
p t
Y FORM # NES 205 2/80
DOCUMENT NO.
80A0475 PAGE 19 OF 38 NUCLEAR ENERGY SERVICES, INC.
o s
- 11. EXAMINATION RECORDS 11.1 CERTIFICATION OF RECORDS The Examiner shall complete and sign all data sheets immediately upon completion of each weld examination. The data sheets may be reviewed by the authorized Code Inspector.
11.2 FILING OF RECORDS NES shall be responsible for 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-1A.
11.3 PROCEDURE CORRECTIONS 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 QA Program Plan 80A0448.
AV 11.3.2 The Examiner shall contact LILCO representatives on site to initiate all changes.
All changes shall be documented in the record of revisions section of this procedure.
l l
D)
L 1
FORM # NES 205 2/80
DOCUMENT NO.
80A0475 20 30 PAGE OF NUCLEAR ENERGY SERVICES, INC.
{
()
LEGEND
_L Perpendicular to Weld
= Parallel to Weld
- Base Material 7_L WRV Weld and Required Volume As Far As Geometry-=.
Permits I n W + 6"
=
e 2" %
W
- 2 " -.
41 3
/
(\\.l 45 L J
1.78" p
U 0 WRV p
O WRV 0
- 0
- 4p =
45
=
p
\\
//!
\\
l u
Carbon Steel 21" 1D Transition Piece Carbon Steel A-508 CL 1 Nozr.le A-508 CL 1 24-9/16" OD Figure 1 - Ultrasonic Examination Procedures for Main Steam (N3) Nozzle to Transition Piece Welds. Cal. Block " Steam" l
v i
FORM # NES 205 2/80
DOCUMENT NO.
80A0475 21 38 PAGE OF NUCLEAR ENERGY SERVICES, INC.
.h\\.7 LEGEND Calibrated L Perpendicular to Weld On SS Side of
= Parallel to Weld n3 pin
=
side of "JPl"
- Use calibration on 53 side of JPI to scan from opposite side use scan path required to inspect entire weld to the root.
m W + 3" -_
e W + 1"**
W + 3" Stainless Steel SafeendA-182 tpk
. in g M in,,,
304
\\
l l
\\
l U
[j
(
.813" f
_L45 o,
45 _L RV 0**
o#
5S"l k
{
o
~45
=
//A a
5/16" Carbon Cladding 3-3/16" 1D Steel Nozzle A-508 CL 2 5-7/16" OD Figure 2 - Ultrasonic Examination Procedures for Jet Pump Instrumentation (N8) Nozzle to Safeend Welds, Cal. Block "JPl" FORM # NES 205 2/80
DOCUMENT NO.
80A0475 PAGE 22 op 38 NUCLEAR ENERGY SERVICES. INC.
L
- 7 LEGEND
_L Perpendicular to Weld
= Parallel to Weld se hterial
=- Calibrated on Cladded CS Side
{
WRV Weld and Required Volume Calibrated on Inconel Side e
of "CRD" W + 3" r
W+1"**q
.e-Inconel Cap 3"
t
+-1"-*
- - l'4+W
+
O 4'e "WRV 4s.1.
_L 45 o*
0
.75" 0
- 0 WRV o
4S "l
\\
45
=
/ //A
/
/
t
/
Carbon Steel 3-7/8" ID Nozzle A-508 CL 2
\\
5-3/8" OD
- Use calibration on inconel side of CRD to scan from opposite side.
Use scan path required to inspect entire weld to the root.
(
Figure 3 - Ultrasonic Examination Procedures for Control Rod Drive (N9) Nozzle to Cap Weld. Cal. Block "CRD" O
V FORM # NES 205 2/80
DOCUMENT NO.
80A0475 11 Aur 38 PAGE_ 23 OF NUCLEAR ENERGY SERVICES, INC.
O A
LEGEND
_L Perpendicular to Weld
= Parallel to Weld
- Base Material WRV Weld and Required Volume Vessel Wall M
N W + 1" u
/
"+1" i
+1/ 2bW
+ 1/2b
.28" 7
F l
45 L do 451 o
0
- way o way 0
- O j
N 45
/ 45
=
=
Stainless Steel Safeend A-182 TP 304 1-15/I6 1D 2.5" oD Figure 4 - Ultrasonic Examination Procedures for Pressure Differential (N10) Nozzle to Safeend Weld.
