ML20054G370
| ML20054G370 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 03/02/1982 |
| From: | Fournell D SOUTHWEST RESEARCH INSTITUTE |
| To: | |
| Shared Package | |
| ML20054G362 | List: |
| References | |
| SWRI-NDT-600-11, NUDOCS 8206210490 | |
| Download: ML20054G370 (10) | |
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SOUTHWEST RESEARCH INSTITUTE SwRI-:,mT-600-11 D ' Ac NUCLEAR PROJECTS Revision 34 February 1982 OPERATING PROCEDURE Page 1 of 10 Title MANUAL ULTRASONIC EXAMINATION OF VESSEL-TO-N0ZZLE I:C;ER RADIUS SECTIONS EFFECTIVITY AND APPROVAL Revision 34 of this procedure became effective on 3/2/82 Other revisions of tne base document may be offective concurrently.
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Written By Date Technicat Review Date R$eurd ws/n g gg $-,j Manager of 0.A. Date Cognizant ' rector Dats L/;. Lot- SSN Y SS ._h/b .f y , ~ -
The following informatrcn may be used for convynience. Complet;,n of this portio Deviation No.
Date Effective Procedure Sect:en(s)
Affected Notes:
D s.al Pym Q A4CA.O 8206210490 820611 PDR ADOCK 05000461 G PDR __ _ _ _ _
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SOUTHWEST RESEARCH INSTITUTE Revision 3.
February 1982
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NUCLEAR PROJECTS OPER ATING PROCEDURE Page 2 of 10 MANUAL ULTRASONIC EXAMINATION OF VESSEL-TO-N0ZZLE INNER RADIUS SECTIONS SwRI-NDT-600-11
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure a complete and accurate manual ultrasonic examination of vessel-to-nozzle inner radius sections in accordance with the applicable ASME Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION (1) The examination of vessel-to nozzle inner radius sections with a thickness range of 3 to 12 inches is described in this procedure and shall be conducted as specified in the applicable SwRI Exami-nation Plan.
(2) Techniques for the ultrasonic examination from the outer blend radius have been selected for the purpose of locating the smallest flaw detectable in the vessel-to nozzle inner radius section.
Flaws propagating radially through the cladding of the inner radina can be detected using the longitudinal-wave angle-beam, manm.i, contact, and pulse echo techniques described within this procedure.
- 3. APPLICABLE DOCUMENTS The following documents, as applicable, form a part of this procedure:
(1) ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition, with Addenda through Su=mer 1975, " Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code,Section IX, 1974 Edition, with Addenda through Summer 1975, " Welding and Brazing Qualifications" (3) ASME Boiler and Pressure Vessel Code,Section V, 1974 Edition, with Addenda through Summer 1975, " Nondestructive Examination" (4) SwRI Nuclear Quality Assurance Program Manual (NQAPM)
O SwRI Form CA 3-2
I SOUTHWEST RESEARCH INSTITUTE S"*[ '*/n-6!
1 -
gg , February 1982 fM 7=h R NUCLEAR PROJECTS OPER ATING PROCEDURE Page 3 of 10 JW-3.1 Applicable Calibration and Examination Records SwRI NDTR Form C_o. Revioion Date 17-19 3-14-79 17-109 2-18-82 4 RESPONSIBILITY (1) The Ditector of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan.
(3) The excminer shall be responsible for implementing the require-ments of this procedure.
(4) The Manager of the Support and Administration Section, Quality Assurance Systems and Engineering Division, shall be responsible for storage of records generated in accordance with this procedure.
- 5. PERSONNEL AND EQUIPMENT 5.1 Perconnel Personnel performing examinations shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control."
5.2 Reference Block An IIW block shall be utilized for the preliminary distance calibration in accordance with Paragraph 6.1.
5.3 Basic Calibration Block Calibration reflectors shall be notches placed in a basic cali-bration block. Basic calibration blocks shall be manufactured from material of the same or equivalent P number grouping as the production material, as identified in Section IX of the ASME Code. P numbers P-1, P-3, P-4, and P-5 are considered to be equivalent for the purposes of this examination. The basic calibration block material shall be determined by the production mate-D rial to which the search unit is applied. Notch reflectors shall be in accor-dance with approved drawings contained in the applicable SwRI Examination Plan.
S*RI Form CA 3 2
SOUTHWEST RESEARCH INSTITUTE S"*I-=-6?-
Revision 34 February 1982 M.
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-~ O NUCLEAR PROJECTS OPER ATING PROCEDURE Page 4 of 10 5.4 Search Units (1) The search unit size shall be a 1/2 x l-inch or 1-inch round.
(2) The contact faces of the search unit wedges shall conform to the nozzle blend radius on the vessel exterior. The wedges shall be designed so that a refracted longitudinal-wave shall strike the inner surface at an angle of 45* 10*.
(3) The nominal search unit, frequency shall be 2.25 MHz.
5.5 Ultrasonic Instrument The examiner shall use a Sonic FIS Mark I ultrasonic instrument.
Each instrument shall be aligned and shall display an alignment calibration tag as required by NQAP 10-1.
