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Inservice Insp Rept,Vol 1,from Jan-Feb 1980 Refueling Outage.Describes Remote Visual Exam of Selected Components at Facility
	ML19344E776
Person / Time
Site:	Pilgrim
Issue date:	08/07/1980
From:	Dunavont D, Lautzenheiser, Riggs M; SOUTHWEST RESEARCH INSTITUTE
To:	;
Shared Package
ML19344E775	List: ML19344E774; ML19344E776; ML19344E779;
References
	17-5964, NUDOCS 8009110299
	Download: ML19344E776 (60)
	v • d • e

{{#Wiki_filter:_ _ _ .-____ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ D , SOUTHWEST RESEARCH INSTITUTE V Post Office Drawer 28510 6220 Culebra Road San Antonio, Texas 78284 1980 REMOTE VISUAL EXAM l NATION OF SELECTED COMPONENTS OF PILGRIM NUCLEAR POWER STATION, UNIT 1 VOLUME I FINAL REPORT WITH APPENDICES SwRI PROJECT 17-5964 Prepared for: Boston Edison Company Pilgrim Nuclear Power Station ! 800 Boylston Street ! Boston, Massachusetts 02199 i l I l April 1980 I l I l Prepared by: Approved by:

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Project Manager ## ClardnceEfau'tz'enkiser l Reviewed by: Vice President / Quality Assurance systems and J/j/ g g Engineering Division O ($009110 %

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                                                                                                                       ~3 4

w) FORM NIS 1 (back)

8. Exa*cination Dates 1/5/80 ,o 5/20/80,, rospection int,rv i from 12 /9 /72 o 12 /9 /8,2 t

10. Abscrset of Examinations. Include a list of exammations snd a statement concerning status of work required

for current interval. Refer to abstract 1n Final Report.

11. Abstraer of conditions Noted. Refer to Summnry and Conclusions in Final Report.

12. Abstract of Corrective Measures Recommended and Taken None We certify that the statements maw in this report are correct and the examinations and corrective mes-sures taken conform to the rules of the ASME Code. Section XI.

  . Date                               19         Signed Boston Edison Co.sy,                         4 Mym

_/ Owner / / Certificate of Authorization No.(if applicable) Expiration Date ! CERTIFICATE OF INSERVICE INSPECTION 1 the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel V laspectors and/or the State or Province of Mass, and employed by

Factory Mutual of Waltham. MA have,jryg the components described in this Owners' Data Report during the period 1/5/80 to m ..and state that to the best of my knowledge and belief, the Owner has pettormed examinations and taken corrective messeres descnbed in this Owners' Data Report in accordance with the requirements of the ASME Code.Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty. expressed or implL. concerning the examinations and corrective measures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection. Date (E 8 19 lA_

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d' Commissions N8 73 Pd

             / Inspectori Signature                                      National Board State. Province and No.
         *Arkwright - Boston Insurance Mutual Boiler and Machinery Division

O FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules i, o.o , Boston Edison Co., 800 Boylston Street, Boston, MA (Name and Address of Owner)

2. Plat Pilgrim Nuclear Power Station, RFD #1, Rocky Hill Rd., Plymout a, MA (Name and Address of Plant)

3. Plant Unic M1 _4. Owner Certificate of Authorization (if required) N/A

5. Commercial Service Date 12 /9 /7 2 6. National Board Number for Unit 20763

7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

Reactor Vessel Combustion Eng. 66107 66207 20763 Pioine Bechtel Corp. N/A N/A 7572 Note Supplemental sheets in form of lists. sketches, or drawings may be used provided (1) size is 8% in. x 11 in.. (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. O e

O i ABSTRACT A remote visual (VT) examination of selected areas of the Reactor Pressure Vessel (RPV) of Boston Edison Company's (BECo) Pilgrim Nuclear Power Station,

,     Unit 1, was performed during the January - February 1960 refueling outage.

This was the first remote VT examination performed during the initial 10 year

      . inspection interval. The components were examined in accordance with the "Proj-ect Plan for the 1980 Inservice Remote Visual Examination of Pilgrim Nuclear Power Station, Unit 1," including any changes made during the examination as approved by BECo.

Four of the examination areas were found to have rep'ortable indications. These indications were reported to BECo on Southwest Research Institute (SwRI) Cus-tomer Notification Form (CNF) No. 000002 which has not been closed at the time this report was written. In addition, the examinations revealed several insig-nificant indications in nine examination areas. No other recordable indications were observed. a l O 4 J. 4 4 1 n m i iii

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( TABLE OF CONTENTS Page VOLUlfE I-FINAL REPORT WITH APPENDICES . 1 [ LIST OF ABBREVIATIONS . . . . . . . . . . . . . . . . . . . . . vil I. INTRODUCTION. . . . . . . . . . . . . . . . . . . . . . . 1 ! r A. Examination Areas. . . . . . . . . . . . . . . . . . 1 i Sumnary of Examination Results . 1 B. . . . . . . . . . . II. DETAILS OF THE INSERVICE EXAMINATION. . . . . . . . . . . 3

'A. Equipment. .. .. .. . . . . . . . . . . . . . . . . . 3 B. Radiation Exposure ... . . . . . . . . . . . . . . . 3 C. Explanation of Field Data Records. . . . . . . . . . 3 l

i D. Summary of Nondestructive Examinations . . . . . . . 4 5 E. Summary Table. . ....... . . . . . . . . . . . 5 APPENDICES A. Southwest Research Institute Nuclear Projects r- Operating Procedures f ( -B. Southwest Research Institute Nondestructive Testing Procedure C. Certificates of Personnel Qualifications D. Material Certification E. Customer Notification Form VOLUME II-FIELD DATA 4 Vessel Cladding Patches Core Spray Nozzler Core Spray Piping and Header Core Spray Sparger Piping

                     '_ Jet Pumps Steam Dryer Lugs Surveillance Specimen Holder i

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,1 1 i LIST OF ABBREVIATIONS i

}- AS!E - American Society of Mechanical Engineers i BECo - Boston Edison Company ;

       -CNF
                     -  Customer Notification Form

ISI - Inservice Examination i NDT- - -Nondestructive Testing

[ NRC - Nuclear Regulatory Commission QA - Quality Assurance Reactor Pressure Vessel Rl'V - i- SwRI - Southwest Research Institute VT - Visual Examination

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f x ,f I. INTRODUCTION . During the' January - Feburary_1980 refueling outage, Southwest Research Insti-tute (SwRI) personnel performed remote visual (VT) examinations of selected components in Boston Edison Company's (BECo) . Pilgrim Nuclear Power Station, Unit 1. - These VT examinations were the first to be performed during the first 10-year inspection interval. A. Examination Areas The examinations were 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 Inservice Remote Visual Examination of Pilgrim Nuclear Power Station, Unit 1. Representative samples of the following components and areas were examined using the remote VT testing technique:

   N          Reactor Pressure Vessel (J

Vessel Cladding Patches Core Spray No=zles Core Spray Piping and Header Core Spray Sparger Piping Jet Pumps Steam Dryer Lugs Surveillance Specimen Holder B.~ Summary of Examination Results The remote VT examinations were conducted in accordance with SwRI Nonde-structive Testing (NDT)-procedure 900-2,~ Rev. 7 which was written to conform to

         .the. requirements of the applicable sections of the ASME Boiler and Pressure

Vessel Code and the SwRI Nuclear Quality Assurance Program Manual.. A copy of

         .this SwRI m)T. procedure is included. in Appendix B.

The-remote.VT examinations revealed numerous insignificant indications, as well as: reportable linear indications in four examination areas. These linear indications, found in the upper and lower Core Spray Sparger Piping, were reported to BECo on CNF No. 000002. . BECo perfor 2ed a safety analysis and deter-mined that no component' repair or replacement would be necessary this outage. j A reeramination will be performed during the next scheduled outage. The NRC has verbally ' concurred with this and will be provic ng BECo with a written reply. At the writing of this report, BECo was awaiting the NRC's written

  /~'%  . reply' prior to' closing out. the CNF. Because of interference from structural

. (,,,) configurations, several examinations were either limited or-deleted. 1 L:

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i l The data for the examinations were recorded on standard SwRI forms. A copy of each of the examination data sheets completed on site is included in the field data volume of this Report. The SwRI Quality Assurance (QA) Section was represented on site by the SwRI QA representative who was present for more than 50 percent of the cxamina-tion period. The QA representative performed the appropriate duties outlined in Section 3.3.l(4), "Onsite SwRI Quality Assurance Activities," of the "Proj-ect Plan f or the 1980 Inservice Remote Visual Examination of Pilgrim Nuclear Power Station, Unit 1." O O 2

2 II. DETAILS ~OF THE INSERVICE EXAMINATION Y I t This. section of the report provides a discussion of the equipment used and radiation exposure encountered during the inservice inspection (ISI), an expla-nation of field data records and 'a summary of the nondestructive examinations ; performed. A. Equipment i 1. Remote Visual Testing Pole } .The SwRI Remote VT Pole was used for the VT examinations of the RPV l

            - internal surfaces and components. The pole is comprised of several sections of                                                           .

aluminum tubing which disassemble into 6-foot lengths to provide easier

handling and shipping. The pole enables positioning of an underwater camera j and lights at the examination areas while the examiner remains at a location, -

such as the refueling crane, where the radiation levels are significantly lower.. j 2. Video System I' The video system includes an underwater camera and lights attached to I the pole and a video recorder and monitor set up at the examiner's location. The camera and lights used_ for the Pilgrim examinations were owned by BECo. ' The SwRI equipment, consisting of the monitor and recorder, provided the exam-iner a " live" picture of what was being observed and a videotape of the exami- , , . nations for the data records. l ' I B. - Radiation Exposure , Radiation exposure encountered during the examinations was of fundamental ' concern to all SwRI~ personnel involved during the daily- examination activities. SwRI personnel took the necessary precautions in order to minimize overall expo-

sure and consequently received the minimum dosage practicable while performing !

the examinations. The radiation level on the refueling crane, where the exami-

              - nation personnel were primarily located, was approximately 15 mrem per hour.

