ML20147J314
| ML20147J314 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/21/1987 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20147J296 | List: |
| References | |
| NUDOCS 8803090337 | |
| Download: ML20147J314 (597) | |
Text
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VOLUME V TVA WELDING PROJECT BROWNS FERRY PHASE II REVIEW AND PROGRAM RESULTS TABLE OF CONTENTS i LIST OF ABBREVIATIONS AND ACRONYMS l
1.0 INTRODUCTION
2.0 BECHTEL AUDIT
2.1 INTRODUCTION
2.2
SUMMARY
2.2.1 AUDIT OF THE OFFICE OF. CONSTRUCTION 2.2.2 AUDIT OF THE OFFICE OF NUCLEAR OPERATIONS 2.3 REVIEW AND CONCLUSIONS 2.4 AUDIT WORK PLAN 2.5 AUDIT. REPORT 3.0 APTECH ENGINEERING REPORT
3.1 INTRODUCTION
3.2
SUMMARY
3.3 RECOMMENDATIONS 3.4 APTECH REPORT i 4.0 BROWNS FERRY WELDINC REINSPECTION REPORT
4.1 INTRODUCTION
4.2 SCOPE 4.3 REINSPECTION PERSONNEL, QUALITY ASSURANCE, AND SPEOIAL CRI'lERFA. 4.4 CRITERIA FOR SELECTION OF WELDS TO BE REINS 7ECTED 4.5 REINSPECTION PROCEDURES 4.6 REINSPECTION RESULTS 4.7 CRITERIA FOR EVALUATION OF REINSPECTION DATA 4.7.1 STRUCTURAL 4.7.2 MECKANICAL ' 4.8 ASSESSMENT OF REINSPECTION RESULTS 4.8.1 STRUCTURAL WELDS 4.8.2 MECHANICAL WELDS 1 4.8.3 OVERALL ASSESSMENT AS RELATED TO EMPLO"F5 dehCRkaS i 4.8.4 REINSPECTION OVERVIEW BY DNQA 4.9 ROOT CAUSE EVALUATION AND CORRECTIVE ACTION TABLES 4.1 REINSPECTION
SUMMARY
FOR STRUCTURAL WELDING 4.2 STRUCTURAL WELDING REINSPECTION DATA 4.3 REINSPECTION
SUMMARY
FOR MECHANICAL WELDS 4.4 MECHANICAL PIPING SYSTEMS WELD REINSPECTION DATA ' ATTACliMENTS 4.1 WELDING PROJECT REINSPECTION Pt.AN 4.2 DNE PLAN FOR THE EVALUATION OF REINSPECTION RESUI.TS 4.3 STRUCTURAL INDEPENDENT OVERVIEW j 4.4 MECHANICAL INDEPENDENT OVERVIEW 4.5 GENERAL CONSTRUCTION SPECIFICATION NO. G-28 DNEL - 0046N i 1 11/21/87 l 1 l l
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VOLUME V - TVA WELDING PROJECT BROWNS PERRY PHASE 11
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REVIEW AND PROGRAM RESULTS TABLE OF CONTENTS (Continued) ') APPENDICES 4.1 4.2 DNE'S EVALUATLON OF DISCREPANT CONDITIONS FOR MECHANICAL REINSPECTION 4.3 DNE'S EVALUATLON OF INDICATIONS OUTSIDE WELD ATTRIBUTE LISTING DISCUSSION PIPING WELDS OF PROCEDURE FOR RE-REINSPECTION AND ACCEPTANCE OF EIGHT 5.0 RESPONSE TO NRC EVALUATION OF PHASE I REPORT 6.0 BROWNS FERRY PROGRAM RESULTS 6.1 EVALUATION OF THE PHASE 1 RECOMMENDATION 6.2 EMPLOYEE CONCERNS CONCLUSIONS 6.3 BECHTEL AUDIT CONCLUSIONS 6.4 APTECH REPORT CONCLUSIONS 6.5 REINSPECTION CONCLUSIONS 6.6 RECOMMENDATIONS
6.1 CONCLUSION
S k ATTACHMENTS ( 6.1 r EMPLOYE?. CONCERNS DETAILED EVALUATION OF BN 6.2 EMPLOYEE CONCERNS REASSIGNED TO OTHER AREAS OF RESPONSIBILITY t' < a e DNE1 - 0046N ' 2 10/25/87 \ .
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VOLUME V TVA WELDING ?ROJECT BROWNS FERRY PHASE It REPORT LIST OF ABBREVIATIONS AND ACRONYMS AEC Atomic Energy Commission AISC American Institute of Steel Construction ANSI American National Standards Institute APTECH Aptech Engineering Services. Inc. ASME American Society of Mechanical Engineers ASNT American Society of Nondestructive Testing AWS American Welding Society BECHTEL Bechtel Power Corporation BFEPC6 Browns Ferry Engineering Project-Civil Group 6 BFN Browns Ferry Nuclear Plant CAR Corrective Action Report CATD Correctivo Action Tracking Document . CEBMA2 Civil Engineering Branch-Mechanical Analysis Group 2 CMTR Certified Mill Test Report CWI Certified Welding Inspector DAR Design Analysis Report DBE Design Basis Earthquake DNE Division of Nuclear' Engineering DNQA Division of Nuclear Quality Assurance DWP Detailed Welding Procedure ERT Employee Response Team FSAR Final Safety Analysis Report CE Ceneral Electric KVAC Heating Ventilating, and Air Conditioning ISI Inservice Inspection LER Licensee Event Report MT Magnetic Particle Examination NCIC Nuclear Construction Isrues Group NEBCSM Nuclear Engineering Branch-Codes, Standards, and Materials NDE Nondestructive Examination NO Nuclear Operations NOI Notification of Indication NQAM Nuclear Quality Assurance Manual NRC Nuclear Regulatory Commission NSRS Nuclear Safety Review Staff OC Office of Construction (Now Known as Division of Nuclear Construction, DNC) PI Project Instruction PQR Procedure Qualification Record PSI Preservice Inspection PT Liquid Penetrant Examination QA Quality Asrurance QC Quality Control . QTC Quality Technology Corporation RT Radiographic Examination SMACNA Sheet Metal and Air Conditioning Contractors National Assoc. SSE Safe Shutdown Earthquake i DNE1 - 0046N 10/25/87
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4 YOLUME V TVA WELDING PROJECT BROWNS FERRY PHASE II REPORT ,s LIST OF ABBREVIATIONS AND ACRONYMS (Continued)
,, SQH Sequoyah Nuclear Plant TR Topical Report j TVA Tennessee Valley Authority
, UE&C United Engineers and Constructors USAS United States of America Standards UT Ultrasonic Examination VT Visual Examination VWAC Visual Weld Acceptance Criteria WBN Watts Bar Nuclear Plant WP Welding Project
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I Th2 c:sults of th] rainsp;cticn rcv cled that c high p;recntcso of { the weld joints reinspected meet design requirements. Complete details of the reinspection are contained in Section 4.0 of this report. The reinspection results did not substantiate the specific or non-specific employee concerns with the exception of e BFN-85-019-001. .
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A complete summary of all the reconunendations and the final conclusion statements are contained in Section 6.0 of this report.
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I 2.0 BECHTFL AUDIT ' 2.1 Introduction The independent Bechtel audit of the Bru welding program implementation during construction and operation was conducted t during the period of February 17, 1986 to March 8, 1986. The audit ' l also evaluated the effect of welding related employee concerns on the program. There were four audit team members and an audit team leader. The personnel had specific expertise in the audit areas - assigned as required by the TVA WP Program Description, Volume I, Page 9, Paragraph IV, Part I. Two audit checklists were prepared and utilized by the audit team. The checklists were identified as TVA-02-0C for Office of Construction and TVA-02-NO for Nuclear Operations. The audit checklists were structured with 17 Key Elements and supplemental attributes which were used to conduct the audit. The audit report and copies of the checklists used are included in Section 2.5. I The audits included review of documentation and procedures for i candemly selected welds in portions of several safety related systems. The welds selected from these systems represent a cross-section which allowed access to all applicable weld program procedures and specifications. The welds selected are listed on Sheet 1. Pages 1 and 2 attached to both audit checklists. These ' 1 l welds were used throughout the audit to generate other auditable l items, e.g. , list of welders, list of Mondestructive Examination 4 l (NDE) inspections, list of drawings, welding and heat treatment procedures and materials. These items are shown on Sheets 2 through 7 of the audit checklists. 1 DNE1 - 0390N 10/25/87 4 O
The Bechtel audit confirmed TVA has had a welding program in place during consttvetion and operations that meets licensing m conunitments . Although there were some audit findings and observations, the WP has concluded that none of the findings and observations had an adverse effect on the installed weldsents. 2.2 SupmerY 2.2.1 Audit of the Office of Consttvetion. Audit TVA-02-OC The WP investigation of those elements with audit findings - and observations is detailed below. Key' Element 2 - Adequacy of Design Output Documents In this portion of the audit, three observations were made. Observations 1 and 2 identify two TVA welding documents stating inadequate preheat temperatures. TVA's cosmitment for welding is to be in accordance with American National' Standards Institute (ANSI) B31.1 1967 sdition Sub-paragraph 131.2 "Preheating" which states, "Preheating shall be in accordance with the qualified welding procedure. Recommended preheat temperatures are shown in Table 131." The temperatures stated in Table 131 were to serve as a guide to good practice and the note to the table reinforces the statement in Paragraph 131.2, that welding is to be perforised
- 1. accordance with a qualified procedure. The TVA procedures 2 DNE1 - 0390N 11/13/87 a
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s nstcd in obesrvation:31 and 2 were gunlified in secordance with the referenced Code. Observation 3 - Key organizational TVA unit responsible for control of welding documents was not specified on the welding document. Welding requirements were issued by Engineering as a requirement. The lack of identification of key organizational unit on the welding document had no adverse ' affect on the quality of the installed weldments. Key Element 3 - Initial Welder or Welding operator Qualifications , The audit team's evaluation of the initial welder and welding - operator qualification resulted in two audit findings. Audit Finding AF-01-0C - Lack of a procedure for qualification of welders. Audit Finding AF-02-0C - Control of welding progression for vertical welding. These two audit findings were determined by the audit team to have no impact on weld quality. Key Element 9 - Use of Appropriate Welding Procedures { During the audit of welding and heat treatment procedures, 1 i 1 one audit finding was issued: 3 DUE1 - 0390M 11/6/87
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Audit finding AF-03-0C - The appilcable revision of the welding procedure used was not always available in the s q permanent plant records for all items. Since the audit team determined that the correct proceduces were used, the failure to maintain on site the applicabin revisions had no effect on weld quality. Key Element 10 - Use of Appropriate Inspection Procedures The audit of appropriate inspection procedures resulted in two audit observations:
' Observation 1 - A review of radiographic film taken during construction indicates that in some cases the "Manufacturer's
, Name" was not evident on the film as r*1uired by American - . Society of Mechs;iical Engineers ( ASME) III. The audit team determined that this had no adverse effect on weld quality. Observation 2 - Some records did not identify the specific procedures which were used. I The WP has determined that failure to list the inspection 1 procedure used had no adverse affect on the quality of the installed weldments. ) i l 4 DEE1 - 0390W 10/25/87 I
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Ksy Element 12 - Uro and Conteci of Welding Fillce Metals , Audit Finding AF-04-0C - Six Certified Material Test Reports (CMTRs) for welding filler material did not comply with TVA requirements. The WP investigation of the six discrepancies concluded these discrepancies had no impact on weld quality. 2.2.2 Audit of the Office of Nuclear Operations - Audit - TVA-02-WO - The WP investigation of the audit findings and observations is detkiled below and refers to the applicable "Key Element" of the audit: Key Element 2 - Adequacy of Design output Documents In this portion of the audit, one observation was made. Observation - The TVA Detailed Welding Procedure (DWP) and the Procedure Qualification Records (PQts) did not show the name of the key TVA organization unit responsible and accountable for welding control documents. Welding requirements were issued by Engineering as a requirement. The lack of identification of key l organizational unit on the welding document had no adverse effect on the quality of the installed weldments. 5 DNE1 - 0390N i 11/21/87 .r e
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I . Key Element 11 - Us3 of Approprictoly TrOined and Qualificd Personnel - . l The audit team's investigation of the use of appropriately trained and qualified personnel resulted in the isruance of one audit finding: Audit finding - AF-01-WO - The requirements of Nuclear Quality Assurance Manual (NQA' A ) Part II, Section 5.3, paragraph 3.1, requires inspections to be performed by , qualified individuals other than those who performed or directly supervised the activity being inspected. Standard Practice Procedure BF-6.2, paragraph 5,31, states in part "the Quality control (QC) inspector shall perform fit up inspection and so indicate acceptance by his signature on the , s
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weld data sheet". Contrary to these requirements, fitup -/ inspections of American Welding society (AW5) D1.1 structural welds on safety related equipment is being performed by the welding foreman who is responsible for the work performed and not a QC inspector. In addition an apparent conflict exists between the Standard Practice Procedure BF-6.2 dated l l November 27, 1985 and N73M2 Process Specification 0.C.1.1 l dated March 9, 1983, which allows the use of weld foreman for l fitup inspection. 1 As stated in the Bru Phase I Report (Volume IV section , 1 3.5.1.4), the WP has determined this ist,.e is not a deficiency at BrN. 6 DNE1 - 0390N 11/6/87 g 44 - A
ly , l K:y Element 12 - Us3 cnd Cantrol of Welding Filler Metcis
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>. The audit of the use and control of welding filler materials
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..l4 observation - The site's controlling procedures for use and f.j control of welding materials are unnecessarily long and l -n Lj
- confusing. Too many procedures are required to be used
., sirmaltaneously to do the job of controlling weld filler ,l material. .
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1 The WP detemined that this had no adverse effect on weld i
.: quality.
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'} LY Four audit findings and five observations resulted from the cudit of 4; -
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;f the OC activities at BFN. Each of these has been evaluated by the WP and detemined to have no adverse effect on weld quality.
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'i The audit confimed that QA was in ef fect at BFN from the beginning
- of construction. The audit also confimed that TVA's program and
.h ,.! procedures for control of welding, although cumbersome, proved ' t, ,-r!.
adequate for the intended application. The audit team was unable to
-l ; .,e substantiate any of the employee concerns as being valid or with M-merit.
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}e t One audit . finding and two observations resulted from the audit of Y
- b the Office of Nuclear Operations activities at BFN. Each'of these T ;
$ i 'd has been evaluated by the WP and determined to have no adverse ! .-?J..
effect on weld quality. The audit of the NO confirmed that TVA had d, in place an adequate Quality Assurance program for control of f h;.'!' holding activities during the operational phase. The audit team was F'
*i unable to substantiate any of the employee concerns as being valid o
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s 2.4 Bechtel Audit Report Audit Work Plan
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UP(ITE TES COVERNMENT Memorandum TENNESSEE VALLEY .' HORITY o : Richard F. Lynskey, LF 4N 89A-Z 860225T0723 / FROM : J. V. Conn, Project knager, Velding Project, W C135 C-K DATE February 14, 1986
SUBJECT:
BROWNS FIR 1T NUCLEAR FLANT - VILDIMC PROJgCT IMFLEMENTATION AUDIT FLAN TEis is to request you to perform a Quality Assurance (QA) review of the Browns Ferry Audit Plan. The independent audit plan will be prepared by Tony Yuksan, Audit Team Leader, and you are to review it against the Ceneral Work Flan, prepared by the Velding Project.
- The audit plan should be ready for review Thursday or Friday, (2/20, 2/21).
Please plan on being at the BFM site by Thursday noon and staying until the review is completed and the plan signed. In adsition, please review the Sequoyah Audit Flau, prepared by Tony Yukaan, Audit Team Leader (copy attached). and forward your comments to me.
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Attachment cc (Attachment): I D!S , SL 26 C-K E. C. Beasley, W12 134 C-K J. A. Crittenden, LP 4N 1045-C
- 1. C. Doner, DZFN, V12 16 C-K i L. E. Martin, LF 63 40A-C 1
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l ,j , E ' B27 '8602 24 - 001 I,/0 ' TO: J.W.Coan, Welding Project Manager i/: s ' FRCH: A.M.Vuksan, Audit Team Leader 860310R0528 DATE: 2/21/36 , SUBJkCT: Browns Ferry Audit ) s , Transmitted with this memo are the nu. fit plan and the key date schedula. ( N
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asu- l $, J///A A.M.Yuksan date l l 1 2/2h/86 JJWC:MP cc (Attachment): R. G. Domer, DEPN, W12 A6 C-K L. E. Martin, Watts Bar, NUC PR J. F. Weinhold W12 535 C-K H . B. Kelly .g LP kN k SA-C N. R. Beaslet . A10-BFN xc: RIMS, SL 26 C-K 1 s s 4 e n, S O (
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- Audit P1nn f r Browns Ferry Prest Plant l l
This audit plan describes the activities to take place at Browns Ferry Nuclear ' Power Plant. These activities shall fulfill the scope of the audit of the I I This audit shall verify, welding elements of the quality assurance progran. by examination of objective evidence, compliance with the welding aspects I of the quality assurance program, shall determine the effectiveness of the I welding aspects of the quality assurance program and shall address the site specific and generic employee concerns belisved to be significant (by the auditors but not as defined in CEP-17) to the proper implementation of the welding elements of the quality assurance program. The quality assurance program for the Office of Construction is outlined in Attachment A. The quality assurance program for the Office of Nuclear Operations is outlined in Attachment B. The audit team will report findings and observations on the quality assurance program based en the review of objective evidence selected
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- by the team and provided by TVA. These findings and observations will be documented in a written report and presented to the TVA Welding Project Manager. The minimum information to be reviewed to provide adequate confi-dence in' the Construction and Nuclear Operation programs will be as follows:
No. of Items Program Examined Organization 1
- Office of Nuclear Operations Str. Steel 6 supports Office of Nuclear Operations Pipe Supports 1 3
Office of Nuclear Operations Piping 6 equipment , Str. Steel 6 supports 2 Office of Construction 2 Office of Construction Pipe Supports 8 Office of Construction Piping 6 equipment These items are in excess of the generic audit plan used by Bechtel for welding and NDE prograas on construction sites. Itent are defined as a specific item on a specific system. For instance, one weld joint on a ' l I system or component. This ites will be reviewed Flexibility for tie adequacy or tne wa. incor-key elements listed in Table 1, as applicable. , i porated into the audit plan to increase samplings at the iiscretion of the audit team. Items for audit and evaluation were selected by the audit l team and are listed in Table 2. The evaluation items will be e'r.panded by the audit checklists to include many hundreds of Tecords. 4 a l l l
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[-[ A review of all the site specific andigansrkc ccncerns provided by TVA to the audit team relating to weldini was p:/ forme.i. The concerns were 4 j deemed significant or not tignificant barc-f on evaluation of technical validity and applicability to the we' ding or t., gram. All the specific 3 i and gee.eric employee concerns provided by TVA and reviewed by the audit team are listed in Table 3 as either significant or not significaat. The con::rns listed as significant will be evaluated for the adequacy ' of the program by incorporation into the mdiz checklists as elenent- i for evaluation. 1 , y1,
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- 4. M. Nuksan i iudit Team Leader l s ,
Approved By* N. )/ I!2/!8d / HP CA Rtmni Coan ggg g fg '. elding Project Manager
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Tablo 1 (*' i Key Ele:ents 1, Implemengation of technical and welding program requirements
- 2. Adequacy of design output documents
- 3. Initial welder or welding operator qualifications
- 4. Maintenance of welder or welding operator qualifications
- 5. Renewal of welder or welding operator qualifications
- 6. Initial welding inspection personnel qualifications
- 7. Maintenance of welding inspection personnel qualifications
- 8. Renewal of welding inspection personnel qualifications
- 9. Use of appropriate welding procedures
- 10. Use of appropriate inspection procedures j
- 11. Use of appropriately trained and qualified personnel !
- 12. Use and control of welding filler materials )
- 13. Inprocess control of welding j
- 14. Documentation of the above activities s
- 15. Nonconformances and corrective actions
- 16. Training programs adequacy 17, Additional areas of concern as determined by a review of employee 1 concerns as specified in Table 3 I
I The technical or engineering adequacy of the design output documents ' is not to be researched; their adequacy is to be checked in the sense of completeness of information for the organization or individual who must use the document to continue forward with the program. s 4
Note: e items 1 - 12 for Office - of Const ruct ion checklist. Use i tems 13 -- 19 for Items for Inspect ion Office of Nuclear Operations checklist. OFFICE OF CONSTRUCTION TABI.E 2 PIPING ltem Ident i fi ca t ion Drawing No. System tini t Class No. of weld GR-1-60 Cil-M-1081-C rev. 6 Recirculation 1 TVA Class A
- 1. ANSI B31.1 CI, OI-M-2139-C rev. 1 Recirculation 3 TVA Class A
- 2. GR-3-46 ANSI B31.1 Cl.
DRWC-1-61 CliM-1098-C rev. 2 Reactor Core Isolation 1 TVA Class B 3. Cooling (RCIC) ANSI B31.1 Cl> RCRD-2-43 CIIM-2073-C rev. 3 Control rod drive 2 TVA Class B 4. ANSI B31.1 Cl TRCIC-2-2 ODf-2073-C rev. 3 RCIC 2 TVA Class B S.
- ANSI B31.1 Cl ORilR-2-8 CliM-2070-C rev. 1 Residual lleat 2 TVA Class B 6.
sheet 1 Removal ANSI B31.1 Cl TilPCI-1-157 CIBI-1099-C rev. 2 liigh Pressure Coolant 1 TVA Class B
- 7. ANSI B31.1 CD Injection (llPCI)
TilPCI-3-73A CitM-2145-C rev. I !!PCI 3 TVA Class B
- 8. ANSI B31.1 CD
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PIPli ilANGliRS
- 9. 11-103 47W455-II-2 rev. A IIPCI 1 N/A
.f, 10. R-13 47W456-1 rev. C RCIC restraint 2 N/A Wq .
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- STRtlCTilRAL SilPPORTS
- 11. Square No. AS 45N816-3 Cable tray support 3 N/A 12 Squarc No. 6A 45N888-1 - Cable tray support 3 N/A
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{'p,h\, Itcas Chascn .O' pecticn , OFFICE OF NilCIIAM OPERATIONS TABI.E 2 (Continued) PIPING AND EQUIPMENT (MODIFIED) pg.z:j Item Identification Of Weld Drawing No. System lini t Workplan No. Clas D No.
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Mt#A-166738 TVA Class
- 13. GR-1-61 OI-M-1081-C rev. 6 Recirculation piping 1 that was overlaid ANSI B31.1 r -1 >
48W 1260-1 rev. 2 Hatches added to 2 WP8 6769 N/A
'...9 14. K (R-1)
U' 's i pressure vessel in
' torus modification
?.}kt: 15. Ray 8 7 48W 1257-1 rev. 5 Piping torus modification 3 WP8 13048 N/A
, g? for sleeves
'l Hark 2 pp>Mj Penetration
{}g.f L pf X-221-1 jfsy . X-221-2 X-221-3
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T PIPE IIANGERS (MODIFIED) w.
.4 Th ' i,d 16 Git-2-56 OI-M-2068C rev. 3 Recirc. pipe hanger 2 MR8A-190669 N/A
.N", f, I (112 support) moved during lilSI
*/. Support No. 47B455-55 ,
Pipe hangers from 3 WP8 13076 N/A 11 - 5 2 - 1 torus :nodification R-52-2 to IIPCI R-52-3 R-52-4 i STRUCTURAL SUPPORT (MODIFIED)
- 18. 9-3-G25 46W414-2 rev. 3 Non-piping structural I WP8 10305 N/A Section F4-F4 ;
wire mesh part'ition rev. 1 I 19. 1-10-Z-R-I 48W1248-1 rev. 9 X4Y Russets 1 WP8 10268 N/A st ructural support re om a orus mn.Ii ric':it ion s .
l TABLE 3
/ CONCERNS
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XX-85-049-X03, XX-85-101-006 XX-85-013-001 XX-85-041-001 XX-85-108-002 WI-85-053-004, XX-85-068-006 J' XX-85-086-003 XX-85-088-001 XX-85-102-004 l IN-85-346-003 J IN-85-007-001 IN-85-134-002 IN-85-406-003 1N-85-007-00.2 IN-85-406-002 WI-85-041-008 IN-85-438-001 . WI-85-041-006 WI-85-013-003 SQM-5-001-002 XX-85-086-004 BFM-5-001-002 BFM-5-001-001 IN-85-405-001
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ATTAQ94E.YT A FLOW CHART OF BROWNS FERRY QUALITY ASSURANCE PROGRAM OFFICE OF CONSTRUCTION r . i SAR , Engineeringe---] f---> Construction m n e RR U bd 3 E- EE . b* kb u a
$5 $$ $k an p___-- q _g _a. _ _ q _-__q p _From SAR OEDC 8
From SAR I I From SAR i l l . APP. D I l APP. D l , QAM l App. D l l L______J L__-__J L__-- J EP's -
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i BF QC BF Const OEDC Handbook QAM QAM 18 G-29 Dwgs l 1 BF Implementing Procedures ! I 1
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Welding Program SAR - Safety Analysis Report OEDC-QAM - Office of Eng. Design 6 Construction QA Manual EN DES-EP's - Eng. Design - Engineering Procedures C Construction of piping systems to boiling water reactor nuclear power plants. . G General Construction Specification for welding, heat treatment, nondestructive . . . . examination, and allied field fabrication operations. l
. l BF QC Handbook - Browns Ferry Quality Control Handbook .
BF Const QA Manual - Browns Ferry Constmetion QA Manual ' BF Procedures - Browns Ferry Procedures NOTE: Flow chart provided by WA. . s 8 - , .I , O y o S 2% ; .,.
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ATTAQ9ENT B FLOW CHART OF BROWNS FERRY QUALITY ASSUR.WCE PROGRAM
.- jr- 0FFICE OF NUCLEAR OPERATIONS 3
(( . SAR TR75-1 NQMI , I G-23 N73M2 N80E3 Drawings
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( . Power Implementing Procedures i Welding Program l SAR - Safety Analysis Report j TR75 Topical Report N73M2 - Process specs for welding, heat treatment, and allied field operations , N80E3 - Nondestructive examination procedures , NQAM - Nuclear Quality Assurance Manual C Construction of p. ping systems for boiling water reactor j nuclear power plants. ! l
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.7TE: Flow chart provided by TVA. ,
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BROWNS FERRY AUDIT SCHEDULE WELDING PROGRAM Orientation, review of employee concerns February 18, 1986: and analysis using key elements. Audit Plan and Checklist development. February 18 through 21, 1986: Begin audit of Office of Construction
' February 22 through March 3, 1986: ,
All checklist elements will be evaluated by audit and documented in accordance with audit plan. Begin audit of Office of Nuclear Operaticr.s. March 4 through 11, 1986: ' All checklist elements will be evaluated by ' audit and documented in accordance with audit plan. Cevelop and write Audit Report. March 12 through 18, 1986: Exit Meeting. Siarch 19, 1986: l I d)#Wdd i J/N/4
' Date A. M. Vuksan l
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I ) I 1 2.5 Bechtel Audit Report a I
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5, B27 '860311 001 . TO : J. W. Cosa, Welding Project Manager ( rum : A. m. vaks. , Awit T.en t..d.e D421 ; Earak 8, 1944 35533CT: IEP0E! 0F BBCETIL QUALITY AUDIT OF 380655 FIRE! NOCLEAR PLANT
, MLDIES PROSIAE5 The sedit tsaa from Bechtel Power Corporation ladependently conducted a formal quality aedit of the Broues Ferry Esclear Flaat's welding programs daring the weeks of Febesary 17th, 24th, and Earek 3rd, 1984. Esthed and scope of the audit were la sceerdasse with the Audit Flaa fee Breums Ferry Baclear Flaat dated February 19, 1984.
The fouowing report details the sedit team activities and identifies endit findiass and ebeervattens of the Brouss Ferry helaar Flaat Quality Assurasco Programs as applied to welding activities. The endit addressed the welding programs as implemented during seastrosties of the Seemas Ferry helaar Flaat and the carrest programs (=p1-ted by Ben'. ear Operations. Ttse audit checklists were utilised by the endit team and are identified as TVA 02-0C fee Office of Constructica and TTA 02-30 for h*1ame Operations, respectively. Copies of the checklists are attaahed se.a part of this repect. (\ _ .
'Andit teen members were assigned specific key elements of the chec uist by the sedit teen leader based on the area of technical expertise held by -
the aeditor. Crees shocking isas done threaghest the sedit between ' meditors and their checklist assiss"Ch .s well as at daily summary sad review meetings seedested by the n40
- 4 leadec.
Reployee cesseras, Broues Ferry s u t h and TTA genocie, were analysed by the sadit team as detailed in the audit plaa and incorporated late cheetlists T7A 02-0C and ITA 02-50 as key element number 17.0 for both checklists. . Fee regeet consistency with the audit sheek11sts, key elemsat summaries, findings and observattens identified for Bromas Ferry Office of Constructies. (checklist TTA 02-0C) form Part A et this report. Key elemoet summaries, findings and observations identified fee Declear operations (chosuist TfA 02-30) feen Part 3 of this repect. Fee tsaatities of semplings and spesifie docummets reviewed by the enditors, reference to the applicable choe utet should be ande. Audit findings and observatises are identified to a key eleesst of the applicable chec uist. 4
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4 i c'j " 1i ., J. W. Cosa * '- March 8, 1986 , 1.. , IIP 0tf 0F BECITIL QUALITT AUDIT OF BROWRS FIREY NUCLEAR PLANT VELDING , b,
- 1 4-d AUDIT SUu8Ae?-FnmIBGS m 0ASIIYATIONS
'A N For Offlee of Construction, there were four findings deemmented for key I;) elements 3.0, 9.0 and 12.0. There were five observatteas decanested foe koy elements 2.0 and 10.0.
91 a li For Nuclear Operation, there was one finding documented for key element 3 11.0. There were two observations dee m ented for key elements 2.0 and 6 12.0. i
*I r' The sedit fosed that prior to July 1972 soms of the appropriate , ,; }
- documentation for geslity assurance was not available but a memorandom from G. I Kimmons (Eaaager of Eas. Design and Construction) to J. P.
Kaight (QA Essager) dated Earth 26, 1973 states: M
- Field constructies work en Browns Ferry units 1 and 2 was j bossa la septamber 1966. The seestreeties permit was 1sesed by
% ABC for saits 1 and 2 es Bay 10, 1967; and fee amit 3 ea I % . July 31, 1968. Subsequently, many ABC rossistions, guides, and y directives have been pressigated, applicable to naclear plaats ;
Y sader constreetion, as well as these belas planned. Ia l parties 1ar, Appendix 5 to 10CFRSO (the 18 criteria os quality l' assersace) became effective se July 27, 1970, oc almost fear dl3 years after grosed was brokes se the Browns Ferry project. ) q 3 The ehreeslogy of events, especially with reference te quality ) 4 assurance, has placed Browns Ferry is sa awkward sitssties. 3 Appropriate documentation for tsality assarames matters, now y rogstred for new ==elaae plaat starts, is simply set available y fee the bulk of design, procurement, and constreetion ' a activities. While retroactive compliance with the 18 eriteria 3 is set possible, various steps have been takaa to implement
.J these requirensets. For saample, a Coastematies % Esamal for ;
41 Browns Ferry, dated July 24, 1970, was prepared and isseed, making extensive use of a formee docummet. Breums Ferry Quality g] centrol Eaadbook. Fee design and procurement, as feenal QA 1 assual has been prepared specific. ally for trowes Ferry. TyA's 3 semitment with respost te % is aestaland la Ammadanet 31 te
,;j the Brewas Ferry PSAE; TyA agreed that effective July 1, 1972 all subsequest desha, pescarenset, fabriestica, constructica, L.}
P and maintenance of safety related components weald ceafecu to 10CF350, Appendir J. See attached memoraadse dated June 20, . 1972, from J. 1. #strisk to These listed. *3eewas Ferry n=1*ae Flaat - Quality Assursace F:rogram.' wenich states 'AEC has agreed that Browns Ferry was too far advanced at tias of u issuance of 10CFRSO, Appeedix 3, to apply the regulaties to all j aspects of the plaat, but ASC insists and we have agreed that j all future design, preeseenest, fabrication, cos truction, and asistossace anst eenform to 10CT150, Appeedix 5.* ? k Q k
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. J. W. Cosa Earth 8, 1986 IIPORT OF BBCETIL AUDIT OF BIDW S FIRE! NCLIAR PLANT WELDINC PROGRANS CENDAL 08SIITATICES
- 1. QUAlnITT ASSUEARCI DURING C053TRUCTION A
Attachanat A of the sedit plaa refers to Appendix D of the SAR. The Flaal Safety Analysis Report (FSAR) Appeedix D for Browns Ferry (Rev. 3) states that the "original QA program for design and construction was described la Appendix D of the Prolialsary Safety Analysis Report (PSAE)." l The sedit teen was unable to obtain this document daring the audit. It seems that this statement in Rev. 3 of the FSAR is incorrect. There was no PSAR but a Design Analysis Esport (DAR). According to the Compliance Section at RFEP the DAR did not have sa Appendiz D. The audit tsaa realizes that the DAX/PSAR have been revised over the years. Efforts to establish that Brouas Ferry committed to and what document this statement refers to were massecessful and shonld be resolved by TTA daring their analysis of this aedit. Appendix D et the FSAR (rev. 3) also diseasses the program being la the Topical Report (TR 75-1). It is net. Althonsh there is program informaties for other TTA anclear power plaats, the Browns Ferry program during design and construction is not included. Boat of the construction for Units 1 & 2 was done betwees May 1967 (Construction Permit Isaned) and Jaly 1972 (ITA's commitarat that subsequest work weald comply with 10CFE50 Appendiz 8). All the welds selected for sadit and most of the critical piping welds were made la the ties frees of 1949 to.1971. The audit team was amable to tie the lower tiered documents listed on the QA program flowsheet (Attachment A of the audit plan) for the Office of Constrsetion to appendix D of the FSAR (rev. 3). In summary, the entire section (D.1, page D.0-1) describing the QA program at Browns Ferry "Quality Assarance During Design and Construction" in the FSAR (rev. 3) appears to be lacotteet la that the first doenment referred to seems to be nonexistaat and the second decament referred te does set cover Browns Ferry daring design and construction.
- 2. F10CIDURES TTA procedure BF-79 for the control of acaconformances and corrective-actions daring the construction phase carries many revision dates leading to contastoa of th control system for identifying proper revision levels.
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EXPolt! 0F BACHTEI. AUDIT OF Btt7tWS FE22y NIiCLEAR H. ANT WEIDING PROGRA33 ..
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- 3. EtMitC05C3853 Wloyee concerns were incocporated and addressed in Toy Element 17.0 of both sudit chechli:tc.
There t.re no audit findings or obs e ations reported which would substantiate the esployee concerns, mur't#SIONS AND RICONNEEDATIONS Office of Construction Activities
- 1. Welding procedures and welder qualification requirenats for piping welding at Browns Ferry between 1966 and 1970 was controlled by a TTA document intended,for use at all TyA facilities.
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- 2. Be structaral welder qualification procedures were la effect betuses 1964 and 1970. The audit did not find evidence of naqualified welders during this time.
- 3. Is.1970 a more complete welding procedure naamal was issued which s seems to have selved many of the problems associated with the older j controlling document.
- 4. Weld inspections, primarily nondestructive examinations were done using controlled NDE procedurst which complied with the applicable codes referenced in the controlling documents.
- 5. The audit team was unable to substantista ar.y of the employee concerns that were incorporated into the audit checklist as being valid or with serit.
- 6. Quality assurance was in effect at Browns Ferry freet the beginalag of construction. During the first four years of construction, mesy AEC regulations were issued relatias to the quality assurance prostaa of nuclear plaats specifLeally abeat documentation. ,
tetroactive compliance to 10Cyt50, Appendix 5 was not possible nor required by the AEC. Ty1 committed that as of July 1. 1972 they would comply with 10Cy150, Aprendiz B fer all subsequest dssign. procurement, Lbrication, con;,cruction 6ad maintenance d safety related components. The audit concluded that prior to July 1972 there were gaps in documentation of the welding aspects of the quality program but af ter that date the audit concluded that there was compliance with TyA's quality program with the exception of one audit finding and two observations. e
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. J. W. Casa Earth 8, 1986 s IIPORT OF B8GTEL AUDIT OF BROW 8 FRIET NUCIA4R PtMT WELDIEG PROGRANS Buclear Oserstions l'
, 1. The Euclear Qaality Assursace Raasal (3Q45) in use at Browns Ferry was foemd to be well writtes with adequate program guidelines and criteria for control of Buelear Operations quality activities as related to weldias.
- 2. TTA has adequate procedures in place goverains welder qualification and costimaity. The sedit indicates that TTA welders are qualified with TTA p. a P Ns as required.
- 3. Inay of the referenced implementing procedures were found to be excessively long, ambiguous, and do not give clear and concise lastructions to persoav l to perform their activity.
- 4. The audit team was amable to substantiate any of the employee caecerns that were incorporated into the audit checklist as being valid or with serit.
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'A. R. Yuksaa Bechtel Audit Team Leader
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A. N. Yuksaa Audit Teen Leader
- 3. 1. Garreffa Auditor W. B. Keyser Auditor S. W. Boreastein Auditor G. R. Henke Auditoe 31rnature Initials hYh!O+] $7?bf
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c l i GlEZACT3 WBO ASSISTED TIE AUDIT TEAR h Ilug, TfA DESARIZATION Jeha Beese Welding Engineer NO Lee Embert S Evaluator 0C Borsae Beckaer Staff Engineer OE Craig Turnbow Staff Engineer OE Jerry Pettitt EedifIcations NO Otto Wilkinson Bechanical Engineer OC - Jeha T. Walker Quality Engineer OC-Larry Farvia QA Supervisor 50 Barbara Lilas Records Clerk NO Barbara M asaha= tesords Officer 30 George Clark @ Easiseer 30
- 5. Morris Compliance NO Terrell Cardes Codes & Standards Supv. NO Earl Strother Engineerias Aide NO Tice Goodson ISI Engineer NO Marshall Leaksaa Rochanical Easineer NO Larry Jones QA Supervisor 50 Jerry Beasley QC Shift Supervisor NO Larry Clardy Surveillance Section Supervisor NO Fred Jefferses. QC Shift Supervisor NO Charles E11 edge Q& Evaluator NO Walt Joest Esta11setical Engineer OE 1
Richard Lynskay QA Supervisor NO I Bob Jesse Eaterial Codes and Standards OE 7
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- AUDIT ASSIGERINIS h Audit Check List Item - (ter Elements)
A. E. Teksas 11.0 14.0 15.0 17.0
- 6. E. Beata 6.0 7.0 8.0 10.0 11.0 16.0
- 3. W. Beresstein 12.0 17.0 S. E. Garreffa 3.0 4.0 5.0 W. 3. Keyser 2.0 9.0 13.0
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t y , EIT EIJDCfT No,1.0 . OFFICE OF CONSTRUCTION : PREPARATION FOR AUDIT OF VILDING A m y m ES l Prior to the start of the audit, the audit team developed an audit plaa and identified applicable documents, specific manuals, specifications and , l procedures which described and implemented the TTA welding activities. W ne audit tesa developed an audit checklist to address all elements '*. identified in the ITA work plan in additiop to analysis of employee 4 1' i concerns for significance and integration into the checklist. . M ne audit team identified and selected a cross section of welded systems from applicable T7A specifications. Welds were selected in a randoca , manner from drawings applicable to each individual system for ;", programmatic audit. - 7 O EIT ILEMENT 2.0 0FFIC3 0F CONSTRUCTION ADEQUACT OF DESIGN OUTPUT DOCUEENTS For items selected for the audit, drawings, welding procedsres and supporting records were reviewed and showed. compliance with the TTA ,$p welding program and procedures. Howevee, there were 3 observations. g .
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.y n eee observations were noted during the audit of the welding output 1ff '
documents.
