ML19344E779
| ML19344E779 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/07/1980 |
| From: | Dunavont D, Lautzenheiser, Riggs M SOUTHWEST RESEARCH INSTITUTE |
| To: | |
| Shared Package | |
| ML19344E775 | List: |
| References | |
| 17-5926, NUDOCS 8009110304 | |
| Download: ML19344E779 (100) | |
Text
{{#Wiki_filter:_ SOUTriWEST RESEARCH INSTITUTE
,g Post Office Drawer 28510 6220 Culebra Road *W San Antonio, Texas 78284 1980 MANUAL INSERVICE EXAMINATION .0F SELECTED AREAS O' F TH.E PILGRIM.
NUCLEAR POWER STATidN, . UNIT 1 VOLUME I FINAL REPORT WITH APPENDICES ~ SwRI PROJECT 17-5926 I
,b f repared for:
Boston Edison Company. Pilgrim Nuclbar Power Station 800 Boylston Street Boston, Massachusetts 02199 Niarch 1980 Prepered by: Approved b - A&& _ lA ] wAQ) (2&Lo A~ Project $ngineer '"U# 6srWLautzenh - Vice President Reviewed by: Quality Assurance systems and l
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ABSTRACT (v) An inservice examination (ISI) of selected areas of the Reactor Pressure Vessel of Boston Edison Company's (BECo) Pilgrim Nuclear Power Station, Unit 1, was performed during the January-February 1980 refueling outage. This examination was the first ISI performed during the third 40-month period of commercial operation. The components were examined in accordance with the " Project Plan for the 1980 Manual Inservice Examination of Pilgrim Nuclear Power Station, Unit 1," including any changes made during the ISI as approved by BECo. Not-able among these changes was the deletion of the scheduled examination areas of the Reactor Recirculation System Piping. The nondestructive examinations were performed using visual (VT), magnetic particle (MT), and manual ultrasonic (UT) techniques. The MT examinations revealed indications which were reported to and accepted "as is" by BECo personnel using Customer Notification Form (CNF) No. 000001. The VT and UT examinations revealed no recordable indications. (_ /
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TABLE OF CONTENTS Page VOLUME I--FINAL REPORT WITH APPENDICES LIST OF ABBREVIATIONS . . . . . . . . . . . . . . . . . . . . . vi
- I. INTRODUCTION . .. . . . . . . . . . . . . . . . . . . . 1 A. Examination Areas . . . . . . . . . . . . . . . . . 1 B. Summary of Examination Results . . . . . . . . . . . 1 II. DETAILS OF THE INSERVICE EXAMINATION . . . . . . . . . . 3 A. Equipment . . . .. . . . . . . . . . . . . . . . . 3 B. Radiation Exposure . . . . . . , . . . . . . . . . . 3 C. Explanation of Field Data Recort's . . . . . . . . . 3 D. Summary of Nondestructive Examinations . . . . . . . 4 E. Summary Table. . . . ..... . . . . . . . . . . . 6 3 APPENDICES A. Class 1 Weld Identification Figures B. Southwest Research Institute Nuclear Projects Operating Procedures C. Southwest Research Institute Nondestructive
-Testing Procedures D. Ultrasonic Calibration Block Drawings and Certifications E. Certificates of Personnel Qualifications F. Material and Equipment Certifications G. Customer Notification Form VOLUME II--FIELD DATA Reactor Pressure Vessel Vessel Ligaments Closure Studs, Nuts and Washers Calibration Records 190000 Series O
V
LIST OF ABBREVIATIONS ASME - American Society of Mechanical Engineers BECo - Boston Edison Company CNF - Customer Notification Form CRT - Cathode Ray Tube DAC - Distance Amplitude Correction deg - Degree (s) ISI - Inservice Examination Lo - Zero Reference Location MT - Magt etic Particle Examination NDT - Nondestructive Testing QA - Quality Assurance RPV - Reactor Pressure Vessel SwRI - Southwest Research Institute UT - Manual Ultrasonic Examination VT - Visual Examination O O vi
<~'s I. INTRODUCTION During the January-February 1980 refueling outage, Southwest Research Institute (SwRI) personnel performed nondestructive examinations of selected areas of Boston Edison Company's (BECo) Pilgrim Nuclear Power Station, Unit 1. These examinations were part of the first ISI for the third 40-month period of com-mercial operation. A. Examination Areas The ISI was performed in accordance with the following documents: Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1974 Edition, with Addenda through Summer 1975. SwRI Project Plan for the 1980 Manual Inservice Examination of Pilgrim Nuclear Power Station, Unit 1. The following areas were examined with nondestructive testing (NDT) techniques. Reactor Pressure Vessel ()
- Vessel Ligaments Closure Studs, Nuts and Washers B. Summary of Examination Results The nondestructive examinations were performed using visual (VT), magnetic particle (MT), and manual ultrasonic (UT) techniques. The various examinations were conducted in accordance with standard SwRI NDT procedures which were written to conform to the requirements of the applicable sections of the ASME Boiler and Pyessure Vessel Code and the SwRI Nuclear Quality Assurance Program Manual. A dcpy of each applicable SwRI NDT procedure is included in Appen-dix C.-
m No recordable indications were observed during the VT and UT examinations. The MT examinations revealed indications which were reported to BECo on CNF
'No. 000001 and accepted "as is."
Test date (instrument calibration records and examination data) for the examinations were recorded on standard SwRI forms. A copy of each of the instrument calibration records and examination data sheets completed on site is included in the field data volume of this report. 1
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The SwRI Quality Assurance Section was represented on site by the SwRI quality assurance (QA) representative who was present for approximately 100 percent of the examination period. The QA representative performed the appropriate duties outlined in Section 3.3.l(4), "Onsite Quality Assurance Activities," of the " Project Plan for the 1980 Manual Inservice Examination of Pilgrim Nuclear power Station, Unit 1." O O 2
, II. DETAILS OF THE INSERVICE EXAMINATION i
This section of the report provides a discussion of the equipment used and radiation exposure encountered during the ISI, an explanation of field data records, and a summary of the nondestructive examinations performed. A. Equipment
- 1. Manual and Mechanized Ultrasonic Instruments Sonic FTS Mark I ultrasonic instruments were used for the UT examina-tions. These instruments were also used as necessary for thickness gauging of matericls and as an aid in determining the acoustic characteristics / properties through measurement of the transmission of ultrasonics in materials.
- 2. Transducers Various brands, sizes, types, and frequencies of ultrasonic trans-ducers (search units) were used to perform the examinations. Certifications for the transducers used for this ISI can be found in Appendix F. For infor-mation on the actual transducer used for any specific examination, consult the data sheets and referenced calibration sheets in the field data volume.
- 3. Manual Stud Device
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( ) The SwRI Manual Stud Device was used to perform volumetric examina-
'/ tions on studs with axial holes 1-1/8 inches in diameter at Pilgrim Nuclear Power Station, Unit 1. The inspection probe was inserted into the central hole of the stud and manipulated both axially and circumferentially using a 60*
radial shearwave. This technique is capable of detecting discontinuities in the base material and thread roots. B. Radiation Exposure Radiation exposure encountered during the ISI was of fundamental e neern to all SwRI personnel involved during the daily examination activities. SwRI personnel took the necessary precautions in order to minimize overall exposure and consequently received the minimum dosage practicable while performing the selected examinations. The following listing details the approximate radiation exposure levels associated with various examination areas. Radiation Exposure Levels Area Exposure Level RPV Ligaments 250 mR/hr Closure Studs, Nuts, & Washers 15 mR/hr C. Explanation of Field Data Records
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( ) The results of the NDT examinations and calibrations performed by SwRI j K/ personnel were recorded on standard SwRI forms. These completed documents i constitute a portion of the Inservice Examination Report. The original records 1 are retained in the SwRI Data Storage Facility, and copies are provided herein l for completeness. I 3
The field data records for each weld or area are assembled into a package preceded by a Summary Sheet. The examination areas and summary sheet numbers correspond to those listed in the Summary Table. A general explanation of the individual field data forms follows. All instruments used in performing UT examinations were calibrated prior to use, and verified at specified intervals during the examina-tions and upon completion of the examinations. The calibration parameters were recorded on the appropriate calibration record sheet as specified in the applicable NDT procedure. The documented cali-bration and calibration verification provide immediate assurance that the examinations were performed using properly calibrated instruments. The results of the examinations were recorded on the applicable data record sheets as specified in the appropriate NDT procedure. The information documented on these forms describes the parameters asso-ciated with those indications which were greater than the recording levels specified in the applicable NDT procedures. Visual Examination and Magnetic Particle Examination Record Sheets were used to record the results of those examinations. The equipment and/or materials used in VT and MT examinations are also identified on the record sheets. D. Summary of Nondestructive Examinations The following sections of this report are presented for explanation of the Summary of Nondestructive Examinations Table (Summary Table). The Summary Table provides information and results for the nondestructive examinations per-formed during the January-February 1980 outage.
- 1. ASME Section XI Item No. and Categorv The ASME Section XI Item No. and Category are listed in the first and second colu=ns respectively.
- 2. Examination Area Identification Column In the column entitled " Examination Area Identification," each com-ponent to be examined (weld, ligament, stud, nut, etc.) is identified by the component description.
For the Reactor Pressure Vessel components examined during this outage, the area identifications consist of components descriptions and are readily identifiable. No piping welds were examined during this ISI period. The scheduled examination of the selected areas of the Reactor Recirculation System Piping : was deleted. However, these areas were retained on the Summary Table as a part of the record for future reference. O 4 l
3 3. Examination Method Column sj a. Visual (VT) Areas requiring VT examinations were examined in accordance with SwRI Procedure NDT-900-1, Rev. 46. This procedure includes the guidelines out-lined in Section V and specifies method of documenting indications.
- b. Magnetic Particle (MT)
FDE examinations were performed in accordance with SwRI Procedure NDT-300-2, Rev. 27. MT material certifications are included in Appendix F.
- c. Manual Ultrasonic (UT)
The specific UT procedures employed in any particular examina-tion covered in this report are detailed in Appendix C. Each component was subjected to examination scans as discussed in the following subsections. Exceptions to these scans were usually due to component configuration which, in some cases, limits the performance of UT examinations. (1) Straight Beam Scan (0*). A 0-deg straight beam exam-ir.ation vas performed on the reactor pressure vessel ligaments and closure nuts in order to locate possible flaws oriented parallel to the threads and propa-O,gatingfromthethreadrootareas. (2) Shear Wave Scan (45* , 60*). The selected studs and nuts were examined using 45- and 60-deg shear waves, as required, to determine the internal characteristics of the base metal.
- 4. Procedure Identification Column The column titled "SwRI Procedure No./Rev." lists the SwRI NDT Proce-dure that was used for each examination.
- 5. Summary Sheet Colum_
The column titled " Summary Sheet No." references the summary sheet provided for each examination area. The summary sheets are included in the field data volume. In addition to summarizing tLe results of the examinations, the summary sheets list the . record sheet numbers, the SwRI examiner, dates of the examinations, and resolution sheet numbers.
- 6. Indications Columns The four columns under the general heading of " Indications" are "No Recordable," " Insignificant," "Ceometric," and "Other." These columns were used as required, and their general description is provided below.
The results for the VT and MT examinations are indicated by an "X" in [) N the appropriate column to be either "No Recordable" or "Other." The term "Other" is used when indications are observed that exceed the recording require-ments of the applicable procedure. , 5
The results of the UT examinations are indicated by recording the angle of the ultrasonic search unit under the column heading which describes the test results for that angle, i.e., the "No Recordable," " Insignificant," " Geometric," or "Other" column. In the performance of the UT examinations, the data recording level was established by the applicable NDT procedure. The term "No Recordable" is applied when no indications were observed greater than the recording level and no indications were observed between 20 percent of the Distance Amplitude Correction (DAC) curve and the recording level which were suspected by the Level II examiner to be other than geometric in nature.
" Insignificant" is applied when (1) the amplitude of any indication observed was equal to or greater than the recording level, but less than 100 percent of the DAC curve and was not resolved as being relevant, or when (2) nonrelevant indications, such as reflections due to standing waves, trapped glycerine, etc. , were observed.
" Geometric" indications are (1) those indications which have an amplitude equal to or greater than 100 percent of the DAC curve, and.have been resolved and documented to be geometric in nature, or (2) indications that are less than 100 percent of the DAC curve but were suspected by the Level II exam-iners to be other than geometric in nature, and were then resolved and docu-mented to be geometric in nature.
"Other" indications include those indications evaluated to be ottm than " Insignificant" or " Geometric" indications, as described above.
The resolution of each " Geometric" and "Other" indication was docu-mented on SwRI Indication Resolution Records and included with the weld data package. These records are listed by serial number along with the appropriate examination data sheets on the summary sheet for that component.
- 7. Remarks Column The " Remarks" column is used to provide additional information perti-nent to the examination results:
When complete coverage of the examination area was not possible, the " Remarks" column was used to indicate the limitations. For VT and FT results reported in the "Other" column, a brief description is given in the " Remarks" column. Reference is made in the " Remarks" column to CNFs used in the reporting of indications. The required UT calibration block number is listed in the
" Remarks" column for the applicable examination.
E. Summary Table The Summary Table is included from page 7 through 9 of this report. 6
(* ^fM~ s J ' PILCRIM NUCLEAR POWER STATION, UNIT 1 1980 MANUAL INSERVICE EXAMINATION REACTOR PRESSURE VESSEL AM AWE CADONS EXAMINATION EXAM ~ SEC.XI SEC.XI PROCEDURE E XAM. SUM HEMARKS ARE A IDENMCATON METN O ITEM NO CA TG Y. N0/REV. SHEET NO. NO RECORDABLE INSIGNIFICANT GEOMETRIC OTHER , VESSEL-To-FLANCE WEl.D (See Figure A-1) i B1.3 B-C UT 600-13/25 (See "Resu rks") To be examined during a later outage when appropriate calibration block is available.
- CLOSURE HEAD-TO-Fl.ANCE 3 WELD (See Flaure A-2) 51.3 B-C ITT 600-15/39 (See "Rema rks") To be examined during a-later outage when appropriate calibration block is available.
CIDSURE STUDS AND NUTS (See Figure A-2)
- y. 51.7 B-C-1 Stud Nos. 38, 39, 40 trr 600-18/26 300043 60* Studs examined in place, and 41 -
6.25-1.125-8-CS-2-PiH (PIL-31) 81.8 B-C-1 Stud Nos. 42, 43, 44 Mr 300-2/27 300044 (See "Remerks") No MT examination due to grease in , and 45 UT 600-18/26 60* the stud threads. Studs were re-moved for UT examination. 6.25-1.125-8-CS-2-PlH (FIL-31) 81.8 B-C-1 Nut Nos. 38, 39, 40, 41, Mr 300-2/27 300045 (See "Remstks") X Nr indications (linear) on Mut Nos, j 42, 43, 44 and 45 UT 600-19/26 0*,45' 42 and 45. 'See CNF 000001. Limi-ted trr examination due to the con-figuration of the nuts. Nuts were removed during examination. 8.75-6.25-8-CS-1-PIM (PIL-32) 1 VESSEL LICAMENTS (See Figure A-2) 4 81.9 B-C-1 Ligaments between stud UT 600-5/27 300041 0* 6.25-1.125-8-CS-2-P1H (PIL-31) holes 37 and 47 Cl.OSURE WASHERS AND j BUSHINGS Bl.10 B-C-1 Washer Nos. 18 through VT 900-l/46 300040 X Washers were removed for examina-45 tion. Bl.10 B-C-1 Bushing Non. 42 through VT 900-1/46 (See " Remarks") Bushings were not available at time 45 of examination, 3 a _ . _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ , * + - -
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APPENDIX B i SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURES Table of Contents Procedure No. ' Title II-FE-101-1 Deviations to Nuclear Field Services Section Operating CHANGE 1 Procedures II-FE-105-0 Recording Data From Direct Visual, Liquid Penetrant, and Magnetic Particle Examination of Welds IX-FE-110-0 Black Light Intensity Measurement X-FE-101-0 Onsite NDT Records Control XIl."-AG-101-0 Control of Nuclear' Inspection Equipment CHAh?E 1 XVII-AG-101-0 Data Storage and Retrieval
- CHANGE _1 e
i 't l l l 1 v B-1 i:
r k - SOUTHWEST RESEARCH INSTITUTE 1x-PE-iot-1 NUCLEAR PROJECTS S*Ptember 1976 OPERATING PROCEDURE Page 1 of S 1 s $2 DEVIATIONS TO NUCLEAR FIELD SERVICES SECTION 5 i. OPERATING PROCEDURES 3, y 1.0 PURPOSE
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o N . The purpose of this operating procedure is to establish guide-
, 1.1
! lines and controls for deviations to Nuclear Field Services g,
Section operating procedures. 40 SCOPE AND APPLICATION i N 2.1 This procedure app 11es to Nuclear Projects Operating Procedures y, used by the Nuclear Field Services Section.
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@ 2.2 Deviations written in accordance with this procedure shall be p) s S*
g et applicable only to the specified plant and examination area described in the Request for Procedure Deviation Form FE-4-3 (sample attached).
- i g 2.3 Deviatiora written in accordance 'with this procedure do not con-S stitute permanent changes or revisions to the applicable pro-N- ,
cedures.
,I 2.4 This procedure meets the requirements of SwRI Nuclear Quality Assurance Program Manual (NQAPM).
I J / 3.0 RESPONSIBILITY
't % The Director of the Department of Engineering Services, or 3.1 j g \ his designated alternate within the Quality Assurance Systems -
3 g and Engineering Division, shall be responsible for the initia-4:: tion of this procedure.
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. k 3.2 Qualification of deviations to operating procedures shall be j * - the responsibility of the Director of the Department of Engi-d neering Services, or his designated alternate.
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$wRI Form QA.3-1 l
O SOUTHWEST RESEARCH INSTITUTE 1x-rE-io1-1 NUCLEAR PROJECTS Septem'er 1976 OPERATING PROCEDURE Page 2 of a a N 3.3 The Manager of the Section, Team Leader, or other cognizant i, persons using the procedure shall be responsible for initiating the request for a deviation to the operating procedure. h 3.4 The Department Director, or his designated alternate, shall be responsible for approval of operating procedure deviations. 9 M 3.5 The Manager of Quality Assurance, or his designated alternate, shall be responsible for reviewing and approving proposed w deviations to operating procedures against the requirements of this procedure.
]c3 [4.0 PROCEDURE w 4.1 The Manager of the Section, Team Leader, or other cognizant V persons who require a deviation to a Nuclear Field Services
\ Section operating procedure shall be responsible for initiating g % a Request for Procedure Deviation Form FE-4-3. Deviations may j be required due to changing technology, applicable code changes p or interpretations, plant or component design, customer require-f, ments, or special cases.
- E <
$ If the request for procedure deviation is initiated by a
_ telephone call from the field, and the requestor is not avail-
, -y able to sign the request, his name shall be typed in the j " Requested By" block.
}5' 4.2 The Manager of the Nuclear Field Services Section, or his K designated alternate, shall assign responsibility for preparing j the NDT procedure deviation.
w [ \ 4.2.1 The Request for Procedure Deviation, Form FE-4-3, shall have, but not be limited to, the following information: N'
===== (1) Site, 5 i (2) Procedure Number, 4
(3) Procedure Section and Page, g (4) Deviation Number, i4 w
's SwRI Form QA-3-1
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- SOUTHWEST RESEARCH INSTITUTE IX-FE-101-1 NUCLEAR PROJECTS September 1978 y OPERATING PROCEDURE Page 3 of 5 U
(5) Date Requested, ds (6)- Deviation Required
, (7) Examination Areas Affected by Deviations, and g
b (8) Basis of Deviations, g b' j 4.2.2 Deviation numbers shall be assigned by the Manager of g . g Support Services and shall be in numerical sequence beginning with "1" for each procedure revision. 3 4.3 The procedure deviation shall be qualified by either field use, 6 l laboratory verification, or review by a qualified Level III individual, under the direction of the Manager of the Nuclear Field
% Services Section or his designated alternate.
y 4.4 Upon qualification in accordance with Paragraph 4.3, and veri-3 fication that the procedure deviation is in compliance with the g applicable code /other requirements, the person conductin'g the g technical review shall sign the deviation. 2 4.5 The Manager of Quality Assurance, or his designated alternate, shall verify that the deviation is in compliance with this s ,N procedure and sign the procedure deviation as reviewed and approved 3 Y and forward to the Department Director, or his designated Q alternate. f 4.6 If approved, the Department Director, or his designated alternate, g j shall sign the procedure deviation as approved and forward it to
.g k the Manager of the Nuclear Field Services Section.
2 2 N 4.7 The final deviation shall carry the signatures as follows: N (1) Requested Bv. Requestor, if available to sign. If he is d s k not available, his name shall be typed in the " Requested M By" block. (2) Technical Review. A technical review shall be conducted by li a person having an adequate understanding of the require-ments and intent of the deviation, who does not adminis-1 , tratively report to the author, and is a representative of E the same group that performed technical review of the l affe-:ed procedure. j
$wRt Form QA.31
O SOUTHWEST RESEARCH INSTITUTE 1x-FE-101-1 September 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of S L_ N k (3) Approved By. Manager of Quality Assurance, or his desig-w nated alternate.
$w$ (4) Approved By. Department Director, or his designated alternate. -h h
5 ./ 4.8 The Manager of the Nuclear Field Services Section shall forward the original Request for Procedure Deviation, Form FE-4-3, to
) the Nuclear Field Services Section file and a copy to the S .
initiating Section Manager or team leader. f 4.9 The requesting team leader may use the deviation of Nuclear g Field Services Section operating procedure upon receipt of m . the final approval deviation and site approval of the deviation. V
\ 4.10 Th3 deviation number shall be recorded in conjunction with the 4
p appropriate NDT procedure number on all records requiring the g recording of procedure number. s' 4.11 A copy of the Request for Procedure Deviation, Form FE-4-3, shall d[ be atteched to the applicable procedure when conducting exami-s nations in accordance with the deviation. 3 5.0 RECORDS 8 _ S.1 Operating procedure deviations and any other documents generated in accordance with this procedure controlling the performance I of onsite critical services shall be retained for the period 5, i specified in the contract with the Client. These records shall M\ Ji \ be indexed, filed, and maintained in the Data Storage Facility of the Quality Assurance Systems and Engineering Division.
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% S.2 The Manager of Support Services shall be responsible for storage and retrieval of documents generated.
s N 5 d' 5.3 A copy of the approved deviation on Request for Procedure Devia-tion, Form FE-4-3, shall be forwarded to the Manager of Quality Assurance for the historical file.
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u s G swr 4 Form QA 31
IX-FE-101-1 Szptember 1976 Page 5 of 5 PROCEDURE DEVIATION SITE' PROCEDURE / P"'SION NO. DATE RECUESTED: SEC TION : PAGE DEVIATION NO. PAGE o
- OF I 0F L E TA W W'e 4 leEAR AM ECT ED .Y DEVf AMCM e List each sp ecifle eres or tem p os se t to se e nemis ed to eccer ease mes e tus ces setles ( state e s e mee s tsee persed , seaposest identificettee , line identificef 6en . w eld ideettfisellee ,
w etc. ) ' N o t, a a e. E 3 t a 2. orviance. it is rec ast.d ine e one sereireene nei.. is pne ene.e pree. der. / re isies n. deviated fre. .e felle.e ( ese esset .ordlag propened , edditiesel sheets may De esed le essessery)s N a ed d U
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SOUTHWEST RESEARCH INSTITUTE $""d*dt-1 $ NUCLEAR PROJECTS September 1978 OPERATING PROCEDURE Page 5a of 5 w' E k EFFECTIVITY
%evision 1 of this Procedure became effective September 1976. Revision 1 consists of the pages, changes, and revisions listed below.
Page Number Change Revision Effective Date j 1-2 3 0 1 1 1 September 1976 September 1978 3
) 4-5 0 -1 September 1976 4 :
Sa 1 1 September 1978 3 a 4 ' (
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S w RI F ov m Q A 3-1
O~ SOUTHWEST RESEARCH INSTITUTE u-" NUCLEAR PROJECTS OPERATING PROCEDURE Page 1 of 6 Q h , s ' 5' RECORDING DATA FROM DIRECT VISUAL, LIQUID PENETRANT, AND MAGNETIC ARTICLE EXAMINATION OF WELDS _k
? H 1.0 PURPOSE 6% /
N 3 > This procedure provides the technical information and detailed steps
}
g required for recording data from direct visual, liquid penetrant, and magnetic
% article examinations.
$ 2.0 SCOPE AND APPLICATION h
s Data from direct visual, liquid penetrant, and magnetic particle examinations of welds, heat-affected zones, and adjacent base material shall be recorded in accordance with this procedure. 2.1 Applicable Documents [ The following documents form a part of this procedure as 3 d applicable: (1) SwRI Nuclear Quality Assurance Program Manual (NQAPM). j w (2) SwRI Operating Procedures for the examinations being conducted.
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j 3.0 RESPONSI-BILITY t 5 (1) The Director of the Department of Engineering Services, Quality j ' Assurance Systems and Engineering Division, shall be responsible j for the preparation, review, approval, and control of this procedure. 3
\ (2) The Manager of the Nuclear Field Services Section, Department of 6 - Engineering Services, shall be responsible for the implementation ,
of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan. 4id. O s . SwRI Form QA.31
SOUTHWEST RESEARCH INSTITUTE u-rr-tos-o O N NUCl. EAR PROJECTS
/ OPERATING PROCEDURE Page 2 of 6 s
u, Y
"', D (3) The examiner shall be responsible for implementing the requirements .s i of this procedure.
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- s (4) The Manager of Support Services, Quality Assurance Systems and Engineering Division, shall be responsible for the storage of
[ , records generated in accordance with this procedure. W s 4.0 PROCEDURE REQUIREMENTS (1)
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g % Personnel utilizing this procedure shall be certified in accor-dance with Nuclear Quality Assurance Procedure NQAP 11-1, "Special Process Control." o g h (2) Examination shall be conducted as required by the applicable EwRI Operating Procedures. 7 5.0 PROCEDURE 3 5.1 Weld Length j Weld lengths, when required, shall be measured with a steel 4 measuring tape and the distance recorded in inches and common fractions to the
.D. nearest 1/16 inch.
