ML20039B268
| ML20039B268 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 08/21/1981 |
| From: | Carr J, Johnson L, Laguardia T NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20039B264 | List: |
| References | |
| 8040468, NUDOCS 8112220474 | |
| Download: ML20039B268 (18) | |
Text
.__
~
PROCEDURE NO.
80A0475s
SUBJECT:
MANUAL SAFEENF WELDS PAGE 1 0F 30 MANUAL ULTRASONIC EXAMINATION PROCEDURES FOR VESSEL N0ZZLE SAFEENDS AND CLOSURE, HEAD
~
N0ZZLE-FLANGE WELDS LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWER STATION UNIT 1 CONTROLLED 30PY un my ms sa is e Prep'd by v
o NES __
12 11 Project Mgr Date REV. NO.
DATE NES
.7.
d 3/2/7f Mgr. 1S.1 Level i Date
~ f2 0
2-15-78 NES
-2 ISI Pro P
. Level 111 Da t'e NES Z-4-7f 9-Date 2
1/16/81
'I* 5e 4 /~1/78 -
3 2/3/81 LILCO me u Date 4
8/28/01 Date g
s.,
hO O
,f e
g_.._,_ _
PROCEDURE NO.
80A0475
SUBJECT:
MANUAL SAFEEND WELDS PAGE 2 0F l l
l l
Rev.
Prep'd No.
Date Description Reason By
' App'd By NES LILCO 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 C
5.2.7,- 7.3.3, and Figures 2,5, Umf 6, and 7.
Incorporated Field Change I g/7/19 Deleted; 2.3 Added;- 5.1.3 CRA-972 (f/
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 & l.5 Changed to Figures 1 through 7 Para 2.1.3, 2.1.4, 2.1.5, Updated Para 5.2 Revised l Para 6.1 Revised Para 6.2 Added Item 10 Para 7.1 Revised Para 7.2 Added & renumber-ed accord.ingly Section 8, 9, 10 Revised Added Fig. 7 Delete Fig. 9, 10, 11, 12, l
13, 14, & Table 1 Added nes Figs, and numbered accordingly CRA 1670 I
e NUCLEAR ENERGY SERVICES, INC.
Procedure No.
80A0475
Subject:
Manual Saleend Welds Page 3
of 30 FIV.
PRE'D APPROVED NO.
DATE DESCRIPTION REASON BY BY 3
2/3/El Para. 4.1.2 added Customer Comment S.
L.
NES LILCO
... Level I Trainee Foote 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 Para. 6.l(S) 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(1) deleted (as a percent of T)
Para. 10.1.2(41 deleted
... hole representing T Para. 10.1.3 revised Para. 10.1.5 deleted (as a percent of T)
Revised to upstream and downstream NUCLEAR ENERGY SER\\tC IS. INC.
u Proc duro No.
SOA0475 Subjacti:
Minual Safa nd U21ds Peg 2_;
4 of 30 f
Ffl.
P TG ' D APPROVED EO.
DATE DESCRIP* TON RFASON 3Y BY 3
2/3/81 Para.11.1 changed shall Customer Cc==ent S. L.
NES LILCO to =ay Foote Para. 11.2 changed ex=m"ner to NES 4
8/28/
Para. 5.3.4 deleted Where Incorporate all previousa gG 81 required...
field changes G:
7.g/
Deleted para. 7.5.5 Renumbered remainder of section
?evised para. 8.4 Revised para. 10.1.6 Revised Figure 7 Revised Figure 12 Refer to CRA 2086 NUCLEAR ENERGY SERVICES, INC.
L
DOCUMENT NO.
80A0475 11 m
PAGE 5
OF 30 NUCLEAR ENERGY SERVICES. INC.
MANUAL ULTRASONIC EXAMINATION PRCCEDURES FOR VESSEL NOZZLE SAFE ENDS AND CLOSURE HEAD NOZZLE-FLANGE WELDS
- 1. SCOPE 1.1 AREA OF EXAMINATION This document covers the manual ultrasonic examination procedures for:
1.
Main Steam (N3) nozzle to transition piece welds.