C. Explanation of Field Data Records I- The results of the examinations. performed by SwRI personnel were recorded ' on standard SwRI forms. These completed documents constitute a portion of the 4 ISI Report. The original records are retained in the SwRI Data Storage Facility, and copies are provided herein-for completeness.

                     .The Visual Examination Record Sheets for each examination area are assem-i 4              ' bled into' a . package preceded by a Summary Sheet. - The examination areas and I                summary . sheet numbers correspond to those listed in .the Summary. Table. These

< record sheets were used to . record the- results of the examinations. Also, the material used'ht the examinations are also identified on the sheets. r I cU

. -3

D. Summary of Nondestructive Examinations The following sections of this report are presented for explanation of the Sumary 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 columns respectively.

2. Eyamination Area Identification Column In the column entitled " Examination Area Identification," each compo-nent examined (nozzle, cladding, patch, etc.) is * :ntified by the component description. The azimuth location for some of tk. components is also provided.

3. Examination Method Column The NDT examinations required by Code, which for this scope of work is remote visual (VT), are identified in this column.

4. SwRI Procedure Identification Column The fif th column of the table lists the SwRI NDT Procedure used for the examinations. The remote VT examinations were performed in accordance with SwRI Procedure NDT-900-2, Rev. 7.

5. Summary Sheet Column The column entitled " 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 the 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 colu=ns under the general heading of " Indications" are "No Recordable," " Insignificant," " Geometric" and "Other." These columns were used as required, and their general description is provided below.

The results for the remote VT examinations are indicated by an "X" in the appropriate column to be either "No Recordable," " Insignificant" or "Other." The term " Insignificant" is used for those indications that the exam-iner observed but determined were of a nature that did not require reporting to the customer. "Other" is used when indications are observed that are of a

nature that should be reported to the customer. O 4

7. Remarks Column The " Remarks" column is used to provide additional information perti-nent to the examination results {

l When complete coverage of the examination was not possible, the

~
                    " Remarks" column was used to indicate the limitations.

For examination results reported in the "Other" column, a brief dr.scription is given in the " Remarks" column.

Reference is made in the " Remarks" column to a CNF used in the i reporting of indications. E. Summary Table , The Summary Table is included from page 7 through 9 of this report. ! t i i ( E .t i t 4 u T r O S 4 _n. -+, 3 -,. , . .e .. , . ,--,,n,..e._-. ,w.e-.r e-. e wr-+-*-**-- - " ' - ' * ' 4 w * *f - t &t-T T~'"-f' " *"'

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I / k / k i Q w/ % PILCRIM NUCLEAR POWER STATloN UNIT I l 1980 INSERVICE REMOTE VISUAL EXAMINATI(el REACTOR PRESSURE VESSEL E X AMINATION EXAM' fliMARKS SE C. XI SEC. XI PHOCEDURE E X AM. SUM IT E M NO CAIGY. ARE A IDENilFICAllON METHOO

                                                                                                   . NO /RE V. Si4EET NO. NO RECORDABLE INSIGNIF ICANI GEOME T R6C OTilER B1.15      B-N-1      Vessel Scaling Surface     VT     900-2/7            (See Remarks)                                        No VT examination due to the inac-censibility of the area. Inacces-sibility of the area was due to the positioner ring.

81.15 B-N-1 VF.SSEL WAl.L VT 900-2/7 300027 K RPV Cladding Patches at 120' and 315' N0ZZl.E INNER RADIUS SURFACES 81.15 B-N-1 Steam Nozzles VT 900-2/7 (See Remarks) No examination due to tlee presence of plugs. u ut.15 B-N-1 Instrumentation NozzJes VT 900-2/7 (See Remarks) No examination due to the presence of plugs. Bl.15 B-N-1 Core Spray Nozzles 0* VI 900-2/7 300u 11 X to 360* n1.15 B-N-1 Feedwater Nozzles VT 900-2/7 (See Remarks) This examination area was deleted at the request of BECo. CORE SPRAY LINES. N0Z-ZIIS AND NITACalMENTS 81.15. B-N-1 Core Spray Piping and VT 900-2/7 300033 X Examined only half of piping due to Header 5' to 175* proximity of vessel wall. Bl.15 B-N-1 Core Spray Piping and VT 900-2/7 300012 X Examined only half of piping due to lleader 185* to 155' prominity of vessel weld. 81.16 B-N-2 Core Spray Sparger VT 900-2/7 300028 X No examination on upper sparger Piping 0* to 90* piping due to camera interference from upper core guide. Bl.16 B-N-2 Core Spray Sparger VT 900-2/7 100016 X VT indicatson (linear) in upper Piping at 5* sparger. See CNF 000002. Examined Tee-to-Pipe only half of weld anJ pipe due to proximity of vessel wall. Reemanina-tion required during next sc heduled outage. EECo await ing NRC writ ten reply prior to closine CNF.

PIIERIN NUCLEAR I4KdER 51 ATION, UNIT 1 1950 l3ERVICE Rett)TE VISUAL EXAMINATION kEACTOR PRESSURE VESSEL (Cont'd)

     ^#I       N                                            S*HI          WELD                       lhDICAllONS E M AM4NA i40N        EXAM A SOM                                                                     Hl.M AR K S AHE A IDiP4f tf 4 CATION Mt I1400 IIE M NO   CAIGY                                       NO /HLV.     $ltE E I NG. NO hlCOHOAbtl INSIGNIF ICAN I GIOME THIC 0144t h CORE SPRAY I.INES, N0ZZI.ES AND ATTAC11MtNTS (Cont'd) 81.6     B-N-2  Core Spray Sparger            VT     900-2/7       300017                                                 I     VT indications (lineae) in ti.e uppes Pipisig at 175*                                                                                                 uparger. See CNF 000002. Examined Tee-to-Pipe                                                                                                     only half of weld and pipe due to -

proximity of vessel wall. Reemam-ination requireJ during next scheduled outage. BECo awaiting NBC written reply prior to closing CNF. 81.16 B-N-2 Core Spray Sparger VT 900-2/7 300034 X Limited VT examination due to upper Piping at 90* to 360* core guide structure and CRD guides interference. Bl.16 B-N-2 Core Spray Sparger VT 900-2/7 300018 I VT indication (linear) in the lower Piping at 355* mparger. See CNF 000002. Examined only half of weld and pipe due to the proximity of vessel wall. Re-examination required during nest m scheduled outage. BECo awaitisig NRC writtcn reply prior to cloming CNF. B l .1-6 B-N-2 Core Spray Sparger VT 900-2/7 300019 X VT indication (linear) in the lower Piping at 185* sparger. See CNF 060002. Examined Tee-to-Pipe only half of welJ and piping due to the proximity of vessel wall. Re-examination required during next scheduled outage. BEco awaiting NRC written reply prior to closing CNF. Bl.15 B-N-1 Upper Core Plate VI 900-2/7 (Sec kemarks) This examination area was deletcJ at the sequest of BLCo. Bl.15 B-N-I 1.ower Core Plate VT 900-2/7 (See temarks) No examination due to the inter-ference by CRD Culde St ruc ture. Bl.15 3-N-l Core Shroud VT 900-2/7 (See temarks) This examination area was deleted at the requent of BECo. Bl.15 B-N-1 Bottom luside Surface VT 900-2/7 (See Remarks) No examination due to in.accessibi-lity of this area. O O O

e /- 7-i I ( l ( f q, ' LJ 'n,- PILCRIM NUCLEAR POWER STATION, UNIT 1 1980 INSERVICE Rt29)TE VISUAL EXAMINATION REACTOR PRESSURE VESSEI. (Cont'di - SEC.XI SEC. XI E XAMINATION EXAM ^ REMARKS PROCE DURE E XAM. SUM ARE A IDENilFICAllON METHOD I TE M NO CAIGY. NO/REV. SHEET NO. W RECORDA8tE INS 4GNIF ICANI GEOME T RIC OTHER JET PUMPS 51.15 B-N-1 Jet Pumps 90* to 270* VT 900-2/7 300038 I Limited examination due to vessel , wall and core shroud interference. Bl.15 B-N-1 Jet Pumps 270* to 90* VT 900-2/7 300015 X Limited examination due to vessel wall and core shrouJ interfenence. STEAM DRYER. SEPARATORS AND ATTACIINENTS 51.15 B-N-1 VT 900-2/7 (See Remarks) No examination due to inaccessibi-lity of these areas. STEAM DRYER LUCS c ,11.16 B-N-2 Lugs at 45*, 133*, 225* VT 900-2/7 300026 I I and 315* SURVEILLANCE SPECIMEN llOI. DER N/A N/A At 120* VT 900-2/7 309039 I Requested by BECo to verify its location.

1 i Y J- l i ! 1 !' l i . O l l I 4 ! l I i i i i i t l i l t i,- 1 1 t I I 1 1 APPENDIX A , j ' SOUTHWEST RESEARCH INSTITUTE i 1 NUCLEAR PROJECTS OPERATING PROCEDURES i t i I I i l } } } 4 l i

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.i APPENDIX A SOUTHWEST RESEARCH INSTITUTE ! NUCLEAR PROJECTS OPERATING PROCEDURES , Table of Contents j Procedure No. Title X-FE-101-0 Onsite NDT Records Control , XIII-AG-101-0 Control of Nucicar Inspection Equipment CHANGE 1 , XV11-AG-101-0 Data Storage and Retrieval ! CHANGE 1 ! f I 1 4 l 4 i A-1~

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SOUTHWEST RESEARCH INSTITUTE x-a -101-0 Mar 6 NUCLEAR PROJECTS OPERATING PROCEDURE

Page 1 of 6 g _

j. p ONSITE NDT RECORDS CONTROL PURPOSE t

j 1.1 The purpose of this procedure is to describe the flow in the field of the nond2structive testing records generated during 3 preoperational and inservice examinations. 2.0 SCOPE AND APPLICATION 7j g e 2.1 This procedure is limited to describing the flow of data records used to document the results of the nondestructive 3 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.

