ML20039B272
| ML20039B272 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 10/12/1981 |
| From: | Define M, Jeremy Munson NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20039B264 | List: |
| References | |
| 8040480, NUDOCS 8112220479 | |
| Download: ML20039B272 (28) | |
Text
.
i EM DOCUMENT NO.
80A0479 REV.
0 NUCLEAR ENERGY SERVICES. INC.
PAGE 1
OF 17 MANUAL ULTRASONIC EXAMINATION PROCEDURE FOR REACTOR VESSEL NOZZLE INNER RADIUS AREAS 1
i LONG ISLAND LIGHTING COMPANY
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PAGE 2
OF 17 PAGE "E[
DATE DESCRIPTION APPROVAL gg l
l F O R M = N E S 206 2 V.
80A0479 DOCUMENT NO.
PAGE 3
op 17 NUCLEAR ENERGY SERVICES, INC.
MANUAL ULTRASONIC EXAMINATION PROCEDURE FOR REACTOR VESSEL NOZZLE INNER RADIUS AREAS
- 1. SCOPE 1.1 AREA OF EXAMINATION This document covers the manual ultrasonic examination procedure for the inner radius areas of the following nozzles:
1.
Recirculation inlet nozzle 2.
Recirculation outlet nozzle 3.
Core spray nozzle 4.
Feedwater nozzle 5.
CRD - Hydraulic system return nozzle 6.
Steam outlet 7.
Jet pump instrumentation nozzle S.
Vent nozzle 9.
Top head spray nozzle 10.
Top head spare nozzle 1.2 TYPE OF EXAMINATION 1.2.1 Volumetric examination, from the shell, shall be performed using ultrasonic puhe echo nominal 70 angle beam shear wave techniques applied to the OD surfaces of the RPV top head and shell adjacent to the nozzles at the proper tangential (skew) angle.
1.2.2 Volumetric examination, from the barrel, shall be performed using compound angle beam shear wave techniques applied to the OD surface of each nozzle barrel to be examined.
1.2.3 The examination shall be performed manually using contact search units (transducers) and/or scan fixtures.
1.2.4 The examination scan movement approach shall proceed no further than the beginning of the radius blend of each nozzle while on the vessel shell, head surface, or nozzle barrel.
FOR'.':tES 2C5 2/80
DOCUMENT NO.
80A0479 OF D
NUCLEAR ENERGY SERV!CES. INC.
1.3 NOZZLE INNER RADIUS CONFIGURATION Typical nozzle inner radius area configuration is shown in Figure 1.
1.4 MATERIALS The reactor shell is constructed of carbon steel with stainless steel cladding on the ID surface. The nozzles are constructed of alloy steel with stainless steel cladding on the ID surfaces, with the exception of the feedwater, steam outlet and the top head nozzles which are not clad.
- 2. REFERENCES 2.1 ASME Boiler and Pressure Vessel Code,Section XI,1977 Edition, up to and including Summer 1978 Addenda.
2.2 ASNT Recommended Practice, SNT-TC-I A,1975 Edition.
2.3 80A9053; NES procedure for Ultrasonic Instrument Linearity Verification, (Latest Revision).
2.4 80A9068; NES procedure for Training and Certification of Nondestructive Examination Personnel, (Latest Revision).
2.5 NUREG-0619; BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking 2.6 Applicable Drawings:
1.
CE Dwg. 234-229 2.
CE Dwg. 234-230 3.
CE Dwg. 234-231 4.
CE Dwg. 234-245 5.
CE Dwg. 234-275 6.
CE Dwg. 234-470
- 3. PROCEDURE COMPLIANCE i
The examination procedure described in this document complies with Section XI of the ASME Boiler and Pressure Vessel Code 1977 Edition, Summer 1978 Addenda, except I
where examination coverage is limited by part geometry or access. Such limitations shall be identified and described on the data sheets.
I i
l FORM :NES 205 2/80
DOCUMENT NO.
80A0479 any 5
17 PAGE OF NUCLEAR ENERGY SERVICES. INC.
- 4. PERSONNEL CERTIFICATION 4.1 Each person performing ultrasonic examination governed by this procedure shall be certified in accordance with the applicable documents referenced in Section 2.