M g 5.1.1 Circumferential Welds C I o 7 Weld length shall be measured along the weld centerline. g 5.1.2 Longitudinal Welds
'i j Weld length shall be measured along the weld centerline.
I j The weld length shall be 12 inches when only 12 inches of the longitudinal weld is required to be examined.
\
% 5.1.3 Branch Connection Welds, Lugs, Supports and Other Similarly
~. Welded Attachments with Fillet Tvoe Weld Surfaces Weld length shall be measured along the junction of the weld fusion line and the component surface , i.e., vessel or pipe surface.
E j . 5.2 "L" Measurements i >
"L" measu::ements shall be recorded in inches and common fractions, to the nearest 1/16 inch.
Swfu Form QA.J.I
(D IX-FE-105-0 V' SOUTHWEST RESEARCH INSTITUTE September 1978 NUCLEAR PROJECTS Page 3 of 6 OPERATING PROCEDURE O k clockwise, looking Measurements for components with a flow direction shall be made in the direction of flow. Branch connection measurements p ,shall be made clockwise, looking at the weld. Measurements for components with-out a flow direction shall be made clockwise as viewed from above the vertical s component or clockwise as viewed from an identified end of a horizontal compo-nent. The end of the horizontal component referenced to determine clockwise
-f shall be recorded in the " REMARKS" section of the applicable SwRI Examination g, fecord.
) ! 5.2.1 Circumferential and Longitudinal Welds 5
* \ Datum = Lo to geometric center of the indication. Measure-F ment will be made along the weld centerline using one of the following methods:
8 s h nn, (1) Measurements shall be made directly from Lo using a steel N measuring tape. (2) Marks shall be made and labeled every 5 inches from to [J N y using a steel measuring tape. Measurements shall be made from these marks using/ a 6-inch steel rule or a steel measuring tape. 3 M (3) The steel measuring tape shall be affixed to the weld centerline with zero at Lo. Measurements shall then be made directly, s n 3 P 5.2.2 Branch connection Welds Datum = Lo to geometric center of the indication. Measurements shall be made along the weld fusion line on the component surface, i.e., pipe f e
,or vessel surface, vn:2 a 6-inch steel rule or steel measuring tape.
*4
- e I 5.2.3 Lugs, Supports, and Other Similar Welded Attachments With Fillet M Type Weld Surfaces Datum = Lo to geometric center of the indication. Measure-
{ ments shall be made along the fusion line on the component surface, i.e., pipe Q or vessel surface, with a 6-inch scale or steel measuring tape. k 5.3 "W" Measurements a y "W" measurements shall be recorded in inches and common fractions 5 h to the nearest 1/16 inch. {m v s a Form oA+1
SOUTHWEST RESEARCH INSTITUTE u-rE-ws-o O NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 6
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U h 5.3.1 circumferential and Longitudinal Welds o Datum = weld centerline to the geometric center of the indi-cation. "W" measurements shall be made perpendicular to the weld center-line using a 6-inch steel rule or steel measuring tape. Bs p ; 5.3.2 Branch Connection Welds
? >
Datum = junction veld fusion line and the component surface to 3
} the geometric center of the indication. The component surface used to determine g g shall be identified in the " REMARKS" section of the applicable SwRI Exami-bnation Record. "W" measurements shall be made perpendicular to the weld fusion g line using a 6-inch steel rule or steel measuring tape.
I (t 7 5.3.3 Supports and Other similarly Welded Attachments With Fillet Type Weld Surfaces
, Datum = junction weld fusion line and the component surface to o J the geometric center of the indication. The component surface used to deter- ! mine Wo shall be identified in the " REMARKS" section of the applicable SwRI U Examination Record. "W" measurements shall be made perpendicular to the weld
[ fusion line using a 6-inch steel rule or steel measuring tape. M 5.4 Indication Types i
*> tion Record asIndications shall be recorded on the applicable SwRI Examina-rounded, linear, or as a group of rounded indications. Further information about the indication shall be recorded under the " REMARKS" section g of the applicable SwRI Examination Record.
if, j , 5.4.1 Rounded Indications 1 A rounded indication shall be an indication which is less than
.three times as long as it is wide.
\
, 5.4.2 Linear Indications E
A linear indication shall be an indication which is equal to or greater than three times as long as it is wide.
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h R $wR4 Form QA.3-1 e
o t i v SOUTHWEST RESEARCH INSTITUTE u-vr-tos-o S' NUCLEAR PROJECTS
/ OPERATING PROCEDURE Page 5 of 6 8 h 5.4.3 Group of Rounded Indications s Y f '
The size of the area and the number of rounded indications 1 required to be recordable shall be as stipulated in the applicable SwRI w Operating Procedure, b I 5.5 b - Indication Size N The size of an indication shall be measured to the nearest 1/32 3 ) inch with a 6-inch steel scale or steel measuring tape. I
' N y 5.5.1 Rounded Indications
{ QS Round indications or indications closer to being round than
# elliptical shall be measured at the mav4== diameter. Elliptical indica-tions shall be measured across the =mv4== length and maximum width.
5.5.2 Linear Indications 3 Linear indications shall be measured along the length of the indication. f' 5.6 Abbreviations g Appropriate abbreviations (listed below) which describe the i R$ indication location with respect to Wo shall be entered on the applicable 8 SwRI Examination Record with the measurements. (1) Up - U
$ (2) Down - D l
[g (3) Clockwise - CW
\ (4) Counterclockwise - CCW !
j (5) Vessel side - V i (6) Lug or support side - L or S
, (7) Pipe Side - P 5 k 2 (8) Other symbols with descriptions entered in the " Remarks" s ) section may be used as approved by the Team Leader.
J Swal Form QA-3 3 1
SOUTHWEST RESEARCH INSTITUTE u-rE-105-0 O September 1978 NUCLEAR PROJECTS
/ OPERATING PROCEDURE Page 6 of 6 un
" D X
6.0 RECORDS g O c' ' Required records shall be specified in the applicable SwRI Operating
-Procedure.
as Permanent documents generated in accordance with this procedure shall be [ ' stored and retained as a portion of the examination report. The examination c' Q report shall be stored by the Manager of Support S ' vices, Quality Assurance 3 , 1 Systems and Engineering Division, in the Data Stor'.ge Facility for the period
} ;specified%
by the contractual agreement with the cuccomer.
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v 4 3 % Y m L e d ! i 3 A i s 5 eci j ! Swal Form QA 31 l
I > SOUTHWEST RESEARCH INSTITUTE 1x-PE-110-0 h NUCLEAR PROJECTS January 1978
/ f [a OPERATING PROCEDURE Page 1 of 3 Q [
3, y " BLACK LIGIT" INTENSITY MEASURDfE.VrS
- D
< 1.0 PURPOSE -
b . This procedure provides the information and detailed steps necessary to ensure the proper measurement of the " black light" intensity for exami-n { M nations utili:ing a " black light." k 40 SCOPE This procedure shall be for the measurement of the " black light" of g N intensity utilizing a Black-Ray J-221 Long Wave Ultraviolet Intensity Meter.
\ 2.1 Applicable Documents The following documents form a part of this procedure:
[ (1) SwRI Nuclear Quality Assurance Progrsm Manual (NQAPM). N (2) The applicable SwRI Nuclear Projects Operating Procedure for the examination requiring the " black light." { 3.0 RESPONSIBILITY a o g [ (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible ;
, 'i for the preparation, review, approval, and control of this ;
j procedure. I j (2) The Manager of the Nuclear Pield Services Section, Department of Sngineering Services, shall be responsible for the implementation 4 of this procedure in accordance with the SwRI NQAPM specified in f the applicable SwRI Project Plan. l E % !
# (3) The examiner shall be responsible for implementing the require- I ments of this procedure.
, (4) The Manager of Support Services, Quality Assurance Systems and l
= j Engineering Division, shall be responsible for storage of records !
! 4 generated in accordance with this procedure. I Eh I i 4
3 SwAI Form QA 34
SOUTHWEST RESEARCH INSTITUTE 1x-PE-11o-0 O d M NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 3
= z 4:0 PROCEDURE k 4.1 Personnel
[ ' Personnel measuring " black light" intensity shall be certified in g accordance with the personnel certification requirements of the g N SwRI Nuclear Projects Operating Procedure to be used with the g g examination requiring the " black light." , g 4.2 Equipment The following equipment shall be utilized for measurements:
. M 2 A' (1) Black-Ray J-221 Long Wave Ultraviolet Intensity Meter with Q sensor cell.
h (2) J-223 Extension cord (4 foot). (3) e Contrast Filter. N 4.3 Measurement
'i w The " black light" Intensity at the surface under examination shall be determined:
2 @ (1) At least every 8 hours (2) Whenever the work location is changed.
$ T NOTE 3 ! ! The meter face shall be vertical for all readings '
3 and meter zero verification. The meter :ero shall
. s be checked with the sensor cell unplugged. If the 1
% reading is not "O," the screw below the scale shall l
{ i be used to adjust the scale to :ero. ; j The Black-Ray J-221 Long Wave Ultraviolet Intensity Meter shall be utilized as follows: ) (
& - (3) Plug the extension cord in the top of the meter housing E j with the red and black plugs aligned with their correspond- ,5% ing holes for proper polarity.
SwRt Form QA 3 I
I > SOUTHWEST RESEARCH INSTITUTE 1x-rE-110-0 January 1978 N D NUCLFAR PROJECTS OPERAT:NG PROCEDURE Page 3 of 3
$ N i g (4) Repeat step (3) plugging the extension cord in the sensor M ce11.
T (5) Select the "B" scale by moving the switch on top of the meter housing to "B." (6) Darken the area and place the sensor cell directly on the
} surface to be examined.
'k N<
(7) Place the " black light" 16 inches (nominal measurement) from the sensor cell after the " black light" has warmed up a
. P minimum of five minutes.
U I (8) Observe the "B" scale. If the needle is pegged, the " black
, light" shall be moved back, up to a maximum of 22 inches (nominal measurement), until a reading can be taken.
NOTE f- The "B" scale range is from 10 to 60. To 3 tg obtain a readhg in microwatts per square g centimeter, multiply the reading by 100. For example, if the reading is 20, multipty 20 by 3 g 100 to obtain 2,000 microwatts per square 3 centimeter. (9) Another reading shall be taken with the 50107 contrast
! filter over the sensor cell and the " black light" located E the same distance as the first reading.
3 I (10) Subtract the second reading from the first. The difference 3 shall be a minimum of 800 microwatts per square centimeter. 2 [ c The distance, during an examination, from the " black light" to the examination surface shall not exceed the distance at which j the " black light" intensity was measured. j S.0 RECORDS a h The difference of the two readings and the distance from the " black j light" to the sensor cell during the readings shall be recorded on the
,E applicable SwRI Examination Record.
D I g
$will Form QA-3-1
\J SOUTHWEST RESEARCH INSTITUTE x-PE-101-0 Mar 6 NUCLEAR PROJECTS OPERATING PROCEDURE
- Page 1 of 6 g s j- , ONSITE NDT RECORDS COVTROL PURPOSE
!i 1.1 The purpose of this procedure is to describe the flow in the 3 \ field of the nondestructive testing records generated during j preoperational and inservice examinations.
b u 2.0 SCOPE AND APPLICATION 7j g
, 2.1 This procedure is limited to describing the flow of data records used to document the results of the nondestructive m tests performed. Data records include Original Data Sheets, Summary Sheets, Resolution Sheets, strip charts, magnetic tapes, video tapes, or other information as defined by the
- Team Leader or Inspection Engineer, v g 2.2 Where necessary to explain the flow of the records, functional
{- steps are provided in this procedure. L 2.3 This procedare provides guidance to personnel of the Nuclear N Field Services Section who are assigned the responsibility of
, preparing, reviewing, or otherwise using data records while ji L in the field performing a preoperational or inservice examination.
3.0 RESPONSIBILITY cs h1 3.1 The Manager of the Nuclear Field Services Section within the Department of Engineering Services shall be responsible for
,L g the implementation and control of this procedure in accordance
< with the applicable portions of the issue of the Nucica.r
-- Quality Assurance Program Manual in effect on the date the s Y procedure is approved.
b* 3.2 The Team Leader has the primary responsibility in the field
\ for assuring compliance with this proceduro.
g Q 3.3 Each person performing functions falling within the scope of g this procedure shall comply with its requirements, b b (3 (y <5
. . . . . . o 24 i
I l l l
O SOUTHWEST RESEARCH INSTITUTE x-PE-ioi-o
' 14 arch 1976
' NUCLEAR PROJECTS OPERATING PROCEDURE
# Page 2 of 6 N k&
j N4 .0 PROCEDURE { 4.1 Original Data Sheets a gi 4.1.1 Original Data Sheets are created when they are 3 reproduced and seriali:ed either at SwRI or the site. fQ 4.1.2 Original Data Sheets will be filled out at the place and time of the examination.
. Y 4.1.3 The Original Data Sheets are returned to the team 5 T staging area (office, trailer, etc.) on a periodic e basis (at meal time, at the end of the day, upon p %
leaving controlled areas during an ISI), and a record is made into a daily log that the examinations have oA
]x been performed. O 2
g 4.1.4 If a computer is being used to record results and W g
%' generate Summary Sheets, computer input will be made 3; for records containing data which requires no s evaluation or resolution, s
d' M. T 4.1.S The Original Data Sheets are then placed into the To-Be-Reviewed file. ' 4.1.6 The Review Process is performed as follows: b 4.1.6.1 The Original Data Sheets will be
] N checked for completeness and, to the extent practicable, accuracy and
( i , h consistency of the data. 4.1.6.2 If clarification of any entry on the 0 g Original Data Sheets is required, the Original Data Sheets are returned to the Examiner, k a 9
! 1 4,
J SwRI Form QA 3-3 G
c \) SOUTHWEST RESEARCH INSTITUTE x-rs-lol-o March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE 4' Page 3 of 6 Q C 4.1.6.3 After clarifications, if any, are made, 8 s the Reviewer signs each Original Data Sheet that does not contain indications which require evaluation and/or reso-lution. j 4.1.7 The Original Data Sheets that have been reviewed and signed are moved to the To-Be-Summarized file. See g Paragraph 4.1.9. 4' .1. 8 Original Data Sheets which contain indications
-- requiring evaluation and/or resolution are placed in g the To-Be-Resolved file.
o 9 N 4.1.8.1 Original Data Sheets in the To-Be-Resolved file which document visual or 9 surface examinations are handled as follows: hN 4.1.8.1.1 The Original Data Sheets are reviewed, signed by the 5' 3 Reviewer, and used to N generate a Customer Notifi-cation Form (CNF). (The s : '. CNF is completed according d' ' to Nuclear Quality Assurance Program Manual, Procedure 13-1).
- c. > 4.1.3.1.2 The Original Data Sheets
' are duplicated in order to 5 be attached to the CNF.
k N 4.1.8.1.3 The Original Data Sheets
""""" are then put into the 2 To-Be-Summarized file. See S Paragraph 4.1.9.
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I N 7 p\ C t \d som r.,- 04-3 2 l J
SOUTHWEST RESEARCH INSTITUTE x-rs-101-0 March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 6 E s o 4.1.8.2 Original Data Sheets in the To-Be-Resolved file which document ultrasonic examinations are used to resolve the { k indications according to Paragraph 4.3 and then follow the flow of Paragraphs C 4.1:6 and 4.1.7. E h 4.1.9 Data placed in the To-Be-Summari:ed file is sum-o mari:ed according to Paragraph 4.2 and filed with the Summary Sheet in the original data volumes. j 4.2 Summary Sheets m 4.2.1 Summary Sheets are created when they are reproduced 8s and seriali:ed either at SwRI or the site. If in
< use, the computer will generate the Summary Sheets
{$y at the completion of all required examinations of an examination area. i , 4.2.2 Summary Sheets will be filled out for each exami- { nation area. In certain cases (studs, nuts, etc.), _ d one Summary Sheet may be used for more than one
, examination area.
_' E 4.2.3 Summary Sheets are to be filled out prior to the completion of site activities for each examination f - area which has its examination requirements com-b i N
;- pleted.
j 4.2.4 Summary Sheets will be filed with the data in the ( 4< original data volumes. 4.3 Resolution Sheets JE 5 j, ' 4.3.1 Resolution Sheets are created when the; are repro-duced and seriali:ed either at SwRI or on the site. 4.3.2 The Level II or Level III will take the steps i necessary to resolve the ultrasonic indications and j ,.sc will complete a Resolution Sheet describing the g 4 results of his analysis. Any additional documenta-
# 4 tion required to support the resolution will be 5 attached.
5
<'3 SwAI Form L. A-31
i") SOUTHWEST RESEARCH INSTITUTE x-FE-lol-o NUCLEAR PROJECTS OPERATING PROCEDURE W Page 5 of 6 31 k
. 4.3.3 Criginal Data Sheets and resolution records with 5 s indications requiring no further action will be placed in the To-Be-Reviewed file and will follow the flow of Paragraphs 4.1.6 and 4.1.7.
a i f 4.3.4 Data with indications requiring further action will 3 be handled in a manner established by the Director, j , Department of Engineering Services. 1 d 4.4 Strip Charts, Magnetic Tapes, Video Tapes 4.4.1 Strip Charts, Magnetic Tapes, and Video Tapes are W s generated durfremvhmi:ed ultrasonic examinations, o 3 4.4.2 As the charts and tapes are generated, they are
." s identified with a sequence number and with the examination areas for which they contain data.
g l as _s (V ~5 ' 4.4.3 During the resolution of any indications, the strip [ charts and tapes may be used by the Level II or g - Level III.
' 4.4.4 The strip charts and tapes are then made ready for transmittal to SwRI.
4.5 Customer Notification Forms p 4.5.1 Customer Notification Forms are created when they g' . are reproduced and serialized either at SwRI or the site. j 4.5.2 Customer Notification Forms are handled according
% % to SwRI Nuclear Quality Assurance Program Manual, Precedure 13-1.
j 5.o RECORDS 5,1 Prior to departing from the site at the completion of a pre-
) operational or inservice examination, the original data package with the exception of st11p charts, magnetic tapes, and video j %a tapes will be reproduced ;nd the copy will be transmitted to
- 1
- S 1
\n e ,e SwRe Form QA.3 3
SOUTHWEST RESEARCH INSTITUTE x-FE-lol-0 March 1976 NUCLEAR PROJECTS LR. OPERATING PROCEDURE dW Page 6 of 6 8 ,% s the appropriate site personnel. At no time will data be d , reproduced for this transmittal until the required examina-tions for a particular area are complete, the data is reviewed, and the Summary Sheets have been completed, i W,
> S.2 At the end of the site activity (or at other times deemed 5 appropriate by the Inspection Engineer or Team Leader), the 3 .
original data package will be transmitted to SwRI in accordance with SwRI Operating Procedure XVII-AG-101-0.
}
U R R 114 g
} 's 4 $m j, i i 4 =
s m l h i nt a d SwRI Form QA-31 g
.r*"'*'- Change 1 SOUTHWEST RESEARCH INSTITUTE xl u-Ac-101-0 June 1977 NUCLEAR PROJECTS Fage 1 of 11 OPERATING PROCGDURE u
~
CONTROL OF NUCLEAR INSPECTION EQUIPMENT s' h.0 PURPOSE 1.1 The purpose of this operating procedure is to provide control for l g, the storage, inventory, issue, shipment, and return to stock of nuclear inspection equipment. Is 2.0 SCOPE AND APPLICATION h i 2.1 The scope of this procedure is the control of nuclear inspection equipment to ensure the integrity of equipment and materials used 3 Q during the examination of nuclear power plant components. 8 Q - 0 2.2 Controls are further required to ensure that maximum utili:ation z s is made of available equipment, i.e., equipment is not " lost" in tle Radiation Control facility, delayed or misplaced during ps Q+ transit from job site to maintenance shops, or allowed to remain Q g g Q idle for long periods of time while being used for research and development pcojects. The flow chart illustrates the control and g process of nuclear inspection equipment (Attachment 4). 2 2 2.3 This procedure is applicable to, but not limited to, control of the following equipment and materials:
$ k (1) Ultrasonic Test Equipment
_s (2) Plastic Wedges (3) Ultrasonic Testing Materials (4) 2 Penetrant Testing Materials
? (5) Magnetic Particle Testing Materials and Equipment
==::-
j (6) Eddy Current Testing Equipment and Standards
- M (7) Mechani:ed Inspection Equipment
'. g() (8) Data Acquisition Systems h I i
5 i i v . . ~ . , -_ i
.. 1
O SOUTHWEST RESEARCH INSTITUTE xuI-AG-101-o Ik NUCLEAR PROJECTS March 1976 L N OPERATING PROCEDURE
# Page 2 of 11 3
. 2.4 The following documents form a portion of this procedure as
! \ applicable.
. 2.4.1 SwRI Nuclear Quality Assurance Pcogram Manual (NQAPM).
si 2.4.2 SwRI Radiological Health and Safety Manual. { 3.0 RESPONSIBILITf 2
$ 3.1 The Vice President of the Quality Assurance Systems and Engi-neering Divisio?. shall designate one or more secure areas to be - used for equipment and materials storage as control facilities.
o $ 3.2 Control facilities shall be operatred by a Stock Clerk under the N supervision of the Manager, Support Services, who will be responsible for inventory, storags, issue, and retrieval of s controlled equipment. 3 3.3 Responsible users, such as Team Leaders, shall be respon-p Q E sible for compiling a list, using SwRI Form SS-17 Equip-ment Control / Shipping List (Attachment 1), of equipment and 4 'N materials required for each job or project. ney shall be W responsible for shipment of the equipment to the job site, security while at the job site, reshipment upon completion g
! }l2 ; of the job, decontamination if required, documentation of C
$ faulty equipment, and turn-in of equipment and unused materials, g
'3 . 4 The Manager, Production and Maintenance or his alternate shall g N be responsible for providing minimum maintenance turnaround time and for providing current certifications as required for nuclear y
y , inspection equipment.
$ E ho PROCEDURE ~
I 3.5 4.1 New rouipment
$ 4.1.1 Newly purchased or fabricated critical equipment shall -" be inspected in accordance with operating procedure VII-AG-101 prior to being routed to the appropriate control facility.
C y
.i 8 _-
S k SwRe Form QA.F1
m .1 n v' u n-^c- ot-o SOUTHWEST RESEARCH INSTITUTE March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 11 L' 0 $ 4.1.2 An identification number (serial number) will be assigned i to noncapital equipment which does not have a manufac-turer's serial number.
~
4.1.3 Upon completion of proper identification, new equipment I will be listed on the control facility inventory records.
$ 4.1.4 Once new equipment is properly identified and inventoried,
}
it will be issued to the appropriate maintenance facility li for an operational check and certification in accordance u with Nuclear Quality Assurance Program Manual (NQAPM) procedure NQAP 10-1. The maintenance facility will return Tj R the equipment, along with copies of certifications g generated, to the control facility. The new equipment may
,L then be issued for nuclear inspection work.
4.2 Equipment Issue
/ 4.2.1 When it is dotemined that equipment and/or materials stocked in the control facility are to be removed from the G j control facility, with the exception of equipment routed through the maintenance facilities (Paragraph 4.6.3), the g Team Leader or Responsible User will compile a list, in triplicate, of required equipment and/or materials needed using Form SS-17. The responsible supervisor shall j
\& complete each blank at the top portion of the form with no N exceptions. On the second part of the form, he will list
'k quantity and nonmenclature of each item of equipment or l
Y materials required and indicate those which require certifications. Serial numbered items must be entered j\ one item on each line. 4.2.2 When the Team Leader or Responsible User has initiated [ g Form SS-17, he may assign any technician to draw and pack ;
-- the equipment. The technician will present Form SS-17 to s
the control facility, and the Stock Clerk will issue the 1 o (N equipment. The Stock Clerk will enter appropriate serial j Q number and estimated replacement cost of each item on Forn SS-17 as the equipment is issued. He will also supply copies of appropriate certifications as required. When , g h requested equipment and/or materials have been issued, the l g e technician will sign each Form SS-17, indicating that he ! i b has received the items for the responsible supervisor. ! I E The Stock Clerk will retain Copy 3 of Form SS-17 for his records.
\ i o ..m__
O SOUTHWEST RESEARCH INSTITUTE m t-^c- ot-o March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 11 3 4.3 Ecuipment Packing and Shiccing I s 4.3.1 If the equipment and/or materials are to be shipped off the Institute grounds, the technician will pack each item 7 in numbered shipping containers. He will then enter the
! container number in the appropriate Box No. space on Fom j SS-17.
i5 4.3.2 If the equipment is to be shipped by freight, a box count must be made and each box must be weighed. Shipping 0 k labels must be completed and affixed to each shipping container.
^
a I g 4.3.3 When the packing has been completed, the technician will
% return Copies 1 and 2 of Fom SS-17 to the responsible
< supervisor. The supervisor will retain Copy 2 for his records, and Copy 1 will be used for insurance purposes if the equipment is to be removed from the Institute grounds.
p QJ 4.3.4 If equipment is to be shipped by freight, the responsible g supervisor will contact the Requisitioning Agent, who will 2 arrange for shipping and for the proper shipping documents s to be completed.
. Q 4.3.5 The responsible supervisor will review Form 55-17, with j g special emphasis placed on ensuring that appropriate certifications are available for each item that requires
, ) certification.
