ML20039D590
| ML20039D590 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/03/1981 |
| From: | Laguardia T, Schoner F LONG ISLAND LIGHTING CO., NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20039D584 | List: |
| References | |
| 80A0469, 80A469, NUDOCS 8201050236 | |
| Download: ML20039D590 (21) | |
Text
\\
PF,0CEDURE NO.
80A0469 SL'BJECT: MANUAL N0ZZLE WELDS PAGE 1
0 F,21_
MANUAL. ULTRASONIC EXAMINATION PROCEDURES FOR CLOSURE HEAD AND VESSEL N0ZZLE WELDS LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWER STATION CONTROLLED COPY VALD ONLY IF Tils STAMP E RED Prep'd by 8v IO-4-77 Date NES IO~l9 ~ll Project Mr' Date
/i g
/O.jp. q NES i
REV. NO.
DATE Mgr IS Level i Date 0
10/20/77 N E.e, pyq,,77 e
1 12-19-78 2
5/21/79 QA Mgr.
Date LILCO 7.Y.$ 4 vm 4/4 /7g 3
6/28/79 Date 4
12/3/81 Date 8201050236 811224 8
DR ADOCK 05000 h NUCLEAR ENERGY SERVICES, INC.
L
f
^
Procedure No.
80A0469
Subject:
Manual Nozzle Welds Page 2
of 2_1 RECORD OF REVISIONS Rw.
Date Description Reason Prepared Approved No.
by by 1
12/19/
2.1 Code References LILCO and NRC com-V. Pranitis 78 ments ug g S
O 8.4 and 8.5 change from 1/2 vee to Full Vee figures 1 and h
2, scan paths.
2 5/21/79 Changed couplant req.
LILCO comments F. Carr Clarified use of 1/2 vee vs. full vee exam. techniques 3
6/28/79 Clarified Calibration LILCO comments F. Carr Ylh Instructions, etc.
CR9 930 hA 4
12/3/81 General Procedure Update Practicality and S. Larson
. pg_g clarification a
i l
- +. NUCLEAR ENERGY SERVICES, INC.
DOCUMENT NO.
80A0469 M
=
NUCLEAR ENERGY SERVICES. INC.
MANUAL ULTRASONIC EXAMINATION PROCEDURES FOR CLOSURE HEAD AND VESSEL NOZZLE WELDS 1.0 SCOPE 1.1 AREA OF EXAMINATION This document covers the manual ultrasonic examination procedures for the following Closure Head and Vessel nozzle Welds:
(1)
Head Spray (N6 A), Spare (N6B), and Vent (N7) Nozzle to Closure Head Welds.
(2)
Main Steam (N3) Nozzles to Vessel Welds.
(3)
Control Rod Drive (CRD) Return (N9) Nozzle to Vessel Welds.
(4)
Jet Pump Instrumentation (JP1) (N8) Nozzle to Vessel Welds.
(5)
Feedwater (N4) Nozzle to RPV Weld.
(6)
Recirculation Inlet (N2) Nozzle to RPV Weld.
(7)
Recirculation Outlet (N1) Nozzle to RPV Weld.
(8)
Core Spray (NS) Nozzle to RPV Weld.
1.2 TYPE OF EXAMINATION 1.2.1 Volumetric examination shall be performed using ultrasonic pulse echo nominal 45 angle beam shear wave and 0 straight beam techniques applied to the outside surfaces of the Closure Head and Reactor Pressure Vessel (RPV).
1.2.2 The examination shall be performed manually using contact search units (transducers).
1.3 TIME OF EXAMINATION These procedures shall govern the preservice examination and rexamination of repaired areas of the Closure Head and RPV as required by the ASME Boiler and Pressure Vessel Code,Section XI.
l 1.4 WELD CONFIGURATION 1.4.1 The Closure Head Nozzle Welds have a nominal thickness of 4-1/16"(Minimum thickness of 3-3/16").
FOR.M = NES 205 2/80
DOCUMENT NO.