4.2 Examination crews shall have one or more members as necessary. At least one member of each crew shall have a minimum qualification of Level II in accordance with the above referenced documents.
The remaining member (s) shall have a minimum qualification of Level L 4.3 In addition to the certification referenced above, each person performing inner radius examinations shall receive an additional 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of training.
This training shall be documented and retained in the individual's certification records.
- 5. EXAMINATION REQUIREMENTS 5.1 EXAMINATION FREQUENCY 5.1.1 The nominal examination frequency shall be 1.0 MHz for all examinations performed from the shell. For closure head examinations and examinations performed from the nozzle barrel, 2.25 MHz shall be used.
5.1.2 Other pulse frequencies may be used if such variables as material attenuation, grain structure, etc., necessitate their use to achieve penetration or resolution. This information shall be recorded on the data sheets.
5.2 EXAMINATION ANGLES AND COVERAGE i
5.2.1 The intent of this procedure is to provide maximum examination coverage.
Each nozzle inner radius shall be scanned with minimum 25% overlap of the transducer width (diameter) for each scan pass.
5.2.2 The rate of search unit a.avement shall not exccti 3" per second.
5.2.3 Each shell side examination (Zone 1) shall be performed, where part geometry and access permits, using 70 angle beam shear wave techniques.
They shall be applied in two directions, clockwise (CW) and counterclockwise (CCW), tangential to the inside radius of each nozzle l
from the OD surfaces of the shell and top head. The scanning approach shall proceed only to the beginning of the OD radius blend of each nozzle, as proceeding onto the blend will cause lif t-off and also distort beam angle entry for this area of examination.
i FOR'i:NES 205 2/80
DOCUMENT NO.
80A0479 ar 6
17 PAGE OF NUCLEAR ENERGY SERVICES. INC.
5.2.4 Each barrel side examination (Zone 2) shall be performed, where part geometry and access permits, using compound angle beam shear wave techniques. They shall be applied in two directions, CW and CCW, 360 around the nozzle barrel OD surface.
The scanning shall proceed no further than the beginning of OD radius blend, as proceeding onto the blend will cause lif t-off and distort the entry angle for this examination.
5.2.5 Other angles may be used if required for aid in evaluation.
5.3 LIQUID COUPLANT The ultrasonic liquid couplant shall be Ultragel, which is certified to contain less than 1% sulfur and halogens by weight.
5.3 DATUM POINTS 5.3.1 The designation and location of each nozzle inner radius area may be found on the appropriate drawings referenced in the Program Plan.
5.3.2 Datum points for the vessel nozzle inner radius areas shall be located at the highest point on the vessel to nozzle weld at the weld centerline.
5.3.3 Datum points for the top head nozzle inner radius areas shall be located at the vessel to nozzle weld centerline at vessel 0 or at the point nearest vessel 0.
- 6. 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 the examination of the inner radius areas specified in this procedure.
1.
Pulse-Echo ultrasonic instrument 2.
Wedges: Std. 70 (for shell side examinations) 3.
Wedges: predetermined compound angles (for barrel side examinations) 4.
Wedge: Std. 45 (for barrel calibration) 5.
Search units: 1.0 MHz,1" diameter (for shell side examinations) 6.
Search units: 2.25 MHz,1/2" x 1" (for barrel side examinations) 7.
Couplant 8.
Miniature angle beam verification block FORY : NES 205 2/80
DOCUMENT NO.
80A0479 my 11 7
PAGE OF NUCLEAR ENERGY SERVICES, INC.
9.
Camera 10.
Thermome er.
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 3.
Adequate temporary lighting 4.
Moving or lif ting devices 5.
Calibration Blocks (Listed in Program Plan) 6.
Vessel layout equipment and supplies (as needed) 7.
Test surface preparation (cleaning and finishing) 8.
Post examination cleanup
- 7. CALIBRATION REQUIREMENTS 7.1 CALIBRATION PACKAGES Calibration Data Packages shall be numbered 0479-1, 0479-2, 0479-3, etc.,and shall be signed by the examiner (s) upon completion noting applicable NDE Certification Levels. All Data Sheet (s) shall be a, notated as either "shell scan" or " barrel scan" for the individual examination Leing performed.
7.2 INITIAL SENSITIVITY LEVEL The initial sensitivity levels shall be the amplitude response from the appropriate notch within the calibration blocks.