Cal. Block "
P" 1
O FORM # NES 205 2/80
DOCUMENT NO.
80A0475 PAGE -- "
NUCLEAR ENERGY SERVICES, INC.
o u
LEGEND L Perpendicular to Weld
= Parallel to Weld
\\
l l
\\
I
- 0 WRV 35
=
5 Examine As
/
/
Far As Geometry
[,
~
Permits WRV 39
=
- 1. 28" r 3-11/16 ID 6-1/4" OD
=
4 I
/
w
/
N Closure Head Carbon Steel Nozzle A-508 CL 2 Figure 5 - Ultrasonic Examination Procedures for Closure Head Vent (N7)
Cal. Block " VENT" FORM # NES 205 2/80
DOCUMENT NO.
80A0475 PAGE 25 Of #
NUCLEAR ENERGY SERVICES. INC.
o u
LEGEND
_l. Perpendicular to Weld
= Parallel to Weld
- Base Material
{ WRV Weld and Required Volume e A-508 CL 2 Flang/
Ii l
/
l l
l l
0
=WRV 35
=
Examine as Far As Geometry Permits 45 O
=- 0 WRv 35
=
e 1. 69'L.
5-5/8" 1D 9" OD Closure Head
/
Nozzle A-508 CL 2 l
1 l
Figure 6 - Ultrasonic Examination Trocedures for Closure Head Instrumentation j
Cal. Block " VENT" l O 1
l l
l l
FORM #NES 205 2/80
DOCUMENT NO, 80A0475 i
my 11
)
26 M
PAGE
_ OF NUCLEAR ENERGY SERVICES, INC.
G SCAN LEGEND
_[,
Perpendicular to Weld
==
Parallel to Weld Base Material WRV Weld and Required Volume Examine as far as Geometry Permits i
1.02 W
l.02 1.02 W
l.02 C
NW W/V
// /
I 45 d. WRV=
1.02" WRV=
.l.
- 0*
',/
r 45 0**
Safe ends A-508 CL1 Note:
Jue to Configuration of Safe end extend scan path as far as geometry permits i
FIGURE 7.
ULTRASONIC EXAMINATION PROCEDURE FOR FEEDWATER (N4) NOZZLE TO SAFE END i
l WELDS. CAL BLOCK 131C8523 (FEEDWATER) l I.
/3
!4 l
FORM # NES 205 2/80
DCCUMENT NO.
8 nan 475 1
PAGE 27 _op 38
)
NUCLEAR ENERGY SERVICES, INC.
h
'7.N Calibrated on SS Side of RC-IN
=
Calibrated on Cladded CS Side of ".C-IN Carbon Steel W + 4"
-l Nozzle
=
+ W + 11"**>=
4 l
i an SS Safeend Piece
~1"
_W 1"
f
'/
/
Ik t
5 1 /
b 45 Y
h
[
0 5
OSTRV Oo*
1.2" 0
0*
45,=
/,4po =
/
14-3/8" oo 1 Perpendicular to Weld
~
= Parallel to Weld 00 Base Faterial WRV Weld and Required Volume Use calibration on SS side of RC-IN to scan from opposite side. Use scan path required to inspect entire weld to the root.
Figure 8 Ultrasonic Examination Procedure for Recirculation Inlet Nozzle Safeend Weld (Cal. Block RC-IN).
l I
FORM = NES 205 2/80
DOCUMENT NO.
80A0476 28 33 PAGE OF NUCLEAR ENERGY SERVICES, INC.
IEGEND
/.
("
.L Perpendicular to Weld 7
Parallel to Weld
=
- 00 Base t'aterial WRV Weld and Required Volume
Calibratec cn Cladded SS Side
=
of RC-OUT
+ Calibrated on Cladded SS Sichof RC-OUT Carbon Steel W + 6" Nozzle' 6"
+
Stainless Steel
/
2" _ W 2"
I i
L
,/
/
/
1.844" g
3 0 WRV 00 00*
45 0
45
/ 45
=
=
0*
///l l
\\
t.