80A0469 m
11 NUCLEAR ENERGY SERVICES. INC.
1.4.2 The RPV nozzle welds have nominal thicknesses of 5-7/8" (Minimum thickness of 5-3/8") and 6-7/8" (Minimum thickness 6-3/8").
1.4.3 Typical Closure Head and RPV nozzle configurations and g
nominal weld thicknesses are shown in Figures 1 through 3.
1.5 MATERIALS The Closure Head and the RPV nozzles are constructed of low carbon steel. The RPV is cladded with 5/16" stainless steel cladding on the ID surfaces.
2.0 REFERENCES
2.1 REFERENCE DOCUMENTS The following documents form a part of this examination procedure:
(1)
ASME Boiler and Pressure Vessel Code,Section XI, g 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.
(4) 80A9068; NES Procedure for Training and Certification of Nondestructive Examination Personnel (Latest Revision).
(5) 80A9053; NES Procedure for Ultrasonic Instrument Linearity Verification (Latest Revision).
2.2 APPLICABLE DR AWINGS The following drawings are part of this procedure:
(1)
CE Assembly Dwg. E-234-275 -
(2)
CE Assembly Dwg. E-234-245 (3)
CE Assembly Dwg. E-234-470 (4)
CE Assembly Dwg. E-234-229 FORM:NES 205 2/80
DOCUMENT NO.
80A01469 mr PAGE 5
OF 21 NUCLEAR ENERGY SERVICES. INC.
3.0 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 examination coverage is limited by part geometry or access.
4.0 PERSONNEL CERTIFICATION 4.1 PERSONNEL CERTIFICATION REQUIREMENTS 4.1.1 Each person performing ultrasonic examination governed by this procedure shall be certified in accordance with the References 2.1(1), 2.1(3), and 2.1(4).
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 shall have a minimum qualification of LevelI.
4.2 PERSONNEL RECORDS 4.2.1 Records of personnel qualification shall be maintained by Examination Contractor.
4.2.2 A copy of the examiner's certification summary and a current eye test as required by SNT-TC-1A shall be filed with each permanent examination record, with a copy submitted to the Plant O'vner, or his Agent, prior to performing examination per this procedure.
5.0 EXAMINATION REQUIREMENTS 5.1 EXAMINATION FREQUENCY 5.1.1 The nominal examination frequency shall be 2.25MHz for all straight beam and angle beam examinaticas.
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 sheets.
5.2 EXAMINATION ANGLES AND COVERAGE 5.2.1 The intent of this procedure is to provide maximum examination coverage to ensure weld integrity.
Each weld shall be scanned with minimum 25% overlap of the transducer width (diameter) for each scan pass.
FCAM : NES 205 2/80
1 DOCUMENT NO.
80A0M9 m
1 NUCLEAR ENERGY SERVICES, INC.
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 1/2T on eagh side of the weld shall be ultrasonically examined using 45 shear wave angle beam techniques applied in one direction perpendicular to the weld axis and in two directions parallel with the weld axis, on both sides of the weld, except where restricted by part geometry or access.
5.2.4 Straight beam techniques shall be applied, where part geometry permits, to all parent material through which the angle beams will pass during angle beam examinations.
Indications detected are to be recorded in accordance with paragraph 10.1.1 of this procedure.
5.2.5 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 paragraph 10.1.2 of this procedure.
5.2.6 Other angles may be used if required for aid in evaluation of reflectors or to accommodate geometric restrictions and limited access. All information shall be recorded on the data sheets.
5.2.7 Where examination surface, geometry, or other conditions g g (weld, contour, access, etc.) do not permit a meaningful ultrasonic examination to be performed, the examiner shall record the area of nonexamination and the particular interfering condition in the space provided on the Calibration Data Sheet. In addition, he may make a sketch of the weld and adjacent conditions and attach to the Calibration Data Sheet.
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 Typical coverage for the welds specified is shown in Figures 1 through 3.
5.3 LIQUID COUPLANT 5.3.1 The ultrasonic couplant shall be suitable for use on nuclear
'g plant material and be certified to have less than 50 ppm halogen and less than 200 ppm sulfur.