- 8. EXAMINATION SYSTEM CALIBRATION 8.1 ANGLE BEAM CALIBRATION FOR EXAMINATIONS PERFORMED FROM THE SHELL Angle beam calibration, using a standard 700 wedge and the appropriate vessel calibration block, shall be performed as follows:
l.
Adjust the instrument sweep controls so that the signal response from the 1/4T and 3/4T holes occur at the 2nd and 6th horizontal screen divisions.
FC:iM:NES 205 2/60
DOCUMENT NO.
80A0479 m
my O
17 PAGE OF NUCLEAR ENERGY SERVICES,INC.
2.
Obtain a maximum response from the opposite surface notch and adjust sensitivity controls to provide a signal amplitude af 80% FSH and mark location and amplitude on the CRT.
3 This is the initial sensitivity level. Record all sensitivity control settings on the appropriate Calibration Data Sheec.
4.
Upon completion of calibration ensure thi.t all data and instrument settings are recorded on the Calibration Data 5'.eet. Sign sheet upon completion, noting applicable NDE Certification Levels.
5.
To establish scanning sensitivity, position the search unit at the 0 reference point of the nozzle. Using the sensitivity control, adjust the cladding interface signal response level to 20% FSH.
This is only for nozzles with cladding.
For nozzles without cladding, increase the sensitivity 2x(6dB) for scanning.
All indications shall be evaluated and recorded at the scan sensitivity. Refer to paragraph 9.2.1.
8.2 ANGLE BEAM CALIBRATION FOR EXAMINATIONS PERFORMED FROM THE NOZZLE BARREL Angle beam calibration, using a standard 45 wedge and the appropriate nozzle calibration block, shall be performed as follows:
1.
Refer to Figure 6 for the appropriate horizontal liner _t range ce'.ibration to be used.
2.
Af ter the horizontal linear range has been established, using the nozzle barrel calibration block, obtain a maximum response from the
'B' calibration notch. Adjust sensitivity controls to provide a signal amplitude of 100% FSH and mark location and amplitude on the CRT.
3.
TNs is the initial sensitivity level. Record all sensitivity control settings or, the appropriate Calibration Data Sheet.
4.
Upon completion of calibration ensure that all data and instrument settings are recorded on the Calibration Data Sheet. Sign sheet upon completion, noting applicable NDE Certification Levels.
5.
To establish scanning sensitivity, add 20 dB to the initia! sensitivity. All indications shall be evaluated and recorded at the scan sensitivity. Refer to paragraph 9.2.2.
8.3 CALIBRATION CHECKS Calibration checks shall be performed at the initial sensitivity level. Signal response obtained during calibtation check shall be within plus or minus 20% of that established during basic system calibration.
1.
If any point on the DAC curve has changed by more than 20% of its amplitude, the Examiner shall:
A.
Void all nozzle inner radius scan data sheets since previous calibration.
B.
Recalibrate examination system.
FCW = NES 2^5 2 80
8 DOCUMENT NO.
80A0479 11 NUCLEAR ENERGY SERVICES. INC.
C.
Reexamine voided areas.
2.
If any point on the DAC curve has moved horizontally more than 5% of the sweep line from its original settings, the Examiner shall:
A.
Correct the sweep calib~ ration and
'ote correction (s) on the Calibration Data Sheet.
B.
Void any recorded indication data taken since the previous calibration, or calibration check, and reexamine the applicable area using the corrected sweep.
- 9. EXAMINATION PRCEDURES 0
9.1 SCAN LAYOUT (360 AROUND EACH NOZZLE)
FOR SHELL SIDE EXAM! NATIONS 9.1.1 Using a suitable marker the ultrasonic examiner may mark, in equal divisions, as many lines as are necessary to aid in maintaining a tangential alignment with the nozzle inner radius area.
9.1.2 There should be as many divisions as necessary to visually aid the ultrasonic examiner to maintain a 25% overlap.
9.1.3 Refer to Figures 3 and 4 for all nozzle locations, their respective identification, scan path distances, and tangential (skew) angles.
9.2 ANGLE BEAM EXAMINATION OF THE NOZZLE INNER RADIUS AREAS 9.2.1 Scanning Sensitivity for Examinations Performed from the Shell 1.