%D One welding document stated inadequate preheat temperatures for some conditions and did not comply with ANSI B31.1. De document was titled 5f "Qualified Welding Procedures and Welding Specifications For Field %
Welding of Principal Piping Low Pressure and Service Piping Steen 7' Turbines, and Boiler Connections " dated March 1. '1965. The inadequate f preheat temperatures were given on page 8, items 4 and 5. p For the second observation Detailed Welding Procedere (DWF) SN 48-8-1, '{C' Ravision 1 dated 2/28/75 randomly selected from G29 "General Construction Specification for Welding Best Treatnest, Beedestructive i t Examination, and Allied Field Fabrication Operations " specified a 4 l ainlaus preheat of 250F, but the ANSI B31.1 code required a minimee , preheat of 300F. ne third observation was with regard to the detailed welding procedures g and the procedure qualification records, nere was no name of the key - organizational group within TVA that was responsible and accountable for . ,;; the welding control documents on the welding control documents. 4 yz
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KET ELEMENT 3.0 0FFICE CONSTRUCTION INITIAL WELDER OR WELDING OPERATOR QUALIFICATIONS AUDIT FINDING-AF-01-0C Between 1968 and 1970 there were no welder qualification procedures in place governing work outside the scope of "Qualified Weldiag Procedures And Welding Specifications For Fleid Welding Of Principal Piping, Low Pressure And Service Piping. Steam Turbines, And Boiler Connections" dated March 1, 1965. The absence of procedures for this time period violates Part 1 (8) and Part II (A) paragraph (4) of the Browns Ferry Nuclear Plant Construction Quality Control Handbook dated 11-1-68 which required the use of welding procedures for all welding. ' i Review of 134 welder qualification records indicates that welders were qualified in accordance with AWS D1.0 or ASME II. Therefore this finding ! has no impact on weld quality. i AUDIT FINDING-AF-02-OC Between 1967 and 1970 sany welder qualification records do not specify or reference procedures which specify progression for vertical welding. 0 Untraceable progression violates Q-22, paragraph W-3 of. "Qualified Welding Procedures And Welding Speelfications For Field Welding Of Principal Piping, Low Pressure And Service Piping. Steam Turbines, And i Boiler Connections" dated March 1, 1965. Seventeen out of 38 welders and 25 out of 134 welder qualification records audited are applicable to this finding. This problem was corrected when TVA replaced the above referenced document with the G-29 "General Construction Specification for Welding, Heat Treatment, Nondestructive Examination, and Allied Field Fabrication Operation." progression. The G-29 has welder qualification procedures which specify This document transition took place between 1970 and 1972. qualification in eliminated Since ASME II 1974, progression as an essential variable for welder no impact on weld quality. untraceable progression between 1967 and 1970 has KET ELEMENT 4.0 0FFICE OF CONSTRUCTION KAIRTENANCE OF WELDER OR WELDING OPERATOR QUALIFICATIONS Retention TVA's Brownsof Ferry welder QAqualification program. continuity records was not required per auditable. Therefore this key element was not l 1 s
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, KEY ELEMENT 5.0 a -.
H OFFICE OF CONSTRUCTION
.d RENEVAL OF VELDER OR WELDING OPERATOR QUALIFICATIONS
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Retention of welder qualification continuity records was not required per
.),-; TVA's Browns Ferry QA program. Therefore this key element was not J
auditable.
*YA l =Q \l KEY ELEMENT 6.0 h 0FFICE OF CONSTRUCTION
- INITIAL WELDING INSPECTION PERSONNEL QUALIFICATION Qualification / Certification records for nondestructive examination '
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personnel (weld inspection) were reviewed for compilance with the appitcable TVA procedure (s) that were in effect from November 1970 i through December 1975. l I The certification of nondestructive testing personnel complied with the
! j TVA personnel qualification requirements of SNT-TC-1A (American Society
;g ,, of Nondestructive-Testing). I l
i 1 The personnel certification procedure (program) did not become mandatory ! until 1 June 1972 per BFNP Construction Procedure BF 27 (Revision 1). J
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There is evidence that the qualification / certification program was being laplemented prior to the mandatory starting period. l .
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i i EET ELEMENT 7.0 r 0FFICE OF CONSTRUCTION Y, MAINTENANCE OF VELDING INSPECTION PERSONNEL QUALIFICATION - Review of inspection personnel qualification records for completeness and 4 recortification confirmed compliance with TVA procedures used for l qualification certification of NDE personnel. Racertification of 9 inspection personnel was accomplished as required by applicable L:i procedures. In many instances recertification of personnel was accomplished on a more frequent schedule than required by TVA procedures or the ladustry standard (SNT-TC-1A). J
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EIT rr ruruf 8.0 OFFICI 0F 032hswuCE : j erneuar- or WELDING IE5Fik.uCE Pt:WhsL 00ALIFICATION Reesmal of all welding inspection personnel goalifications selected for sedit indleated compliance with referenced TTA programs and procedures. ) EIT seruruf 9.0
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OFFICE OF CONSTRUCTION USE OF APPROPRTAPI VELDIEG PROCEDURES Detailed welding procedures and quellficatiot records applicable to the audit items were reviewed. Postweld heat treatment escords were audited and showed compliance with the TTA program and procedure. ' AUDIT FIIDIES AF-03-0C Based spes the requirement given la the G-27 specification dated 12/12/68 that velding procedures shall be kept permanently, there was one audit flading regarding the welding precedures for audit iten 1. 2. 3. 5, 7 and 8. wereThenotapplicable available.revisions of the welding procedures for these items EIT rrevumT 10.0 0FFICI 0F CONSTRUCTION USE OF AFrauP87 ATE IISPECTION PEOCauURIS For itans used. selected for audit, appropriate inspection procedures were and referenced codes and standards. Procedure review showed complian OSSEIT&TIONS Two observations were noted during the audit for use of appropriate procedates. 1 The review of radiographic film taken during construction, indicated 3 of i the 5 welds reviewed did not meet the requirements of ASME III (Summer 1947 addenda) 5-424 Paragraph 624.7 (a) that requires the "Manufacturers Name"; this element film unidentifiable to of its identification origin. was missing therefore leaving the This condition would have ao safety impact on the effected welds as the-radiographic report that was filled out at the time of laterpretation and review identified the four alments required by ASME See III paragraph N-624.7 information. (a) and is signed (or initialed) to attest to this required
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Records that woro required to be mado and kept did n2t meet tho requirements of G28 Appendix C, T1, Par gesph 4.1 which requires "inspection procedure identification." Some records do not identify t.he .s specific inspection procedures which were used. Tour examples are as ' follows: (a) T7A BFIP tadiographie Record (TTA 10047), (b) T7A BFRP Quality Assurance Records - Piping Systees - Welding Inspection Data, (c) T7A BFNP Quality Assurance Records - Piping Systems - Weld Inspection Data (BF45 Rev. 3 Attachment 1), (d) TTA Quality Assurance Records s BFNP - Nechanical Equipment - Weld Data. ! l IIY ELEMENT 11.0 0FFICE OF CONSTRUCTION I USE OF APPROPRIATELT TWA MED AND QUALIFIED PERSONNEL l I Training records of personnel were only retained or tequired to be ' ' retained by the T7A procedures until completion of the construction preoperational test phase. I IIT ELEMENT 12,0 - 1 OFFICE OF h avCTION l USE AND CONTROL OF VELDDG FILLER METALS I
) l AUDIl FINDDG AF-04-OC Six certified material test reports (CETR's) for welding filler material did not comply with T71 requirements. Details on each package are identified in Attachment A.
On six CITE's, details that indleated that the test reports met the contract esquirsaents were omitted from the test reports.For example, a CITE does not give any test temperature of impact testing required to be
-20F by the contract. This does not indleste that TYA specifications were followed and the impset on quality can not be determined.
Some of the six CITR's omitted information that wu more significant from a quality standpoint. Two CRTR's do not give information that impact testing was performed as required by contract. The system for determining if impact tested asterial was required frost a design standpoint was determined by the engineering design group (EN-DES). No system by system list as to impact requirements was available to the audit team. The EN-DES group put the laqHet requirements for base materials on the bill of materials for the piping components and completed a spread sheet which gave the information about the joint, such as welding procedure to be used. s
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.3 The fracture toughness requirements that T7A committed to foe Units 1 & 2 7: (f'; are states:
very vague. The GE Design Specification 22 A1406 on'this topic ..i "The possibility of brittle fracture in ferritic steel piping and "", equipment pressure parts... shall be considered." Reconstructing the
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- requirements and documentation of the eriginal asterials and procedures is difficult.
The audit team recommeads that T7A review the system q' requirements and establish fracture toughness requirements by system for % all future work (modifications, repair or replacement) on Units 1 and 2 as sa integral part of establishing the current design basis for the $ plaat. 9.I i. KEY st.rmnrr 13.0 -) . 0FFICE OF CONSI1tUCTION I IN PROCESS CONTROL OF WILDING ' V The improcess control procedures for welding were identified for the s
, items that were selected for the audit. T7A docume9ts that controlled !
i welding activities and operation checklists were reviewed. The esview ' f, results showed the construction work was accomplished in accordance with the T7A welding program and procedures. l
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IIT ut.rmnrf NO.14.0 1
,e ~ s OFFICE OF CONSTEUCTION DOCUMENTATION OF TECHNICAL AND QUALITY ACTIVITIES
[ Is general, the documentation of technical and quality activities was adequate through except as noted. Refer to Eey Element 2.0 through 13.0 and 15.0 17.0. M EET ELEMENT 15.0
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OFFICE OF CONSTRUCTION BONCONFormaMCIS AND CORRECTIVE ACTIONS W l [ Eeview of nonconformance and corrective action reports for completion and
,' closure confirmed compliance with the IVA program and procedural
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requirements for this activity. I q, IIT IT3NtwT 16.0 OFFICE OF CONSTRUCTION TRAINING ptOGRANS
- l Training programs developed foe the construction phase were reviewed for
- ~n compliance to the IVA program requirteents.
i certification, records of training were maintained only throughFor personnel not r
.j completion training procedure of the construction BF-110. preoperational test phase as required in y
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Fot' training programs requiring certifications, refer to Key Element 11.0 of this report for details. . 3, KEY ELERIFf 17.0 0FTICE OF CONSTRUCTION EMPLOYEI CONCEIES 17.1 Concerns No. II-85-049-ID3 and II-85-069-006 regard wider certification. The concerns w ee not substantiated by the audit of a random sampling of 38 welders which involved 134 welder qualification records 'from 1967 to 1975. 17.2 Concern No. II-85-108-002 is regarding weld inspections. This c'oncern could not be substantiated as evidenced by audit of inspection procedures and weld history records. , 17.3 Concern No. WI-85-053-004 and II-85-68-004 regard wid rod control satisfying code requirements. These concerns were not substantiated by audit of a sampling of 25 CETR's which involved 11 types of weld metal covering the years 1970 to 1975. Asdit finding, AF-04-CC against Key Eleasat Be. 12 of this report is documented against the TTA progree and involves weld rod control not satisfying contract requirements. l
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&aditor Audit Check List Items - (E47 Elements)
A. M. Yukaan 11.0 14.0 15.0 17.0 l l G. R. Reake 6.0 7.0 8.0 10.0 11.0 16.0 b S. W. Boreastela 12.0 S. R. Garreffa 3.0 1.0 5.0 , W. 8. Keyser 2.0 9.0 13.0 i e l 1 i 6 l l t i
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ETL EttHENT NO. 1.0 i l NUCLEAR OPERATIONS F.Egit)TJON FOR AUDIT OF WILDING AvnnnES Prior to the start of the audit, the audit team developed an audit plan i and identified applicable docuseets, specific manuals, specifications and procedans wkleh describe and implement TyA wlding activities. The audit taan, developed an audit checklist to address all elements ideetified in the T7A w:rt plan in addition to analysis of employee concerns for significance ar.d integration into the cheetlist. Tae audit toes identified and selected a cross section of welded systems based on availability. Only systems which had been modified, repaired or ' replaced under the Nuclear Operations program were selected for audit. Welds were selected in a random manner feca work plans applicable to systems selected for programmatic audit. ggy rf m ut 2,0 NUCLIAI OPrvATIONS ADE00ACY OF DESIGN OUTPUT 00wanad For items selected for the audit, drawints, welding procedures and supporting progrsa andrecords procedures. were reviewed and showed compliance wich the TVA OBSIIVATION One observation documents. was noted durint the audit 'of the welding output The TTA Detailed Valding Proceduces (DWP) and the Procedure l Qualification group. Records did not show the name of the key organizational By showing the name of the key tait that is responsible and accountable for the welding control dtzcaments, any ipestions concerning the welding doemonats could be sore rudily resolved. i I g 1T2EINT NO._3;,0,, i NUCIJAR OPJtAlTONS_ M AL VELDER OR WILDIBG OPERATOR QUALIFICATIONS Based on an audit of welder qualification records and supporting documentation and procedures. TV4 weldees are qualified in accordance with T7A progenas 4
, .5.__ .e __ , e,.
s - , ERY EL T gfT 30. 4.0_ 19"LEAIL0PERAH_0ER , HAINTENANCE OF WELDEI 08 VILDING 0,P,g&IQR QUALIH C&TI0tt$ ' Based on an audit of welder contisutty records. T7A widers demonstrated welding within certification expiration dates as required by TTA programs
, and procedures. -
EIY nm"Y NO. 5.0 30 CLEAR.OP_BATIJNS ' REGWAL OF WELDER 08 WE!JIN CPERATot QUALIUCATIO?4. Based on an audit of welder qualification records and coatinuity re:oeds, ' T7A welders are requalified in accordance with T7A programs and
. procedures, .
e '; I E .[i G R _6,0
~
n!k:LaaR_onsluous INITIAL WELDIM TN3ptCTION 78f30NNEL QUALIMC&TTOR All inspector gus11tication records (IDE. includias; visual exanimation) audited indicated compliance with TTA programs and procedurws and the ' referenced codes and standards. 2 1 ELERINT 7.0 A E&I_9,PERATIONS P' Mg,@ OF VELDING INSPECTION l j H Etq E % QUALIFICATIONS i i i All welding inspection personnot qualification records audited were in compliance with TYA programs azi priocedures and the refereseed codes and I standards. J l 9
s EIT ELIIINT 8.0 ( 50 CLEAR OptIATIONS ewusunt. OF VILDIEG IISPECTION Pii50masL QUAf7FICATIONS For all records of perseasel audited, renewal of welding inspectica porocanal gas 11tications were la compliance with TTA programs and precedares. EILILEEEE.14 ugCLEAR optIATIONS
, g3 OF APptDretatt wr13IEG PE- - 3eni Use of weldias procedures and heat treatias procedures were audited .
against the reforeseed Baclear Operations documsats and found to be in compliacce.
. .I EUCLEAR OpIIATICWB 33I 0F APptDFeratt in*PECTICE rW; 9f*
/
( For all items audited, the use of appropelate inspecties procedures was ver*.fied as complying *with TTA program and procedsres. ! III ELIIINT 11.0 H EE g.,0pIIATIOE8 33 or eravetv Tuarwen aan nnat ryten p_c- -. All audited receeds of certified perseasel indicated that appropriata trainias had been administered and qualifications were la accordanes with TTA programs and procedsres for perseasel trained and qualified lacluding eye ===imations. Astaal copies of writtaa amanisations were es file. AseIT FtunIns-AF-01-up A) ESE part II Sec. 5.3 dated 7/30/84 paragraph 3.1 stotes in part *QC Inspostica shall be performed by qualified ladividuals other than these l d e perfeemed er directly esporvised the sativity belag laspected." i' B) Standard ?ractica procedure 8F-4.2 dated Nov. 27, 1943 paragesph 5.3.1 states la part "the QC inspector shall perform fit up laspections and se indicate acceptance by his sigastare on the weld data eheet." Centrary'te A & 3 above, fitsp inspecties of AM D1.1 structural welds sa (, safety related ogstguest is being perferned bF the welding foreman who is respeasthis ter the work performed and set a QC inspector. Furthermore a ceaflict 27, 1985exists between the Standart! practica procedure 5F-4.2 dated Bev. t and from 573E2
- process specifications of welding, heat t treatment sad allied f1 eld operatioas* proce.s Specif testion 0.C.1.1.
dated 3/9/83 which allows the use of weld foremas for fitsp inspecties. 1 .
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- IIT ILIIINT 12.0 j
- x NUCt.IAI 0Ft14TIONS ;
USI AND CONIEDL OF WILDING FILLER IITALS i ORSIIYATICE . I The site's controlling procedures for use and conteel of welding - materials are unnecessarily long and confusing. Too many ptocedures are , required to be used simmitaneously to de the job et controlling weld l filler material. This puts the program and the perseasel trying to esforce the program in a vulnerable position. The program could be condessed and simplified to be more fanational and less vulnerable to error and misinterpretation by the users. Extract 1oas are for example "Receipt Inspecties' Standard Practice 8F 16.4
'2.5.2 As part of the receipt inspection of QA level I items, Level II 10CF121 ites. Level II substitated items, and og ,
original ordered items with Quality Assurance requirements or 10CTI21 applicability, the QC inspector shall review and verify asaufacturing documentation and material certifications of physical properties as listed below. The eristastor of the part.hase request or his representative shall assist the receipt taspector la verifiestica of eartifications and documentation se % Intel II substituted items, and will assist when requested by the receipt laspecter em QA Level I Assurance requirement or 10CFI21 applicability.
- a. -Assursace that the itan received ;
was fabricated, tested, and taspoeted prior to shipment in accordance with appliaable code, specification, and/or drawings as required by the procurement documents.
- b. Physical Properties-Assurance that physical peeporties ceaform to the specified requirements and that chemical and physical test reports,'if required, meet the procurement document requirements.
Unidentified items and'itans withest the required quality assurance documents shall be handled as aeaconforming material la aseerdanes with refersees 2. I i Level I Level II substitate items, Intel II 10CF121 required items, and 08 eriginal ordered items wite Quality Assersase requiremsats se 10CFE21 applied 111ty, will prior to use, isselag, or belas pleasd inte stock, have verifiestica of proper documentaties by the Flaat M staff superviser.* Receipt Inspection for veld filler metal casset be deae by this procedure alone. Althemgh 2.5.2.b implies that the receiving "Jerk eas necept weld material, 8F 6.2 "Quality Control of Welding Activiti d and 573E2 Process Specification 1.E.3.a are aise accessary before weld f t.11er metal can be accepted. Stsadard Practice SF 6.2 is 82 pages less and difficult to use. It is recomunoded that SF 6.2 be rewrittaa to give cisar directions for the normal flow of welding material (for eaample for recelot at site, to power stores, to red rooms, to issue to welder, to completlea of all. documentation includtag of weld data sheet).
% 9
, . ~--- - ---w--- - - - - - -
Traceability of welding asterial is critically important *.o comply with 10CFE50toAppeediz difflemit implement. 8 and the precedsres is effect at Browal Ferry are la three of the seres items for Euclear Operations.There were CAR's relating to we EE! ELIIINT 13.0
- f. MCLIALQFH m _- m &IIDuf 0, m or Aediting operations.covered the TTA document 5 *. hat coateolled the weldies centrol requirassets of the evfect. aced T7A documents.The audit results c EIT re m wr 30, 14,o .
NUt*** OPERATIONS DCwamarATION OF TEN _=1 CAL AND 00ALITY Asriv1 TIES . i In seeeral, adequate the documentation ezespt as seted. of technical and quality activities was 15.0 through 17.0. Reference Key Elements 2.0 thremsk 13.0 and EIT rrrn wr 30, is,o NtK*** OPttATIO53 isumwarumr e AND COR8: IAVE ACTIONS A review of asaconferinances and corrective action reports for completion and closure confirmed requiremsats for this activity. compliance with TTA program and procedural EIT rr ruwT 16.0 NOr OPreAtross T8Ai=1s0 PROGaAmm _ l Training programs Esference Eey Elementwere No.11.reviewed for compliance to the T7A Program. i t 0 0
NU r.9. s OFFICI 0F NUF8A' OpfeATION3
.' 7.1 Concerns No. II-45-049-ID3 and II-45-069-004 regard welder certification. nose concerns w ee not substantiated by the audit of a random samplias of 47 w iders which involved 132 wider qualification records from 1978 to 1986.
17.2 Concera No. ZZ-45-108-002 is regarding wlding inspections. n is concera could not be substantiated as evidence by an audit of inspection procedures and wold history escords. 17.3 Concerns No. W1-45-053-004 and 11-45-68-006 regard weld rod control sa.isfying code requiremsats. nose conceras were not substantia *e4 by audit of a random sampling of 25 receiving - documents and associated CRIT's which involved 25 heat and/or lot numbers, and 8 different types of weld metal covering the years 1978 to the present. 17.4 Concera No. IL 45-102-004 is regarding inspection and verification of corrective action of notice of indications (301's). He following 11 NOIs were reviewed: n/C4-001 M/C4-39 ' j R/C6-002 U2/C5-062 l R/C4-003 U1/C4-73 ' U1/C6-004 U1/C4-76
- U1/C4-12 U2/C5-135 U2/C5-015 Based on review of the above sample, there was no evidence l found to substantiate the concern that NOI's were nisbandled.
vi: 3": 4 cttatnaent a u. j.ef I . , u- ' se m 0F FIrJapes AND OaSERYATIONS Fog gt.mnuMT 12.0
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" 'f - (as refersaced (C La thestlist) Eaterial Meat Ee. Comments
,j 4 57018 302701
%.1 See Comment 1
.: 8 l* i EE309 7-10279 See Comment 2
.: . - 10 Vi E703-4 00147
. See Comet 4 y.: 11 E403-3 490627 See Comment 3
- g. - 12 E703-3 82E317 See Comment 5 6 31
.; E304-16 610327 See Comment 6
'U .C 1 COREENTS
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's 1.
Q Centract required 1) impact testing and 2) tensile testing la the j as-welded and heat treated condition. CRTE does not give 3 values i
'for impact data as required by contract, nad does not give internaties that heat treated tessile spee.ianas were tested.
2. fj De teeted taforestion to as regaired es CITE as to what standard the inforestion was by contract.
.g
, contract requirements of ASTR A371 II 309.The material does conform to the 3 3. _.
Contract test data.required impact testing. CITE does not give any impact 4' 4. 2', Centract required impact testias and tessile testing. CITE does not
? give any lapaat or tessile test data. -['. S.
Centract required impact testing at -20F. A temperstare of impact testing. CITE does not give test y
- , 6.
tG The receivias report (form 209) was approved with heat no. and j anterial (carbes steel) not matching the CITE that had the same heat { 5 as, bat differest material (stataloss steel). 1 I l
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s c . t QUALITY AUDIT CHECKLIST COVER SHEET m .. m
, , , Welding Project Audit
. ...u., TVA 02-0C
. = e, Browna Fa m . ...n .
- 2-86
. .. 16985 !
Welding Program
. .. , See page 2 n . no.
. .. ... .... .. (OC) Office of Construetion
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- See Attachment A i. n *.. a ""
1 SAR 2 N/A N/A SF Constr. QAM N/A 3 OEDC - QAM July'1970-July 197: [ 4 N/A July 1972-to 11cen.m 4 G-28)6-29 Rev. 0-7/N/A 1968-1982/1965 to l licens.e 800 "O .. MOIO80 0 O'
.... . 9 9. . W . . 9 gggg 0 See page 2 2/20/86 A. M. Yukaan //p 2/21/86 1
Conections to Sheet 1 3/4/86 gg/ 3/4/86 1 1
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A. N. Yuksen Audit Taen I,:.2cor S. R. Gcrecrte. Audit:r
-tf- Keyser Auditor S. Eersastsic Auditor G. 3. Hants Saditor Sinnature Initici:'
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" , Obscr7stica 0 i Audit 71 di:t Cross-chseling by sucitor: 31(at :.t4 by circlou initials in auait neult column.
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1.0 Preparation for Audit of Welding (1) 1.0 Determine and identify' applicable Sheet 1
, Activities (2) documents, the required edition, !
(3) addenda, revision or amendeonts of i (4) specific manuals, specifications, b I standards, and procedures which apply , y/A 1.1 Identification of Governing Docuasats (Manuals, specificaticas, Standards, Procedures). 4 2.0 Randomly select systems and items by drawing review. Seleci; specific welds to be audited. 1.2 Determine what to audit. 4 3.0 The welde'shall be a cross sectica from safety related systems to allow complete access to all applicable wel I $ 9 programs, procedures and specificatto is . Enter selected items on sheet'1. g } . 680 g Aio r anu c A ati 45 ^M AUDs T Ky E CLEnE NT 1 l i 2hML see ses i1 ] i , I
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- 1) 1.0 Sample a minimum of 15 "drawings for See sheet 5 2.0
- 2) adequacy 1.e. where applicable g
- 3) Sec 9 drawing number, revision number, .
45 title, details and weld symbols. 1
.I
- Adequacy of Design Output Docu-uents' 2.0 Sample 10 welding procedures for See sheet 6
'ils e ite.tuscal or angineering 4.dequacy: 1.e. *,elding variables '
a..le.pa a * .a the seea9n output ,
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Jocuse. s. 4 1.s .wc t o ...: c a uc a r cia .sz choir ..:!u.gusey is to be enacted in ' time eenee of completeness of inforas s *..sa for the or<;anization . or tod;**3 duals who .aur.t ese the document to continus forward l uith ti.t. program. ') . O Vority pr6codure .gualification recGrdo. 8 1.0 Ths, c.1,uvt, ca..nples shall includa
' tho drauisags and welding prce.edu ra s. Idantified in ehcet 1.
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Initial welder or welding operator 3.0 . qualifications.
- 2) seo 7.0 1.0 Verify that welders
- ars' qualified
- 4) G-29 in accordance with WA approved -
AfPuca sar 4,sa m go 4 6,,,s 4 rs*J procedures. rneu sos a s : , 4 ** * ' a .u ss os (soua.rass n~e onese**G 8 hes4 r. s r,a ,,,g., , , , , , , , , , ,, , , , , , , , , . . ,
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- 2.0 Esamine a stalaus of 20 initial See sheet 2
. * * 't 0 rea c.e L, su f, welder qualifications. This sample shall include weldere identitled a< e- ~ , . . . . . ,.. "'"'"'*"'*--
I M 1. I foE 4*- AF 6/ ss-as *se I * (- - l i / poss-c / c,-s y-go ( M ol-at.)
# # 8 /Asv- A / s - s's h 3.0 List applicable welder geaaliti-
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- For the purpose of this audit the i Sof a OJe s //4ree, 4.ect es .,p. 4 rs s term welders shall include welders
-TK S roas c, . and welding operators.
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5.0 Renewal of welder or welding 2) sec 7.0 1.0 operator qualifications. Esamine the meistenance"recorde See sheet
- 4) G-29 s
for a minimum of 10 welders to verify renewal. Al/A . Sf( E8td7 J 2.0 List applicable welder qualift- MK 4 cation procedures. , SEE a rse 2.0 SE
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s . 6.0 Initial welding inspection personnel (1) 1.0 Review inspecto'r personnel qualift- See sheet 1 l qualificatione. [2) cation recorde using the welde (3) Sec 9 & eclected for the audit le the Sec 10 aseans for identifying inspectors. DGAM U.xL OMiwssrqATioN Cearts Cic Av.o % *1DT v3 c2 G C*C N OH htr s'T C2.0 C.Tw c a
. 1MSN ON 9GLSot* C- D 4 M ch qualification C..A-4CL-: **
FL% Ti w C,. "NM w aidL 2 DnkA-eview records for c *P11ance with referenced pro-GLv A ti Ct c ters om Awo cedureo.
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C ? N v rea ..; C T t O N 9Q sX. ten v .hd 3.0 Randomly select qualificatton See eheet 3
,) recordo for a minimum of 10
\' T'- bb 8- i additional velding inspection 14 DT 'g M f2 3 ce w M c't Cc:(2.TsCtc4 TIC. l
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7.0 Maintenance of welding inspection 1) 1.0 Review welding inspectiba personnel
, personnel qualification. 2) qualification records for complete-
- 3) Sec 9 ness and re-certificaton compliance ,
to identified procedure. REdmQrt t'FsCATnOM 3T$.T*J3 9fic6JZAM QX2 koMtimtTit2A'Teot 1 , g g, (g a>C NoMbe:.wTwa h-Srtwq gg Sq 3 h .M M =ct CDv AL_s Ct c ATsCMM AMD O t .t2 'r s DCA Tt o1r g , 2.0 As a minimum, review qualification See sheet 3 records on 10 personnel. Ch"2.W' 8 C.WOM hh% Q_c N O__- bb d} N DY h"h OLEfl7'ELCAh , 3.0 List the applicable procedures 4 OJN tCicAm.o% used. Mh C Sc9 T % I J69 TanN i R% :o 19 15 seer 'Documev-a L.rren , AT LeFT i .l 1
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a_ . . . . I, 1.0 Select and identify a minimum of' See sheet 3 g, Renewal of welding inspection (1) 8.0 (2) 10 inspectioa preonnel qualif1- l personnel .gualification. cations. (3) Sec 9
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2.0 Review for renewal of qualift- l cations in accordance with TVA proceaures. Identify controlling procedures and list below. Nma ra_ Aowi.,, :crewrios 09 hoMD m t Q. tac r W45. w7sg fYN pena m w e_ G o,st_wse m os. M a
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9.0 Use of appropriate welding 2) Sec 7 1.0 Ideettfy welding and he'at treatment g j procedures. 3) sec 5 procedures applicable to welds .'
& Sec 9 listed on sheet 1.
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2.8 List welding and heat treatment procedures on sheet 6. 1 - i 3.0 Verify that the welding pro-cedures are applicable to $ referenced weld joints. i 8 1 4.0 Verify that heat treatment pro- - l cedures have been used where applicabl e. $ l
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11.0 Use of appropriately trained and (2) Sec 2 & 4 1.0 Identify prograins and procedures , see sheet 3
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G-27. *ATCo oa.fss/sv - tv -A s sDA TCO s yssjss-pf-11 t SF- vs' de-V7 2.0 saamine a maalaus of 10 operation checklists (travelers) for - M procedure compliance. 3Ec' 3 4 **=' . 3.0 sample shall include welds identi-fled in sheet 1.
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'2.0 & minimum of 20 aca-conformance see sheet 4 reports and related corrective action reports shall be reviewed.
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\l ATTAOHLVT A FIAN CHART OF BROWNS PERRY QUALITY ASSURANCE PROGRAM i 0FFICE OF CW STRUCTION SAR kngineeringe---] f---* Construction
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- From SAR i i From SAR OEDC l ' i i App. 0 l i App. D i l APP. D QAM '
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, CEDC Handbook QAM QAM
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G-28 C-29 Dwgs i \ l 8F Implementing Procedures
'#elding Prograa SAR - Safety Analysis Report OEDC-QAM - Office of Eng. Design 4 Construction QA Manual ,
EN DC3-Ep's - Eng. Design - Engineering Procedures 1 G Construction of piping systems to boiling water reactor nuclest power plants. G General Construction Specification for welding, heat treatment, nondestructive examination, and aliled field fabrication operstions. BF QC Handbook - Browns Ferry Quality Control Handbook BF Const QA Manual - Browns FerTy Construction QA Manual BF Procedures - 3rcrns Ferry Procedures N'OTE : Flow chart provided by TVA. 3
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of Construction checklist. Items for Inspection Use items 13 - 19 for Office of Nuclear Operations OFFICE OF CONSTRUCTION f ' checklist. _
, j Sheet 1 I PIPING .
l 9, ' Item Identification System Unit Class of weld Drawine !!o. TVA Class A No.
^
CII-H-!03f T rew. 6 Recirculation I
- 1. CR-1-60 ANSI B31.1 Class Recirculation 3 TVA Class A GR-3-46 OI-N-2139-C rev. I ANSI S31.1 Class 2.
Jteactor Core Isolation 1 TVA Class B O M-1998-C rev. 2 ANSI B31.1 Class
- 3. DRWC-1-61 j
Cooling (RCIC) Control rod drive 2 TVA Class R RCRD-2-43 OH-2073 -C rev. 3 ANSI B31.1 Class 4. 2 TVA Class 5 ,' RCIC I! shCIC-2-2 O H-2073-C rev. 3 ANSI B31.1 Class 5. ' ~ Residual Heat 2 TVA Class A I DRHR-1-8 O M-2070-C rev. I ANSI B31.1 Class 6 sheet 1 Removal 8 High Pressure Coolant 1 TVA Class S THPCI-1-157 O M-1099-C rev. 2 ANSI B31.1 Class
- 7. Injection (HPCI)
HPCI 3 TVA Class B DIPCI-3-73A O M-2145-C rav. 1 ANSI S31.1 Class 8. PIPE' HANGERS l HFCI 3 N/A g H-103 E7W455-H-2rev.A
- 9. I RCIC restraint ,, 3 N/A R-13 47W456-1 rev. C
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10. STRUCfURAL SIFPORTS Cable tray support 3 N/A
$ sare No. A5 45N816-3 Cable tray support 3 N/A Square No. 6A 45N888-1
- 12.
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WELDER 00ALIFICATIani N., ,. j l'- Date of Are Walder Initial Maintenance Records Renewal Item No. Satisfactorvi Date Audit Status Welders Name Stamp C J r_tification (Note 3) ' (Note 4) (Nota 4) - ', # (Note 1) (Note 2) 4-21-70 N//.. N/A (See Note 5) .i England 6T9 1 Peugh 6869 2-25-71 1 i M/A. N/A b , Guthrle 6TTI 1-16-71 - 1 P/A N//. Brindley 6S7 1-16-71 1 N/A N/A 4' Rhodes 6A3 5-15-72 2 N/A -4/A
'r ;
s Evans 6F3 10-26-70 3 N/A 48 / 6 ~ SFG g,g Young 689 7-21-70 4 N/A N/A (See Note 6) Enunons 603 3-13-08 5 N/A N/A (See Note 7) A 16 Roberts 6G6 4-30-71 6 N/A N/A b ,,c. . .c . Rhodes 6A3 22-69 7 N/A N/AE ' ($se Note 8)
- 3-03-69 _
' ~ Guthrle 6LL3 10-09-70 7 N/A N/A (See Note 9) Hunt 6RR8 3-25-71 8 N/A N/A' $ sgc , ,.r-el Pittman 6CG2 9-14-71 N/A N/A N/A '(Se Wote 10) 7-30-70 6GG3 12-31-71 N/A N/A N/A (See Note 11)
- Cembow '
7-30-70 _ _ . . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ ___ __ _ __ w_
Itcas Chosan for Insptctior./
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OPPICE OP NUCLEAR OPERATIONS Sheet 1 (bntinued) , PIPING AND EQUIPMENT (NODIFIED) - Item Identification System Unit Workplan No. Class Drawing No. No. Of_ Wald Recirculation piping 1 MRfA-166738 TVA Class A
- 13. GR-1-61 Ot-N-1081-C rev. 6 ANSI B31.1 Class that was overlaid Hatches added to 2 WP8 6769 N/A
- 14. K (R-1) 48W 1260-1 rev. 2 pressure vessel in torus modification ,
Piping torus modification 3 WP8 13048 N/A
- 15. Bay 8 7 48W 1257-1 rev. 5 Hark 2 for sleeves Penetration X-221-1 X-221-2 X-221-3 X-221-4 PIPE HANGERS (M00lFIED) 1 Recirc. pipe hanger 2 Mt#A-190669 N/A 16 GR-2-56 OI-M-2068C rev. 4 (112 support) noved during IllSI g
TRil-2(modified weld I.D) 3 WP8 13076 ,N/A Support No. 478455-55 Pipe hangers from
- 17. tonas modification R-52-1 R-52-2 to HPCI R-52-3 R-52-4 STRUCTURAL SUPPORT (MODIFIED)
Non-piping structural I WP8 10305 N/A IS. 9-3-G25 46W414-2 rev. 3 Section F4-F4 wire mesh partition rev. I 48W1248-1 rev. 9 XkYgusscts I WP8 10268 N/A
- 19. 1-10-Z-R-1
**'actural support Rev. I 3/4/86 torus modification g --
P I Sheet 2 Page 2 of 5 WELDER 00ALIFICATIONS
. Date of Are Welder i Initial Malatenance Records Renewal -
Welders Name Stamp Certification Iten No. Satisfactorvi 9111 Audit Status
- (Note 1) (Note 2) (Note 3) (Note 4) (Note 4)
Stinson 6GG1 6-15-11 N/A N/A N/A (See Note 12) 8-31-10 S Foster 66A8 1-06-75 N/A N/A N/A NcGregor 66A9 10-06-75 N/A N/A N/A 1-03-75 Thornton 6681 1-14-75 N/A N/A N/A Henry 6682 2-07-75 N/A N/A N/A Corum 6683 2-27-75 N/A N/A N/A Hargrove 6684 2-28-75 N/A N/A l N/A
' $sGp-EL i Butler 6J3 2-09-70 N/A -
N/A N/A (See Note 13) 6-06-74 , Partain 6J4 11-27-10 N/A N/A N/A (See Note 14) i 9-28-70 Terry 6J5 2-12-11 N/A N/A N/A -b gg ,,, Blevins 102 9-19-70 N/A N/A N/A (See Note 15) 8-27-10 Letson 103 12-23-70 N/A N/A N/A (See Note 16) 4 1 O b
Shast 2 Page 3 of 5 WELDER QUALIFICATIONS Date of Are Welder Initial Maintenance Records Renewal Welow,5 Name Stamp Certification Ites No. Satisfactorv7 Ralt Audit Status (Note 1) (Note 2) (Note 3) (Note 4) (Note 4) IE1 8-11-69 N/A N/A N/A (See Note 17) Nichols 6-08-70 IE4 3-10-72 N/A N/A N/A (See Note 18) Hester 11-25-69 161 3-24-70 N/A N/A N/A (See Note 19) Herritt Hicks 4A1 12-10-70 N/A N/A N/A S g,4 s.s-tu 4A2 6-23-69 N/A N/A N/A (Ses Note 20) Hayes 6-18-69 481 11-26-75 N/A N/A N/A (See Note 21)
, Gordon 9-12-69
- Brickley 485 5-05-72 N/A N/A N/A b 3-24-10 4C9 11-18-75 N/A N/A N/A Quico I 6-17-11 P4yrick 5F2 11-29-68 N/A N/A N/A 6-23-10 N/A 'N/A N/A .
Plunkett 501 Murphy 5-C 6-13-67 N/A N/A N/A Myric 582 7-16-70 N/A N/A N/A sr Wl111ams $81 6-19-70 N/A N/A N/A St6 1-02-68 c. g 4
l Sheet 2 !. Page 4 of 5 (Note 1) The stamp prefix number identifies the craft as follows: 1-8o11er Maker 4-Electrician
- 5-Iron Worker 6-Pipefitter (Note 2) Many widers have multiple qualifications. Tw dates listed indicates tw separate w1 ding processes or separate qualification codes.
(Note 3) Specific wider certifications are not traceable to wid joints for Items 9 thru 12. Items 9 thru 12 do 'not require ' wider traceability. (Note 4) Welder maintenance records wre not retained nor required to be retained per TVA Quality Assurance Manual. Therefore . checklist items 4.0 and 5.0 are not auditable. I (Note 5) The wider qualification record does not specify or reference a procedure d ich specifies progression for vertical wlding. Per qualified wlding procedures and wlding specifications dated March 1,1965 progression is an essential variable for wider qualification. This comment applies to wider qualification records dated: 4-21-70 and 9-8-70. (Note 6) Same comment as Note 5 applicable to wider qualification records dated: 7-21-70, 6-13-67, 9-1-70, and 3-5-70. (Note 7) Same comment as Note 5 applicable to wider qualification records dated: 3-13-68 and 5-16-68. (Note 8) Same comment as Note 5 applicable to wider qualification l records dated: 10-22-69 and 3-3-69. (Note 9) Same comment as Not: 5 applicable to wider qualification record dated: 10-9-70. (Note 10) Same comment as Note 5 applicable to wider qualification record dated: 7-30-70. (Note 11) Same comment as Note 5 applicable to wider qualification record dated: 7-30-70. s es
, 'g
l Sheet 2 Page 5 of 5 O
f 1
(Note 12) Same conument as Note 5 epplicable to wlder qualification records dated: 8-31-70 and 8-28-70. l (Note 13) Same comument as Note 5 applicable to wider qualification records dated: 8-7-70, 2-9-70, 10-9-49, 4-7-49, and 4-2-69. (Note 14) Same comument as Note 5 applicable to wider qualification records dated: 9-28-70 and 4-8-69. (Note 15) Same oaument as Note 5 applicable to wider qualification records dated: 10-31-68, 7-7-70, 10-17-69, 3-19-69, ,
" 68, and 10- 29-68.
(Note 16) Same coaument as Note 5 applicable to wider qualification - record dated: 5-14-69. (Note 17) Same conenent as Note 5 applicable to wlder qualification records datcd: 6-8-70, 3-23-70, 11-6-69 and 8-11-69. (Note 18) Same comment as Note 5 applicable to wlder qualification records dated: 10-9-70, 3-30-70,11-25-49 and 11-24-69. (Note 19) Same comument as Note 5 applicable to wider qualification records dated: 3-23-70,and 3-24-70.