///o a
29-1/16" OD 25-3/8" ID Figure 9 Ultrasonic Examination Procedures for Recirculation Outlet Nozzle Safeend Welds (Cal. Block RC-0UT) 8 l
FORM NES205 2/80
DOCUMENT NO.
80R0475 29 OF NUCLEAR ENERGY SERVICES. INC.
?
/ _..
Calibrate on CS-1-1B***
(Inconel) x Calibrate on CS-1-1A CS-2-19 x
on CS-2-B***
Core Spray fe Ed Core Spray Core Spray
(--
W4 125"->
Nozzl Transition 3 + 2" W + 3.r" 3 5" W +.7514
) 1.25 W
- 1. 25" c g
e-2'! -->
eW ->
e
/
\\
7k 81 4501v v
i >g1 N
g= \\
og8Y 0
45 t h 450.L o=
l a
=
sss s LEGEND Nozzle Cladded
.L = Perpendicular to Weld
== Parallel to Weld 0
- =
0 Base Metal Use CS-1-1B Calibration to scan
=
weld from opposite Side. Use Scan Path required to inspect entire weld to the root
- =
Use CS-2-B Calibration to Scan Weld from opposite Side. Use Scan Path required to inspect entire weld to i
the root.
WRV Weld Required Volume
=
FIGURE 10.
ULTRASONIC EXAMINATION PROCEDURE FDR CORE SPRAY SAFE END WELDS (CAL. BIDCK CS-1-1A, CS-1-1B, CS-2-A, CS-2-B) l I
FORM #NES 205 2/80
DOCUMENT NO.
80A0475 my PAGE 30 OF 38 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" O
5.0 "
> 0.8"
_< l.7"
> 0.6"
_< l.2"
> 0.4"
_< 0.8" v
10.0 "
> 1. 7" - < 3.5"
> 1.2" - < 2.5"
> 0.8" - < l.6" 20.0 "
> 3.5"
_< 7.0"
> 2.5"
_< 5.0"
> 1.6"
_< 3.3" 1/2 VEE SCAN PATH EXAMINATION Metal Path Calibration Material Thickness Range Recommended 45 60 70 2.5 "
< l.7"
< l.2"
< 0.8" 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"
> 3.0" - < 10.0"
> 3.3" - < 6.6" i
INSTRUCTIONS: The Vee Path and the examination angle are given in the specific procedure.
Using the appropriate Vee Path Examination Cha.t (1/2 Vee, Full Vee, end 1-1/2 Vee Paths) and the appropriate examination angle column, find the thickness g
range that encompasses the thickness of the material being examined.
FIGURE 11
[4\\
FORM # NES 205 2/80
DOCUMENT NO.
80A0475 PAGE 31 OF 38 NUCLEAR ENERGY SERVICES. INC.
g ANGLE BEAM VERIFICATION BLOCK
[
)
100%
R-1 R-2
/N jl l
90 s '1 in.
80 s
30 \\
45
/
00
\\
600 70 I
2 in. N N
60 i
O N
s 60 700 N
50 40 1
30 20 1
m 10 1
2 3 4 5
6 7 8 9
10 METAL PATH CALIBRATION FOR A 2.5" CRT PRESENTATION 1-Obtain a maximized indication from the short radius (R-1) reflection surface of the
" Miniature Angle Beam Verification Block" (l" metal path).
2-Using the material calibration control and the delay control, align this signal at CRT position 4.
3-Revolve the search unit around and obtain a maximized indication from the long radius (R-2) reflection surface (2" metal path).
4-Using the material calibration control align this signal at CRT position 8.
5-Repeat steps 1 through 4 until no further adjustments need to be accomplished.
6-The CRT is now calibrated in inches of metal path, (cach major division equaling 1/4 inch). Make no further adjustments to the sweep range or delay controls.
O i
Figure 12
DOCUMENT NO.
80A0479 PAGE 32 OF
-3R NUCLEAR ENERGY SERVICES, INC.
ANGLE BEAM VERIFICATION BLOCK
[
}
R-2 100%
R-1 1
^
11 1
90
'l in.
3 N 80 0
N45 60 70 I
\\
N 60 I
l 0
2 in.