2.
Jet Pump Instrumentation (JPI) (NS) nozzle to safe end piece welds.
3.
Control Rod Drive (CRD) (N9) return nozzle to cap weld.
4.
Core Differential Pressure ( AP' 'NIO) nozzle to safeeend piece weld.
5.
Closure Head Vent tN7) and Instrumentation (N6) nozzle to flange welds.
6.
Feedwater (N4) nozzle to safe end welds.
1.2 TYPE OF EXAMINATION 1.2.1 Volumetric examination sh til be performed using ultrasonic pulse echo nominal 300 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.
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 EX AMIN ATION 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 CONFIGURATlON 1.4.1 The nuzzle and safe end/ transition piece / flange weld configurations covered by this procedure are shown in Figures 1 through 7.
1.4.2 Nominal weld thicknesses range from 0.2S" to 1.78" and are specified in Figures I through 7.
FCR.': NES 205 2/60
DCCUMENT NO.
80A0475 PAGE 6
op 30 NUCLEAR ENERGY SERVICES. INC.
1.5 MATEC.LS The nozzles, safe ends and fittings are contructed of austenitic stainless steel, carbon steel, or inconel, as designated in Figures I through 7.
- 2. REFERENCES 2.1 REFERENCE DOCUMENTS 2.1.1 ASME Boiler and Pressure Vessel Code,Section XI,1971 Edition, and the Summer of 1972 Addenda.
2.1.2 ASME Boiler and Presssure Vessel code,Section III,1971 Edition, and the Summer of 1972 Addenda.
2.1.3 ASNT F ecommended Practice, SNT-TC-1 A,1975 Edition.
2.1.4 NES " Procedure for Ultrasonic Linearity Verification," 80A9053 (Latest Revision) 2.1.5 NES " Procedure for Training and Certification of Nondestructive Examination Personnel",80A9068 (Latest Revision).
2.2 APPLICABLE DRAWINGS The following drawings are part of this procedure:
1.
CE Assembly Drawing E-234-233 2.
CE Assembly Drawing E-234-229 3.
CE Assembly Drawing E-234-275 4.
CE Assembly Drawing E-234-245 5.
CE Assembly Drawing E-234-470 6.
GE Drawings 137C5644,137C5632
- 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 Sammer Addenda, except where examination coverage is limited by part geometry or access.
FORM NES 205 2/80
i DOCUMENT NO 80A0475 30 PAGE_
7 OF NUCLEAR ENERGY SERVICES, INC.
l
- 4. PERSONNEL CERTIFICATION 4.1 PERSONNEL CERTIFICATION REQUIREMENTS 4.1.1 Each person performing ultrasonic examination governed by this procedure shall be certified in cccordar.c.e with the documents referenced in paragraphs 2.1.1, 2.1.3, and 2.1.5 above.
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 11 in accordance with che above referenced documents.
The remaining member (s) shall have a minimum qualification of Level I or d
Level I Trainee.
4.2 PERSONNEL RECORDS 4.2.1 Records of personnel qualification shall be maintained by the Examination Contractor.
4.2.2 A copy of the examiner's certification summary and a current eye test report as required by SNT-TC-1 A shall be filed with each permanent examination record, with a copy available for the Plant O.vner, or his b
Agent, prior to performing examinations per this procedure.
- 5. EXAMINATION REQUIREMENTS 3.1 EXAMINATION FREQUENCY 5.1.1 The norr.inal examination f requency shall be 2.25 MHz for all straight beam and angle beam examinations.
5.1.2 Other pulse frequencies shall be used if such variables as material attenuation, grain structure, etc., necessitate their use to achieve penetration or resolution. This inforrnation shall be recorded on the data sheets.
5.1.3 5.0MHz trarisducer may be required to achieve resolution of the side drilled d holes in the calibration standards.
5.2 EXAMINATION ANGLES AND COVERAGE 5.2.1 The intent of this procedure is to provide maximum coverage to ensure d
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 d examination of each separate zont.
(
FORM :NES 2CS 2/80 J
DOCUMENT NO.