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(Note 20)- Same conssent as Note 5 applicable to wider qualification record dated: ~6-23-69. (Note 21) Same cosument as Note 5 applicable to wider qualification records dated: 10-23-70, 8-4-70, and 10-3-69. Skcs
.)
l Sh ot 3 i INSPECTION PERSONNEL QUALIFICATIONS (Training Records) Inspector Trainian Res, of Trainina Audit Status
% M D. .kracy Eass. 3poe. Leak Toat 105.5/.&999=/9 PI - g J. Usiker Bass. Spee. Leak Test 85.5/1975 C. E11 edge Bass. Spec. Leak Test 90.5/1975
[ E. Nichols Eass. Spec. Leak Test 89.5/1975 T. Cardes Eass. Spee. Leak Test 53.5/1975 i 1
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0FFICI 0F CONSTRUCTION IESPECIOR PERSOlGIRL QUALIFICATI0ES Aadit Insoector Qualification 9111e Status Bailey, Billy R. PT II 26 Feb 72 PT II recortification 23 Feb 73 PT II recortification 22 Feb 74 RT II 25 Ape 72 ET II recortifiestion 10 Apr 73 f IT II recortification 6 Apr 74 Bentley, Norman R. ET III 1 Dec 81 - UT III 22 Dec 81 Boney, Samuel J. Sr. none specified III by appolataent 3 Nov 70 Brown, W. IT II 22 Apr 72 RT II recertification 20 Apr 73 IT II reeertification 8 Eay 74 PT II 10 Ear 71 PT II recortif1 cation 8 Ear 72 - PT II recortification 5 Ear 73 - PT II recortificatiou 8 Eay 74 ; Burch, R. Lloyd PT II 15 Eay 72 : PT II recortifiestion 10 May 73 , PT II recertification 6 Eay 74 Hardy, Edward S. PT II 10 Ear 71 Hasting, Ioanoth A. IT II 5 Feb 72 IT II recortification 5 Feb 73 Thompson, Jack 8. PT II 5 Jan 73 PT II recortification 5 Jun 73 PT II recortification 8 May 74 PT II recertification 8 Ear 75 Self, John W. PT II 15 Apr 72 PT II recortification 11 API 72 IT II 1 Eay 72 Andrews, Geoege E. PT II 26 Feb 72 PT II recortification 23 Feb 73 , PT II recertification 22 Feb 74 RT II 11 Ear 72 QQM ET II escortification 23 Feb 73 RT II recertification 22 Feb 74 % ji i
l l Sheet 3 Page 2 of
- CFFICE OF CONSTRUCTION IMSPECTOR PERS01DIEL QUALIFICATIONS IANDON SAMPLINGS Audit Inspector Qualification -
gitgs Status Byrd, Joka D. PT II 5 Jun 72 PT II recertification 5 Jun 73 PT II recertification 23 May 74 Cole, Justin L. PT II 20 May 72 PT II recortification 11 Ape 73 Berbert, Jobason, L PT II 23 May 72 i PT II recertification 23 May 73 PT II recertification 8 Ray 74 Eing, John W. PT II 4 Jun 73 PT II recortification 8 Jun 73 Linginfelter PT II 5'Jun 72 PT II recertification 5 Jun 73 PT II recortification 6 May 74 UT II .15 Sep 72 UT II recortification 14 Sep 73 UT II recortification 6 Jun 74 IT II recortificttion 15 Jan 74 IT II r, certification 6 Jun 74 Bassey, Robert I. PT II 15 Jan 73 PT II recertification 15 Jan 74 PT II recertification 2 Dec 74 Nee, Isaaeth, C PT II 27 Mar 81 Nichols, Kenneth C PT II 9 Feb 71 PT II racertification 7 Feb 72 PT II recertification 7 Feb 73 PT II recortification 7 Feb 74 PT II recortification 23 May 74 UT II 19 Feb 72 UT II recortification 16 Feb 73 UT II recortification 15 Feb 74 (;zgy UT II racertification 28 May 74 ET II 11 Mar 72 7 P1 Ast 86 9
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Sheet 3 Page 3 of 3 - OFFICE OF CONSTRUCTION IESPECTOR PERSOMMEL QUALIFICATICES BANDOE SAsFLInes Audit Inspector Qualification gg13,e Status Olson, Robert W. PT II 25 Sept 72 Pt II recortification 25 Sept 73 PT II recertification 6 May 74 Wages, Charles W. IT III Appointaant 26 Ear 74 - UT III ET III PT III
. ET III
-- E! III Appointment 10 Jan 75 UT III
, NT III PT III . l ET III ) l RADIOGRAPHIC PERSOMEEL l
Hasting. Kenneth IT II 5 Feb 72 gqq RT reeertification 5 Feb 13 '
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Sheet 4 RETIIW OF NONCONF0EXANCE REPotTS AND CORRICTIVE ACTION l NER 30. Date Corrective Action Audit Status D05-30 12/29/72 12/29/72 jc{ D05-44 4/05/73 4/11/73 D05-110 4/25/73 4/26/73 D05-111 4/2G/73 5/01/73 D05-113 5/04/73 5/24/73 D05-131 5/22/73 6/18/73 DDG-147 6/11/73 6/25/73 i DDG-156 3/17/73 8/28/73 D05-157 8/20/73 9/17/73 D05-161 9/18/73 10/05/73 DDR-201 10/29/74 11/04/74 DD5-203 10/29/74 12/03/74
~
D05-221 10/27/75 11/11/75 DEF-6902-1 2/19/69 2/25/69 DEF-6902-2 2/19/69 2/25/69 DEF-74-2-2 2/74 4/29/74 DEF-7001-2 1/26/70 1/26/70 DEF 7101-19 1/29/71 2/03/71 DEF 7101-21 1/29/71 2/03/71 DEF-N74-4-15 7/09/74 6/27/74 M A S
Sheet 5 0FFICE OF CONSTRUCTION DRAWIEG RETIEW t Drawing No. Rev. System Date Audit Status 47C430 1 Recirculation System Piping, Units 1, 2, & 3 12/28/71 g CH-N1081-C P 6 Weld ID, Recire. Systen 6/05/81 CH-N-2139 1 Weld ID, Rectre. System 9/02/81
/
CH-M-1098-C 3 Wold locations, 7/27/81 ! Reactor Core Isolation Cooling CH-N-2073-C 3 Weld Identification. 7/01/81 Reactor Water Clean-Up & RCIC 47W456 9 Reactor Core - Isolation Cooling Systen 2/06/73 CH-M-2070-C 1 Weld Locations, 3/25/81 Residual Heat Removal (RHR) CH-N-1099-C 2 Weld Identification, 3/21/81 High Pressure Coolant Injection CH-N-2145-C 1 Wold Identification, 7/07/81
.High Pressure Coolant -
Injection (HPCI) { - 3 47W455-H-22 A Rochanical Righ Pressure testored 5/29/75 Coolant Injection 47W456 C Mechaalcal Isactor Core 4/22/85 Idolation Cooling System Issued to Depict as-constructed Endes, Rev. 29 l Bergen-Patterson 3 RCIC Pipe Support 5/31/72 45N830-1 D Cooduit & Grounding, 10/22/85 Cable Trays 45N816-3 5 Conduit & Grounding, 11/15/85 EL. 664.0 Plaa 45N888-1 7 Conduit & Grounding, 11/20/01 Floor Plaa , 1 i
- -- ,i
i Sheet 6 OFFICE OF CONSTRUCTION
, RITIEW OF WILD AND HEAT TRIAIRENT PROCEDURE (
Proce4ste No, Rev. Ee. 2311 Audit Status i GT-SES$-0-1A & PQR 2 8/31/72 b r l i GT-SE11-0-3 & PQt 5 12/19/72 GT-5E11-0-3 & PQt 5 12/19/72 - GT-18-0-1 & PQt 0 12/10/70 ST-GE11-0-2 & PQt 3 12/19/72 GT11-0-1 & PQt 0 12/07/70 W-1811E-1 0 3/01/65
, WB-11112-1 0 3/01/65 x W-4411E-1 0 3/01/65 SE11-8-3 2 1/05/73 Bote 4. E 702I Dus. 455830-1 D 10/22/85 ils-111 11-2 0 3/01/65 Post Wold Best Treatamat of 4 9/12/73 Carbon Steel Pipe, 8F-19 l l
Esat Chart, Unit 1 3/A 4/07/72 ) Best Chart, Unit 3 N/A 11/14/74 if l Qualified Welding Procedures and nieldlas Specifications for Field nielding of Principal l Piping, Low Pressure and Service Pipias, Steam Turbines, and Seiler A r,-* 3-8 3 Connections. 0 3/01/45 o 5544-8-1 & PQt 1 2/28/75 0
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Sheet 7 Page 1 of 3 WELD FILLER NETAL Oi'FICE OF CQusassvCT]OR Ites No. Contract Date Data Audit 1per Shee! Q No Heat No. Lot No, Notorial Received
- Wel494 Status S
N _ 1 1 45130 - ER308 Note 1 3/71 S 2 1 05924 - 5308-16 Note 1 3/71 3 1 29846 E305-16 Note 1 3/71 4 1 29825 - E308-16 Note 1 6/72 ,, 5 2 mone listed - ER308 Note 1 5/71 Note 2 5 6 3 302701 - E7018 Note 1 5/71 Note 3 4 F E70S-3 5/71 (AF-Ov-OL) 7 3.. 09L521 - Note 1 5 8 4 32-79246 7-10279 - ER309 Note 1 4/71 Note 4 Af 9 6 - none listed ER308 Note 1 9/72 Note 2 S 10 7 - 00147 E70S-G Note 1 11/70 Note 6 AF 11 7 - A9D627 M603-3 !Jote 1 12/71 Note 5 AF 12 8 - 82E317 E70S-3 Note 1 12/71 Note 7 A f 13 3 - 07L354 E7018 ilote 1 12/71 .3 14 - 72s32-60480-3 3636 - Iuconel 182 11/72 - j 15 - 73a33-60480-2 58063 - 3R308 6/73 - I 16 - 70C32-83516 625537 - E60S3 's/73 I 72a32-60480-1 641212 - 270S3 12/75
- 'Y 17 -
5td I * ,\th
- storia. . pection report approved. ,
* 'J l .
Sheet 7 i Pag's et 3 WLD FILLER Ngygt OFFICE OF CONSTRUCTION Sd" Ites No. Contract Date Date Audit No. Iper Sheet 1) & Heat No. Lot No. Material Beceived* Welded Status 18 71C32-82044 OF238 Nis 13 E308L-16 4/18/71 3 19 - 71C32-82001 5681 - Inceael 82 3/25/71 - EENICE-3 20 - 71C32-82009 5589 - Incomel 82 2/24/71 - EENICE-3 'i 21 - 71C32-82009 5988D - Incomel 82 2/24/71 - EENICE-3 22 - 71C32-82009 3102 - Inceaal 182 3/22/71 - ENICEFE-3 + 23 - 75E12-70828 AA-1004225 - EE5356 8/75 - 24 - 75C32-79377 26188 4336-22144 E70418 12/74 - 25 - 72C32-54572 48573 8059 RE308 5/15/72 - 26 - 72x32-60480-1 402J9741 3121242 E7018 2/23/73 - 27 - 72x32x6080-1 401M7411 2640132 E7018 8/74 - 28 - 70C32-83516 422C3841 - E7033 11/71 - 29 - 70C32-83516 432C1271 - 57018 10/71 - i 30 - 70C32-83516 30115 - E308-16 10/71 - U 31 70C32-83516 610327 8308-16 10/71 Note 8hf 32 - 70C32-83516 B-20443 - EE309 10/71 - 3 o.te ..t.ci.i to.g.ction c port pprov.4.
nut 7 . l Page 3 of 3 l OFFICE OF CORSTRUCflon BOTES Q
- 1. No receivias reports (forn 709's) available which gives QA documentation of inspection.
- 2. Procedure #BF 45 rev. 3. May 11, 1972 changed requirensets and heat ,.
no's were no longer required on weld history records.
- 3. Contract required 1) lapact testing and 2) tessile testing la the as A.
. welded and heat treated condition. CITE does not give 3 values for impact data as required by contract; CITE also does not give '
information that heat treated tensile specianas were tested. ,
- 4. No information on CITE as to what standard the infonsation was s tested to as required by contract. The asterial does conform to the ,
contract requirements of ASTR A371. El 309. .
- 5. Contract required impact testing. CRTE does not give any impact
- test data.
- 6. Contract required impact testing and tessile testing. CIft does not give any impact or tensile testing. CETE does not give any impact ,
or tensile test data. .'
- 7. Contract required lapact testing at -20F. CNTE does not give test ,
temperature of lapact testing. E' s.
- 8. The receiving report (form 209) was approved with host no. and "'
asterial (carbon steel) not matching the CITE that had the same beat ;> no. but different satorial (stainless steel). N
- - 2 n% '
s t i e s
.M' ._ . . - . . _ - - - . . - - .-. f .' ,
F Sheet 8 i RADIOGRAPHIC REVIEW OFFICE OF CONSTRUCTIDIl Audit Item No. Weld Drawin No. Procedure RT-Dete status Comuments 1 TECIC 2-2 CHN 2073-C Rev. 3 BF 15 23 May 71 E. Maettet RT-II 5 Feb 72 2 DEHR 2-8 CHN 2070-C Rev. 1 BF 15 6 Sept 72 E. EastinE ET-II 5 Feb 72 l 3 GR-1-62 - BF 15 12 Feb 71 Randon 4 TRHR 2-479F - RF 15 - Randam 5 TCS 3-280 - SF 15 - Random BECHTEL NDE LEVEL III q g n Aca 1 ad 4
)
9 e
pft QUALITY AUDIT CHECKLIST COVER SHEET A
,m.a Welding Project Audie
, , , , TVA 02-NO ,
. . . , Browns Ferr7 ,,, 2-86
****=*- 16985
.,,.e.,
Welding Program See page (2)
, , , , , , , , , , (NO) - Nuclear Operations 1
8
- See Attachment B a"'***= " * * "
1 Topical Report (TR 75-1) 8 2 N/A NQAM N/A 3 573M2 license to 11/14/85 4 N/A license to 12/20/85 N80E3 N/A license to 1/12/85
" = n .. ..
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O See page 2 2/23/86 A. M. Vukaan [8 './20/86 1 Corrections to Sheet 1 3/4/86 //yjy[ 3/4/86 see senes - 1 20
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. - . _ - _ ~ . _ . _-.
FDIT T3AD ,-) , A. H. Yuksan Audit Teca Leedse S. 1. Gaeroff s inditor
- --4. Emy s er Auditor S. Berenstein Auditor G. 1. liente Auditoe Sinnature Initials ,
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%9LQ Lestood 3n Satistsetory 0 a observnties af Meilt Ficding Cross-checting by auditors signifis4 37 circlod isitials ic :ndit ::: alt column.
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'N QUALITY AUDIT CHECKLIST - ---
, 10
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. ,,e sammewe emeneeve.. .e es see=ee me,=ee se wesee ge,,p. even esees, 1.0 Preparation for Audit of Welding (1) 1.0 Determine and 1'dentify' applicable Sheet 1
. Activities (2) doc'amente, the required edition, (3) advena , revision or amendments of ar ealtic manuals, specifications,
/h (4)
,Mg g .
standards, and procedures which apply Sue BA-/fL
'1.1 Identification of Governing Document's #24 < 3 )'[#4 (Manuals, Specifications, Standards, Procedures). b 0 SusaNu, 2.0 Randomly select systems and items by drawing review. Select specific welds to be audited.
1.2 Determine what to audit. 3.0 The welds shall be a cross section
, from safety related systems to allow complete access to all applicable wel I ,
programs, procedures and specificatto ss. p Enter selected items on sheet 1. i f- /d A/VVirs$$ AS A& AsU
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(1) Sec 17.0 1.0 Sample a minimum of 15 drawings for See sheet 5 , 2.0 Adequacy of design output documents. adequacy; i.e. where applicable Sec 17.1, Sec 17.2 drawing number, revision number, b (2) Part II, title, details and weld symbols. Sec 3s Sec ti-(3)
*r.dequac, of Design output Documents
- I 2.0 Sample 10 welding procedures for see sheet 6 The tece :! cal or engineering .1dequacys i.e. welding variables ,
adequa. T cine design cutput g i v .in. documenta is not to be tousarcheds their juacy is to be checked in the aus.a of completeness of inform 41on for the organization or indi,lddals who must use the documenc to continue forward with L: 2cogram. 3.0 V4 -if y ps ..ceduca luali f ication p ' r e.c c.r d:s . J 4.0 The above samples shall include thu drawings cond welding procedures idesatified in aiheet 1. 7 I b yes.__ e 9
i l i i 1.* i t . Site
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/,2 QUALITY AUDIT CilECKLIST - - - - - - - -
L84 ' ,. . e. s .. _2L._
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i 3.0 Initial welder or welding operator (1) sec 17.0 1.0 Verify that wel'ders* are qualified. a qualifications. (2) Part II, in accordance with TVA approved { Sec 6 procedures. A PPLit*10L { svELDEA QvAsers c 4 rso d , Psa cg ousag s . G eca e na t. gog6o..;ca 2.0 Examine a minimum of 20 initial f** * 'd o ud t V6 car.< 4 rw s See sheet 2 welder qualifications. This sample
/. M . /. I /x 4 at / -29 g g shall include welders identified per veld number in sheet 1.
O .C. I. ! / uu-o / 3-9-23 I I* C I 2 / Rev-2 / 3-2-g2
/ l. /. / /4so-2 / 37-7.2 3.0 List applicable welder qualift-cation procedures.
WC L Diot Pgarsam,e a gg ava t,,e, gs g ,ea SGC LEFr HAub leLam J l * *' 1 2 /Aco-3 / t -2 g. g S For the purpose of thie audit the
/. C. 2. 2 / R(i/- / / 3, _y2 term welders shall include welders and welding operators.
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1.0 Examine the maintenance records See sheet 2 - Maintenance of welder or welding (1) Sec 17.0 l 4.0 operator oualifications (2) Part II, for a minimum of 20 welders to verify welding within welder ! Sec 6 1 (3) certification expiration dates. 2.0 List applicable welder qualifi- I cation procedurua for review. 4 solsase psuonut6 Qu^s e e a sa fs
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. . e. 7 . 20
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1 S.O Renewal of welder or welding (1) Sec 17.0 1.0 Examine the maihtenance records . See sheet 2
. operator qualifications. (2) Part II, for a minimum of 10 welders to sec 6 verify renewal.
]
I 2.0 List applicable welder qualiti-cation procedures. EnELots Pcsson-Aa G qasLascecArtoJ I. A. 2. 2 / peu-3 / s-a y -s s I.C.1.1 / g;y. ; / 3-y-r3 V>ELbre Qans r.cA rtsd e courinvo ry j Ecc.ov>M M a r1 Aa D tccato 5 DPm HD. rd ']3p 2. N N8 U .* edean~4<E arw4os u SR0 c.e n ran u ., y et a s.<a s **c Svasoa y
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f GUALITY AUDIT CllECKLIST a 20 [pf-w, ,
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e i Initial weiding inspectics* personnel :2) Part II, 1.0 Review inopector person'nel quellfi- See sheet 1 6.0 qualifications. Sec 6.3 cation records using the welds l3) selected for the audit as the seans for identifying inspectors. ! 'T N/A 001 - - if M o c.(_ e w t2. b <:.rt. 41 N# '- N'l 752 A4 H sw G 9 Qct.qam hto N wen '1_Dev-vTtCn @ car s Q s., Att','sc. A'riOw k Cdtry p scat k 2H 2.0
/ %eux- 'h Review qualification records for
-- compliance with referenced pro-orc 44R A M mn. Non esa.s.cnve: ; , ,,,,,,,,
&t AM t N f-Ts aM GGStrs . r .s c *L ..
i bla.44%.> 6a.7. 02O2. M 3.0 Randomly celect lualification ties sheet 3 8 o g 'Ql) 1h ' recorda for a minimum of 10 additional welding inspection personnel and review. both .s . . i s / B {2 M N b y (
- 2. fdtu d84 l
4.0 List procedures used for qualift- . cation of inspectton personnel.
. see tw. t-m u m ,_ .,
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., i m esaae=, . eve.. ..essease .. . ee es..e gover. , eveee me.=se 7.0 Maintenance of welding inspection (2) Part II 1.0 Review welding.4nspectt'on personnel personnel qualification. Sec 6.3 qualification records for completof (3) nesc and re-certificaton compliance (4) to identified procedure.
RG. CEC 2.T. t U\C o.'T a on STATu % oC IMMN=r
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*2.0 As a minimum, review qualification See sheet 3 records on 10 personnel.
u - ,aatw % % % No Al ifs cATicw i CE4Tt Ftc ATtoH PourECtAM Coq MowDnTrtve rWt2 3.0 List the applicable procedures u minATsc>,-,-pn. An.som et_ m,A u..d. Peoce o uruz 02c> 7_ .14 /o\ strea bcc_v en tsscwco 9 % nas om uc, Unne>2 w DPM N 7 5 c_o ) i 2 M a. 13 81 GJ2.H 6maa [igi3,WI?, s s . , soe soooo ,
i i Brown. ....f SI"" TVA-02-NO -
/
QUALITY AllDIT CilECKLIST , n .. ., 10 ,, 20
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(2) Part II 1.0 Select and identify a minimum of' see sheet 3 Renewal of welding inspection 8.0 j Sec 6.0 10 inspect!M personnel qualiti-personnel qualification. . isi cutions. I*I QE ceQCNrtow OTNT03 OI , IWAPECT t Od-. '\h'2.chw m .
\ MWC A'T G c2 u 3 n o t t- 3 I
Review for renewal of qualift- I 2.0 l cations in accordance with TVA procedures. Identify cuatro111ng j procedures and list below.
'W A; OVtsce t%ct_enet. h i NVh TMththC. NMQAM f
' io caue uncuv ow .e con sviccios , [.
EM OR NOMMTC20Crnle e m nis w ri m p ozsc.m e 1 9hv(2e O~2.0 2 14 b was 9 Tem 1 . . kneuy tea a neo g 2 Amt._ t*)S t ORH i I
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f, 9.0 Use of appropriate welding (2) Part II 1.0 Identify welding and heat treatment g proceduroa. Sec 6 procedures applicable to welds (3) listed on sheet 1. ' 4
/
2.0 List welding and heat treatment l procedures on sheet 6. - I-I a i 1 3.0 Verify that the welding pro-cedures are applicable to O referenced weld joints. i i I 4.0 Verify that heat treatment pro-cedures have been used where applicab e. i S
, stuusfocars u i=an porr sags p e44 t* nte.ornsin r , 7.5 2.M . 8- 1, AEv. 4, s/2 vf1i5-Ato stuescox o rex arsa a rms xngar aseo n sr < one wn r 4 qG .
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- - - - :- ,i GUALITY AUDIT CHECKLIST
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*r Ii Identify and review inspection " See sheet 1 (2) **rt U 1.0 10.0 use of appropriate inspection procedure;J used for examination o&
Sec'6'~~. procedures. (J) - . welde identified for audit. O ' j x (4) { .s j - s SU AL i T 'likGmEEEt'.hC=
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N'NI-1 7. dDQ. 198'$ 2.0 Verify that the inspect 1_oa N -\1 T-P_ / h 1 Lu 1982 procedures are applicable to A4 , c.f.renced werd joint.. N -\1T 1 23 A% . N 64 I M T~. gg DC,0 Mg3 MD n.m 3 A u n.w esa m. om test a - uT-m A so % naz g eta'i esa N - o T- L5 h~ o . J s E I
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?.i.? . QUALITY AUDIT CHECKLIST
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11.0 Une of appropriately trained and (2) Part II, 1.0 Identity prograhe and procedures, See sheet 3 h".].
'S.p #
, qua11Csed personnel. .
Sec 5s used for training of personnel. Part III, Using the welds selecteJ for audit, l1.*J-
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l Sec 6 identity a mintaus of 10 personnel ((.6/-A/O 1 l3) training and qua11tication recorde. d .j
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/',..' ,'} 2.0 Review training records for compliance and completeness with 6
- U '.' [,c t ] i governing procedures. M
- 5 3.0 List applicable procedures usgd.
5
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"Q^* . N ? w 2, RF-L 2, dF- 7.f 2.0 Esamine a minimum of 10 operation checklista (ttavetets) for S
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$ EE B flete 3.0 sample shall include welds identi-fled in sheet 1.
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l ATTACINENT B l FLON CHART OF BROWNS FERRY QUALITY ASSURANCE PROGRAM OFFICE OF NUC12AR OPERATICNS 1 1 SAR 1 l TR75-1 4 l l 1 i NQAll 1 . G-28 N80E3 Drawings _N73M2 Power Implementing Procedures i Welding Prograa SAR - Safety Analysis Report TR75 Topical Report N73M2 - Process specs for welding, heat treatment, and allied field operations NMOE3 - Nondestructive examinttien procedures NQAM - Nuclear Quality Assurance Manual G Construction of piping systems for boiling water reactor l nuclear power plants.
ote: Use items 1 - 12 for Offico of Construct ion checklist. items for Inspection Use items 13 - 19 for Office of Nuclear Operations OFFICE OF CONSTRUCTION t checklist. ; St.eet 1 PIPING . i 5 L Identification Item System Unit Class of weld Drawing No._ TVA Class A No. CII-N-1081-C rev. 6 Recirculation 1
- 1. GR-1-60 ANSI B31.1 Class Recirculation 3 TVA Class A
- 2. GR-3-46 Ol-N-2139-C rev. 1 ANSI B31.1 Class Reactor Core Isolation 1 TVA Class B
- 3. DRWC-1-61 O N-1098-C rev. 2 ANSI B31.1 Class I Cooling (RCIC)
Control rod drive 2 TVA Class B l
- 4. RCRD-2-43 O N-2073-C rev. 3 ANSI B31.1 Class I
RCIC 2 TVA Class B Opt-2073-C rev. 3
- 5. TitCIC-2-2 ANSI B31.1 Class 2 TVA Class A I O H-2070-C rev. 1 Residual Heat
- 6. DRilR-2-8 Removal ANSI B31.1 Class sheet 1 liigh Pressure Coolant 1 TVA Class B TilPCI-1-157 O H-1099-C rev. 2 ANSI 831.1 Class 7 Injection (ilPCI) i IIPCI 3 TVA Class 8 116PCI-3-73A O H-2145-C rev. 1 ANSI B31.1 Cla ss
- 8. g PIPE HANGERS HPCI 3 N/A 3 11-103 47W455-H-2 rev. A 9.
I RCIC restraint ., 3 N/A R-13 47W456-1 rev. C 10.
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STRUCTURAL SUPPORTS Cable tray support 3 N/A Square No. A5 .45N816-3 . I 11 N/A 5 Cahic tray support 3 , Square No. 6A 45N888-1
- 12.
Rev, t 3/4/86 t - . . - - .
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OPPICE OP Ni! CLEAR OPERATIONS [. Shoot 1 (Continued) PIPING AND EQ111 PENT (MODIPIED) Item Identification No. Of Weld Drawing No. System Ignit Workplan No. Class
- 13. CR-1-61 Ol-N-1081-C rev. 6 Recirculation piping 1 MR8A-166738 TVA Class A ,
l that was overlaid ANSI 831.1 Class
- 14. K (R-1) 48W 1260-1 rev. 2 Hatches added to 2 WP8 6769 N/A pressure vessel in torus modification
- 15. Bay 8 7 48W 1257-1 rev. 5 Piping torus modification 3 WP8 13048 N/A Hark 2 for sleeves Penetration X-221-1 X-221-2 X-221-3 X-221-4 PIPE HANGERS (MCDIFIED)
- 16. GR-2-56 OI-M-2068C rev. 4 Recirc. pipe hanger 2 MR8A-190669 N/A I (H2 support) moved durir:g IHSI TRil-2(modified weld I.0) ,
g 17 Support No. 478455-55 Pipe hangers from 3 WP8 13076 ,N/A R-52-1 torus modification R-52-2 to HPCI , R-52-3 p R-52-4 4 STRUCIURAI. SUPPORT (MODIPIED) IS. 9-3-G25 46W414-2 rev. 3 Non-piping structural I WP8 10105 N/A Section F4-F4 wire mesh partition rev. 1
- 19. 1-IO-Z-R-1 48WI248-1 rev. 9 X 4 Y gussets 1 WP8 10268 N/A structural support Itev . I 3/4/86 fro o ta'-+ s modi ficat ion <
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t Sheet 2 Page 1 of 6 WELDER 00ALIFICATIONS i Date of Are Welder Initial Nalatenance Records Renewal ' Stamp Etrtification Iten No. Satisfactory? R111 Audit Status Welders Name Craft (Note 2) (Note 3) (Note 1) Brannon G-1 GAPC0 4-26-83 13 N/A N/A $ G-2 GAPC0 4-28-83 13 N/A N/A Baldwin G-3 4-29-83 13 N/A N/A , Taft GAPC0 G-4 GAPC0 5-02-83 13 N/A N/A Dumas G-5 GAPCO 5-08-83 13 N/A N/A Buttons G-o GAPCO 5-02-83 13 N/A N/A Madsen 6-7 GAPC0 7-18-83 13 N/A N/A Tilman Walden G-8 GAPCO 7-18-83 13 N/A 'N/A Brantly G-9 GAPCO 7-18-83 13 N/A N/A G-11 GAPC0 7-18-83 13 N/A N/A Sexton G-13 GAPCO 7-18-83 13 N/A N/A Lawson Mackelprang G-14 GAPCO 7-18-83 13 N/A N/A G-15 GAPC0 5-12-83 13 N/A N/A Mathis Kellerman G-lb GAPC0 8-08-83 13 N/A N/A , e sRs
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Sheet 2 . i Pa8e 2 of 6 i WELSER 00ALIFICATIONS Date of Are Welder Initial Maintenance Records Renewal Walders Name Stamo Craft Certification Item No. Satisfactorv7 3811 Audit Status (Nate 1) (Note 2) (Note 3) Hull G-18 GAPCO 4-28-83 13 N/A N/A , 3 Deady 6-19 GAPCO 8-15-83 13 N/A N/A Hish G-20 GAPCO 8-15-83 13 N/A N/A 81evins SAMP SOILER 2-02-82 14 YES N/A MAKER 8-06-80 Lyttle SFO-282 80 LIER 8-10-82 14 YES N/A MAKER 11-24-82 Henderson SFO-379 SOILER 7-27-83 15 YES N/A MAKER Springer 8FO-459 STEAM 3-27-85 16 YES N/A FITTER Johnson SFO-506 STEAM 2-27-85 16 YES N/A 1 FITTER Parker 8FO-305 STEAM 9-26-82 17 YES 4-10-83 j FITTER - Surchas 8F0-349 STEAM 4-20-83 17 YES N/A FITTER Ezell 8FO-129 IRON 4-30-81 18 YES N/A y g i WORKER
- 3 - C-tc i .
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( l . Sheet 2 Page 3 of 6 WELDER QUALIFICATIONS . Date of Are Welder Initial Maintenance Records Renewa) Stamp Craft Certification Iten No. Satisfactorv7 9811 Audit Status Welders Name (Note 2) (Note 3) (Note 1) McDole BF0-291 BOLIER 8-12-82 19 YES N/A b i MAKER Davis 8FO-413 STEAM 6-23-78 19 YES 8-18-82 FITTER Cannon 8FO-009 STEAN 8-25-80 N/A YES 4-07-83 FITTER 8-28-80 4-09-83 Claunch 824 8F BOILER 3-06-84 N/A YES 10-23-84 MAKER 6-21-83 10-24-84 ELECT. 7-20-83 N/A .YES N/A Olal 699 9-29-83 Gautreau SFO-422 STEAM 12-01-78 N/A YES N/A ' FITTER 4-19-19 Golden 8FO-424 STEAN' 3-19-85 N/A YES N/A FITTER 3-26-85 Grisham 8-1-8F 80 LIER 6-28-85 N/A VES N/A ' MAKER . Gosch 138F IRON 4-23-82 N/A YES N/A WORKER 5-14-82 League 8FO-042 ELECT. 4-12-84 N/A YES N/A y 4-03-85 seg, 3- G - tG 1
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{ Sheet 2
,PaSe 4 of 6 WELDER OUELIFICATIONS Date of Are Welder Initta) Main'.enance Records Senewal L41ders Name Stamp Craft [_ortification Ites No. Satisfactorvi 3319. Audit Status (Note 1) (Note 2) (Note 3)
Jackson 9-04-80 SFO-052 80 LIES MAKER 8-29-80 N/A YES N/A $ McCray 8FO-438 STEAM 8-20-82 N/A YES 4-09-83 FITTES 1-26-83 4-10-83 McGregory 8FO-249 STEAM 11-08-84 N/A VES N/A FITTER 11-07-84 Nesbitt 8FO-497 SHEET 1-14-85 N/A YES N/A METAL I-15-85 Pettus B-4-8F SOILER 3-05-85 N/A YES N/A MAKER 3-01-05 Posey 8-16-BF 80ILER 11-28-84 N/A YES N/A 1 MAKER 10-25-84 Smith STSS IRON 1-05-19 N/A YES N/A WORKER 2-04-83 Sims 8FO-544 CARPENTER 7-24-85 N/A YES N/A Tanner BF0-461 STEAM 8-07-19 N/A YES N/A l f!TTER 3-01-84 Woods M6 8F MACHINIST 9-15-80 N/A YES N/A V 9-21-83 SM j , 7-(, - Ft. i' .
e t r Sheet 2 Page 5 of 6, 6.(
idELKR QUALIFICATIONS Date of Are Welder Initial Maintenance Records Renewal Stamo Craft certification Ites No. Satisfactorv7 Bate Audit Status
,.- widers Name I (Note 2) (Note 3)
(Note 1) . b~* SFO-062 STEAM 9-10-80 N/A YES N/A Walton dde . FITTER 9-11-80 SFO-100 STEAM 1-22-81 N/A YES N/A sgt, 4 White c FITTER 1-15-81 3. g.g
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Sheet 2 Page 6 of 6 (Nots 1) Welders applicable to Item 13 wre subcontracted to TVA from SAPCO. Welder Maintenance Records wre not applicable to Item 13., (Note 2) Many widers have multiple qualifications. Tw dates listed indicates tw separate widing processes or separate qualification codes. I (Note 3) N/A indicates that renewl of qualification is not applicable.
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Sheet 3 Page 1 of 3 m I NUCLEAR OPERATIONS IISPECTOE PERSONNEL QUALIFICATIONS Inspector ovalification 231g3, Audit Status 1 TTA Bedingfield, Larry W. YT II LSME III 3 Ear 83 2 T7A Bullington, Gene TI II ASME III 3 Mar 83 3 TTA Sander, Willie YT II ASME III 7 Mar 83 , 4 T7A Smedley, Paul E YT II ASME III 19 Jan 83 I 5 TVA Thompson, Sandra TT II ASME III 3 Ear 83 6 T7A Hulsey, Chris NT II 1 Apr 82 MT II Racertification 22 Mar 85 7 T7A Priest, W. L. R II 2 Aug 84 ; 8 TTA Sander, Willie IT II 1 Apr 82 9 TVA Thompson, Sandra NT II 1 Ape 82 NI II Escortification 22 Mar 85 10 T7A Blackburn, George T. PT II 15 Apr 81 . PT II tacertification 16 Feb 84 ; 11 TTA Eartin, J. 7. PT II 14 Feb 85 i 12 TVA Miller D. L. PT II 14 Feb 85 ' 13 T7A Sanders, Willie PT II 1 Apr 81 14 T7A Smedley, Paul 1 PT II 15 Ape 81 PT II tacertification 19 Apr 84 15 T7A Thompson, Sandra PT II 3 Nov 83 16 T7A 8entley, E. Roger TT III 22 Dec 81 TT E-7T-25 30 Mar 83 7T IGSCC 20 Apr 84 1 l 17 UTL Iurtz, Ianneth TT II N-7T-25 26 Jul 83 I 18 UTL Whigdon, Sherrie 7T II 31 Jul 83 77 N-VT-25 19 Aug E3 19 T7A Wille, tudolph TT II 15 Mar 83 VT IGSCC 8 Mar 85 9 MM 86 - - - - - - - - - - , , - - - - , , - - p - , , , , , --.----,y v--+ - -
Sheet 3
~ Page 2 of 3 (Cestinued) .
4 NUCLEAX OPERATIONS IESPECTCE PEE 3005EL QUALIFICATIONS Inspector Qualifiestion gg131 Audit Status 20 UTL Burdett, David UT II 7 Aug 83 l UT N-UT-25 26 Aug 83 ' l 21 UTL Stephes, Timothy L. UT II 19 Jun 83 - UT N-UT-25 24 Jul 83 UT 5-UT-18 25 Jul 83 I 22 UTL Flint, Gary UT II 7 Jul 83 UT E-UT-18 7 Jul 83 UT E-UT-18 27 Jul 83 23 ITA 8ebbias, Richael UT II 15 Ear 83 UT ISSCC 8 Ear 85 24 UTL Baras. Thomas E Uf I 27 May 83 UT 5-UT-25 3 Jun 83 25 UTL Johnson, Patrick UTII N-UT-25 3 Jun 83 26 UTL Colvia UT II 2 Aug 82 UT N-UT-25 f 22 Ray 83 l 27 TTA Schroeder, Thomas 8. IT III 15 Jaa 82 IANDOR SAMPLIEGS
- 1. ITA Barnett, Reasie E. PT II 17 Jan 85
' 2. TTA Bedingf1 eld, Larry W. ff II 14 Apr 83 WgII ASEE III 3 Mar 83 W ET II ingaeah 5 Ray 83
- 3. TTA 8eidges, Crill PT II 19 Apr 84 4 TTA Coffmaa C. O. PT II 17 Jan 85
- 5. ITA Crever, J. F. PT II 19 Sept 84
- 6. TTA Gatewood D. E. MT II 22 Nor 85 PT II 17 Jan 85 g 6 Mast 86
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Sheet 3 Page 3 of 3 m (Continued) Low
- 7. STA M UTL Leinbach. Dean DT II 5-VT-25/ 31 Jul 83 UT ISSCC 4 Aug 83
- 8. UTL Overtoa. James N. UT II 5-7T-25/ 21 Aas 83 UT IG3CC 26 Ass 83 l
- 9. UTL Silva, Crus UT E-YT-25/ IGSCC 29 Jul 83 QR.W
- 10. UTL Warren, todacteh
- UT II 5-TT-25/ 24 Jul 83 9 n A4. 6 UT ISSCC 29 Jul 83 ,
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/ 13
. \u IE8PECTot PERSONNEL QUALIFICATIONS (Tralains and certification of Survey Poesonnel)
,j Suveyor Tralaina/ Certification Audit Status
.,' P. R. Bevil 5/17/85
- 1 a
b " .J C. Bridges 1/23/85
-.f G. Ballingtoa
, 1/23/85 T. Bardette 4/24/85
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., L. Clardy 2/20/85
.- J. Dial 1/30/86 hl i i
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i l l Sheet 3 s j , INSPECIOR PERS0EEEL QUALIFICATI0Its Audit Inspector Qualification Date Certified Status
- 1. E. Barnett Yis. Weld Insp. Lavel II ,
$/22/85 Nechanical - Partial 6/13/84 Receipt Insp. 11/14/84 Cable Iray Inst. 7/30/85 L. Bedingfield Vis. Weld Exam Level II 1/28/86 -
In Serv. Yis. Weld Exta Level II 12/18/84 Dia. Insp./ Comp & Pipe Supports 5/31/83 Receipt Insp. 3/15/84 Rech. & Hydro 10/11/82 /,Md/tf sat hV)w C. Bridges Vis. Wold Izas (ASHI III) Level II 2/24/83 U Ibehanical 6/9/83 fj[ G. N. Balliatton Vis. Wold Exas (Sect. III) Level II 3/3/83 & 1/17/86 Receipt Insp. 7/18/84 Nechanical . 2/12/86 C. O. Coffman Yts Wold Level II 5/23/85 5echanical-Partial 2/25/85 Cable Iray Installation 7/25/85 . R. D. Cooper Rochanical 4/16/85 J. Craven Yis Wold Ezam Sect. III Level II 3/10/43 & 1/29/86 In Service Yis. Level II 6/24/85 Rochanical 2/21/84 5echanical - Dimensional 12/14/83 Rochanical - Comp. & Pipe Support 6/22/84 Rochanical - Alignment 12/14/83 J. Dlal Mechanical-Dimensional 2/17/85 D. E. Gatewood Vis. Wold Esta (Sect. III) Level II 7/01/83 In Service Yis (Sect II) Level II 2/16/84 ' Nechanical - Full Cert. 4/10/85 W. L. Priest Yis Weld Exas (Sect III) Level II 4/17/84 Receipt Insp. Full Cert. 10/21/85 Mechanical Equip 8/23/84 Jimensional Insp. 8/23/84 (W
Sheet 4
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1I7I57 0F MNm** EIPORTS 15D CO**KTIVE ACTIp_Hf, ggLg, Corrective action audit Status 3C1 Wo. CAR 82-165 FS 8-16-42 8-31-42 $ 1 CAR 82-170 FS 8-09-42 4-27-42 CAR 83-162 10-14-43 1-12-44 CAR 83-168 10-2*-43 12-01-43 . CAR 83-171 11-14-43 4-23-44 CAR 83-176 12-05-43 4-10-44 Cat 83-56 2-23-43 3 05-43 CAR 85-010 2-19-45 3-21-45 CAR 85-055 8-01-45 . 10-10-45 DE 82-07 11-12-42 11-12-42 DR 83-410 1 8-21-43 11-02-43 DE 83-429 1 9-04-43 10-07-43 DE 84-0024 1-30-84 1-30-44 DE 84-0055 3-06-84 3-25-44 - DE 85-0135 2-26-45 2-24-45 DE 85-0265 5-6-45 5-29-85 DE 85-0349 7-23-85 7-23-85 DR 85-0427 9-10-45 OPEI 4// N Me (f.py) DE 85-0451 1-02-85 11-13-45 DE 85-0552 10-29-85 OPEI 4/4 # bhi[hH)
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Sheet 5 e~ . NUCLEAR. OPERATIONS s l DEAWING RETIEW l Drawinz No, tev. Systes h hdit Status CE-N-1081-C 6 Weld Identificatica. tectre. 6/05/81 I F 48W1260-1 2 Torus Access Esteh 6/16/81 48V1257-1 5 Torus Penetratica Reinforcessats 6/11/82 CX-E-2068 4 Weld Identifiestion. Recire. 12/07/45 475455-55 2 Nechateal EPCI System Pipe 6/01/81 Supports 46W414-4 4 Wire Nesh Partition 4/29/83 - 48V1248-1 9 Torus Ring Girder, External l'J84 Rainforcement 47V455-2 F High Pressure Coolant 1/20/85 W455-E-10 A High Pressure Coolant, 2/19/80 As-Constructed s 45k830-5 8 Cable Trays 1/18/81 47C430-12 1 IWCD. System ' 12/28/71 47V812-1 20 Ilgh Pressure Coolaat Injectica 5/01/81 47V813-1 13 Rosetor Core Isolation Cooling 3/11/80 47W820-5 0 Control tod Drive Hydraalic 6/16/82 System 47C430-7 2 Feedwater Piping. Wold 9/11/73 -
& Not lequirements if p/r' 9
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i RITIEW OF VII.D Am MitAP TmTmr pgDCIDURES 1 Procedure No. Eav. No. Egg, audit Status 4 l GAPCD E 8/8-OL & PQt's 1 3/14/43 8 l ST-SE11-0-3C & PQt's 1 4/19/79 i l SE11-5-98 & PQt 0 10/18/78 l l ST-88-0-1A & PQt 1 11/04/78 35-P-1 & PQt 8 5/27/81 i SE11-89 & PQt 4 1/29/81 SI88-b 4A & PQt 0 10/30/80 SE 8.43-8-1A & PQt 1 2/28/75 8T-3514-4-1 & PQR 0 10/31/78 I SE55-B-2A & PQt 1 2/28/75 I Specification for Post 4 1/24/85 i Wold Best Treatnest, P.S.2.E.1.1 ye#
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Sheet 7 3 p3 Page 1 of 2 f%.j WEIA FILLER BETAL 0FFICE OF NBCLEAR OPERATIONS ,; ,f,3 i .; , .,.1 And5L
- O d Contreet Date Dette Ites No.