N, N
I 60o N,
50 70 40 30 1
20 10 l
1 2 3 4 5
e i
8 9
10 METAL PATH CALIBRATION 5" CRT PRESENTATION 1-Obtain a maximized indication from the short radius (R-1) reflection surface of the
" Miniature Angle Beam Verification Block" (l" metal path).
2-Using the material calibration control and the delay control, align this signal at CRT position 2.
3-Increase the instrument gain until a secondary echo occurs.
4-Align the secondary signal at CRT position 8.
5-For reference check the primary signal from the long radius (2").
This signal should peak at CRT position 4.
6-The CRT is now calibrated in inches of metal path, (each major division equaling 1/2 inch). Make no further adjustments to the sweep range or delay controls.
1
. O l
l l
Figure 13 l
I
DOCUMENT NO.
Snanh7s 33 38 PAGE OF NUCLEAR ENERGY SERVICES, INC.
ANGLE BEAM VERIFICATION BLOCK
[
)
R-1 R-2 100%
l
/\\
ll 1
90 s
/ /
80
/ 1 in.00 30 N45 60 70 l
4 60 l
l 0
2 in.
g g
60 N
50 l
I 70 3
I I
20 h
5 10 1
i i
t 1
2 3 4 5 6 7
8 9
10
_Mr.TAL PATH CALIBRATION 10" PRESENTATION.
1 - Obtain a maximized indication from the long radius (R-2) reflection surface of the
" Miniature Angle Beam Verification Block" (2" metal path).
2 - Using the material calibration control and the delay control, align this signal at CRT position 2.
O)
,'I - Increase the instrument gain until secondary echos occur.
4 - Align the secondary echos shall be aligned at CRT positions 5 and 8.
5 - The CRT is now calibrated in inches of metal path (each major division equaling 1 inch). Make no further adjustments to the sweep range or delay controls.
O Figure 14 FORM CNFA 205 2/A0
DOCUMENT NO.
80A0475 34 38 PAGE OF NUCLEAR ENERGY SERVICES. INC.
l
)
ANGLE BEAM VERIFICATION BLOCK
[
)
R-2 100%
R-1 I
p '\\
ll I
90 e
y 1 in.
300N 45o 80 0
N 60o 70
[
60 l
0 2 in.
/
N 50 60 70 40 30 20 l
l 10 1
2 3 4 5
6 7 8
9 10 METAL PATH CALIBRATIOM FOR A 20" CRT PRESENTATION 1-Obtain a maximized indication from the long radius (R-2) reflection surface of the
" Miniature Angle Beam Verification Block" (2" metal path).
2-Using the material calbiration control and the delay control, align this signal at 4
g CRT position 1.
3-Increase the instrument gain until secondary echos occur.
4-Secondary echos shall be aligned at CRT position 2.5 and 4.
5-The CRT is now calibrated in inches of metal path (each major division equaling 2 inches). Make no further adjustments to the sweep range or delay controls.
I Figure 15
DOCUMENT NO:
80A0475 Plant / Unit FIGURE 16 Page 35 of 38 Comp / System CAL 1BRATION DATA SHEET Data Sheet No.
ISO Loop Procedure No.
Subject:
Rev/ Change No.
TNSTRINENT RETTTMC9
<FARen TNTT Calibration Mfg /Model No.*
Scan Ancle!
Mode:
Block No.
Fabrication No.
Fixturine (if anv):
Serial No.
Surface
[F Sweep Leneth :
Style or Tyne Nn-Block Temp Comp. Temp Sweep Delay :
Size & Shnner Thickness Pulse Lencth/Damoinc:
Freannncv CRT Calibrated in Fren.:
Rep. Rate!
Sorin 1 Nn/Rennd?
Each Maj. Screen Div=
Filter:
Video:
Jack; binasured Anclo nFCICato Sufreh Rnneer nah1o..T no K ton,th-Mode Select Reiect?
rnun1nne nenna.
Cnin (cnnveni.
(finni.
Couolant Ratch?
DAC PLOT 0 WRV sc,n s o n e < e isr4 *,..