5.3.2 The couplant shall be supplied in clean containers of sufficient quantity to perform the examination.
so:w = NES 205 2/a0
DOCUMENT NO.
80A0469 mr 11 W
NUCLEAR ENERGY SERVICES. INO.
5.3.3 The couplant shall be applied manually with a brush or other suitable device.
5.3.4 The examiner shall be responsible for verifying that the couplant has been removed 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, etc., or any other condition which 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 Each weld shall be located and identified per the appropriate weld map located 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 all examination data and reported indications shall 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 RPV Nozzle to vessel weld datum point shall be at the highest point on the weld centerline.
5.6.4 The Closure Head to N6A and N6B nozzle weld datum points shall be at the highest point of the weld centerline.
5.6.5 The head-centered Vent nozzle to Closure Head weld datum point shall be at 0 orientation of the vessel at the weld centerline.
5.6.6 Each weld datum point along with respective weld reference points and divisions shall be shown on each examination report.
6.0 EQUIPMENT REQUIREMENTS 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 the Closure Head and RPV nozzle welds.
FORM :t4ES 205 2/80
80A0469 DOCUMENT NO.
m 1
NUCLEAR ENERGY SERVICES, INC.
(1)
Pulse Echo Ultrasonic Instrument.
0 (2)
Wedge,45, Refracted Shear Wave.
(3)
Scarch Units,1/2", 3/4", or 1" Dia., 2.25MHz, 0.
(4)
Search Units,1/2" x 1", 2.25MHz.
(5)
Couplant.
6.2 PLANT OWNER'S EQUIPMENT The Plant Owner, or his Agent, shall provide the following service facilities and equipment as required:
(1)
(2)
Water, Air, and Electricity.
(3)
Temporary Lighting.
(4)
Moving or Lif ting Devices.
(5)
Calibration Block No. SNPS-4.
(6)
Calibration Block No. SNPS-6.
(7)
Calibration Block No. SNPS-7-1/4.
l (8)
Test Surface Preparation (cleaning and finishing).
1 (9)
Drawings of Each Examination Area.
(10)
Post-Examination Cleanup of Test Area.
7.0 CALIBRATION REQUIREMENTS l
7.1 CALIBRATION DATA SHEETS Calibration Data Sheets shall be numbered 469-1, 469-2, 469-3, etc.,
and shall be signed by the examiner (s) upon completion.
FORM : NES 205 2/80
DOCUMENT NO.
80A0469 mr 11 m'
NUCLEAR ENERGY SERVICES. INC.
7.2 CALIBR ATION BLOCKS 7.2.1 The calibration blocks designatad in paragraphs 6.2(5), (6), and (7) shall be used for basic instrument calibration and for establishing reference sensitivity levels for examination of the specified welds.
7.2.2 The identity of the calibration block 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 OD surface of the calibration block.
7.2.4 The temperature of the calibration block shall be within 25 F of the component temperature.
Calibration block 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 g
curve initially obtained directly from the calibration block and shall be the sensitivity level used for evaluating and recording all indications.
7.3.2 During actual weld scanning, the reference sensitivity level shall be increased a minimum of 2X (6dB).
7.4 TIMES OF CALIBRATION 7.4.1 Basic instrument calibration shall be performed using the appropriate calibration
- block, search
- units, and instrumentation immediately prior to the examination of the Closure Head and RPV nozzle welds.
7.4.2 Instrument vertical linearity checks shall be performed at the beginning of each day of examination in accordance with the technique in the procedure referenced in paragraph 2.1(5).
7.4.3 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 8.5 of this procedure.
FORM:NES 205 2 23
DOCUMENT NO.
80A0469 1
NUCLEAR 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 plus or minus 20% of that established during basic system calibration.
7.5.3 If any point on the DAC curve has decreased by more than 20% of its amplitude, the examiner shall:
(1)
Mark all weld data sheets void since previous calibration.
(2)
Recalibrate examination system.