Bts, West We, Let Ee, Natorial Received
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* ?d . h leer ebeet 1) .'. f,' 17 83E71-661784-2 8215 23324 57018 - 12/82 S 80F72-254381 72624 9297B222143 57018 7/81 12/82
.hf.i 17 l ' 22468 9338D122143 E7018 7/81 12/82
- 3}1 4 - 80F72-254381 gj 9334A122143 E7018 7/81 12/82
- 80F72-254381 22468 .-l 80F72-254381 22468 9338C122143 E7018 7/81 12/82 '[' ,
I '. . p' g, 43878 9298C222143 57018 7/81 12/82
- 4 - 80F72-254381
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- 25431? 658C253 - 17056 .sbout 79 12/82
- 340107 92121D E7013 8/83 (Transf. Reg.)
- - 340107 - 920780 E7018 8/83 (Tran= C Seg.)
0 82F74-324688 972.9C ' - 57018 2/82 79F89-254352 64355s 026886 E7018 1/81 -
. 1 80E76-607876 431L245 0268222 E7018 4/82 - , /
2 14, 17 81FEl-18660 27433 - 57083 11/81 12/82 (Nete CAR on 3
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' Data material inspection report approved.
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Eheet 7 - Page 2 of 2 - WELD FILLIE BETAL - 0FFICE OF NUCLEAR OPERATI0ti3 It.e No. Contract Date Date Audit h (por sheet 1) h Eggt MS, Let Nou Meteriel Received
- Welded stetos 14 14, 18, 19 -
N16873 0268219 57018 12/82 (Note CAR on $ (item 19) 15 16 - 761408 - EE308L - 3/31 $ 16 15, 18 80F72-254381 43878 9298C2-22143 E7018 9/25/81 1/84 (Note CAR on 3 (item 15) 17 17. 14 31P74-17893 421L729 10751A E7018 8/81 5/84 5 18 - 7DP70-254314 10220-1 5309-15 3/79 -
.3 19 -
7aP70254314 10171-1 - E308-15 3/79 free red room 5 20 - 78P70254314 ' 50017-1 - E309-15 3/79 free rod room 21 - 78P70-254314 50065-1 - 5308-15 3/79 tres red roce , 22 - 78F70-254314 10218 E309715 3/79 free rod room i 23 - 73P70-254314 56193 - E3'08 L- 15 3/79 frea rod room 24 - 78P70-254314 %)32-1 - ENICSFE-3 10/;S free rod room ,'
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l 3.0 APTECH ENGINEERING REPORT [ 3.1 Introduction TVA, through its contractor Aptech Engineneing Scritcoa Inc. ( APTECH), has performed a review of weldhlg an subsequent J* l preservice and inservice inspection activiiles et,3cowns Ferry l '
/
Nuclear P antfo'jf the purpoco of determining the s$ltability for 5 i
/
continuing sor'/ ice of we'ios purrently installed at Browns Ferry. The basis for this determination is derived from historical records and activities related to the production of quality welds (via an 4 appropriate welding and inspection program) and historical performance of welds during the operating phase of the plant. This review is an adjunct to other TVA activities focused on weld quality determination, wold reinspection, and wolding program assessment, problem identiff. cation and resolution. 3.2 Summary The results of this covlow are positivo and indicato suitability for service of BFN wolds. '.'owever, two wolds identified by the report required further investigatica to close out these items. Weld RCRD-3-43 was identified in Section 2.4 of the- report as
"...containing a relevant indication not closed out...." This weld has been evaluated by a TVA American Society of Nondestructive l
Testing (ASNT) Level III inspector. The results are that the
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indication designated as ..near in the original report is in fact "geometric" in nature, caused by the weld crown, and therefore noncelevant. This weld was a.septed with no further investigation required. l DhE4 - 0661N 1 11/6/87
- l e
Weld DRWC-1-2 was reported on a Licenseo Event Report (LER) as having a linear indication with no cause glven. The report > did not identify if the weld indication was service induced or was an initial ' quality of weld' problem. The LER covering the e
. indication 'us issued in 1980. The Ultrasonic (UT) examinations for Cycle 0 of this weld (performed in 1973) indicates the weld was accepted and the 1-inear indication was not identified. Therefore, WP determined that this indication is service related and not a result of initial construction. .
3.3 Recommendations APTECH recommend 5' additional inspections be performed on supports within the ISI program during the next snopoetion interval. e APTECH also recommends Chat supports and hangers within the ISI program be examined for such attelbutes as configuration and missing welds. This would bring TVA's ISI program more in line with the program existing at other plants. This inspection should be performed by augmenting the existing ISI procedures to facilitate detection of configuration defects as well as service induced damage. a e O d v -
4 3.4 Aptech Report { l 4 0
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IS APPLIEDTECHNOLOGY AES 8604658AQ-1 Rev. 0 I EVALUATION OF THE QUALITY OF WELDS l AT BROWNS FERRY NUCLEAR PLANT l l 1 I l l 1 Prepared by l j Jeffrey L. Grover l Erwin L. Capener l l l l Aptech Engineering Services, Inc. 1257 Elko Drive Sunnyvale, California 94089 I Prepared for Tennessee Valley Authority Chattanooga Office Complex Chattanooga, Tennessee 37401 July, 1987 1257 ELKO ORIVE . . SUNNYVALE I.1 CAUFORNIA 94049 O (404) 745-7000 601 NORTH FAAFAA STREET. Sulf E 420 ' ALEXANOAtA
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Copynged < 1987 Aptoch Er9neenng Serw:es, tre. NOTICE TNs rooort we: preoared by 4pech Er9neenng Serw:et,Inc ,(APTECH) as an accours of wort p sored Dy the orgarwtate named hereen. Nenhor AFTECH not any person acang on bemerf of APTECH ) m maos ny n.nry, owee. or imoned. -un re.oec. = me use of any <*armaan. aooarmus, a method, or proce.s disciotad m this report or that such use may not irWrtnge privmofy owne1 ngNte; or (b) assumes any liscehties eth respect to the use of, or for damages reeufung frorn (f4 use of, any mtormaton, apparatus, method. or procese CeClosed m t?At report. O
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QUALITY ASSURANCE VERIFICATION RECORD SHEET 4 EVALUATION OF THE QUALITY OF WELOS AT BROWNS FERRY NUCLEAR PLANT (July 7, 1987) (AES 8604658AQ-1) Originated By: Jeffrey I _W GYper,ProjectManager 7!7/b) Date 7/7/g7 Verified By: Nicnael T. CrdninT Verifier ' Date Yevi 6By? 7f?f87 Russell C. Cipolla, QA Engineer Date l f por val 5 \, i 7/7/7 Peter 0, hedjecock, QA Manager 'Date ( 9 APTECHj EPGediac SEW t 51st AMQ4 s
TABLE OF CONTENTS l
. 1 1 =
Section P.Aga l ABSTRACT 1 INTRODUCTION 1-1 l 2-1 l 2 REVIEW OF PRESERVICE AND INSERVICE INSPECTION RESULTS 2.1 Review of Preservice and Inservice Inspection 2-1 l 1 Programs 2.2 Summary of Inspection Data 2-4 ( 2.3 Indication Rates 2-5 2.4 Review of Disposition of Indications 2-6 3 REVIEW OF OPERATIONAL EXPERIENCE 3-1 4
SUMMARY
, CONCLUSIONS AND RECOMMENDATIONS 4-1 5 EXTERNALLY GENERATED CONTROLLED DOCUMENTS USED 5-1 APPENDIX A - PSI AND ISI INSPECTION DATABASE A-1 r 4 4
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ABSTRACT The quality of piping and support welds at Browns Ferry Nuclear Plant was evaluated by a review of relevant records. ' The welding and quality programs were evaluated by an audit performed by Bechtel Power Corporation. The rate of relevant inspection indications in the preservice and first five cycles of inservice' inspection were reviewed and a
, projection was made as to the indication rates for those welds not yet inspected under the inservice inspection ;
program. Licensee Event Reports were reviewed to determine f if any were related to welding. Based on these reviews, ) ! there is no indication that piping welds are unfit for service. Additional inspection may be required to provide' j the same assurance for support welds. oo enn 4 k f e 9 e
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,. I l-1 l.0 INTRODUCTION ' As a result of employee concerns regarding the quality of the welding program at Tennessee Valley Authority's Watts Bar Nuclear Plant, the quality of welds made by TVA at j
other plants within the TVA system also came into question, l Aptech Engineering Services, Inc. (ApTECH) was asked by TVA to review the quality of welds made at the Sequoyah Nuclear l A Plant in support of their effort to restart that plant. l report was prepared in January 1986 and the results were , The presented to the Nuclear Regulatory Commission (NRC). scope of that project was subsequently extended to include Browns Ferry Nuclear Plant. This report covers the l activities specifically related to the Browns Ferry Nuclear
' 1 During the first phase of this project, a program Plant.
plan was developed to evaluate the quality of welds based upon a three-pronged approach. That approach is' illustrated in Figure 1-1 and is described below. The first aspect of this evaluation is a -eview of the overall welding and quality assurance (QA) program at Browns Ferry. This review was performed by Bechtel Power I i Corporation, which audited the welding programs of both the l I Office.of Construction and Nuclear operations. The two remaining paths in Figure 1-1 were evaluated by APTECH under the scope of this project and are reported herein. The second step in determining the quality of the welds is to evaluate the preservice and inservice inspection (PSI and ISI) results. As,the inspection techniques and personnel involved in the PSI and ISI programs are typically different than those employed during construction (especially for piping) these inspections represent an independent measure. of the quality of the welds. If the weld quality was poor, it would be anticipated that the inspection results would l indicate an abnormally high indication rate. 4
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l i The final step in validating the quality of the welds is to review the successful operating experience of the three ! Browns Ferry units. As cach of the three units has experienced more than 45,000 hours of operation, any initially defective welds should have already been screened ,
, out by the "infant mortality" period associated with the initial operation of any component. Review of Licensee ;
Event Reports (LER's) would show whether there has been any failures due to poor initial quality of the welds. The lower half of Figure 1-1 illustrates the process that would be followed after the three separate reviews have been ss completed and the overall quality of the welds has been determined. If the results of those three reviews shows
, that the quality of welds is good, then no additional work is required. However, if these reviews indicate that the
. welds may not be satisfactory for their intended service, '
then several options still exist, including augmenting the existing ISI program and determining the consequence of failure of specific components. The scope of this review was limited to two types of welds: piping welds and structurally significant or safety related structural welds, such as component supports and piping hangers. The basis for this delineation is that piping and structural welds are built to different procedures and acceptance criteria and therefore represent different populations that could have different measures of weld quality. A third population could be defined which falls somewhere between the other two categories: integrrl attachments. The welds on integral attachments resemble _ structural welds, but as the weld is made to the pressure boundary, fabrication procedures and inspection criteria are more rigorous than for typical structural velds. Structural
- y welds made to the American Welding Society standard AWS-D1.1 m
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y _ _ 1 r l l.f. ' lY 1-3 .] 4 L,a 'W ,r g W' s , h require only visual examination, while integral attachments are usually inspected with penetrant or magnetic particle T^f , usually / v i ;., and may be inspected ultrasonically, which is l It is therefore likely ) q'.j limited to pressure boundary welds. s,.
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that indication rates on integral attachments will be higher N,,,l than either of the other two populations. Although the Md intent of this project is to establish the quality of welds e. M} made by TVA, indication rates for welds made by other
. . /.. l 'il fabricators were also reviewed for comparison. ,
M and l Ub pf Section 2 of this report describes the scope of the PSI ) l
'i ISI programs, reviews the inspection records obtained from '
gi i those programs and presents the rate of indications date ,ted
-l to date. The operating experience and any relevant licensee event reports are reviewed in Section 3. The results and gj
[ conclusions of this review are summarized in Section 4. I
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I Figure 1-1 - Browns Ferry Weld Review Flow Chart Evaluate Welding Review ISI and Evaluate successful and Quality PSI Program Operating Experience Asstrance Programs and Results
,r 1r o indication Rate Weld Related Quality Established and Confidence Licensee Event Level Set Reports Bechtel w/ APTECH "APTECH APTECH Review Quality Established and - ,
m Service Suitabilty Reaffirmed a '
- Ondcation Rate and ,
Confidence Level Established) I Report and Yes Presentation cceptadie?
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4 And/Or No g 4 Augment Consequence iSI Prograrn Analysis
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2-1 l 1 2.0 REVIEW OF PRESERVICE AND INSERVICE INSPECTION RESULTS l l The best way to measure the quality of welds at Browns Ferry Nuclear Plant, short of inspecting 100% of the welds, which
- may be impossible to do because of problems of accessibility j is to reinspect the welds using some form of sampling plan I to ensure high confidence in the inspection results. The ]
preservice and inservice inspections required by Section XI of the ASME Code represent independent sampling inspections l of the quality of the welds. The PSI and ISI examinations - l are performed by different personnel (in some cases outside contractors) than those invclved in the fabrication of the l welds, and the techniques and procedures are different, ensuring an evaluation which is independent of the original construction inspections. Thus, the PSI and ISI results will be used as indicators of the quality of welds at Browns l Ferry Nuclear Plant. If chronic deficiencies existed in the welding program at Brovns Ferry, it would be expected that i an unusually high number of defective welds would be detected in the PSI and ISI programs. The rate of generation of Notices of Indication (NOI's) will be used here as a measure of weld quality. 2.1 Review of Preservice and Inservice Inspection Programs Browns Ferry is a relatively old nuclear plant (dates of commercial operation for the Browns Ferry units are 8/1/74, 3/1/75, and 3/1/77) and regulatory and TVA requirements have changed over the subsequent years. The inservice inspection l program at Browns Ferry has undergone at least two major l
\
changes over the years to make it more consistent with the ' newer plants. In fact, the first baseline inspection was performed prior to the use of an ASME Section XI inspection plan, and is therefore not a true Section XI preservice ; inspection. This baseline inspection is still called the preservice, or cycle zero, inspection, however. ! Q. .
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h During the preservice and firat three cycles of inservice inspection most indications that would be representative of poor weld quality were handled by trouble reports. trouble report indicated some deficiency in the weld that The $ jj had been inspected, however there was no closed loop to 11 ] ensure that the deficiency was properly resolved. Prior to );,; the fourth cycle of inservice inspection the inspection procedure was changed so that it employed maintenance , reports instead of trouble reports. The maintenance , 1 reports were part of a clc, sed loop designed to ensure that -; the deficiencies were resolved. The use of notices of . , indication was also started at this time, however when surface conditions would not permit performance of the examination, some discrepancies were resolved through the , maintenance report rather 'than the notice of indication. .4 e During the preservice and first three cycles of inservice . inspection the potential therefore existed for an indication j[ to be detected but never dispositioned. In order to ensure M.. that all indications detected in the early inspections were g. adequately dispositioned, all weld quality indications were investigated for proper closure. Section 2.4 descr11.as the
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, work performed under this project to ensure that the early 'ij... indications were adequately dispositioned. '@ 4 TVA provided APTECH with a summary of the inspections JY -n performed during the preservice inspection and five cycles of inservice inspection (the cycle 6 inspection data were not complete at the time this project was performed). These 3 data were contained in externally generated controlled , documents ECD-5 and ECD-10 (see the reference list in Section 5.0 for the controlled documents used in this project). The summary included all piping welds on systems larger than four inches in diameter, pressure vessel welds, f' ' tf and some support and hanger welds. Because NOI's were not
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used during the PSI or first three cycles of ISI, any l~ s I' [k
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- 2-3 discrepancies were simply noted without further description.
Therefore, if an indication was noted for a given weld, there was no means of establishing if the indication was due to poor initial weld quality or due to some other cause (service related) . Starting with cycle 4, NOI information is available which allows the determination of the type and cause of many, but not all of the indications. Because the scope of this project was limited to fabrication related defects, indications that were determined to be service induced, primarily those indicative of intergranular stress , corrosion cracking (IGSCC) were deleted from the data provided to APTECH. It is likely that some of the indications included in the database are also service induced, but unless it can be positively shown to be service induced, the indication is conservatively assumed to be fabrication related. This information was developed into a computer database for use in a statistical analysis of the indication rates. Welds from the reactor pressure vessel or heat exchangers were deleted from the computer database as they are outside the scope of this review of piping and support welds. Those velds that were deleted specifically include all those with a system name of RPV (reactor pressure vessel) or RCH (reactor closure head), or a weld number starting with N (nozzle), JP (jet pump), or RHRG (residual heat removal heat exchangers). Appendix A contains a complete listing of the data in the computer data base. Each entry represents a single inspection. An analysis of these data will be summarized in Section 2.2. In order to perform a statistical analysis of the inspection results, it is necessary to know the size of the total population of welds. The total number of welds was assumed to be the same as the total population in the ISI program which was determined from Browns Ferry Surveillance
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1 2-4 { i
'N s Instruction SI-4.6.G.(ECD-2) Table 2-1 shows . the assumed f values for the ISI population of piping welds and Table 2-2 l shows the population of supports. These values are taken :
from Tables A and B of SI-4.6.G for Class 1 and Class 2 piping welds, and from Tables 13.1 through 13.3 of SI-4.6.G for supports. Note that the numbers in Table 2-2 represent numbers of supports, not welds. Many supports cont'ain j multiple welds, and the number of welds per component can not be easily determined from the ISI program plan. I 4 2.2 Summary of Inspection Data l Using computerized sorting techniques, the inspection database shown in Appendix A war interrogated to establish l the rate of occurrence of welds containing indications. As j the database contained all inspections performed as a part i of the PSI and ISI programs, the indication rate could be
]
established for any population that could be identified. This could include the unit, piping system, inspection l cycle, type of weld, type of NDE performed, or the fabricator. For piping welds, the fabricator is easily l identified by the first letter of the weld identification ! The majority of the welds were made by TVA, number. ' although both Dravo and Kellogg provided piping systems I containing shop welds. Thes's are identified by the letters ; DS (for Dravo) or K (for Kellogg) at the start of the weld l number. The primary population of interest is field welds I fabricated by TVA. For comparison p1rposes, the populations ! associated with each fabricator were evaluated. The means of establishing the fabricator for each weld are described in the beginning of Appendix A. Table 2-3 summarizes the results of the evaluation of inspection results for piping welds. The inspection results for supports are summarized in Table 2-4. Because many j welds were inspected more than once over the years, each O 4
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- c. unique weld inspected was only counted once. The number of NOI's reported includes only th'ose determined not to be geometric in nature. Relevant NOI's include only those indications that were considered to be reportable based upon !
- the relevant acceptance criteria. In most cases, this was from ultrasonic inspection procedure N-UT-10 (Rev.0 12/9/79) which uses a 100% distance-amplitude correction (DAC) as the I reporting criterion. In addition, a given veld could have I more than one NOI written against it but is only counted once. All indications were conservatively characterized as fabrication related.
From the values shown in Table 2-3, it is clear that the indication rate for TVA piping welds is low and is consistent with the indication rate for welds fabricated in ! the shop by Dravo. The indication rate for supports in Table 2-4 is higher. This is due to the anticipated high indication rate in integral attachments. No indications were noted in non-integral supports, although a relatively small number of these hangers were inspected. 2.3 Indication Rates The values shown in Tables 2-3 and 2-4 represent the percentage of the number of piping welds and supports inspected that contained indications. As the inspection did , l not cover 100% of the components, there is some statistical uncertainty as to the rate of indications for the entire population. In crder to quantify this, the size of the
. entire population must be known. From the information in l Tables 2-1 and 2-2, the population size is known for any l given piping system, for all systems in a given unit, or for all piping in all three units. The size of the populations associated with each f abricator are unknown, and therefore j 1
1 l 1
2-6 m J the actual indication rates can not be determined. The expected indication rate can only be determined from the overall population of welds. l l Based on a hypergeometric distribution of indications, the indication rate for the total population of piping welds is calculated to be 1.4% with greater than 95% confidence. The indication rate is determined to be 12.8% for integral attachments and 10.8% for all supports, with greater than
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95% confidence. Even the non-integral hangers, which had no , j indications during the PSI and ISI programs have an expected I indication rate of 10.04, due to the low number of j inspections. The reliability (one minus the indication j
.i rate) is lower than the 95% occurrence level /95% confidence l 1
limit that is normally accepted by the NRC for all types of l 1 supports. However, the indication rate for supports is j based on the number of supports, not the number of welds. ? l The indication rate per veld will be a smaller number. f 2.4 Review of Disposition of Indications . l As discussed in Section 2.1, the procedures in place for the l preservice end first three cycles of inservice inspection did not ensure that all indications detected were properly dispositioned. This does not mean that the indications were not dispositiened, but means that no record was made of any l repair or other action on the original trouble report. Without that record it is very difficult to locate the actual records related to the disposition of the indication.
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In this project, it was noted that many welds were inspected more than once, and often after an indication was noted, a re-examination was performed during the same inspection cycle. If the subsequent re-inspection was satisfactory, it could be assumed that the indication was adequately j dispositioned. This assumption was extrapolated such that O 9
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2-7 >. if a weld was inspected during a later cycle with the same inspection technique and no indication was noted, it was assumed that the indication had been properly closed out. l Based on this assumption, only three welds containing relevant indications were identified as not being closed out 1 by subsequent reinspection. These are welds RCRD-3-43, RCRD-3-47, and DSHS-3-9, all of which are from Unit 3, inspection cycle 2. Weld RCRD-3-47 had an ultrasonic
- indication equal to the threshold for reporting and.is ,
therefore technically acceptable (the procedure states that an "indication exceeding 100% of the primary reference distance amplitude curve shall be evaluated", but the indication is reported as 100% DAC). The indication reported for veld DSHS-3-9 is weld spatter located 4-9 inches away from the weld, which is outside the area of examination and will not affect the integrity of the weld. Thus, the only weld containing a relevant indication not closed out by reinspection is weld RCRD-3-43. i l l l l l l 4 4
j 2-8 s Table 2-1 Summary of Piping Weld Population in ISI Program Plan Tvoe of Weld
- Unit 1 Unit 2 Unit 3 Total Class 1 Piping
. Recirculation (cire) 72 72 72 216 Recirculation (branch) 11 11 11 33' Main Steam (circ) 110 107 108 325 Main Steam 27 27 27 81 (branch) -
Feedwater (circ) 68 67 73 208 2 6 Feedwater (branch) 2 2 Core Spray (circ) 0 20 20 40 RHR (circ) 50 47 47 144 CRD (circ) 11 11 11 33 RWCU (circ) 18 15 17 50 RCIC (circ) - 4 6 4 14 HPCI (circ) 20 20 18 58 - Head Spray (circ) 27 25 25** 77 Total 1285 Class 2 Piping Main Steam (circ) 58 58 58 174 ~ Main Steam (branch) 1 1 1 3 RER (circ) 162 162 162 486 CCW (circ) 8 8 8 24 HPCI (circ) 16 20 20 56 RCIC (circ) 8 8 8 24 Core Spray (circ) 12 12 12 36 Auxilary Steam (circ) 41 40 35 111 Total 919 Total Class 1 and 2 Piping Welds 2204 1
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- cire = circumferential weld, branch = tee branch weld )
** This system has been removed 4
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l l Table 2-2 l Summary of Support Population in ISI Program Plan
- Unit i Unit 2 Unit 3 Total Tvoe of sunoort l Class 1 17/24 7/13 24/37 RJiR 2/2 2/2 4/4 RWC i 31/33 35/35 66/68 ,
R 32/32 32/32 32/32 96/96 FW 34/34 34/34 34/34 102/102 MS 3/3 3/3 3/3 9/9 HPCI 6/10 6/10 12/20 CS 1 Total 313/336 J l Class 2 91/135 98/119 86/124 275/378 RHR 17/43 17/41 16/41 50/125 1
- MS )
CCW 0/1 0/2 0/2 0/5 CDR 6/37 4/36 6/31 16/104 CS 14/38 20/30 16/48 50/116 l I HPCI 22/43 20/44 20/50 62/137 11/23 11/27 30/76 RCIC 8/26 Total 483/941 Total Class 1 and Class 2 Supports 796/1277
- The values in the table represent the number of integral attachments / number of total supports. For example, the value
- listed as 17/24 indicates that there are 17 integral attachments and 7 non-integral hangers, for a total of 24 supports.
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2-10 l 3 Table 2-3 Percentage of Piping Walds Inspected Containing Indications System Number of No. of No. of Relevant Name Fabricator Insoections Welds NOI's NOI's i Aux Steam (AS) TVA 2 2 0 0 Dravo 8 5 0 0 TOTAL 10 7 0 0 Closed Cooling Water (CCW) TVA 3 2 0 0 Control Rod Drive (CRD) TVA 377 210 13 4 (1.9%) l Core Spray (CS) TVA 405 107 24 3 (2.8%) l
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Dravo 240 46 13 2 (4.3%)
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TOTAL 645 153 37 5 (3.3%) Feedwater (FW) TVA 252 102 18 0 Kellogg 277 105 29 0 TOTAL 529 207 47 0 High Pressure Coolant Injection (HPCI) TVA 152 67 7 1 (1.5%) Head Spray (HS) TVA 89 38 3 0 Dravo 89 38 1 1 (2.6%) TOTAL 178 76 4 1 (1.3%) e 9 m
2-15 . Table 2-3 (continued) Percentage of Piping Welds Inspected Containing Indications System Number of No. of No. of Relevant NOI's NOI's Naine Fabriegfftr Insoections Welds Main Steam (MS) 113 29 0 266 TVA - 9 0 0 Dravo 11 306 27 0 Kellogg 709 428 56 0 - TOTAL 986 Recirculation (R) 598 2'00 38 2 (1.0%) TVA Kellogg 538 166 37 1 (0.6%) 1136 366 75 3 (0.8%) TOTAL Reactor Core Isolation Cooling (RCIC) ' 20 3 0 TVA 42 N :' dual Heat Removal (RHR) TVA 308 146 11 4 (?.7%) l 47 11 0 1 Dravo 143 1 TOTAL 451 193 22 4 (2.0%) l Reactor Water Cleanup (RWC) TVA 181 46 7 2 (4.3%) 169 37 4 0 Dravo TOTAL 350 83 11 2 (2.4%) All Systems TVA 2675 1048 151 16 (1.5%) Dravo 660 179 29 3 (1.7%) Kellogg 1524 577 93 1 (0.2%) TOTAL 4859 1804 273 10 (1.1%) g
I 2-12 l
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Percentage of Supports Inspected Containing Indications , i Support Number of No. of No. of Relevant i Inseections Welda NOI's NOI's - ; Type '
. )
i 184 144 18 12 (8.3%) Integral Attachments n 28 0 0 Hangers 28 , Total Supports 212 172 18 12 (7.0%) , j l 4 '. . g i s I S T e e m 4 O o (
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3-1
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3.0 REVIEW OF OPERATIONAL EXPERIENCE !' the three units at Browns Ferry As discussed in Section 1, This have compiled a significant amount of operating time. amount of service should be enough to identify any piping welds which are not of sufficient quality for their intended service. Once a plant is in operation, any failures would be reported to the Nuclear Regulatory Commission (NRC) as The LER's from Browns Ferry Licensee Event Reports (LER's). , were reviewed looking for any events related to welds or welding.(ECD-6) The results of that review are summarized below. Browns Ferry Unit I went into commercial operation August 1, 1974 and has compiled 59,521 reactor critical hours of operation. During this period, seven LER's related to welding were issued. Three of these events were related Both of to f atigue cracks and two were related to IGSCC. these types of indications are service induced and do not bear any indication of the initial quality of the welds. and no The final two events are linear indications detected, cause was given. As these indications can not be ruled out as being fabrication related, they must be considered to be related to the initial quality of the weld. One of these two indicati.ons was considered acceptable by a later addendum of the ASME Code. Browns Ferry Unit 2 went into commercial operation March 1, Five weld 1975 and has compiled 55,860 hours of operation. Two are fatigue related LER's have been filed with the NRC. cracks and two are intergranular stress corrosion cracking l (IGSCC). The fifth is likely IGSCC, as the indication was noted after induction heat stress improvement (IHSI) and was repaired with a weld overlay. No LER's related to the initial quality of the welds have been issued for this unit. h A
3-2 Browns Ferry Unit 3 went into operation March 1, 1977 and has compiled 45,307 hours of operation. Nine LER's related to welding have been issued for Unit 3. Three of these appear to be IGSCC, one is likely a fatigue failure on a . motor mount and the other five are likely service induced f ailures 'on small instrument lines which are outside the Therefore no LER's related to the scope of this review. initial quality of welding on safety related or structurally significant welds were issued for this unit. All'of the LER's f or Browns Ferry Units 1, 2, and 3 are summarized in Table 3-1. O d l 1
. i s
e S 4
3-3 b Table 3-1 '/ Summary of Licensee Event Reports Related to Welding
\
LER No,_ Docket Unit Comments Linear indication in weld DRWC-1-2, no 80-004 259 1 cause given . 81-037 259 1- Indication on vessel side of primary ' containment isolation valve - 82-020 259 1 Fatigue crack in 0.75 inch test connection . in RWCS 82-056 259 1 Cracked weld in 1.0 inch switch line on ' jet pump riser (fatigue crack) s . 2-099 259 1 Fatigue crack in weld in 0.5 inch samples
' , , s :,
line on core spray system 83-023 259 1 IGSCC in Weld KR-1-37 .
~
83-049 259 1 IGSCC in welds DCS-1-7 and DSRWC-1-3 78-016 260 2 Fatigue crack in 1.0 inch instrument line 82-040 260 2 Cracks in welds KR-2-36 and KR-2-14 appear to be fatigue - analysis requested 83-059 260 2 IGSCC in weld DSHS-3-2 84-008 260 2 IGSCC in recirc piping, cleanup piping and jet pump instrumentation nozzles - 85-001 260 2 Through-wall crack in riser - post IHSI l\ . b $
- n. . . . _ . .
3-4 , s ii -
\ % l i
, x, s l Table 3-1 (continued)
~
LER No. Docket Enit Comments s 78-019 296 3 Broken weld on 1,.0 inch instrument sensing l q line on jet pump riser - design evaluation required, - 79-019 296 3 Suspected IGSCC in weld DCS-3-18
\
\
81-064 (296 I)3 Weld on gas divider broke - no cause given l
, 1 i
.1 83-059 296 3 Suspected I IGSCC in Wald DSHS-3-2 N
84-005 296 s 3 Linear indication in reactor water cleanup system weld after IHSI treatment 84-006 296 3 Cracked welds in jet pump instrumentation *
nozzles l
85-005s 296 ' 3 Cracke1 weld on 0.75 inch test connection ! line 85-009 296 3 Cracked weld on pump motor surge ring . 85-016 296 3 Pinhole leak in diesel generator fuel line/ filter weld I I 1
.l 4 ,
4-l' 4.0
SUMMARY
, CONCLUSIONS AND RECOMMENDATIONS The welding and quality programs at Browns Ferry Nuclear Plant were evaluated by a quality audit performed by Bechtel Power Corporation. No significant problems related to weld quality were found in that audit, althoughasseveral well as recommendations for improvement were provided, recommendations required to evaluate the impact of the audit findings. The results of the preservice and inservice inspections through five cycles have been reviewed to aid in the determination of the quality of the piping a..d structurally That significan welds at Browns Ferry Nuclear Plant. review showed that piping welds made by TVA had similar iuication rates as shop welds made by other fabricators and the welds meet a 95% reliability /954 confidence limit. This means that the welds made by TVA at Browns Ferry are cu parable to industry standards in quality. The indication Idt* for all types of supports, especially integrally V91ded al.tuchments exceeds the industry standard acceptance level of 95% reliability with 95% confidence. Based upon the program flow chart shown in Figure 1-1 and the position taken by the NRC on the question of the quality of welds at Sequoyah we conclude that no additional inspecticn is required at this time to ensure confidence in the qual'.ty of piping welds, but additional inspection may be required tn provide the confidence level required for supports.
s reinsoection should be performed in conj unct ' - ,:.th t'- '.<'. sting ISI program because the indic. ati: 2' ie s :s is not significantly greater
' s 'n the industry and because the than t h .' t.
- i i
r plant has
- c ~r ' No hours of operation without any demonstrateC wwe v *y induced problems.