1007 INSTR. LINEARITY CAL.
O W e '1 Amnlitude 70
== To Weld High Low Hich Low 1 To Weld 1
6 40 g,,43,,,,n,
( ) 2 6
30 3
7 20 Ay4,1 10 4
8 ltii lll l ti 111 1tll llll ll l11 ll l Circ 0
1 2 3 4 5 6 7 8 9 10 AMPT CO* TROT. T.T?"FAR TTY Initial dB Result Recordable EXAMINATION Indications COMMENTS / REASON FOR 80
-6 WELD / AREA Yes No l Geom INCOMPLETED SCAN (S) 80
-12 cqygy g--
ggg y 40
-4
~ ' '
~
20
+12 i
9i
! /' "U "W
AhfO 1 AILII Atj
.-e
=%<
wr a i %a yy3 33 V l 3 i
qui RE I HE SAP, iE CALIBRATION CHECKS TIME Initial Cal.
,I h.l.C A D (4 A rin A f A r9 r A AAFmea me -
v3g yin i im n gg c",
f g y y g g g,
Intermediate Intermediate Intermediate EXAMINERS 1 Date
, Level l
Final Cal.
2 Date Level l
l ADDITIONAL SHEETS? CHECK BOX REVIEWERS 1 Date Continuation Renn Pine 2
Date sunnlomonts Nnno 3
Date
~
NUCLEAR ENERGY SERVICES, INC.
NUCLEAR ENERGY SERVICES, INC.
Project No.
Site L Location Cate: (Day /Mo/Yr)
W Location Page of Y
Item Identification o
- w *L l
___J 4
Examiner: TC-1A Level Angle 0
45 _L 45_
Attached Cal. Data Sheet J
\\ :
o o
o p/f'
""d Thickness h'
Examiner: TC-1A Level scanning
~
I Diameter (nom.)
.,w g MP Metal Path W max Distance from ( to S.U. at maximum respons,a.
RBR Remaining Back Reflection W
L Distance from Datum 0 Distance from weld ( at 50% of DAC (fud) rti-
~ * ' * " '
Distancefromweld{at 50% of.DAC (backward) i, j
W i
l Ind.
FyrD BACKWARD L
L RBR S.U.
2 W
MAX 567 DAC 50%
],
(
W MP W
MP W
MP 50%
max 50%
amp Loc.
C-2 y
2 No.
SAMPLE ONI y l
SIMII ? -
2,'"
vVHICH o,-
8\\'VU:i. L iNI Or?'
. r' LADLE.
DRAW FULL SCALE PLOT HERE:
REVIEWER DATE REVIEWER DATE REVIEJER DATE FIGLTE 17 PAGE 36 of 38
~~ -
~
DOCUMENT NO.
80A0475 m
PAGE 37 op 38 NUCLEAR ENERGY SERVICES. INC.
l l
TECHNIQUE SHEET FOR RECIRCULATION OUTI.ET ANGLE BEAM EXAMINATION (from the stainless steel side including the weld) 1)
The examination shall be conducted with a longitudinal unit exhibiting a 1.0 MHz nominal frequency.
2)
The surface of the lucite wedge shall be contoured to the outside radius of the component being examined. (This is to enhance the percentage of sound induced into the material and increase the signal to noise ratio.)
3)
Due to the curved lucite wedge design all angles will be measured directly from the components designated calibration standard.
4)
The calibration shall be conducted utilizing the technique referenced in Section 8.4 of Document 80A0475.
5)
Scanning sensitivity will be 6db above reference.
6)
All indications noted within the material shall utilize the typical recording levels noted in Document 80A0475.
q g
7)
Due to the lower sensitivity of the notch response in relation to the DAC curve when examining with refracted longitudinal techniques, all indications found at the ID will be recorded at 50% of the notch response. This will enchance a mote conservative examination.
f.
Figure 18
/7 l
h FORM # NES 205 2/80
l o
DOCUMENT NO.
80A0475 PAGE 38 op 38 NUCLEAR ENER3Y SERVICES. INb.
f
- ~
\\
TECHNIQUE SHEET FOR FEE 0 WATER SAFE-ENDS 1)
Axial Scans _.i_
A 600 angle beam shear wave technique, either full vee or half vee' calibration shall be used for examination areas mask.ed by excessive excavations.
2)
Circumferential Scans =
A 550 angle beam hear wave technrue, either full vee E half vee calibration, i
shall be used for examination areas masked by excessive excavations.
I h
1..
.h A
or Figure 19 f7\\
l k
l FORM # NES 205 2/80
- -..