ML19207B860
| ML19207B860 | |
| Person / Time | |
|---|---|
| Issue date: | 08/14/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19207B849 | List: |
| References | |
| NUDOCS 7909050437 | |
| Download: ML19207B860 (2) | |
Text
. -
TOPICAL REPORT EV/;.UATION O
Report Nunber:
TVA-TR75-1A, Revision 3. Nonproprietary Report
Title:
Quality Assurance Program Description Report Date:
August 11, 1977 Revised August 1979 Originating Organization:
Tennessee Valley Authority Reviewed by:
Quality Assurunce Branch SU""ARY OF TOPICAL Topical Report TVA-TR75-1A, Revision 3, describes the quality assurance progra'n which the Tennessee Valley Authority applies to those design, procc.ement, cons.truction, preoperational testing, and. cperations phase activi ties involving safety-related structures, systems, and components of nuclear po; er plants.-lithin the TeEnessee Valley Autiority scope of work.
TVA-TR75-1 A, Revi;4 cn 3, commi ts the Tennessee Valley Authority to comply slith the requirements of Appendix B to 10 CFR Part 50.
It also commits the Tennessee Valley Authority to follow the NRC Regulatory Guides and ANSI standards listed below or has provided alternatives which the s taf f has found acceptable.
Design &
Construction Caeration Regulatory Gui e 1.8 NA 9/75 1.28 6/72 3/78 1.30 B/72 8/72 1.33 NA 2/78 1.37 3/73 3/73 1.38 10/76 5/77 1.39 10/76 9/77
'.58 P/73 8/73 1.64 6/76 6/76 1.74 2/74 2/74 1.83 10/76 10/76 1.94 4/76 4/76 1.116 6/76 6/76 1.123 10/76 7/71 ANSI N45.2.12 (D3, R4) 2/74 2/74 The Tennessee Valley Authority has provided for our evaluation a detailed organi-zational description of those individuals and groups involved in carrying out activities recuired by the quality assurance program and a delineation of duties, responsibilities, and authority of those organizational elements involved in the quality assurance program. Revision 3 of TVA-TR75-l A contains a description of the measures used to carry out the Tennessee Valley Authority quality assurance EiL4028 roomors 7
.c.
program activi ties and describes hed applicable requirements of Ippendix 5 10 10 CFR Part 50 will be satisfied by the adainistration and iglea.entation of these measures.
3UWiARY OF REGULATORY EVALUATION AND POSITION We have evaluated t..e quality assurance progra n and the organizations responsible for quality assurance functions described in Revision 3 of TVA-TR75-1A.
We find that quality assurance policy and direction originate at an acceptably hign managen.ent level and are effectively communicated to other parts of the organizdtion.
Those performing quality assurance functions have responsibility and authority commensurate with their duties in implementing the program. We also find that measures have been established to be implemented by written procedures and instructions, which address each of the criteria of Appendix B to il CFR Part 50 in an acceptable manner.
Based on our review and evaluation of TVA-TR75-1A, Revision 3, we conclude that:
1.
The organizations and persons perfonning quality assurance functions within the Tennessee Valley Authority have the required independence and authority to effectively carry out the quality assurance program wishout undue influence from those directly responsible for costs and schedules.
2.
The Tennessee Valley Authority quality assurance program contains roquirements and cnatrols which, when properly implemented, comply with the rcquiren.ents of Appendix B to 10 CFR Part 50.
3.
The Tennessee Valley Authority Topical Report 71A-iR75-1 A, Revision 3, " Quality h
Assurance Program Description," is acceptable for use in the design, procurment, construction, preoperational testing, and operations phase activities of TVA's nuclear power plants.
3.!A02S
TVA-7R75-1 Fev. 3 TAELE OF CCNTENTS Secticn Title Faqe 17.0 QUALITY ASSUFANCE 17.0-1 Introduction 17.0-1 Policy 17.0-2 17.0.1 TVA Crqanizaticn 17.0-3 17.0.1.1 Board of Dir?ctors.