( g 2.2 -r.ere necessary to explain the flow of the records, functi, mal {- steps are provided in this procedure. L

2.3 This procedure provides guidance to personnel of the Nuclear

Field Services Section who are assigned the responsibility of

           ,                           preparing, reviewing, or otherwise using data records while in the field performing a preoperational or inservice 29 examination.

lg5 3.0 RESPONSIBILITY b 3.1 The Manager of the Nuclear Field Services Section within the j Department of Engineering Services shall be responsible for 15 g the implementation and control of this procedure in accordance with the applicable portions of the issue of the Nuclear Quality Assurance Program Manual in effect on the date the s $ procedure is approved. k 3.2 The Team Leader has the primary responsibility in the field for assuring compliance with this procedure. g Q 3.3 Each person performing functions falling within the scope of g this procedure shall comply with its requirements. E n di () ..ai 6 a .a u

SOUTHWEST RESEARCH INSTITUTE x-PE- 101-0 March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 6

k j 4.0 PROCEDURE 4.1 Original Data Sheets a

yi [{k 4.1.1 Original Data Sheets are created when they are d reproduced and seriali:ed either at SwRI or the g site. Q 4.1.2 Origina1 Data Sheets will be filled out at the place

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and time of the examination. 3 & 4.1.3 The Original Data Sheets are returned to the team d T staging area (office, trailer, etc.) on a periodic

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 been performed.

      "Q                    4.1.4      If a computer is being used to record results and
      '1 generate Summary Sheets, computer input will be made 3;                                    for records containing data which requires no s                                    evaluation or resolution, s'         ,

4.1.S The Original Data Sheets are then placed into the d' s. To-Be-Reviewed file. 4.1.6 The Re;iew Process is performed as follows: 5s 4.1.6.1 The Original Data Sheets will be j N checked for completeness and, to the j extent practicable, cecuracy and g A consistency of the data.

      ]n                               4.1.6.2       If clarification of any entry on the i                                                  Original Data Sheets is required, the M                                             Original Data Sheets are returned to the Examiner.

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A mO SwRI F orm QA.3-1

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SOUTHWEST RESEARCH INSTITUTE X-FE-101-0 NUCLEAR PROJECTS OPERATING PROCEDURE

                          -                                                           Page 3 of 6 3       Q 4.1.6.3       After clarifications, if any, are made, j              s                                   the Reviewer signs each Original Data Sheet that does not contain indications
                    ~

which require evaluation and/or reso-lution. f j , 4.1.7 The Original Data Sheets that have been reviewed and signed are moved to the To-Be-Summarized file. See a 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 m 4.1.8.1 Original Data Sheets in the To-Be-Resolved file which document visual or

                 ]m\                                           surface examinations are handled as p) 1 f

s j, N ' follows: 4.1.8.1.1 The Original Data Sheets

             !! '                                                           are reviewed, signed by the 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 p                                                              13-1).

p The Original Data Sheets z q 4.1.8.1.2

            ]2           j                                                  are duplicated in order to be attached to the CNF.

k N 4.1.8.1.3 The Original Data Sheets 1V are then put into the To-Be-Su=marized file. See i C Paragraph 4.1.9. N h k 5 h., 7 e {mI

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          $wAI Form GA-M

SOUTHWEST RESEARCH INSTITUTE x-Ps-101-0

                                                                                 !.tarch 1976 NUCLEAR PROJECTS OPERATING PROCEDURE
                      . N, ,
               ~                                                                  Page 4 of 6 E   N 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 S 4.1.6 and 4.1.7.

o N 4.1.9 Data placed in the To-Be-Su=mari:ed file is sum-marited according to Paragraph 4.2 and filed with the Summary Sheet in the original data volumes.

    . 7 g    ~.                  4.2 Summary Sheets m

4.2.1 Summary Sheets are created when they are reproduced 8p and serialized either at SwRI or the site. If in use, the computer will generate the Summary Sheets M s at the completion of all required examinations of an examination area. s, 4.2.2 Summary Sheets will be filled out for each exami- { nation area. In certain cases (studs, nuts, etc.), __ one Summary Sheet may be used for more than one examination area, di 4.2.3 Summary Sheets are to be filled out prior to the completion of site activities for each examination C ' area which has its examination requirements com-js ;- pleted.

    $  N j      W                     4.2.4       Summary Sheets will be filed with the data in the original data volumes.

4 4.3 Resolutien Sheets

     .   -k                                                                                       ~

d ' 4.3.1 Resolution Sheets are created when they 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 Q necessary to resolve the ultrasonic indications and j 3; will complete a Resolution Sheet describing the g results of his analysis. Any additional documenta-E y tion required to support the resolution will be attached.

        ]
        <"5 SwRI Form QA-31

m ( I c/ SOUTHWEST RESEARCH INSTITUTE X-FE-101-0 NUCLEAR PROJECTS b"R_ g' 9 OPERATING PROCEDURE Page 5 of 6 8 k

          .                          4.3.3       Original Data Sheets and resolution records with 5

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 5 be handled in a manner established by the Director, j , Department of Engineering Services. f 4.4 Strip Charts, Magnetic Tapes, Video Taces 4.4.1 Strip Charts, Magnetic Tapes, and Video Tapes are g N generated during mechani: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 as (,) 11 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. M 4.4.4 The strip charts and tapes are then made ready for transmittal to SwRI. s d' 4.5 Customer Notification Forms p , 4.5.1 Customer Notification For=s are created when they p , are reproduced and seriali:ed either at SwRI or the y site, j 4.5.2 Customer Notification Forms are handled according N % to SwRI Nuclear Quality Assurance Program Manual, F Procedure 13-1. _W I D5.O RECORDS S 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 strip charts, magnetic tapes, and video
          =       %a                 tapes will be reproduced and the copy will be transmitted to
           ! l

A

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SOUTHWEST RESEARCH INSTITUTE X-FE-101-0 March 1976 NUCLEAR PROJECTS LRo OPERATING PROCEDURE 1 Page 6 of 6 8 -$

  .                  the appropriato 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. a g,

             >   5.2 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 g with SwRI Operating Procedure XVII-AG-101-0. U E 3 M il4 i4 9 1 ===========i 5 k' ' j 1

s 1 3

  !     1 i   4 d!

Seat Form QA 31

n ( ) b' Change 1 SOUTHWEST RESEARCH INSTITUTE u n-Ac-101-0 June 1977

                  ,,$; .                         NUCLEAR PROJECTS                       Page 1 of 11 OPERATING PROCEDURE
          ~

N 6 CONTROL OF NUCLEAR INSPECTION EQUIPMENT s' hl.0 PURPOSE 1.1 The purpose of this operating procedure is to provide control for l the storage, inventory, issue, shipment, and return to stock of g, nuclear inspection equipment. 2.0 SCOPE AND APPLICATION 8' I

                     ;         2.1   The scope of this procedure is the control of nuclear inspection
          ==:=,                      equipment to ensure the integrity of equipment and materials used during the examination of nuclear power plant components.

3 Q o O O 2.2 Controls are further required to ensure that maximum utilization z s is made of available equipment, i.e., equipment is not " lost" in the Radiation Control facility, delayed or misplaced during y transit from job site to maintenance shops, or allowed to remain x

     ")     -

g q-Q idle for long periods of time while being used for research and development projects. The flow chart illustrates the control and 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:

__s k (1) Ultrasonic Test Equipment (2) Plastic Wedges f N' ($ (3) Ultrasonic Testing Materials (4) Penetrant Testing Shterials 7 (S) Magnetic Particle Testing Materials and Equipment j (6) Eddy Current Testing Equipment and Standards

          -       M                  (7)    Mechanized Inspection Equipment
                  .w    Q            (8)    Data Acquisition Systems k

5 1 f3 ( ) Qr

    \.d   $wRI Fo7m QA-31

SOUTHWEST RESEARCH INSTITUTE u n-AG-101-0 h NUCLEAR PROJECTS March 1976 (R OPERATING PROCEDURE Pabe 2 of 11 8

    .                2.4   The following documents form a portion of this procedure as 8            \         applicable.
        -                  2.4.1    SwRI Nuclear Quality Assurance Program Manual (NQAPM).

i< 2.4.2 SwRI Radiological Health and Safety Manual. d { f 3.0 RESPONSIBILITY 3

    $                3.1   The Vice President of the Quality Assurance Systems and Engi-neering Division shall designate one or more secure areas to be used for equipment and materials storage as control facilities.

S $ 3.2 Control facilities shall be operated by a Stock Clerk under the supervision of the Manager, Support Services, who will be

g 3 s responsible for inventory, storage, issue, and retrieval of contro11ed equipment. 3.3 Responsible users, such as Team Leaders, shall be respon-G sible for compiling a list, using swr 1 Form SS-17 Equip-3- E ment Contro1/ Shipping List (Attachment 1), of equipment and g materials required for each job or project. They shall be N responsible for shipment of the equipment to the job site, security while at the job site, reshipment upon completion g Y , of the job, decontamination if required, documentation of faulty equipment, and turn-in of equipment and unused materials. C g 3.4 The Manager, Production and Maintenance or his alternate shall j $ be responsibic for providing minimum maintenance turnaround time c q and for providing current certifications as required for nuclear y , inspection equipment. I dho PROCEDURE 4.1 New Equipment i .3

         $"                4.1.1    Newly purchased or fabricated critical equipment sha11 be inspected in accordance with operating procedure VII-AG-101 prior to being routed to the appropriate control facility, e    :

o W s.m ,.- om h

4n) SOUTHWEST RESEARCH INSTITUTE n tt-^c-tot-o March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 11 _v

       -      b                  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.
              -3 s                  4.1.3   Upon completion of proper identification, new equipment 3k      <                     will be listed on the control facility inventory records.