4.4 Onsite Control j h 4.4.1 The Team Leader or Project Engineer shall assume respon-A \ sibility for the security of equipment once it has been h drawn from the control facility. At the job site, he will obtain a secure area to be used for equipment storage and 7'e 3 will arrange for issue of the equipment or materials as the work load demands. He will ensure that equipment o
$ placed into ensite storage after use is dry and clean and that any equipment damaged or found to be inoperative
'p or out of tolerance is tagged with a red hold tag, SS-19,
> to indicate its condition (Attachment 3).
i k" t 5 %
.v s
- 1 v
SOUTHWEST RESEARCH INSTITUTE 0^"%101_o June 1977 NUCLEAR PROJECTS OPERATING PROCEDURE Page S of 11 i _s
$ h '
4.S Decontamination s E ' 4.S.1 Equipment being returned from an inservice inspection must
] % V be delivered to a radiation control area immediately upon return to the Institute. Equipment that can be decontami-l nated may be returned to the control facility after g< decontamination, in accordance with SwRI Radiological y
Health and Safety Manual, Paragraph S.2. Equipment that
.= l cannot be decontaminated must be stored in a radiation
} control area. The Division Health Physics representa-l tive will prepare a memorandum addressed to the Manager, Q Nuclear Field Services; the Manager, Support Services; and the Equipment Control Clerk, listing equipment from j each hot inservice inspection site that must remain in oQ' the hot radio logical controlled storage facility. The N \ Equipment Control Clerk will initial and date the remarks s section of the Form SS-17, copy 3 indicating that the (N g' particular equipment has been returned to the Institute.
b - 4.6 Equipment Turn-In i
; 4.6.1 Upon completion of a project or the return to the Insti-
- tute of equipment used off the grounds, the equipment
- A and/or unused materials will be returned to the control facility. As each item is checked in, the Stock Clerk H-3 a }h will enter the date and his initials in the appropriate
_."!n remarks block of copy 3 of the Form SS-17. He will also
. enter the date that the equipment was returned and his f initials in the appropriate remarks block of copy 2 of the Form SS-17 when requested.
ji s 4.6.2 The Stock Clerk will check each item for disposition.
. Equipment requiring repair, cleaning, or recertification/
6 recalibration within the next 30 calendar days must be accompanied by a Form SS-19, Hold Tag; (Attachment 3)
; and taken to the appropriate maintenance facility.
4.6.3 When repair and/or certification is completed, the item will be returned to the control facility and placed in ; Y' stock for reissue. l W l
.= ,
\
; i %
SwRt Form QA.31
Change 1 e SOUTHWEST RESEARCH INSTITUTE n u-Ac-1ot-1 June 1977 NUCLEAR PROJECTS Page 6 of 11 e OPERATING PROCEDURE
!! s 3 $ 4.6.4 Expendabie materials such as Penetrant Testing Material g3 and Magnetic Particle Testing Materials will be returned o N to the appropriate stock room. When the stock clerk can
- determine that the material has not been used and identify-h ing data is available to trace the material to the appropriate certif.icates and to the original purchase j i order, he will credit the appropriate job site by C,
. processing an appropriate store requisition.
E 4.7 Special Issue Recuirements 4.7.1 Occasionally it will be necessary for a (eam Leader who 7 is in the field to request that equipment be checked out
! and sent to him. When this circumstance arises, he will
*[q contact the Examination Activities Coordinator or his alternate and make his needs known. The Examination Y, Activities Coordinator or his alternate will initiate 4,
% Form SS-17 and draw, pack, and ship the equipment. He c will perform the review and enclose Copy 1 of Form SS-17
'n the shipping container so that the Team Leader will
[ (.j nave a record of what was actually shipped.
4 M 4.7.2 If equipment is to be shipped from one job location to
- Y^ another without returning to the Institt.te, a packing list will be made using Form 55-17. One copy will be j { retained by the responsible person making the shipment, one copy will be enclosed with the shipment, and one copy 3 will be returned to the control facility at the Insti-tude. The responsible supervisor will review the Form 4'sy*.( SS-17 to insure that certificates were included as required.
i 4.8 Lost or Destroyed Ecuipment g 4.8.1 In the event any item other than normally consumabie
, h materials are lost or destroyed while it is signed out of j the control facility, the responsible supervisor will ,__ m initiate a memorandum addressed to the Assistant Manager, Nuclear Field Services, and the Manager, Production and g Maintenance. with a copy to the Manager of Support Ser-vices. The memorandum will identify the equipment and describe the circumstances involved with its loss or g}
I
;; destruction.
v SwAl Porm QA 34 e
jf 4 v Change 1 SOUTHWEST RESEARCH INSTITUTE XIII-AG-101-0 June 1977 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 11
-Ga 4.9 Recall of Equipment for Recalibration s,
4.9.1 When notified that a particular piece of equipment is cue recalibration, the Stock Clerk will determine the { h location of the equipment by reviewing his equipment inventory records. If the equipment is located within 3 the stock room, he will place a " Hold Tag" on the item y
. and take the equipment to the appropriate certifying a facility. When the equipment has been issued, the Stock l Clerk will notify the Field Services Activity Coordinator or other responsible supervisor by completing a Form
_ 1 SS-42. (Attachment 2) The Activity Coordinator or 3 4\ responsible supervisor will ensure the equipment is a Q sent to the' Stock Clerk on or before the recalibration e! date. The Stock Clerk will then place a " Hold Tag" on g
-.s the item and take it to the appropriate certifying facility.
4 A e h $ [, , , Note: If a particular piece of equipment is being used in a non-critical application, it need not be returned
- t. until completion of the project.
D s 5.0 RECORDS
~~
~R
, 5.1 Copy of Form SS-17 shall be maintained ty the control facility a for a minimum of six months after the last item on the form was
% turned in. Copy 1 shall be retained by Field Services.
. 5.2 SwRI Form SS-42 may be destroyed upon return of equipment to the g stock room.
x 9
%' 5.3 The Stock Clerk will maintain a file of current equipment k\ certification records. An adequate number of copies will be included for issue during equipment issue.
mm=: nae C
- 4
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$wRI frorm QA.J 1
O XIII-AG-101-0 March 1976 Page 8 of 11 EQUIPMENT C0ffrROL/ SHIPPING LIST Project No. Site Date Required Shipping Method Approximate Return Date Responsible Supervisor l CERT.
- 3. (7TY. NOMENCIATURE REQ'D SERIAL NO. BCX NO. COST REMARKS O 1 i
l TOTAL COST Audited by: Received by: SwRI Form SS-17-0 Attactunent 1 I O
(~1 Change 1 SOUTHWEST RESEARCH INSTITUTE x111-Ac-toi-o June 1977 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 11 e Q & REC ALIBR ATION NOTICE i
- r. . , .. o.ra .
W hi ' tw ca.w.t ustro actow ou et om .sc.v e.. ? i.. .s i.corso nun e .. r no ., r. r= . . . , .... .... .. u.t. g
- i. - .-. . - . ,., . . . .
7a #A n Y N.\ Cs J / t S v a 1 W l 5 2 t H l
$5 3
i
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. j _s , 1 L D I 2 . - . . s, b Recalibration Notice I
- p '
(SwRI Form SS-42) Attachment 2 l q s.a Form w31 l ! i l l
l l O XIII-AG-101-0 e March 1976 Page 10 of 11 1, i ). HOLD O DO NOT USE ie
- 2 5
m J 1 O C J O Z m O2m O VJ 4 W W m 2 4 Z Attachment 3 9
l XIII-AG-101-0 March 1976 Page 11 of 11 NEW EQUIPMENT N EQUIPME.Vr CONTROL _______q l l _ t INVENTORY I-
' ' RADIATION EQUIPMENT MAINTENANCE 7l STORACE l CONTROL LAB
! ISSUE L _ _ _ _ _ __ _ _I "
f n
-o c EQUIP? O T a USER Attachment 4 O
O SOUTHWEST RESEARCH INSTITUTE E7??**c'101-0 June 1977
% NUCLEAR PROJECTS OPERATING PROCEDURE *I* 1 * '
8 &
- EFFECTIVITY PAGE
- Revision 0 of this Operating Procedure became effective in March 1976. vision 0 consists of the pages and changes listed below. Ei l Page Number Change Revision Effective Date 9 0 June 1977
! 1 1 March 1977 }
o 2-4 5-7 0 1 0 0 June 1977 8 0 0 March 1977 9 1 0 June 1977 I g' 10-11 0 0 hbrch 1977 pf 11a 1 0 June 1977 D [{ p d8~ R 5 4 __ a kP $ \
% I l,
P b s e SwRt Form GA 31
gb SOUTHWEST RESEARCH INSTITUTE xvrt-^c-tot-o March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 1 of ., s DATA STORAGE AND RETRIEVAL o I Y
- 1.0 PURPOSE 3 1.1 This procedure establishes a system for the control and the i s storage of data for nuclear power plant components classified 5 by ANSI N4S.2.9, " Requirements for Collection, Storage, and i [$ Maintenance of Quality Assurance Records for Nuclear Power 3 Plants." This operating procedure satisfies the requirements d .N of Appendix B to 10CFR50, Criterion XVII and the SwRI Nuclear p; Quality Assurance Program Manual.
( s .0 SCOPE AND APPLICATION 2.1 The scope of this procedure is limited to the documentation of n # N
) examinations performed by Nuclear Field Services, Quality Assurance Systems and Engineering Division, and to other 1V ) c documentation as designated by the Vice President, Qaality
'5 I Assurance Systems and Engineering Division.
.t 2.2 This procedure applies to the Data Control Clerk, Team Leaders,
[ Inspection Engineers, and all other personnel who enter and h receive documer.cs from the Data Storage Facility.
; 2.3 Other divisions of the Institute may store quality assurince C
M records for nuclear power plants in the Data Storage Facility. Once these records have been entered in the facility, they will g , be controlled according to this procedure. c'
,3.0 RESPONSIBILITY
'N b
. 3.1 The Manager of Support Services within the Quality Assurance Systems and Engineering Division shall be responsible for the implementation and control of this procedure, j 3.2 The Data Control Clerk of Support Services shall be responsible for controlling, filing, and maintaining documentation covered by 3s (g this procedure in the Data Storage Facility. He shall assume this responsibility when documents are neeived in accordance (q
i
\ with Paragraphs S.1, 5.2, and S.3.
m 5, 3.3 Team Leaders, Inspection Engineers, and other personnel compiling
$ documentation shall be responsible for ensuring completeness and accuracy of documentation being entered into the Data Storage V Facility. (See Section S.O.)
SwRt Fbm QA-3-1
SOUTHWEST RESEARCH INSTITUTE ch=== t O k tR NUCLEAR PROJECTS OPERATING PROCEDURE June 1979 D Page 2 of 7 a h The tfanager of Support Services, or his representative, shall 3.4 J 3 p$ routinely review Section performance against the requirements of 4 this procedure. 3 3.5 The Manager of Quality Assurance, or his designated representative, y, shall routinely audit performance against the requirements of this ' 3 }, procedure and shall report the results of such audits to the Manager of Support Services and the Vice President, QuTlity Assur- { g 3 ance Systems and Engineering Division.
! \
( '
,4 . 0 DATA STORAGE FACILITY DESCRIPTION s 4.1 The Data Storage Facilities for SwRI-retained quality assurance d
records are located in Building 124 and Building 139. The con-struction of Building 124 is concrete block with a steel door kb entrance. The construction of the facility in Building 139 is concrete block with a steel vault door. Both facilities have temperature control devices to regulate temperature and humidity. O PROCEDURE
$ 5.1 Examination data and related material will be listed on a Form SS-1, Records Transmittal and Receipt. Upon completion of the form and arrival at the Institute, the Form SS-1 and related material
- s. Will be delivered to the Data Control Clerk.
8 5.2 Upon receipt of the data, the Data Control Clerk will use the l transmittal form as a checklist to ensure all material listed has been received. The Data Clerk will inventory the data by preparing h a listhg of Summary Sheet numbers or by entering the Summary Sheet number on the weld table. If the Summary Sheet number was previ-ously entered on the weld table, the Data Clerk will ensure that k' , the number is correct. He will also ensure that each Examination
- Data Sheet listed on each Summary Sheet is in the Data package. In those cases where a Summary Sheet is not used or has not been pre-pared at the time of receipt of the data, the Data Clerk will pre-8
- pare a listing showing the number of each data sheet received. The g
completed inventory will be filed with the field data until the final Report is prepared. In addition, the Data Control Clerk will ensure that all documentation to be stored contains the following: N k S #RI frorm QA-31
i
" SOUTHWEST RESEARCH INSTITUTE xvrt-^c-lol-o March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE
, 3 a q n
b
, (1) Reactor Site Name.
g g (2) Date of Record Entry. W \- 5 4 (3) Description of Material. Analog and video tape and strip i i charts will have a complete description of infomation 3 contained therein. This information is entered by the Team j Leader, the Inspection Engineer, o: their designated alternates, s M. The Data Control Clerk will then enter the data into the Data 5 4 Storage Facility. Q 5.3 PSI and ISI reports, other nuclear pow-r plant examination c g reports, examination plans, etc., relating to a particular f I e reactor will be furnished the Data Control Clerk by the Report V } k Coordinator. 5.4 Other recurds designated by the Vice President, Quality Assurance Systems and Engineering Division, as authori:ed for storage in M the Data Storage Facility, will be furnished the Data Control Clerk. 5.5 Items being removed from the Data Storage Facility shall be signed out. The individual withdrawing the material shall be responsible for the safekeeping and return of the material. Original field data will be returned to the Data Storage Facil-c .\" ity at the end of each day. If the d?.ta need to be used after h normal duty hours, special arrangements will be made with the Data Control Clerk. s 4 d
.a y
6 N s bi SwRI Form QA.3-1
SOUTHWEST RESEARCH INSTITUTE xv n-^c-tot-o O March 1976
., NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 7 5 k 3 [ 5.6 The Data Storage Facility will be maintained in a neat and orderly manner. As much as practicable, records will be kept 3
3 inside file cabinets. Loose papers, drawings, etc. shall be placed in folders, binders, or envelopes for filing. a A. i 6.0 RECORDS 5 't i ," 6.1 The Data Control Clerk will maintain an up-to-date list of 3 . records covered by this procedure and their respective locations.
$ 1
( 6.2 Data maintained in the Data Storage Facility will be retained n, for the periods indicated in Appendix A or according to written s instructions furnished the Data Control Clerk at the time the
$[#
records are placed into the Data Storage Facility. The period of retention will in no circumstances be less than the time specified in the applicable contract, if any. 6.3 Project Managers should review the records in the Data Storage 3 g Facility relating to closed projects to determine their ultimate dispositioning; i.e., return to client upon termination of 3
}l a contract, continual storage in the Data Storage Facility, etc.
ky Decisions should be coordinated with the appropriate Director and the Data Control Clerk notified in writing. The Data Control Clerk will comply with the written instructions. m N., , N . n
=
[ s y - h $ E\ u SwRt Fo'em QA.r1 \
XVII- AG- 101-0 March 1976 Paga 5 of 7 Date: RECORDS TRANSMITTAL AND RECEIPT l I From:(Nome of Team Leader Site: To: Data Manager or 1. E.) Olvision 17 SWRI B O X N O. DESCRIPTION OF DATA No. of Volumes Examination Data Sheets No. of Volumes Instrument Calibration Sheets No. of Reels Video Tapes No. of Reels Analog Tapes No. of Rolls Strip Charts No. of Personnel Personnel Certifications No. of Search Units Search Unit Spectrum Analysis and Boom Profile No. of Certs. Material Certi fico flon No. of Certs. Instrument Certifications Yes . List of Procedures l Yes No i Photogrcphs Yes No Scan Plan ( Mechanized) l Other Data and Comments: l l Signature (Team Leader or 1.E.) SwRI FORM FS-1-0
SOUTHWEST RESEARCH INSTITUTE xvit-^c-tot-o O March 1976 NUCLEAR PROJECTS
- OPERATING PROCEDURE I d' Page 6 of 7 0 $
, y APPENDIX A 3
3 The following .is a list of documentation maintained by Data Control in the 3
, Data Storage Facility with retention periods, i
h, .; l- (Record Type Retention Period
) PSI, ISI, and other examination As detemined by the reports Proj ect Manager 3
s k Includes: E Personnel certifications Y D Search unit, material, and instru-
$V ment certifications 3;N Zero reference location I U, Ifeld identification isometric
[, J drawings Calibration standards
% Nondestructive testing procedures ; j (2) PSI, ISI, and other examination As detemined by the e data Proj ect Manager Includes:
8 N Original data e Video tapes e s Analog tapes k\ Eddy current data Eddy current tapes y Strip charts j d Equipment calibration sheets
$p (3) PSI, ISI, and other examination plans ^8 *"i 3 t Flanage T (4) Photographs relating to examination of As determined by the 8 nuclear power plants Proj ect Manager gy (S) Logs, drawings, and summaries created As. determined by the i by field crews during an ISI or PSI Proj ect Manager Swm Foren QA-3-1 Ol l
o Ns SOUTHWEST RESEARCH INSTITUTE SuRl-sDT-900-1 Revision 46
' NUCLEAR PROJECTS OPERATING PROCECURE Page 5 of 6 El f (2) Method and techniques used in the examination. This shall include visual aids, if used.
[ (3) Examination results with location and a description of any abnormalities.
$ Name and certification level of personnel performing the 3 ; (4)
$Ny examination.
3
} (5) Date of examination.
- 90 EVALUATION I Evaluation of reportable indications shall be the responsibility of the f custoner, or the customer's representative, in accordance with Paragraph IWA 3000 of Section XI of the ASME Boiler and Pressure Vessel Code. The h applicable year of the Code shall be as specified in Paragraph 2.l(1) of this
@ procedure.
q < (V i O 10.0 RECORDS r k
) M The customer shall receive copies of documents generated in accordance with this procedure in the examination report.
- Permanent documents generated in accordance with this procedure shall be j s stored and retained as a portion of the examination report. The examination report shall be stored by the Manager of Support Services, Quality Assurance Systems and Engineering Division, in the Data Storage Facility for the period
[ specified by the contractual agreement with the customer. b ,
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5 $ f 1 ; E l h
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f , 1 L/ SwRt Form QA Fi
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W O L F S E H T T A l H I e F O s
- E D
*. - R o E U N P S Y A F T T E G D M A E ( P E L H E H S W T G
N5 ED LL E DW K L C EF O WO L D a C E T D N R O O R A E I H T D s T N A E E 4 S E C T T 2 T T O O A E E D D E M E E L M E H H a R I TSS L R O S C ) E E R O D I R Y
)
- A N T L N O C A O I E U N M T
A R SI O I Y
- C I ID V 6 l
E A F S
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D B K R E e ( O I N A E i E H R C A M T l D T N T A I E _S E N I ( M _E D R S D M . _ A E A HT I D X R U EON RG E D E Z E I L C . S O . V L R P o N E R - R A ) Y OR U t B E A PDE ) S M YNN E I E TUI T S OL V S A L L R A T E E S B V U V E E N N WM O I S L O S
/ L IOA R s TDE ,
E T ARR E E N T T N N COT N w I S ( I L S S OSP LU O N
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s r S F e r t N - ( I s u - O I 7 e T N m y o WA O t e s C I T n n o O A e c L T e
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t a o N N N : O . O R T I D s T I T R F E E A e C A N N . Wm E N IN I E O J I M I D .o M s M I e M A N N A V n O A A I E o R X X X X E R t P E E E
p V SOUTHWEST RESEARCH INSTITUTE xvu-AG-tol-o March 1976 NUCLEAR PROJECTS g OPERATING PROCEDURE Page 7 of 7 2 % Record Type Retention Period 4 8 (6) General information which would be As determined by the of value in conducting future I3Is Proj ect Manager l g, (7) Makeready IS0s and standards Destroy when revised, superseded, 3 or no longer required. Minimum p t retention period is 1 year. h8) Makeready procedures; personnel, Destroy 6 months after issuance
,, material, and instrument certifi- of Final Report.
cations; ar.d other report data s N. 3 (9) Other general information which will Destroy after 2 years.
- not provide valuable information in g conducting future ISI's 3
. O
,k.
L t Q EN s L A.% 1 ( 4 s em , 7 af> Y\ ip ' I [N
$*RI Form QA 3-4
SOUTHWEST RESEARCH INSTITUTE Change 1 XVII-AC-101-0 O [5' , NUCLEAR PROJECTS June 1979 R TQ OPERATING PROCEDURE (I.l '" Page 7a of 7 E EFFECTIVITY s v Revision 0 of the Operating Procedure became effective in March 1976. Revision 0 consists of the pages, changes, and revisions listed below: d Page Number Change Revision Effective Date E j 1 0 0 March 1976 3 2 1 0 June 1979
\through7 0 0 March 1976
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SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURES l . Table of Contents t
, Procedure /Rev. No. Title , 300-2/27. ' Fluorescent Magnetic Particle Examination i
600-5/27 Manual Ultrasonic Examination of Nuclear Reactor Pressure
; Vessel Flange Ligament 600-18/26 . Manual Ultrasonic Examination of Pressure-Retaining Studs
- and Bolts 2" or Greater in Diameter Containing Access I. . Holes i
i 600-19/26 Manual Ultrasonic Examination of Pressure-Retaining Round Nuts Two Inches or Greater in Diameter 4 900-1/46 ~ Visual Examination of Nuclear Reactor Components by Direct or Remote Viewing 4 1 4 I i
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SwRI-NDT-300-2 SOUTHWEST RESEARCH INSTITUTE Revision 27 November 1979
/
k NUCLEAR PROJECTS OPERATING PROCEDURE
- g. Page 1 of 10 FLUORESCENT MAGNETIC PARTICLE EXAMINATION f SwRI-NDT-300-2 8, u b '
1.0 PURPOSE f, { This procedure provides the technical information and detailed steps 3 : required to ensure proper fluorescent magnetic particle examinations of k: ( rromagnetic materials in accordance with the applicable ASME Boiler and FPressure Vessel Codes. s h 2.0 SCOPE AND APPLICATION 1 This procedure shall be utilized for the fluorescent magnetic particle examination of ferromagnetic materials, employing alternating current (AC) yoke p , techniques. i C
3' Areas to be examined shall be components, longitudinal and circumferen-tial welds, butt and fillet welds of branch connections and support attach-3 'ments, and adjacent base material as specified in the applicable SwRI Examina-tion Plan.
2.1 Applicable Documents s 5 The following documents form a part of this procedure as applicable: l (1) ASME Boiler and Pressure Vessel Code, Section XI, 1974 j ] Edition, with Addenda through Summer 1975, " Rules for
! N Inservice Inspection of Nuclear Power Plant Components."
(2) ASME Boiler and Pressure Vessel Code, Section V,1974 Edition with Addenda through Summer 1975, " Nondestructive Examination." (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM). (4) ASTM E138-63, " Standard Method for Wet Magnetic Particle Inspection." 5 p ? \ ,
'nJ
$wAl Form QA 3-1
SOUTHWEST RESEARCH INSTITUTE %"C""7E -' O November 1979 hi NUCLEAR PROJECTS
/ OPERATING PROCEDURE Page 2 of 10 E N 3.0 RESPONSIBILITY fM -
(1) The Director 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. 3 5A > d (2) The Manager of the Nuclear Field Services Section, Department of { \ Engineering Services, shall be responsible for the implementation 3 . of this procedure in accordance with the NQAPM specified in the g applicable SwRI Project Plan. (3) The examiner shall be responsible for implementing the require-3 , ments of this procedure. o e a (4) The Manager of Support Services, Quality Assurance Systems and Engineering Division, shall be responsible for storage of records generated in accordance with this procedure. 4.0 CODE AND PROCEDURE REQUIREMENTS i
% The requirements listed below shall be applied when performing fluores-3 % cent magnetic particle examinations.
Requirements Section 2 og (1)~ Materials, shapes, or sizes to be examined 2.0 & 7.0 (2) Type of magnetization to be used 6.0 g v
= l (3) Equipment 5.0 ]
t (4) Surface preparation (finishing and claaning) 7.0
, (5) Ferromagnetic particles to be used 5.0 j (6) Magnetization current 2.0 & 5.0 (7) Demagnetization 6.0 s
(8) Coverage 7.0 E i . (9) Personnel Certification 5.0 T SwAI Form QA 3-1 e 1
o U SOUTHWEST RESEARCH INSTITUTE C'Z E -2 November 1979 LI - NUCLEAR PROJECTS
/ ,J OPERATING PROCEDURE U k 5.0 PERSONNEL AND EQUIPMENT 5.1 Personnel Certification
[- Personnel performing examinations shall be certified in accor-dance with SwRI NQAP 11-1, "Special Process Control." M' g, 5.2 Yokes E N[ i l AC electromagnetic yokes, with a lifting power of 10 pounds or geaterwhenapolespacingof3to9inchesexists,shallbeused.
?
5.3 Magnetic Particles 3 hv 8 g r. (1) A fluorescent magnetic suspension shall be utilized as the - examination medium. It shall fluoresca with a color that will provide adequate contrast with the background of the area being examined when illuminated by an ultraviolet lamp y of suitable characteristics. v i . g~ (2) Magnetic particles shall be suspended in a suitable liquid ( medium in the concentration recommended in ASTM E138-63, 3
% " Standard Method fer Wet Magnetic Particle Inspection."
Certified reports for magnetic particles, giving batch numbers and analysis results, shall be obtained from the e supplier or by sample analysis of the, batch to be used. 3 Copies of the certified reports shall be retained with the N examination records.
} ! (3) Examinations shall be performed by utilizing one of the d ) materials from the following list:
l N j
; (a) Magnaglo No. 20A fluorescent powder concentrate in a deionized water suspension.