80A0475 8
M PAGE OF NUCLEAR ENERGY SERVICES. INC.
l 5.2.2 The rate of search unit movement shall not exceed 6" per second.
5.2.3 Each weld and the volume of metal (WRV) for IT on each side of the weld shall be ultrasonically examined using 300 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.
5.2.4 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 with paragraph 10.1.1 of this procedure.
There faminations are found to interfere with the angle beam examination, the angle beam techrique shall be modified to result in maximum examination of the specified required volume. In addition, straight beam techniques shall be applied to the WRV where part geometry permits.
Indications sha'l be recorded in accordance with paragraph 10.1.2 of this procedure.
5.2.5 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.
5.2.6 Where the examination surface, geometry, or other conditions (weld, M
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 ont the Weld Scan Data Sheet. In addition, he shall 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 (See Figure 10). Photos will be taken when possible and incorporated as part of the report.
5.2.7 All examination weld / areas shall be entered in the space provided on the Calibration Data Sheet. If there are no recordable indications, it shall be so recorded.
5.2.8 Coverage for the welds specified in this procedure is shown in Figures 1 through 7.
5.3 LIQUID COUPLANT 5.3.1 The ultrasonic couplant shall be suitable for use on nuclear plant materials k
and be certified not to eceed 50 ppm halogen and 200 ppm sulfur.
5.3.2 The couplant shall be supplied in clean containers of sufficient quantity to perform the examination.
5.3.3 The couplant shall be applied manually with a brush'or other suitable device.
FORM : NES 2C5 2 M
DOCUMENT NO.
80A0475 PAGE 9
OF 30 NUCLEAR ENERGY SERVICES. INC.
5.3.4 The examiner shall be responsible for removing couplant from 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 otner 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 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 datum point for all safe end/ transition piece welds in horizontal lines shall be located on the top of the pipe at weld centerline.
5.6.4 Closure Head nozzle to flange weld datum points shall be on the weld centerline at Closure Head 00 5.6.5 Each weld datum point, along with respective weld reference points and divisions, shall be shown on each examination report.
- 6. EQUIPMENT REQUIREMENTS 6.1 EX AMINATION 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 instruments.
2.
Search Units,1/4" thru l-1/S" dia., 2.25 MHz, 00 3.
Search Units,1/4" thru l-1/8" dia., 5.0 MHz 00 4.
Search Units,2.25 MHz (all sizes) for angle beam wedges 5.
Wedges: Aosorted sizes to accomodate search units FCRM NES 205 ?/80
DOCUMENT NO.
80A0475 my 10 30 PAGE OF NUCLEAR ENERGY SERVICES, INC.
6.
Any additional angle wedges to aid in examination or evaluation b
7.
Couplant i
S.
450 Dual ref racted longitudinal wave f or use on meterial >.750" in thickness, when required d
9.
Miniature angle beam verification block 10.
Camera 11.
Thermometer 6.2 PLANT OWNER'S EQUIPMENT The Plant Owner, or his Agent, shall provide the f ollowing service f acilities and equipment as required:
1.
Scaffolding 2.
Water, air, and electricity 3.
Tem porary lighting 4.
Crane or lif ting devices 5.
Calibration Standard No. STEAM 6.
Calibration Standard No. JPl 7.
Calibration Standard No. CRD 8.
Calibration Standard No. IP 9.
Calibration Standard No. VENT 10.
Calibration Standard No.131C8523 (f eedwater) gg i 1.
Test Surf ace Preparation (cleaning and finishing) 12.
Drawings of each Examination Area 13.
Post-examination cleinup of Test Area
[
FOR?.':NES 205 2.50
DOCUMENT NO.
80A0475 mr PAGE -
11 OF 30 NUCLEAR ENERGY SERVICES. INC.
- 7. CALIBRATION REQUIREMENTS 7.1 CALIBRATION DATA SHEETS Calibration Data St.eets 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 STANDARDS 7.2.1 The miniature angle beam calibration standard designated in 6.l(9) shall be g
used to establish horizontal linea.- instrument range.
7.2.2 The Calibration Stardards designated in 6.2 (5) through 6.2 (10) shall be used for establishing reference sensitivity levels for examination of the specified welds.