Select the proper tangential (skew) angle for the nozzle to be examined.
2.
Position the searc_h unit at the 0 reference point of the nozzle, then using the sensitivity control, adjust the cladding interface signal response level to 20% FSH for clad nozzles. For uncladded nozzles, increase sensitivity 2x(6dB).
NOTE: The examiner is cautioned to use adequate gain to obtain the clad signal. This may require in excess of 20dB over the initial sensitivity level.
3.
Record this sensitivity and the nozzle identification in the comments section of the Calibration Data Sheet.
4.
During scanning adjust sensitivity as required to maintain a nominal 20% cladding interface response level signal for 360 around nozzle.
Record changes in sensitivity and corresponding nozzle reference da tum.
FORM : NES 205 2/ED
DOCUMENT NO.
80A0479 my PAGE OF 17 10 NUCLEAR ENERGY SERVICES. INC.
5.
All indications shall be recorded at the scanning sensitivity.
9.2.2 Scanning Sensitivity for Examinations Performed from the Barrel 1.
Using the initial sensitivity established in paragraph S.2, add 20 dB.
This is the scanning sensitivity. All indications shall be recorded at the scanning sensitivity.
2.
Record this sensitivity and the nozzle identification in the comment section of the Calibration Data Sheet.
9.2.3 Scanning Precedures 1.
With the transducer at the proper tangential (skew) angle (right or left), scan the inner radius area 360 around the nozzle following the layout lines and scan paths limits. For barrel scans, the Examiner must remove the standard 450 wedge and attach the appropriate inner radius wedge.
2.
Transducer movement shall not proceed onto the OD radius blend of the nozzle. The radius blend does not permit proper angle entry of the sound.
3.
Repeat the foregoing paragraphs for the oppcsite tangential (skew) angle to complete the scanning requirements of two directions for each nozzle inner radius area.
4.
A!1 information shall be recorded on the appropriate Data Sheet (s) and the Data Sheet (s) shall be annotated as follows: shell scan for examinations performed from the shell, or barrel scan for examinations performed from the barrel.
- 10. EVALUATION CRITERIA 10.1 RECORDING OF INDICATIONS NOTE: All signals to be recorded must have some metal path movement. Metal path movement of a signal is when the indication " walks" across the screen in a continuous sweep. For nozzles with cladding, the signal must be above the " clad roll."
10.1.1 All indications, during shcIl side examinations (Zone 1), within the zone specified for the nozzle inner radius area being examined showing a signal amplitude response > 50% FSH (at the scan sensitivity) shall be recorded on the appropriate exa6iination data sheet at the time of examination.
10.1.2 All indications, during barrel side examinations (Zone 2), within the zone specified for the nozzle inner radius area being examined showing a signal amplitude response > 25% FSH (at the scan sensitivity) shall be recorded on the appropriate exahiination data sheet at the time of examination.
FORM:NES 2:5 2/80
DOCUMENT NO.
80A0479 my 11 17 PAGE OF NUCLEAR ENERGY SERVICES, INC.
10.1.3 Indications from all barrel side and shell side examinations shall be reported in inches and degrees CW or CCW from the datum point when looking towards the vessel and in inches away from the shell (for barrel side examinations) or away from the nozzle barrel (for shell side examinations) to the search unit exit point.
10.2 EVALUATION OF INDICATIONS 10.2.1 Evaluation of all indications shall be made at the initial sensitivity and in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Article IW A-3000.
10.2.2 The results of this evaluation shall be reported to the Plant Owner, or his Agent, in accordance with the requirements of the referenced ASME Boiler and Pressure Vessel Code,Section XI, Article IWA-6000. All evaluations shall be performed by a Level 11 or Level 111 Examiner.
I1. EXAMINATION RECORDS 11.1 CERTIFICATION OF RECORDS The Examiner (s) shall complete and sign the appropriate scan data sheet (s) immediately upon the completion of each nozzle inner radius area examination, noting applicable NDE certification levels.
11.2 FILING OF RECORDS 11.2.1 Records of personnel qualifications shall be maintained by the Examination Contractor.
I1.2.2 The Examination Contractor 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.
11.3 PROCEDURE CORRECTIONS AND ADDITIONS 11.3.1 All procedure corrections and/or additions required during the examinations may be initiated by either the Owner or the senior NES Site Supervisor. All such changes shall have the approval of the Owner and an NES Level III.