(b) Magnagio No. 14A fluorescent powder concentrate in a 2 deionized water suspension with water conditioner C WA-2A. yv (c) Magnaglo No. 14AM aerosol packaged fluorescent magnetic particle material. E i , O E
$wRI Forrn QA.31
l 1 l r-SOUTHWEST RESEARCH INSTITUTE SwaI-NDT-300-2 Revision 27 Oi NUCLEAR PROJECTS Q OPERATING PROCEDURE
~
Page 4 of 10
$ k (4) If premixed magnetic particle suspension material is not g; used, the magnetic particle suspension shall be mixed in
~
o accordance with the manufacturer's instructions. ) 5.4 Lighting ; Bt I [ . A " black light" shall be used when conducting examinations in 0 ? accordance with this procedure. The " black light" intensity shall be measured 3 4 at the examination surface at least every 8 hours and whenever the work loca-E , tion is changed. These measurements shall be in accordance with SwRI Proce-k N e II-FE-110-0, " Black Light Intensity Measurements." The time of the " black ilight" intensity measurements shall be entered on the "SwRI Magnetic Particle l l I Examination Record." ' I de RN 5.5 Calibration Block A calibration block of a ferromagnetic material weighing a mini-
, mum of 10 pounds shall be used to confirm the lifting power of AC yokes.
C. 5.6 Thermometer E \
$ Quicktemp thermometer Model SX-666, calibrated and certified in accordance with Procedure XII-FM-104-0 shall be used to measure surface l h temperature.
j 6.0 CALIBRATION AND EXAMINATION METHODS 6.1 Calibration a
,E qh (1) The applicable block described in Paragraph 5.5 shall be j q used to verify proper operation of the magnetic particle l
! N yoke when any of the following occur j t l (a) At the start of a series of examinations l
, (b) With any substitution of extmination personnel i E l (c) With any substitution of power source l (d) At least every 4 hours during the examination f N (e) At the finish of a series of examinations 5 (
( i )
, _ .... l
I SwRI-NDT-300-2 SOUTHWEST RESEARCH INSTITUTE aevision 27 November 1979 k NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 10 nm (f) At any time, when in the opinion of the examiner, there is doubt as to the proper operation of the d' - yoke. (2) The time that a magnetic particle yoke is verified shall be g entered on "SwRI Magnetic Particle Examination Record." M
$ 6.2 Examination Method 5
g (1) The examination surf ace temperature shall be measured and g %
- recorded on the "SwRI Magnetic Particle Examination Record." The examiner shall assure the temperature is less than 135'F.
s 5 [& (2) The magnetizing yoke shall be applied twice in each exami-nation area. The second application shell be conducted with the lines of magnetic flux approximately at right 4 angles to those used in the first application. Overlap
$ shall be such as to ensure the entire examination area is o' covered.
N (3) A " black light," as described in Paragraph 5.4 of this
% proceduro, shall be used to illuminate the examination 3 area. A minimum of 5 minutes shall be allowed for warm-up.
s k (4) The magnetic particle suspension shall be applied by C [, flooding the surface of the examination area and then allowing the excess to drain off. a (5) All examinations shall be conducted using the " continuous
- method." The magnetizing current shall remain on continu-g ously during application of the magnetic suspension medium, j i while the excess is being drained, and during the
' observation.
, (6) Af ter draining, the part being examined shall be observed j ,
for indications of discontinuities while the fluorescent lamp is directed from various angles so that the part is illuminat?d over G4 entire surface being examined. I - Obsmations shail be made in a darkened area within the plant and shall c ommence approximately 5 minutes af ter the j space is darkened, in order for the examiner's eyes to
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$wAt Form QA.M l
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SOUTHWEST RESEARCH INSTITUTE swal-sDr-3*-2 Revision 27 O NUCLEAR PROJECTS g OPERATING PROCEDURE Page 6 of 10
$ b (7) Variable electromagnetic yoke pole spacing shall be a 3 ,
maximum of 9.0 inches, measured on the material surface, o i between the centerline of the poles. The distance measured
' between the centerline of the poles shall not exceed 6.0 s inches under any circumstances.
Be I ; (8) Demagnetization of the examination area is not required. 7.0 EXAMINATION t k ' 5 7.1 Examination Areas Examinations shall be performed on materials in their completed 8 ,. condition. o r~ 7.1.1 Surface Preparation
, (1) It shall be the responsibility of the customer, or the o customer's representative to ensure that the examina-3' tion area and a minimum of one inch on each side shall be l
y q clean, dry, free from oil, sand, rust, grease, paint, slag, loose scale or other conditions which may mask the indica-q tion of unacceptable discontinuities. 3 (2) After slag removal, as-welded surfaces shall be considered i suitable, without grinding, if the weld contour blends into the base material without undercutting.
] (3) The examination area of welds and adjacent base materials j g] shall be free from sharp surface irregularities such as 'i deep valleys between stringer beads.
l j E 7.1.2 Welds and Base Material
. (1) The examination area for circumfarential and longitudinal welds shall be the weld and adjacent base material for a j distance of it to either side of the weld fusion line. i (2) The examination area for branch pipe connections shall include the weld and adjacent base material for a distance l of it from the weld fusion line on the main run pipe and at J
" least 2 Inches of the base material along the branch run.
I 5 , 3
$wRI Form Q A.31 O
)
e SOUTHWEST RESEARCH INSTITUTE s R1-NDT-3w -2 Revision 27 N NUCLEAR PROJECTS OPERATING PROCEDURE
" Page 7 of 10 0! k (3) The examination area for support attachments shall include s d the weld and base material of the main'run pipe for a o distance of it from the weld fusion line, and the base material of the support attachuant for a distance of two times the support thickness from the weld fusion line.
3 If the base material thickness is less than 1/2 inch, the [. C, (4) examination area shall include the weld and adjacent base jh material for a minimum distance of 1/2 inch on each side of j, the weld fusion line. ( 4 % 7.1.3 Threaded Components i e CAUTION O h Extreme care should be exercised to prevent damage to threaded components during handling and examination. ('N o4 \ ; 3 The entire surface of studs, bolts, or cap screws and the entire l', . outer surface of nuts for studs, bolts, or cap screws shall be examined. 2 %" 7.2 Examination Data
% The completed "SwRI Magnetic Partic1- '5 amination Record" shall j contain, but not be limited to:
(1) Identification of the extxi d ".rt and the extent of the g i examination, including surfa6e preparation, if required
'E j MN (2) Equipment used in the examination
! Method and technique used in the examination, includ-i I (3)
^ ' ing visual aids, if used
, (4) Examination results with location and a description of any j ,
abnormalities (5) Name and certification level of personnel performing the
}
examination f E (6) Date and time.of examination 5 (7) Any examination limitation
,, , 3 SwRI Form QA 31
r j l l l SOUTHWEST RESEARCH INSTITUTE S RI-uDT-300-2 Revision 27 O
*** *# l' '
h NUCLEAR PROJECTS
,n OPERATING PROCEDURE ,
Page 8 of 10
$ h (8) Lo location h , (9) Wo location (10) Temperature of the examination surface I
h (11) Yoke verification times ) E g g (12) Black light verification times 2
} % 7.3 Postexamination Cleaning Arrangements shall te made with the customer for postexamination
. removal of fluoreccent magnetic particle materials.
E
% 8.0 RECORDING CRITERIA 8.1 Base Materials, Studs, Nuts, and Cap Screws
$ The following indications shall be recorded on the "SwRI Magnetic Particle Examination Record" and reported to the customer:
3 % (1) Any linear indications greater than 1/16 inch long for , materials less than 5/8 inch thick; greater than 1/8 inch '
} long for materials from 5/8 inch thick to 2 inches thick;
. and 3/16 inch 1cng for materials 2 inches thick and ;
i 3 g greater. (2) Rounded indications with dimensions greater than 1/8 inch l
! for thicknesses less than 5/8 inch, and rounded indications l
- E with dimensions greater than 3/16 inch for thicknesses 5/8 l
' inch and greater. I 3 l i
j t (3) Four or more indications in a line separated by 1/16 inch or less edge to edge. l l { (4) Ten or more indications in any 6 square inches of area 0' whose major dimension is no more than 6 inches with the dimensions taken in the most unfavorable location relative to the indications being evaluated. a (5) Any linear indication appearing in the thread root area of 5 studs and cap screws. 3 (6) Any linear indication appearing in the head-to-shaft junction of cap screws. Swm Form QA.31
1 n v SOUTHWEST RESEARCH INSTITUTE swr 1-uDT-300-2 Revision 27 NUCLEAR PROJECTS g OPERATING PROCEDU'1E Page 9 of 10 m
- y 8.2 Welds s .
d . The following indications shall be recorded on the "SwRI Mag-netic Particle Examination Record" in accordance with SwRI Procedure II-FE-105-0 and reported to the customer: [B , (1) Any cracks or linear indications.
)
1
% (2) Rounded indications with dimensions greater than 3/16 inch.
I (3) Four or more rounded indications in a line separated by 1/16 inch or less edge to edge. { C % h (4) Ten or more rounded indications in any 6 square inches of surface with the major dimension of this area not to exceed 6 inches when the area is taken in the most unfavorable location relative to the indications being evaluated. \ 9.0 EVALUATION jk N Evaluation of reportable indications shall be the responsibility of the customer, or the customer's representative, and shall be conducted in accordance with Article IWA 3000 of Section XI of the ASME Boiler and Pres-Y sure Vessel Code. The applicable year and Addenda of the Code shall be as specified in Paragraph 2.l(1) of this procedure. s 5 10.0 RECORDS g u The customer shall receive copies of documents generated in accordance I with this procedure in the examination report. i il
! Permanent documents generated in accordance with this procedure shall be j stored ar.d retained as a portion of the examination report. The examination report shall be stored by the Manager of Support Services, Quality Assurance Systems and Engineering Division, in the Data Storage Facility for the period
,specified by the contractual agreement with the customer.
5' b, t E i
=
Q/ swste Form QA-3-1 l
Sw. R. I. MAGNETIC PARTICLE EXAMIN ATION RECORD PROJECT No.: SITE: DATL. (DAY- MO - YR ) TIME:(24 HR. CLOCK) SHEE T No.: EX AM STARTED: EXAM ENDED: EX AIAIN ATION ARE A: LINE / SUB ASEEMBLY: IDENTIFIC AT10ti: L o LOCATION: Wo LOC ATION : (SYS r E M /CO MPONE NT ) EXAMINER: SNT LEVEL PNOCEDuflE SURFACE FINISH: WELD TYPE (-FLOW +) M AGNETIZ ATION YOKE SPACING: IN N o. E X AIAIN E R: SNT LEVEL REV- M ATE RI AL SERI AL No.: ORAND: WET O DRV O SURFACE TEMP. *F Call 8R ATION BLOCK CALIBRATION VERIFICATION DISTANCE FROM BATCH No.: FLUORESCENT O -
' "*' 0 ' "
TIME: TO SENS0 TYPE: NIXED N00 YESO T HE ftM0 MET ER INITIALS CELL IN COLOR: MIXED WITH SERI AL No.: WillGitT : DLACK LIGitT INTENSITY METER BLACK LIGliT OUTPUT QLACK LIGHT OUTPUT VERIF. M ATERI AL DUSTING O APPLICATION: BRAllD: BR AND: T if4E : FLOODING O P W/C m' INITIALS: SPRAYING O SERI AL No.: SERI AL No.: IND No. L W LOCATION "M ,,0 " N#[,8[^6 REMARKS: INI. l EX AMIN ATION ARE A LIMITATION: (IF NONE SO STATE ) EEEE
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- a. I REVIEWED BY: SNT LEVEL DATE: PAGE OF $776 O
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SwRI-NDT-600-5 SOUTHWEST RESEARCH INSTITUTE Revision 27 March 1979 b NUCLEAR PROJECTS
/ OPERATING PROCEDURE Page 1 of 14 3 f s' W c' D '
MANUAL ULTRASONIC EXAMINATION OF NUCLEAR REACTOR PRESSURE VESSEL FLANGE LIGAMENTS SwRI-NDT-600-5 w 5 n 11 . 0 PURPOSE k a This procedure provides the technical information and detailed steps 7 equired to ensure proper manual ultrasonic examination of reactor pressure vessel flange ligaments in accordance with the applicable ASME Boiler and 8 I, Pressure Vessel Codes. C y' 2.0 SCOPE AND APPLICATION s (1) Reactor pressure vessel flange ligaments shall be examined in J o, $ accordance with this procedure. Areas to be examined shall be as
! specified in the applicable SwRI Examination Plan.
5 '
}. (2) The ultrasonic examinations shall be perfomed using a longie M tudinal-wave , straight-beam, manual, contact, pulse-echo technique.
Y This technique has been selected for the purpose of locating flaws
, y oriented parallel to the threads and propagating from the thread root.
2.1 Applicable Documents
! ~# The following documents form a part of this procedure as % applicable:
1 i (1) ASME Boiler and Pressure Vessel Code, Section II, 1974 Edition with Addenda through Summer 1975, " Rules for N Inservice Inspection of Nuclear Power Plant Components."
. k 5 ( (2) 'ASME Boiler and Pressure Vessel Code, Section V, 1974
% Edition with Addenda through Summer 1975, "Nondestruer.ive Examination."
, (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM).
$ 4 f'
O " Swm Form QA-3-1
SwRI-NDT-600-5 SOUTHWEST RESEARCH INSTITUTE Revisi- 27 March 1979 L Tq NUCLEAR PROJECTS
/p j OPtiRATING PROCEDURE Page 2 of 14 E b 3.0 RESPONSIBILITY j ,, L (1) The Director of the Department of Engineering Services, Quality a Assurance Systems and Engineering Division, shall be responsible for the preparation, review, approval, and control of this m
procedure. k The Manager of the Nuclear Field Services Section, Department of 4 [ (2) Engineering Services, shall be responsible for the implementation g
; ] of this procedure in accordance with the SwRI NQAPM specified in ,j %
the applicable SwRI Project Plan. N L (3) The examiner shall be responsible for implementing the require-3 i ment.s of this procedure. c k1 s (4) The Manager of Support Services, Quality e.ssurance Systms and Engineering Division, shall be responsible for storage of records generated in accordance with this procedure. c-4.0 CODE AND PROCEDURE REQUIREMENTS
!! % The requirements listed below shall be applied when perforhing manual 2
% ultrasonic examinations in accordance with this procedure.
Y Requirements Section
$ (1) Configurations to be examined 7.0 (2) No welds shall be examined -
e
$ (3) Automatic defect alarm and recording equip- -- ] ment shall not be used E
3 (4) Search unit wedges, shoes, or saddles 5.0 g (5) Rotating, revolving scanning mechanisms - s ; shall not be used a [ (6) Personnel certification 5.0
, (7) Examination surface or surfaces 7.0 E
E - (8) Surface finish 7.0 E u 2 swr 6 Form Q A.31 O
O SOUTHWEST RESEARCH INSTITUTE SuR1-xDr-600-5 2evision 27 March 1979 N NUCLEAR PROJECTS
/ OPERATING PROCEDURE page 3 og 14 E [ (9) Couplant 5.0 (10) Method used 2.0
, (11) Technique used 2.0 (12) Calibration method and method of 5.0, 6.0 m I correlating indications with defects 8.0, 9.0 N
l (13) Scanning 1.0 8'
% . (14) Mode of transmission 2.0
. (15) Type and size of search unit 5.0 m e o o s (16) Examination frequency 5.0 (17) Ultrasonic instrument align =ent 5.0 '
)s3 N
( 5.0 PERSONNEL AND EQUIPMENT
@%% 5.1 Personnel Certification y Personnel conducting ultrasonic examinations shall be certified in accordance with SwRI NQAP 11-1, "Special Process Cottrol."
8 4 3 k 5.2 Reference Block
, The reference' block used for screen distance calibration and j verification shall be an IIW block (Sketch 1).
I 3 5.3 Basic Calibration Block 2 3 The basic calibration block shall be a threaded calibration block
- as used for the reactor pressure vessel stud examinations. Calibration reflec-ors shall be notches machined 1 thread deep or 1/8-inch deep, whichever is 2 smaller. Notches shall be measured from the thread root, and shall follow the a
3 pitch angle of the threads. The distance of these reflectors from the surface at which the search unit is applied shall be such that a distance amplitude correction (DAC) curve can be established covering the anticipated examination distance. An example of a basic calibration block is shown in Sketch 2.
~3 f Approved drawings of the basic calibration block are contained in the applicable SwRI E < amination Plan.
g I I B 4 SwRt Form QA.J.!
O SwRI-NDT-600-5 SOUTHWEST RESEARCH INSTITUTE aevision 27 March 1979 9 NUCLEAR PROJECTS e k
.w OPERATING PROCEDURE Page 4 of 14 E N 5.4 Search Units s
j, b (1) The search unit size shall be 3/4" or 1" round. (2) The nominal search unit frequency shall ba 2.25 MHz. O 5.5 Ultrasonic Instrument p J The examiner shall select an appropriate ultrasonic instrument j from the following:
* (1) Sonic FTS Mark I g (2) Sonic FTS Mark II O h (3) Sonic UWA Mark III Each instrument shall be aligned and display an alignment y calibration sticker as required by NQAP 10-1.
2 3 g 5.6 couplant a 2 H (1) USP grade glycerine or deionized water (with or without y wetting agent) shall be used when performing ultrasonic calibrations and examinations in accordance with this
.', procedure.
o (2) Couplant materials used for examinations shall be the same
, as used in the calibration.
t
$ (3) Light oil or other compounds, which in the opinion of the ]
Level II examiner provide adequate ultrasonic coupling, may J .be used upon concurrence of the section manager responsible 3 for the examination. (4) All couplants other than deionized water shall be certified 2 'l for sulfur content and total halogens in accordance with C [ 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, whea used, shall be supplied by the customer. E c M w SwRI Form Q A-3-1 3
q; {' ' '> SwRI-NDT-600-5 SOUTHWEST RESEARCH INSTITUTE Reviston 27 March 1979 h NUCLEAR PROJECTS
/ j OPERATING PROCEDURE Page 5 of 14 E 6.0 CALIBRATION METHOD j The complete ultrasonic examination system calibration shall be performed Q'. prior to the examination.
NOTE [ k 3 L The " REJECT" control shall be maintained in the "O" position h during calibration and examination. y 6.1 Distance Calibration
t h' A
- Select the shortest screen size that includes at least a distance 3 equal to 1.5 times the diameter of the stud. Observing back reflections from an IIW block, adjust the " MATERIAL CALIBRATION," " DELAY," and " RANGE" controls 3
[} so that the sound path distance is displayed linearly along the screen base-line. Full screen sweep distance shall be 10 or 20 inches. Ol J g 5 6.2 Distance Amplitude Correction (DAC) g (1) Position search unit on top surface of appropriate basic
; calibration block to obtain maximum response from the 3 % reflector producing the highest amplitude.
Y ( 2). Adjust signal amplitude to obtain primary reference 3 response 80% 5% of full screen height (FSH) and mark the 3 amplitude on the instrument screen.
, . (3) Without changing gain controls, position search unit to y obtain maximum response froi each of the remaining re-3 % flectors.
3 5 (4) Mark the respective amplitudes on the instrument screen and 3 join the points with a snooth curved line.
\
, (5) This DAC shall cover at least a distance equal to 1.25 2 i times the diameter of the stud.
[ Secondarv DAC Calibrations 6.3 j If all points on the DAC curve do noc appear at 20% or greacer of E C
} FSH, a secondary DAC curve shall be constructed as follows:
= 1 P
\d N
.g .
SwAI Form QA-31
SwRI-NDT-600-5 SOUTHWEST RESEARCH INSTITUTE Revision 27 March 1979 NUCLEAR PROJECTS
/[h J
OPERATING PROCEDURE Page 6 of 14 (1) All secondary DAC curves shall contain at : east 2 points. 4 j, s - (2) The DAC point at 2 lines or greater in amplitude and adja-N cent to a DAC point that falls below 2 lines of amplitude shall be brought c' the primary reference level by manip-3 ulating the gain control. This point shall be marked on R , the instrument screen. The adjacent point (s), previously ( , at less than 2 lines of amplitude, shall be marked on the j M screen and each point connected with a smooth line. The 2 gain setting for this secondary DAC curve shall be recorded b % on the SwRI Instrument Calibration Record. b '. EXCEPTION 2 U-t o h 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 and marked on the screen. The other points, previously at less than 2 lines of amplitude, 5 shall be marked on the screen and each point connected with 3 a smooth curved line. The gain setting for this secondary
% DAC curve shall be recorded on the SwkI Instrument Calibra-g g tion Record.
Y 6.4 Sweep Range and DAC Curve Verification g Sweep range calibration shall be verified on the appropriate o W reference block and DAC curve calibration shall be verified on the appropriate basic calibration block when any of the following occurs: I (1) Start of a series of examinations g c j a , (2) 2 Substitution of search unit cabic 5 (3) Substitution of power source
;C- (4) At least every 4 hours during the examination I } l m (5) At the finish of a series of examinations l 1
j (6) At any time when, in the opinion of the examiner, there is doubt as to the validity of the calibration E e .b n w SwRt Form QA 31 e
SwRI-NDT-600-5 SOUTHWEST RESEARCH INSTITUTE nevision 27 March 1979 b NUCLEAR PROJECTS OPERATING PROCEDURE Page ~ of 14
, a r_ 6.4.1 Calibration Changes j - (1) Perform the following if any point on the DAC curve has decreased more than 20% or 2 dB in amplitude, or any point on the sweep line has moved more than 5% of full screen
, width: ,
~
/ (a) Void all examinations referring to the calibraticn in
()K j ij question and performed af ter the last valid caliFra-tion verification. d % (b) Conduct a new calibration. 3 I, (c) Reexamine the areas for which the examinations have 8 been voided. (2) Perfor:n the following if any point on the DAC curve has increased in amplitude more than 20*. or 2 dB: 3 (a) Correct the calibration. (b) Reexamine all indications recorded since the last 3
% valid calibration verification.
Y (c) Enter proper values on a new "SwRI Ultrasonic 3 Examination Record for Bolting." C E 6.4.2 Recalibration s g Substitution of any of the following shall be cause for
= '
recalibration:
]
5 (1) Search unit (shoe / transducer) 8 g (2) Couplant { 3 (3) Ultrasonic instrument k Examination personnel (4) i
; 6.5 Calibration Data E i l' 9 Calibration data shall be recorded on the SwRI Instrument 5c Calibration Record and shall include, but not be limited to:
g I l M Q SwRI Form QA-34
SwRI-NDT-600-5 i SOUTHWEST RESEARCH INSTITUTE Revisie 27 March 1979 NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 14 7& w
- v Serial number of the basic calibration block used c) (1) j (2) Serial number of the IIW block used (3) Type, and serial number of the ultrasonic instrument h (4) Type, size, beam angle, and serial number of the ultrasonic search unit j .
jh ' (5) Nocinal search unit frequency (6) Couplant (which shall be the same type as used in the actual examination) s (7) 3 {h Signature and ultrasonic certification level of examiner making calibration (8) Date calibrated 5 1 (9) Time of calibration and verification (s). k' g 7.0 EXAMINATION
- li M
g 7.1 Examination Area a The area to be examined shall be at least 1 inch on all sides of 5 )' the threaded stud hole and shall include 100% of the ligament area between threaded stud holes. This examination shall include a depth equal to at least the diameter of the stud. g
?,
m Manual ultrasonic examination of nuclear reactor pressure vessel l flange ligaments shall be performed from the top surface of the vessel flange. j Examinations shall be performed on ligaments in their completed condition.
% Attempts to determine differences in the acoustic properties s between the basic calibration block and the production material which would i ? result in an instrument grin change are not permitted.
t 7.2 Surface Conditions
. The contact surfaces must be free from weld spatter, rough-5 '! ness, or other conditions which interfere with free movement of the search unit I or impair the transmission of ultrasound.
f h. 4 G Swm Form GA-34 h
o \"' SOUTHWEST RESEARCH INSTITUTE swRl- = -6* -5 Revision 27 March 1979 g NUCLEAR PROJECTS OPERATING PROCEDURE
, g.
Page 9 of 14
* %D 7.3 Scanning E
Oy When practicable, scanning shall be performed at a minimum gain setting of 2 times the reference level sensitivity, Scanning overlap shall be a minimum of 10% of the search unit [jRyiezoelectric element dimension perpendicular to the direction of the scan. SN I Instrument gain setting for scanning shall be determined on the 3 basic calibration block as follows for each primary reference level utilized.
} N E (1) With the instrument at the primary reference level, manipu-late the search unit on the basic calibration block to I o- obtain a signal from a calibration raflector (nocch) of 40%
%" FSH. .
(2) Add 6 dB of gain by utilizing the fine gain control only.
< Observe the signal amplitude.
v 3 (3) Add 6 dB of gain by utilizing a combination of both fine {g and coarse gain controls. Observe the signal amplitude. I h (4) Add 6 dB of gain by utilizing the 6 dB switch, if present. N Observe the signal amplitude, j, (5) Ch'oose the method above which yields a signal response closest to 80% FSH. l (6) The method chosen shall then be used during the valid 3 calibration period for all scanning at 2 times the
~
reference sensitivity. j - The examiner shall ensure that the signal response of the method chosen is within 2 dB of 80% FSH and record this amplitude and method on the N wR1 Sonic Instrument Calibration Record."
)' The search unit movement rate for scanning shall not exceed 6 inches per second.
7.4 Postaxamination Cleaning j' Arrangements shall be made with the customer for postexami-nation removal of couplant materials. y
.l ,
(.- 6 Swat Form QA J 1
SwRI-NDT-600-5 SOUTHWEST RESEARCH INSTITUTE aevision 27 March 1979 r
~
L 5 NUCLEAR PROJECTS l
/ g OPERATING PROCEDURE Page 10 of 14 E b3.0 RECORDING CRITERIA
, Ultrasonic reflectors producing a response 50% or greater of the refer-ence level shall be recorded on the "SwRI Ultrasonic Examination Record for Bolting. -
, Indications producing a response 100% or greater of the reference level g, shall be investigated by a Level II or Level III examiner to the extent g %,lnecessary to determine the shape, identity, and location of the reflector, e .
fr 4be Indications 100% or greater of ret?rence level investigated and found to
% other than geometrical in nature shall be reported to the customer for evaluation.
= I 2 ' Any scanning limitations shall be recorded.
9.0 EVALUATION g Evaluation of indications shall be the responsibility of the customer, or i the customer's representative, and shall be conducted in accordance with the E ASME Boiler and Pressure Vessel Code, Section XI, Article IWA-3000. The appli-
- f. h cable year and Addenda of the Code shall be as specified in Paragraph 2.1(1) of 2 this procedure.