5.6 guolant (1) USP grade glycerine or deionized water (with or without wetting agent) shall be used when performing ultrasonic calibrations and examinations in accordance with this procedure.
(2) Couplant materials used for examinations shall be the same as used for the calibration.
(3) All couplants other than deionized water shall be certi-fied for sulfur content and total halogens in accordance with ASTM D-129-64 and ASTM D-808-63. The residual amount of total sulfur or halogens shall not exceed 1% by weight.
Deionized water, when used, shall be supplied by t!.a customer.
- 6. CALIBRATION METHOD The complete ultrasonic, examination system calibration shall be per-formed prior to the examination.
NOTE The " REJECT" control shall be maintained in the "0" position during calibration and examination.
The "FREQ MHZ" control shall be turned to "2" when a 2.25 MHz search unit is used.
SARI Form QA 3-2
m C SOUTHWEST RESEARCH INSTITUTE 'NI2o'n~'!-'
February 1982 W
L ,, NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 10 6.1 Distance Calibration The search unit wedge shall be removed from the search unit prior to the preliminary distance calibration.
(1) Position the search unit on the 4-inch dimension of an IIW block and observe back reflections.
(2) Adjust the instrument " MAT 'L CAL," " RANGE" and " DELAY" controls to obtain a 10 or 20-inch linear sound path dis-tance display along the baseline of the screen. The short-est screen distance size which encompasses the last calibra-tion point shall be utilized. This completes the prelim-inary distance calibration.
(3) Mount and couple the search unit on a curved wedge, as de-scribed in Paragraph 5.4.
(4) Position the search unit on the basic calibration block.
El (5) Maximize the signal from the nearest appropriate notch and physically measure this metal path distance.
(6) Adjust only the " DELAY" control to position the signal at the appropriate metal path distance on the screen baseline.
6.2 Distance Amplitude Correction Distance amplitude correction (DAC) curves shall be constructed utilizing the responses from the appropriate notches in the basic calibration block.
(1) Position the search unit.to obtain maximum response from the appropriate notch with the highest amplitude.
(2) Adjust the instrument gain to set this signal at the primary reference response of 75% 5% of full screen height (FSH) and mark this amplitude on the screen.
(3) Without changing the instrument gain control, position the search unit to obtain maximum response from the other appropriate notches and mark the amplitude of each on the screen.
(4) Join these points with a smooth curved line.
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Sw Al Form QA 3 2 e
S"*I- * -6 -
SOUTHWEST RESEARCH INSTITUTE Revision 34 February 1982 y NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 1(,
d 6.3 Secondary DAC Calibration Each point on the DAC curve shall appear at a minimum of 207. of FSH or a secondary DAC curve shall be constructed as follows:
(1) Secondary DAC curves shall contain at least 2 points.
(2) Adjust the instrument gain controls to bring the DAC point at 2 lines or greater in amplitude and adjacent to the point that falls below 2 lines of amplitude to the primary refer-ence level. Mark this response on the instrument screen.
(3) Obtain maximum response from the adjacent points previ-ously at less than 2 lines of amplitude; mark the responses on the instrument screen and join these points with a smooth curved line.
(4) The instrument gain setting used to construct the second-ary DAC curve shall be recorded on the SwRI Sonic Instrument Calibration Record.
EXCEPTIONS When the first DAC point is the only point above 2 lines of amplitude, the next highest point shall be brought to the primary reference level. This point shall ce marked on the instrument screen. The other points, previously at less than 2 lines of amplitude, shall be marked on the screen and 3
these points connected with a smooth curved line. The instrument gain setting for this secondary DAC curve shall be recorded on the SwRI Sonic Instrument Calibration Record.
6.4 Calibration Verification 6.4.1 Sween Range and DAC Curve Verification Sweep range and DAC curve calibration shall be verified on the appropriate basic calibration block:
(1) At the start of a series of examinations (2) With any substitution of search unit cable (3) With any substitution of power source (4) At least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during the examination i SwRI Form CA 3-2
SwRI-NDT-600-11 SOUTHWEST RESEARCH INSTITUTE xevision 34 !
February 1982 !
R7d=h NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 10 '
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i (5) At the finish of a series of examinations (6) Whenever the validity of the calibration is in doubt 6.4.2 Calibration Changes (1) Perform the following if any point on the DAC curve has decreased more than 20% of FSH or 2 dB in amplitude, or any point on the DAC has moved on the sweep line more than 5% of full screen width:
(a) Void all examinations referring to the calibration in question and performed after the last valid calibra-tion verification.
( b, Conduct a new calibration.
(c) Reexamine the areas for which examinations have been voided.
(2) Perform the following if any point on the DAC curve has increased in amplitude more than 20% or 2 dB:
(a) Correct the calibration.
(b) Reexamine all indications recorded since the last valid calibration verification.
(c) Enter proper values on a new SwRI Examination Record.