7.2.3 Spot thickness checks of the components shall be made prior to preservice examinations to ensure that the proper Calibration Standard is used.
7.2.4 The identity of the Calibration Standard used for performing calibration shall be recorded on each Calibration Data Sheet.
7.2.5 Sy:; tem calibration shall be performed using the material side which corresponds to the material which will be examined; i.e., carbon and carbon; stainless and stainless; of the Calibration Standard.
7.2.6 The temperature of the calibration standard shall be within 250F of the component temperature.
Calibration standard and component temperatures shall be recorded on the Calibration Data Sheet.
7.3 REFEWU SENSITIVITY LEVEL 7.3.1 The ref er ?nce sensitivity level shall be ti-e distance-amplitude curve initially obtained directly from the calibratio.. Standard and shall be the sensitivt f level used for evaluating and recording all indications.
7.3.2 During actual weld scaaning, the reference sensitivity level shall be 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 7.4.1 Basic instrument calibration shall be performed using the appropriate calibration standard, search units and instrumentation immediately prior to the examination of the welds specified in this procedure.
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 2.1.4 using an angle beam search unit applied to a code calibration standard.
FORM :NES 205 2/60
DOCUMENT NC.
soA0475 m
11 NUCLEAR ENERGY SERVICES. INC.
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 Level 11 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 8.5 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.
FO4*.' = NES 205 2/80
80E0
- DOCUMENT NO.
13 30 PAGE OF NUCLEAR ENERGY SERVICES, INC.
- 8. EXAMINATION SYSTEM CALIBRATION S.1 STRAIGHT BEAM CALIBRATION FOR INTERFERING CONDITIONS d
Straight beam calibration for all base material through which the angle beams will pass shall be perf ormed at a sensitivity level which gives e.n initial back reflection signal amplitude from the component safeends of at least 80% FSH.
8.2 STRAIGHT BEAM CALIBRATION FOR WELD AND REQUIRED VOLUME (WRV)
Straight beam sweep calibration and Distance-Amplitude Correction shall be perf ormed as follows for each type of material which will be examined; i.e., d c_arbon and carbon; stainless and stainless on the Safe end Calibration Standard.
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.
Positic.) search unit to obtain. maximum response f rom the sid? drilled (1/4T if T >l" or 1/2T if T 51") calibration hole. Adjust sensitivity control to proside a signal amplitude of 80% of FSH and mark location and amplitude on CRT screen.
3.
This is the reference sensitivity level.
Record all sensitivity control settings on the appropriate Calibration Data Sheet.
4.
This completes calibration for thicknesses 31". No DAC is necessary.
5.
For weld thicknesses >l" DAC curve shall be established as follows:
A.
Without changing the sensitivity obtained in (2) above, position the search unit for maximum response f rom the 3/4T hole and mark amplitude on the CRT screen.
B.
Plot a DAC curve by connecting the twc signal response positions with a continuous line extending over the full examination range.
6.
Upon completion of calibration, ensure that all data and instrument settings are recorded on the Calibration Data Sheet. The examiner (s) shall sign the completed data sheet, noting applicable SNT-TC-1 A levels.
7.
Repeat steps (1) thru (6) for each different weld thickness just prior to examination.
FCW = NES 205 2/80
DOCUMENT NO.
80A0475 my E
N OF 30 NUCLEAR ENERGY SERVICES. INC.
S.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 m the material side, i.e., carbon or stainless and adjust the sensitivity control settings to match those recorded in paragraph 8.2(5).
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 standard and repeat step (2).
4.
See Section 7.5 for signal response requirements during calibration check.
8.4 ANGLE BEAM CALIBRATION
/I\\
Calibration shall be performed for each type of material which will be examined, i.e., carbon for carbon, stainless for stainless on the Safe end calibration block, as follows:
1.
Adjust the instrument sweep comtrols so that the examination area is displayed en the CRT screen.
Mark the horizontal screen positions selected for the hole (s) directly on the CRT screen and on the Calibration Data Sheet.