17.0-3 17.0.1.2 Office of the General Manager 17.0-3 17.0.1.3 Office of Power 17.0-3 17.0.1.4 office of Nanagenent Services.
17.0-3 l3 17.0.1.4.1 Divisicn of Purchasing.
17.0-3 l3 17.0.1.5 Office of Engineering Design and Ccnstructicn.
17.0-4 17.0.1.6 TVA CA Program Assessment 17.0-4 l3 17.0.1.7 Interoffice Lines cf Communication.
17.0-4 17.0.1.8 TVA CA Steering Connittee.
17.0-4 l3 LIST OF TAELES l3 Table Title l3 TVA Interdivisional Cuality Assurance Procedures l 3 17.0-1 LIST OF FIGURES FiqurE Title 17.0-1 TVA Crganization iii 32.4030 8-79
(
TVA-TR75-1 Soction Tit to Pg 17.1 QUALITY ASSUFANCE DTIFING CESIGN A@
CGNSTRUCTION 17.1A-1 17.1A Quality Assurance - Office of Engineerino Desion and construction 17.1 A-1 17.1 A.1 arcanization 17.1A-1 17.1A.1.1 Office of Engineering Design and Construction (OEDC) 17.1A-1 17.1A.1.1.1 Manager of the Office of Engineering Design and Construction 17.1A-1 17.1A.1.1.2 Quality Assurance Manager 17.1A-2 17.1A.1.1.3 Quality Assurance Supervisors 17.1A-4 17.1 A.1.1. 4 CEDC Quality Assurance Committee.
17.1A-5 O
17.1A.1.2 Division of Engineering Design 17.1A-5 17.1n.1.2.1 Director of Engineering De s ig n 17.1A-6 17.1 A.1. 2. 2 EN DES Quality Engineering Branch.
17.1A-6 17.1 A.1. 2. 2.1 E'1 DES Q"31ity Assurance Group.
17.1A-7 17.1A.1.2.2.2 EN DES Q lity Control Group 17.1A-9 17.1A.1.2.3 Thermal Power Engineering Branches (Mechanical, Electrical, and Civil) 17.1A-10 17.1A.1.2.4 Thermal Power Engineering Design Project 17.1 A-15 17.1A.1.2.5 Architectural, Hydro, and Special Projects Engineering and Design Branches 17.1 A-16 iv 914031
TVA-TR75-1 Fev. 3 TAELE CF CCNTENTS Secticn Title Faqe 17.2 QUALITY ASSEBANCE FECGFAM FCE STATICN CFEFATICN 17.2-1 17.2.1 C rqa niz a t icn 17.2
- 17.2.1.1 Cffice cf Ecwer 17.2-1 17.2.1.1.1 Assistant Manager cf Pcwer.
17.2-2 17.2.1.1.2 Quality Assurance Manager 17.2-2 17.2.1.1.3 Fegulatory Staff 17.2-6 17.2.1.1.4 Eivisicn of Fuels (FUELS) 17.2-7 17.2.1.1.5 Manager, Fewer Cperaticns 17.2-7 2
17.2.1.1.6 Division of Fower Froduction (F FFCE) 17.2-7 17.2.1.1.7 Division of Power System CpErations (FSC) 17<2-15 17.2.1.1.8 Divisien of Cccupational Health and Safety.
17.2-15 3
17.2.2 Cperational Quality Assurance Progran.
17.2-16 17.2.3 Mcdificaticn Centrol.
17.2-19 17.2.3.1 General 17.2-19 17.2.3.2 As-Euilt Verificaticn 17.2-19 17.2.3.3 Modification.
17.2-19 17.2.4 Frocurement Document Contro_1 17.2-21 Secticn Title Fage 17.2.5
_ Instructions,_rrocedures, and Erawings,
17.2-23 xi G3-n '3 0 a.s.'j G O 4 g
8-79
TVA-TR 7 5-1 O
Section Title Page 17.2.5 Instructions, Procedures, and Drawings. 17.2-23 17.2.6 Document control.