6.4.3 Recalibration Substitution of any of the following shall be cause for recalibration:
(1) Search unit (wedge / transducer)
(2) Couplant (3) Ultrasonic instrument (4) Examination personnel I
S*RI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE STT'oT-r February 1982 Q) NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 10
- 7. EXAMINATION 7.1 Examination Areas Inner radius sections of nozzle-to-vessel junctures within a thick-ness range of 3 to 12 inches shall be examined in accordance with this proce-dure. Component thickness shall be the wall thickness of the section of the component containing the nozzle inner radius to be examined.
7.2 Surface Conditions The contact surfaces shall be free from weld spatter, roughness, or otler conditions which interfere with free movement of the search unit or impair the transmission of ultrasound.
7.3 Scanning Examine the nozzle inner radius section by manipulating the search unit completely around the outer blend of the nozzle. From the outer blend of the nozzle, scan once in a cicekwise direction and once in a counterclockwise direction. The sound beam shall be tangential to the nozzle, only deviating t10* from tangent. Observe the instrument screen for reflectors in the zone of the inner radius.
Cladding ripple echoes are to be expected. These cladding ripple echoes occur at the same distance as flaws in the nozzle inner radius. A flaw must be distinguished from cladding ripple by the greater eche amplitude of a flaw compared to the amplitude of the cladding ripple at the same location.
The search unit movement rate for scanning shall not exceed 6 inches per second.
When practicable, examinations .shall be performed at an increased instrument gain setting of 2 times the reference level sensitivity, or 6 dB increase.
Instrument gain setting for scanning shall be determined on the basic calibration block as follows for each primary reference level utilized:
(1) With the instrument at the primary reference level, manip-ulete the search unit on the basic calibration block to obtain a signal from a calibration reflector (notch) of 40%
FSH.
(2) Add 6 dB of gain by utilizing the fine gain control only.
Obse rve the signal amplitude.
SwAl Form CA 3-2
SOUTHWEST RESEARCH INSTITUTE S"RI- = -6 -
Revision 34 February 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 10 l ~ ,r-~
(3) Add 6 dB of gain by utilizing a combination of both fine and coarse gain controls. Observe the signal amplitude.
(4) Add 6 dB of gain by utilizing the 6 dB switch, if present.
Observe the signal amplitude.
(5) Choose the method above which yields a signal response closest to 80% FSH.
(6) The method chosen shall be used for all scanning at 2 times the reference level sensitivity.
The examiner shall ensure that the signal response of the method chosen is within 2 dB of 80% FSH and shall record this amplitude and method on the SwRI Sonic Instrument Calibration Record.
Instrument gain settings for scanning shall be recorded on the applicable SwRI Examination Record.
Scanning overlap shall be a minimum of 10% of the search unit piezoelectric element dimension perpendicular to the direction of the scan.
Attempts to determine differences in the acoustic properties between the basic calibration block and the production material which would result in an instrument gain change are not permitted.
7.4 Postexamination Cleaning Arrangements shall be made with the customer for postexamina-tion removal of couplant materials.
- 8. RECORDING CRITERIA Ultrasonic reflectors producing a response 50% o'r greater of the reference level shall be recorded on the SwRI Nozzle Inner Radius Ultrasonic Examination Record.
Indications 100% or greater of the reference level shall be investi-gated by a Level II or a Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector.
Indications 100% or greater of the reference level investigated and found to be other than geometrical in nature shall be reported to the customer for evaluation.
l "L" measurements shall start at L o, the junction of the vessel wall and blend radius.
S*RI Form CA 3 2
S"RI*-6 O
SOUTHWEST RESEARCH INSTITUTE Revision 34 February 1982
. NUCLEAR PROJECTS OPERATING PROCEDURE Page 10 of 10 k_U "L" measurements shall be made to the axial center of the search unit.
The measurements shall be recorded in inches and co= mon fractions to the nearest 1/16 inch.
"W" measurements shall start at Wo and be made clockwise as viewed from a position perpendicular to the vessel surface. "W" measurements shall be made along the junction of the blend radius and vessel wall to the exit point of the search unit.
"W" measurements shall be recorded in inches and common fractions to the nearest 1/16 inch.
Metal path measurements shall be made to the nearest 0.1 inch at each location requiring "W" measurements.
When conditions are encountered which limit scanning, the limitations shall be recorded.
- 9. EVALUATION Evaluation of reportable indications shall be the responsibility of the customer, or the customer's representative, and shall be conducted in accor-dance with the ASME Boiler and Pressure Vessel Code,Section XI, Article IWA-3000. The applicable year and Addenda of the Code shall be as specified in Paragraph 3.(1) of this procedure.
- 10. RECORDS The customer shall receive copies of documents generated in accordance with this procedure.
Documents generated in accordance with this procedure shall be stored and retained as a portion of the examinatioti report. The examination report shall be stored by the Manager of the Support and Administration Section, Qual-ity Assurance Systems and Engineering Division, in the Data Storage Facility for the period specified by the contractual agreement with the customer.
O SwRI Form GA 3 2