Note:Due to the high attenuation of the stainless steel /inconel material or stainless steel cladding,it may be necessary to divide calibration into two zones. Use an additional Calibration Data Sheet to record this information.
2.
Weld thicknesses < 1":
A.
Position the search unit for maximum response from the calibration hole at the 1-1/2T position.
Adjust the instrument sensitivity controls to provide a si;;nal amplitude of SO% FSH and mark location and amplitude on the CRT screen.
B.
This is the primary reference sensitivity.
Record all sensitivity control settings on the appropriate Calibration Data Sheet.
C.
Wit' ut changing sensitivity, position the search unit for maximum respor.ses from the calibration hole at 1/2T, 2-1/2T, and 3-1/2T positions respectively and mark location and amplitudes on the CRT screen.
FOP'.1: NES 205 2/80
my DOCUMENT NO.
80A0475 1"
PAGE OF NUCLEAR ENERGY SERVICES. INC.
D.
Plot a DAC curve by connecting the signal response positions with a k
continuous line extending over the full examination range.
Note:In bi-metalic calibration blocks (CRD and JPI) the gain setting shall be checked against the equivalent response from the weld hole (l or = ).
If the gain setting is different, it shall be so recorded and used as the primary reference response.
The difference in gain settings will establish a gain correction factor to be applied when calculating and recording indications found during the examination.
E.
Note position and amplitude of ID and OD notch responses through 3T calibration range (ID at IT and 3T; OD at 2T).
3.
Weld thicknesses > 1":
A.
Position the search unit for maximum response from the calibration hole at the 3/4T position. Adjust the instrument sensitivity controls to provide a signal amplitude of 80% FSH and mark location and amplitude on the CRT screen.
B.
This is the primary reference sensitivity.
Record all sensitivity control settings on the appropriate Calibration Data Sheet.
C.
Without changing sensitivity. position the search unit for maximum responses from the calibration hole at the 1/4T,1-1/4T, and 1-3/4T positions respectively and mark location and amplitudes on the CRT screen.
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 (if available) through 2T calibration range (ID at IT; OD at 2T).
4.
Repeat steps A through E for each different weld thickness just prior to examination.
5.
Record all data and instrument settings on the Calibration Data Sheet and sign upon completion, noting applicable SNT-TC-1 A certification !cvel(s).
S.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 match those recorded for the calibrated reference sensitivity.
FORV = NES 205 2160
7 f
80Ao m DOCUMENT NO.
11 PAgr 16 cc 30 NUCLEAR ENERGY SERVICES. INC.
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 duririg caliN ation check.
- 9. EXAMINATION PROCEDURES 9.1 EXAMINATION FOR INTERFERING CONDITIONS Straight beam examinations to detect laminar reflecters which might affect the interpretation of angle beam results shall be performed at a sensitivity level giving a back reflection from the component of S0% FSH as noted in SecC.on 8.1.
9.2 STRAIGHT AND ANGLE BEAM EXAMINATION OF WRV r
9.2.1 All straight and angle beam examination of weld and required volume shall be perforrned 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.
9.2.4 For the location and numbers of the welde, refer 10 the Program Plan.
Examinz.tions shall not be considered complete until all recordable indications have been evaluated.
- 10. EVALUATION CRITERIA 10.1 RE';ORDING 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.
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 incremerits not to exceed that permitted by the 25% overlap of transducer element (width).
=CCM = NES 2^5 2 E3
DOCUMENT NO. _
80A0475 NUCLEAR ENERGY SERVICES, INC.
10.1.2 For straight beam 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 res'ponse shall be recorded on the appropriate data sheet at the time of weld examination.
1.
Each recorded nongeometric indication shall b: 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).
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 ' rom the notch if available.
10.1.3 Geometric indications shall be recorded at one location and noted es geometric caused by thickness change, ID geometry, etc.
10.1.4 Nongeometric Ir_dications 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.
10.1.5 Each recorded indication shall be identified as to depth, length, signal amplitude, and location relative to the weld datu,1 point.
10.1.6 Indications from all welds shall be recorded in inches upstream or downstream in relation to the flow from the weld center line, and in inches CW or CCW from the datum pcht.