17.2-25 17.2.7 Cont rol of Purchased Material, Equipmen+, and Services 17.2-27 17.2.7.1 General 17.2-27 17.2.7.2 Source Evaluation and Selection 17.2-27 17.2.7.3 Inspection and surveillance at Vendor Flant 17.2-28 17.2.7.4 Receiving Ins pection
- 17. 2-29 17.2.8 Identificat ion and Control of Material,
,Part s, and Components 17.2-31 17.2.9 Control of Special Frocesses 17.2-32 17.2.10 Inspection 17.2-33 lll
- 17. 2. 11 Test Control 17.2-35 17.2.12 Cont rol o' Measu 3; q and Test Equipment 17 2-37 17.2.13 Handlina, Otorace, and shipping 17.2-39 17.2.14 Inspection, Test, and Operating Status 17.2-40 17.2.15 Nonconforming Materials, Parts, or Comoonents
- 17. 2-42 17.2.16 Adverse Conditions and corrective Action 17.2-44 17.2.17 Quality Assurance Records 17.2-46 17.2.18 Audits 17.2-48 xii O
314033
TVA-TR75-1 Rev.3 LIST OF TABLES Table Title 17.2-1 office of Power - QA Manuals Chart 17.2-2 Co, trolled Procelures and Instructions 17.2-3 of fice of Power Procedures Which Impl ement 10 CFR 50, Appendix B 17.2-4 of fice of Power Quality Assurance Procedures 17.2-5 Division of Power Production Operational Quality Assurance Proceduren 17.2-6 Controlled Documen+ s 17.2-7 Commitments for Quality Assurance During Station Operation LIST OF FIGURES mm g
Fiqure Titlo 17.2-1 TVA Organization for Operational Quality Assurance 17.2-2 Power Plant Maintenance Branch Organization Chart 17.2-3 Ouality Assurance Lines of Audit
- 17. 2-4 Oftice of Power Quality Assurance and Audit Staff Organization 17.2-5 Flow Diagram - Design Change Requests 17.2-6 Flow Diagram - Design Change Request for Core Components 17.2-7 Flow Diagram - Field Change Request 3
xiii 31.4034 9
A
19A-TR75-1 Fev. 3 O
LIST OF ABEPEVIATICNS The folicwing abtreviations are used in this report:
ANSI American National Standards Institute ASME American Society cf Nechanical Engineers CASE Coordinating Agency fcr Supplier Evaluation CEO Ccnstruction Engineering CrganizaticU CFR Code of Federal Regulations CSB Construction Services Eranch CSSC Critical Structures, Systeas, an3 Ccmponents CCNST Eivision of Construction DER Design Eeficiency Report CCNST-CAP Eivision of Construction Quality Assurance FICCedure CCNST-CCF Eivision cf Construction Cuality Ccotrcl Frccadure DCR Cesign Change Request EN DES-QAF Division of Engineering Design Cuality Assur.~e Procedure EN DES Civisico of Engineering Design FCC Functional Configuration Ccntrol FCP Field Ctange Beouest l3 F SAF Final Safety Arslysis Repcrt FUELS Civisicn of Fuels GSB Geologic Services Eranch l2 IE-QAP Interdivisional Quality Assurance Frocedure Ic'i Indefinite cuantity 7ern MEDS Management and Engineering Cata Syster MIQP Manuf acturing and Installaticn Cuality Plan NCR Nonconfermance Feport NDE Nondestructive Examination NEG Nuclear Systems Engineering Group NLS Nuclear Licensing SECtion NFC Nuclear Pegulatcry Ccarissicn NESS Nuclear Steam Supply Systen OEDC Cffice cf F.ngineering Design anc Constructicn OIE Office cf Inspection and Enforcement CNFF Cffice cf Nucleas EEaCtor FegulatiCn PCFC Flant Operations Feview Ccanittee FCWEF Cffice cf Pcwer P PEOE Division of Power Prcducticn PEAR Preliminary Safety Analysis Repcrt FSO Civisicn of Fower Systen Cperations QA Quality Assurance QAC CEDC Guality Assurance Cognittee QAS-CAP OEEC Quality Assurance Staff - Cuality Assurance Procedure CC Cuality Contrcl xiv 8-79
TVA-7R75-1 Fev. 3 CCRU Quality Control and Fecords Unit QEB Guality Engineering Branch PG Fegulatcry Guide BFV Feactor Fressure Vessel SAR Safety Analysis Fepcrt SNEL Singletcn Materials Engineering Latcratcry SCCDL System Configuration Control Drawing List l3 TVA Tennessee Valley Authority 9
XV 314036 8-79
TVA-TF75-1 Fev. 3 17.0.1 ivA Organization The overall relationship among the principal TVA 3
organizational eierents is shcwn in Figure 17.0-1.