Y 10.0 RECORDS , 8 >' d The customer shall receive copies of documents generated in accordance with this procedure in the examination report. j Permanent documents generated in accordance with this procedure shall be a: stored and retained as a portion of the examination report. The examination
} report shall be stored by the Manager of Support Services, Quality Assurance i Systems and Engineering Division, in the Data Storage Facility for the period 3 specified by the contractual agreement with the customer. ,
M 2 s ' 0 . e E 1 l A l g J , c.
) l l
Sw Al Form QA-3-1 l 1 m l
SwtI-NDT-600-5 Revision 27 March 1979
' *" "
- f 1'
_IIW REFERENCE ELOCK D. _._ do so- so- L l b i'ra
! A
. IV TYPE 1
.12 5' l2 =
l l
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e I i - l TYPC 9 ) S l l l l 6 i
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.i 6 60' 70* I 5
i l 0 1 3 E y .09jg 9 L 8 t i It t i NOTE: M9 IIW APPP(MD Fi:stni.NCE ELOCKS wm1 SL!GMTLY Ons-ENT CMENSiCNS CR CSTAtG CALERATiCN SLOT F:JTURES ARE PERMGSSLE. SKETCH 1
SwRI-NDT-600-5 Rsvision 27 March 1979 Page 12 of 14 O \ 1
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a) G Sw.R.I SONIC INSTRUMENT CAllBRATION RECORD PIOJECT No a SIT E s OATL (DAY- MON -YR.) ' ilMEs (24 IIR CLOCK) SilEEf No.
- 8) E X A MINER:(SIGNATURE) SNT LEVEL PROCEDURE IN3TRUME N Ts SERIAL No.
CALIBRATION VERIFICATION goNigARK No.
- 2) EX A MINER s ( OPER ATOR ) SNT LEVEL C g' ig REV, OTilF R (S PECIFY)
S E A R Cil UNITS VERIFICATION BLK S/N s SwRI No. INiilALS NOMINAL ANGLE MEASURED ANGLEt E X AMINA TION AR E A (S) e MEASURED ANGLE SIGNAL AMPLITUDE 1 RAND SERIAL NUMBER (SCREEN DIVISIONS)s SIGNAL DISTANCE (INlt _, SCREEN DIVISIONSs
~
COARSE RANGE: SI Z E s d B COARSE: NOM:N A L FRE041ENCY (MilZ): d 8 FINEe INSTRUMENT SETilNOS 100 g -y ; q-90 - - '- -4 -
-t - T-REJECTe 80 TO
-l-
-l-
-l-
-+-
-g- q-
-r- -+-
FINE d 88 60 -l- -- -g- -j- -g-COARSE dus 50 -*- -T- - r- t- t-FREQUENCYa -l-
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DELAY: REMARKSs i MAT,L CALe 20 -j- -l-i0 +-
-l-+
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+ -)-
C! ANGE a O ! ! b -' l- m*g:oin BAMPlNO s IN C elES OF METAL
- 9 ::
M 7 ca z REP RAIE, SCHEEN DIVISIONS s w e-* O d
*D LONGITUDINAL Cl SIIEAR O o 7 i
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Sw.R.I. ULTR ASONIC EXAMIN ATION RECORD FOR BOLTING PROJECT No. SI T E: DATE'( UAY - MON -YR. ) reut tre un - CLocal 'SH EET No. SMEET STAR TED SHEff E N0f D COMPONENT SUB ASSEMBLY 0 0 E " 'd "0" 8 L e LOCAT80" ". LOC'3 80" EX AMINER SNT LEVEL PROCEDURE CAllBRATION SHEEl(S) ANGLE 0' 45* 60* OTHER DI A MET ER No USED E X A MIN ER : SNT LEVEL REV. SC A NNihG dB IND /* W MAX Lg L SEARCH REMARLS OF L2 Na NAX UNIT DAC W MP ANGLE 5h$$ o S. p.e
* .A VwoB R EVIEWED bye O SNT LEVEL: DATE "*U$
V $ u FORM he. Se R.I. hD T A IF-IF ( A EW. 4-s-Ps) O O O
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f '~ ,'4 SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-6ao-18 Revision 26 N NUCLEAR PROJECTS
., n. OPERATING PROCEDURE Page 1 of 16 M [ MANUAL ULTRASONIC EXAMINATION OF PRESSURE-RETAINING s STUDS AND BOLTS 2" OR GREATER S IN DIAMETER CONTAINING ACCESS HOLES SwRI-NDT-600-18 ,
M fQ a l.0 PURPOSE This procedure provides the technical information and detailed steps
-} b ired to ensure proper ultrasonic examination of pressure-retaining studs
' nd bolts, in accordance with applicable ASME Boiler and Pressure Vessel Codes, j 2.0 SCOPE AND APPLICATION ,,
(1) Pressure-retaining studs and bolts 2 inches or greater in diameter
/7 I ,
h N with access holes shall be examined as specified in the applicable SwRI Examination Plan. 1, c $ x'./ -
? (2) Shear-wave angle-beam, manual, contact pulse-echo ultrasonic exami-f nation techniques utilizing the SwRI Manual Stud Examination Probe j y have been selected for the purpose of locating flaws in an orienta-tion perpendicular to the axis of the stud and propagating from the
.M thread root. l i
j 9,1 Applicable Documents The following documents form a part of this procedure as l l applicable: G i f (1) ASME Boiler and Pressure Vessel Code, Section XI, 1974
~[
Edition with Addenda through Summer 1975, " Rules for s Inservice Inspection of Nuclear Power Plant Components." (2) ASME Boiler and Pressure Vessel Code, Section V, 1974 j( Edition with Addenda through Summer 1975, " Nondestructive , j {; Examination **
-(3) U. S. Atomic Energy Commission Regulatory Guide 1.65 dated
{ October 1973, " Materials and Inspections for Reactor Vessel l i 4 Closure Studs." m
!: (4) SwRI Nuclear Quality Assurance Program Manual.
5 n . k l Q ,l g l Y l SwM Form QA.J.1 l l
r-SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-18 Revision 26 March 1979 N% > NUCLEAR PROJECTS t.R d@ OPERATING PROCEDURE P.ge 2 of 16 0 s f 3.0 RESPONSIBILITY h ' 0 (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible s for the preparation, review, approval, and control of this
!, procedure.
b S (2) The Manager of the Nuclear Field Services Section, Department of 3 N ' Engineering Services, shall be responsible for the implementation [ of this procedure in accordance with the NQAPM in effect on the date this procedure is approved. E (3) The examiner shall be responsible for implementing the require-j y ments of this procedure. (4) The Manager of Support Services, Quality Assurance Systems and Engineering Division, shall be responsible for storage of records g generated in accordance with this procedure. 4.0 CODE AND PROCEDURE REQUIREMENTS i
- l W The requirements listed below shall be applied when performing manual
> ultrasonic examinations in accordance with this procedure.
Requirements Section
~
4 (1) Configurations to be examined 7.0
~
l (2) No welds shall be examined -- 3 ; 9 (3) Automatic defect alarm and recording equip- --- j ; ment shall not be used i
~
(4) Search unit wedges, shoes, or saddles 5.0 3 $ (5) Rotatine, revolving scanning mechanisms -- 3 sh.11 not be used (6) Personnel certification 5.0 I g j (7) The examination surface or surfaces 7.0 e )
$ (8) Surface finish 7.0 g (9) Couplant 5.0
=:
$wRt Fcem QA 3 ]
O l L
o t
> SOUTHWEST RESEARCH INSTITUTE S Rl-NDT-600-18 Revision 26 March 1979 NUCLEAR PROJECTc
/ ,g
~'
OPERATING PROCEDURE Page 3 of 16 8 7 (10) Method used 2.0 (11) Technique used 2.0 (12) Calibration method and method of correlating 5.0, 6.0, p - indications with defects 8.0, 9.0
=3 (13) Scanning 7.0 e '
i (14) Mode of transmission 2.0 N (15) Type and size of search unit 5.0 f 4 (16) Examination frequency 5.0 (17) Examinations . .1 be cond'icted on studs and --- ( < k t bolts in their completed condition ( s' $ (18) Ultrasonic instrument alignment 5.0 2 f 5.0 PERSONNEL AND EOUIPMENT j 5.1 Personnel Certification
, Personnel performing ultrasonic examinations shall be certified j in acesedance with SwRI NQAP 11-1, "Special Process Control."
. 5.2 Reference Block j Reference blocks used for screen distance calibration and veri-3 , fication shall be as follows:
i j - (1) ' SRI Half-Round (Sketch 1) (2) AWS Type DC (Sketch 2) n (3) IIW (Sketch 3). {< The reference block shall be of the same basic mattrial as the production material, e.g., carbon steel. E I g 2 Reference blocks shall be used as follows for screen distance if calibt?. ion: ( \ E v} SwAl Form QA 3-1
SOUTHWEST RESEARCH INSTITUTE SwRI-unT-600-18 Revision 26 7 March 1979 Mg NUCLEAR PROJECTS OPERATING PROCEDURE Sg$J
'b TO 23 Page 4 of 16 M
[ Angle-Beam
% s c
. . Screen Block t s Distance Block Type Dimension 2
5.0" SwRI Half-Round AWS Type DC 1.0" Radius 1.0" and 2.0" Radii
? 10.0" AWS Type DC 1.0" and
- 2.0" Radii
! IIW Block 4.0" Radius 3 SwRI Half-Round 1.0" Radius c N 4 20.0" IIW 4.0" Radius 5.3 Bas 3 . Calibration Block c
3 The basic calibration block shall be fabricated from material
- j. ,which is acoustically similar to the component to be examined. It shall be
( % threaded as the component and have an access hole equal in size to that of the 2 qcomponent to be examined. The basic calibration reflectors shall be notches y machined one thread deep, or 1/8-inch deep, whichever is smaller. Notches shall be measured from the base of the thread root and follow the pitch angle 3 % of the threads (Sketch 4). The particular notch utilized for the calibration, 5 h as stated in Paragraph 6.2 of this procedure, shall be identified on the SwRI Instrument Calibration Record.
$ Approved drawings of the basic calibration block are contained in d the applicable SwRI Examination Plan. ; Q.
I \ 5.4 Search Units s (1) The search unit shall have an active element size of 1/4 x 3 1/4 inch or 1/4 inch round.
- k d 4 (2) A special search unit wedge shall be used to' produce a 60* 2' refracted shear-wave. This angle and the exit ,
point of the sound beam shall be determined on an IIW I
-] block. l E $
j ' (3) The nominal search unit frequency shall be 2.25 MHz. i V l D G SwRt Form QA 31 l
o(
/
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-6oo-18 Revision 26 March 1979
+ NUCLEAR PROJECTS
/ $ OPERATING PROCEDURE UJ$ Page 5 of 16
. 5.5 Ultrasonic Instrument s '
k The examiner shall select an appropriate ultrasonic instrument
'from the following:
(1) Sonic-FTS Mark I q (2) Sonic FTS Mark II h (3) Sonic UWA Mark III. Each instrument shall be aligned and display an alignment calibration stickar as required by NQAP 10-1. h N( - 2 5.6 Couplant (1) USP grade glycerine or deionized water (with or without / < wetting agent) shall be used when performing ultrasonic C' S
- 4 calibrations and examinations in accordance with this Q procedure.
s M f q (2) Couplant materials used for examinations shall be the same as used for the calibration. Y
,, (3) Light oil or other compounds, which in the opinion of the j! Level 11 examiner provide adequate ultrasonic coupling, may be used upon concurrence of the section manager responsible for the examination.
I
.! + (4) All couplants other than deionized water shall be certified I 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. 1 Deionized water, when used, shall be supplied by the l
[ e. customer. b 5 6.0 CALIBRATION METHOD 3 The complete ultrasonic examination system calibration shall be performed prior to the examination. 5- . E 2 / i Q.) % l Q
$wRI Form Q A-3+1 I
I l I
SOUTHWEST RESEARCH INSTITUTE swr 1-NDT-600-18 Revision 26 March 1979 r9,
.- % NUCLEAR PROJECTS
[ ' OPERATING PROCEDURE Page 6 of 16 { NOTE s n' Y< The " REJECT" control shall be maintained in the "0" y, position during calibration and examination. n - Calibration of the ultrasonic instrument shall be accomplished with the hbasiccalibrationblockinaverticalposition. N[ j
, 6.1 Distance Calibration i
%' Using the applicable reference b%ck selected in accordance with
. Paragraph 5.2, adjust instrument " MATERIAL CALIBRATION," " RANGE," and " DELAY" t
controls so that the sound path distances are displayed linearly along the g i a screen baseline. The screen distance chosen shall be the smallest applicable O f size which includes at least 10% of the screen distance past the examination area. y 6.2 Distance Amplitude Calibration Position the SwRI Manual Stud Examination Probe in the access I , hole of the basic calibration block to obtain maximum response from the notch j reflector nearest the center of the threaded portion of the block. Adjust amplitude of this signal to 75% 25% of full screen height (FSH) and mark this
\, amplitude on the instrument screen. This is the primary reference response.
g Indications shall be recorded as a percentage of this signal amplitude. The jlg area to be examined shall extend no more than 20% of the wall thickness to y either side of the calibration point. [ 6.3 Sweep Range and Distance-Amplitude Calibration Verification
% Sweep range and distance amp'~.ude calibrations shall be veri- ) fied on the appropriate reference and basic calibration block when any of the i following occur: e 1
(1) At the start of a series of examinations
. T j i (2) Substitution of search unit cable 9
(3) Substitution of power source f (4) At least every 4 hours during the examination
= 1 ! 2 (5) At the finish of a series of examinations 5$
g' (6) At any time when, in the opinion of the examiner, there is
. any doubt as to the validity of the calibration.
Sw R t F oe m Q A 3 3 L _
p 's' SOUTHWEST RESEARCH INSTITUTE SwRl-uDr-6oo-18 Revision 26 M^rCh 1979 N' NUCLEAR PROJECTS l.R OPERATING PROCEDURE u e @,, Page 7 of 16 8 k* 6.3.1 Calibration Changes (1) Perform the following if any point on the DAC curve has decreased more than 20% of 2 dB in amplitude, or any point M on the sweep line has moved.more than 5% of full screen
% ', width: -
8 - z C' 3 h i (a) Void all examinations referring to the calibration in quertion and performed after the last ' valid calibra-1 tion verification.
%gA, (b) Conduct a new calibration.
j 4 (c) Reexamine the areas for which examinations have been voided. , (2) Perform the following if any point on the DAC curve has p) \ U y increased in amplitude more than 20% or 2 dB: i (a) Correct the calibration. I y y (b) Reexamine all indications recorded since the last valid calibration verification. (c) Enter proper values on a new "SwRI Ultrasonic Exami-j { nation Record for Bolting." 6.3.2 Recalibration I J Substitution of any of the following shall be cause for
; recalibration:
)
j (1) Search unit (wedge / transducer) h (2) Couplant
= b j- T (3) Ultrasonic instrument b
(4) Examination personnel. 6.4 Calibration Data
$ 3 Calibration data shall be recorded on the SwRI Instrument Cali-5- bration Record, and shall include but not be limited to:
S., . , > n
%/
$wRI Form QA 31
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-18 Revision 26 O March 1979
.$7' aw NUCLEAR PROJECTS t,F M: OPERATING PROCEDURE
# Page 8 of 16 E
3 (1) Serial number of the basic calibration block used b (2) Type and serial number of the reference block used (3) Type and serial number of the ultrasonic instrument k p (4) Type, size, be.im angle, and serial number of the ultrasonic 3 N search unit (5) Nominal search unit frequency (6) Couplant (which shall be the same type as used in the actual examination) c o
- (7) Signature and ultrasonic certification level of the examiner conducting calibration g (8) Date calibrated 5
i (9) Time of calibration and of calibration verification s q (10) The particular notch utilized for the calibration. 4,
- 7.0 EXAMINATION i
3 N 7.1 Examinatiin of Pressure-Retaining Studs and Bolts Studs and bolts shall be examined from the inside surface of the
! access hole. The examirition shall be conducted in a manner to assure 100 per-
! cent coverage (with the exception of the nonloadbearing portion beyond the nut)
]; of the areas from which indications as described in Paragraph 2.0(2) may propa-ij gate inward. Calibration shall be in accordance with Paragraphs 6.1 and 6.2.
.! I F
( 7.2 Surface Conditions
; The contact surfaces must be free from roughness or other condi-a g ti'ns which interfere with free movement of the search unit or impair the tra.'smission of ultrasound.
.j 7.3 Scanning Parameters 1 When practicable, scanning shall be performed at a minimum gain E 3 5 t setting of 2 times the reference level sensitivity.
N 9 SeRI Form Q A 31 e
~
O SOUTHWEST Ri SEARCH INSTITUTE SwaI-sot-600-18 Revision 26 NUCLEAR PROJECTS
< .wm OPERATING PROCEDURE Page 9 of 16 s t Instrument gain setting for scanning shall be determined on the
; l basic calibration block as follows for each primary reference level utilized:
o. (1) With the instrument at the primary reference level manip-
- ulate the search unit on the basic calibration block to g '
obtain a signal from a calibratioit reflector (notches) of
- y. 40% FSH.
%{
! y (2) Add 6 dB of gain by adjusting the instrument fine gain control only. Observe the signal amplitude.
{ \
! (3) Add 6 dB of gain by adjusting a combination of both fine and coarse instrument gain controls. Observe the signal o
b amplitude. (4) Add 6 dB of gain by manipulating the instrument 6 dB switch, if present. Observe the signal amplitude. [ !?' (5) Choose the method above which yields a signal response closest to 80% FSH and record this method and amplitude on I the SwRI Instrument Calibration Record. (6) The method chosen shall then be used during the valid lg \ calibration period for all scanning at 2 times the i l reference level sensitivity. I i s I The examiner sh'all ensure that the signal response of the method l chosen is within 22 dB of 80% FSH. The search unit movement rate shall not exceed 6 inches per !
; "second.
j
^
, Scanning overlap shall be a minimum of 10% of the search unit ;
piezoelectric element dimension perpendicular to the direction of scan. l
- -\ Attempts to determine differences in the acoustic properties
, 6 j between the basic calibratio" block and the production material, which would l D{ result in an instrument gain change, are not permitted. !
t 7.4 Postexamination Cleaning f Arrangements shall be made with the customer for postexamination
$],
~
removal of couplant materials.
/% ,A l SwRt Form QA.31
SwRI-NDT-600-18 SOUTHWEST RESEARCH INSTITUTE aevi i= 26 March 1979 h NUCLEAR PROJECTS g'5 OPERATING PROCEDURE Page 10 of 16 8.0 RECORDING CRITERIA s' s o' ; Ultrasonic reflectors producing a response of 50% or greater of the reference level shall be recorded on the appropriate "SwRI Ultrasonic Exami-nation Record and Bolting." f f . Indica. cions producing a response 100% or greater of the reference level ds shall be investigated by a Level II or Level III examiner to the extent
..j b' necessary to determine the shape, identity, and location of the reflector.
Indications 100% or greater of the reference level, investigated and nd to be other than geometrical in nature, shall be reported to the customer for evaluation. i $v C j^ Scanning limitations shall be recorded. D 9.0 EVALUATION c Evaluation of indications shall be the responsibility of the customer, or j the customer's representative, and shall be conducted in accordance with the g g ASME Boiler and Pressure Vessel Code, Section XI, Article IWA 3000. The appli-3 y cable year and Addenda of the Code shall be as specified in Paragraph 2.l(1) of this procedure. y i.. 10.0 RECORDS I 0-g The customer shall receive copies of documents generated in accordance w ith this procedure in the examination report. Ig Permanent documents generated in accordance with this procedure shall be j stored and retained as a portion of the examination report. The examination
! , report shall be stored by the Manager of Support Services, Quality Assurance j
Systems and Engineeiing Division, in the swr 1 Data Storage Facility for the period specified by the contractual agreement with the customer. s ,o M f
- e. I a
y d SwRl F oem Q A-31 G
SwRI-NDT-600-18 Rtvision 26 March 1979 Page 11 of 16 em N (j\ s u; O X
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.V SwRI-NDT-600-18 Revision 26 March 1979 Page 13 of 16 IIW REFERENCE ELOCK T' b- .io' io' e'o' L
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1 l Sw.R.I. ULTRASONIC EXAMIN ATION RECORD FOR BOLTING PROJECT No. SIT E: DAT - DAY - MON -Y R. ) reut(24udctatsi SHEET 110. Ste t E T S'Anigr
$NI&T 'P ef D COMPONENT SUB ASSEMBLY 0 6 E " """ " 8 L e #"*" "* '8"' 80" EX AMINER s SNT LEVEL PROCEDURE 'l CAllBRATION SHEET (S) ANGL E 0* 45' 60*l OTHER DI A M E T ER No USED EXAMINER: TNT LEVEL REV. SC A NNING dB (ND /* W MAX Lg L SEARCH REMARKS L2 N o~
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- SvRI-NDT-600-19 SOUTHWEST RESEARCH INSTITUTE Revist- 26 March 1979 [b NUCLEAR PROJECTS
/ OPERATING PROCEDURE Page 1 of 19
= y o MANUAL ULTRASONIC EXAMINATION OF PRESSURE
, RETAINING ROUND NUTS 2 INCHES OR GREATER IN DIAMETER Q ' SwRI-NDT-600-19 k '
e W }1.0 PURPOSE k This procedure provides the technical information and detailed steps
- required to ensure proper manual ultrasonic examination of pressure-retaining g
round nuts in accordance with the applicable ASME Boiler and Pressure Vessel i sR Code. 9 2.0 SCOPE AND APPLICATION h j< (1) Pressure-retaining round nuta 2 inches or greater in diameter shall o be examined in accordance with this procedure and as specified in the SwRI Examination Plan. I
) Q (2) The ultrasonic examinations to be performed shall use longitudinal-wave straight-beam and shear-wave angle-beam, manual, contact,
\ pulse-echo techniques. These techniques have been selected for locating flaws both parallel and transverse to the longitudinal
, axis of the nut, including flaws extending from the thread root areas, g 2.1 Applicable Documents C '
} .
The following documents form a part of this procedure as j applicable: t
- h (1) ASME Boiler and Pressure Vessel Code, Section XI, 1974
\ Edition with Addenda through Summer 1975, " Rules for . $ Inservice Inspection of Nuclear Power Flant Components."
o T
* (2) ASME Boiler and Pressure Vessel Code, Section V, 1974 Edition, with Addenda through Summer f973, "Nondestruc-tive Excmination."
E Y
=
5 Swat Form GA.31
SOUTHWEST RESEARCH INSTITUTE RUIfs -" O March 1979 rg NUCLEAR PROJECTS
/
OPERATING PROCEDURE Page 2 of 19 m O (3) U.S. Atomic Energy Commission Regulatory Guide 1.65 dated R . October 1973, " Materials and Inspections for Reactor Vessel pk - Closure Studs." (4) SwRI Nuclear Quality Assurance Program Manual (NQAPM). g 3.0 RESPONSIBILITY (1) The Director of the Department of Engineering Services, Quality
.5 i Assurance Systems and Engineering Division, shall be responsible k,
for the preparation, review, approval, and control of this pro-cedure. 3 , (2) The Manager of the Nuclear Field Services Section, Department of 5 8 Engineering Services, shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan. y q (3) The examiner shall be responsible for implementing the require-o ments of this procedure.
. (4) The Manager of Support Services, Quality Assurance Systems and 3 V Engineering Division, shall be responsible for storage of records y generated in accordance with this procedure, s 4.0 CODE AND PROCEDURE REQUIREMENTS d k The requirements listed below shall be applied when performing manual
~
3 ultrasonic examinations in accordance with this procedure. e i i Requirements Section
?
j
, (1) Components and configurations to be ext. mined 7.0
, (2) No welds shall be examined --
R 2 j (3) Automatic defect alarm and recording - Q equipment shall not be used f (4) Search unit wedges, shoes, or saddles 5.0 I (5) Rotating, revolving scanning mechanisms -- S E shall not be used O SwRl Form QA.J.3 t l L-
i $ SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-19 a- ision 26 l March 1979 ! NUCLEAR PROJECTS [YEl ., OPERATING PROCEDURE Page 3 of 19 l 8 n [ y (6) Personnel certification 5.0 l g, . o (7) The examination surface or surfaces 7.0 l (8) Surface finish 7.0 i
!s (9) Couplant 5.0 9 N j d (10) Method used 2.0 k (11) Technique used 2.0 g
(12) Calibration method and method of correlating 5.0, 6.0, i te indications with defects 8.0, 9.0 o gn r4 (13) Scanning 7.0 O , M (14) Mode of transmission 2.0 (15) Type and size of search unit 5.0
} .
(16) Examination frequency 5.0 M Y (17) Examinations shall be performed on components - in their completed condition
$ (18) Ultra:.onic instrument alignment 5.0
~
g 5.0 PERSONNEL AND EQUIPMENT t 5.1 Personnel Certification
} ,
f
, Personnel conducting ultrasonic examinations shall be certi-fied in accordance with SwRI NQAP 1'-1. "Special Process Control."