(3)
Re-examine 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)
Re-evaluate 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 the sweep calibration and note it on the Calibration Data Sheet.
(2)
Void any data sheets made since the previous calibration which have recorded indications and re-examine those areas.
8.0 EXAMINATION SYSTEM CALIBRATION l
8.1 STRAIGHT BEAM CALIBRATION Straight beam calibration shall be performed as follows:
h (1)
Adjust the instrument sweep controls so that the signal responses from the 1/4T and 3/4T holes occur at the second and sixth horizontal screen positions.
1 FORM:NES 205 2/E0
80A0469 DOCUMENT NO.
my 1
11 OF 21 PAGE NUCLEAR ENERGY SERVICES, INC.
(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.
(3)
Without changing sensitivity, position the search unit respectively on the remaining hules and mark signal amplitudes and locations on the CRT.
(4)
Plot a DAC curve by connecting the locations (Marked on the CRT) with a continuous line extended to cover the full examination range.
(5)
This is the primary reference sensitivity. Record all sensitivity control settings on the appropriate Calibration Data Sheet.
8.2 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 8.1(2).
(2)
Reposition search unit at each respective test hole and observe maximum signal response amplitudes, and horizontal screen positions.
(3)
See Section 7.5 for signal response requir: ments during calibration check.
8.3 ANGLE BEAM CALIBRATION (NOZZLES IN REACTOR SHELL)(1/2 b
VEE TECHNIQUE)
Angle beam calibration shall be performed as follows:
(1)
Adjust the instrument sweep controls so that the signal response from the 1/4T and 3/4T holes occur at the second and fourth horizontal screen positions.
To verify sweep calibration, ensure that response from ID notch appears near the eighth horizontal positions.
(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.
FORM = NES 205 2/83
DOCUMENT NO.
80A0469 nw 1
NUCLEAR ENERGY SERVICES, INC.
(3)
Without changing sensitivity, position search unit respectively on the remaining angle beam calibration holes and mark signal amplitudes and locations on CRT.
(4)
Position search unit for maximum response from the far surface notch and "X" mark the screen and data sheet to indicate amplitude.
(5)
If the instrument is equipped with an Electronic DistanceAmplitude Corrective device, the primary reference response shall be equalized at 80% of FSH over the distance range to be employed in the examination.
(6)
Plot a Distance-Amplitude Correction (DAC) curve by connecting the locations (marked on the CRT) with a continuous line extended to cover the full examination range.
(7)
This is the primary reference sensitivity. Record all sensitivity control settings on the appropriate Calibration Data Sheet.
(8)
Report all data and instrument settings on the Calibration Data Sheets.
8.4 ANGLE BEAM CALIBRATION (NOZZLES IN REACTOR HEAD)
FULL VEE TECHNIQUE Angle beam calibration should be performed as follows:
(1)
Adjust the instrument sweep controls so that the signal response from the 1/4T and 1-3/4T holes occur at the c
first and seventh horizontal screen positions. To verify sweep calibration, ensure that responses from the ID and OD notches appear near the fourth and eighth horizontal positions.
(2)
Position search unit to obtain maximum response from the 3/4T hole. 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.
FORM:NES 205 2/80
DOCUMENT NO.
8nanh60 NUCLEAR ENERGY SERVICES, INC.
1 (4)
Position search unit for maximum response from both the ID and OD surface notches and "X" mark the screen and data sheet to indicate amplitudes.
(5)
If the instrument is equipped with an Electronic Distance-Amplitude Corrective device, the primary reference response shall be equalized at 80% of FSH over the distance range to be employed in the examination.
(6)
Plot a Distance-Amplitude Correction (DAC) curve by connecting the locations (marked on the CRT) with a continuous line extended to cover the full examination range.
(7)
This is the primary reference sensitivity. Record all sensitivity control settings on the appropriate Calibration Data Sheet.
(8)
Report all data and instrument settings on the Calibration Data Sheets.
8.5 ANGLE BEAM CALIBRATION CHECK Angle 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 8.3(2) or 8.4(2) as appropriate.