These facts
j 1 4-2
)
'ustify the continued operation until the welds are ! reinspected over the next inspection interval. An additional recommendation, which is based on a review of ; inspection procedures at TVA and on experience gained from other plants, is that supports and hangers should be examined for such attributes as configuration and missing welds. This reinspection should be performed in conjunction with the existing ISI program by augmenting the existing procedures to facilitate detection of configuration defects as well as service induced damage. Once configuration has been verified for a given component, that acpect can be deleted from the ISI program plan for future inspections of that component. In order to ensure the proper disposition of the indication on weld RCRD-3-43 during cycle 2, this weld should be reinspected or a further search of the records should be ~ made to verify that the indication was properly closed out. If reinspection is selected as the corrective action, the reinspection should be performed under the ongoing ISI program, as is the case with the configuration examination of supports and integral attachments. a i
) !
j 7 e
1 5-l ' ( 5.0 EXTERNALLY GENERATED CONTROLLED DOCUMENTS USED 1 ECD-2 Sarveillance Instmetions SI 4.6.G (date of latest ' revision 02/08/85). ECD-5 Browns Ferry Nuclear Plant Wald Data Summary (dated j 09/09/86). ECD-6 Licensee Event Report Batch Search (dated 03/13/86). ECD-10 Browns Ferry Nuclear Power Plant NDE Inspection Data, Unit 2 (dated 12/12/86) . . .f s 1
- a. -
v - w, - - w A-1 s APPENDIX A PSI AND ISI INSP2CTION DATABASE s ,
.l h 1
s
f l l k. I i KEY TO SYSTEM ABBREVIATIONS USED IN DATABASE AS = AUXILIARY STEAM CCW = CLOSED COOLING WATER CRD = CONTROL ROD DRIVE CS = CORE SPRAY FW = FEEDWATFJL _ HPCI = HIGH PRESSURE COOLANT INJFCTION HS = READ SPRAY MS = MAIN STEAM R = RECIRCULATION RCIC = REACTOR CORE ISOLATION COOLING
,. RHR = RESIDUAL HEAT REMOVAL k RWC = REACTOR WATER CLEANUP KEY TO NDE ABBREVIATIONS USED IN DATABASE UTO = ULTRASONIC O DEGREE WAVE UT45 = ULTRASONIC 45 DEGREE WAVE VT = VISUAL TESTING PT = PENETRANT TESTING RT = RADIOGRAPHY ,
( I
l l KEY TO DETERMINING FABRICATOR FROM WELD NUMBER Weld number Fabricator CRDxxx TVA Dxxx (except DSxxx) TVA DSxxx Dravo FMxxx TVA Gxxx TVA HPCIxxx TVA Kxxx Kellogg MX-TEE TVA RCICxxx TVA RCRDxxx TVA RWCUxxx TVA Txxx TVA 3-RNR-xxx TVA xxx implies any combination of letters and numbers .) i I l 1
- )
a
. Papa 1 BROWNS FERRY NUCLEAR PLANT 07 /02 /67 INSPECTION RESULTS
( F O SYSTEM: FW 1 % UNIT 1 CYCLE I NDE INDICATIONS WELD NO. UTO GFW-1-1 UT45 GFW-1-1 UT70 GFW-1-1 UTO KFW 1 UT45 KFW 1 UT70 KFW-1-1 UTO GFW-1-2 UT45 GFW-1-2 UT70 GFW 2 UTO GFW-1-3 UT45 GFW-1-3 UT70 GFW-1-3 UTO GFW-1-4 UT45 GFW-1-4 UT70 GFW-1-4 UTO KFW-1-5 UT45 KFW-1-5 KFW-1-5 0T70 UTO GFW-1-5 GFW-1-5 0745 ' GFW-1-5 UT70 UTO i KFW-1-7 KFW-1-7 UT45 KFW-1-7 UT70 UTO KFW-1-8 KFW-1-8 UT45 KFW-1-8 UT70 UTO GFW-1-6 GFW-1-6 UT45 GFW-1-6 UT70 GFW-1-7 UTO GFW-1-7 0T45 GFW-1-7 UT70 KFW-1-9 UTO KFW-1-9 UT45 KFW-1-9 UT7 0 KFW 10 UTO KFW-1-10 UT45 KFW-1-10 UT70 GFW-1-8A UTO GFW-1-8A UT45 GFW-1-8A UT70 KFW 11 UTO KFW-1-11 UT45 KFW-1-11 UT70 j MFW-1-12 UTO ! KFW-1-12 UT45 KFW-1-12 UT70 ( GFW-1-8 UTO GFW-1-8 UT45
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}
Paga 2 BROWNS FERRY NUCLEAR PL' ANT INSPECTION RESULTS , , 07 /02 /8-UNIT 1 CYCLE O SYSTEM: FW WELD NO. NDE INDICATIONS {) GFW-1-8 UT70 KFW-1-13 UTO KFW 13 UT45 KFW-1-13 UT70 GFW-1-9 UTO GFW-1-9 UT45 GFW-1-9 UT70 GFW-1-10 UTO GFW-1-10 UT45 GFW-1-10 UT70 KFW-1-14 UTO KFW-1-14 UT45 KFW-1-14 UT70 KFW-1-15 UTO KFW-1-15 UT45 KFW-1-15 UT70 GFW-1-11 UTO GFW-1-11 UT45 GFW-1-11 UT70 GFW-1-12 UTO GFW-1-12 0745 GFW-1-12 UT70 GFW-1-13 UTO GFW 13 UT45 GFW 13 UT70 ,; KFW-1-16 UTO KFW-1-16 UT45 KFW-1-16 UT70 KFW-1-17 UTO KFW 17 UT45 KFW-1-17 UT70 GFW-1-14 UTO GFW-1-14 UT45 GFW-1-14 UT70 GFW-1-15 UTO GFW 15 UT45 GFW-1-15 UT70 KFW-1-32 UTO KFW-1-32 UT45 KFW-1-32 UT70 KFW-1-33 UTO KFW-1-33 UT45 KFW-1-33 UT70 GFW-1-28 UTO { GFW-1-28 UT45 GFW-1-28 UT70 KFW-1-39 UTO KFW-1-39 UT45 . KFW-1-39 UT70 GFW-1 16 UTO f' 3 l 1 1
Page 3 BROWHS FERRY NUCLEAR PLdNT INSPECTION RESULTS . 07 /02/87 UNIT 1 CYCLE O SYSTEM: FW WELD NO. NDE INDICATIONS GFW-1-16 0745 GFW-1-16 UT70 KFW-1-18 UTO KFW-1-18 UT45 KFW-1-18 U770 KFW 19 UTO KF W 19 UT45 KFW-1-19 UT70 GFW 17 UTO GF W 17 UT45 GFW 17 UT70 KFW-1-3 UTO KFW-1-3 UT45 UTO GFW-1-18 GFW-1-1* UT45 KFW- 1-21 UTO KFW-1-21 0745 GFW 19 UTO GFW-1-19 0745 GFW-1-20 UTO GFW-1-20 UT45 I-GFW-1-21 UTO GFW-1-21 0745 KFW-1-23 UTO KFW-1-23 0T45 GFW-1-22 UTO , GFW-1-22 0745 KFW-1-24 UTO KFW-1-24 UT45 KFW-1-25 UTO KFW-1-25 UT45 KFW-1-26 UTO KFW-1-26 UT45 GFW-1-23 UTO ' GFW-1-23 UT45 GFW-1-24 UTO GFW-1-24 UT45 GFW-1-32 UTO GFW-1-32 UT45 l KFW-1-38 UTO ' KFW-1-38 UT45 GFW-1-33 UTO GFW-1-33 UT45 KFW-1-36 GTO KFW-1-36 UT45 KFW-1-37 UTO KFW-1-37 UT45 ( GFW-1-34 UT0 GFW-1-34 UT45 KFW-1-27 UTO
_ - . . . . . ~ ~ m . . BROWNe FERRY NUCLEAR PLANT Pago 4 INSPECTION RESULTS ,, 0~ /02 /87 UNIT 1 CYCLE 0 SYSTEM: FW INDICATIONS WELD NO. HDE
})
KFW-1-27 UT45 KFW-1-28 UTO KFW-1-28 UT45 KFW-1-29 UTO KFW-1-29 UT45 GFW-1-29 UTO GFW-1-29 UT45 GFW-1-30 UTO GFW-1-30 UT45 KFW-1-34 UTO KFW-1-34 UT45 KFW-1-35 UTO KFW-1-36 UT45 GFW-1-31 UTO GFW-1-31 UT45 KFW-1-30 UTO KFW-1-30 UT45 GFW-1-35 UTO . GFW-1-35 0745 KFW-1-31 UTO KFW-1-31 UT45 GFW-1-26 UTO GFW-1-26 UT45 GFW-1-27 UTO GFW-1-27 UT45 '. s NO. OF INSPECTIONS: 175 l l l l l l l
,__,. . a
Page. 5 BROWHS FERRY NUCLEAR PLANT 07 /02/8-INSPECTION RESULTS ,, (' UNIT 1 CYCLE O SYSTEM: HPCI . WELD N0. NDE INDICATIONS THPC I 148 UTO T HPC I 148 UT45 THPC I 149 UTO THPC I 149 UT45 THPC I 150 UTO THPCI-1-150 UT45 THPCI-1-151A UTO THPC I 151 A UT45 THPC I 151 UTO THPC I 151 UT45 THPOI 152 UTO THPC I 152 UT45 THPCI-1-153B UTO
~
THPCI-1-153B UT45 THPCI 153 A UTO THPC I 153 A UT45 THPC I 153 UTO THPC I 153 UT45 THPC I 154 UTO THPC I 154 UT45
- THPC I 155 UTO I. THPCI-1-155 UT45 THPC I 156 UTO
- THPC I 156 UT45 THPC I 157 UTO THPC I 157 UT45 THPCI-1-158 UTO THPC I 158 UT45 THPC I 160 UTO THPCI-1-160 UT45 THPCI-1-5 UTO THPCI-1-5 UT45 THPCI-1-4 UTO THPCI-1-4 UT45 THPCI-1-3 UTO THPCI-1-3 UT45 THPC I 1 UTO
- THPC I 1 UT45 No 0F INSPECTIONS: 38
(
.....s, ..
BROWNS FERRY NUCLEAR PLANT Page 6 INSPECTION RESULTS .. 07 /02 /P.7 UNIT 1 CYCLE 0 SYSTEM: MS WELD NO. HDE INDICATIONS g DHS-1-6 UTC DHS-1-6 UT45 t DSHS-1-19 UTO ', DS HS 19 UT45 r DSHS-1-18 UT0 } DS HS 18 0745 DS HS 17 UTO l DS HS 17 UT45 DHS-1-5 UTO DHS-1-5 UT45 DHS-t-4 UTO DHS-1-4 UT45 DSHS-1-16 UTO DSHS-1-16 UT45 DS HS 15 UTO
, DS HS 15 UT45 DSHS-1-14 UTO DSHS-1-14 UT45 DS HS 13 UTO
'DSHS-1-13 UT45 DSHS-1-12 UTO DSHS-1-12 UT45 DS HS 11 UTO DSHS-1-11 UT45 DSHS-1-10 UTO '
DS HS 10 UT45 l DSHS-1-9 UTO DSHS-1-9 UT45 DFS- 1-3 UTO DHS-1-3 UT45 DSHS-1-8 UTO DSHS-1-8 UT45 DSHS-1-7 UTO DSHS-1-7 UT45 DSHS-1-6 UTO DSHS-1-6 UT45 DHS-1-2 UTO DHS-1-2 UT45 DSHS-1-5 UTO DS HS 5 UT45 DSHS-1-4 UTO DSHS-1-4 UT46 DSHS-1-3 UTO DSHS-1-3 UT45 DSHS-1-2 UTO DS HS- 1-2 UT45 DSHS-1-1 UTO DSHS-1-1 j UT45 ' DSHS-1-1A UTO DSHS 1 A UT45 l l
- .. -. --~ ... . . - . . . . _ . - . . ~ . . . - . . -.--..-.. .-.-. . - - . -
': e BROWNS FERRY NUCLEAR' PLANT.
.Page 7 l i
INSPECTION RESULTS -
-07 /02/6? t i
l ( UNIT 1- CYCLE O SYSTEM: 'HS -t WELD NO. NDE INDICATIONS DHS 1 UTO !- DHS-1-1 0745 ,
- j. i NO. OF INSPECTIONS: 52 I
r k
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r h r l1 - i - 1 I i t . i + , , P n om 1 i e i i 1 i
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, -. ,,,--+,,x-- - - - , v., , , , . . - - - - , , - - , , , - - - - - -.,
. ,.,-. ,,.--,i-,, e n r- ,,,---,n---,.,.n,-A,.w,-- ,,N Amem ~ ~ , , , -
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l BROWNS FERRY NUCLEAR PLANT Page. 6 INSPECTION RESULTS ,,
-07 /02/87 UNIT 1 CYCLE O SYS7?M: CRD WELD NO. NDE INDICATIONS )
RCRD 19 UTO RCF D 19 UT45 I RC R D- 1-20 UTO i RCRD- 1-20 UT45 RCRD- 1-21 UTO , RCBD-1-21 UT45 RCRD-1-22 UTO RCRD-1-22 UT45 RCBD-1-23 UTO RCBD-1-23 UT45 RCR D 24 UTO RCRD-1-24 UT45 RCR D- 1-25 UTO RCRD-1-25 UT45 BCRD-1-26 UTO l RCRD- 1-26 UT45 i RCRD-1-28 UTO I RCRD- 1-28 UT45 l RCRD-1-29 UTO RCRD- 1-29 UT45 l RCRD-1-30 UTO ) RCRD-1-30 UT45 RCR D 31 UTO RCRD 31 UT45 . l RCRD-1-32 UTO ^ J l RCRD-1-32 UT45 l RCRD-1-33 UTO ! BCRD-1-33 UT45 No. OF INSPECTIONS: 28 l i l l I 1 I
Page 9 BROWNS FERRY NUCLEAR PLANT INSPECTION RESULTS ,
'07/03/37 k-- UNIT 1 CYCLE O SYSTEM: CS WELD NO. HDE IND! CATIONS DCS 13 UTO DCS 13 UT45 DSCS-1-7 UTO DSCS-1-7 UT45 DSCS-1-8 UTO DSCS-1-8 UT45 DSCS-1-9 UTO DSCS-1-9 UT45 DCS-1-14 UTO DCS 14 UT45 DCS 15 UTO DCS 15 UT45 DSCS-1-10 UTO DSCS 10 UT45 DSCS-1-11 UTO DS CS 11 UT45 DSCS-1-12 UTO DSCS-1-12 UT45 DCS-1-16 UTO DCS-1-16 UT45 DCS-1-17 UTO DCS-1-17 UT45
( DSCS 1-13 UTO DSCS 13 UT45 DCS 18 UTO DOS-1-18 UT45 DCS-1-4 UTO DCS-1-4 UT45 UTO DS CS 1 DSCS 1 UT45 DSCS-1-2 UTO DSCS-1-2 UT45 DCS-1-5 UTO DCS-1-5 UT45 d DCS-1-6 UTO DCS-1-6 UT45 DSCS-1-3 UTO DSCS-1-3 UT45 DSCS-1-4 UTO DSCS-1-4 UT45 DSCS-1-5 UTO DSCS-1-5 UT45 DCS- 1 -7 UTO DCS-1-7 UT45 DCS-1-8 UTO DCE-1-8 UT45 DSCS-1-6 UTO DSCS-1-6 UT45
- i. DCS-1-9 UTO DCS-1-9 UT45 No. OF INSPECTIONS: 50
. . m . ,
BF0WNS FERRY NUCLEAR PLANT- Paae 10 TNSPECT10N.RESULTS ,. 07 /02 /F.- UNIT 1 CYCLE O SYSTEM: MS WELD NO. NDE INDICATIONS }; GMS-1-8 UTO i GMS-1-8 UT45 KMS-1-28 UTO KMS-1-28 UT45 KMS-1-27 UTO KMS-1-27 UT45 GMS- 1-7 UTO GMS-1-7 0745 GMS-1-6 UTO l-GMS-1-6 UT45 KMS-1-24 UTO KMS-1-24 0T45 KMS-1-21 UTO KMS-1-21 UT45 KMS-1-22 UTO KMS-1-22 UT45 KMS-1-23 UTO KMS-1-23 UT45 KMS-1-18 UTO KMS-1-18 UT45 KMS-1-19 UTO KMS 19 UT45 KMS-1-20 UTO - KMS-1-20 UT45 UTO 3 KMS-1-15 KMS-1-15 UT45 KMS 16 UTO KMS 16 UT45 KMS 17 UTO KMS 17 UT45 KMS-1-12 UTO KMS 12 UT45 KMS 13 UTO KMS-1-13 UT45 KMS-1-14 UTO KMS 14 UT45 KMS-1-9 UTO KMS-1-9 UT45 KMS-1-10 UTO KMS-1-10 UT45
- KMS-1-11 UTO KMS-1-11 UT45 KMS-1-6 UTO KMS-1-6 UT45 KMS-1-7 UTO KMS-1-7 UT45
- KMS-1-8 UTO 4
KMS-1-8 UT45
- KMS-1-3 UTO KMS-1-3 UT45 I
I 1 4 i a J A l } -_
Pege 11 BROWNS FERRY NUCLEAR PLANT 07 /02/87 INSPECTION RESULTS ,, UNIT 1 CYCLE O SYSTEM: MS WELD NO. NDE INDICATIONS KMS-1-4 UTO KMS- 1-4 UT45 KMS-1-5 UTO KMS-1-5 UT45 KMS-1-25 UTO KMS-1-25 UT45 KMS-1-2 UTO KMS-1-2 UT45 KMS-1-26 UTO KMS-1-26 UT45 GMS-1-5 UTO GMS-1-5 UT45 GMS-1-4 UTO GMS-1-3 UTO GMS-1-3 UT45 GMS-1-2 UTO GMS-1-2 UT45 GMS-1-1 UTO GMS-1-1 0745 GMS-1-34 UTO GMS-1-34 UT45 KMS-1-108 UTO ( KMS-1-108 UT45 MMS 10~ UTO KMS 107 0745 GMS-1-33 UTO GMS-1-33 UT45 GMS- 1-32 UTO GMS-1-32 UT45 KMS-1-104 UTO KMS-1-104 UT45 KMS-1-101 UTO KMS-1-101 UT45 KMS-1-102 UTO KMS-1-102 UT45 KMS-1-103 UTO KMS-1-103 UT45 KMS-1-98 UTO KMS-1-98 0745 KMS-1-99 UTO KMS-1-99 UT45 KMS-1-100 UTO KMS-1-100 0745 KMS-1-95 UTO i KMS-1-95 UT45 KMS-1-96 UTO UT45 4 KMS-1-96 UTC { KMS-1-97 l i KMS 97 UT45 UTO 1 KMS-1-92
. . . . . m._... .., .
BROWNS FERRY NUCLEAR PLANT Pega 12 INSPECTION RESULTS ,_ 07 /02/8" UNIT 1 CYCLE O SYSTEM: MS WELD N0. NDE INDICATIONS KMS-1-92 UT45 5'MS 93 UTO KMS-1-93 UT45 KMS-1-94 UTO ' KMS-1-94 UT45 KMS-1-89 UTO KMS-1-89 UT45 KMS-1-90 UTO KMS-1-90 0745 EMS-1-91 UTO KMS-1-91 UT45 KMS-1-86 UTO KMS-1-86 UT45 KMS-1-87 UTO KMS-1-87 UT45 KMS-1-88 UTO KMS-1-88 UT45 KMS-1-83 UTO KMS-1-83 UT45 KMS-1-84 UTO KMS-1-84 UT45 KMS-1-85 UTO KMG-1-85 UT45 KMS-1-15 UTO - - KMS-1-15 UT45 l# KMS-1-82 UTO KMS-1-82 UT45 KMS-1-106 UTO KMS-1-100 UT45 GMS-1-31 UTO GMS-1-31 UT45 GMS-1-30 UTO GMS-1-30 UT45 KMS-1-81 UTO , KMS-1-81 UT45 GMS-1-29 UTO , GMS-1-29 UT45 GMS-1-28 UTO GMS-1-28 UT45 GMS-1-27 UTO GMS-1-27 UT45 GMS 1.' UTO GMS-1-17 UT45 KMS-1-55 UTO KMS-1-55 UT45 KMS-1-54 UTO KMS-1-54 UT45 GMS-1-16 UTO GMS-1-16 UT45 GMS-1-15 UTO 1
Pcga 13 07 /02/87 BROWNS FERRY NUCLEAR PLANT ,,
, INSPECTION RESULTS
(, SYSTEM: MS CYCLE O UNIT 1 NDE INDIC ATIONS WELD NO. UT45 GMS-1-15 UTO GMG-1-14 UT45 GMS-1-14 UTO KMS-1-40 UT45 KMS-1-40 UTO KMS-1-41 0745 KMS-1-41 UTO KMS-1-42 UT45 KMS-1-42 UTO KMS-1-43 UT45 KMS-1-43 UTO KMS-1-44 UT45 KMS-1-44 UTO KMS-1-45 UT45 KMS-1-45 070 KMS-1-53 UT45 KMS-1-53 UTO KMS-1-46 UT45 KMS-1-46 UTO KMS-1-47 UT45
- KMS-1-47 UTO KMS-1-48 0745 KMS-1-48 UTO KMS-1-49 0745 KMS-1-49 UTO KMS-1-50 UT45 KMS-1-50 UTO
- Ki!S 51 0745 KMS-1-51 UTO KMS-1-52 UT45 KMS-1-52 UTO KMS-1-38 0T45 KMS-1-38 UTO KMS-1-35 UT45 KMS-1-35 UTO KMS-1-36 0745 KMS-1-36 UTO KMS-1-37 ,
UT45 KMS-1-37 UTO KMS-1-32 UT45 KMS-1-32 UTO KMS-1-33 UT45 KMS-1-33 UTO l KMS-1-34 0745 l KMS 3 4 UTO l KMS- 1-31 UT45 1 KMS-1-31 UTO l (' GMS 13 UT45 I l GMS 13 UTO GMS-1-12 l
. . ~ . . . .. , , .
Peas 14 BROWNS FERRY NUCLEAR PLANT 07 /02/87 INSPECTION RESULTS ,, CYCLE 0 SYSTEM: MS 11 NIT 1 WELD NO. NDE INDICATIONS
.. }
CMS-1-12 UT45 KMS '-30 UTO KMS-1-30 UT45 j UTO GMS-1-11 GMS-1-11 UT45 GMS-1-10 UTO l GMS-1-10 UT45
- l. GMS-1-9 UTO GM5 9 UT45 GMS-1-26 UTO GMS-1-26 UT45 KMS-1-80 UTO KMS-1-80 UT45 KMS-1-79 UTO KMS-1-79 UT45 GMS-1-25 UTO GMS-1-25 UT45 KMS-1-78 UTO KMS-1-78 UT45 KMS-1-77 UTO KMS-1-77 UT45 GMS-1-24 UTO GMS-1-24 UT45 GMS-1-23 UTO GMS-1-23 UT45 ,,
KMS-1-64 UTO KMS-1-64 UT45 KMS-1-05 UTO KMS-1-65 UT45 KMS-1-66 UTO KMS-1-66 UT45 KMS-1-67 UTO KMS-1-67 UT45 KMS-1-68 UTO KMS-1-68 UT45 KMS-1-69 UTO KMS-1-69 UT45 KMS-1-70 UTO KMS-1-70 UT45 KMS- 1-71 UTO KMS- 1-71 UT45 KMS-1-72 UTO KMS-1-72 UT45 J KMS-1-73 UTO j KMS-1-73 UT45 KMS-1-74 UTO KMS-1-74 UT45 KMS-1-75 UTO KMS-1-75 UT45 KMS-1-76 UTO
)
)
l Page 15 BROWHS FERRY NUCLEAR PLANT 07 /02/87 INSPECTION RESULTS ._ g MS CYCLE O SYSTEM: UNIT 1 NDE INDICATIONS WELD NO. UT45 KMS-1-76 UTO KMS-1-62 UT45 KMS-1-62 UTO KMS-1-63 ' UT45 XMS-1-63 UTO KMS-1-61 UT45 KMS-1-61 UTO KMS-1-60 KMS-1-60 UT45 UTO KMS-1-59 KMS-1-59 UT45 KMS-1-58 UTO KMS-1-58 UT45 GMS-1-22 UTO GMS-1-22 UT45 GMS-1-21 UTO GMS-1-21 UT45 KMS-1-57 UTO KMS-1-57 UT45 KMS-1-56 UTO KMS-1-56 UT45 g UTO GMS-1-20 GMS-1-20 UT45 UTO GMS-1-19 GMS-1-19 UT45 UTO GMS-1-18 GMS 18 UT45 NO. OF INSPECTIONS: 277 sq
..- ~.v.. ~, v s s BROWNS FERRY NUCLEAR PLANT Pcas 16 INSPECTION RESULTS ,,
07/02/87 UNIT 1 CYCLE 0 SYSTEM: R HDE INDICATIONS g WELD NO. ,J GR-1-53 UTO GR-1-53 UT45-KB-1-45 UTO KR-1-45 UT45 GR-1-54 UTO GR-1-54 UT45 GR-1-55 UTO GR-1-55 UT45 KR-1-46 UTO KR-1-46 UT45 KR-1-47 UTO KR-1-47 UT45 GR-1-56 UTO GR-1-56 UT45 GR-1-51 UTO GB-1-57 UT45 KR-1-49 UTO KR-1-49 UT45 KR-1-48 UTO < KR-1-48 UT45 GR-1-58 UTO GR-1-58 UT45 GR-1-1 UTO 08-1-1 UT45 GR-1-2 UTO :./ . GR-1-2 UT45 GR-1-3 UTO GR-1-3 UT45 KR-1-2 UTO KR-1-2 UT45 KR-1-55 UTO KR-1-55 UT45 GR-1-65 UTO GR-1-65 UT45 1 KR-1-1 UTO KR-1-1 UT45 GR-1-4 UTO GR-1-4 UT45 KR-1-5 UTO KR-1-5 UT45 KR-1-6 UTO KR-1-6 UT45 l KR-1-7 UTO l KR-1-7 UT45 l KR-1-8 UTO UT45 ; KR-1-8 GR-1-5 UTO GR-1-5 UT45 GR-1-6 UTO GR-1-6 UT45 I
Pero 17 BROWNS FERRY NUCLEAR PLANT 07/02/87 INSPECTION RESULTS ,, SYSTEM: R UNIT 1 CYCLE O NDE INDICATIONS WELD NO. KR-1-9 UTO KR-1-9 UT45 UTO KR-1-10 KR-1-10 UT45 GR-1-7 UTO GR-1-7 0T45 UTO KR-1-4 KR-1-4 UT45 KR-1-3 UTO KR-1-3 UT45 GR-1-8 UTO GR-1-8 UT45 KR-1-12 UTO KR-1-12 UT45 KR-1-15 UTO KR-1-15 UT45 KR-1-14 000 KR-1-14 UT45 GR-1-9 UTO GR-1-9 UT45 GR-1-10 UTO GR-1-10 UT45 {, KR-1-16 UTO KF-1-16 UT4b GR-1-11 UTO GR-1-11 UT45 KR-1-13 UTO KR-1-13 UT45 GR-1-12 UTO GR-1-12 UT45 i GR-1-13 UTO GR-1-13 UT45 ; KR-1-17 UTO ) KR 17 UT45 GR-1-14 UTO GR-1-14 UT45 KR-1-11 UTO KR 11 UT45 GR 15 UTO GR-1-15 UT45 GR-1-16 UTO ; GR 16 UT45 KR 18 UTO l KR 18 UT45 l GR 17 UTO l GR 17 UT45 l GR-1-18 UTO , l GR-1-18 UT45 KP-1-19 UTO 1 KR 19 UT45
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Page 18 BROWNS FERRY NUCLEAR PLANT 07/02/87 INSPECTION RESULTS __ UNIT 1 . CYCLE O SYSTEM: R WELD NO. NDE INDICATIONS y GR 19 UTO GR-1-19 UT45 GR-1-20 UTO GR-1-20 UT45 KR-1-21 UTO KR-1-21 UT45 GR-1-21 UTO GR-1-21 UT45 KR-1-20 UTO KR-1-20 UT45 GR-1-22 UTO GR-1-22 UT45 GR-1-23 UTO GR-1-23 UT45 KR-1-22 UTO KR-1-22 UT45 GR-1-24 UTO GR-1-24 UT45 GR-1-25 UTO GR-1-25 UT45 GR-1-26 UTO GR-1-26 UT45 GR-1-59 UTO GR-1-59 UT45 KR-1-50 UTO ' KR-1-50 UT45 GR-1-60 UTO GR-1-60 UT45 GR-1-61 UTO GR-1-61 UT45 KR-1-51 UTO KR- 1-51 UT45 GR-1-62 UTO GR-1-62 UT45 GR-1-63 UTO GB-1-63 UT45 ' GR-1-63B UTO UT45 l GR-1-63B KR-1-53 UTO KR-1-53 UT45 l GR-1-63A UTO GB-1-63A UT45 l KR-1-52 UTO KR-1-52 UT45
- GR-1-64 UTO GR-1-64 UT45
, GR-1-27 UTO GR-1-27 UT45 GR-1-28 UTO GR-1-28 UT45
)
i
Peas 19 BROWNS FERRY NUCLEAR PLANT 07 /02/87 INSPECTION RESULTS , ,
~
0 SYSTEM: R UNIT 1 CYCLE HDE INDICATIONS WELD NO. UTO GR-1-29 GR-1-29 UT45 UTO KR-1-24 UT45 KR-1-24 KR-1-54 UTO UT45 KR-1-54 GR-1-66 UTO UT45 GR-1-66 KR-1-23 UTO UT45 KR-1-23 GR-1-30 UTO GR-1-30 UT45 UTO KR-1-27 KR-1-27 UT45 KR-1-28 UTO KB-1-28 UT45 KR-1-29 UTO KR-1-29 UT45 KR-1-30 UTO KR-1-30 UT45 GR-1-31 UTO (~ GR-1-31 UT45 UTO GR-1-32 GR-1-32 UT45 KR-1-31 UTO KR 31 UT45 KR-1-32 UTO KR-1-32 UT45 GR-1-33 UTO GR-1-33 UT45 KR-1-26 UTO KR-1-26 UT45 KR-1-25 UTO KR- 1-25 UT45 GR-1-54 UTO GR-1-34 UT45 GR-1-44 UTO CR-1-44 UT45 GR-1-51 UTO GR-1-51 UT45 GR-1-52 UTO GR-1-52 UT45 KR-1-42 UTO KR-1-42 UT45 GR-1-48 UTO GR-1-4' UT45 GR-1-49 UTO GR-1-49 UT45 (, UTO KR-1-44 KR-1-44 UT45 OM8 4 , e , ,
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BROWHS FERRY NUCLEAR PLANT Pago 20 INSPECTION RESULTS 07/02/87 UNIT 1 CYCLE O SYSTEM: R WELD NO. NDE INDICATIONS GR-1-50 UTO GR-1-50 UT45 KR-1-41 UTO KR-1-41 UT45 GR-1-45 UTO GR-1-45 UT45 GR-1-46 UTO GR-1-46 UT45 KR-1-43 UTO KR-1-43 UT45 GR-1-47 UTO GR-1-47 UT45 3 KR-1-33 UTO KR-1-J3 Uf45 GR-1-41 UTO GR-1-41 UT45 GR-1-42 UTO GR-1-42 UT45 KR-1-40 UTO KR-1-40 UT45 GR-1-43 UTO GR-1-43 UT45 KR-1-34 UTO KR-1-34 UT45 KR-1-35 UTO KR-1-35 UT45 i GR-1-38 UTO GR-1-38 UT45 GR-1-39 UTO GR-1-39 UT45 KR-1-39 UTO KR-1-39 UT45 GR-1-40 UTO GR-1-40 UT45 - KR-1-36 UTO KR-1-36 UT45 GR-1-35 UTO GR-1-35 UT45 GR-1-36 UTO GR-1-36 UT45 KR-1-38 UTO KR-1-38 UT45 GR-1-37 UTO GR-1-37 UT45 KR-1-37 UTO KR-1-37 UT45 NO. OF INSPECTIONS: 246
)
Pags 21 BROWNS FERRY NUCLEAR PLANT 07 /02/67 INSPECTION RESULTS ,, RCIC (- UNIT 1 CYCLE 0 SYSTEM: WELD NO. HDE INDICATIONS TRCIC-1-5 UTO TRCIC-1-5 0745 , TRCIC-1-4 UTO TRCIC-1-4 UT45 TRCIC-1-3 UTO TRCIC-1-3 UT45 TRCIC-1-3A UTO TRCIC-1-3A 0T45 TRCIC-1-2 UTO TRCIC-1-2 UT45 NO. OF INSPECTIONS: 10 J l l
BROWNS FERRY NUCLEAR PLANT Peas 22 INSPECTION RESULTS , 07/02 /87 UNIT 1 CYCLE O SYSTEM: RHR WELD NO. NDE INDICATIONS g DRHR-1-3 UTO DRHR-1-3 UT45 DRHR-1-4 UTO DRHR-1-4 UT45 DS RHR 1 UTO , DS RHR 1 UT45 - DS RHR- 1-2 UTO DSRHR-1-2 UT45 DRHR-1-5 UTO DRHR-1-5 UT45 DRHR-1-6 UTO DRHR-1-6 UT45 DS RHR 3 UTO DSRHR-1-3 UT45 DSRHR-1-4 UTO DSRHR-1-4 UT45 DSRHR-1-4A UTO DS RHR- 1-4 A UT45 DRHR-1-7 UTO DRHR-1-7 UT45 DRHR-1-8 UTO DRHR-1-8 UT45 DRHR-1-9 UTO DRHR-1-9 UT45 DRHR-1-12 UTO ; DRHR-1-12 UT45 DRHR-1-13 UTO DRHR-1-13 UT45 DSRHR-1-5 UTO DSRHR-1-5 UT45 DSRHR-1-SA UTO DSRHR- 1-S A UT45 DRHR 14 UTO DRHR-1-14 UT45 DRHR-1-15 UTO DRHR-1-15 UT45 DSRHB-1-6 UTO DSRHR-1-6 UT45 DSRHR-1-7 UTO 1 DSRHR-1-7 UT45 DSRHR-1-8A UTO DS RHR- 1-8 A UT45 l DSRHR- 1-8 B UTO DSRHR- 1-8 B UT45 I DRHR-1-16 UTO DRHR-1-16 UT45 DRHR-1-17 UTO DRHR 17 UT45 DRHR-1-18 UTO l DRHR-1-18 UT45
)
Paga 23 BROWNS FERRY NUCLEAR PLANT 07 /02 /87 INSPECTION RESULTS O SYSTEM: RHR UNIT 1 CYCLE NDE INDICATIONS WELD NO. UTO DRHR-1-19 UT45 DRHR-1-19 UTO DSRHR-1-8 UT45 DSRHR-1-8 UTO DSRHR-1-9 UT45 DSRHR-1-9 UTO DRHR-1-20 UT45 DRHR-1-20 UTO DRHR 21 UT45 DRHR-1-21 UTO DSRHR 10 UT45 DSRHR 10 UTO DS RHP 11 UT45 DS RHB 11 UTO DRHR-1-22 UT45 DRHR-1-22 UTO TRHR-1-190 TRHR-1-190 UT45 UTO TRHB-1-191 UT45 TRHR-1-191 UTO TRHR-1-194 UT45 (- TRHR 19 4 UTO TRHR-1-454A TRHh-;-454A UT45 UTO TRHR-1-454D TRHR-1-454D 0745 UTO TRHR-1-454E UT45 TRHR-1-454E UTO TRHR-1-454F UT45 TBHR-1-454F UTO TRHR-1-454G UT45 TRHR-1-454G 82 NO. OF INSPECTIONS: i i
- f i
l Paga 24 BROWNS FERRY NUCLEAR PLANT 07 /02 /87 l INSPECTION RESULTS .. ; UNIT 1 CYCLE 0 SYSTEM: RWC l WELD NO. HDE INDICATIONS i DRWC-1-1B UTO DRWC 1-IB UT45 DRWC-1-1A UTO DRWC-1-1A UT45 DRWC 1 UTO DRWC 1 UT45 DSRWC-1-1 UTO DS RWC 1 UT45 DRWC-1-2 UTO DRWC-1-2 UT45 DRWC-1-3 UTO DRWC-1-3 UT45 DSRWC-1-1A UTO DSRWC-1-1A UT45 DSRWC-1-2 UTO DSRWC-1-2 UT45 DSRWC-1-3 UTO DSRWC-1-3 UT45 DSRWC-1-4 UTO DSRWC-1-4 UT45 DS RWC- 1-5 UTO DSRWC-1-5 UT45 DSRWC-1-6 UTO DSRWC-1-6 UT45 DSRWC-1-7 UTO i DSRWC-1-7 UT45 DRWC-1-4 UTO DRWC-1-4 UT45 DRWC-1-4A UTO DRWC-1-4A UT45 DRWC-1-4E UTO DRWC-1-4E UT45 DRWC-1-59 UTO DRWC-1-59 UT45 DS RWC 11 UTO DSRWC-1-11 UT45 DS RWC 10 UTO DSRWC-1-10 UT45 DSRWC-1-9 UTO UT45 l DSRWC-1-9 ; DS RWC- 1-8 UTO DSRWC-1-8 UT45 l DRWC-1-61 UTO DRWC-1-61 UT45 DRWC-1-60 UTO DRWC-1-60 UT45 NO, OF INSPECTIONS: 46 I
4 Pese 25 BROWNS FERRY NUCLEAR PLANT 07/02/87 INSPECTION RESULTS , UNIT 1 CYCLE 1 SYSTEM: CRD I WELD NO, NDE INDICATIONS RCRD-1-33 UTO RCRD 33 UT45 NO. OF INSPECTIONS: 2 l ( r t
Page 26
-BROWNS FEDRY NUCLEAR PLANT 07 /02 /F,7 INSPECTION RESULTS .-
CYCLE SYSTEM: CS UNIT 1 1 WELD NO, NDE INDICATIONS g j DSCS-1-6 UTO UT45 I DSCS-1-6 UTO DCS-1-8 - DCS-1-8 0745
. DCS-1-7 UTO DCS-1-7 UT45 DSCS-1-3 UTO n
e DSCS-1-3 UT45 DSCS-1-4 UTO
< DSCS-1-4 UT45 DCS-1-6 UTO DCS-1-6 UT45 DCS-1-5 UTO DCS-1-5 UT45 1 DSCS-1-2 UTO DSCS-1-2 UT45 DSCS-1-1 UTO DSCS 1 UT45 DCS-1-4 UTO DCS-1-4 UT45 DSCS-1-13 UTO DSCS 13 UT45 DCS-1-17 UTO l
DCS 17 UT45 l DCS-1-16 UTO i DCS-1-16 UT45 , DSCS 12 UTO DSCS 12 UT45 DSCS 11 UTO DSCS 11 UT45 DSCS 10 UTO
. DSCS 10 UT45 DCS-1-15 UTO .
DCS-1-15 UT45 I DCS-1-14 UTO t DCS-1-14 UT45 DSCS-1-9 UTO DSCS-1-9 UT45 ! DSCS-1-8 UTO DSCS-1-8 UT45 DSCS-1-7 UTO DSCS-1-7 UT45 DCS-1-13 UTO DCS-1-13 UT45 DSCS-1-5 UTO DSCS-1-5 UT45 NO. OF INSPECTIONS: 46
Para 27 BROWNS FERRY NUCLEAR PLANT 07 /02/87 INSPECTION RESULTS _ i UNIT 1 CYCLE 2 SYSTEM: CS WELD NO. NDE INDICATIONS DCS-1-4 UT45 DSCS 1 UT45 DSCS-1-2 UT45 DCS-1-5 UT45 DCS-1-6 UT45 DSCS-1-3 UT45 DSCS-1-4 UT45 DSCS-1-5 UT45 DCS-1-7 0745 DCS-1-8 UT45 DSCS-1-6 UT45 DCS-1-13 UT45 DS CS 7 UT45 DSCS-1-8 UT45 DSCS-1-9 UT45 DCS-1-14 UT45 DCS 15 0745 DSCS-1-10 UT45 DSCS-1-11 UT45 DSCS-1-12 UT45 DCS-1-16 UT45 i DCS-1-17 UT45 DSCS-1-13 0745 DCS-1-18 UT45 DCS-1-9 UT45 NO. OF INSPECTIONS: 25 l i g
- ,, ,- x, Pago 28 BROWNS FERRY NUCLEAR PLANT INSPECTION RESULTS G7 /02 /87 UNIT 1 CYCLE 2 SYSTEN: FW WELD NO. HDE UTO INDICATIONS
)
KFW-1-26 KFW-1-26 UT45 KFW-1-9 UTO KFW-1-9 UT45 KFW-1-10 UTO KFW-1-10 UT45 KFW-1-38 UTO KFW-1-38 UT45 GFW-1-29 UTO GFW-1-29 UT45 NO. OF INSPECTIONS: 10 J
l
. I Pcso 29 i BROWNS FERRY NUCLEAR PLANT 07 /02/87 i INSPECTION RESULTS _
UNIT 1 CYCLE 2 SYSTEM: MS ( i I WELD NO. NDE INDICA 1. INS GMS-1-15 UTO l GMS-1-15 UT45 ' GMS-1-24 UTO GMS-1-24 UT45 ' GMS-1-12 UTO I GMS-1-12 UT45 KMS-1-30 UTO KMS-1-30 UT45 i KMS-1-59 UTO ' KMS-1-59 UT45 KMS-1-60 UTO
. KMS-1-60 UT45 KMS-1-36 UTO KMS-1-36 UT45 NO. OF INSPECTIONS: 14-
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Page 30 BROWNS FERRY ~ NUCLEAR PLANT 07/02 /6" INSPECTION RESULTS . , , UNIT 1 CYCLE 2 SYSTEM: R WELD No. NDE INDICATIONS ]) , KR-1-24 UTO KR-1-24 UT45 GR- 1-28 UTO 1 GB-1-28 UT45 ' GR-1-42 UT45 GR-1-49 UTO 'GR-1-49 UT45 GR-1-20 0745 GR 13 UT45 GR-1-43 UT45 GR-1-20 UT45 No. OF INSPECTIONS: 11 J I d
BROWNS FERRY NUCLEAR PLANT Page 33 INSPECTION RESULTS 07 /02/87
, UNIT 1 CYCLE 2 SYSTEM: RHP
( WELD NO. NDE INDICATIONS DSHS-1-14 UTO DSHS 14 UT45 NO. OF INSPECTIONS: 2 i 1 l l r l g l l 1
_g Pcas 32' 5 BROWNS FEBRY NUCLEAR PLANT 07/02 /87 INSPECTION RESULTS ,, CYCLE '3 SYSTEM: CRD UNIT 1 WELD NO. NDE UTO INDICATIONS
)
kCBD-1-45 RCR D 4 3 UTO BCR D 4 4 UTO UTO RCRD 49 RCBDS-1-1 UTO RCBDS-1-2 UTO RCRDS-1-3 UTO RCRDS- 1-3 UT45 RCRD-1-49 0745 UT45 LINEAR IND RCRD-1-48 RCRD-1-47 0745 RCRD-1-46 0745 RCRD-1-45 UT45 RCRD-1-44 0T45 RCRD-1-43 UT45 RCRD-1-48 UT45 LINEAR IND NO. OF INSPECTIONS: 16 i l i i 3
BROWNS FERRY NUCLEAR PLANT Page 33 INSPECTION RESULTS ,, 07/02/87 (- UNIT 1 CYCLE 3 SYSTEM: CS WELD NO. HDE INDICATIONS DCS 18 UT45 DSCS 13 UT45 DCS 17 0745 DCS-1-16 0745 DCS-1-9 UT45 DSCS-1-6 UT45 DCS-1-7 UT45 DSCS-1-5 UT45 DCS-1-8 UT45 DS CS 4 UT45 DSCS-1-3 UT45 DCS-1-6 UT45 DCS-1-5 UT45 DSCS-1-2 UT45 DSCS-1-7 UT45 DSCS-1-8 UT45 DSCS 1 0T45 LINEAR IND DCS-1-4 UT45 DCS-1-6 UT45 DSCS-1-4 UT45 DSCS-1-9 UT45 ( DCS 14 UT45 DCS 15 UT45 DSCS 10 UT45 l DSCS-1-11 UT45 ~ DSCS 12 UT45 ! DCS-1-8 UT45 DCS 17 UT45 DCS 17 UTO DCS 16 UTO DCS 15 UTO DCS 14 UTO DCS-1-5 UTO DCS-1-6 UTO DCS-1-7 UTO DOS-1-8 UTO NO. OF INSPECTIONS: 36 ; l C
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BROWNS FERRY NUCLEAR PLANT Pero 34 07 /02/8~ INSPECTION RESULTS UNIT 1 CYCLE 3 SYSTEM: RWC i WELD NO. NDE INDICATIONS l DRWC 1-1 UT45 ! DS RWC 1 UT45 ; DRWC- 1-2 UT45 GEOMETRY j DRWC-1-3 UT45 f l DSRWC 1-2 UT45 j DSRWC-1-1A UT45
)
DSRWC-1-3 UT45 ' DSRWC-1-4 UT45' DSRWC-A-5 0T45 DSRWC-1-6 UT45 DSRWC-1-7 UT45 ; DRWC-1-4 UT45 i DRWC 1 UTO DRWC-1-P UTO DRWC-1-5 UTO TRWC-1-2 UTO TRWC-1-2 UT45 TRWC-1-1 UTO - TRWC-1-1 UT45 NO. OF IN,3PECTIONS: 19 J b
BROWNS FERRY NUCLEAR PLANT Page 35 INSPECTION RESULTS 07 /00/87 ( UNIT 1 CYCLE 4 SYSTEM: CRD WELD NO. HDE INDICATIONS RCRD-1-40 PT CRD MIX TEE UT45 RCRD-1-3 UTO RCRD-1-44 UTO RCRD-1-45 UTO RCRD-1-3 UT45 CRD MIX TEE UTO RCB D 4 5 UT45 RCRD- 1-4 4 UT45 NO. OF INSPECTIONS: 9 1 l l l T 1 1 3 5 i i l
BROWNS FERRY NUCLEAR PLANT Pass 36 07 /02 /F,7 INSPECTION RESULTS . UNIT 1 CYCLE 4 SYSTEN: CS WELD NO. NDE INDICATIONS j DCS 17 UTO - DCS 15 UTO DCS-1-15-S UTO ' DSCS 10 UTO DSCS-1-11 UTO : DSCS 11 - S UTO DSCS-1-12 UTO DSCS-1-12-S UTO ! DCS 16 UTO ' DCS 18 UTO , DSCS-1-4 UTO t DSCS-1-13-S UTO < DSCS 13 UTO DCS 17 - S UTO , DCS-1-6 UTO ! DSCS-1-3 UTO l DSCS-1-5 UTO DSCS-1-5-S UTO l DCS-1-7 UTO DCS-1-8 UTO , DCS-1-8-S UTO ! DSCS-1-6 UTO DSCS-1-6-S UTO DCS-1-9 UTO
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DCS 16 -S UTO DCS 18 - S UTO DCS-1-9-S UTO DCS 15 UT45 ; DSCS 10 UT45 ' DSCS 16 UT45 DSCS 17 UT45 i 1 DCS 18 UT45 DSCS 12 UT45 DSCS 11 UT45 DSCS-1-13 UT45 l i DCS-1-9 UT45 l DSCS-1-6 UT45 DCS-1-8 UT45 DCS-1-6 UT45 UT45 l DSCS-1-3 DSCS-1-4 UT45 DSCS-1-5 UT45 DCS-1-7 UT45 DCS-1-15 0745 ; DCS 17 UT45 DS CS 13 UT45 DCS-1-7 UT45 DSCS-1-5 UT45 CS-1-H3 PT l CS-1-H6 PT l
BROWNS FERRY NUCLEAR PLANT Page 37 INSPECTION RESULTS , 07 /02/87 (. UNIT 1 CYCLE 4 SYSTEM: CS WELD NO. NDE INDICATIONS CS-1-R8 PT l CS-1-R1 PT ' CS-1-R2 PT CS-1-89 PT ' DSCS-1-6 0T45 NO. OF INSPECTIONS: 55 t j i ( ' i 4 t. l 4 s l l i e l l 1 i i l ) I ' i i i i i i 1
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I BROWNS FERRY NUCLEAR PLANT Pago 38 !t INSPECTION RESULTS 07/02/87 UNIT 1 CYCLE 4 SYSTEM: FW WELD NO. NDE INDICATIONS [k , KFW-1-25 UT45 I KFW-1-26 UT45 i GFW-1-12 UT45 ! f GFW-1-9 0745 ' , KFW-1-15 UT45 ' KFW-1-13 UT45 l GFW-1-26 UT45 l KFW-1-3 UT45 i KFW-1-24 0745 No OF INSPECTIONS: 9 i i i i I i 5 l i f l l l
)
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Peas 39 BROWNS FERRY NDCLEAR PLANT 07/02/87 INSPECTION RESULTS , ,_ ( UNIT 1 CYCLE 4 SYSTEM: HPCI WELD NO. NDE INDICATIONS THPC I 151 UT45 THPC I 153 B 0745 THPC I 1 UT45 THPCI-1-3 UT45 NO. OF INSPECTIONS: 4 I f f I l 6 l
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} -l HS-1-H5 PT !