5 9 4.1.4 Once new equipuent is properly identified and inventoried, it will be is sed to the appropriate maintenance facility j

j. for an operar.onal check and certification in accordance u with Nucler Quality Assurance Program Manual (NQAPM) procedure NQAP 10-1. The maintenance facility will return

the equipment, along with copies of certifications

           . ir j y4                          generated, to the control facility. The new equipment may
              -'                         then be issued for nuclear inspection work.
                                    quantity and nonmenclature of each item of equipment or i %'                         materials required and indicate those which require
           .!                           certifications. Serial numbered items must be entered j\

~~one icem'on each line.~~
~~l 2 ~ [ g 4.2.2 hhen the Team Leader or Responsible User has initiated l Form SS-17, he may assign any technician to draw and pack~~
-- the equipeent. The technician will present Form SS-17 to . N the control facility, and the Stock Clerk will issue the l c ( equipment. The Stock Clerk will enter appropriate serial 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. hhen l g h requested equipment and/or materials have been issued, the I g e technician will sign each Form SS-17, indicating that he i b has received the items for the responsible supervisor.
~~E The Stock Clerk will retain Copy 3 of Form SS-17 for his {~~
~~% records.~~
~~m %~~
~~\ / 5*RI Form QA*3-1~~
~~0-ntt-^c-to -o SOUTHWEST RESEARCH INSTITUTE March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 11 E k 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 in numbered shipping containers. He will then enter the I]~g' container number in the appropriate Box No. space on Form ! SS-17.
N
} 4.3.2 If the equipment is to be shipped by freight, a box count i-0 k) must be made and each box must be weighed. Shipping labels must be ecmpleted and affixed to each shipping container.
~~IN 4.3.3 When the packing has been co=pleted, the technician will j 'y A 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.
pQd 4.3.4 If equipment is to be shipped by freight, the responsible g supervisor will contact the Requisitioning Agent, who will sA arrange for shipping and for the proper shipping documents A to be completed.
, g 4.3.5 The responsible supervisor will review Form SS-17, with a g special emphasis placed on ensuring that appropriate certifications are available for each item that requires % certification.
~~3 4.4 Onsite Control~~
} h 4.4.1 The Team Leader or Project Engineer shall assume respon- ,L,d s sibility for the security of equipment once it has been drawn from the control facility. At the j ob site, he will fh ,
~~obtain a secure area to be used for equipment storage and 7'd c e will arrange for issue of the equipment or materials as~~
$ the work load demands. He will ensure that equipment placed into onsite storage after use is dry and clean and that any equipment damaged or found to be inoperative or out of tolerance is tagged with a red hold tag, SS-19, b ~
~~to indicate its condition (Attachment 3).~~
;
~~k t f %~~
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4 SOUTHWEST RESEARCH INSTITUTE 0*"!L_101-0 [_. NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 11 a 4 4.5 Decontamination e d s 4.S.1 Equipment being returned from an inservice inspection must
% be delivered to a radiation control area immediately upon y return to the Institute. Equipment that can be decontami-E nated may be returned to the control facility after !< decontamination, in accordance with SwRI Radiological Health and Safety Manual, Paragraph S.2. Equipment that = cannot be decontaminated must be stored in a radiation fr S control area. The Division Health Physics representa-tive will prepare a memorandum addressed to the Manager, 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
( the hot radio logical controlled storage facility. The Equipment Control Clerk will initial and date the remarks e g section of the Form SS-17, copy 3 indicating that the particular equipment has been returned to the Institute. 4.6 Equipment Turn-In
~~E j 4.6.1 Upon completion of a project or the return to the Insti-tute of equipment used off the grounds, the equipment~~
-4 and/or unused materials will be returned to the control 3 g facility. As each item is checked in, the Stock Clerk 6' a b will enter the date and his initials in the appropriate
_.2n remarks block of copy 3 of the Form SS-17. He will also enter the date that the equipment was returned and his p initials in the appropriate remarks block of copy 2 of the Form SS-17 when requested.
~~s 1 [ 4.6.2 The Stock Clerk will check each item for disposition. i~~
, . Equipment requiring repair, cleaning, or recertification/ l 6 recalibration within the next 30 calendar days must be === =*9 accompanied by a Form SS-19, Hold Tag; (Attachment 3) g and taken to the appropriate maintenance facility.
~~O 4.6.3 When repair and/or certification is completed, the item wil1 be returned to the control facility and placed in~~
*9 stock for reissue.
M h m i: % SwRI Form QA.3-1
Change 1 O SOUTH' WEST RESEARCH INSTITUTE n u-Ac-iol-1 June 1977 h, NUCLEAR PROJECTS Page 6 of 11 R m OPERATING PROCEDURE ii_k& l2 G m 4.6.4 Expendable materials such as Penetrant Testing Material d and Magnetic Particle Testing Materials will be returned to the appropriate s tock room. When the stock clerk can o@ determine that the material has not been used and identify-
]
h ing data is available to trace the material to the appropriate certificates and to the original purchase W i order, he will credit the appropriate job site by O' . processing an appropriate store requisition. i 4.7 Special Issue Recuirements 4.7.1 Occasionally it will be necessary for a Team Leader who g is in the field to request that equipment be checked out Q,g 8 and sent to him. When this circumstance arises, he will contact the Examination Activities Coordinator or his alternate and make his needs known. The Examination Activitiss Coordinator or his alternate will initiate c % Form SS-17 and draw, pack, and ship the equipment. He C will perform the review and enclose Copy 1 of Fom SS-17 in the shipping container so that the Team Leader will k (J have a record of what was actually shipped. S., 4.7.2 If equipment is to be shipped from one job location to another without returning to the Institute, a packing A 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 y will be returned to the control facility at the Insti-4 .( tude. The responsible supervisor will review the Form i y' SS-17 to insure that certificates were included as required. g - 4.8 Lost or Destroyed Ecuiement
~% , , 4.8.1 In the event any item other than normally consumable j , ( materials are lost or destroyed while it is signed out of the control facility, the responsible supervisor will u initiate a memorandum addressed to the Assistant Manager, Nuclear Field Services, and the Manager, Production and Maintenance, with a copy to the Manager of Support Ser-Og vices. The memorandum will identify the equipment and g
i describe the circumstances involved with its loss or destruction. y d' 1 k SurRt Form QA 31
p 'V SOUTHWEST RESEARCH INSTITUTE change t XIII-AG-101-0 June 1977 NUCLEAR PROJECTS i^w OPERATING PROCEDURE Page 7 of 11 4.9
~
Recall of Equipment for Recalibration 2. 4.9.1 When notified that a particular piece of equipment is due recalibration, the Stock Clerk will determine the j. h location of the equipment by reviewing his equipment inventory records. If the equipment is located within g, - the stock room, he will place a " Hold Tag" on the item y
. and take the equipment to the appropriate certifying g facility. When the equipment has been issued, the Stock @ Clerk will notify the Field Services Activity Coordinator or other responsible supervisor by completing a Form - l SS-42. (Attachment 2) The Activity Coordinator or . M) responsible supervisor will ensure the equipment is d Q sent to the Stock Clerk on or before the recalibration e! date. The Stock Clerk will then place a " Hold Tag" on gl\ the item and take it to the appropriate certifying O
~~g facility. t c' (") 3 3 Note: If a particular piece of equipment is being used~~
~~,( in a non-critical application, it need not be returned until completion of the project.~~
~~E 3 S.0 RECORDS 7 S.1 Copy of Form SS-17 shall be maintained by the control facility 3~~
a for a minimum of six months after the last item on the form was k turned in. Copy 1 shall be retained by Field Services. S.2 SwRI Form SS-42 may be destroyed upon return of equipment to the stock room. S.3 The Stock Clerk will maintain a file of current equipment 5 certification records. An adequate number of copies will be included for issue during equipment issue. 2 3
~~% 4 0 , 9 2~~
p<
~~\I SwAl Form QA 3-1~~
~~-- 1- -'~~
XIII-AG-101-0 O March 1976 Page 8 of 11 EQUIPMENT CONTROL / SHIPPING LIST Project No. Site Date Required Shipping Method Approximate Return Date Responsible Supervisor CERT. QTY. NOMENCLATURE REQ'O SERIAL NO. BOX NO. COST REMARKS O I I l l TOTAL COST Audited by: Received by: SwRI Form SS-17-0 Attachment 1 9
/^% i 1 Change 1 SOUTHWEST RESEARCH INSTITUTE xiu-Ac-tot-o June 1977 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 11 8 d_: o . R F.C AllB R A TION NOTICE ro. nou . cars .
.i o, L r,. ..w., um. -t. . .u .: - n.~.o rio. a. ,, ors. .g essau marum= r=s rauww.r to r,. sou,wn, acou as soon as ... .te 3 " tecario.
~~iriu lsmat nu un l ncaunaance mars l~~
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l I F Recalibration Notice p) (d\ w (SwRI Form SS-42) Attachment 2 j swas Form oA-21 ) I I l 1
4 XIII-AG-101-0 O March 1976 Page 10 of 11 HOLD O e DO NOT USE s e 2 2 i e s e O25 W m E 2 Z Attachment 3 O
XIII-AG-101-0 March 19*6 Page 11 of 11 NEW EQUIPMENT EQUIPMENT CONTROL 1 I _ t INVENTORY I:
~~' RADIATION~~
~~%\ E :I STORAGE l CON OL l ISSUE l_ __ __ __ T~ __ __ _u_ _ J~~
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EQUIIMENT a USER Attachment 4 l l l