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,15-300. All evaluations shall be performed by a Level II or Leve! III 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.
FCnM # NES 205 2:E3
DOCUMENT NO.
80Ao475 PAGE 18 Op 30 NUCLEAR ENERGY SERVICES. INC.
- 11. EXAMINATION RECORDS 11.1 CERTIFICATION OF RECORDS Tne 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.
I 1.2 FILING OF RECORDS NES shall be responsible for submitting to the Plant Owner, o.- his Agent, a completely. documented set of examination records including certification of personnel qualifications with a current eye test repor* 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 Pian 80A0048.
I1.3.2 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.
SC *.' :NES 2:5 2 53
1 80A0475 DOCUMENT NO.
l PAGE 19 OF 30 m =
=
NUCLEAR ENERGY SERVICES, INC.
LEGEND 1 Perpendicular to Weld
= Parallel to Weld
- Base Material 7
WRV Weld and Required Volume A
t
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i J
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Carbon Steel 21" 1D Transition Piece Carbon Steel A-508 CL 1 Nozzle A-508 CL 1 24-9/16" OD Figure 1 - Vitrasonic Examination Procedures for thin Steam (N3) Nozzle to Transition Piece Welds. Cal. Block " Steam" FORM c NES 205 2/80
DOCUMENT NO.
80A0475 PAGE 20 OF 30 NUCLEAR ENERGY SERVICES, INC.
LEGEND Calibrated L Perpendicular to Weld
= Parallel to Weld Onsq'JP
=
side of "JPl" m
W + 3" x
W + 3" Stainless Steel Safeend A-182 TP
,,,_ i n _. g l in _
304
" Y\\
/
og
/
o
.813" I
',' Wf 0
=
45 _L o
0 */
i o
0 WRV Y
o*
0 f /
/
j 10
/ /,1 f
=
A
/
g l
5/16" Carbon Cladding 3-3/16" 1D Steel Notzle i
A-508 CL 2 l
5-7/16" OD Figure 2 - Ultrasonic Examination Procedures for Jet Pump Instrumentation (N8) Nozzle to Safeend Welds, Cal. Block "JP1" FCRM e NES 205 2/80
80A0475 DOCUMENT NO.
1 au NUCLEAR ENERGY SERVICES. INC.
LEGEND J. Perpendicular to Weld
= Parallel to Weld Calibrated on Cladded CS Side WRV Weld and Required Volume f "CRD" Calibrated on Inconel Side e
of "CRD" W + 3" r
Inconel Cap
+ 3"
\\
\\
L
'w e1"-d l
+y
+
T 45 L 1
o L 45 o*
=f,
/
g
.75" 0
- O WRV o
45 45
=
/ ///
/
h A
I Carbon Steel
-7/8" ID Nozzle A-508 CL 2 5-3/8" OD Figure 3 - Ultrasonic Examination Procedures for Control Rod Drive (N9) Nozzle to Cap Weld. Cal. Block "CRD" FORM
- NES 205 2/80
DOCUMENT NO.
80A04/5 PAGE 22 op 30 NUCLEAR ENERGY SERVICES,INC.
LEGEND Perpendicular to Weld
= Faralle.1 to Weld
- Base Material WRV Weld and Required Volume Vessel Wall A~
N W + 1"
=
/
n
"+1"
=
+1/ 2'E-W -*l+ 1/ 2+l A
4 d,'/
/
,2gn f
n o
451 0 45 _L WRV 0 WRV 0
- N 45
/ 45
=
=
c Stainless Steel Safeend A-182 TP 304 1-15/I6 ID 2.5" OD Figure 4 - Ultrasonic Examination Procedures for Pressure Differential (N10) Nozzle to Safeend Weld.
Cal. Block "
P" FCCM = NE5 2C5 2l60
DOCUMENT NO.
80A0475 PAGE _23 OF 30 NUCLEAR ENERGY SERVICES, INC.