(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 cheek.
9.0 EXAMINATION PROCEDURES 9.1 EXAMINATION OF BASE MATERIAL FOR LAMINATION 9.1.1 Straight beam examinations to detect laminar reflectors which might affect the interpretation of angle beam results shall be performed as a sensitivity level giving an initial back reflection signal amplitude of 80% FSH.
9.1.2 A rectilinear scan pattern shall be used.
FORM:NES 205 2/80
DOCUMENTNO.
80A0469
" =
NUCLEAR ENERGY SERVICES, INC.
9.1.3 For the location and the numbers of the welds, refer to the Program Plan.
Examination shall not be considered complete :mtil all recordable indications have been evaluated.
9.2 STRAIGHT AND ANGLE BEAM EXAMINATION OF WRV 9.2.1 Straight and angle beam examination of weld and required volume shall be performed at a scanning sensitivity level at least 2X (6dB) greater than the calibrated reference sensitivity level.
9.2.2 For all examinations, a rectilinear scan pattern shall be used.
9.2.3 For angle beam examinations, the search unit shall be swiveled to ensure maximum coverage as it is moved along a rectilinear scan pattern.
9.2.4 For the location and the numbers of the welds, refer to the Program Plan. Examination shall not be considered complete until all recordable indications have been evaluated.
10.0 EVALUATION CRITERIA 10.1 RECORDING OF INDICATIONS 10.1.1 For straight beam examinations of the 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 weld and the required volume.
(1)
Each recorded area shall~ be identified as to distance l
from surface, 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 examinations of the WRV, all indications showing a signal amplitude response equal to or greater than 50% of the reference response shall be recorded on the appropriate i
l data sheet at the time of weld examination.
Planar indications at or near the far surface shall be compared i
directly with the amplitude obtained from the notch.
(1)
Each recorded indication shall be identified as to depth (as a percent of thickness), distance from surface, length, signal amplitude, and location relative to the weld datum point.
FORM :NES 205 2/80
1 DOCUMENT NO.
80A0M9 av 11
=
NUCLEAR ENERGY SERVICES. INC.
(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.
10.1.3 Indication from all nozzle welds shall be reported in inches CW or CCW from datum points when looking at the outside of the vessel, and in inches inboard (toward center of nozzle) or outboard (away from center of nozzle) of the weld centerline.
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, IS-300.
All evaluations shall be performed by a Level II or Level III.
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, 1S-600. Disposition of evaluation results shall be made in accordance with the Owner's Plant Procedures.
11.0 EXAMINATION RECORDS 11.1 CERTIFICATION OF RECORDS The examiner shall complete and sign all data sheets immediately upon the completion of each weld examination. The data sheets may j
be reviewed by the authorized Code Inspector.
j 11.2 FILING OF RECORDS l
The examiner 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 i
test report in accordance with SNT-TC-1A.
(
11.3 PROCEDURE CORRECTIONS AND ADDITIONS l
11.3.1 All procedure corrections and/or additions required during l
i the preservice examinations shall be made in accordance with requirements of NES QA Program Plan # NES 80A0448.
l 11.3.2 The examiner will contact the LILCO representative on site to initiate all such changes.
All changes shall be i
documented in the record ci revisions section of this procedure.
l FCR! = NES 205 2180
DOCUMENT NO.
80A0469 16 NUCLEAR ENERGY SERVICES, INC.
PAGE OF 21 LEGD!D l
Perpendicular to Weld
=
Parallel to Weld 00 Ease Ehterial 5.875" -
3125" Cladding WRV Weld and Required Voltm s
s 00*
45 L
10.5"t (OAE7T s
3" 45 = N NA\\\\\\\\\\\\\\\\\\
be ry pe t
1 1.5" s s s s s -
s s 4 s
f i
TYPICAL N0ZZE CONFIGURATIOtl l
FIGUFE 1 ULTPASONIC EXA?GIATION OF:
1.
CRD Return Nozzle (N9) to Vessel Weld 2.