O SOUTHWEST RESEARCH INSTITUTE EII?"Ic'101-0 June 1977 NUCLEAR PROJECTS Page lla of 11 hR g OPERATING PROCEDURE , L% s EFFECT1VITY PAGE 5 \ Revision 0 of this Operating Procedure became effective in March 1976. vision 0 consists of the pages and changes listed below. 31 W Page Number Change Revision Effective Date 9
~~! 1 1 0 June 1977 0 March 1977 }o 2-4 5-7 0~~
1 0 June 1977 8 0 0 March 1977 g' 9 1 0 June 1977 I g" 10-11 0 0 March 1977 0 June 1977 of lla 1
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k l NO4 l Cd h i 55 SwRt Form QA.31 O
n V 4 SOUTHWE5T RESEARCH INSTITUTE xvtt-^c-tot-o March 1976 NUCLEAR PROJECTS (M 4'.} OPERATING PROCEDURE Pa 1 f7 DATA STORAGE AND RETRIEVAL 8 qY 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 8 i by ANSI N45.2.9, " Requirements for Collection, Storage, and ; ij N Maintenance of Quality Assurance Records for Nuclear Power i 3 d Th\N Plants." This operating procedure satisfies the requirements of Appendix R to 10CFRSO, Criterion XVII and the SwRI Nuclear Q Quality Assurance Program Manual. m s g 0 SCOPE AND APPLICATION h " 2.1 The scope of this procedure is limited to the documentation of examinations performed by Nuclear Field Services, Quality
\ Assurance Systems and Engineering Division, and to other O o documentation as designated by the Vice President, Quality V ! Assurance Systems and Engineering Division.
I 3t 2.2 This procedure applies to the Data Control Clerk, Team Leaders, [ Inspection Engineers, and all other personnel who enter and h receive documents from the Data Storage Facility. { 2.3 Other divisions of the Institute may store quality assurance C
~~$ 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. 3.0 RESPONSIBILITY ,~~
.g ii . 3.1 The Manager of Support Services within the Quality Assurance k\ Systems and Engineering Division shall be responsible for the implementation and control of this procedure.
~~l j 3.2 The Data Control Clerk of Support Services shall be responsible~~
~
for controlling, filing, and maintaining documentation covered by l (g t this procedure in the Data Storage Facility. He shall assume this responsibility when documents are received in accordance 1 l h 7h with Paragraphs S.1, S.2, and S.3. l 1 g, 3.3 Team Leaders, Inspection Engineers, and other personnel compiling !
$ documentation shall be responsible for ensuring completeness and l fm accuracy of documentation being entered into the Data Storage j (v ) Facility. (See Section S.O.) l SwRI F Im QA.J-1 1
I
SOUTHWEST RESEARCH INSTITUTE ch == = 1 O XVII-AG-101-0 L NUCLEAR PROJECTS
/g 2 9 OPERATING PROCEDURE June 1979 Page 2 of 7 Si h , s 3.4 The Manager of Support Services, or his representati/e, shall 3
routinely review Section performance against the requirements of chis procedure. 3 3.5 The Manager of Quality Assurance, or his designated representative, s shall routinely audit performance against the requirements of this - 3 }, procedure and shall report the results of such audits to the j, g M Manager of Support Services and the Vice President, Quality Assur-3 ance Systems and Engineering Division. TON > 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 f acility in Building 139 is concrete block with a steel vault door. Both facilities have temperature control devices to regulate temperature and humidity.
.0 PROCEDURE Q 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 te tF , Data Control Clerk.
~~3, , 5.2 Upon receipt of the data, the Data Control Clerk will use the~~
~~, transmittal form as a checklist to ensure all material listed has been received. The Data Clerk will inventory the data by preparing m~~
~~f a listing of Sum =ary Sheet numbers or by entering the Summary Sheet numoer on the weld table. If the Summary Sheet number was previ-~~
~~= ously entered on the weld table, the Data Clerk will ensure that M , , 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 -~~
~~j 1 pared at the time of receipt of the data, the Data Clerk will pre-~~
~ - pare a listing showing the number of each data sheet received. The 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:
~~_A L~~
~~% O SwRI Form Q A-3-1 r~~
b.
V SOUTHWEST RESEARCH INSTITUTE xvtt-Ac-tot-o March 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 7 a q n I C (1) Reactor Site Name. g (2) Date of Record Entry. W \- d i (3) Description of Material. Analog and video tape and strip j charts will have a complete description of informatinn 3 contained therein. This information is entered by the Team d , Leader, the Inspection Engineer, or their designated alternates. 3 I The Data Control Clerk will then enter the data into the Data 5 - Storage Facility, q 5.3 PSI and ISI reports, other nuclear power plant examination ,x g reports, examination plans, etc., relating to a particular
~~) e reactor,will be furnished the Data Control Clerk by the Report (J~~
L
~~] k Coordinator.~~
5.4 Other records designated by the Vice President, Quality Assurance Systems and Engineering Division, as authori:ed for storage in h the Data Storage Facility, will be furnished the Data Control Clerk. I o y' 5.5 Items being removed from the Data Storage Facility shall be signed out. The individual withdrawing the material shall be g , responsible for the safekeeping and return of the material, p Original field data will be returned to the Data Storage Facil-c . ity at the end of each day. If the data need to be used after h jik normal duty hours, special arrangements will be made with the Data Control Clerk. s a a e l
~~,5 5 .s E~~
~~q m ,g~~
~~$weRI Form QA-31~~
~~SOUTHWEST RESEARCH INSTITUTE wit-^c-tot-o O March 1976 6 NUCLEAR PROJECTS tg D OPERATING PROCEDURE~~
~~' Page 4 of 7 u Q 3 rg~~
[ 5.6 The Data Storage Facility will be maintained in a neat and orderly manner. As much as practicable, records will be kept inside file cabinets. Loose papers, drawings, etc. shall be placed in folders, binders, or envelopes for filing.
! 6.0 RECORDS 5 'l E 6.1 The Data Control Clerk will maintain an up-to-date list of f k records covered by this procedure and their respective locations.
G ' ( 6.2 Data maintained in the Data Storage Facility will be retained g for the periods indicated in Appendix A or according to written s instructions furnished the Data Control Clerk at the time the
~~$[#~~
records are placed into the Data Storage Facility. The period of retention will in no circumstances be less than the time 8% spetified in the applicable contract, if any. e 6.3 Project Managers should review the records in the Data Storage
} G Facility relating to closed projects to determine their ultimate dispositioning; g f i.e., return to client upon termination of g contract, continual storage in the Data Storage Facility, etc.
~~Decisions should be coordinated with the appropriate Director q and the Data Control Clerk notified in writing. The Data Control Clerk will comply with the written instructions, s s p - 5~~
~~.e s~~
~~e i 4 o Q~~
*b a
e u SwRI Fo'rm QA-31 e
XVII-AG-101-0 March 1976 Page 5 of 7 l RECORDS TR ANSMITTAL AND RECEIPT From:(Name of Team Leader Site: To: Data Manager or I. E.) Division 17 SWRI BOX NO. DESCRIPTION OF DATA ,
;
No. of Volumes 1 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 Beam Profile No. of Certs. Material Certificoflon No. of Cer ts. Instrument Certifications Yes List of Procedures Yes No Photographs Yes No Scan Plan ( Mechanized) Other Data and Comments: i 4 Signature (Team Leader or 1.E.) SwRI FORM SS-1-0 l
SOUTHWEST RESEARCH INSTITUTE xvtt-^c-tot-o O March 1976 L4 g NUCLEAR PROJECTS OPERATING PROCEDURE ev Page 6 of 7 0 $ 3 y APPENDIX A The following is a list of documentation maintained by Data Control in the Data Storage Facility with retention periods. 3 i t 5' j $ 3- KRecord Type Retention Period
~~& M .[ y(I) PSI, ISI, and other examination As determined by the reports Proj ect Manager a~~
~~s k Includes: Personnel certifications Y y Search unit, material, and instru-~~
~~# D $NN, ment certifications 3 Zero reference location $D '~~
~~Weld identification isometric p drawings~~
~~% Calibration standards~~
~~Nondestructive testing procedures~~
~~; j (2) PSI, ISI, a'nd other examination As determined by the c g data Proj ect Manager , Includes:~~
~~Original data~~
~~; Video tapes~~
( x Analog tapes Eddy current data g\ Eddy current tapes y Strip charts i f Equipment calibration sheets o 9 A8 i"
$ (3) PSI, ISI, and other examination plans ?[tfbnage 'N(4) Photographs relating to examination of As determined by the 8 nuclear power plants Proj ect !!anager 5
E g{ (5) Logs, drawings, and summaries created As determined by the by field crews during an ISI or PSI Proj ect Manager O $wn1 Form QA.J.1
m O SOUTHWEST RESEARCH INSTITUTE xv11-Ac-101-0 ar 1976 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 7 8 k g Record Tyne Retention Period 3 (6) General information which would be As determined by the of value in. conducting future ISIS Proj ect Manager j s, (7) Makeready IS0s and standards Destroy when revised, superseded, 3 or no longer required. Minimum p
~
retention period is 1 year. h fyk8) Makeready procedures; personne1, Destroy 6 months after issuance material, and instrument certifi- of Final Report. o cations; and other report data s 'N 6M a (9) Other general information which will not provide valuable information in Destroy after 2 years. g conducting future ISI's T O v bew tj kg N s
~~$' s I~~
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~~.l"b ii:~~
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~~\_/ h $wRI Form QA-3-1 j~~
Change 1 SOUTHWEST RESEARCH INSTITUTE XVII-AG-101-0 O k NUCLEAR PROJECTS June 1979 yk s OPERATING PROCEDURE 7" Page 7a of 7 EFFECTIVITY j f.Revision 0 consists of the pages, changes, and revisions listed below: Revision 0 of the Operating Procedure became effective in March 1976. Page Number Change Revision Effective Date E j 1 0 0 March 1976 1 2 1 0 June 1979 [ \through7 0 0 March 1976 ( .
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s 1 w's 3 I' ( i, ? Swa t Foem GA.31 e
i
9 ,
l i i i 5 i l . i i i l l l i i , APPENDIX B SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURE f a f 4 I t i