^
b 5.2 Reference Blocks Y
'O Reference blocks used for screen distance calibration and veri-fication shall be as follows:
,[ (1) SwRI Half-Round (Sketch 1)
(2) AWS Type DC (Sketch 2) G w 3 SwAl Porri QA-3-1
SwRI NDT-600-19 SOUTHWEST RESEARCH INSTITUTE Revision 26 March 1979 ($ NUCLEAR PROJECTS
/ OPERATING PROCEDURE w Page 4 of 19 E IIW (Sketch 3)
(3) p s (4) Radius Surface Reference (RSR) (Sketch 4) s Reference blocks shall be of the same basic material as the [ production material, e.g., carbon steel. h Reference blocks shall be used as follows for screen distance g - g calibration: a f (5) Straight-Beam
- Screen Block
. j Distance Block Type Dimension o o 4 2.5", 5.0" SwRI Half-Round, 1.0" AWS Type DC 1.0" IIW l.0" y RSR 1.0" a
g 10.0" IIW 4.0" 4 7
'3 W (6) Angle-Beam Y Screen Block g e D,istance Block Type Dimension o b 2.5" t 5.0", 10.0" RSR 2.5" Radius x 5.3 Basic Calibration Block A
j The basic calibration block for both straight- and angle-beam shall be a threaded calibration block representing the acoustic and geometric gropseties of the pressure-retaining round nut being examined. Calibration 4: reflectors for straight-beam shall be notches in the threaded bore machined to { y a depth of one thread or 1/8 inch whichever is smaller, measured from the b thread root and following the pitch angle of the threads. The straight-beam calibration reflectors shall be located such that a distance amplitude correc-tion (DAC) curve can be established including the anticipated examination distance. The angle-beam reflector shall be a notch transverse to the direc-A tion of the threads machined to the base of the thread root t.005 inch. An j example of a basic calibration block is shosn in Sketch 5. Approved drawings
,E ,
of the basic calibration block are contaisi in the applicable SwRI Examination
% Plan.
Db D SwRI Form QA 31
]
SOUTHWEST RESEARCH INSTITUTE '""I~ITU - March 1979
'b - NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 19 N N 5.4 Search Units j
+ (1) Search units shall be selected from the following sizes:
1/4" R, icud i 3/3" l'J od 1/2" Roh.sd o% 7 3/4" Round 5 N j (2) The contact surfaces of the angle beam search unit wedges {s , shall conform to the surface of the nuts being examined, The angle of search unit wedges shall be determined as follows: 2 5 ga h (a) Using a scale drawing of the pressure-retaining round
" nut, determine the angle required to produce a sound beam in the nut tangent to the inner bore.
y (b) Position the search unit on the RSR block and obtain i che maximum response from the 2.5-inch radius. Using
$ the index groove at the 2.5-inch radius, mark the exit
( point of the sound beam on the search unit wedge. W y (c) Place the search unit on the RSR block and peak the signal from the 1/2-inch diameter hole. Using the s}'} portion of the scale located closer to the 1/2-inch 8 t diameter hole, read the refracted angle at the exit f point of the search unit. This angle is the actual refracted beam angle and shall coincide by 2* with j the angle determined in 5.4(2)(a) above. e
]
(3) A search unit producing O' longitudinal-waves shall also be 5 used. 8 (4) The nominal search unit frequency shall be 2.25 MHz. k { 4 5.5 Ultrasonic Instrument D The examiner shall select an appropriate ultrasonic instrument j from the following: a (1) Sonic FTS Mark I c 4 (2) Sonic FTS Mark II (3) Sonic UWA Mark III 3 SwRt Form QA.31
SwRI-NDT-600-19 SOUTHWEST RESEARCH INSTITUTE Revision 26 March 1979 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 19 W E [.bration stickerEach instrument shall be aligned and display an alignment cali-as required by NQAP 10-1. g ,'
, 5.6 Couplant (1) USP grade glycerine or deionized water (with or without h wetting agent) shall be used when performing ultrasonic calibrations and examinations in accordance with this 4 procedure.
g N e / ff (2) Couplant materials used for examinations shall be the same D % as used in the calibration. L
. I (3) Light oil or other compounds, which in the opinion of the j
h Level II examiner provide adequate ultrasonic coopling, may be used upon concurrence of the section manager responsible for the examination.
< (4) 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.
9 Deionized water, when used, shall be supplied by the y customer. 3 'Lh 6.0 CALIBRATION METHOD E i The complete ultrasonic examination system calibration shall be per-formed prior to the examination. e d NOTE 1 i The " REJECT" control shall be maintained in the "O" position 3 during calibration and examination. Thc "FREQ MHz" control shall be turned to "2" when a 2.25 MHz s k search unit is used. E t O 6.1 Straight-Beam Distance Calibration Observing back reflections from the applicable reference block, J .' adjust the " MATERIAL CALIBRATION," " DELAY," and " RANGE" controls of the ultra-j sonic instrument to obtain the required linear sound path distance, displayed
? along the screen baseline. The screen distance chosen shall be the smallest applicable size to include at least 10% of the screen distance past the lase calibration point.
swr $ Form QA-31
v
/G.
!" SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-19 aevision 26 March 1979 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 19 8 k 6.2 Straight-Beam Distaace Amplitude Correction 8 - (1) Place search unit on the basic cali'uation bicek surface W corresponding to the examination contact surface. Posi-tion search unit to obtain maximum response from the
,' reflector producing the highest amplitude.
b
= - (2) Adjust signal amplitude to obtain primary reference response hy a
) at 80% 5% of full screen height (FSH) and mark the ampli-tude on the instrument screen.
h , % % (3) Without changing gain controls, position search unit to obtain maximum response from each of the remaining re-3 flectors. 8 + (4) Mark respective amplitudes on the instrument screen and join the points with a smooth curved line extended to include the anticipated examination distance. O () 6.3 Angle-Beam Distance Calibration Using the shear-wave angle-beam search unit and radius echoes from 3 the ESR block, adjust instrument " MATERIAL CALIBRATION," " DELAY," and " RANGE" y y controls to obtain the required linear sound path distance displayeo across the screen baseline. The screen distance chosen shall be the smallest applicable , 3 , size to include at least 10% of the screen distance past the examination area. ! 8 % 6.4 Angle-Beam Distance Amplitude Correction l s 5 (1) Position search unit on the outer cylindrical surface of the l d out basic calibration block and obtain maximum response from '
] ,
the notch transverse to the direction of the threads. j i < d (2) Adjust instrument gain controls to display this reference
\ notch at the primary reference response of 80% 5% FSH and
, mark amplitude on the instrument screen. The area to be s 4 examined shall extend no more than 20%'of the wall thickness 1 0
h co either side of the calibrated point. 6.5 Secondary DAC Calibration for Straight Beam 1 l 2 If all points on the straight beam DAC curve do not appear at 20% , j 1 of FSH or greater, a secondary DAC curve shall be constructed as fallows: ) 1 (1) All secondary DAC curves shall contain at least 2 points.
\j '
swRI Form QA 3-1 r._-- _._-- - , , - - -
! SwRI-NDT-600-19 SOUTHWEST RESEARCH INSTITUTE Revision 26 March 1979 h NUCLEAR PROJECTS
/ OPERATING PROCEDURE Page 8 of 19 El
[ (2) The DAC point at 2 lines or greater in amplitude and adja-cent to a DAC point that falls below 2 lines of amplitude g , o g shall be brought to the primary reference level by manip-ulating the instrument gain controls. This point shall be marked on the instrument screen. The adjacent point (s), pre-
}) ,
viously at less than 2 lines of amplitude, shall be marked on the screen and each point connected with a smooth curved
$s%' line. The instrument gain setting for this secondary DAC ] cur re shall be recorded on the SwRI Instrument Calibration Record.
y ext.EPTIONS i > Mien 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 be marked on the instrument screen. The other point (s) previously at less y than 2 lines of amp?.',tude shall be marked on the screen and C '
each point connected with a smooth curved line. The instru-ment gain setting for this secondary DAC curve shall be recorded on the SwRI Instrument Calibration Record. s f 6.6 Sweep Range and DAC Curve Verification Sweep range and DAC curve calibration shall be verified on the j [ appropriate reference and basic calibration 'alock when any of the following occurs: 1 (1) Start of a series of examinations (2) Substitution of search unit cable (3) Substitution of power source (4) At least every 4 hours during the examinations
. r-3 (5) At the finish of a series of examinations (6) At any time when, in the opinion of the examiner, there is doubt as to the validity of the calibration.
a : c 4 e E n 4 SwRI Form QA 31
/'s k 'I
' SwRI NDT-600-19 SOUTHWEST RESEARCH INSTITUTE Revisi- 26 M4rch 1979 S'. NUCLEAR PROJECTS g OPERATING PROCEDURE Page 9 ot 19 m -
- 6.6.1 Calibration changes j/ g. (1) Perfora the following if any point on the DAC curve has decreased more than 20% or 2 dB in amplitude, or any point on the sweep line has moved more than 5% of full screen p width:
P - b . (a) Void all exauinations referring to the calibration in { N a question and performed after the last valid calibration verification. 9 A
,, (b) Conduct a new calibration.
3 (c) Reexamine the areas for which examinations have been d
- voided.
4 (2) Pertc.rm the following if any point on the DAC curve has iner,,ased in amplitude more than 20% or 2 dB:
$ (a) Correct the calibration, k
4 (b) Reexamine all indications recorded aince the last 3
- y velid calibration verification.
Y (c) Enter proper values on a new SwRI Examination Record. 2 3 % 6.6.2 Reralibration
. Substitution of any of the following shall be cause for re-calibration:
f c
] / (1) Search unit (wedge / transducer) s -
3 (2) Couplant 1% y (3) Ultrasonic instrument l s N l 5 k (4) Examination personnel. l l E c 4 4 6 ) G
$wRt Form QA.31
SwRI NDT-600-19 SOUTHWEST RESEARCH INSTITUTE Revision 26 March 1979 h gg
/ "v NUCLEAR PROJECTS OPERATING PROCEDURE Page 10 of 19
-g h_. 6.7 Calibration Data
. 4 d Calibration data shall be recorded on the SwRI Instrument Calibration Record and shall include, but not be limited to:
b (1) Type and serial number of the reference block used. r4) (2) Serial number of the basic calibration block used. j
< \
(3) Type and serial number of the ultrasonic instrument. N *
% Type, size, angle produced, and serial number of the sear:h
; (4) unit.
I de C { (5) Nominal search unit frequency. (6) Couplant used (which shall be the same type as used in the
, actual examination).
o I (7) Signature and ultrasonic certification level of examiner making calibration.
- E
%. (8) Date calibrated.
Y (9) Time of calibration and calibration verifications. 0 I " 7.0 EXAMINATION
~
g 7.1 Examination Area i j ' The combination of angle-beam and straight-beam examinations shall j be such that a 100% coverage of the pressure retaining round nut is attained. t 7.2 Surface Conditions { The contact surfaces of the nut must be free from roughness or j T foreign particles which interfere with free movement of the search unit or 1 impair the transmission of ultrasound.
, 7.3 Scanning fj ,f f When practical, scanning shall be performed at a minimum gain setting two times the reference level sensitivity.
p . s SwRI Form QA 31 I:..
SwRI-NDT-600-19 SOUTHWEST RESEARCH INSTITUTE aevision 26 March 1979 NUCLEAR PROJECTS OPERATING PROCEDURE Fage 11 of 19 U ki. basic calibration Instrument gain setting for scanning shall be determined on the block as follows for each primary reference level utilized: E E (1) With the instrument at the primary reference level s manipulate search unit on the basic calibration block to N obtain a signal from a calibrstion reflector (nocch) of 40%
%. FSH.
(2) Add 6 dB of gain by utilizing the fine gain control only. 5 J Observe the signal amplitude, h 3 ' (3) Add 6 dB of gain by utilizing a combination of both fine and coarse gain contrcls. Observe the signal amplitude, 8 s & (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
}y closest to 80% FSH.
'5 k (6) The method chosen shall then be used during the valid
$ calibration period for all scanning at 2 times the reference 3
W 1evel sensitivity. Y (7) The examiner shall ensure that the signal response of the 3 method chosen is within 2dB of 80% FSH and record this 3 amplitude and method on the SwRI Instrument Calibration Record, Instrument gain settings for scanning shall be recorded on the
=
f
$ appropriate SwRI Examination Record.
3 2 Search unit movement rate for scanning shall not exceed six inches 3 'per second.
\ Scanning overlap shall be a minimum of 10% of the search unit f
2 A piezoelectric element dimension perpendicular to the direction of the scan. o a 7.3.1 Straight-Beam N.ition the O' longitudinal-wave search unit on the end (top or
# , bottom) of the pressure-retaining round nut which has the most favorable Scanning shall
} J examination surface with respect to the geometry of the nut.
include 100% coverage of the appropriate surface, or such a portion that is E Q accessible. G q-k SwRt Form QA.31
SOUTHWEST RESEARCH INSTITUTE UEEEU ~" O
. March 1979 h NUCLEAR PROJECTS OPERATING PROCEDURE Page 12 of 19 E k4 .
7.3.2 Angle-Beam , kY Position the shear-wave search unit on the outer cylindrical
$ surface of the nut such that the sound beam follows the direction of the s threads and examine the thread root area for the full ciret=rference and length of the nut. Turn the search unit 180* and repeat the above examination.
P
- p .
7.4 Postexamination Cleaning
> Arrangements shall be made with the customer for postexamina-g '
gonremovalofccuplantmaterials. s
- 1. 0 RECORDING CRITERIA 2
3 & Ultrasonic reflectors producing a response 50% or greater of the
~ reference level shall be recorded on the "SwRI Ultrasonic Examination Record for Bolting."
y g Indications producing a response 100% or greater of the reference level i shall be investigated by a Level II or Level III examince to the extent necessary to determine the shape, identity, and locatioti of the reflector. 3 Indications 100% or greater of the reference level investigsted and found y y to be other than geometrical in nature sh 'l be reported to the customer for evaluation, s 3 $ Scanning limitations shall be recorded. 9.0 EVALUATION c . Evaluation of indications shall be the responsibility of the customer, or
] % the customer's representative, and shall be conducted in accordance with the 1 ASME Boiler and Pressure Vessel Code, Section XI, Article IWA 3000. The 3 applicable year of the Code shall be as specified in Paragraph 2.l(1) of this grocedure.
2 d 10.0 RECORDS d f b The customer shall receive copies of documents generated in accordance with this procedure in the examination repor*..
~
s Permanent documents get ersted in accordance with this procedure shall be
! stored and retained as a portion of the examination report. The examination gEj repott shall be i cored by the Manager of Support Services, Quality Assurance Systems and Engi.eering Division, in the Data Storage Facility -for the period specified by the. contractual agreement with the customer.
SwRt Irorm QA 31
SwRI-NDT-600-19 Rsvicion 26 March 1979 Page 13 of 19 O 0 u V h i O
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t U SOUTHWEST RESEARCH INSTITUTE SuRr-NDT-900-1 Revision 46
' ' I NUCLEAR PROJECTS OPERATING PROCEDURE Page 1 of 6 4 b s VISUAL EXAMINATION OF NUCLEAR REACTOR COMPCNENTS
$ g BY DIRECT OR REMOTE VIEWING
- SwRI-NDT-900-1 I
g, 1.0 PURPOSE e w { g {fre This procedure provides the technical information and detailed steps w % quired to ensure ponents the proper in accordance with visual examination the applicable ASMEofBoiler nuclear andpower plant Pressure Vessel LCodes. j 2.0 SCOPE AND APPLICATION (1) Direct and remote visual techniques for the examination of nuclear
,h power plant components are described 4.n this procsdure.
O < f S (2) Components and welds to be examined are specified in the applicable SwRI Examination Plan.
- s 2.1 Applicable Documents
\ The following documents form a part of this procedure, as p applicable:
hh 5 (1) ASME Boiler and Pressure Vessel Code, Section XI,1974 Edition, with Addenda through Summer 1975, " Rules for j Inservice Inspection of Nuclear Power ?lant Components." 3 i (2) ASME Boiler and Pressure Vessel Code, Section V, 1974 l Edition with Addenda through Summer 1975, "Nondestruc-j tive Examination." N (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM). s k a 4 3.0 r RESPONSIBILITY (1) The Director of the Department of Engineering Services, Quality y Assurance Systems and Engineering Division, shall be responsible
, 'l for the preparation, review, approval, and control of this j procedure.
[5 p
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g Swas Form QA+3,1
t r SOUTHWEST RESEARCH INSTITUTE SwRl-NDr-900-1 Revision 46 O
/
b NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 6 0 h" (2) The Manager of the Nuclear Field Services Section, Department of 3 Eogineering Services, shall be responsible for the implementation a g r,f this procedure in accordance with the NQAP.4 specified in the applicable SwRI Project Plan. g (3) The examiner shall be responsible for implementing the require-ments of this procedure. { 3 %) (4) The Manager of Support Services, Quality Assurance Systems and Engineering Division, shall be responsible for storage of records
}g % generated in accordance with this procedure.
'4.0 CODE AND PROCEDURE REQUIREMENTS I
q The requirements listed below shall apply when performing visual exami-nations in accordance with this procedure. Requirements Section
E (1) Personnel certification 5.0 3fN M (2) Examination area 7.0 W
Y (3) Surface condition and cleaning requirements 6.0 j (4) Examination method 6.0 (5) Equipment 5.0 I 6.0 C (6) Lighting requirementr. (7) Resolution 6.0 50 PERSONNEL AND EQUIPMENT I A
\ The Visual Examination Acceptability Test Card shall be made from Kodak j Neutral Test Card No. R-27 or an equivalent, with an 18:: neutral grey side having a 1/32-inch-wide black line down the center.
Commercially available equipment shall be used as required for the per-formance of examinations or operations by the techniques described in Para-j graphs 6.1, 6.2, and 6.3. {
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4 2 Swal 9orm GA 3-5 9 L
g U SOUTHWEST L(. SEARCH INSTITUTE S""'Z1 - July 1979 NUCLEAR PROJECTS JPERATING PROCEDURE Page 3 of 6 E b Pecsonnel performing examinations shall be certified in accordance with
,s SwRI NQAP 11-1, "Special Process Control."
[ , 6.0 EXAMINATION METHOD g 6.1 Surface Cleaning X* . L Visual examinations which require clean surfaces or decontamina-g N tion for valid interpretation of results shall be preceded by appropriate cleaning processes.
% 4
; Examinations may be required where the surface is painted o~ has
'other types of coatings. This shall be permitted if it is determined ths., such s coatings do not interfere with valid interpretation of results.
O g' 6.2 Direct Visual Technicue h Direct visual examination shall be performed by placing the eye [s y 4 within 24 inches of the surface to be ex. mined and at an angle no less than V 1 30 degrees.with the 'rf ace to be examine ' Mirrors may be used to improve the
\ angle of vision, and aids such as magnifying lenses may be used.
y L 3 Y 6.2.1 Lighting In add'ition to the general lighting, illumination of the area to s g be examined shall be provided at right and oblique angles to expose cracks or c evidence of corrosion or erosion. 6.2.2 Resolution a c Resolution shall be considered adequate when the combination of
)
j % , access, lighting, and angles of vision, either unaided or corrected, can resolve a black line, 1/32-inch-wide, on an 18% neutral grey card placed on the
- surface to be examined.
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6.3 Remote Visual Technique
' M
- ( Remote visual examination may be used where conditions exist that do not permit direct visual examination. Remote visual examination may include visual aids such as rolescopes, periscopes, borescopes, fiber optics, or TV
'{ etmeras and monitoring systems, with or without attachments for permanent E re cording. Remote techniques shall demonstrate the ability to provide a reso-
! it,cion at least equivalent to that obtainable by direct visual examinscion.
j, R.rrors, movable lights, or rotating optics, or any combination thereof, may be n D employed to display cracks, surface scratches, or evidence of corrosion, ero-( sion, misalignment, or movement. V
- 5*M Form QA-31 4
i SOUTHWEST RESEARCH INSTITUTE Swal-aT-900-1 Revision 46 O July 1979 Y#h
- NUCLEAR PROJECTS
. OPERATING PROCEDURE
'~ -? Page 4 of 6 8 T* 6.3.1 Resolution o Resolution shall be considered adequate when the combination of access, lighting, and angles of vision, either unaided or corrected, can resolve a black line, 1/32-inch-wide, on an 18% neutral grey card placed on the
- p. surface to be examined or in a situation similar to the area to be visually
-examined.
O )
~ % 6.4 Replication h % Surface replication techniques shall be considered acceptable provided the surface resolution is at least equivalent to that obtainable by direct visual technique.
s qe g 7.0 EXAMINATION AREAS
. Components, parts and areas to be ext.nined shall be as specified in the , applicable Examination Plan. Remote visual examinations utilizing mechanized c scanning devices shall be as specified in the applicable Scan Plan. Scanning
- 3 parameters, if required, for the remote visual examination, shall be included f 9 in the applicable SwRI Scan Plan.
3 Y The examination area of welds shall include the weld and the adjacent g v base material for at least one wall thickness beyond the edge of the weld. s jM ; The examinations described in this procedure are designed to determine the general condition of the reactor component, part or surface to be exam-ined. These general conditions shall include scratches, wear, cracks, corro-sion or erosion on the surface. Evidence of leaking, misalignment and relative [ movement of the part or component shall also be toted. j , i j 8.0 RECORDING CRITERIA 3
^
Indications shall M recorded in accordance with the techniques cutlined
'in IX-FE-105-0, " Recording Data From Direct Visual, Liquid Penetrant, and Mag-
. R netic Particle Examination of Welds."
C
- Visual abnormalities shall be recorded on the "SwRI Visual Exanination Record" and reported to the customer.
, The completed "SwRI Visus 1 Examination Reccrd" shall contain, but not be j:,
, linited to, the following information:
si (1) Identification of the examined part and the extent of the examina-D tion, including surface preparation, if required. a SveAl Form GA M G I I l l I
1 e l
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i l 1 i APPENDIX D ULTRASONIC CALIBRATION BLOCK DRAWINGS 1 i AND CERTIFICATIONS ) ): 1 4 , a i J e i 4 t I i i. } l 9 f i 1 I i
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'N ACCORDANCE WITH THE M AT ERI ALS SPECIFICATION S EC T IO N H OF THE ASME BOILE R AND PRESSURE VESSEL CODE .
*SA 540 material specification for bolting material does not have a P-Number classification.
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. SOUTENEST RESEARCH INSTITUTE 34270Sw CUSTOMER'S ORDER NO SAN ANTQfIO, TEXA3 OTHER ORDER NCo PR61373 NUMSER OF PA*TS. THREE (3) we men., ciene, v=ar n.e caers oescm.e. we.e oeven t=e souown.o went veranne., PART NUM8ERS, SEE SUPLIMENT nans Ar meat COOLANT ,
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SOUTHWEST RESEARCH INSTITUTE P-NUMBER CLASSIFICATION FOR CALIBRATION STANDARDS Call 8 RATION STANDARD
. - - -P N IS HEREBY CLASSIFIED AS P-NUM8ER *N/A GROUP -
IN ACCORDANCE WITH SECTION 2 E DITIO N OF THE ASME BOILER AND PRESSURE VESSEL CODE . THE P - NUM B ER CL ASS!FIC A TlON FOR THIS CAllB RATION S TP-:DARD IS SUBSTANT!ATED WITH THE A T T ACH E D CHEMICAL ANALYSIS REPORT FOR SA 540
'N ACCORDANCE WITH THE M ATERIALS SPECIFICATION SECTION U OF THE ASME BOILE R AND PRESSURE VESSEL CODE .
*SA 540 material specification for bolting material does not have a P-Number classification.
/
( SIGN ATURE ) f ONO ( DATE ) .. . .... e x-i.e D-5
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- r. a. sox mo e.oustose, taxAs rno. . tivenmi CERTIFICATION OF HEAT TRE ATMENT i DATE. 5/5/77 i
. SOUTEBtBST RESEARG INSTITUTE l SAN ANTCMIO, TCULS CUS*OMER'S ORDER NO 34270SW
. I OTHER ORDER N05.2 PR61373 HUMBER OF PART!* N $3I
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l i i , s 4 l !O 4 I I, N 4 W i i e i 1 1 i f APPENDIX E 1 l CERTIFICATES OF PERSONNEL QUALIFICATIONS l9 1 i f I i l l I l.-- . . _ _ _ , . . . . , . . _ _ _ _ _ . _ . _ _ . . . . _ . . . _ . . _ _ . ._,. .._. _ _ ._ _ _ _._ __
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~I APPENDIX E .
CERTIFICATES OF PERSONNEL QUALIFICATIONS 1 i ! Table of Contents i i Name VT Mr UT Pm ; 1 l Clay, A. W. I I II E-1 i . ! Jaschke, T. I Ltd. I I E-4 i i Jorgensen, W. C. I I Ltd. I E-i 1 l. j Mikolajczyk, R. I Ltd. I Ltd. I Ltd. E-10 Reaves, L. C. II I II E-13 I s Turner, R. L. II II II E-16 'i j i i 4 i Wilson, W. I I Ltd. I E-19 i l q , I i 4 4-1
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' .:$'MISOOTNWEST' RESEARCH INSTITUTE
. i ;;?f0f9 NONDESTRUCTIVE TESTING n M W M6cSTATEMENTJ OF CERTIFICATION THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSUR ANCE SYSTEMS AND ENGINEERING OlVISION, CERTIFIES THAT Andrew Clav is QUALIFIED AS LEVEL I IN Visual TESTING, IN ACCORD.
ANCE WITH THE REQUIREMENTS OF SCUTHWEST RESRARCH INSTITUTE NUCLEAR QUALITY ASSURANCE PROCEDURENDT-100-2. Rev. 3 WHICH INCORPOR ATES THE GU10ELINES OF THE N/A EolTION OF SNT.TC 1 A. , CERTIFICATION LIMITATIONS tlF ANY) SIGNED. Wayne T. Flach /M alm l3CATE OF CERTIFICATION. DIRECTOR OF DEPARTMENT OF ENGINEER %S CES ! QUALITY ASSURANCE SYSTEMS AND ENGINEERlWG DIVISION C. m . STRAINING.*.,6r ~ * - EDUCATIONAL HISTORY INAME) ,Y E ARS) 10EGREE) CLASSROOM: HIGH SCHOOL.Littl'f l ork-Bie Falls MS(Minn) 4 ("a An LA BOR ATOR Y: Included in ADDITIONAL: ,Hutchinson* 2 C/ COMP Classroom MAJOR FIELD OF STUDY McP2ddo Tech - 1 vr - t.reldine EXAMINATION GRADE ISCOR ES) (WEIGHTl EMPLOYMENT HISTORY GEN ~RAL: 96,14 .33-1/3 SPECIFIC: 100.00 .33-1/3 OATE EMPLOYED: S*RI 06/05/78 olv.17 06/05 /78 PRACTICAL: 90.88 .33-1/3 PREVIOUS NOT RELATED: (COMP AN Y 1 lYEARS) COMPOSITE. 95.67 *See Educational History Mobile Lab 3 mos.