DSHS-1-13 UTO ! DS HS 12 UTO DSHS-1-11 UTO r HS-1-H4 PT l HS-1-H6 PT HS-1-H1 PT - DSHS-1-13 UT45 ! DSHS-1-12 UT45 DSHS-1-11 UT45 j NO. OF INSPECTIONS: 10 i l l
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i i e BROWNS FERRY NUCLEAR PLANT Page 41 INSPECTION RESULTS 07/00/87 (, UNIT 1 CYCLE 4 SYSTEM: MS WELD NO. NDE INDICATIONS GMS-1-8 UTO GMS-1-8 UTO GMS-1-34 UTO GMS-1-34 UTO KMS-1-108 UTO KMS-1-108 UTO KMS-1-108 UTO KMS 108 UTO GMS-1-8 UT45 GMS-1-34 UT45 KMS 108 UT45 KMS-1-108 UT45 KMS-1-9 PT KMS-1-6 PT 1 KMS-1-3 UT45 KMS-1-21 UT45 KMS-1-22 0745 KMS-1-8 UT45 KMS-1-7 UT45 KMS-1-5 0746 KMS-1-4 UT45 KMS-1-5 UTO ( KMS-1-4 UTO
, KMS-1-7 UTO ! KMS-1-8 UTO KMS- 1-22 UTO GMS-1-6 UT45 GMS-1-30 UT45 GMS-1 30 UT45 KMS-1-63 PT KMS-1-21 UTO ,
KMS-1-3 UTO ' KMS 104 UT45 NO. OF INSPECTIONS: 33 i j
r , Pass 42 BROWNS FERRY NUCLEAR PLANT 07/02/87 INSPECTION RESULTS- , UNIT 1 CYCLE 4 SYSTEM: R NDE INDICATIONS i WELD NO. .) GR-1-50 UTO KR-1-44 UTO KR-1-44 UT45 l GR-1-50 UT45 R-1-H10 PT GR-1-51 UT45 KR-1-42 UT45
- GR-1-51 UT45 GR-1-48 UT45 l
GR-1-45 UT45 R-1-SS3 PT GR-1-51 UTO KR-1-42 UTO GR-1-48 UTO GR-1-45 UTO R-1-H6 PT KR-1-55 PT KR-1-54 PT R-1B-H1 PT GR-1-2 UTO KR-1-54 UT45 KR-1-55 UT45 KR-1-2 UT45 GR-1-2 UT45 R-1B-H1 UT45 R-1-H7 PT i R-1-H2 PT GR-1-7 PT { KR-1-4 PT GR-1-4 PT , GR-1-30 PT GR-1-33 PT l R-1-SS6 PT R-1-H11 PT R-1-H3 PT R-1-SS1 PT l R-1-SS4 PT R-1-H8 PT l R-1-H1 PT R-1-HS PT R-1-H9 PT R-1-SS2 PT k-1-SS5 PT l HO. OF INSPECTIONS: 43 i
i i BROWNS FERRY NUCLEAR PLANT Page 43 INSPECTION RESULTS 07 /02 /87 i UNIT 1 CYCLE 4 ' SYSTEM: RCIC ! t WELD NO. HDE INDICATIONS i TRCIC-1-5 UTO TRCIC-1-5 0745 l NO. OF INSPECTIONS: 2 4 i 4 i 9 i l I 1 1 1 l i 1 i J l i e j i i 1 l l 1
BROWNS FERRY NUCLEAR PLANT Pere 44 INSPECTION RESULTS ,, 07/00/87 UNIT 1 CYCLE 4 SYSTEM: RHR WELD NO. NDE INDICATIONS g RHR-1-H3 PT I DSRHP-1-8A UT45 DS RHR 8 A UT45 DS RHR 8 A UT45 DRHR-1-16 UT45 , DSRHR-1-8 PT DS RHR- 1-8 B UT45 DS RHR- 1-8 B TIT 45 SPOT 60% DAC DRHR-1-16 UTO TRHR 191 UT45 TRHR-1-454G UT45 TRHR-1-454G UTO DFHR-1-16 UTO j TRHR-1-454G PT RHR-1-H7 PT DRHR-1-16 UT45 NO. OF INSPECTIONS: 16 i e I 3 i I l
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Pag? 46 07 /0L /87 BROWNS FERRY NUCLEAR PLANT INSPECTION RESULTS , ( RWC CYCLE 4 SYSTEM: flNIT 1 NDE INDICATIONS WELD NO, l 0745 I T RWC 1 UT45 DRWC-1-3 UT45 DSRWC-1-1A UT45 DRWC-1-4 0745 DSRWC-1-7 UT45 DSRWC-1-5 0745 DSRWC-1-6 UT45 DSRWC-1-4 0745 DSRWC-1-2 UT45 DFWC-1-1 UT45 DRWC-1-1A UTO DFWC-1-1 UTO TRWC 1 UTO TRWC-1-2 UTO DFWC-1-3 UTO DSRWC 1 A UTO DSRWC-1-2 UTO DSRWC-1-3 UTO DSRWC-1-4 UTO DSRWC-1-5 UTO DSRWC-1-6 , ( UTO DSRWC-1-7 UTO DRWC-1-4 UTO DSRWC-1-9 UTO TRWC-1-3 UT45 TRWC-1-3 UT45 ! TRWC-1-2X1 UT45 TRWC-1-4 PT TRWC-1-2XI PT j TRWC-1-4 UTO DRWC-1-1A UT45 DSRWC-1-9 PT 1 TRWC-1-5 33 NO. OF INSPECTIONS: 1 l
BROWNS FEBRY NUCLEAR PLANT Pege 46 07 /00 /p.; INSPECTION RESULT 3 .. IINIT 1 CYCLE 5 SYSTEM: CCW WELD NO. NDE INDICATIONS TCCW-1-1D UT45 NO. OF INSPECTIONS: 1 4 i
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l l BROWNS FERRY NUCLEAR PLANT Pago 47 INSPECTION RESULTS 07/02/87 UNIT 1 CYCLE 5 SYSTEM: CRD ( WELD NO. NDE INDICATIONS TCRD-1-33 UTO TCRD-1-33 UT45 TCR D 3 4 UTO TCRD-1-34 UT45 TCRD-1-35 UTO TCRD- 1-3 5 0745 TCRD-1-36 UTO TCRD 36 UT45 TCRD 37 UTO TC B D 37 UT45 TCRD-1-38 UTO TCRD 38 UT45 TC R D 21 UTO TCRD- 1-21 UT45 TC RD 22 UTO TCRD-1-22 UT45 TCBD-1-23 UTO TCRD-1-23 UT45 TCRD-1-24 UTO TCRD-1-24 UT45 TCBD 2 5 UTO c TCRD-1-25 UT45 TCR D 26 UTO { TC RD 2 6 UT45 TC R D 27 UTO TCR D 27 U145 TCBD 2 9 UTO TC E D 29 UT45 TCBD-1-30 UTO TCRD-1-30 UT45 TC R D 31 UTO TCB D- 1-31 UT45 TC R D- 1-3 2 UTO TCBD-1-32 UT45 TCBD-1-65 UTO TCB D 6 5 UT45 TCRD-1-30 PT RCRDS-1-3 UT45 CRD MIX TEE UTO RCRD-1-45 UT45 RCR D 4 4 UT45 TCRD- 1-7 0 UTO TCED-1-69 UTO TCRD-1-68 UTO TCRD-1-67 UTO TCRD-1-66 UTO TCRD-1-66 UT45 l TCRD-1-25A UTO f' TCBD-1-28 UTO ' I I TCBD-1-9 UT45 l l
BROWNS FERRY NUCLEAR PLANT Page 48 INSPECTION RESULTS 07/02/67 UNIT 1 CYCLE 5 SYSTEM: CRD WELD NO. NDE INDICATIONS J TCRD 12 UT45 TCRD 15 UT45 TCRD 18 UT45 TCRD 18 PT TCRD-1-28 UT45 TCRD 122 UT45 TCRD 121 UT45 TCRD 12 0 UT45 TCRD 119 UT45 TCRD-1-66 PT TCRD-1-67 UT45 TCRD-1-68 UT45 TCRD-1-25A UT45 TCRD-1-69 UT45 TCRD-1-70 UT45 NO, OF INSPECTIONS: 65 I 1 l l 1 1 1 l
Page 51 BROWNS FERRY NUCLEAR PLANT 07 /00 /8" INSPECTION RESULTS , UNIT 1 CYCLE 5 SYSiEM: FW i. WELD NO. NDE INDICATIONS KFW-1-34 UT45 GFW-1-34 UT45 FW-1-SSB1 MT NOI 121 BUILD-UP FW-1-H3 MT FW-1-SSB4 MT FW-1-H3 PT FW-1-SSB1 VT FW-1-SSB4 VT FW-1-SSB1 MT NO. OF INSPECTIONS: 9 I.
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BROWNS FERRY HUCLEAR PLANT Peg 52 INSPECTION RESULTS ,, 07/02/5" UNIT 1 CYCLE 5 SYSTEM: HPCI WELD NO. HDE UT45 INDICATIONS
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THPC I 152
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Page 53 BROWNS FERRY NUCLEAR PLANT 07 /02/87 INSPECTION RESULTS , , (' UNIT 1 CYCLE 5 SYSTEM: HS WELD NO. NDE INDICATIONS DHS-1-5 UT45 DSHS-1-16 UT45 DSHS-1-15 UT45 DHS-1-3 U745 H-109 MT DS HS 1 A PT DHS-1-5 UT45 7 NO. OF INSPECTIONS: f,- ( - - - - . - . _ - . _ _ _ # Er7,-er-- 7,.
BROWNS FERRY NUCLEAR PLANT Page 54 INSPECTf0N RESULTS ,, 07/02/87 UNIT 1 CYCLE 5 SYSTEM: MS I WELD NO. NDE INDICATIONS } l bSAS-10 UT45 l DSAS-6 UT45 GMS-1-6 UT45 KMS-1-104 UT45 ; GMS-1-23 UT45 l HPASH-1-7 MT KMS-1-73 MT KMS-1-43 MT MSGEH 17 MT MS-1-GB1 PT NOI 110 MS-1-GB1 VT CRACKED WELD MS-1-GA1 PT NOI 112 MS-1-GA1 VT CRACKED WELD MS-1-GD1 PT NOI 113 MS-1-GD1 VT CRACKED WELD l MS-1-GC1 PT NOI 114 MS GC 1 VT CRACKED WELD MS-1-SSB1 MT NOI 118 ARC STRIKES GMS-1-8 UT45 DS MS 1 UT45 DSMS-1-28 UT45 DSMS-1-38 UT45 MS-1-SSB4 MT NOI 106 ARC STRIKES MS-1-HC3 MT GMS-1-3 GMS-1-3 PT UT45
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GMS-1-19 UT45 MS-1-SSC6 MT NOI 107 ARC STRIKES MS-1-SSD12 MT NOI 108 ARC STRIKES MS-1-SSC6 MT MS-1-SSD12 MT MS-1-SSB1 MT MS-1-GB1 PT MS-1-GC1 PT MS-1-GD1 PT MS-1-GA1 PT l NO. OF INSPECTIONS: 36
}
BROWNS FERRY NUCLEAR PLANT Page 55 INSPECTION RESULTS ,, 07 /02/S~ UNIT 1 CYCLE 5 SYSTEM: R WELD NO. NDE INDICATIONS KR-1-1 PT GR-1-63A PT KR-1-53 PT KR-1-4 PT GR-1-7 PT GR-1-55 UT45 GR-1-51 UT45 GR-1-52 UT45 KR-1-42 UT45 KB-1-35 UT45 KP-1-41 UT45 KR 19 UT45 KR 13 UT45 GR-1-26 UT45 GR-1-25 UT45 KR 13 UT45 KR-1-3 UTO KR-1-3 UT45 KR-1-3 UT70 KR-1-23 PT GR-1-30 PT g GR-1-60 UT45 KR-1-15 UTO KR 15 UT45 KB 15 UT70 KR-1-36 UTO KR-1-24 UT45 GR-1-33 PT GP-1-8 PT GR-1-8 UT45 GR-1-57 PT GR-1-56 PT P-1-SS5 PT R- 1-558 PT KR-1-26 PT KR-1-49 PT GR-1-4 PT
- R-35-B MT NOI 120 l
NO. OF INSPECTIONS: 38 i l r
BROWNS FERRY NUCLEAR-PLANT Page 56 fHSPECT10N RESULTS ,, 07 /02 /8" UNIT 1 CYCLE 5 SYSTEM: RHR WELD NO. NDE INDICATIONS
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B- 17 MT j R-35-B MT R-50 MT H- 17 MT 1 H- 158 MT H-30 MT , R-12 MT ! H-112 MT I RHR PUMP MT l HOUSING 'IA" MT DSRHR-1-8 PT i TRHR 191 UT45 1 RHR-1-R24 PT j DRHR-1-7 UT45 : TRHR-1-454G UT45 J TRHR-1-454G PT l TRHR-1-369 UT45 1 TRHR-1-372 UT45 l TRHR 17 5 UT45 i TRHR-1-120 UT45 ; DRHR-1-3 PT i TRHR-1-339 UT45 l H-4 MT I I TRHR-1-246 UT45 TRHR-1-359X UT45 TRHR-1-300 UT45 TRHR-1-266 UT45 TRHR-1-375 UT45 TRHR-1-81 UT45 TRHR-1-108 UT45 TRHR-1-313 UT45 TRHR-1-429 UT45 DRHR-1-12 PT DSRHR-1-9 PT DSRER-1-8B UT45 DSRHR-1-4 UT45 DRHR-1-20 UT45 H-52 MT H-109 MT RHRPH-1-A MT HPASH-1-7 MT NO. OF INSPECTIONS: 41
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BROWNS FERRY NUCLEAR PLANT Page 57 INSPECTION RESULTS ,, 07/02/67 ( UNIT 1 CYCLE 5 SYSTEM: RWC WELD NO. NDE INDICATIONS TRWC-1-4 PT TRWC-1-2X1 PT DRWC-1-4 UT45 TRWC-1-1 UT45 TRWC-1-2X1 UT45 TRWC-1-4 UT45 DSRWC-1-1A UT45 DSRWC-1-2 UT45 DSRWC-1-4 UT45 DSRWC-1-3 UT45 DSRWC-1-6 UT45 DSRWC-1-7 UT45 DSRWC-1-5 UT45 DRWC-1-1A UT45 DFWC-1-1 UT45 RWC-1-H2 PT DRWC-1-61 UT45 DSRWC-1-1AX UT45 TRWC-1-4A UT45 DSENC-1-2X UT45 DS RkC ' 3 X UT45 DSRWC-1-4X UT45 ( DP5C 1 A PT LRWC-1-1A PT NOI 174 CRACK NO. OF IN.5PECTIONS: 24 \ I
BROWNS FERRY NUCLEAR PLANT Page 58 INSPECTION RESULTS ,, 07 /02/87 UNIT 2 CYCLE O SYSTEM: HS WELD'NO. NDE INDICATIONS ]) FW- 1 UTO l FW-1 UT45 l FW-2 UTO FW-2 UT45 FW-3 UTO FW-3 UT45 ; FW-4 UTO FW-4 UT45 FW-5 UTO FW-5 UT45 FW-6 UTO FW-6 UT45 FW-7 UTO FW-7 UT45 FW-8 UTO FW-8 UT45 GEOMETRY FW-9 UTO FW-9 UT45 FW-10 UTO FW-10 UT45 FW-11 UTO FW- 11 UT45 FW-12 UTO FW-12 UT45 FW-13 UTO , FW-13 UT45 FW-14 UTO FW-14 UT45 FW-15 UTO FW- 15 UT45 FW-16 UTO FW- 16 UT45 FW- 17 UTO FW-17 UT45 FW-18 UTO FW-18 UT45 NO, OF INSPECTIONS: 36 i < _u
l Page 59 BROWNS FERRY NUCLEAR PLANT 07 /02/87 INSPECTION RESULTS .. 5, UNIT 2 CYCLE O SYSTEM: RCIC WELD NO. HDE INDICATIONS TRCIC-2-1 UTO TRCIC-2-1 UT45 GEOMETRY TRCIC-2-1A UTO TRCIC-2-1A UT45 GEOMETRY TRCIC-2-2 UTO TRCIC-2-2 UT45 TRCIC-2-3 UTO TRCIC-2-3 UT45 TBCIC-2-4 UTO TRCIC-2-4 UT45 TBCIC-2-7 UTO TRCIC-2-7 UT45 NO. OF INSPECTIONS: 12 { r
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Pago 60 BROWNS FERRY NUCLEAR PLANT INSPECTION RESULTS G7 /02 /87 UNIT 2 CYCLE O SYSTEM: FW WELD HO. NDE UTO INDICATIONS
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KFW 17 KF W 17 UT45 KFW-2-16 UTO KFW-2-16 UT45 GEOMETRY GFW-2-13 UTO GFW-2-13 UT45 GFW 17 UTO GFW-2-17 UT45 GEOMETRY KFW-2-19 UTO KFW-2-19 UT45 KFW 18 UTO KFW-2-18 UT45 GE0 METRY GFW 16 UTO GFW-2-16 UT45 GFW-2-33 UTO GFW-2-33 UT45 GE0 METRY GFW-2-9 UTO GFW-2-9 UT45 KFW 13 UTO KFW-2-13 UT45 GFW-2-8 UTO GFW-2-8 UT45 KFW-2-12 UTO KFW-2-12 UT45 GEOMETRY GFW 12 UTO GFW 12 UT45 > KFW 11 UTO KFW-2-11 UT45 GEOMETRY KFW-2-10 UTO KFW 10 UT45 GEOMETRY KFW-2-9 UTO KFW-2-9 UT45 GEOMETRY GFW-2-15 UTO GFW-2-15 UT45 GEOMETRY GFW-2-15 UT45 GEOMETRY KFW-2-39 UTO KFW-2-39 UT45 GEOMETRY GFW-2-7 UTO GFW-2-7 UT45 GEOMETRY GFW-2-6 UTO GFW-2-6 UT45 GEOMETRY KFW-2-8 UTO KFW-2-8 UT45 SMALL IND <DAC KFW-2-7 UTO I KFW-2-7 UT45 GEOMETRY J GFW-2-26 UTO GFW-2-26 UT45 KF W 31 UTO KFW-2-31 UT45 GEOMETRY GFW-2-25 UTO I
BROWNS FERRY NUCLEAR PLANT Page 61 INSPECTION RESULTS 07 /02/87 4 UNIT 2 CYCLE O SYSTEM: FW WELD NO. HDE INDICATIONS GFW-2-25 0745 KFW-2-30 UTO KFW-2-30 UT45 GEOMETRY GFW-2-29 UTO GFW-2-29 UT45 KFW-2-29 UTO KFW-2-29 UT45 GEOMETRY KFW-2-28 UTO KFW-2-28 UT45 GEOMETRY KFW-2-27 UTO KFW-2-27 UT45 GEOMETRY GFW-2-32 UTO GFW-2-32 UT45 KFW-2-38 UTO KFW-2-38 UT45 GFW-2-24 UTO GFW-2-24 UT45 GEOMETRY GFW-2-23 UTO GFW-2-23 UT45 GEOMETRY KFW-2-26 UTO KFW-2-26 UT45 GEOMETRY KFW-2-25 ( KFW-2-25 KFW-2-6 UTO UT45 UTO GEOMETRY KFW-2-6 UT45 GEOMETRY KFW-2-5 UTO KFW-2-5 UT45 GEOMETRY GFW-2-4 UTO GFW-2-4 UT45 GEOMETRY GFW-2-3 UTO GFW-2-3 UT45 GEOMETRY KFW-2-24 UTO KFW-2-24 UT45 GEOMETRY GFW-2-20 UTO GFW-2-22 UT45 GEOMETRY KFW-2-23 UTO KFW-2-23 UT45 GEOMETRY GFW-2-21 UTO GFW-2-21 UT45 GEOMETRY GFW-2-20 UTO GFW-2-20 UT45 GFW 18 UTO GFW 18 UT45 SMALL POROSITY < DAC GFW-2-19 UTO GFW 19 UT45 SPOT IND < DAC KFW-2-21 UTO I KF W 21 UT45 GFW-2-1 UTO GFW 1 UT45 (- KFW-2-1 UTO SMALL IND < DAC I l
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BROWNS FERRY NUCLEAR PLANT Page 62 INSPECTION RESULTS ,_ 07/02/87 UNIT 2 CYCLE O SYSTEM: FW INDICATIONS WELD NO. NDE l} KFW-2-1 UT45 GEOMETRY KFW-2-3 UTO KFW-2-3 UT45 GEOMETRY KFW-2-36 UTO KFW-2-36 UT45 GFW-2-34 UTO GFW-2-34 UT45 GFW-2-30 UTO GFW-2-30 UT45 KFW-2-34 UTO KFW-2-34 UT45 KFW-2-35 UTO KFW-2-35 UT45 SUCKBACK < DAC GFW-2-31 UTO GFW-2-31 UT45 GEOMETRY GFW-2-28 UTO GFW-2-28 UT45 GEOMETRY KFW-2-33 UTO KFW-2-33 UT45 GEOMETRY KFW-2-32 UTO KFW-2-32 UT45 GEOMETRY GFW-2-27 UTO GFW-2-27 UT45 GFW-2-11 UTO GFW-2-11 UT45 GEOMETRY "' KFW-2-15 UTO KFW-2-15 UT45 GEOMETRY KFW-2-14 UTO KFW 14 UT45 GEOMETRY GFW-2-10 UTO GFW-2-10 UT45 GEOMETRY GFW-2-14 UTO GFW 14 UT45 GFW-2-2 UTO GFW-2-2 UT45 KFW-2-37 UTO KFW-2-37 UT45 GEOMETRY GFW-2-5 UTO GFW-2-5 UT45 NO. OF INSPECTIONS: 139
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BROWNS FERRY NUCLEAR PLANT Page 63 INSPECTION RESULTS 07/02/87 UNIT 2 CYCLE O SYSTEM: CS ( WELD NO. NDE INDICATIONS DCS 17 UTO DCS 17 UT45 DCS-2-13 UTO DCS 13 UT45 GEOMETRY DCS-2-18 UTO DCS-2-18 UT45 DCS-2-9 UTO DCS-2-9 UT45 GEOMETRY DSCS-2-6 UTO DSCS-2-6 UT45 SPOT IND 5% DAC DCS-2-8 UTO DCS-2-8 UT45 DCS 16 UTO DCS-2-16 UT45 DSCS-2-12 UTO DSCS 12 UT45 GEOMETRY DSCS-2-11 UTO DS CS 11 UT45 GEOMETRY DSCS-2-10 UTO DS CS 10 UT45 DCS-2-15 UTO DCS-2-15 UT45 ' ( DCS-2-14 UTO DC S 14 UT45 DSCS-2-S UTO DSCS-2-9 UT45 GEOMETRY DSCS-2-5 UTO DSCS-2-8 UT45 DSCS-2-7 UTO LSCS-2-7 UT45 GEOMETRY DCS 13 UTO DCS-2-13 UT45 LINEAR IND 32% DAC DCS-2-4 UTO DCS-2-4 UT45 DSCS-2-1 UTO DSCS-2-1 UT45 DSCS-2-2 UTO DSCS-2-2 UT45 GEOMETRY DCS-2-5 UTO POROSITY 25% DAC DCS-2-5 0745 DCS-2-6 UTO DCS-2-6 UT45 DSCS-2-3 UTO DSCS-2-3 UT45 DSCS-2-4 UTO DSCS-2-4 UT45 CSCF-2-5 UTO DSCS-2-5 UT45 SPOT IND 20% DAC DOS-2-7 UTO
- f. . LCS-2-7 UT45
Page 64 BROWNS FEFFY NUCLEAR PLANT INSPECTION BESULTS , 07 /02 /F-UNIT 2 CYCLE O SYSTEM: CS WELD HO. NDE INDIC ATIONS [) DCS 12 UTO f ! DCS 12 UT45 ? DCS-2-3 UTO DCS-2-3 UT45 I NO. OF INSPECTIONS: 54 f 1 l l I
BROWNS FERRY NUCLEAR PLANT Page 65 INSPECTION RESULTS ,, 07/02/87
- k. UNIT 2 CYCLE O SYSTEM: CRD WELD NO. NDE INDICATIONS RCR D 3 7 UTO RCRD-2-37 UT45 RCRD-2-36 UTO RCRD-2-36 UT45 GEOMETRY RCRD- 2-3 5 UTO RCRD-2-35 UT45 BCRD 3 4 UTO RCRD-2-34 UT45 RC R D 3 3 UTO RCB D 3 3 UT45 RCRD-2-32 UTO R C R D 3 2 0745 BCRD 31 UTO RCRD-2-31 UT45 RCR D- 2 -3 0 UTO RCRD-2-30 UT45 GROMETRY RCRD 2 9 UTO RCRD 2 9 UT45 GE0 METRY RCRD-2-28 UTO RCB D 2 8 UT45 GEOMETRY RCRD-2-17 UTO RC R D 27 UT45 GEOMETRY k' RChD-2-26 UTO RCRD 2 6 UT45 BCRD-2-25 UTO RC R D 2 5 UT45 -
RCBD 22 UTO , RCEL-2-22 UT45 RCRD-2-23 UTO B05D-2-23 UT45 NO. OF INSPECTIONS: 30
Page 66 BROWNS FERRY NUCLEAR PLANT INSFECTION RESULTS ,, 07/02/87 UNIT 2 CYCLE, O SYSTEM: RHR WELD NO. NDE INDICATIONS {g DHS-2-7 PT DHS-2-7 UTO DHS-2-7 UT45 GEOMETRY TRHR-2-479-H UTO TRHR-2-479-H UT45 GEOMETRY TRHR-2-479-G UTO TRHR-2-479-G UT45 GEOMETRY TRHR-2-479-D UTO TRHR-2-479-D UT45 POROSITY 20% DAC DHS-2-6 UTO DHS-2-6 UT45 DS HS 19 UTO DSHS-2-19 UT45 SPOT & GEOM <DAC DHS-2-5 UTO DHS-2-5 UT45 GEOMETRY DHS-2-4 UTO DHS-2-4 UT45 DSHS-2-16 UTO DSHS 16 UT45 DS HS 15 UTO DS HS 15 UT45 DRHR-2-6 UTO DRHR-2-6 UT45 DSRHR-2-3 UTO DSRHR-2-3 UT45 ,, DSRHR-2-4 UTO DSRHR-2-4 UT45 , DSRHR-2-4A UTO DSBHR-2-4A UT45 DRHR-2-7 UTO DRHR-2-7 UT45 DRHR-2-3 UTO DBHR-2-9 UT45 DRHR-2-6 UTO DRHR-2-8 UT45 DHS 19 UTO DHS 19 UT45 DRHR-2-18 UTO DRHR-2-18 UT45 DRHR 17 UTO DRHR 17 UT45 DRHR-2-16 UTO DRHR-2-16 UT45 GEOMETRY DSRHR-2-7 UTC DSRHR-2-7 UT45 DSRHR-2-6 UTO DSRHR-2-6 UT45 DR HR 15 UTO , l DRHR 2 15 UT45 POROSITY 10% DAC DRHR-2-14 UTO l. J
BROWNS FERRY NUCLEAR PLANT Page 67 INSPECTION RESULTS , , 07/02/87 ( UNIT 2 CYCLE O SYSTEM: RHR WELD NO. NDE INDICATI0HS DRHR-2-14 UT45 DSRHR-2-5A UTO DS RHR 5 A UT45 DRHR 13 UTO DRHR 13 UT45 DRHR 19 UTO DRHR 19 UT45 DSRHR-2-9 UTO DSRHR-2-9 UT45 DS RHB 8 UTO DSRHB-2-8 UT45 GEONETRY DRHR-2-21 UTO DRH3-2-21 UT45 DRHR-2-22 UTO DBHB-2-22 UT45 DS RHR 10 UTO DS RHR 10 UT45 GEOMETRY DS RHR 11 UTO DS RHR 11 0745 DRHR-2-23 UTO DRHF-2-23 UT45 (_ TRHR 192 UTO TR HF 15 2 UT45 TRHF 191 UTO TRHR 191 UT45 DRHR-2-4 UTO DRHR-2-4 UT45 DSRHR-2-2 UTO DSRHR-2-2 UT45 DSRHF-2-1 UTO DS RHR 1 UT45 DRHB-2-5 UTO DRHR-2-5 UT45 DRHR-2-12 UTO DRHR 12 UT45 TRHR-2-194 UTO TRHR 194 UT45 DRHR-2-3 UTO DRHR-2-3 UT45 TRHR-2-479B UTO TRHR-2-479B 0745 TRHR 192 PT NO. OF INSPECTIONS: 92 I
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Page 68 BB0WNS FERRY NUCLEAR PLANT 07 /:)2 /2 ' INSPECTION RESULTS ,, UNIT 2 CYCLE O SYETEM: HPCI WELD NO. NDE INDICATIONS } THPCI-2-66 UTO THPCI-2-66 UT45 THPC I 66 A UTO THPCI-2-66A UT45 THPCI-2-67 UTO THPCI-2-67 UT45 GEOMETRY THPC I 68 UTO 4 i THPCI-2-68 UT45 THPCI-2-68 A UTO THPC I-2-68 A UT45 THPCI-2-69 UTO THPCI-2-69 UT45 GEOMETRY THPCI-2-7 0 UTO THPCI-2-70 UT45 THPC I-2-6 5 UTO THPC I-2-6 5 UT45 GEOMETRY THPCI-2-63 UTO THPCI-2-63 UT45 THPCI-2-62 UTO THPCI-2-62 UT45 GEOMETRY TH PC I 61 UTO ; THPC I-2-61 UT45 THPC I- 2 -7 4 UTO THPCI-2-74 UT45 GEOMETRY '; 1 UTO ' THPC I-2 -7 3 THPCI- 2 -7 3 UT45 THPCI-2-75 UTO THPC I- 2 -7 5 UT45 THPCI-2-76 UTO THPC I-2-7 6 UT45 THP2I-2-72 UTO THPCI-2-72 UT45 THPC I- 2-71 UTO THPC I-2 -71 UT45 T HPC I- 2 -7 0 A UTO THPC I 7 0 A UT45 THPC I 82 UTO THPC I 82 UT45 NO. OF INSFECTIONS: 38 i l l
BROWNS FERRY NUCLEAR PLANT Page 69 INSPECTION RESULTS , 07 /02/87 i* UNIT 2 CYCLE O SYSTEM: RWC WELL NO. NDE INDICATIONS DSRWC-2-5 UTO DSRWC-2-5 UT45 DSRWC-2-6 UTO DSRWC-2-6 UT45 DSRWC-2-4 UTO DSRWC-2-4 UT45 DSRWC-2-3 UTO DSRWC-2-3 UT45 DSRWC-2-2 UTO DSRWC-2-2 UT45 DSRWC-2-1A UTO DS RWC 1 A UT45 LRWC-2-3 UTO DRWC-2-3 UT45 LRWC-2-2 UTO DRWC-2-2 UT45 DS RWC 1 UTO DS R WC 1 UT45 DRWC-2-4 UTO DRWC-2-4 vi45 DRWC-2-1A UTO [' DRWC-2-1A UT45 DRWC 1 UTO DRWC-2-1 UT45 DRWC-2-60 UTO DRWC- 2-6 0 UT45 GEOMETRY DSRWC-2-8 UTO DSRWC-2-8 UT45 GEOMETRY DSRWC-2-9 UTO DSRWC-2-9 UT45 GEOMETRY DFWC-2-58 UTO DRWC-2-58 UT45 GEOMETRY LS RWC 7 UTO DSRWC-2-7 UT45 DEWC-2-59 UTO DRWC-2-59 UT45 GEOMETRY DEWC-2-5A UTO LRWC-2-5A UT45 DRWC-2-5B UTO DFWC-2-5B UT45 C. OF INSPECTIONS: 40 (
Page 70 B80WNS FERRY HUCLEAR PLANT INSPECTION R25ULTS ,. 07 /02/87 UNIT 2 CYCLE O SYSTEM: R WELD NO. NDE INDICATIONS ]) GR-2-47 UTO GB-2-47 UT45 KR-2-43 UTO KB-2-43 UT45 GEOMETRY GR-2-46 UTO GR-2-46 UT45 GR-2-43 UTO GR-2-43 UT45 KR-2-40 UTO KR-2-40 UT45 GEOMETRY GR-2-42 UTO GR-2-42 UT45 , GR-2-40 UTO GR-2-40 UT45 KR-2-39 UTO KR-2-39 UT45 GEOMETRY GR-2-39 UTO GR-2-39 UT45 GEOMETRY GR-2-37 UTO GR-2-37 UT45 POROSITY < DAC GR-2-36 UTO GB-2-36 UT45 GEOMETRY GR-2-59 UTO GR-2-59 UT45 KR-2-50 UTO KR-2-50 UT45 KB-2-60 UTO KR-2-60 UT45 GEOMETRY GR-2-11 UTO GR-2-11 UT45 KR-2-16 UTO KR-2-16 UT45 GR-2-10 UTO GR-2-10 UT45 GEOMETRY GR-2-14 UTO GR 14 UT45 KR 17 UTO KR 17 UT45 GE0 METRY GR-2-13 UTO GR 13 UT45 G R 17 UTO G R 17 UT45 ) KB 17 UTO KR-2-17 UT45 GR-2-16 UTO Gh-2-16 UT45 GEOMETRY Gh 2 21 UTO GR-2-21 UT45 SPOT IND < DAC KR-2-21 UTO KR-2-21 UT45 GEOMETRY
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l Page 71 j BROWNS FERRY NUCLEAR PLANT ' INSPECTION RESULTS , _ 07 /02/87 k- UNIT 2 CYCLE O SYSTEM: R I WELD NO. NDE INDICATIONS GE-2-20 UTO GF-2-20 UT45 GP-2-24 UTO GR-2-24 UT45 KR-2-22 UTO KR-2-22 0T45 GR-2-23 UTO GP-2-23 UT45 GP-2-53 UTO GF-2-53 UT45 GEOMETRY Gk-2-54 UTO CB-2-54 UT45 GB-2-45 UTO GE-2-45 UT45 GEOMETRY GF-2-34 UTO GE-2-34 UT45 KB-2-37 UTO KF-2-37 UT45 KB 11 UTO KP-2-11 UT45 GF-2-8 UTO GF-2-8 UT45 ( KB-2-3 UTO KF-2-3 UT45 GEOMETRY GR-2-25 UTO GF-2-25 UT45 - GR-2-51 UTO GE-2-f: UT45 KR-2-41 UTO KP-2-41 UT45 GE-2-44 UTO GE-2-44 UT45 KE-2-34 UTO KE-2-34 UT45 KB-2-33 UTO KR-2-33 UT45 GE-2-41 UTO GR-2-41 UT45 GR-2-3B UTO GE-2-38 UT45 GR-2-38 UTO GP-2-38 UT45 GEOMETRY KF-2-35 UTO KR-2-35 UT45 GF-2-35 UTO GB-2-3! 0745 Kh-i-36 UTO KF-2-36 UT45 4 (- KB-2-15 UTO KF-2-15 0T45 l l t s-r- a w ..e e- a . - I- - , __
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L Page 73 BROWNS FERRY NUCLEAR PLANT 07 /02/87 INSPECTION RESULTS __ (' UNIT 2 CYCLE O SYSTEM: R WELD No. HDE INDICATIONS Kh-2-29 UTO KR-2-29 UT45 GEOMETRY KR-2-30 UTO KR-2-30 UT45 GR-2-31 UTO GR-2-31 UT45 GEOMETRY KR-2-24 UTO KR-2-24 0T45 KR-2-54 UTO KR-2-54 UT45 INDICATIONS (DAC KR-2-47 UTO KR-2-47 UT45 GEOMETRY GR-2-56 UTO GP-2-56 UT45 GR-2-57 UTO GR-2-57 0745 GEOMETRY KR-2-49 UTO KR-2-49 UT45 KR-2-48 UTO KR-2-48 UT45 GR-2-58 UTO (. GB-2-58 UT45 GR-2-1 UTO GP-2-1 UT45 GR-2-2 UTO GR-2-2 UT45 GP-2-3 UTO GF-2-3 UT45 KR-2-2 UTO KR-2-2 UT45 KR-2-55 UTO KR-2-55 UT45 GEOMETRY KR-2-8 UTO KR-2-8 UT45 ' GR-2-6 UTO I GR-2-6 UT45 GR-2-5 UTO GB-2-5 0745 GEOMETRY KR-2-7 UTO , KR-2-7 UT45 KR-2-6 UTO KR-2-6 UT45 GEOMETRY KP-2-5 UTO KR-2-5 UT45
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Page 7f. BROWNS FERRY NUCLEAR PLANT INSPECTION RESULTS . 07 /02/87 t UN!T 2 CYCLE O SYSTEM: MS WELD NO. NDE INDICATIONS KMS-2-50 UTO KMS-2-50 UT45 KMS-2-51 UTO KMS-2-51 UT45 KMS-2-46 UTO KMS-2-46 UT45 KMS-2-47 UTO KMS-2-47 UT45 KMS-2-48 UTO KMS-2-48 UT45 KMS-2-43 UTO KMS-2-43 UT45 KMS-2-44 UTO KMS-2-44 UT45 KMS-2-45 UTO KMS-2-45 UT45 MMS-2-40 UTO KMS-2-40 UT45 KMS-2-41 UTO KMS-2-41 UT45 f-KMS-2-42 UTO KMS-2-42 0T45 GMS-2-14 UTO GMS-2-14 UT45 GEOMETRY GMS-2-15 UTO GMS-2-15 UT45 GEOMETRY KMF-2-38 UTO KMS-2-38 UT45 GEOMETRY KMS-2 35 UTO KMS-2-35 UT45 KMS-2-36 UTO KMS-2-36 UT45 KMS-2-37 UTO KMS-2-37 UT45 KMS-2-32 UTO KMS-2-32 UT45 KMS-2-33 UTO KMS-2-33 UT45 KMS-2-34 UTO KMS-2-34 UT45 KMS-2-31 UTO KMS-2-31 UT45 GEOMETRY KMS-2-5E UTO KMS-2-58 UT45 GEOMETRY KMS-2-61 UTO KMS 61 UT45 KMS-2-60 UTO KMS-2-60 UT45 { KMS-2-59 UTO KMS-2-59 UT45
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l Page 92 BROWNS FERRY NUCLEAR PLANT INSPECTION RESULTS .. 07/02/f7 UNIT 2 CYCLE 1 SYSTEM: FW ; WELD NO. NDE INDICATIONS ) KFW-2-8 UTO KFW-2-8 UT45 'EOMETRY KFW-2-9 UTO KFW-2-9 UT45 GEG.'5TRY , 1 KFW-2-26 UTO KFW-2-26 0745 GEOMETRY : KFW-2-10 UTO KFW-2-10 UT45 GEOMETRY GFW-2-15 UTO GFW-2-15 UT45 KFW-2-38 UTO KFW-2-38 UT45 GEOMETRY KFW-2-39 UTO KFW-2-39 UT45 GEOMETRY NO. OF INSPECTIONS: 14 i