Fhin Steam Nozzle (N3) to Vessel Weld 3
Core Spray Nozzle (NS) to Vessel Weld 4
Feedwater Nozzle (N4) to 7essel Weld l
l l
A
\\
l ICRM :NES 205 2/80 l
cp o
DOCUMENT NO.
80A0460 NUCLEAR ENERGY SERVICES. INC.
OF N
EGEND L Perpendicular to Weld
=
Parallel to Weld O Base Faterial
@ WRV Weld and Rec,uired Volt =e
~%
00*
%l 1
%0 [_
5 l
12.0" }
NNN
-00 WRVh l
3 5" 45 = N
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i %;e$b AN M:
1 5" g
4 s ss s s s s
//
Tf?ICAL I!OZZE COEIGLETIGI FIGUEE 2 ULT?ASONIC EXA!CIATION OF:
1 1.
EECIPMdTION OIRET NCZZLE (N1) 'IO VESSEL ELD 2.
RECIRCULATION INET NOZZE 'N2) TO ESSEL KELD 3
JET PULT INSTRULEiTATION NOZZE (NS) 'IO VESSEL HELD i
l
(
FCRM :NES 205 2/80 8
M p
my DOCUMENT NO.
80A0460 11 NUCLEAR ENERGY SERVICES. INC.
GE OF 21 l
N Exardne as far as N
gecret"y pernlits N
/
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12" L
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j i
TYPICAL N0ZZIE TO CLOSURE Hr.AD CONFIGU?ATICti LEGEND j__
Ferpendicular to Weld Parallel to Weld
=
Full Vee Technique WRV Weld and Required Volune 0
0 Base Faterial FIGL=E 3 ULTRASONIC EXET!ATION OF:
1.
l'ENT N07.ZIE (N7) TO CLOSURE EAD WELD 2.
EAD SEPAY RID SPARE NOZZIES (N6A AND N63) TO CLOSURE EAD l.' ELDS.
AAA FC:M NES 205 2/80 o
.M D
Plant / Unit Page 19 of 21 Comp / System CALIBRATION DATA SHEET Data Sheet No.
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Block No.
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~~
Intermediate Intermediate EXAMINERS 1 Date Level Final Cal.
Date Level
- ADDITIONAL _ SHEETS? CHECK BOX REVIEWERS 1 Date Continuation !
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Date Sunplements___
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3 Date
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Plant / Unit SCAN DATA SHEET Comp / System CONTINUATION SHEET Procedure No.
80A0! 69 4
Subject FIGUE 5 Pace 20 og 21 Recordable Examination Indication COMMENTS / REASON FOR Ueld/ Area OBSTRUCTIONS Incompleted Scan (s)
YES NO GEOM SA MPLE ONLY SIMILAR VERSIONS WHiCH ndnin.opTMF RAME
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..-i m_ _ A OC A rnFP"ABLE INl-UKt /tM i i six _ru s _
1
- l xaminers 1.
Date Level Additional Sheets?
(Check Box) 2-Date Level Reviewers 1.
Date 2.
Date Continuation 3.
Date Supp1'ements
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NUCLEAR ENERGY SERVICES. INC.
Project No.
Site L Location Date: (Day /Mo/Yr) lTtem Identification location Page
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TC-1A Level Angic 0"
4 5".L 45=
Attached Cal. Data Sheet
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Thickness k
Examiner:
TC-1A Level scanning
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L--
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dn Diameter (nom.]
MP Metal Path W max Distance from ( to S.U. at maximum response.
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IRBR Remaining Back Reflection W
Distance from weld at.50% of DAC (fwd)
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L Distance from Datun 0 W
Distance from weld
,'at 50% of DAC (backward) l l
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L RBR S.U.
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DAC d
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MP W
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max 50%
amp Loc.
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DAC DAC RDIARKS 3
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hi SIMIDW V ERSIONS WHICH
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..REQU IRE THE SAME
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DRAW FULL SCALE PLOT HERE:
9 4 REVIEWER DATE REVIEWER DATE REVIEWER DATE l
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