i 17.0.1.1 Ecard of Citectors.
The Ecard of Cirectors is vested with all the powers of the Corporation.
It establishes general policies and programs; reviews and appraises progress and results; and approves projects, programs, and specific itens of major importance.
17.0.1.2 Cf fice of the General Manager.
The General Manager is the principal TVA administrative cf ficer.
He serves as liaiscn between the Ecard and the offices and divisicns in the handling of matters of Board ccncern and is responsible for coordinating the executicn of programs, policies, and decisions which the Board of Directors approves or adopts.
17.0.1.3 Cffice of Power.
The Office of Power has overall esponsibility for the TVA power program.
FCKEF's organizaticnal scructure and responsibilities are discussed in secticn 17.2.1.
- 17. 0.1. 4 C f f ice o f Management Services.
The Cffice of Fanagenent Services plans and ranages logistical and administra tive management support services tc TVA programs and organizations.
It prcvides building, of fic(, l.and acquisition, ccmputing, and transportation services and provides for law enforcement and the protection of TVA property.
It develops and adrinisters policies and proccoures relating to finances and fcr prccurement, 3
transfer, disposal, and stipping cf equipment, materials and services needed by TVA.
It is also respcnsible for the radiological hygiene program at operating nuclear plants.
17.0.1.4.1 Division cf Purchasing.
The Civisicn of Purchasing within the Office cf Nanagement Services administers all procurements but is nct responsible for deterrining the technical and quality assurance requirenents of any procurement; these requirements are attained from or established by, and are administered by, the crganization initiating the procurement.
2ne Divisicn of Purchasing i' respcnsible for preparing end issuing the Invitaticn to Eid; opening and reading tids it.
public; evaluating responsiveness to the terms and conditiocs; submitting the bids tc the requisitioner for technical a..
quality assurance evaluation and reccamendaticns; ottaining the necessary administrative approvals; awarding and issuing contracts; and ns,getiating and naking changes of contract.
A ccntracting officer is naaed for each contract by the Civisicn of Purchasing.
The ccntracting officer is responsible for assurinc that provisions of the contract are met.
Changes affecting 17.0-3 8-70 SJAOSP
TVA-TR75-1 Fev. 3 9
techt cal or quality assurance requirLmentf are approved by the requis'
- ning organizi. tion and the contracting officer.
These respo. itilitien are Lefined by interc visional procedures listed 3
i in Tatle 17.0-1.
17.0.1.5 Cffice cf Engineering Desion and Construction.
The Office of Engineering Design and Ccrmtruction (CEEC) has design and ccnstruction responsibilities for majcr projects in the overall TVA prograr, including nuclear power plants.
CEEC's organizational structure and respcnsitilities are discussed in secticn 17.1A.1.
17.0. 1.6 TVA CA FFCGFAM ASSESSMENT.
The Office of Pcwer and OEDC at least ainually will either jointly or separately ccnduct independent managerent reviews of selected parts of their respective pcrtions of the TVA QA Frogram to assess its sccre, implenentation, and effectiveness and to assure that each scrtion is meaningful and affectively complies with Appendix E.