9
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~~. . _ . . _ _ . . _ ~ _ _ _ . . _ . . . _ . _ _ _ _ . . _ . .~~
~~3 i. i-J~~
~~). APPENDIX B' k r~~
~~. SOUTHWEST RESEARCH. INSTITUTE ,~~
~~i NONDESTRUCTIVE TESTING PROCEDURE l l~~
~~> .~~
l Table of Contents l t ,
~~j. Procedure No. Title !~~
1-900-2/7 Visual-Examination of Nuclear Reactor Internals By Direct or Remote Viewing i I t I i - i i 5 4 5 e. i t' I, - 4 i-1 t g B-1'-
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O SOUTHWEST RESEARCH INSTITUTE U"I.;E% i ~* March 1978
% NUCLEAR PROJECTS p OPERATING PROCEDURE Page 1 of 6 8 _V s VISUAL EXAMINATION OF NUCLEAR REACTOR INTERNALS I, .
~~BY DIRECT OR REMOTE VIEli1NG a SwRI-NDT-900-2 h N~~
!'h 1.0 PURPOSE TN $ This procedure provides the technical information and detailed steps ) 9f required to ensure proper visual examination of nuclear reactor internals, 4 'l?P accordance with the applicable ASME Boiler and Pressure Vessel Codes.
~~3 2.0 SCOPE AND APPLICATION 3$ 2 Nuclear reactor internals as specified in the applicable SwRI Examina-qion Plan shall be examined visually by direct or remote viewing. ( t~~
! 3-2.1 Applicable Documents p The following documents form a part of this procedure, as g applicable: , , (1) ASME Boiler and Pressure Vessel Code, Section XI, 1974 -' Edition, with Addenda through Summer 1975, " Rules for gl g Inservice Inspection of Nuclear Power Plant Components." =b
~~ASME Boiler and Pressure Vessel Code, Section V, 1974 (2)~~
~~Edition, with Addenda through Su=mer 1975, " Nondestructive [ Examination."~~
~~= 'j (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) .~~
~~2. 0 RESPONSIBILITY s~~
[ (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible T 3 for the preparation, review, approval, and control of this 7 procedure. (2) The !!anager of the Nuclear Field Services Section, Department of 4- Engineering Services, shall be responsible for the implementation a of this procedure in accordance with the NQAP!! specified in the applicable SwRI Project Plan. g = 3 SwRt Form QA.31
SOUTHWEST RESEARCH INSTITUTE %"U"%-?~2 March 1978 Q NUCLEAR PROJECTS
~~/Sg '~~
~~OPERATING PROC 5 DURE Page 2 of 6 a .y .~~
~~, -k (3) The examiner shall be responsiDie for implementing the require-i ments of this procedure.~~
m, (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 REQUIREFENTS g The following is a guide to the requirements for this procedure. U R-quirements
^
~~Section 2 N k[ (1) Personnel certification 5.0 g (2) Equipment 5.0~~
~~% Surface condition and cleaning~~
~~( 1-(3) requirements 6.0 ka d 4 (4) Examination method 6.0 (5) Lighting requirements 6.0 s o .nh~~
] (6) Resolution 6.0 (7) Examination areas 7.0 5.0 PERSONNEL AND EQUIP 5ENT l ' . 5.1 Personnel Certification 2
d Personnel performing examinations shall be certified in gaccordance with SwRI NQAP 11-1, "Special Process Control." w i 7 5.2 Equipment c V The Visual Examination Acceptability Test Card shall be made from Kodak Neutral Test Card No. R-27 or an equivalent, with an 18% neutral 5 j t grey side having a 1/32-inch wide black line down the center. i 5 hk 6 , 3 SwRl Form QA 3-1 i l l
l SOUTHWEST RESEARCH INSTITUTE S$2N - March 1978
~~. , , NUCLEAR PROJECTS R. OPERATING PROCEDURE~~
~~A .~~
~~Commercially available equipment shall be used as required for the per-i % formance of examinations by the techniques described in Paragraphs 6.2~~
~~% and 6.3. %a 6.0 EXAMINATION METHOD kQ j %- 6.1 Surface Cleaning N~~
~~5 Visual examinations which require clean surfaces or decontamina-~~
} N' tion for valid interpretation of results shall be preceded by appropriate eaning processes. . M Examinations may be required where the surface is painted or has j other types of coatings. This shall be permitted if it is determined that
~~[A' such coatings do not interfere with valid interpretation of results. Y 6.2 Direct Visual Techniaue~~
, Direct visual examination shall be performed by placing the eye within 24 inches and at an angle no less than 30 degrees with the surface to be examined.- Fiirrors may be used to improve the angle of vision, and aids 2 such as magnifying lenses may also be used.
~~N- 6.2.1 Lighting l N In addition to the general lighting, illumination of the area to be examined shall be provided at right angles and oblique angles to expose~~
~~, , cracks or evidence of corrosion or erosion.~~
~~s j 6.2.2 Resolution i 3 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 surface to be examined.
6.3 Remote Visual Techniaue Remote visual examination may be used when conditions exist that do not permit direct visual examination. Remote visual examination rny g , include visual aids such as telescopes, periscopes, borescopes, fiber optics, 5 Y
~~!4 ^~~
G y swr $ Form QA 31 O
SOUTHWEST RESEARCH INSTITUTE ["';5?-2 March 1978 O Nr NUCLEAR PROJECTS
' --.. OPERATING PROCEDURE " Page 4 of 6 l2 fJ or TV cameras and monitoring systems, with or without attachments for perma- ' nent recording. Remote techniques shall demonstrate the ability to provide ;'
o a resolution at least equivalent to that obtainable by direct visual examina-tion. Mirrors, movable lights or rotating optics, or any combination thereof, may be employed to display cracks, surface scratches, or evidence of corro-
~~! Y sion, erosion, misalignment, or movement.~~
y!k 6.3.1 Resolution a ' Resolution shall be considered adequate when the combination { N 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 or in a situation similar to the area to be i visually examined. * ?~~
S 6.4 Replication g % Surface replication techniques shall be considered acceptable o provided the surface resolution is at least equivalent to that obtainable by
? . the direct visual technique, s, ( 7.0 EXAMINATION AREAS N Section XI of the ASME Boiler and Pressure Vessel Code requires g visual examination as a part of the inservice examination requirements j Mg in order to provide a report of the general condition of the reactor Q pressure vessel internals. This report shall include such conditions as wear, cracks, corrosion or erosion on the surfaces, or misalignment or j *, movement of the internals.
~~( 3~~
~~; - The areas to be examined shall include major load bearing elements j '~~
~~of the reactor internals which are relied upon to retain the core structure i~~
~i in position, the lateral, vertical, and torsional restraints within the '( g reactor vessel, the locking and bolting devices whose failure could adversely affect the structural integrity of the internals, surfaces that are known *j tolocations be or may onbecome reactor contact internal surfaces during components as operation, and the identified from the critical vibration j
~~b analyses, and the interior of the reactor vessel for evidence of loose parts or foreign material.~~
~~. Components, parts, and method of examination shall be as specified in *' the applicable SwRI Examination Plan.~~
~~5 s SwRI Form Q A 3-1 e~~
~~-2 ) SOUTHWEST RESEARCH INSTITUTE- 2 "l;7 5 1 March 1973 i~~
~~NUCLEAR PROJECTS gj OPERATING PROCEDURE p M M 8.0 RECORDING CRITERIA s 4 o~~
~~$' Visual indications shall be recorded on the "SwRI Visual Examination Record" and reported to the customer.~~
a % be limited The coc:pleted "SwRI Visual Examination Record" shall contain, but not to, the following information: 5 b (1) Identificatis of the examined part and the extent of the { examination, acluding surface preparation, if required. (2) Method and tec.iniques used in the examination. This shall include visual aids, if used. C I 7 (3) Examination results with location and a description of any S indications. h N (4) Name and certification level of personnel performing the o examination.
~~') li ) (5) Time and date of examination.~~
~~s J 9.0 EVALUATION Evaluation of reportable indications shall be the responsibility { g of the customer, or the customer's representative, in accordance with Article C~~
~~/ IWA-3000 of Section XI of the ASME Boiler and Pressure Vessel Code. The -~~
applicable year of the Code and Addenda shall be as specified in Paragraph g 2.1(1) of this procedure. C C 10.0 RECORDS j, The customer shall receive copies of documents generated in accor- , dance with this procedure in the examination report.
~~, s Permanent documents generated in accordance with this procedure shall l 3 ~~~
be stored and retained as a portion of the examination report. The examina- l tion report shall be stored by the Manager of Support Services, Quality l Assurance Systems and Engineering Division, in the Data Storage Facility for the period specified by the contractual agreement with the customer. l I '
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E P t I f I o ! i l l i 1 l l l APPENDIX C CERTIFICATES OF PERSONNEL QUALIFICATIONS O i I