BROWNS FERRY NUCLEAR PLANT Fase 93 INSPECTION RESULTS .- 07/02/87 (' UNIT 2 CYCLE 1 SYSTEM: CS WELD NO. NDE INDICATIONS TCS-2-401 UTO TCS-2-401 UT45 GE0 METRY TCS-2-402 UTO TCS-2-402 UT45 GEOMETRY TCS-2-403 UTO TCS-2-403 UT45 GE0 METRY TCS-2-404 UTO TCS-2-404 UT45 GEOMETRY TCS-2-405 UTO TCS-2-405 UT45 TCS-2-406 UTO TCS-2-406 UT45 TCS-2-407 UTO TCS-2-407 UT45 GEOMETRY TCS-2-406 UTO TCS-2-408 UT45 GEOMETRY TCS-2-409 UTO TCS-2-409 UT45 GEOMETRY TCS-2-410 UTO TCS-2-410 UT45 GEOMETRY TCS-2-417 UTO (. TCS-2-417 TCS-2-418 UT45 UTO GEOMETRY r TCS-2-418 UT45 GEOMETRY TCS-2-419 UTO TCS-2-419 UT45 GEOMETRY TCS-2-420 UTO TCS-2-420 UT45 GEOMETRY TCS-2-421 UTO i TCS-2-421 UT45 TCS-2-422 UTO TCS-2-422 UT45 GEOMETRY TCS-2-423 UTO i TCS-2-423 UT45 GEOMETRY TCS-2-424 UTO TCS-2-424 UT45 i TCS-2-425 UTO 705-2-425 UT45 GEOMETRY TCS-2-426 UTO TCS-2-426 UT45 NO. OF INSPECTIONS: 40 (
m BF0WNS FERRY NUCLEAR PLANT Page 94 INSPECTION RESULTS - 07 /02/87 l UNIT 2 CYCLE 1 SYSTEM: MS WELD NO. NDE INDICATIONS .) KMS-2-30 UTC LAMINATION 25% DAC KMS-2-30 UT45 GEOMETRY KMS-2-30 UTO INCLUSIONS < 20% DAC KMS-2-30 UT45 GMS 15 UTO GMS-2-15 UT45 GEOMETRY GMS-2-24 UTO ' GMS-2-24 UT45 GEOMETRY GMS-2-32 UTO GMS-2-32 UT45 GEOMETRY KMS-2-102 UTO KMS-2-102 UT45 GEOMETRY KMS-2-37 UTO KMS-2-37 UT45 DROP-THROUGH < DAC KMS-2-59 UTO KMS-2-59 UT45 KMS-2-36 UTO KMS-2-36 UT45 KMS-2-60 UTO KMS-2-60 UT45 No. OF INSPECTIONS: 20
Page 95 BROWNS FERRY NUCLEAR PLANT .- 07 /02 /87 INSPECTION RESULTS SYSTEM: B UNIT 2 CYCLE 1 WELD NO. NDE INDICATIONS GR-2-53 UTO GR-2-53 UT45 GEOMETRY GR-2-27 UTO GR-2-27 UT45 GEOMETRY GR-2-24 UTO GR-2-24 UT45 GEOMETRY GR-2-37 UTO GR-2-37 UT45 INCLUSIONS 20% DAC GR-2-40 UTO GR-2-40 UT45 GEOMETRY GR-2-47 UTO GR-2-47 UT45 GEOMETRY NO. OF INSPECTIONS: 12 i I i
BROWNS FERRY NUCLEAR PLANT Pare 96 INSPECTION RESULTS - 07 /0L /A7 UNIT 2 CYCLE- 1 SYSTEM: RHR WELD NO. NDE INDICATIONS DSRHR-2-7 UTO DS RHR- 2-7 UT45 GEOMETRY NO. OF INSPECTIONS: 2
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Page 99 BROWNS FERRY NUCLEAR PLANT .- 07/00/87 INSPECTION RESULTS , - (' UNIT 2 CYCLE 3 SYSTEM: R t WELD NO. NDE INDICATIONS GR 18 UTO : GR-2-18 UT45 KR-2-19 UTO KR-2-19 UT45 R-2 A- H1 PT - R-2-H1 VT l R-2-H3 VT , R-2-SS1 VT R-2-H14 VT R-2A-H3 PT NO. OF INSPECTIONS: 10 i l
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BROWNS FEBRY NUCLEAR PLANT Pase100 INSPECTION RESULTS .- 07 /02 i A 7 UNIT 2 CYCLE 3 SYSTEH: HPCI . ; WELD NO. NDE INDICATIONS ) l THPCI-2-65 UTO THPCI-2-65 UT45 GEOMETRY NO. OF INSPECTIONS: 2 l l l I l l I r s :
L BROWNS FERRY NUCLEAR PLANT Page101 INSPECTION RESULTS .- 07/02/87 , ( UNIT 2 CYCLE 3 SYSTEM: RHR WELD NO. NDE INDICATIONS DHS-2-6 UTO DHS-2-6 UT45 DSHS 19 UTO DSHS-2-19 UT45 HS-2-H11 VT HS-2-H11 PT HS-2-H73 VT HS-2-R73 PT HS-2-H72 VT TRHR-2-191 UTO TRHR-2-191 UT45 TRHR-2-191 PT TRHR-2-191 PT - DSRHR-2-11 UTO DSRHR-2-11 UT45 DSRHR-2-4A UTO DSRHR-2-4A UT45 RHB-2-H-10 VT i NO. OF INSPECTIONS: 18 ( J .i P
BROWNS FERRY NUCLEAR PLANT Para 102 INSPECTION RESULTS .. 07 /02 /87 UNIT 2 CYCLE 3 SYSTEM: CRD . WELD NO, NDE INDICATIONS [h RCBD-2-44 UTO RCRD-2-44 UT45 BCRD-2-43 UTO RCRD 4 3 UT45 BCRDS-2-3 UTO RCRDS-2-3 UT45 BCBDS-2-1 UTO i RCRDS 1 UT45 RCRD-2-47 UTU RCRD-2-47 UT45 GEOMETRY RCRD-2-45 UTO BCB D-2-4 5 UT45 RCRD-2-46 UTO RCRD 4 6 UT45 GEOMETRY RCRD-2-48 UTO RCBD 4 8 UT45 GEOMETRY RCRD-2-49 UTO BCRD-2-49 UT45 GE0 METRY BCBD-2-7 UTO RC R D 2 UT45 R C R D 2 PT ' BCRD-2-49 PT NO. OF INSPECTIONS: 22 i l 1 l i I
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Pcg2104 BROWNS FERRY NUCLEAR PLANT INSPECTION RESULTS .. 07 /02 /C-UNIT 2 CYCLE 3 SYSTEM: CS WELD NO. NDE INDICATIONS h CS-2-H3 VT CS-2-H3 MT CS-2-H6 VT CS-2-H6 MT CS-2-H1 VT No. OF INSPECTIONS: 5 J l 1 1 1 J
Paga105 BROWNS FERRY NUCLEAR PLANT ._ 07/02/87 INSPECTION RESULTS ( CYCLE 3 SYSTEM: RCIC UNIT 2 HDE INDICATIONS WELD NO. TRCIC-2-2 0T0 UT45 GEONETRY TRCIC-2-2 2 NO. OF INSPECTIONS: 1
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Page107 BROWNSFERRYNUCLEARPLkNT INSPECTION RESULTS . _ 07 /02/87
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BROWNS FEBRY NUCLEAR PLANT Pagel10 I INSPECTION RESULTS - 07 /02/0 1 UNIT 2 CYCLE 4 SYSTEM: CS WELD No. NDE INDICATIONS [] ! DCS-2-5 UT45 DSCS-2-2 UT45 DSCS-2-1 UT45 DCS-2-4 UT45 DCS-2-3 UTO DCS-2-3 UT45 DCS-2-3 PT DCS-2-12 UTO DCS-2-12 UT45 DCS 12 PT DCS-2-13 UT45 DCS-2-7 UT45 DSCS-2-9 UT45 DCS-2-14 UT45 TCS-2-423 UT45 TSCS-2-424 UT45 TCS-2-410 UT45 IND NOI TCS-2-410 PT IND NOI TCS-2-406 UT45 TCS-2-406 PT TCS-2-401 UT45 TCS-2-401 PT TCS-2-410 PT DCS-2-2 UT45 , l DCS-2-13A UT45 NO. OF INSPECTIONS: 25 l
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1 Page111 BROWNS FERRY NUCLEAR PLANT INSPECTION RESULTS
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BROWNS FERRY NUCLEAR PL NT Page113 INSPECTION RESULTS - 07 /02/67 ( UNIT 2 CYCLE 4 SYSTEM: FW WELD NO. NDE INDICATIONS KFW-2-24 UT45 GFW-2-4 UT45 GFW-2-8 UT45 KFW 31 UT45 GFW-2-26 UT45 GFW-2-12 UT45 KFW-2-14 UT45 GFW-2-11 UT45 KFW-2-26 PT FW-2-SSB1 MT FW-2-SSB2 VT NO. OF INSPECTIONS: 11 b r
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BROWNS FERRY NUCLEAR PLANT Page115 INSPECTION RESULTS - - - 07 /02/87 UNIT 2 CYCLE 4 SYSTEM: MS WELD NO. NDE INDICATIONS GMS-2-6 UT45 KMS-2-104 UT45 KMS-2-55 UT45 KMS-2-54 UT45 GMS-2-23 UT45 KMS-2-25 UT45 GMS-2-29 UT45 KMS-2-90 UT45 KMS-2-91 UT45 KMS-2-7 UT45 KMS-2-8 UT45 KMS-2-65 UT45 KMS-2-89 MT KMS-2-6 MT KMS-2-63 MT MS-2-HB4 VT MS-2-HB4 MT MS-2-SSA1 PT IND NOI 64 DMS-2-3 UT45 DSMS-2-27 UT45 DAS-2-3 0745 (' DAS-2-6 UT45 DSMS-2-26 UT45 KMS-2-89 MT MS-2-SSA2 PT NOI
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i BROWNS FERRY NUCLEAR PLANT Page117 INSPECTION RESULTS 07 /02/87 [ UNIT 2 CYCLE 4 SYSTEM: R WELD NO. NDE INDICATIONS GR-2-54 UT45 GR-2-54-LS UT45 GR-2-51 UT45 GR-2-20 UT45 KR-2-51 UT45 i l KR 16 UT45 , KR-2-53 PT R-2-H6 VT R-2-H6 PT R-2-553 VT R-2-553 PT GR-2-4 PT GR-2-33 PT KR-2-45 UT45 GR-2-14 UT45 KR 17 UT45 GR 12 UT45 I GR-2-41 UT45 NO. OF INSPECTIONS: 18 {_ C i
BROWNS FERRY NUCLEAF FLANT Fage11f INSPECT!ON RESULTS 07/0;/67 UNIT 2 CYCLE 4 SYSTEM: RWC WELD NO. NDE INDICATIONS ik DRWC-2-1A UT45 DRWC-2-1A PT DRWC-2-1 UT45 DSRWC-2-1 UT45 DRWC-2-2 0745 DRWC-2-3 UT45 DRWC-2-3 PT DS RWC 1 A UTO DSRWC 1 A UT45 DS R WC 2 UT45 DSRWC-2-3 UT45 DSRWC-2-4 UT45 DSRWC-2-5 UT45 DSRWC-2-6 UT45 DSRWC-2-7 UT45 DRWC-2-4 UT45 DRWC-2-59 UT45 NO. OF INSPECTIONS: 17 s
BROWNS FERRY NUCLEAR PLANT Page119 INSPECTION RESULTS 07/02/87 UNIT 2 CYCLE 4 SYSTEM: RHR WELD No. HDE INDICATIONS DSRHR-2-7 UT45 DSRHR-2-5 UT45 DSRHR-2-6 UT45 ThHR 2 192 UT45 17::11:: ;- 14 IIT46 DllS 7 PT IND NOI DSBHR-2-8 PT RHR-2-H3 VT RHR-2-H3 PT DHS-2-6 PT DHS-2-7 PT TRHP-2-222 0745 TR HR 17 0 UT45 TRHP-2-67 UT45 TRHR-2-241 UT45 TRHR-2-262 0745 TRHR-2-362 UT45 TRHR-2-385 0745 TRHR 182 0745 TRHR 110 UT45 ( TRHR-2-35 UT45 TRHR-2-319 (1T45 TRHb 2 406 IIT45 I :::::: : tu:; ilT4h I':.ittlU ;: 9 LIT 4 D DHS-2-1 UT45 TRHR-2-395 UT45 TRHR-2-35 UT45 DRHR-2-7LS UT45 DSRHR-2-4 UT45 NO. OF INSPECTIONS: 30 C
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Page RC BROWNS FERRY NUCLEAR PLANT ( ~ / n '. ' T - INSPECTION RESULTS CYCLE 5 SYSTEM: HPCI UNIT 2 s _f HDE INDIC ATIONS WELD NO. THPC I 1 A UT45 THPC I 13 F UT45 THPCI-2-60 UT45 THPCI-2-63 UT45 THFCI-2-65 UT45 THPC I 127 UT45 HPC I- 2 1 UT45 HF~I-2-2 UT45 HPCI-R-23 MT IIPC I - R- 2 4 MT T HPC I- 2 -fl 1 X UT45 No. OF INSPECTIONS: 11
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BROWNS FERRY' NUCLEAR PLANT 07 /02 /87 l INSPECTION RESULTS , CYCLE' 5 SYSTEM: RCIC : UNIT 2 WELD NO. NDE INDICATIONS d[ : TRC IC 14 4 UT45 BC IC-2-C07 X1 UT45' RCIC-2-1R4 UT45 RCIC-2-2X1 UT45 , NO. OF INSPECTIONS: .4 ; b l i F l i i i I a
Page137 BROWHS FERRY NUCLEAR PLANT ~~ ( INSPECTION RESULTS 07/02/87 UNIT 2 CYCLE 5 SYSTEM: R WELD NO. NDE INDICATIONS GF-2-4 PT GE-2-4 PT GB-2-8 PT NOI 129 GF-2-8 PT GR-2-9 PT GR-2-12 PT GF-2-15 PT NOI 125 GF 15 PT GB 18 PT GF-2-19 PT GF-2-20 UT45 GF-2-22 PT GF-2-30 PT GP-2-30 PT GP-2-33 PT GF-2-34 PT GP-2-38 PT GR-2-41 PT GF-2-41 0745 GE-2-44 PT (' GE-2-45 PT GE-2-45 PT GF-2-48 PT GF-2-35 PT GF-2-53 PT GF ".-53 UT45 GP-2-55 PT GF-2-59 PT GE-2-61 PT ^ GP-2-63A PT GE-2 -6 3 3 PT GR-2-63B PT GR-2-7 PT GB-2-7 PT KF-2-33 PT KR-2-34 PT KF-2-37 PT KP-2-37 PT KP-2-45 UT45 KF-2-46 PT KF-2-49 PT KF-2-49 PT KE-2-53 PT KF-2-53 PT KE-2-1 PT
- KB-2-1 PT
{ KR-2-3 PT KE - 2 '.1 PT KE 12 PT NOI 127 KE-2-23 PT l l l I
- _ i .
1 Pcgt138 BROWNS FERRY NUCLEAR PLANT ~~ 07/02/87 INSPECTION RESULTS UNIT 2 CYCLE 5 SYSTEM: B f WELD NO. NDE INDICATIONS ) 1 KR-?-23 PT ! KR-2-25 PT l KR-2-26 PT I i NO. OF INSPECTIONS: 53 l l s
)
I l l 1 l i
BROWNS FERRY NUCLEAR PLANT ~ Page139 i INSPECTION RESULTS 07 /a; /re UNIT 2 CYCLE 5 SYSTEM: RWC WELD NO. NDE INDICATIONS DRWO 1 PT DRWO 1 A PT NOI 126 LRWC-2-1A PT DRWC-2-2 PT DRWC-2-3 PT DRWC-2-4 UT45 DRWC-2-5A PT DRWC-2-5B PT DSRWC-2-6 UT60 DSRWC-2-7 UT45 DSRWC-2-7 UT60 DRWC-2-4A UT45 DRWC 4 B UT45 DRWC-2-7 A UT45 DRWC- 2-7 B UT45 NO. OF INSPECTIONS; 15 k. L
= + * * - . --
~.
1 BROWNS FERRY NUCLEAR PLANT ._ Pare 140 : INSPECTION RESULTS 07 /00 '!' l UNIT 2 CYCLE 5 SYSTEM: RHR h ! WELD NO. NDE INDICATIONS DRHR-2-2 PT DRHR-2-3 PT DRHR-2-4 PT ' DRHR-2-5 PT NOI 134 DRHR-2-5 PT DRHR- 2-7 PT DRHR-2-9 PT DRHF 11 PT DR HR 12 PT DRHR-2-13 PT NOI 133 DRHR 13 PT DRHR 17 PT DRHR-2-18 PT DRHR-2-19 PT DSRHR-2-4 UT45 DSRHR-2-5 PT DSRHR-2-SA RT DSRHR-2-5A RT DS RHR 5 A RT DSRHR- 2-5 A PT DSRHR-2-5A PT
)
DSRHR-2-6 PT DS RHR- 2-6 UT45 DS RHR 8 PT DSRH5-2-8 PT DS R HR 9 PT DSRHR-2-9 PT DS RHR 9 UT45 B HR-H- 12 MT BHR-H-22 MT RHR-H-7 MT RHR-H-31 MT RHR-H-36 MT RHB-H-54 MT RHR-H-55 MT RHR-H-120 MT RHR-R-12 MT RHR-R-35B MT RHR-R-51 MT BHB-B-64 MT RHRPH-2-B VT RHRPH-2-B MT ! TRHR-2-29 PT u
)
TRHR-2-29 UT45 TBHR-2-191 PT TRHR-2-462 PT TRHR-2-462 UT45
- )
NO. OF INSPECTIONS: 47
BROWNS FERRY NUCLEAR PLANT ,. Pagel41 INSPECTION RESULTS 07 /0L . '.7 ( UNIT 3 CYCLE 0 SYSTEM: CRD WELD NO. HDE INDICATIONS RC R D 37 UTO RCRD-3-37 UT45 BCRD-3-!C , ' UTO RCR D 36 UT45 BCRD-3-35 UTO RCRD-3-35 UT45 FC B D 3 4 UTO R C F D 34 UT45 BCRD-3-33 UTO RCBD-3-33 UT45 BCRD 3 2 UTO
- RCRD-3-32 UT45 1
PCBD-3-30 UTO RCB D 3 0 UT45 BCBD-3-29 UTO RCRD-3-29 UT45 RCR D 28 UTO RCRD-3-28 UT45 RCRD-3-27 UTO ( RCRD-3-27 UT45 ' BCR D 2 6 UTO RCRD-3-26 UT45 BCRD-3-25 UTO , RCRD-3-25 UT45 FORD-3-22 UTO RCRD-3-22 UT45 BCRD-3-23 UTO BCRD-3-23 UT45 FCR?-3-3* . UTO RCF D-3-31 UT45 i i t:0. OF INSBECTIONS: 30 4 i
)
- (I J
BROWNS FERRY NUCLEAR PLANT ,, P4Fel4L INSPECTION BESULTS 07 /02 /5- 3 UNIT 3 CYCLE 0 SYSTEM: CS- ; i -
~# '
WELD NO. NDE INDICATIONS DCS 18 UTO DCS-3-18 UT45 DCS 17 UTO DCS 17 UT45
'DCS-3-16 UTO DCS 16 UT45 DC3-3-7 UTO l' DCS-3-7 UT45 DSCS-3-5 UTO DSCS-3-5 UT45 DCS-3-8 UTO l DCS-3-8 UT45 DCS-3-9 UTO l LCS-3-9 UT45 l DSCS-3-6 UTO DSCS-3-6 UT45 DSCS-3-2 UTO DSCS-3-2 UT45 i DSCS-3-12 UTO DSCS 12 UT45 DSCS-3-11 UTO DSCS 11 UT45 DSCS 10 UTO <
DSCS 10 UT45 ., DCS 15 UTO DCS 15 UT45 , DCS 14 UTO l DCS 14 UT45 I
- DSCS-3-9 UTO l
, DSCS-3-9 UT45 l DSCS 3-8 UTO DSCS-3-8 UT45 DSCS-3-7 UTO DSCS-3-7 UT45 DCS-3-13 UTO DCS-3-13 UT45 DSCS 13 UTO DSCS-3-13 UT45 DSCS-3-4 UTO DSCS-3-4 UT45 DSCS-3-3 UTO DSCS-3-3 UT45 DCS-3-6 UTO ICS 3-6 UT45 ICS S UTO DCS-3-5 UT45 DSCS 1 UTO DSCS-3-) UT45
)
DCS-3-4 UTO - [CS 3-4 UT45
i
. l BROWNS FERRY NUCLEAR PLANT . . Pagel43 ,
( INSPECTION'RESULTS 07 /02/8, l UNIT 3 CYCLE O SYSTEM: CS l WELD NO. NDE INDICATIONS i DCS-3-12 UTO DCS-3-12 UT45 DCS-3-3 UTO DCS-3-3 UT45 NO. OF INSPECTIONS: 54 P i i l l l i I ( i 0 ! i , l i i _ __ _ . _ . _ _ , _. ---s . - _'-- - - - - - - - -
Page144 BROWNS FERRY NUCLEAR PLANT .. INSPECTION RESULTS 07/02/87 UNIT 3 CYCLE O SYSTEM: FW WELD NO, NDE INDICATIONS GFW-3-32 UTO GFW-3-32 UT45 KFW-3-38 UTO KFW-3-38 UT45 KFW-3-28 UTO KFW-3-28 UT45 KFW-3-27 UTO KFW-3-27 UT45 GFW-3-24 UTO GFW-3-24 UT45 GFW-3-23 UTO GFW-3-23 UT45 KFW-3-26 UTO KFW-3-26 UT45 GFW-3-9 UTO GFW-3-9 UT45 KFW-3-13 UTO KFW-3-13 UT45 GFW-3-8 UTO GFW-3-8 UT45 KFW 12 UTO KF W 12 UT45 GFW-3-12 UTO .} GFW 12 UT45 KFW 11 UTO KFW-3-11 UT45 KFW-3-10 UTO KFW 10 UT45 KFW-3-9 UTO KFW-3-9 UT45 KFW-3-39 UTO KFW-3-39 UT45 GFW-3-15 UTO GFW-3-15 UT45 GFW-3-7 UTO GFW-3-7 UT45 GFW-3-6 UTO GFW-3-6 UT45 KFW-3-8 UTO KFW-3-8 UT45 GFW-3-22 UTO GFW-3-22 UT45 KFW-3-24 UTO KFW-3-24 UT45 KFW-3-23 UTO KFW-3-23 UT45 GFW-3-4 UTO GFW-3-4 UT45 g KFW-3-5 UTO , KFW-3-5 UT45 L
BROWNS FEBRY NUCLEAR PLANT . Pagel4b ( INSPECTION RESULTS 07 /0'c /67 UNIT 3 CYCLE 0 SYSTEM: FW WELD NO. NDE INDICATIONS GFW-3-5 UTO GFW-3-5 UT45 KFW-3-6 UTO KFW-3-6 UT45 GFW-3-6 UTO GFW-3-6 UT45 GFW-3-34 UTO GFW-3-34 UT45 KFW-3-37 UTO KFW-3-37 UT45 KFW-3-36 UTO KFW-3-36 UT45 GFW-3-33 UTO GFW-3-33 UT45 GFW 17 UTO GFW 17 UT45 KFW 19 UTO KFW 19 UT45 c KFW 18 UTO q, KFW 18 UT45 GFW-3-10 UTO GF W 16 UT45 GFW-3-14 UTO GFW 14 UT45 KFW 17 UTO KFW 17 UT45 KFW 16 UTO KFW 16 0745 GIW-3-13 UTO GFW-3-13 UT45 a GFW 11 UTO GFW-3-11 UT45 KFW 15 UTO KFW 15 UT45 KF W 14 UTO KFW-3-14 UT45 GFW-3-28 UTO GFW-3-28 UT45 KFW-3-33 UTO KFW-3-33 UT45 GFW-3-37 UTO GFW-3-27 UT45 GFW-3-;l UTO G F W 31 UT45 /' KFW-3-35 I UTO KFW-3-35 UT45 KFW-3-34 UTO KFW-3-34 UT45 GFW-3-30 UTO GFW-3-30 UT45
BROWNS FERRY NUCLEAR PLANT ._ Pege146 INSPECTION RESULTS 07 /02/8" UNIT 3 CYCLE 0 SYSTEM: FW _) WELD NO. NDE INDICATIONS GFW-3-26 UTO GFW-3-26 UT45 KFW-3-31 UTO KF W 31 UT45 GFW-3-25 UTO GFW-3-25 UT45 KFW-3-30 UTO KFW-3-30 UT45 GFW-3-29 UTO GFW-3-29 UT45 KFW-3-29 UTO KFW-3-29 UT45 GFW-3-19 UTO GFW 19 UT45 KFW-3-21 UTO KFW-3-21 UT45 GFW-3-18 UTO GFW-3-18 UT45 GFW-3-2 UTO GFW-3-2 UT45 KFW-3-3 UTO KFW-3-3 UT45 KFW-3-1 UTO / KFW 1 UT45 GFW-3-1 UTO GFW 1 UT45 GFW-3-21 UTO GFW-3-21 UT45 GFW-3-20 UTO GFW-3-20 UT45 KFW-3-25 UTO KFW-3-25 UT45 KFW-3-7 UTO KFW 7 UT45 KFW-3-40 UTO KFW-3-40 UT45 KFW-3-32 UTO KFW-3-32 UT45 GFW 10 UTO GFW-3-10 UT45 NO, OF INSPECTIONS: 140
BROWNS FERRY NUCLEAR PLANT _ Pagel47 INSPECTION RESULTS 07 /02 /f.'. i, UNIT 3 CYCLE O SYSTEM: HS WELD NO. NDE INDICATIONS TRHR-3-455C UTO TRHR-3-455C UT45 TRHR-3-455D UTO TRHR-3-455D UT45 TRHR-3-455E UTO TRHR-3-455E UT45 DS HS 15 UTO DSHS-3-15 UT45 DSHS-3-16 UTO DSHS-3-16 UT45 DHS-3-4 UTO DHS-3-4 UT45 DHS-3-5 UTO DHS-3-5 UT45 DHS-3-6 UTO DHS-3-6 UT45 DHS-3-7 UTO I DHS-3-7 UT45 DHS-3-1 UTO ( DHS 1 UT45 DHS-3-1A UTO DHS-3-1A UT45 DSHS-3-1 UTO DSHS-3
- UT45 DSHS-3-2 UTO DSHS-3-2 UT45 DSHS-3-3 UTO DSHS-3-3 UT45 DSHS-3-4 UTO DSHS-3-4 UT45 DSHS 3-5 UTO DSHS-3-E UT45 DHS-3-2 UTO '
DHS-3-2 UT45 DSHS-3-6 UTO DSHS-3-6 UT45 DS HS 7 UTO DSHS-3-7 UT45
- DSHS-3-6 UTO DSHS-3-8 UT45 DHS-3-3 UTO DHS-3-3 UT45 DSHS-3-9 UTO 1
DSHS-3-9 UT45 DSHS-3-10 ( DSHS-3-13 UTO UT45 DSHS-3-11 UTO DSHS-3-11 UT45 DSHE-3-12 UTO DS HS 12 UT45
.- . . ~ .
BROWNS FERRY NUCLEAR PLANT ,_ Pese146 INSPECTION RESULTS~ 07/03/5'
~
UNIT 3 CYCLE O SYSTEM: MS
.b.
WELD NO. HDE -INDICATIONS DSHS-3-13 UTO DSHS-3-13 UT45 DSHS-3-14 UTO - DS HS 14 UT45 NO. OF INSPECTIONS: 54 J I
a - - a Page149 BROWNS FERRY NUCLEAR PLANT ,. INSPECTION RESULTS 07 /00 /P7 ( UNIT 3 CYCLE O SYSTEM: HPCI WELD NO. NDE INDICATIONS THPCI-3-65 UTO THPCI-3-65 UT45 THPCI-3-64 UTO THPCI-3-64 UT45 THPCI-3-61 UTO THPCI-3-61 0745 THPCI-3-62 UTO THPCI-3-62 UT45 THPC I- 3 -6 8 UTO THPCI-3-68 UT45 THPCI-3-67 UTO , THPCI-3-67 UT45 THPCI-3-66 UTO THPCI-3-66 UT45 T HPC I 6 9 UTO THPCI-3-69 UT45 THPCI-3-70 UTO THPC I- 3 -7 0 UT45 THPC I- 3 -7 05 UTO I, THPC I- 3-7 0B UT45 THPCI-3-70A UTO THPC I- 3-7 0 A UT45 THPC I- 3 -71 UTO THPC I 71 UT45 THPCI-3-72 UTO THPCI-3-72 UT45 THPC I 7 3 UTO THPCI-3-73 UT45 THP I-3-73A UTO TH?CI-3-73A UT45 THF:I-3-73B UTO THPCI-3-733 UT45 THPC I 73 E UTO , THPCI-3-73E UT45 THPC I 7 3 G UTO TH?CI-3-73G UT45 , I
.lI NG OF INSPECTIONS: 36 !
l
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Page150 BROWNS FERRY NUCLEAR PLANT 07 /03 /8" INSPECTION RESULTS UNIT 3 CYCLE O SYSTEM: MS INDICATIONS bk WELD No. NDE KMS-3-103 UTO KMS-3-103 UT45 KMS-3-102 UTO KMS-3-102 UT45 KMS-3-100 UTO KMS-3-100 UT45 KMS-3-99 UTO KMS-3-99 UT45 KMS-3-95 UTO KMS-3-95 UT45 KMS-3-97 UTO KMS-3-97 UT45 KMS-3-92 UTO KMS-3-92 UT45 KMS-3-94 UTO KMS-3-94 UT45 KMS-3-89 UTO KMS-3-89 UT45 KMS-3-91 UTO KMS-3-91 UT45 KMS-3-88 UTO KMS-3-88 UT45 KMS-3-87 UTO ' KMS-3-87 UT45 KMS-3-86 UT0 KMS-3-86 UT45 KMS-3-83 UTO KMS-3-83 UT45 KMS-3-85 UTO KMS-3-85 UT45 KMS-3-84 UTO KMS-3-84 UT45 KMS-3-3 UTO KMS-3-3 UT45 KMS-3-6 UTO KMS-3-5 UT45 KMS-3-4 UTO KMS-3-4 UT45 KMS-3-59 UTO KMS-3-59 UT45 KMS-3-61 UTO KMS-3-61 UT45 KMS-3-66 UTO KMS-3-66 UT45 KMS-3-65 UTO KMS-3-65 UT45 KMS-3-64 UTO UT45 KMS-3-64 I KMS-3-69 UTO KMS-3-69 UT45
BROWNS FERRY NUCLEAR PLANT Pagelb1 [ INSPECTION RESULTS 07 /00 /8~ UNIT 3 CYCLE O SYSTEM: MS WE!.D NO. NDE INDICATIONS KMS-3-68 UTO KMS-3-68 UT45 KMS-3-67 UTO KMS-3-67 UT45 KMS-3-70 UTO KMS-3-70 UT45 KMS-3-71 UTO KMS-3-71 UT45 KMS-3-72 UTO KMS-3-72 UT45 KMS-3-73 UTO KMS-3-73 UT45 KMS-3-74 UTO KMS-3-74 UT45 KMS-3-75 UTO KMS-3-75 UT45 ' KMS-3 -98 UTO KMS-3-96 UT45 ( KMS-3-101 UTO KMS-3-101 UT45 KMS-3-49 UTO KMS-3-49 UT45 KM3-3-35 UTO KMS-3-35 UT45 : F,.% 36 UTO KMS-3-36 UT45 , KMS-3-32 UTO i MMS-3-32 0T45 KMS-3-33 UTO ; KMS-3-33 UT45 : KMS-3-7 OTO I KMS-3-7 UT45 l KMS-3-8 UTO ! KMS-3-8 UT45 ' KMS-3-9 UTO KMS-3-9 UT45 KMS-3-10 UTO l KMS-3-10 UT45 : KMS-3-11 UTO : EMS-3-11 UT45 ! KMS-3-12 UTO , KMS 12 UT45 KMS-3-13 UTO i e KMS 13 UT45 '. EMS 14 UTO KMS-3-14 UT45 ! KMS-3-15 UTO KMS-3-15 UT45 KMS-3-16 UTO KMS 16 UT45
Pago152 BROWNS FERRY NUCLEAR PLANT .. INSPSCTION RESULTS 07 /02 /8-UNIT 3 CYCLE O SYSTEM: MS
.b WELD NO. NDE INDICATIONS KMS 17 UTO KMS-3-17 UT45 .
KMS-3-18 UTO KMS-3-18 UT45 ] KMS-3-19 UTO KMS-3-19 UT45 KMS-3-20 UTO KMS-3-20 UT45 KMS-3-21 UTO KMS-3-21 UT45 KMS-3-22 UTO KMS-3-22 UT45 KMS-3-23 UTO KMS-3-23 UT45 i l KMS-3-24 UTO KMS-3-24 UT45 l KMS-3-63 UTO KMS-3-63 UT45 KMS-3-42 UTO KMS-3-42 UT45 KMS-3-41 UTO KMS-3-41 UT45 , KMS-3-40 UTO s KMS-3-40 UT45 KMS-3-44 UTO KMS-3-44 UT45 KMS-3-43 UTO KMS-3-43 UT45 KMS-3-47 UTO j KMS-3-47 UT45 KMS-3-46 UTO KMS-3-46 UT45 KMS-3-50 UTO KMS-3-50 UT45 KMS-3-96 UTO KMS-3-96 UT45 KMS-3-90 UTO KMS-3-90 UT45 KMS-3-104 UTO KMS-3-104 UT45 KMS-3-25 UTO KMS-3-25 UT45 KMS-3-2 UTO KMS-3-2 UT45 GMS-3-24 UTO GMS-3-24 UT45 KMS-3-62 UTO KMS-3-62 UT45 ) GMS-3-23 UTO GMS-3-23 UT45
BROWNS FERRY NUCLEAR PLANT ._ Page153 ( INSPECTION RESULTS 07/02/87 UNIT 3 CYCLE O SYSTEM: MS WELD NO. NDE INDICATIONS KMS-3-60 UTO KMS-3-60 UT45 KMS-3-76 UTO KMS-3-76 UT45 KMS-3-82 UTO KMS-3-82 UT45 KMS-3-38 UTO KMS-3-38 UT45 KMS-3-37 UTO KMS-3-37 UT45 KMS-3-34 UTO KMS-3-34 UT45 GMS-3-6 UTO GMS-3-6 UT45 GMS-3-5 UTO GMS-3-8 UT45 KMS-3-27 UTO KMS-3-27 UT45 KMS-3-26 UTO 8< KMS-3-28 UT45 GMS-3-7 UTO GMS-3-7 UT45 GMS-3-34 UTO GMS-3-34 UT45 KMS-3-108 UTO KMS-3-108 UT45 F.MS 107 UTO KMS-3-107 UTd5 GMS-3-33 UTO GMS-3-33 UT45 GMS-3-25 UTO i GMS-3-25 UT45 ! KMS-3-79 UTO ' KMS-3-79 UT45 KM5-3-80 UTO KMS-3-60 UT45 GMS-3-26 UTO GMS-3-26 UT45 GMS-3-17 UTO GMS-3-17 UT45 I KMS-3-54 UTO { KMS-3-54 UT45 i GMS-3-16 UTO . GMS-3-16 UT45 t f GMS-3-15 UTO GMS-3-15 UT45 GMS-3-14 UTO GMS-3-14 UT45 GMS-3-11 UTO GMS-3-11 UT45
Pago154 BROWNS FERRY NUCLEAR PLANT 07 /02 /8-INSPECTION RESULTS UNIT 3 CYCLE 0 SYSTEM: MS WELD NO. NDE INDICATIONS , GMS-3-10 UTO GMS-3-10 0745 GMS-3-19 UTO GMS-3-19 0T45 GMS-3-20 UTO GMS-3-20 UT45 KMS-3-57 UTO KMS-3-57 UT45 GMS-3-22 UTO GMS-3-22 UT45 GMS-3-31 UTO GMS-3-31 UT45 GMS-3-29 UTO GMS-3-29 UT45 GMS-3-28 UTO GMS-3-28 UT45 KMS-3-106 UTO KMS-3-106 UT45 GMS-3-4 UTO GMS-3-4 UT45 GMS-3-2 UTO GMS-3-2 UT45 1 KMS-3-26 UTO ! l KMS-3-26 UT45 GMS 13 UTO GMS-3-13 UT45 GMS-3-27 UTO l GMS-3-27 UT45 i GMS 18 UTO , GMS-3-18 UT45 GMS-3-1 UTO GMS-3-1 UT45 GMS-3-9 UTO GMS-3-9 UT45 GMS-3-3 UTO GMS-3-3 UT45 KMS-3-31 UTO , KMS-3-31 UT45 l KMS-3-55 UTO SMS-3-55 UT45 GMS-3-5 UTO GMS-3-5 UT45 KMS-3-58 UTO KMS-3-58 UT45 KMS-3-52 UTO KMS-3-52 UT45 KMS-3-53 UTO KMS-3-53 UT45 -' GMS-3-21 UTO GMS-3-21 UT45
Pagelbb BROWNS FERRY NUCLEAR PLtMT .. i INSPECTION RESULTS 07 /02/8" UNIT 3 CYCLE O SYSTEM: MS WELD NO. NDE INDICATIONS GMS-3-30 UTO GMS-3-30 UT45 , GMS 12 UTO GMS-3-12 UT45 KMS-3-30 UTO KMS-3-30 UT45 KMS-3-105 UTO , KMS-3-105 UT45 KMS-3-51 UTO i KMS-3-51 UT45 KMS-3-93 UTO KMS-3-93 UT45 ' GMS-3-32 UTO GMS-3-32 UT45 KMS-3-6 UTO KMS-3-6 UT45 V25-3-45 UTO KMS-3-45 UT45 ' p KMS-3-48 UTO KMS-3-48 UT45 , NO. OF INSPECTIONS: 270 4 i 1 r J j i i l l l l l 1 < l I l r ,, , - --
BROWNS FERRY NUCLEAR PLANT
- Page156 INSPECTION RESULTS 07 /00 /8~
UNIT 3 CYCLE O SYSTEM: RCIC WELD NO. NDE INDICATIONS TRCIC-3-2 UTO TRCIC-3-2 UT45 TRCIC-3-5 UTO > TRCIC-3-5 UT45 l TRCIC-3-6 UTO I TRCIC-3-6 UT45 TRCIC-3-7 UTO I THCIC-3-7 UT45 NO. OF INSPECTIONS: 8
+J
- BROWNS FERRY NUCLEAR PLANT .. Page157 k INSPECTION RESULTS 07 /02 /P.7 UNIT 3 CYCLE O SYSTEM: R WELD NO. NDE INDICATIONS GB-3-38 UTO GR-3-38 UT45 KR-3-26 UTO KR-3-26 UT45 GR-3-33 UTO GR-3-33 UT45 KR-3-32 UTO KR-3-32 UT45 GR-3-45 UTO GR-3-45 0T45 KR-3-41 UTO KR-3-41 UT45 KR-3-29 UTO KR-3-29 UT45 KB-3-30 UTO KR-3-30 0745 GR-3-32 UTO GF-3-32 UT45 /- KR-3-31 UTO *- KR-3-31 UT45 KR-3-24 UTO KR-3-24 UT45 GR-3-29 UTO .