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. Mc. m: .y _ ;f VISUALACulTYAND COLOR PERCEPTION TEST CORR. CORR.
DATE R EQ. VERIFIED BY DATE R E Q. VERIFIED BY 06/16/79 No Angela M. Graf aw, =-
, < c. - . y n -. p .y , , , - s.RECERTIFICATION 53 CERTIFICATION DATE B ASIS SIGNATURE l
l BASIS.1-CONTINUING SATISFACTORY PERFORMANCE 2-R E EX AMIN ATION REMARKS. 0 -l
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J-Wi.E. . d. ss.STATEMENTMO Es. .C. ERTIFICA. TION: .. . THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING *ARVICES. QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION, t'ERTIFIES THAT Andrew Clay iS QUALIFIEO AS LEVEL IN Magne:ic Particle TESTING, IN ACCORO-ANCE WITH THE REQUIREMENTS OF SOUTHW"ST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE PROCEDURE 111, REVISION 1 WHICH INCORPORATES THE GUlOELINES OF THE 1975 EDITION OF SNT.TC.1 A. CERTIFICATION LIMITATIONS (IF ANY) SIGNED: Wayne T. Flach ./ OATE OF CERTIFICATION: DIRfCTOR OF OEPARTMENT OF ENGINEERIN ICES QUALITY ASSUR ANCE SYSTEMS AND ENGINEERING OlVISION "N MM' TRAINAPJI@id 3@l)NJ,7:W?$4{ S-EDUCATIONAt. HISTORY / - ' (NAME) (YEARS) (CEGREE) HOURS CLASSROOM. 12 HiG:4 SCHOOL. Littlefork-B12 Falls HS(Minn) 4 GP L LA BOR ATOR Y: Included in ADDITIONAL: Hutchinson*: McCaddo Tech E C/ COMP: classroom MAJOR FIELO OF STUDY NDT; Welding NO EXAMINATION GRADE ISCOR ES) (WEIGHT) W , TMOTMN?.i* EMPLOYMENTHISTORY ' GENERAL: 100.00 0.3 SPECIFIC. 98.30 0.3 OATE EMPLOYED: SwRl 06/05/78 oiv.i7 06/05/78 PR ACTICA L: 100.00 _0.4 PREvlOUS NOT RELATEO: (COMPANY lY E ARS) COMPOSITE: 99.49 *See Educational Historv Mobile Lab 3 eos, f 'id hd5DPL'b.ylStJAL ACutT AMOICOLORPERCEPTION.TESP: 'T i !. ' 'e CORR. CORR. DATE R EQ. VERIFIED BY OATE R E O. VERIFIEO BY 06/16/79 No Angela M. Graf /2mm f 4
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RECERTIFICATION DATE BASIS SIGNATURE BASIS: 1-CONTINUING SATISFACTORY PEFiFORMANCE 2-R E E XAMIN ATION
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THE DIRECTOR OF THE DEPARTMENT OF ENGINEERIN'I SERVICES, QUALITY ASSUR ANCE SYSTEMS AND ENGINEERING DIVISION, CERTIFIES THAT Andre.r Clay l$ QUALIFIED AS LEVEL II IN Ultrasonic TESTI.*JG, IN ACCORD. ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSUR ANCE PROCEDURE 111, F.EVISION 1 WHtCH INCORPOR ATES THE GUIDELINES OF THE 1975 EDITION OF SNT.*C 1 A. CENTIFICATION LIMITATIONS (IF ANY) SIGNED- Wayne T. Flach [/C . . ._ f DATE OF CERTIFICATION: 10-17-79 OM4ECTOR OF DEPARTME OF ENGINEERING SERVICES QUALITY ASSURANCE SYST S AND ENGINEERING OlVISION 2**%%S.TRR NINGd@%$%RY RW[iW,#$5% fit EDUCATIONAL i HISTORYj : ' .- - INAME) (YEARS) (DEGR E E) CLASSROOM: 56 HiGH SCHOOL: Littlefork-Big Falls HS (Minn) 4 GRAD LA BOR ATOR Y: Included in ADDITIONAL: Hutchinson* 2 C/Como Classroom MAJOR FIELD OF STUOY McCaddo Tech-1 vr. welding 1 EXAMINATION GRADE Nondestructive Testinir at Hutchinson (SCOR ES) (WEIGHT) _c 4'dhey;p%4'<A; ElWLOYMENTHISTORY_' ~' " ' GENERAL: 97.50 0.3 1 SPECIFIC: 87.04 0.3 OATE EMe'LOYED: S*RI 6/5/78 oiv.37 6/5/78 i PR ACTICA L: 91.00 0.4 PREVIOUS NOT RELATED. (COMP ANY) (YEARS) l COMPOSITE: 91.76 *See Educational History I Mobile Lab } mos.
'NO: .M5FE;fd{N[fTiSi,Q1GSUA6ACINTY"AND COLOR PERCEPT 10ftTEST- iT~ e-CORR. CORR.
DATE R EQ. VERIFIED BY OATE R EQ. VERIFIED BY 6/16/79 L Annela M. Graf /l)M/l J PWJ bic-MM+2581tyffaECERTIFICATIONU ~ / M ' : '.W z#E6 "6 R ECiRTIFICATION DATE BASIS SIGNATUR E l l B ASIS: 1-CONTINUING SATISFACTORY PERFORMANCE 2-R E EX AMIN ATION
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. 7 STATEMENT- OF CERTIFICATION THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSUR ANCE SYSTEMS AND ENGINEERING OlVISION, CERTIFIES THAT Anthony R. Jaschke IS QUALIFIED AS LEVEL I Ltd. IN Visual TESTING, IN ACCORD-ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSUR ANCE PROCEDURE NDT-100-2, Rev. 3 WHICH INCORPOR ATES THE Gul0ELINES OF THE N/A E0lTION OF SNT TC 1 A.
CERTlFICATION LIMITATIONS IIF ANY) [ SIGNED: Wayne T. Flach ,
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, . 90 ATE OF CERTIFICATION. 02/15/79 DIRECTOR OF DEPARTMENT F ENGINEERING SERVICES QUALITY ASSURANCE SYSTEM ND ENGINEERING OtVISION 1
TRAINING ' -. A - EDUCATIONAL HISTORY (NAME) (Y E ARS) (CEGREE) HOURS HIGH SCHOOL: Ed hnn H _ c: . (Ta vn a 4 CRAD . CLASSROOM. f LABORATORY Included in ADDITION A L. U.S. Navy Tech School 1.3 _C/ COMP Classroom MAJOR FIELO 08 STUOY MectTonics EX ANilNATION GRADE (SCOR ES) IWEIGHT) EMPLOYMENT HISTORY GE N ER A'.: N/A N/A SPECIFIC: N/A N/A DATE EMPLOYED: S*RI 02/12/79_ oiv.i7 02/12/79 PRACTICAL: N/A N/A PREVIOUS NOT RELATED: iCOMP ANY) (YEARS) N/A U.S. Navy (UT on ship welds) 4 COMPOS?TE: , 1 +: ,
- VISUAL ACulTY AND COLOR PERCEPTION TEST CORR. CORR.
DATE R EQ. VERIFIED BY DATE R EO. VERIFIED BY 02/12/79 No Jean M. Dreyer OP M er3r/ 02/26/80_ No Angela M. Craf" (lAVri ' 7 o
- '* . RECERTIFICATION RECERTIFICATION CATE BASIS SIGN ATUR E B ASIS: 140NTINUING SATi$F ACTORY PERFORMANCE 2-R EEX AMIN A e ION HEMARKS:l H
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%. W @ JAIEMENMOEkCERTIFICATIONdzM THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES. QUALITY ASSURANCE SYSTEMS AND ENGINEERING DIVISION. CERTIFIES THAT Ar.thony R. Jaschke iS QUALIFIED AS LEVEL I IN Magnetic Particle TESTING. IN ACCORD-4 ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE PROCEDURE 111, REVISION 1 WHICH INCORPORATES THE CUIDELINES OF THE 1975 soirioN OF SNT.TC 1 A. ;
CERTIFICATION LIMITATIONS (IP ANY) l I SIGNED: Wayne T. Flach 2 Mr70 ATE OF CERTIF? CATION: [
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DIRECTOR OF DEPARTMENT OF ENGINEERIN Rv/lCES OUALITY ASSURANCE SYSTEMS AND ENGtNEERING OlVISION
-'rONMY.TJudNRMEEW4EiN'?998d.B}MEDUCATIONAL HISTORYLD,% **
(NAMEl (YEA 95) (CEGREE) ) CLASSROOM: 12 HIGH SCHOOL: Edison H.S. (Texas) 4 ~ GRAD LA BOR ATORY: Included in A006 flONAL: _U.S. Navy Tech School 1.3 C/ COMP classroom MAJOR FIELD OF STUOY Electronis EXAMINATION GRADE ISCORES) IWE;GHT1 J18+M j E Q Q+ d d 4 N N T HtST N O ..' ;I i/-S 't s GENERAL: 88.89 0.3 l SPECIFIC: 95.00 , 0. 3 OATE EMPLOYED: SwRl 02/12/79 Div.17 02/12/79 l PR ACTICAL: 99.00 0.4 PREVIOUS NOT RELATED: (COMPANY) (YEARS) l
- U.S. Navy (UT on ship welds) 4 j COMPOSITE:
i
' MO.WYi_f@'dMM_VISUAh AND col.OR PERCEPTIOlt TEST.1 J4.2( W.*. ~ j CORR. CORR. 1 l
DATE R E3. VERIFIED BY DATE R EO. VERIFIED BY 02/12/79 No Angela M. Graf d/m4 ~ 02/26/80 No Angela M. Graf dwl 1 0
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- ydSOUTHWEST: .RESEARCH INSTITUTE fC'1 NONDESTRUCTIVE TESTING
. M.hSTATEMENT; OF CERTIFICATION !
l THE DIRECTOR OF THE DEPARTMENT CF ENGINEERING SERVICES. QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION, CERTIFIES THAT Anthony R. Jaschke iS QUALIFIED AS LEVEL T IN Ultrasonic TESTING, IN ACCORD. ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR OUALITY AS$URANCE PROCEDURE 111. REVISION 1 WHICH INCORPOR ATES THE Gul0ELINES OF THE 1975 EomON j OF SNT.TC.1 A. CERTIFICATION LIMITATIONS (IF ANY) SIGNED: Wayne T. Flach 8M/f_ /M f OATE OF CERTIFICATION: 9/10/79 DIRECTOR OF DEPARTMEN F ENGINEERING SERVICES QUALITY ASSURANCE SYSTEA AND ENGINEERING DIVISION _. TRAINING - EDUCATIONAL HISTORY (NAME) lY E ARS) (CEGREE) HOURS CLASSROOM: HIGH SCHOOL: Edison H.S. (Texas) 4 GRAD LA BOR ATORY: Included in ADDITIONAL: U. S. Navy Tech School 1.3 C/ COMP classroom MAJOR FIELD OF STUDY Electronics EXAMINATION GRADE ISCOR ES) IWEIGHTl EMPLOYMENT HISTORY GENERAL: 92.50 0.3 SPECIFIC. 90.00 0.3 OATE EMPLOYED: SwRl 02/12/79 eiv.i7 02/12/79 PAACTICAL: 96.00 0.4 PREVIOUS NOT RELATED: ICOMP AN Y) (Y E ARS) COMPOSITE: 93.15 U.S. Navy (UT on ship .ields) 4
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'J' CORR. CORR.
DATE R EQ. VERIFIED SY DATE R EO. VERIFIED BY ' 02/12/79 No Angela M. Graf /Imta 02/26/80 No Angela M. Graf 0.wik; 3
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RECERTIFICATION OATE BASIS SIGN ATU R E BASIS: 1-CONTINUING SATISF ACTORY PERFORMANCE 2-R E E X AMIN ATION REMARKS] O Sw RI PQ RM QA-114 E-6
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- bSTATEMENT70F -CERTIFICATION THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES. QUALITY ASSUR ANCE SYSTEMS AND ENGINEERING OlVISION. CERTIFIES THAT Wallace C. Jornensen iS QUALIFIED AS LEVEL I IN Visual TESTING. IN ACCORD.
ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUA LITY ASSUR ANCE PROCEDURE NDT-100-2. Rev. 3 WHICH INCORPOR ATES THE CUIDELINES OF THE N/A EDITION OF SNT TC 1 A. CERTIFICATION LIMITATIONS tlF ANY) SIGNED: Wayne T. Flach hd' '
/ OATE OF CERTIFICATION: 7/30/79*
OIRECTOR OF OEPAR NT OF ENGINEER!NG SERVICES QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION
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RS CLASSROOM: 12 HiGH SCHOOL: Crent Falls (% nema ~4 CRAN LABORATORY: IUCluded in ADDITIONAL-ClaSSr0Om MAJOR FIELD OF STUDY EXAMINATION GRADE (SCOR ES) IWEIGHTl EMPLOYMENT HISTORY O GENERAL: SPECIFIC: 93.03 92.34
.33-1/3
.33-1/3 DATE EMPLOYED: SwRl 10/09/78 oiv.37 10/09/78 PR ACTICAL: 77.10 .33-1/3 PREVIOUS NDT RELATED: tCOMPANY) (YEAR $1 COMPOSITE: 87.49 N/A
'. F- 3 * 'i n e VISUAL ACulTY AND COLOR PERCEMION TEST CORR. CORR DATE R EQ- VERIFIED BY CATE R EQ. VERIFIED SY 10/11/78 No Angela M. Graf dw4 09/04/79 Yes Angela M. Graf J ' 4.4 4 C' . % . RECERTIFICATION RECERTIFICATION OATE BASIS SIGN ATUR E BASIS: 1-CONTINUING SATISF ACTORY PERFORMANCE 2-R EE X AMIN ATION RE"*""I *Effectivity remains unchanged. Retyped to correct clerical error.
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;@fs?$3%[??iSYATEMENIQO EJCERTIElCAT!O N 7' f THE OlRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSURANCE SYSTEMS AND '
ENGINEERING OlVISION. CERTIFIES THAT Wallace C. Jorgensen gg QUALIFIED AS LEVEL I Ltd. IN Magnetic Particle TESTING, IN ACCORD. I 1 ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE ' PROCEDURE 111, REVISION 1 WHICH INCORPOR ATES THE GUIDELINES OF THE 1975 soiTiON OF SNT.TC 1 A. j CERTIFICATION LIMITATIONS (IF ANY) SIGNED: ,_ [ "I OATE OF CERTIFICATION:11/06/78 e v vg - OIR TOR OF DEPARTMENT OF ENGINEERING SERV!CES QUAL ASSURANCE SYSTEMS AND ENGINEERING DIVISION gig'NNh.TRAININGTl?$IW.N MfAYthAMMMMEOUCATf0NAL HISTORY ' 1 HOURS CLASSROOM. 4 HIGH SCHOOL: Great Falls (Montana) 3 . GRAD , LA BOR ATOR Y: Included in ADOITION A L. - - - Classroom MAJOR FIELD OF STUDY EXAMINATION GRADE ISCOR ES) IWEfGHT) '6c4**@lN.Shp;'NEMPt'OYMEMTHISTORY - , GENERAL; N/A SPECIFIC: N/A 0 DATE EMPLOYEO: SwRIJ0f09]78 Div. i710 /09 / 78 PR ACTICA L: N/A PREVIOUS NOT RELATED: ICOMPANY) lYEARS) COMPOSITE: N/A N/A j
.N#431%d?[9/M:7#N35Up CNWITYAND COLOR PERCEPTION.TESC ' l' -
COR R. CORR. DATE R EO. VERIFIED BY OATE R E O. VERIFIED BY < 10/11/78 A Jean M. Drever ddR. - ! 09/nl./74 h Aneela M. Graf/ / Ante s
**? i'%*M'M?.fMiiDl" [d%8MREI:ERTIFICATIONrlfgN&T$Niti.iC A / -
RECERTIFICATION DATE BASIS SIGNATURE BASIS: 1--CONTINUING SATISF ACTORY PERFORM ANCE 2-REEXAMINATION REMARMy O SwRI PO RM QAall=4 E-8 l l
' M@)MSOUTHWEST~RESEARCH INSTITUTE A. yp.qge: NONDESTRUCTIVE TESTING A %-l:# % STATEMENT OF . CERTIFICATION THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, CUALITY ASSUR ANCE SYSTEMS AND ENGINEERING DIVISION, CERTIFIES THAT Wallace C. Jorgensen IS QUALIFIED AS t.EVEL I IN Ultrasonics TESTING, IN ACCORD-ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE PROCEDURE 111, REVISION 1 WHICH INCORPORATES THE Gul0ELINES OF THE 1975 EolTiON OF SNT.TC 1 A. CERTIFICATION 1.lMITATIONS (IF ANY) SIGNED Wayne T. Flach k - __ / OATE OF CERTIFICATION: 0[0[79
- -. 4 DIRECTOR OF DEPARTME OF ENGINEERING SERVICES QUALirY ASSURANCE SYSTE S AND ENGINEERING DIVISION
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^ TRAINING - 'i' EDUCATIONAL HISTORY (NAME) lYEARS) (DEGREE)
HOURS CLASSROOM: 60 HIGHSCHOOL: Great Falls (Montann) 1 CRAD LA BOR ATCRY: IUCluded in ADDITION A L: classroom MAJOR FIELD OF STUOY EXAMINATION GRADE , Q Q GENERAL: (SCOR ES) (WEIGHT) 87.50 0.3 EMPLOYMENT HISTORY SPECIFIC. 94.83 0.3 OATI EMPLOYED: SwRI 10/09/78 Div. i; 10/09/78 PRACTICAL: 89.00 0.4 PR EvlOUS NOT R ELATEO: (COMP ANY ) (Y E ARS) COMPOSITE: 90.30 N/A
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DATE R EO. VERIFIED BY DATE R EO. VERIFIED BY 10/.11/78 No Angela M. Graf ANtG uv/U4//y Yes Angela M. Graf /]<m
. fr .*.' .iW 51M "r1 ' F t. 'D- RECERTIFICATION R ECERTIFICATION DATE BASIS SIGNATURE BASIS: i-CONTINUING SATISFACTORY PERT JAMANCE 2-R E E X AMIN ATION REMARICS:l O
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*CERTIFICATlON 1
THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION. CERTIFIES THAT Raymond T. Mikolaiczyk i$ CUALIFIED AS LEVEL T T.ed. IN Visual TESTING, IN ACCOR D-ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE PROCEDURE NTW 100-2 Rev. 3 WHICH INCORPORATES THE GuiOELINES OF THE N/A goiTioN OF SNT.TC 1 A. CERTIFICATION LIMITATIONS (IF ANY) SIGNED: Wayne T. Flach d_ (( M DATE OF CERTIFICATION. 11/30/79 OIRECTOR OF DEPARTMENT ENGINEERING SERVICES QUALITY ASSURANCE SYSTEM AND ENGINEERING OlVISION MNMVITUUtutistg&M*A ?$MA$3f[F' IMS EDUCATIONAL HISTORY (NAME) (Y E ARS) (CEGREEl CLASSROOM: 4 HIGH SCHOOL: North H.S. (Oh) 3 Grad LABORATORY: Included in ADDITIONAL: None N/A N/A Classroont MAJOR FIELD OF STUDY EXAMINATION GRADE ISCOR ES) (WEIGHT) kM[Mhhd$^kEMPtDYMENT HISTORY GENERAL: N/A N/A SPECIFIC: N/A N/A DATE EMPLOYED: SwRI 9/24/79 o,y.37 9/24/79 PRACTICAL: N/A N/A PREVIOUS NOT RELATEO: (COMPANYI IYEARS) COMPOSITE: N/A None NM N 'i' 'l
-" T-r545 wiAND COLOR PERCEPTION TEST CORR. CORR.
DATE R EQ. VERIFIED BY OATE R EQ. VERIFIED BY 11 /97/74 A Ancela M. Graf /1 m a . O R ECERTIFICATION DATE BASl3 SIGN ATUR E BASIS.1-CONTINUING SATISF ACTORY PERFORM ANCE 2-R E E X AMIN ATION
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THE OIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSURANCE SYSTEMS AND ENGINEERING DIVISION, CERTIFIES THAT Raymond T. Mikolaiczyk IS QUALIFIED AS LEVEL I Ltd IN Magnetic Particle TESTING, IN ACCORD. ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE PROCEDURE 111, REVISION 1 WHICH INCORPORATES THE GUIDELINES OF THE 1975 = DiriON OF SNT TC 1 A. CERTIFICATION LIMITATIONS (1F ANY) SIGNED: Wayne T. Flach kI[- . .h OATE OF CERTIFICATION. 11/30/79 OIRECTOR OF DEPARTME OF ENGINEERING SERVICES QUALITY ASSURANCE SYSTINS AND ENGINEERING DIVISION
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THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION, CERTIFIES THAT Raymond T. Mikolaiczyk IS QUALlFIEO AS LEVEL T T.ed . IN Ultrasonic TESTING, IN ACCORO-ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE PROCEDURE 111. REVISION 1 WHICH INCORPORATES THE GUlOELINES OF THE 1975 go: Tion OF SNT.TC-1 A. CERTIFICATION LIMITATIONS (IF ANY) SIGNED: Wayne T. Flach [h _ _ /[ / gbATE OF CERTIFICATION: 11/26/79 OIRECTOR OF DEPARTMENT O ENGINEERING SERVICES , QUALITY ASSURANCE SYSTEMS NO ENGINEERING OlVisiON
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@XQSTATEMENMOEICERTIFICATION@BF THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES. QUALITY ASSURANCE SYSTEMS AND ENGINEERING DIVISION. CERTIFIES THAT Larry C. Reaves IS QUALIFIED AS LEVEL TT IN Visual TESTING, IN ACCORD.
ANCE WITH THE REQUIREMENTS OF $OUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE
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CERTIFICATION LIMITATIONS (IF ANY) SIGNED: Wayne T. Flach C ._ /// (/ OATE OF CERTIFICATION: 09/04/79 DIRECTOR OF DEPARTMENT F ENGINEERING SERVICES QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION jvygbiTRA'tNifeGd:6d%% /P@ij@@@@'EDUCATIONAhMISTORY i.N 'ew . ?> (NAME) (YEARS) IDEGREE) l HOURS CLASSROOM:
- 24 HIGH SCHOOL: Bass High-GA 5 GRAD I LABORATORY: Included in ADDITIONAL: North Georgia College 2 No Classroom MAJOR FIELO OF STUDY Physics i EXAMINATION GRADE Ft. Carson School of Aeronautics - 1 vr. 1 l
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1 94.18 33-1/3 [~N) L, GENERAL: SPECIFIC: 92.50 33-1/3 OATE EMPLOYED: SwAl 02/20/78 oiv i7 02/20/78 l PRACTICAL: 94.50 33-1/3 PREVIOUS NOT RELA TED: ' . (COMPANYI (YEARS) COMPOSITE: None i oIPMNU.6YE$@ME$8NACutTTAND.COLDEPERCEPTTON.TESTd .yE 4 d P'c CORR. CORR. DATE R EO. VERIFIED BY DATE R EQ. VERIFIED BY 01/?? /70 _.Nn._ Angela M. Graf O,Mel 01/08/80 Jo_ Angela M. Graf LM J
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[ i directly froC Visual I LTD to Visual II. All training hours and experience hours U have been met for certification to both Level I and Level II Visual. f Sw Al PO RM QA.I14 I E-13 l l
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THE DIRECTOR OF THE DEPARTMENT Or ENGINEERING SERVICES, CUALITY ASSURANCE SYSTEMS AND , ENGINEERING OlVISION, CERTIFIES THAT Larry C. Reaves is QUAUFIED AS LEVEL I IN MagneCic Particle TESTING, IN ACCORO-ANCE WITH THE REQUIREMENTS O* SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSUR ANCE PROCEDURE 111. REVISION 1 WHICH INCORPORATES THE GUlOELINES OF THE 1975 goirios OF SNT.TC 1 A. CERTIFICATION Lilk TATIONS (IF ANY) SIGNEO. Wayne T. Flach h/hj _ , // $ DATE OF CERTIFICATION: 07/03/79 DIRECTOR OF DEPARTMEN OF ENGINEERING SERVICES QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVIGION "Ef!Nf' TRAINING @&ft_LT$d MJJh@2(-@MpIEDUCATIONALHISTORY ~ 'd (NAME) (Y EARS) (CEGREE) CLASSROOM: 12 HiGH SCHOOL: Bass High - GA 5 GRAD LA BOR ATOR Y: Included in ADDITIONAL; North Georgia College 2 No classroom MAJOR FIELO OF STUOY Physics EXAMINATION GRADE Ft. Carson School of Aeronautics - 1 vr. a-- - ISCOR ES) IWEIGHT) t;a .t%;r)TY'U'.,}.2W@ ERFLOYMENT HISTORY' '
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i THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlvlSION, CERTIFIES THAT Larry C. Reaves is QUALIFIED AS LEVEL II IN Ultrasonics TESTING, IN ACCORD.
ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE PROCEDURE 111, REVISION 1 WHICH INCORPOR ATES THE Gul0ELINES OF THE 1975 goiTion 1 08 SNT.TC.1 A. . CERTIFICATION LIMITATIONS (IF ANY) ' SIGNED: Wayne T. Flach h(q M [ ATE OF CERTIFICATION: 05/14/79 OIRECTOR OF OEPARTME OF ENGINEERING SERVICES QUALITY ASSURANCE SYST S AND ENGINEERING OlVISION
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HOURS CLASSROOM: 56 HiGH SCHOOL: Bass High - GA 5 GRAD t.A BOR ATOR'/: Included in ADDITIONAL: North Georgia College 2 No classroom MAJOR FIELO OF STUDY _ Physics EXAMINATICA GRADE Ft. Carson School of Aeronautics - 1 vr. (SCORES) (WEIGHT) Dis.iG2TSki.I'-WEll ' \OYMENT HISTORY L.J m ' - G E N E R A'.: 92.5 0.3 SPECIFIC: 80.53 0.3 02.TE EMPLOYED: SwAI_ '/20/78 aiv.37 02/20/78 PR ACTICAL: 87.5 0.4 PREVIOUS NCT RELATED: (COMPANY) (YEARS) COMPCSITE: 86.91 None
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DATE R EQ. VERIFIED BY OATE R EQ. \ ERIFIED BY 01/22/79 No Angela M. Graf 1%1 01/08/80 No Angela M. Graf (Lrnd 0
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RECERTIFICATION DATE BASIS SIGN ATU R E BASIS.1-CONTINUING SATISF ACT']RY PERFORMANCE 2-R E EX AMIN ATION REMARg Certification retyped to correct typographical error. Effectivity remins unchanged. SwRl FORM QA ll 6 a E-15
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THE DIRECTOR OF THE DEPARTMENT OF, ENGINEERING SERVICES. QUAllTY ASSURANCE SYSTEMS ANO FNGINEERING DIVISLON. CERTIFIES THAT Runnell L Turne r tS QUALjFIED AS LEVEL II IN Visual _ TESTING, IN ACCORD. ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH tNSTITUTE NUCLEAR QUALITY ASSUR ANCE PROCEDURE NDT-100-2.Rev. 2_ ,WHICH INCORPORATES THE GUIDELINES OF THE N/A EDITION OF SNT.TC 1 A. CERTIFICATION L.!*.e8TATIONS (IF ANY) SIGN E D- Wayne T. Flach
.,, g, d$ ' M OATE OF CERTIFICATION: 11/10/7A DIRECTOR OF DEPARTM T OF ENGINEERING SERVICES QUALITY ASSURANCE SYS MS AND ENGINEERING DIVISION MYN$_@NM'ifY 78d**4"$YMf: DUCAT 10NAL HISTORYT - T '-fi (NAME) (Y EARS) (CEGREE)
CLASSROOM: 12 HIGH SCHOOL: Roosevelt H.S.(Tevn=1 4 CRAN LA BOR ATORY: Included in ADDITIONAL: San Antonio Collene 1 sem. No Classroom MAJOR FIELD OF STUDY General Academics EXAMINATION GRADE ISCOR ES) (WElGHT) T 9M 5 4 kifE34PEDYMW.HIS7011Y,- *^< GENERAL: 091.00 _.33 SPECIFIC: 084.00 .33 DATE EMPLOYED: SwRI 05/20/74 civ.17 05/20/74 PRACTICAL: 080.00 .33_ PMVIOUS NOT RELATED: ICOMP ANY) (YEARS) COMPOSITE: 084.00 None prior to SwRI
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CORR. CORR. DATE R EO. VERIFIED BY DATE R EO. VERIFIED BY 03/20/78 _vgg Jean M. Dreverd % M 02/71/79 va. .Tann v_ nr y.vdfJftA7/a/7M 02/19/80 Yes Angela M. G'raf /IAM_ d IIINNIbf485,[M^h *hNd 2,hky'N[hh",% .M - ' RECERTIFICATION OATE BASIS SIGNATU E 11/30/77 1 Unvn. T_ vinch
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c THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES QUALITY ASSURANCE SYSTEMS AND ENGINEERING DIVISION. CERTIFIES THAT Russell L. Turner iS cVALIFIED AS LEVEL II IN Magnetic Particle TESTING. IN ACCORD. ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCE PROCEDURE 111. REVISION O WHICH INCORPORATES THE Gul0ELINES OF THE 1975 eOITiON OF SNT.TC 1 A. ; CERTIFICATION LIMITATIONS (IF ANY) SIGNED: Wayne T. Flach k ,s (( OATE OF CERTIFICATION: 08/03/76 DIRECTOR OF DEPART NT OF ENGINEERING SERVICES QUALITY ASSURANCE SYS EMS AND ENGINEERING OlVISION Q +4.0.*$TRAINtmeM_N E d [3PFE;hg?5"U[$ EDUCATIDNAC HISTORY' : : t HOURS ) CLASSROOM: 0 HIGH 3CHOOL: Roosevelt H.S. (Texas) 4 GRAD LA BOR ATOR Y: Included in ADDITIONAL: San Antonio College 1 sem. No classroom MAJOR FIELO OF STUDY General Academics EXAMINATION GRADE 1 O t5e.ifd.pf,9y{GNMEMPt.OYMENT'HISTORI A - (SCORES) (WEIGHTl ' [V GENERAL; SPECIFIC: 070.03 100. 0
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COMPOSITE: 089.00 None prior to SwRI )
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CORR. CORR. l DATE R EQ. VERIFIED BY OATE R EO. VERIFIED BY 03/20/78 _,Xgg Jean M. Dreyer M __ 02/23/79 _Xgg Jean M. Drever#Altw7/s%9 02/19/80 Yes Angela M. Graf'(LOct/ , 1 d v vWyffphiygsp;@d4DRECERTIFICATICWI . i"NY -i.:PW* R ECERTIFICATION DATE SASIS SIGN AT;lR E 08/03/79 1 Wayne T. Flach .
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THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSURANCE SYSTEMS AND ENGINEERING DIVISION, CERTIFIES THAT Russell L. Turner IS QUALIFIED AS LEVEL II IN Ultrasonic TESTING, IN ACCO'40 ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSURANCii PROCEDURE N0AP't IX-AG-1-1 WHICH INCORPORATES THE GU!OELINES OF THE 1968 G DITION OF SNT.TC-1 A. CERTIFICATION LIMITATIONS (lF ANY) SIGNED- Wayne T. Flach l , J,M [ OATE OF CERTIFICATION: 01/11 /78i DIRECTOR OF DEPARTM T OF ENGINEERING SERVICES l QUALITT ASSURANCE SYS EMS AND ENGINEERING DIVISION 1 MMMhTcj$ninr aTIONALHISTORYJ j+J
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*03/31/78 1 Wavne T. Flach . , - -
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. y :YF iSTATEMENT' O F CERTIFICATION THE DiPECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION. CERTIFIES TH AT Vfilinm M. Uflann is QUALIFIED AS LEVEL I IN Visttal TE3 TING, IN ACCORD.
ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEA'4CH INSTITUTE NUCLEAR QUALITY ASSUR ANCE PROCEDURE NDT-100-2. Rev. 3 wHiCH INCORPO9ATES THE GUiOELINES OF THE N/A EDITION OF SNT.TC 1 A. CERTIFICATION LIMITATIONS (IF ANY) . SIGNEO: Wayne T. Flach l[//// - ,
, OATE OF CERTIFICATION: 7/30/79*
DIRECTOR OF DEPARTMEN F ENGINEERING SERVICES QUALITY ASSURANCE SYSTE S AND ENGINEERING OlVISION
< " TRAINING :. 9 EDUCATIONAt. HISTORY (NAME) lYEARSI IDEGREEl CLASSROOM: 12 HIGH SCHOOL: USAF CED LA BOR ATOR Y: Included in ACOlTIONAL: USAF Technical School 3-1/4mos C/C ClaSSroott! MAJOR FIELD OF STUDY NDT and Jet Engines EXAMINATION GRADE ISCOR ES) IWEIGHTl EMPLOYMENT HISTORY (j GE N E R A L: 95.54 .33-1/3 SPECIFIC: 85.68 .33-1/3 OATE EMPLOYED: SwRl 09/05/78 Oiv. i7_09 /05 / 78 PR ACTICAL. 80.00 .33-1/3 PREVIOUS NOT RELATED: (COMP AN Y I (Y E ARS)
COMPOSITE: 87.08 See Educational History USAF - Jet Engine Work 6 Lear-Siegler (NDT in MI, PT, UT & RT) 5 mos
; ,(' - M .q.. ,VtSUALACUITY AND COLOR PERCEPTION TEST CORR. CORR DATE R EQ. VERIFIED BY DATE R EQ. VER FIED BY 09/13/78 L Aneeln M. Crnf OmttL 08/29/79 A Ancela M. Graf antl J
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s TE*? -STATEMENT OF . CERTIFICATION ! l THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSURANCE SYSTEMS AND ENGINEERING DIVISION, CERTIFIES THAT William H. Wilson iS QUALIFIED AS LEVEL I ltd IN Magnetic Particle TESTING, IN ACCORD-ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSUR ANCE PROCEDURE 111, REVISION 1 WHICH INCORPORATES THE GUIDELINES OF THE 1975 goirion OF SNT-TC 1 A. CERTIFICATION LIMITATIONS (lF ANY) SIGNED: Wayne T. Flach [fk _ . m ., /ft! / (OATE OF CERTIFICATION:09/14/78* DIRECTOR OF DEPARTMENT ENGINEERING SERVICES QUALITY ASSURANCE SYSTEMS ND ENGINEERING D VISION ETRAINING .a , EDUCATIONAL HISTORY (NAME) (YEARS) (CEGREE) CLASSROOM: 0 HIGH SCHOOL: USAF GED LA BOR ATOR Y: Included in ACOlTION AL. USAF Technical School 3-1/4 mos C/C classroom MAJOR FIELO OF STUOY NDT and Jet Engines EX AMINATION GRADE iSCORES) (WEIG HT) EMPLOYMENT HISTORY GENERAL: N/A N/A SPECIFIC: N/A N/A DATE EMPLOYED- Swal 09/05/78 oiv.37 09/05/78 PRACTICAL; N/A N/A PREVIOUS NOT RELATED: (COMP ANY) (Y E ARS) COMPOSITE: N/A See Educational History USAF - Jet Engine Work 6 Lear-Siegler NDT in MT, PT, UT & RT) 5 mos.
' VISUAL ACulTY AND COLOR PERCEPTION TEST CORR. CORR.
DATE R EQ. VERIFIED BY DATE R EQ. VERIFIED BY 09/13/78 No Angela M. Graf dew 08/29/79 No Angela M. Graf &nel 6 { g- + . c* , RECERTIFICATION-RECERTIFICATION DATE BASIS SIGNt TUR E BASIS.1-CONTINUING SATISF ACTORY PERFOHMANCE 2-R E E XAMIN ATION
*Effectivity remainn vin c hnn eed . 4pevnnd en entrare elav4ast errer_
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. INSTITUTE AW% 4 STATEMENT- OF CERTIFICATION l THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICESs QUALITY ASSURANCE SYSTEMS ANO ;
ENGINEERING OlVISION, CERTIFIES THAT William H. Wilson iS QUALIFIED AS LEVEL 1 IN Ultrasonic TESTING, IN ACCORD.
%NCE WITH THE REQUIREMENTS OF SOUTHWEST RES? tRCH INSTITUTE NUCLEAR QUALITY ASSURANCE P30CEOURE 111 REVISION 1 WHICH INCORPOR ATES THE GulOELINES OF THE 1975 gOiTiOn OF SNT.TC 1 A.
CERTIFICATION LIMITATIONS (IF ANY) SIGNEO: Wayne T. Flach N ~ m , y-8 OATE OF CERTIFICATION: 07/30/79 DIRECTOR OF DEPARTMENT dF ENGINEERING SERVICES QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION
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EDUCATIONAL HISTORY HOURS CLASSROOM: 60 HIGH SCHOOL: USAF CED LA BOR ATOR Y: Included in ADDITION A L: USAF Technical School E /I mos C/C classroom MAJOR FIELO OF STUOY NDT and Jet Engines EXAMINATION GRADE (SCOR ES) (WElGHTl O GENERAL. SPECIFIC: 97.50 91.50 0.3 0.3 EMPLOYMENT HISTORY OATE EMPLOYED: SwRl 09/05/78 Div.17 09/05/78 PRACTICAL: 93.00 0.4 PREVIOUS NOT RELATEO ICOMPANY) (YEARS) COMPOSITE: YTE See Educational History USAF - Joe Engine Work _ 6 Lear-Siegler (NDT in MT, PT, UT & RT) 5 mos.
..;,:..s a n, ud VISUAL ACulTY AND COLOR PERCEPTION TEST CORR. CORR.
DATE R EQ. VERIFIED BY DATE R EQ. VERIFIEO BY 09/13/78 No Angela M. Graf AMIA-8/29/79 _Jq,Annela M. Graf SMo_ i
- Je ? u 6 ::: r;. p;,, . *' ' S. RECERTIFICATION RECERTIFICATION 7
OATE BASIS SIGNATURE l I e BASIS.1-CONTINU4NG SATISFACTORY PERFORMANCE 2-R E EX AMIN ATION
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e i i l0 1 1 t I i I 1 I i I I J i i 1 APPENDIX F l MATERIAL AND EQUIPMENT CERTIFICATIONS l@ 1 t t a 1 e i I d ,e i 4 l \O f f..__, :...--..--------.-..-~,., ----~~c-----~
7
.(j APPENDIX F MATERIAL AND EQUIPMENT CERTIFICATIONS Table of Contents MATERIAL 5'
M Date M
- Pencils (Prismacolor Black) #935 22 Jun 1979 F-1 i Pencils (Prismacolor White) #938 22 Jan 1979 F-1 1 Magnetic Particle #14AM Batch #79H007 06 Aug 1979 F-2 Ultragel II Batch Log #1192 01 Oct 1979 F-3 Glycerine Log.#0977 20 Jun 1979 F-4 EQUIPMENT Type Serial No. Date Page Dayton Quick-Temp Pyrometer 032 12 Sep 1979 F-5 Dayton Quick-Temp Pyrometer 035 20 Sep 1979 F-7 Black-Ray Intensity Meter 11654 21 Dec 1979 F-9 Sonic.FTS MK I 774713 14 Nov 1979 F-11 i
Sonic FTS MK I 780415 29 Nov 1979 F-13 TRANSDUCER Brand Serial No. Date Page Aerotech 012654 03 Oct 1979 F-15 j Aerotech 014505 11 Sep 1979 F-17 Aerotech 014397 11 Sep 1979 F-19
'SwRI 925 24 Sep 1979 F-21 1
a. ? . F-1
U SOUTHWEST RESEARCH INSTITUTE S23e CULEBR A ROAo o POST OFFtCa o#AWER 34S10
- SAN ANToN8o. TEM AS Passe imaAUTV *=*am systsang TEtes enz.
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January 22. 1979 l Mr. E. Coehring Quality Assurance Systems & Engineering Division Southwest Research Institute San Antonio. Texas
Dear Sir:
Tour request for analysis of two types of Eagle Brand marking pencils has been completed. The results are as follows: Sulfur. % Wt. Chlorine. % Vt. ASTM D-129 ASTM D808 A Eagle Prismacolor Black Pencil #935 0.39 & 0.37 0.00 & 0.00 g Eagle Prismacolor White Pencil #938 0.00 & 0.00 0.00 & 0.00 W_ u Ralph W. Bowen
'A Senior Research Chemist RWB:mk S-31 j-P. 0. -
- r. a.
7 /3$3M - L30 l1 G g g 5 e S 9 D F -I
O 312-UN 7-8000 TELEX 25-4194 MAGNAFLUX CORPORATION 1 - -sr - - - - -
- TO: Date: Auoust 6. 1979
?urchase Order No. 81834sw Attention:
We hereby certify that the Magnetic Particle Inspection Material Type: 814AM Preoared Bath . Batch nc. 79H007 . meets the pquirements of the following specifications: A. ASME Boiler and Pressure Vessel Code Section V Paragraph T-725.2 or T-725.3. B. ASTH E 138-63 Paragraphs 6.1, 6.2.1, or 6.2.2, 6.3.1 and 6. , C. NAVHIPS 250-T500-1, Rev. 9 August 1973. Paragraphs 12.4.2.2(a) and 12.4.2.2(c), 12.4.2.3 and 12.4.2.4. D. MIL-I-6868E. 27.Eebruary 1976. Paragraphs 5.1, 5.1.1, 5.2 and 5.2.2. E. MIL-STD-2710, IN4 arch 1965, Paragraphs 4.2.8, 4.3.2.1, 4.3.2.2(a) . 4.3.2.2(c) 4.3.2.3, 4.3.2.4 and 4.3.2.4.1 or 4.3.2.4.2. F. HIL-STD-271E 31 October 1973, Parsgraphs 4.2.6. 4.3.2.2(a). 4.3.2.2(c), and 4.3.2.4. G. The flash point of the material is over 175' F. when tested by the Pensky-Marten's Closed Cup Method (ASTM D-93). Batch numbers appear on labels of bulk containers and on the bottoms of aerosol cans. MAGNAFLUX CORPORATION Sant -
?0. N DYSY
?* 3*$YU f&)r,'t.v T. Schmiot, Chief Control Chemist
- r. 3 J_118 J For#m No.1565C R-10/78 (9CM,14AM) woeerstnueme resTws sysTeus . usmoos . ssmes O
! F-2 l
O ca. m i,na io cn eencss n 17 International {$iidgbarainties, Inc.
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WalghersKSampi.6 sjadd Assayers 578-582hx.rr wuwann. M. J., ettes STnEET poseenes egg aghdyymume REPORT OF ASSAY No. 446802 DATE Oct.1.1979 Omr essey of the semple of U1tragel II Batch Fie= Echo Laboratories. Inc. Merl*l: #79263' Spec. ASTM-D-129 and D-808 (1374)
~
earchase Order No. 002103 .g submitted to y Halogen : 25.0 ppe Sulphur : 47.7 ppm Sworn to and subscribed before se
- t. day of Octo 1979.
My tary Public w ssion expires Nov. 26. 1983. To Echo Laboratories. Inc. Lewistown, Penna. 17044 INTERNATIONAL TISTING IA80RATORIE3, INC. W.C$$i d ~' %." "N.~~N D L p.))c o
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SOUTHWEST RESEARCH INSTITUTE 4220 CULEenA AOAD e POST OFFICE OmAwER 24980
- SAN A N TONIO, TEMAS 78384 i
4 June 20, 1979 Quality Assurance Systems & k gineering Division Southwest Research Institute 6220 Culebra Road
- San Actonio, Texas 78284
Dear Sirs:
! The analysis of your Dow Chemical Clycerine sample has been com-plated. The results are as follows: Sulfur, I we. (ASDt D-129) = 0.02 & 0.02 Balogens Z vt. (ASTM D-808 = 0.02 & 0.02 Very truly yours. W ""' Ralph U. Bowen Manager Engines, Fuels and Lubricante F & L Evaluation I.aboratoriu RVB/djb s.a1
- p. O. ff7971w
- r. s. /29714 1.:o d977 SAN ANTONIO. MouSTON. TEMAS, AND WASM8NGTON. D.C.
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STANDARDS MFGR. .Model . Description . S/N Cal. . Due . lA2*bs J a m s 9tPt Mtittarresritran tw1zir iz- zi-9g
' ENVIRONMENT; Temperature #7 t.'
- F Humidity,, 8/#) *g /R.A/
AO.C. Min d t ^ Roeg 9 Qt. _ k Q f u t.1,
- PROCEDURE ~ ~ '
O Essentiatir as outitned in urcRs serace Manuai - () - Ia sw.u,nxacu s w m x , , - n1 - aj_- o . an. nag __ mess.ous... CONCLUSION . . . . C Iteni within tolerance. No adjustment was necessary. [._., ._ O. Ite= ADJ/ repaired to tolerance M... $df 00[A., ?t.f.? f M AJ Tf/ /Af Ukf f*f / pfdgff
- .%Cft9 AML . . . . .
Calibration was in accord with requirements of MIL-C45662A, MIL-Q98SS. _ and MIL-C45203. Measurements are traceabic to the National Dureau of Standards. . ,
.Y7here required by type or use of equipment, actual inspection and test . _..
. data are on file and available for inspection.
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. STANDARDS MFCR Model Description S/N Cal. Due kvarthezskip Nft . pe-w~ rw.~rm intzo- 12 . z i - 77 ENVIRONMENT: Temperature ffw F Humidity 3 j g /,f/
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. O . Es senti =117 as outlined in urGRS Service Manuat
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._E Item within tolerance. No adjustment was necessary . I
. . ... C Item ADJ/ repaired to tolerance __... __ ..
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. Calibration was in accord with requirements of MIL-C45662A, MIL-Q9858,
._.. and MIL-C45208. Measurements are traceable to the National Bureau of Standards.
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data are on file and available for inspection. . . . . _ _
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DATE f _F~_.. - _ _ Calibratlon Due: 7.._.14.~ _k_ . . . . e m F-7
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F (v) CAUBRATION/ CERTIFICATION REPORT FOR BLAK-RAY
- J-221 LONG WAVE ULTaAVIOLET INTENSITY METER
- 1. Date of Certification 12* 21 7 I P, d I bn e i1 >
- 2. Serial Number II f a M U
- 3. Method of Calibration:
A. The J-221 meter la calibrated by adjusting the meter to read identically to J-221 meter S/N 7728 when expoet J equally and simultaneously to long wave ultraviolet intensities of 600,W/cm* ("A" scale) and 3.500 a
,W/cm ("B" scale) as determined by motor S/N 7728.
B. J-221 meter S/N 7728 is the tong wave ultraviolet transfer standard meter at Ultra-Violet Pror*. cts. Inc.
- 4. N.B.S. Traceability Proceoore:
A. J-221 motor S/N 7728 is calibrated by use of the MCS-44 Meter Certi-fication Standard S/N 2. Meter S/N 7728 is recalibrated semi-annually
. (oroftenor).
B. The MCS-44 S/N 2 consists of an SPR-33 Stable Ultraviolet Source S/N 1581 and an LAS-11 Comparator Lamp and Amplifier S/N LAS-11-2. SPR-33 S/N 1581 is the working standard for J-221 meter calibrations,its long wave ultraviolet radiation is calibrated by com-parison with SPR-33 S/N 1560. the primary standard at Ultra-Violet Products, Inc. SPR-33 S/N 1560 la recalibrated after 200 hours of - operation (or oftener). n.- - Nh -
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C.'s .-SPR-33 S/N 1560 has been examined and calibrated for its accuracy .
'* of irradiance in the 254nm (short wave) and 365ntn (long wave) regions by Eppley Laboratories. whose facilities have been certified by the Nattonal Bureau of S!andarda. SPR-33 S/N 1560 is resubmitted to Eppley Laboratories,Inc. after each 200 hours of woration.
D. The N8S carbon lamp S/N C-1107 was calibrated on July 26,1963 Test No. 2.1/176963. cum-vuxn mooucrs, mc.eg- _ ~ sm. [" senmuse O F-9
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l 1 SONIC FTS MARK I FLAW DETECTOR CALIBRATION l I OPERATIONA L CHECKLI ST FOR SONIC FTS MK I No. 7 W7/3 l REFERENCE PROCEDW Ill-9/M-IO 3'~ h ALIGNMENT OF SONIC FTS MARK I FL AW DETECTOR i
- 1. CURRENT DRAIN ( 350 MA. TO 450 M A. ) NJ MA.
- 2. AMPLITUDE LINE AR ITY /% FSH
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- 4. Call 8R ATION OF GAIN 08 ( FINE J /7 M -
- 5. HORIZONTAL LINE ARIT Y /% FSW !
- 6. CHECMS OF POTS AND SWITCHES :
I FREQUENCY MHZ A- - REJECT &8 RANGE d U- DELAY POT. A d-FILTER d K- MATL. CAL, OF REP. RATE Ad DELAY SW, A. M VCEO S'.V . AY- THR'J TRANS - NORM . O U-DAMPlNG d- - DEC. - # 6 08 SWITCH AM- 14 D8 SWITCH A #- 7 LOW BATTERY LIGHT ADJUSTMENT M */~# >d . 75 " ( JUST ON AT 10.75 VOLTS) II CERTIFICATION : ALIGNMENT PERFORMED BY A Mh #d--- [ NIGNA TURE ) J'/ A/W Y9 ( DATE ) NJ ) sene eens eu . ii . e F-ll
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- 2. AMPLI TUDE LINE ARITY ! % FSH
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- 4. CALIBR ATION OF GAIN 08 ( FINE ) O
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- 6. CHECKS' OF POTS' AND SWITCHES :
FREQUENCY MHZ ' O# REJECT O[ RANGE O!I DELAY POT. O FILTER O[ MATL. CAL. O[ REP. RATE MI DELAY SW. O/ m VCEO SW. 8I THRh TR ANS - NORM . OE DAMPING O DEC. O[ 6 D8 SWITCH _M[ 14 08 SWITCH [Y
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J. t t l 1 l t i O , 1 i + t i 1 5 ! I s t l 1 ! i i ( APPENDIX G l CUSTOMER NOTIFICATION FORM ! O l t i 1 4 l f i 9 ' I i D' 1 I
Southcest Research Institute _S riti NE. 00000i ' utmty Bos+e s E A , s,,, c', CUSTOMER NOTIFICATION FORM S,,e pi ln ci~ l Part I- Sw RI Findings g Project N9.rlg. qq7 g Type of Examination NOTg Method 967 OPT 3 ro e / Rev. Enomination Date' l FA % 0 0 PSI dSI G64T ORT O ET OVT 30g, p Comments 5 m a n e- t a ke ce$/c ri n o n!n e- i n c P, 6 9' v6 Y N LU n 4
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Esaminotion Referencei h,k %+- A>a 420an f - R P v && Co W . 54 k AJe /aeco, - heAMz ; Y !' l$ $"N 5 f '$ i "D W 80 Mart 11- Customer Notification Notification Acknowledged by Dofe y Port til- Indication Disposition by Customer C** * *" G Ased c e A e_ Rock 4b4 i; Mon &b wo4c. me< o a L 4 rasen m &, eyamined Awl wn s w A ic34 tons w er e ve d ,A 4bu- e: , L e s sndio hnns we acer oled hsi bemo s Wowmb6 7
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