11.3.2 The Plant Owner, or his Agent, and the Authorized inspector shall be notified of such changes and their approval obtained as required.
FORM : NES 205 2/80
DOCUMENT NO.
80A0479 mur PAGE 12 op 17 NUCLEAR ENERGY SERVICES, INC.
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PICTORIAL VIEW OF THE ULTRASONIC EXAMINATION OF THE INNER RADIUS AREA FROM THE SHELL SIDE AND THE NOZZLE SIDE (CUT-A-WAY VIEW).
I FORM:NES 205 2/80
my DOCUMENT NO.
80A0479 NUCLEAR ENERGY SERVICES. INC.
PAGE 13 OF 17 Wedge Designation Identifies Exa.nination Area o
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TYPICAL WEDGE CONFIGURATION USED FOR INNER PADIUS EXAMINATION PERFOPMED FRCM THE BARREL FORM = NES 205 2:83
DOCUMENT NO.
00A0479 14 17 PAGE OF NUCLEAR ENERGY SERVICES. INC.
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FIGURE 3.
ULTRA 50:;IC EXAMI!;ATIC:: CY :;OZZLE I ;;;ER PJcIUS AEEAS (AFPROXIMAnD S12 4 A!;3LES FCR ZO;E 1 EXAMI!;ATIO!;5).
FC.?.!:?.ES 205 2/83
DOCUMENT NO.
80A2823 mr PAGE 15 OF 17 NUCLEAR ENERGY SERVICES, INC.
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Recirc. Outlet 6.8 6.7 16 Recirc. Inlet 6.8 4.0 16 Steam Out 5.8 7.0 16 Feedwater 5.8 5.5 16 Core Spray 5.8 5.2 16 Instrument 3.1 3.2 12 Vent 3.5 2.0 10 Spare 3.1 3.2 12 JPI 6.8
.91 16 CRD - Hyd Return 5.8 3.2 16 FIGURE 4.
ULTRASONIC EXAMINATION OF NOZZLE INNER RADIUS AREAS.
FORM : NES 205 2/80
i DOCUMENT NO.
80A0479 my PAGE 16 OF 17 NUCLEAR ENERGY SERVICES. INC.
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FIGURE 5.
ULTRASONIC EXAMIIIATION CALISRATICN SIf4FS 1
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FORM :NES 2 25 2'EO
DOCUMENT NO.
80A009 1
\\
PAGE 17 OF 17 NUCLEAR ENE9GY 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" - 5 1.0"
> 0.4" - 5 0.8"
$0.5" 10.0 "
> 1.0" - 5 2.0"
> 0.8" - 5 1. 6"
> 0.5" - 5 1.0" 20.0 "
> 2.0" - 3 4.5" 1.6" - 5 3.3"
> 1.0" - 5 2.2" FULL VEE SCAN PATH EXAMINATION Metal Path Calibration Material Thickness Range Recommended 45 60 70 2.5 "
50.8" j0.6"
$0.4" 5.0 "
> 0.S" - 5 1.7"
> 0.6" - 5 1.2"
> 0.4" - 5 0.8" 10.0 "
> 1.7" - 5 3.5"
> 1.2" - 5 2.5"
> 0.8" - 5 1.6" 20.0 "
> 3. 5" - 5 7.0"
> 2. 5" - 5 3.0"
> 1.6" - 3 3.3" 1/2 YEE SCAN PATH EXAMINATION Metal Path Calibration Material Thickness Range Recommended 45 60 70
- 2. 5 "
-.1.7"
_ l.2"
- 0.8" 5.0 "
> 1. 7" - 5 3.5"
> 1.2" - 5 2. 5"
> 0.S" - 5 1. 6" 10.0 "
> 3.5" - 5 7.0"
> 2. 5" - 5 5.0"
> 1.'6" - 5 3.3" 20.0 "
> 7.0" - 5 14.0"
> 5.0" - 5 10.0"
> 3.3" - 5 6.6" INSTRUCTIONS: The Vee Path and the examinatien angle are given in the specific pro-cedure. 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. To the extreme lef1 is the Metal Path Calibration to be utilized.
FIGURE 6
- - _ -