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Change 1 APPENDIX C f CERTIFICATES OF PERSONNEL QUALIFICATIONS Table of Contents Personnel VT Page + Masden, T.E. I C-1 i Reaves, L. C. II C-2 Riggs, M. W. II C-3 1 C-4 Salam, J. B. I Ltd. Shimkus, R. P. III C-5 , Turner, R. L. II C-8 I i 4 k i C-1
,r SOUTHWEST RESEARCH INSTITUTE V) NONDESTRUCTIVE TESTING , STATEMENT OF CERTIFICATION THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, QUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION. CERTIFIES THAT Thomas E. Masden iS QUALIFIED AS LEVEL I IN _ Visual TESTING. IN ACCORO-ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUA LITY ASSURANLa PROCEDUR& NDT-100-2,Rev. 3 wy,CH INCORPORATES THE Gul0ELINES OF THE-. N/A E DITiON OF SN T TC.1 A. CERTIFICATION t.lMITATIONS (IF ANY) SIGNEO. Wayne T. FlaCh /,hf / _ _ M/. MATE OF CERTIFICATION. 0/0/79 DtRFCTOR OF DEPARTMEN P ENGINEER NG SERVICES QUALITY ASSUR ANCE SYSTEMS AND ENGINEERING OlVISION TRAINING EDUCATIONAL HISTORY 1AME) (Y E AR S) ICEGREE) HOURS CLASSROOM 12 HIGH SCHOOL; Kaiserslautern AmerienM(Ced 4 CU f) LABORATORY. Included in ACOITIONAL: Anne Arundel Comm. COII I I No ClaSSrQQl2 MAJOR FIELO OF STUOY Cen- MtMdie9 iM A"7 4 " e* Pi" 7 " e EX AMINATION GR ADE ISCOR ES) (WE!GHT1 EMPLOYMENT HISTORY h GENERAL. 85.30 .33-1/3 SPECIFIC: 90.01 .33-1/3 OATE EMPLOYED $*RI 01/23/77 Div 17 02/14/70 PR ACTICAL: 87.00 .33-1/3 Previous NoT RELAreo: cOMFANvi tvEARS COMPOSITE: 87.44 None prior to SwRI Div. 17
~~' VISUAL ACUITY AND COLOR PERCEPTION TEST CORR. CORR.~~
DATE R EQ. VERIFIED BY OATE R EQ. VERIFIED BY 02/19/70 A Angels M. Graf M 4-02/27/80 A Angela M. Graf /Lt>to d RECERTIFICATION R ECERTI FICATION OATE BASIS SIGN ATUR E BASIS. I-CONTINulNG SATISF ACTORY PERFORMANCE 2-R E E X AMIN ATION REMARASl
~~\ .~~
i Sw As FO R M Q A 114 l C-1 I l
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$1Mdf4NON'DESTRUCTIVEL TESTING- . M Nd(STATEMENTi lO F " CERTIFICATION THE DIRECTOR OF THE CEPARTMENT OF ENGINEERING SERVICES. CUALITY ASSUR ANCE SYSTEMS AND ENGINEERING OlVISION, CERTIFIES THAT larM C. Reaves IS QUALIFIED AS LEVEL TT IN Visual TESTING, IN ACCOR D-ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QUALITY ASSUR ANCE PROCECURE NDT-100-2. Rev. 3 WHiCH INCORPOR ATES THE GulCELINES OF THE N/A gOirios OF SNT-TC 1 A.
CERTIFICATION LIMITATIONS (IF ANY) SIGN ED Wayne T. Flach / // . /// // OATE OF CERTIFICATION: 09/04/79 DIRECTOR OF DEPARTMENT F ENGINEERING SERVICES OUALITY ASSURANCE SYSTEMS AND ENGINEERING OIVISION 4 TRAINING - < *a% :. 4;M J./+ LF.' EDUCATIONAL _ HISTORY - (NAME) (YEARSI 10EGRE9 HOURS
~~24 HiGH SCHOOL. Bass High-CA 5 GRAD CLASSROOM:~~
North Georgia College 2 No LABOR ATORY. Included in A00lTION AL: classroom MAJOR FIELO OF STUOY EhVSiCC EXAMINATION GR ACE 7t. Carson School of Aeronautics - 1 yr. ISCORESI (WEIGHT) FCc?i. h*:-4 la.W EMPLOYMENT HISTORY GE N ER AL; 94.18 33-1/3 SPECIFIC. 92.50 33-1/3 CATE EMPLOYED: S*RI 02/20/78 Olv.,7 02/20/78 PR ACTICAL; 94.50 33-1/3 PREVIOUS NOT RELATEO; . (COMP AN Y) (Y E ARS) COMPOSITE: 93*73 None
~~.T "7. Jr%;; hVISUAL. ACUITY ANDCOLOR PERCEPTION-TEST CORR. CORR.~~
DATE R EQ. VERIFIED BY OATE R EO. VERIFIED BY 01/99/70 A Angela M. Graf d iF (L I 01/08/80 No Angela M. Graf dM J
~~' - a9J :fr44.40%fW$tp LRECERTIFICATIOft ~w L. - -w -~~
~~R EC ERTIFICATION OATE BASIS SIGN ATUR E BASIS- 1-CONTINUING SATISFACTORY PSRFCRMANCE 2-R E EX AMIN ATION REMARej~~
Includes 12 hours level I Visual training. Mr. Reaves is-being Certifi ad directiv from Visual I LTD to Visual II. All training hours and experience. hours have keen met for certification to both Level I and Level II Visual.
~~t Sw A4 FQ R M QA.t 3 4 1 l C-2 i~~
, . . . m ,r. . - m. . . - . ~ .~, . s . -. . . - . - = _ .. . . ..- - %_25 SOUTHWEST 2 RESEARCH ~ INSTITUTE ~ ~
~~G NMEiniffi@ NO'N D ESTRU CTLV E ?.TESTI NG~~
~~- C.Ei3.M... . STATE, MEN,.E.. O E.jC.ERTIFICATIO N - ~ - - , -- .~~
THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES, CUALITY ASSURANCE SYSTEMS AND ENGINEERING CIVISION. CERTIFIES TH AT Mir'hael W. Ri Me tS CUALIFIED AS LEVEL II IN Visual TESTING, IN ACCCRO. ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAR QU A LITY ASSUR ANCE PROCEDURE NDT-100-2,Rev.3 wHiCH INCORPOR ATES THE Gul0ELINES OF THE N/A EDITION OF SNT.TC 1 A. CERTIFICATION LIMITATIONS (IF ANY) A SIGNEo- Wavne T. Flach 4 89
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~~Y* If 0 ATE OF CERT;FICATION. 06/09/76 i / DIRECTOR OF DEPARTME OF ENGINEERING SERVICES QUALITY ASSUR ANCE SYST S AND ENGINEERING OlVISION~~
~~9M'fTRAININGd;Ou'ith I 2ffM'fi@:i-~;'E.~E EDUCATI O NA L H ISTO R Y (N AM E) (YEARS) 10EGR EE)~~
HOURS CLASSROOM: 12 HIGH SCHOOL. Oliver Wendell Holmes (Texas) 4 GRAD LABOR ATOR Y: Included in ACOITION A L: Texas A&M 4 3S classroo13 MAJOR FIELO OF STuoy Electronics EX AMINATION GR ACE ISCOR ES) (WEIGHT) C;0 n -j;42/.6*~L4%YEMPf OYMENT HISTORY-GENERAL: 097.50, .33-1/3 SPECIFIC. 097.50 .33-1/3 cATE EMPLOYEo: S.Al 08/05/74 civ.17 09 /05 /74 PR ACTICA L. 080.80 .33-1/3 PREVIOUS NOT RELATEO: ICOMP ANYI (YEARSp COMPOSITE: 088.60 Nn . ,, an ,. *n qupt
~~' CD2Od',M7.'Eisi VtStJAl'.ACUltrANDLCOLORPERCEPTTON TEST .~~
CORR. CORR. DATE REC. VERIFIED BY DATE R EQ. VERIFIED SY 12/19/78 No Jean M. Drever OdF 8 01/07/80 No Angela M. Graf u ppyg
~~@' iP@%3.TM;3hgQRER.'J6MC RECERTIFICATIO C 2: 9 O'- t*f.', - M i ;L " '~~
~~RECEF.TIFICATION DATE SASIS [ StGNATURE 06/09/79 1 Wayne T. Flach . ..-, >[[d~~
~~, 74 J~~
S ASIS: 1-CONTINUING SATISF ACTORY PERFORMANCE 2-R E EX AMIN A TION Effectivity 0-, REMARKS:l remains unchanged. NOTE- Certification transferred from obsolete form. Sw R t FO R M QA l l-e C-3
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N l37dM.TSTATEMENIs.OEECERTIFICATIONR _ ~ THE DIRECTOR OF THE DEPARTMENT OF ENGINEERING SERVICES. CUALITY ASSURANCE SYSTEMS AND ENGINEERING OlVISION. CERTIFIES THAT 3GUaid 3. Salad IS CUALIFIED 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 INCORPORATES THE GulOELINES OF THE N/A EDITION OF SNT.TC.1 A. CERTIFICATION LIMITATIONS (IF ANY) i SIGNED- Wayne T. Flach t' , d- , N# M OATE .'S CERTIFICATION: 9[7/77 DIRECTOR OF DEPARTME OF ENGINEERING SERVICES QUALITY ASSURANCE SYST MS ANO ENGINEERING OlVISION
~~' ?-' " C'.f. TRAINtNGi "r ' f'I $ 1:S*b.'d.-M;WMC. L EDUCATIO NA L H iSTO R Y 1 -~~
~~(NAME) (YEARS) (CEGREE) HOURS~~
pakistan CLASSROOM: 4 HIG'r4 SCHOOL; St. P ar M etra Miek 4chnn1* 5 run LA BOR ATORY: Included in ADDITIONAL; (1) Univ. ,of Lowe'.1 (Mass.) 4 BS classroom MAJOR FIELO OF STUOdl)l*lectrical Engineerine EXAMINATION GRADE (2) Univ. of Peshawar BS -Math & Physics ISCORESI (WEIGHT) 9 bfl.jM25.e:.'1S-Ji03;v EMPLOYMENT HISTORY : . ;
GENERAL: N/A N/A SPECIFIC: N/A N/A DATE EMPLOYED: SARI 7/18/77 Olv.17 7/18/77 - PR ACTICAl.: N/A N/A PREVIOUS NOT RELATEO: tCOV' ANY ) (YEARS) COMPOSITE: N/A None f.~lM 'SO @. .JyM.."-VISUA LACU1TTANor CO LOR PER CEPTIOlt TEST : - -, CC A R. CORR. DATE R EO. VERIFIED BY DATE R EC. VERIFIED BY 9/21/78 No Belinda V. Richter OF6 7/10/79 No Angela M. Graf 47Vf Tr.*J-'M4Z~J5f@&WM@fi#4RECERTIFICATIOW ~4"8 t4f .WN ' W-" . R ECER TIFICATION DATE BASIS SIGNATURE BASIS.1-CONTINUING SATISF ACTORY PERFORMANCE 2-R E E X AMIN ATION REMA RKS-l NOTE: Certification transferred from obsolete for:1. Effectivity remains anchanged. Sw R $ FQ hM Q A.I t-4 C-4