GR-3-29 UT45 GR-3-26 UTO GR-3-28 UT45 GR-3-27 UTO j GB-3-27 UT45 KF-3-52 UTO ; KR-3-52 UT45 ) GR-3-64 UTO i GR-3-64 UT45 l GR-3-63B UTO GR-3-63B UT45 GR-3-63A UTO GR-3-63A UT45 GR-3-63 UTO GR-3-63 UT45 GR-3-62 UTO GR-3-62 UT45 KR-3-51 UTO KB-3-51 0T45 KR-3-54 UTO KR-3-54 UT45 ( KR-3-27 UTO FS-3-27 UT45 GR-3-30 UTO GR-3-30 UT45 KB-3-26 UTO KR-3-28 UT45
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BROWNS FERRY NUCLEAR PLANT -- Pero 15e INSPECTION RESULTS 07 /03 /6-UNIT 3 CYCLE O SYSTEM: R
. )
WELD NO. NDE INDICATIONS GR-3-58 UTO GR-3-58 UT45 KR-3-48 UTO KR-3-48 UT45 GR-3-57 UTO GR-3-57 UT45 KB-3-13 UTO KR 13 UT45 KR-3-15 UTO KR 15 UT45 GR-3-31 UTO GR-3-31 UT45 GR-3-61 UTO GR-3-61 UT45 KR-3-8 UTO ; KR-3-8 UT45 KB-3-7 UTO KB-3-7 UT45 GR-3-6 UTO GR-3-6 UT45 GR-3-5 UTO i GR-3-5 UT45 KR-3-55 UTO KR-3-55 UT45 l KE-3-2 UTO l KR-3-2 0T45 GR-3-4 UTO GR-3-4 UT45 KR-3-5 UTO KB-3-5 0745 KR-3-6 UTO KB-3-6 UT45 l KR-3-4 UTO ! KR-3-4 UT45 ! GR-3-7 UTO l GR-3-7 UT45 ! KB-3-10 UTO l KR 10 UT45 i KB-3-9 UTO KR-3-9 UT45 KR-3-1 l UTO KR-3-1 UT45 KR-3-49 UTO KR-3-49 UT45 GR-3-48 UTO GR-3-48 UT45 KR-3-42 UTO KR-3-42 UT45 i KR-3-34 UTO KR-3-34 UT45
, BROWNS FERRY NUCLEAR PLANT ._ Page159 1 INSPECTION RESULTS 07 /02/87 UNIT 3 CYCLE O SYSTEM: R WELD NO. NDE INDICATIONS GR-3-44 UTO '
GR-3-44 UT45 KR-3-35 UTO KR-3-35 UT45 KR-3-36 UTO KR-3-36 UT45 GR-3-35 UTO GR-3-35 UT45 KR-3-37 UTO KF-3-37 UT45 KR-3-25 UTO KR-3-25 UT45 GR-3-13 UTO ' GR-3-13 UT45 GR-3-11 UTO , GF-3-11 UT45 KR 16 UTO KR-3-16 UT45 ( GR-3-10 GR-3-10 UTO UT45 GF-3-31 UTO GR-3-21 0745 GR-3-20 UTO J GR-3-20 UT45 GF -59 UTO ! GR-3-59 UT45 KR-3-50 0T0 ' KR-3-50 UT45 GR-3-60 UTO ; GR-3-60 UT45 GR-3-51 UTO GR-3-51 UT45 I GR-3-52 UTO ' GR-3-52 UT45 GR-3-55 UTO ; GR-3-55 UT45 ! KR-3-46 UTO ! 13-3-46 UT45 GR-3-26 UTO GF-3-26 UT45 i GR-3-25 UTO GR-3-25 UT45 KR-1 cU l UTO
- KR-3-20 UT45 I
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BROWNS FERRY NUCLEAR PLANT Pere S1 ' INSPECTION RESULTS 0"' /t. :. UNIT 3 CYCLE 5 SYSTEM: CRD , WELD No. NDE INDICATIONS RC RD 4 0 UT45 RCRD 4 4 UT45 PCRD 4 5 UT45 bCRD-3-49 PT RCR D 4 9 UT45 RCRD-3-9A UT45 BCRDS-3-3 UT45 TCED 1 UT45 TC R D 1 PT TC R D 101 UT45 TCR D 11 UT45 TCRD 13 UT45 T C R L 13 PT TC R D 15 UT45 T C R D 15 PT TC F D 21 UT45 TCRD- 3-21 A UT45 TCRD-3-22 UT45 TCR D 22 A UT45 TCR D 2 3 UT45 "TE D ' - 14 UT45 TCRD-3-25A UT45 3 TCRD 25 X UT45 TCRD-3-26 UT45 - TCRD-3-26A UT45 ; TCRD-3-27 UT45 TOR'-3-27A UT45 l TCRD-3-28A UT45 ! TCR D 28 X UT45 TCRD-3-29 UT45 TCRD-3-29A UT45 TCB D 3 UT45 TCRD-3-3 PT l TCRD-3-30 UT45 i TCRD 31 UT45 1 TCRD-3-30A UT45 TCRD-3-33 UT45 TCRD-3-34 UT45 TCRD-3-35 UT45 TCRD-3-36 UT45 TCRD-3-37 UT45 TCRD-3-38 UT45 1 TCRD-3-39 UT45 TCRD-3-39B UT45 TCRD-3-5 UT45 TC R D 7 UT45 TCRD-3-7 PT 's TCRD-3-9 UT45 ). TCRD-3-9 PT s
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Page19? \ BROWNS FERRY NUCLEAR PLANT 07 /00,8-INSPECTION RESULTS 5 SYSTEM: CS UNIT 3 CYCLE WELD NO. NDE INDICATIONS DCS 10 PT DCS-3-11 PT DCS-3-12 PT DCS-3-13 UT45 DCS-3-14 UT45 DCS-3-14 PT DCS-3-3 PT DCS-3-4 UT45 , DCS-3-5 PT L05-3-5 UT45 DSCS-3-1 UT45 - DSCS-3-2 UT45 DSCS-3-7 UT45 DE05-3-8 UT45 DSCS-3-9 UT45 T I-S-10E UT45 TCS-3-203 UT45
/ TCS-3-205 PT PT
\ TCS-3-207 TCS-3-405 PT TCS-3-405 UT45 TCS-3-406 PT TC9-?-406 UT45 TCS-3-410 PT TCS-3-410 UT45 TCS-3-421 PT TCS-3-421 UT45 TCS-3-422 UT45 TCS-3-422 PT TCS-3-426 UT45 TCS-3-426 PT TCS-3-402 UT45 TCS-3-402 PT TCS-3-418 PT TCS-3-418 UT45 DSCS 1 UT45 NO. OF INSPECTIONS: 36
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BROWNS FEERY NUCLEAR PLANT - - F:q - : . .; INSPECTION RESULTS C~ . . :. . UNIT 3 CYCLE 5 SYSTEM: HS WELD NO. NDE INDICATIONS DHS-3-3 UT60 DHS-3-4 PT DHS-3-5 PT DHS-3-5 UT60 DHS-3-7 UT45 DSHS-3-15 PT DSHS-3-IC UT60 NO. OF INSPECTIONS: 7 e 9 W4 g gem , y
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[ 07 /00 c - t BROWNS FERRY NUCLEAR PLANT ? INSPECTION RESULTS SYSTEM: HPCI CYCLE 5 ' UNIT 3 NDE INDICATIONS . WELD NO. , UT45 THPCI 111 PT
.1 THPCI 120 A UT45 THPCI 120 A U745 THPC I 4 i 4 i NO, OF INSPECTIONS: f f
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p . P a g e '. : *. BROWNS FERRY NUCLEAR PLANT 07 /C; .i ~ INSPECTION RESULTS UNIT 3 CYCLE 5 SYSTEM: RCIC - WELD Ho. NDE INDICATIONS l TRCIC-3-144 UT45 ; No. OF INSPECTIONS: 1
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/ Pa g e l .< ? BROWHS FERRY NUCLEAR PLANT 07 /i:: 's INSPECTION RESULTS , 5 SYSTEM: RWC UNIT 3 CYCLE NDE INDICATIONS WELD NO. DRWC 1 UT45 DRWC-3-1 UT60 PT DRWC-3-1A DRWC-3-1 A 0745 DRWC-3-1A UT60 DRWC-3-2 PT DRWC-3-2 0745 DRWC-3-2 UT60 DBWC-3-3 PT DRWC-3-3 UT60 . DRWC-3-4 UT60 DS RWC 1 UT60 l DSRWC-3-1A PT DS RWC 1 A UT60 DSRWC-3-1B PT DSRWC-3-1B UT60 LSRWO-3-2 UT45 0T60 : DSRWC-3-2 i DSRWC-3-3 UT45 , DSRWC-3-3 UT60 DSRWC-3-4 0760 ' DSRWC-3-5 UT60 ' DSRWC-3-6 0760 ; DSRWC-3-7 UT60 NO. OF INSPECTIONS: 24 l 7-
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UNIT 3 CYCLE 5 SYSTEM: R ; } WELD NO. NDE INDICATIONS GR-3-7 PT GR-3-8 PT KR-3-1 PT KR-3-11 PT KR-3-16 UT45 KR-3-23 PT KR-3-26 PT KR-3-33 PT KB-3-4 PT KR-3-43 UT45 KR-3-45 UT45 GR-3-30 PT GR-3-33 PT GR-3-34 PT GR-3-29 UT45 GR-3-4 PT GR-3-51 UT45 GR-3-51 UT45 GR-3-20 UT45 KR-3-49 PT KR-3-53 PT KR-3-54 PT y s KR-3-55 PT GR-3-20 UT45 , NO. OF INSPECi!ONS: 24
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Page19f-BROWHS FEBRY NUCLEAR PLANT 07 /t:. /r-INSPECTION RESULTS 5 SYSTEM: RHR UNIT 3 CYCLE NDE INDICATIONS WELD NO. DRHR 11 PT DBHR 12 PT DRHR 13 PT DRHR-3-2 PT DRHR-3-3 PT DRHR-3-5 PT DRNR-3-6 0745 DSPHR-3-4 UT45 DSRHR-3-4 0745 (\ 'I l 1 ^ I
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4.0 bE0k'NC FEREY WELDINO REINSPECTION REPORT 4.1 Introduction The weld reinspection ef fort at Browns Ferry Duclear Plant (BFN) was developed to address generic and plant specific employee concerns, to determine adequacy of welds produced by the Bru weldAng pens. m. and to provide additional data for determining the suitsbility o7 welding for restarting of the BFW units. 4.2 Scope The reinrpectier. focused or, safety-related systems and componehts of
*he plant exeert for there covered by the FS!!!.91 prohrnm. The ryrte ,r cevered by the PSI /ISI programs oire rkviewed and are included in APTECH's report "Weld Quality Review r^. Bror.e Terj/
TSe Plant" and are addressed in Section 3.P of this report > reinspection was performed in accordance with the "brocas ferry Nuclear Plant-Welding Project Reinspectitr ?lah" Atwachment 4.1 The discrepancies were evaluated in accordance with TVA Welding 4 Project Frocedurc WP-07, "Browns Ferry Nuclear Plant-DNE Plan for the Evaluation of Reinspection Results" Attachment 4.2. A total of
)
70 structural itens, 21 spiral welded duct butt welds, and 391 l mechanical piping welds were included in the reinspection. Information concerning the structural and mechanical welds reinspected is tabulated on the following pages. 1 DNE1 - 04 75N 1 11/6/87 m., . l. .r..,
Et!!4!4ARY OF STRUCTURAL WELDS REEXAMINED No. of Items IXEe Reinspected Welds of Pipe Supports (including mix instrumentation piping supports) 33 Welds of cable tray and conduit supports (including two each for electric pull box supports and electrical panels) 16 Structurally significant welds on miscellaneous structural steel (includes instru .cntation panel attachments to building steel, platform components, barriers, main steel items, monorails, and motor generator anchorage) 12 heating. Ventilating, and Air Conditioning (KVAC) supports 9 Total 70 h l 1 s 1 4 i d 2 DNE1 - 0475N 11/6/87 a is th
SUMMARY
OF PIPING WELDS REEKAMINED TVA Wo. Welds System Class Reinspected Materials PIPING Diesel Generator-Starting P 20 Carbon Steel Air (DCA) Diesel Generator-Fuel Oil P 12 Carbon Steel (DCFO) Diesel Generator-Emergency M&P 116 Stainless Steel & F,uipment Cooling Water Carbon Steel (EECW-DG Feactor buildint-Emergency P 31 Stainless Steel Equipment Cooling Water (EECm-he) kuel Fool Cooling (FPC) F 50 Carbon Steel & , Aluminum . ., instrument Sentint Lines (ISL) D&B31.1 66 Carbon Steel RHR DrLin Pump Piping (RME) F 25 Carbon Steel Residual Heat Removal E.M&P 54 Carbon Steel Service Vater (RXT. ' Reactor Building & Service Tunnel Radwaste System Piping (RW) F 10 Carbon Steel Reactor Building Standby Liquid Control (SBLC) E 7 Stainless Steel ; HVAC ! Standby Gas Treatment (SBGT) NA 21 Carbon Steel i Total 412 Note: TVA piping classes are defined in Specification C-28 (Attachment 4.5) f
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DNEl - 0475N 3 11/6/87 , 4,, ., . , :.;; , \**~~
4.3 Reinnection personnel. Quality Assurance, and Spacial criteria
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Personnel who performed the reinspection were given site specific training to familiarize th e with the reinspection plan the methods to be employed, and the specifications and acceptance criteria to be followed in performing the reinspection. Personnel performing the structural ard structural support reinspections were AWS Certified Welding Inspectors (CWIs). Personnel performing the piping reinspections were Level II inspectors enttified in accordance with SNT-TC-1A or equivalent (certification program for visual patterned after the fottat of Noncu truct h s 1.>.onination established in SNI- T;- 1/.) . An independent overview of thc rcit.gettion was performed by Bechtel personnel. The pipint reinspections were overviewed by a SNT-TC-1A Level 111 inspector and structural reinspections by an AWS CWI . The overviews confirmed compliance to the reinspection procedure and W rific' the accuracy of data collected. Reports of the independent overview inspectors are shown in Attachments 4.3 (structural) and 4.4 (piping). During the conduct of the overview, the AWS CW1 made additional observations which indicated problems in the welding program and the welder qualification program. These observations were concidered in the detailed Welding project technical evaluations of the corresponding issues raised by the employee concerns. I I 4 DNE1 - 04 75N 11/19/87
l In additicn to the specific ecquirements nstcd in thi impicmenting procedures, the inspectors confirmed the use of generic weldins f iller material using a magnet. Acceptability was based on the weld / filler j material being: carbon steci (magnetic), austenitic stainless steel (slightly magnetic or not magnetic), or aluminum (not magnetic). l Stainless steel welds exhibiting strong magnetic attraction were
'I confirmed as being stainless steel by measuring ferrite content using a Fisher ferritescope. The inspectors also perfomed a subjective evaluation of the general workmanship of the welder and rated the welder perfomance as: better than average, average, or unacceptable. The surface coating of sttvetural welds was noted.
Where painted thc paint thickness was measured and recorded. Coating on mechanical piping welds was removed for all reinspections. All data f ro:t visual reinspections were recorded on the foms included in Attachment 4.1. Supplemental sketches were prepared to provide specific as-built details if the details were not shown on the drawing, were different from those shown on the drawing, or a drawing did not exist. 4.4 Criteria for Selection of Welds to be Reinspected Th( u ketion of the welds to be reinspected was based on the following criteria: o Selection not statistically based. J o Provide a representative look at each of the classes of items to be reinspected. l o Cover the work of both construction and operations. o Cover the work of all crafts (e.g. pipefitters, ironworkers, etc.) i DNEl - 0475N 5 11/19/87
o Cover safety-related systems End structuras but exclude items covered by the PS;/ISI program. o Select items to minimize radiation exposure of the inspectors. o Cover the range of welded materials-(carbon steel, stainless steel, and aluminum) . o Cover various types of weld joint configurations in both piping and structures (e.g. , butt welds, fillets, sockets, etc.). o Select from all three units using piping and structural drawings, weld maps, flow diagrams, and a physical walkdown of each unit. o Select structural welds to include all positions in areas of lb ited accerritility. 4.5 Reinspection Procedures Current revicien ef TVA-approved nondestructive examination prvced.rer wert use; fv: piping reinspection with exceptions taken te reflect the criteria in effect at the time the wolds were originally inspected. The exceptions are noted in Attachment 4.1. St ruc tural wcld reinrpeetien was in accordance with TVA-approved procedures which ! reflect the NRC approved "Nuclear Construction Isrues Group" NCIG-01 kev. 2 "Visual Weld Acceptanco Celteria (VWAC) for Structural Welding at Nuclear Power Plants." l l A.6 Reinspection _Results ! Reinspection data have been tabulated and are shown in Tables . and 41 4.2 for the structural welds and Tables 4.3 and . 4 4 for e piping andth HVAC duct welds. f 6 DNE1 - 0475N 11/19/87
l l 4.7 Criteria for Evaluation of Rainspection D'tm 4.7.1 St ruc tural The results of the reinspection were evaluated by design engineers. The evaluation was conducted in two ways, structural and attribute. The structural evaluation considered i the suitability for service based on the adequacy of the weld to carry the loads within the design allowables. The attribute evaluation was performed as defined in the DNE plan for the evaluation of reinspection results (Attachment 4.2). Attribute discrepancies in excess of those allowed by NOIG-01 are showr. in the Structural Weld Attribute Summary in Section 4.8.1. The NCIG approved equivalency methodology wac used to derive the tabulated values. The attribute evaluation was performed independently of the structural evaluation and was not used to qualif y any structures for suitability for service. The structural evaluation consisted of a design reanalysis of the joint using data from the reinspection. The reanalysis was compared to the original analysis when available to assure that uniformity in design concept existed and that any new loads were identified and considered. For cases where the reinspection report confirmed compliance to the original drawing requirements, evaluation was not required. Calculations were performed to verify the adequacy of the as f constructed welds for those structures that did not have design I DNE1 - 0475N 7 11/19/87 i i
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drcwings (generally field dssign:d structurcs far fiold 1ccated or routed items) . l l 1 4.7.2 Mechanical i The results of the reinspection were evaluated by design engineers. The evaluation consisted of a two-step process. o Step one was an evaluation of the weld's attributes as determined by the reinspection. If the results of the reinspection were satisfactory, no further evaluation was required, o _S_ter two - Those welde with speelfic attribute indications were evaluated by the cognizant design discipline for their ability to carry the required loads within the design allowable stresses and consequently meet code requirements. A total of 412 wolds were reinspected visually and for generic filler metal type. In addition to the Visual (VT) examination, . 164 pipe welds also received Liquid Penetrant (PT) or Magnetic Particle (MT) examination and 30 pipe welds received a review of the weld Radiographic (RT) examination by re-reading the original film. 4.8 Assessment of Reinspection Results I 4.8.1 Structural Welds (Tables 4.1 and 4.2) l The structures included in the reinspection are from the following major categories:
- 1. Pipe Supports
- a. Process Pipe Supports
- b. Instrumentation piping Supports I
I 8 DNE1 - 0475W { 11/19/87 !
- 2. Electrical
- a. Electrical Pull Box Supports
- b. Electrical Panel Supports
- c. Cable Tray Supports
- d. Conduit Supports
- 3. Structural
- a. Structural Steel
- b. Miscellaneous Steel
- c. Instrumentation Panel Supports
- 4. HVAC Supports The reinspection results for each major category are described bc le. mi.h a discussion of the results.
' T'r Surforte - This category was further sudivided into twe sub-categories:
a, process piping Supports - There were 3,843 inches of weld reinsp2cted with 2,392 inches accepted by reinspection. There were 188 inches of weld which had no reportable indications and were accepted after determining that weld cire was suf ficient. There were 603 inches of weld which had indications that were found to be acceptable after an engineering evaluation,
- b. Instrumentation Piping supports - There were 149 inches of weld reinspected. None of the welds were accepted as reinspected. Eighty-seven inches of weld had no reportable indications and were accepted after determining that weld size was sufficient. Twenty-one inches of weld had indications that were found to be 4 acceptable after an engineering evaluation. Sixteen i DNEl - 0475N 9 11/19/87
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l inchas of wcld ware ettsched to structuras d:termin!d by engineering-to be unstable for seismic loading. i Twenty-five inches of weld required rework to conform ' to design requir?nents. Evaluation of the results of the reinspected items indicates a deficiency exists in instrument piping support welding in that two of the six supports reinspected were determined to be unsuitable for service for seismic loading. The suitability for continued service of the instrument piping supports and associated wolds has been proven adequate by some 45,000 hours of operating history for Unit 3 with approximately 56,000 f or unit 2 and 60,000 for Unit 1. The adequacy of the instrumentation piping supports for scismic loading will be , assured by TVA's program of "Small Bore pipo Reconciliatiot. program," PI 87-40. The evaluation will include welding and weld attributes. Therefore additional investigations by the WP are not required.
- 2. Electrical - This category was further subdivided into four sub-categories:
- a. Electric Pull Box Supports - There were 86 inches of i weld reinspected. None of the welds were accepted as reinspected. Fifty-eight inches of weld had no reportable indications and were accepted after determining that weld size was sufficient.
Twenty-eight inches of weld were accepted after an engineering evaluation.
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1 i i DNR1 - 0475N 10 11/19/87 i
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- b. Elcetric Pinal 0.pports - Thers wera 82 inchss of weld reinspected. Eighty-one inches of wcld were accepted by the reinspe? tion and one inch was accepted after an engineering evaluation.
l e Cable Tray Supports - There were 392 inches of weld reinspected with 345 inches accepted as reinspected. Thirty-seven inches of weld had indications that were ' found to be acceptable after an engineering evaluation to the original design requirements. Ten inches of ; weld were deemed acceptable for interim (start-up) service. The long term qualification of these structures will conside: welding as part of the program. Therefore, additienal investigations by the WP are not required,
- d. Conduit Supports - There were 632 inches of weld reinspected with 598 inches accepted as reinspected.
Thirty-four inches of weld had indications that were found to be acceptable after an engineering evaluation. Therefore, additional investigations by r the Welding project are not required. l I 3. Structural I
- a. Structural Steel - There were 529 inches of weld 1
reinspected with all 529 inches of weld accepted as reinspected. Additional investigations by the WP are not required.
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l DNE1 - 0475N I 11 11/21/87 f 1
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- b. Miscellcnsous - Th;ro wcrs 1.813. inches cf weld reinspected with 1210 inches of weld accepted as reinspected. There were 413 inches of weld that had no reportable indications and were accepted after determining that weld size was sufficient. There were 100 incher of weld that were accepted after an engineering evaluation. I
- c. Instrumentation panel Supports - There were 367 inches i l
of weld reinspected. Forty-eight inches of weld were ' accepted by the reinspection. There were 313 inches of 1 weld that had no reportable indications and were accepted after determining that weld size was sufficient. Six inches of weld were accepted after an engineering evaluation.
- 4. HVAC Supports - There were 682 inches of weld reinspected l I
with 464 inches accepted as reinspected. There were 206 ' inches of weld that had indications that were found to be acceptable after an engineering evaluation. Twelve inches of weld was attached to structures determined by engineering to be unstable for seismic loading. Evaluation of the reinspection data shows that the HVAC supports meet design requirements with two exceptions. Items WP-C-BFN-25 and -26 were determined to be unstable under seismic lateral loading. In the period from 1970 to 196b various reviews of HVAC supports were undertaken by TVA I DNE1 - 0475N 12 11/21/87
including th2 WP roinsp;ction. Th2 ccnelusion escch:d by these reviews and reinspections is that a number of HVAC supports are not adequatoly designed and built for lateral seismic loading. Items 25 and 26 were found to be adequate to carry the vertical seismic and vertical deadloads. However, the portion of the support which was designed to resist the seismic lateral load was unstable and therefore, the welds associated with this portion of the support were not analyzed. TVA's planned Scismic Qualification Program for Browns Ferry implemented as the result of Significant Condition Report SCR BFNCEB8603 will include evaluation of structurally significant weld attributes. Therefore, additional investigations by the Welding Project are not required. As noted previously, a weld attribute evaluation was performed. The results are shown below: STRUCTURAL WELDS - ATTRIBUTE
SUMMARY
BASED ON REINSPECTION RESULTS Inches of Weld Weld Attribute Inches Percent (%) l Attribute Reinspected Acceptable Rejectable Acceptable Rejectable Size 8575 7635 940 89.03 10.97 Incompletc Fusion 8575 8549 26 99.69 0.31 Overlap 8S75 8573 2 99.98 0.02 Craters 8575 8536 39 99.55 0.45 1 Undercut 8575 8547 28 99.67 0.33 l Correct k Filler Metal 8575 8575 0 100.00 0.00 l DHEl - 0475N 13 11/19/87
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Even though 11% (940 inchts) cf the w31ds coinsp:cted wero rejected for size, only 21 inches (for instrument piping supports) require rework (additional weld metal deposited). l The balance of the attribute inches reported i.e. Incomplete fusion, overlap, cratere, profile, and undercut amounted to 95 inches or 1.1% of the total.
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Except for size, none of the attributes had a significant ef fect on the structure's ability to meet design requirements. In addition to the attributes noted above, one characteristic l "No Weld" was reported as part of the reinspection. This characteristic can be further subdivided into Underlength and Missira Welds. 1 Underlength is the length that e given weld is short of cc ., re v. i re cr.te , i.e. weld length required minus weld length provided. Underlength welds constituted 4.4% of the 1 I weld reinspected. Underlength welds (326 inches) were randomly located in all structures. However, two structures l accounted for the major amount (244 inches) of underlength. ! l An electrical panel, item 43, required by drawing I approximately 200 inches of continuous fillet weld. The "as-built" connection was made with an intermittent fillet which eliminated 170.5 inches of weld. The engineering evaluation shows that the "as-built" configuration providec a 3 DME1 - 0475W 14 11/19/87
l l connaction thet meats d: sign requircments. Tha "as-built" condition of a HVAC support, item 1, had 13.5 inches of weld ! l underlength. The engineering evaluation shows that the l "as-built" configuration, however, provided a structure that meets design requirements. A weld is considered missing when the entire weld indicated by a weld symbol is absent. Missing welds constituted 0.78% of the welds reinspected. All af fected joints with reported missing weld meet design requirements af ter engineering evaluation. The lack of adequate welding details on the drawinge (when they existed) wac a contributor to this problet.
. During the reinspection of structural items, certain welds were reported as "inaccessible." Where the presence of the weld could not be verified, inacccessible welds were considered not to exist and credit was not taken in the design evaluation of the load carrying capabilities of the welded connection.
Considering the structurally significant attributes. 99.4% of the linear inches of reinspected structural weld is ; acceptable based on reinspection and engineering evaluation. The balance of 0.6% is composed of two categories: < l 1 o Weld acceptable - Structure deemed unstable 0.3% ; o Rework required 0.3% j
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DME1 - 0475W 15 11/19/s7 i
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Th3 Welding Projcet has datcrmint.d th t weld charactoristics other than size, length, end location are not a significant problem with structural welding at BFN. THE RESULTS OF THE REINSPECTION AND AN ENCINCCUING EVALUATION OF THE REPORTABLE _ IMPERFECTIONS CONFIRM THAT A HIGH PERCENTAGE OF THE REINSPECTED WELD _ JOINTS MEET DESIGN REOUIREMENTS. IN THE INSTANCES WHERE THE WELD JOINTS DID WOT HEET SEISMIC DESIGN REQUIREHENTS. ENGINEERING OUAI,IFICATION PROGRAMS ARE PLANWED THAT WILL IDENTIFY AND CORRECT WELDING DISCREPANCIES. THEREFORE ApDITIONAL REINSPECTIONS ARE NOT REQUIRED. 4.E.2 Hoehanical Welds (Tables 4.3 and 4.4) The at.alysis of the mechanical reinspection results show that ot t l. . sv 16 e ec.nspceted, 360 (6).4%> had no reportable indicationr and were accepted ac reinspected. The retaining 52 welds had indications which warranted further evaluation by Engineering. All were subsequently accepted. The wolds carry the required loads within the design allowable stress and consequently, meet code requirements. Engineering evaluated these 52 welds for the attributes shown in Appendix 4.1. All welds were accepted by calculation or engineering evaluation techniques. However, eight welds
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DME1 - 0475N 15 12/17/R7
- v. . mm -
ecquired cdditienal inv:stigOtton by grinding er filing to characterize the identified indication for engineering evaluation. (A detailed account of these welds is given in Appendix 4.1.). Eleven of the 52 welds had indications not covered by the attributes of Appendix 4.1 or code requirements. All 11 welds art acceptable by engineering evaluation. (A detailed account of these welds is given in Appendix 4.2.). The review of the radiographs for 30 pipe welds identified that several criginal or repair radiographs were not readily avhilable from the plant record system. The inspector identific.' and reported this as a rejectable condition. This condit ion was resolved when the records were located. The radiographs were determined to be acceptable. The reinspection identified one weld (T-RHRS-3-18) with rejectable radiographic indication that was not noted on the oriE inal reader sheet. Engineering evaluation was performed by usinr. RT and UT examination and excavation of part of the weld to characterize the indication. This weld has been , determined to be acceptable. (A detailed account of this I condition for weld T-RRRS-3-18 is included in Appendix 4.3.) The weld attribute summary for nochanical welds is shown on thn following page.
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4 DNE1 - 04 75W ' 17 11/19/87 {
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PIPING AND DUCT BUTT WELDS - WELD ATTRIBUTE
SUMMARY
FROM REINSPECTION REPORTS No. Welds No. of Attributes Attribute Erinspected Acceptable Rej ec table % Weld Attributes Acceptable Rejectable A. Cracks 412 412 0 100.0 0.0 E. Contour / Transition 412 410 2 99.5 0.5 C. Offset / Alignment 412 412 0 100.0 0.0 D. Unde:iat 412 404 8 98.1 1.9 E. Reinforcement (Butt Welds) 234 226 8 96.6 3.4
- k. Spatter / Arc Strikes 412 412 0 100.0 0.0 1;
tillet/Sockc' Weld Size 118 163 15 91.6 8.4
) LL . s. Euston 412 406 6 98.5 1.5 j, Ov e .u, 412 409 3 99.3 0.7 M. Underfill 412 404 8 i
98.1 1.9 N. { Surface Porosity 412 407 5 98.8 1.2
- 0. Slag 412 409 3 99.3 0.7 RK. Radiographic- 30 29 Lack of Fusion 1 96.7 3.3 Y. 1.inear Indications 1 412 412 0 (Weld Metal) 100.0 0.0 TOTAL ATTRIBUTES 4974 4915 59* 98.8 1.2
*All rejectable attributes were shown to be acceptable by engineering evaluation .
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18 DNE1 - 0475N 11/13/87
The table below shows additional attributes reported that do not advctsely affect weld quality. Welds Attributes Indication Reinspected Acceptable Rej ec t able* I. Base Metal Indications 412 406 6 T. Overheating 412 411 1 U. Improper prep for PT or HT 185 183 2 V. Base Metal / Weld Metal 39 39 0 (Ferritt headings of SS Welds) W. Base Metal / Weld Metal 412 412 0
- 2. Weld Covering Threade 2 0 2
$A1! rejectable attributes were shown to be acceptable by engineering evaluation.
1 In summary, the NDE indications and visual imperfections i ider.lified during the reinspection are not injurious or in any way j l detriments 1 to the function of the welds. All 391 piping welds and the 21 duct butt-welds are acceptable. THE RESULTS OF THE REINSPECTION AND THE ENGINEERING EVALUATION AND DISPOSITION OF THE REPORTABLE CONDITIONS CONFIRM THAT THE REINSPECTED MECMANICAL WELDS HEET CODE REQUIREMENTS AND ARE ACCEPTABLE FOR USE: THEREFORE. ADDITIONAL REINSPECTIONS ARE NOT REQUIRED. k DNEl - 04/SN 19 11/6/87 l . _ m.,,n gy-~~ ~ -
l 4.8.3 Ovsrall Assassment as Related to Employee Concerns I The Employee Concerns (as listed in Attachment 6.1) indicated potential problems related to various aspects of welding. The concerns have been addressed through the Phase I and Phase II Welding Project activities. The reinspection ecaults do not substantiate the specific or non-specific employee concerns with the exception of BFN-8 5- 019- 001. The percentage of weld size (size, length, and location), identified as rejectable in the structural weld attribute sumary of Section 4.8, gives support to the question of adequacy of welds and hangers expressed in BFN-85-019-001. i EnLinm ing evaluatione of 940 inches of weld rejected for size ! C T- . ' t in only 25 inches of weld requiring rework for seismic loading requirements. The requirements identified in the commitment section of 6.6 will address the concern and provide
-"mrtive action required.
The reinspection data indicated that: o Generic control of filler material was accomplished, o Overall weld quality is commensurate with the industry practices in effect at the time the work was performed, o No cracks were identified and porosity was minimal indicating that electrode moisture control was effective, o The equipment used was adequate.
]
DMEl - 0475W 20 11/13/87
4.8.4 Reinspection Overview by DNOA A surveillance of the Welding Project reinspection ef forts by the DNQA BFN Site Quality Manager's Staff resulted in a Corrective Action Report (CAR) (BF-CAR-87-0043) being issued. The CAR stated that WP personnel did not alweys adhere to the requirement for reinspection and that the reinspection personnel were not always accurate in identifying the discrepant conditions. The WP agreed that some of these conditions did occur. However, it has been concludsd that the intent of the reinspection effort was accomplished and that no ccrrective action by WP was required. The surveillance report by the Quality Manager's Staff indicated that the inspectors were qualified and did an effective reinspection. ;;nce weldirt inspection often involves a subjective evaluation, occassional dif ference of interpretation is to be expected and is not a matter for concern. Discrepancies were identified that were not reported in the reports of the WP reinspection. After additional investigations and evaluations, all of the discrepancies reported in the CAR were found to have no affect on the WP results or conclusions. 4.9 Root Cause Evaluation and Corrective Action Analysis to determine the root cause and required corrective action of each significant variant has been performed. For the pipe and duct welds, there were no significant variants to be considered. DNEl - 0475N 21 11/6/87
- . .. .. n . ,,. ~ - . . - -
The significant variants in the structural rainspncticn d:ts th t required a root cause analysis are:
- 1. Weld Undersize
- 2. Weld Underlength
- 3. Weld Missing Weld was reported as being undersize for 10.97% of the reinspected weld. Considering the circumstances of the reinspection and the time of neiginal construction, this rejection rate is to be expected. The methods and tools for reinspection were not the same as those in use in the initial inspection. Typically, the original inspector did not perf orm detailed measurements of each weld but evaluated weld size on basis. Corrective action for undersize welds is not
.m..
the engineering evaluation determined that all items a with under size wold meet original design requiremente but not necessarily the loads due to seismic upgrade. To ensure that structural evaluations are based on as constructed data, TVA is instituting a requirement that weld size, length, and location be determined in all programs at BFN that require a walkdown to obtain data for structural evaluation. Weld was reported underlength for 4.4% of the weld reinspected and , less than 1% for weld missing. The root cause for underlength and weld missing lies in the manner in which information was presented on the drawings and the interpretation of the drawing and specification requirements by the cunstruction engineers, craf tsmen, and , 1 DNEl - 0475N 22 11/13/87 i l l l
inspectors. The drawing requirements were not always depicted in a I clear manner as was noted in the Phase I review. The requirements for wrap around and starts and stops were not always interpreted in the I same manner as today. Corrective action for underlength is not required since the engineering evaluation determined that all items i with underlength or missing welds meet design requirements. As noted above, TVA is instituting a requirement that weld size, length, and location be determined in all programs at BFN that require a walkdown to obtain data for structural evaluation. 6 i DNEl - 0475N 23 11/6/87
....w._,,,,.... . , . ~. _ ._ _
TABLE 4.1 Table 4.1_is a compilation of the reinspection data by structure type showing the total number of eeet type structure included in the reinspection effort. The table also shows the inches of weld reinspected for each type structure and the baris of acceptability of the weld.
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i l l TABLE 4.2 Table 4.2 !! e listing of the reinspection data for structural welding showing weld number, size, type, drawing number, organization performing the weld, and inspection / reinspection dates. The table also shows the unit, type of structure, item number, and the basis of acceptance of the weld. l l 1 l i l I DNE1 - 0374N
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! c5 'PFN-04: F1 & 84 : WE : 6.50 : : .
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I ' PC :9eN-Ca' P: 1 93 l0.188 0.188 FILLET: FILLET: 473454-5 . lie : 8.03 : : : : : :
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E3 :0.250 0.188 l FILLE!: FILLET: a;pr54-3 : y :06r0'5:08 ? C 'hWE : 7.25 : : : : : : 2 : PS :9r4 .15: E4 :0.250 l0.!88-: FILLET: FILLET: 8'P854-3 ' 1 '06T 75:080:4 7 . 'S :Prv.p5- :W : '.50 : F1 l0.188 l0.188 l FILLET FILLE ** 4?P854-3 : N l06f: 5:08r F': 'n ! : '.25 : : : : : : ; 2: PS 8c1-05' F2 l0.188 l0.188 l FILLET; FILLET: 573a54-; ' g 069"5'08^:b 2 : FS :Pr M 5 F lWE : '.5c : * *
- 0.188 l0.188 l FILLET: FILLE!! 47E454-3 : M:06r!'5:0ENE*: ;WE : 2.25 ' : :
2
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!O.188 : N TT l FILLET: 47?s54-3 : 1 066 75?0232M : t?'E 2 : nE : '.25 : : : :
2
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- 4 206r:75:08r:86: :n i ; i.:5 :
2 : PS :8Fv-05: : : : : : : H3 : !0.188 : NTT ' FILLE 479:5a-3
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- 0.250 l0.108 l FILLET: FILLET: '7Pc5a-3 ' N !O60:75:0er-gy : w i : .25 :
2 : 'S !?'* 45: : : : : : :
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PS : Pet-05: H6 : 0.250 :0.!88 : FILLET FILLE" 879154-!
- N l06 C 75:0B# FC :WE : 125 : : :
2: PS 53tt-05: J1 : : : : : l0.188 : NTT FILLER 473834 ' ' N l060'75:09?2M *C'E 2 lWE : 2.25 : ' 7 ' FS :Pr445 J2 : : : : l0.188 : NTT ' FILLE': 87E454-3 *N:06r-'5:0E6?FC %C E 2 lHE .6' : *
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l0.188 : NTT lFIRET: 479 54-3 * % '060:75'00M8C %C'E 2 lWi : 2A3 ! :
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