LEGEND
_L Perpendicular to Weld
= Parallel to Weld
\\ \\
l l
i T
-- 0 WRV 30*
=
51 Examine As
,/
Far As Geometrv
/
Permits WRV 30
=
+ 1. 28" : :
3-11/16 ID I
l 6-1/4" OD l
/
e j
f/
w
/
N l
Closure Head Carbon Steel Nozzle A-508 CL 2 Figure 5 - Ultrasonic Examination Procedures for Closure Head Vent (N7)
Nozzle to Flange Weld, Cal. Block "VE'iI" FORM :NES 205 2/80
DOCUMENT NO.
80A0475 PAGE 24 OF 30 NUCLEAR ENERGY SERVICES, INC.
LEGEND l_ Perpendicular to Weld
= Parallel to Weld
- Base Material
{ WRV Weld and Required Volume e A-508 CL 2 Flang/
1 l
/
t o
o 3
/ eWRv 300
=
Examine as Far a
As Geometry Permits 45 8
o
- 0 WRV 30
=
~ 1.69" 5-5/8" 1D e
9" OD
=
Closure Head N
Y i
i
/
Nozzle A-508 CL 2 l
l Figure 6 - Ultrasonic Examination Procedures for Closure Head Instrumentation (N6) Nozzle to Flange Welds.
Cal. Block " VENT" 1
l FORM NES 205 2/80
DOCUMENT NO.
80A0475 m
PAGE 25 OF 30 NUCLEAR ENERGY SERVICES. INC.
SCAN LEGEND
_.l_
Perpendicular to Weld
==
Parallel to Weld Base Material
] WRV Weld and Required Volume Examine as far as Geometry Permits 1.02 W
l.02 1.02 W
l.02
/
1.02 WRV=
1 I
I 45 1 WRV=
'l l/f,"
,/,f,A5'
- 0*
Oc*
Safe ends A-508 CLl 1;ote: Due to Configuration of Safe end extend scan path as far as gecretry permits FIGUPI 7.
ULTRASONIC EXAMII;ATIO; PROCEDURE FOR FEEDWATER (N4) tiOZZLE TO SAFE E!!D WELDS.
CAL ELOCK 131C8523 (FEEDWATER)
!3\\
4\\
i FOR*/ E NES 205 2/80
DOCUMENT NO.
80A0475 11 PAGE 26 op 30 W
NUCLEAR ENERGY SERVICES. INC.
y
'N T
Examination Surface h
M'-[.7 i
5/16" SS Cladding O
' :c Side 1 Side 2 Cal. Block Block Hole Hole Notci.
Side 1 Side 2 No.
T OD ID 1/2T Dia.
Depth Depth MAT.
MAT.
i
~
.75" 5-3/8" 3-7/8".375" 3/32" 1.5" 10%T Clad.
.81" 5-7/15 3-13{6
.405" 3/32" 1.5" 10%T Clad.
SS l
l l
l Figure.8 - Ultrasonic Calibration Blocks "CRD" and "JPI" FORM 2 NES 205 2 50
~
o DOCUMENT NO.
80A0475 m
PAGE 27 Op 30 NUCLEAR ENERGY SERVICES, INC.
EXAMINATION SURFACE
~
EXAMINATION i
SURFACE T[
T
- n s O 4
- n o
O O
c:::
g
- l AP VENT,
EXAMINATION
~ SURFACE f
,9 o
l ';
0l l'
,p T
6/,q 4'I, f
131CE323 T
g d,'
/
6--;
I n
v ll ll s
ft STEAM '
c::::
- a l
CALIBRATION BLOCK ELOCK HOLE HOLE NOTCH NO.
T OD ID 1/4T 1/2T 3/4T DIA.
DEPTH DEPTH STEAM 1.78"
.445".89" 1.335
.125" 3.0" 2% T VENT 1.50" 6.25" 2:25".375".75" 1.125
.093" 1.5" 2% T 6P
.28" 2.5" 1.94".07"
.140"
.210
.093" 1.5" 10% T risdwater
~131C8523
.94" 14.12"12.24".19"
.43"
.66"
.093" 1.5" N/A b
FIGURE 9.