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SAM A N f oNio. TE M As 76284 January 2,1974 NCNDESTRUCTIVE TESTING QUALIFICATION RECORD This is to certify th tt Mr. Robert P. Shimkus is certified to be Level III in the fields of radiography, liquid penetrant, magnetic particle and visual ins pe ction.
QUALIFICATION STATEMENT _ Mr. Shimkus has many years' experience at a level equivalent to Level II and has been working at a level equivalent to Level III for over 14 years. This certification is based on experience and not on an examination. Signed: M r Dater _ Md /*f7g Allen R. Whiting, Chapan
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~~Technical Operations Committee Level III Ce rtified~~
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~~. E. L,1r6tzenheiser Datey / , ;r.f Directo,r Department of Special Engineering Services San A n t o n e o. =ou tro n, co m eus c u eilvi. v a n a s. An o wa s- =o rou. o.c. */~~
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d O Atta chment to RT, PT, MT, VT Level HI Nondestructive Testing Qualification Record fo r I ROBERT P. SHD.f KUS VISUAL ACUITY AND COLOR PERCEPT!ON TEST
, Date of Test Verified By *LO/12/73 Allen R. Whiting h *9/27/74 Allen R. Whitt n e _ c 7
~~4/17/75 Allen R. Whiting~~
*10/1/76 Belinda V. Presas f[ 4; # *9/8/77 Belinda V. Presas 4 , 4f p *9/18/78 Belinda v. Richter ph p. @t acn er-crive 1-n se s recuired for Nea r vis t en RECERTIFICATTON Date of Recertification Signatu r e */7/?* Allen R. Whiting [
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Attachment to RT. PT . T. VT Level 111 Nondestructive Testing Qualification Record for ROBERT P. ' 5HIMitCS VISUAL ACUITY AND COLOR PERCEPTION T EST l Date of Test Verified Bv
~~09/17/79 Angela M. Graf ? fpr a~~
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~~Corrective lenses required for Near vision I R ECERTIFICATION Date of Recertification Sign a tu r e s~~
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~~.S. T..A. TEM. EN, D. *c.. .E, . .:C. ,E,.R. .TIFICA. TIO N .~~
THE DIRECTCA OF THE DEPARTMENT OF, ENGINEERING SERVICES, QUALITY ASSUR ANCE SYSTEMS AND ENGINEERING DIVIslON, CERTIFIES THAT Russell I.. Tu m e r IS QUALIFIED AS LEVEL II IN Visual TESTING. IN ACCCRD. ANCE WITH THE REQUIREMENTS OF SOUTHWEST RESEARCH INSTITUTE NUCLEAP QUALITY ASSUR ANCE PROCEDUR E NDT-100-2. Rev. 2 WHICH INCORPORATES THE GUl0ELINES OF THE M/A EDITION OF SNT.TC 1 A. CERTIFICATION LIMITATIONS (lF ANY) SIGN ED: Wayne T. Flach
.j. ) // k DATE OF CERTIFICATION 11/10/74 DIRECTOR OF OEPARTM T OF ENGINEERING SERVtCES QUALITY ASSURANCE SYS MS AND ENGINEERING DIVISION I"T.MMTRAINING@fj? ISM @fMWW.M EDUCATIONAL HISTORY (NAME) (Y E ARS) (CEGREE) p CLASSROOM: 12 HiGH SCHOOu Roosevelt H . S - (Tera d 4 cvAn LABOR ATOR Y: Included in ADDITION AL: San Antonio College M No Cl&SarOOM MAJOR FIELD OF STUDY CeNefal AcMde"iF9 EXAMINATION GRADE (SCOR ES) (WEIGHT) I*.EQUM,MECREEMPr.OYMENT HISTORY GENERAL: 091.00 .33 SPECIFIC: 084.00 .33 CATE EMPLOYED: SARI 05/20/74_ oiv. i7 05 /20/74 PR ACTIC A L 080.00 .33 PREVIOUS NOT RELATE 0: ICOMP ANY) (Y E ARS)
~~COMPOSITE: 084.00 None crior to SwRI~~
~~?@."7/REGSES$Q?gi SUAt'; VIACUITY *AND"C0t.ORPERCEPTIONrTEST '~~
CORR. CORR. DATE R EO. VERIFIED SY DATE R EO. VERIFIED SY 03/20/73 A Jean M. Dreverdirk 02/21/70 na T .m v_ n .y ,4$ffnMr1 02/19/80 Yes Ange).a M. G'raf gM 6'; d Ji~'??X9$S.C%%";. mwd. :El#RECE5T)EiCRII0th;iUAW -M.i.,9/ .1
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~~4 RECERTIFICATION OATE BASIS SIGNATU E 11/30/77 1 m v.,o T - eleck~~
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SwRI Pur-S**e Order No. '39377 'Date B/ 7/77 e, ,.w., ov ., e, .~, n .s certifies the' follo dag with (supplier's Namej respect t , the above purchase order: (1) T5.a: the ar:icles ' delivered under the above SwRI Pu c;use Order Ite= No.}s) .M7 s 7~7Ju/ c:cyly fully with the require =ener specified therein. s V I2, That the above supplier ag ees to' caintain and preserve records of evidence of co=pliance with SwRI require =ents for th se (3) years fron the date of final pay =ent. These records shall include any doc =.::enention required to substantiate state =ents m.'.de on this fors end shall .be '=ade available for review upon request of SwhI or its designated represe .:::ive. Sigted* ,C A-t'. bbV (Culy Author::ed Supplie.' ..epresenta 17e i i TI:le: /4 M d. ~ Dateh .f"/h/~77
~~/ / /. $w2I Fot . QA-36-0 U~~
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O N SCtJTHWEST RESEAT!CH INSTITUTE 9- RECEIVING INSPECTION REPORT N O. CR!TICAL. / CONTROL JCC NO. 39377 sw . PeoaEcf a 17-3300-101-PuncNusE oncEn No. P O. ITEM NO. ITEM DESC3tPTICN , t.CG , 10. NO. , S/N .ETC. QUANT!TT A. KODAK, NEUTRAL GRE,Y CARDS, R k7 10 PACKS B. SVTri QA-FCRM-36-0 ' CF* **JPT:CN CF INSPECTIONL 3 ) PERFORME3 8
.The materiallisted above was vissually inspected by Jolus H. Phillips on August 22 1977, and was -found to be i= cor=pliance with 'the Purchase Order. ,
suwuAay aEs:;t.73 cF ins 7EcncN( s1 i The material was received in good condities from the vendor. Material will now be logged is and will be assigmd a log number,, and will than be issued to the requestor. Above item is considered as Critical.
~~** SwRI QA FCRM CA-36-0 was received on August 2:1 1977.**~~
~~DISPC3! TION CF ITDI INSPECTED 4 The material upon inspecf.on of receipt, will be issued to the Purchase l~~
~~. requestor, i~~
l *OATE SIGNATURr AUGUST 22 1977 l 4 - y . O D-2
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~~I a 4 I a 1 s I p 4 1 t 6 4 APPENDIX E i CUSTOMER NOTIFICATION FORM I .i 4 i i l i. t I 1 4 5 i i 4 I i , I. !9 1-l~~
.
Southwest Research Institute S*riil NR. 000002 ueini, 6 e.J #'n%A c,o' CUSTOMER NOTIFICATION FORM S ,,e p., i, ,;. i
.# Port l- Sw RI Findings Project N2 g g ,, g g g , u, Type of Examinotton NOT Method O UT O PT h*,8, ,,j g,,,
Esamination Dateg 7 ye O PSI SI OMT ORT CET MT q g .,7 7: Comm en ta 4 h **M e tw t e .s Mt u< d if 't_ e 1 e f f T 6kc d.k T fri9>#- fs ae OM * [-c ll m4 n n :- '. 4 . v '." ; *
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[the aA M (*fw-Ecw tu l. tch u3 p r o ' 'a n , i w e b s .*% A l d u',4 = , 4r . 4 Esomanotton Ref erence s J bek I k ord OnS nM 'h # d #3 #. w e *_ M ("t b n U O, Signature of SwRI Representative - Date a W L.rUn l {t ) wj ) A 'f $0 Port II'- Cusf'om er Not i f i ca tion m S. Notificollon Acknowledged by Date Port til- Indication Disposition by Customer Com m e n t s 3 n ,);, .fy,,,, ,, f ,,,,,g! ,jn, , 4), ;nggyl,(n,,,ogff, ,7
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_ j-d 2 m a - d e,,Bn , Signature at Customer Representative [g f Date p p g Port IV Reexamination j Comment s , I Reesomenotion R ef erence Signature Octe ! l CNF Closee (Castoiner Re pres en ta tive Signat ure ) Date j s.a r rous more -cup -e, n ,-s
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