ULTRASONIC CALIBRATION BLOCKS FC=M = hES 2 5 2180
D CUMENT NO:
80A0475 Plant / Unit FIGURE 10 Page 28 of 30 Comp / System CALIBRATION DATA SHEET Data Sheet No.
ISO Loop Procedure No.
Subject:
Rev/ Change No.
T*:cTo1Nrsm trTTTNcq gnPru m7,.
Calibration Mfg / Mod Q iio.*
Scan Ancle; unde Block No.
Fabrication No.
Serial No.
fixturine (if anv):
Surface Block Temp i
Sween teneth -
Stvle or Tv-a No.
Size 's Sh,.,,.
Comp. Temp F
Sween Delav Thickness Pulse Lencth/Darninc:
rr e c i,..,,-,.
CRT Calibrtced in Frec.-
Ren. Rate:
Serin 1 Nn/nrnna.
Filter:
Video:
Jack:
Meaeured Ancia DEC/Cate Cv4 *,-h e P,-o ? _
rnklo T.-- n i T n 7*t -
Mode Select:
Pe4ect rn,,-12 n
,-a.
Cnin (conven)-
(#4-nT.
Courlant B,tch; e., c 4 4,. 4...
1007 DAC PLOT e, n.,
0 WTIV n
i 1
l
?
1 6
I 5
U INSTR. LINEARITV CAL.
I I
O vn*'1 Arnlitude 70
== To Weld High Low Hich Low 60 I
1 To Weld 1
5 40 l
1 l
r,14krneinn f
I I
3 7
20 3.,4, 3 g
g g
4 l
8 10 t pl l
a iiltiln iil Cire 0 1 2 3 4 5 6
7 8 9 10 A*.rpi _ rn'7Dn? T T *'r A P TTV Initial,I dB Result Recordable A
nd a ns COS M S/R M ON FOR 80 l
-6 VELD / AREA Yes No l Geom INCOMPLETED SCAN (S) 80
-12 40
+6 20
+12 CALIBRATION CHECKS TIME Initial Cal.
Intermediate Intermediate j
Intermediate EXAMINERS 1 Date Level inal Cal.
2 Date-Level ADDITIONAL SHEETS? CHECK BOX REVIEWERS 1 Date Continuation En,- P!nr 2
Date Sunnle ente Nnno 3
Date
~
NUCLEAR ENERGY SERVICES, INC.
l tn> t cArlon i<t:l'UliT Ullht:1' 4_\\
Document No. 80A0475 FIGURE 11 m
Project No.
ISite L Location Date: (Day /Mo/ir)
I o
8>
,i W Location Page 29 of 30
{, '3, _/ -[j ],
Item IdentifIcatlon t
o E::aminer :
TC-1A Level Angle 0"
45_L 45=
Attached Cal. Data Sheet
[
I f
-[ "'
Thickness l
//
Examiner: TC-1A Level scanning e
an Diameter (nom.)
MP Metal Path W max Weld C DistancefromgtoS.U.atmaximumresPonse.
RBR Remaining Back Reflection W
Distance from weld at 50% of DAC (fwd)
I r-l--
L Distance from Datum 0 W
Distance from weld at 50% of DAC (backward) l l
t',
{
Ind.
FWD BACKWARD L
L RBR S.U.
"_[__
y 2
l _ __
W MAN 50*z DAC 50%
DAC Z,
1
.y.
of C'- M W
MP W,
MP W
MP 50%
max 50%
amp Loc.
2 No.
DAC DAC DAC REMARKS DRAW FULL SCALE PLOT llERE:
REVIEWER DATE REVIEWER DATE REVIEWER DATE A
w a,
- m..
r
~, - = = = = = =
DOCUMENT NO.
80A0475 PAGE 30 OF 30 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.S"
_< l. 7"
> 0.6"
_< l.2"
> C.4"
_< 0.8" 10.0 "
> 1. 7"
_< 3. 5"
> 1.2"
_< 2.5"
> 0.8"
_< l. 6" 20.0 "
> 3. 5"
_< 7.0"
> 2.5" - < 5.0" i
> 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" INSTRUCTIONS: The Vee Path and the examination angle 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.