A review of all parts of the TNA CA prcgran will te completed in a two year cycle.
Feports cf these reviews will be made to the Nanager of OEEC and the Manager of Power for their acticn.
In addition to the reviews descrited above, the QA prcgrams are reviewed cn a continuing basis by the Manager of CEEC as descrited in secticn 17.1A.1.1.1 and the Assistant Manager of Eower as descrited in secti.cn 17.2.1.1.1.
17.0.1.7 Interoffice lines of Com:unication.
To assure proper overall direction of the CA programs and resolutica cf CA problema, lines cf communication have been established tetween the Manager of Quality Assurance for CEDC and the Manager cf Quality Assurance fcr the Office cf Power.
Audit reports are exchanged between organizations, procedures and instructions are exchanged fcr review, audit team members a.e exchanged fcr audits of interface functicns, and periodic ranagement meetings are teld to discuss and resolve mutual problems.
Table 17.0-1 is a 3
listing of TVA Interdivisional cuality Assurarce Procedures.
- 17. 0.1.8 1NA_$A Steer ing Ccami_t tee.
A TVI. Quality Assurance Steering Committee hos oeen ese blished to assure uniforn interpretation and application cf the quality assurance Eclicies of TVA and requirerents established by regulations, codes, and standards.
The ccamittee is conprised of executive, line, and CA management menters f rca appropriate of fice level and divisicn level organizations.
-n carrying cut its objectives, the committee:
keeps nemt rs mutually inforned en nuclear industry-related quality issues; recommends new quality assurance policies; reviews quality trends and reccarends carrective action; censiders and reccmaends sclutions to interdivisional quality assurance protlems; arranges independent nanagenent 17.0-4 314038 8-79
19A-TR75-1 Fev. 3 revieks of the CA prcgrams; and recommends ways of improving the effectiveness of these prograns.
3 17.0-5 93.4039 8-79
IABLE 17.0-1 (sheet 1)
TVA INTERDIVISIONAL QUALITY ASSURANCE PROCEDURES Criterion I - Organization ID-QAP-1.1 Preparation, Review, Revision, and This procedure defines the responsibilities and Approval of Interdivisional QA procedures for preparing, reviewing, revising, Procedures and approving TVA interdivisional quality assurance procedures.
ID-QAP-1.2 Transfer of Construction and This procedure covers the transfer of design and Engineering Design Responsibilities construction responsibilities at various milestenes as construction is completed, systems or subsystems are trsnsferred
_o P PROD, and the unit is operated and maintained by P PROD.
ID-QAP-1.3 Work Control Thit procedurc defines and implements the responsi-bilities and functions of EN DES, CONST, and P PROD for controlling work on unlicensed units.
Criterion II - QA Program ID-QAP-2.2 EN DES-P PROD-CONST Interfaces and This procedure establishes the policy for interface Responsibi!ities During and Following and responsibilities of EN DES, CONST, and P PROD Zransition from Design and Construc-during and following the transition from design and tion to Operation construction to operation of a nuclear power plant.
(O 1D-QAP-2.3 Physical Interfaces Between Licensed This procedure defines the responsibilities and
>=
and Unlicensed Units the functions of EN DES, CONST, and P PROD in Ek identifying and maintaining physical and functional
$h interfaces (separation) between licensed and
- [
unlicensed units.
%s ID-QAP-2.4 Future Modification This procedure defines the methods and interactions between EN DES, CONST, and P PROD and the responsi-bilities for the implementation of modifications to co licensed nuclear units.
d ne<
e u
Table 17.0-1 (sheet 2)
Criterion III - Design Control ID-QAP-3.1 OEDC Site Investigation for Jesign This procedure defines the responsibilities and Purposes procedures required for OEDC site investigations for design purposes.
Criterion IV - Procurement Document Control ID-QAP-4.1 Responsibilities and Functions of This procedure defines the responsibilities and the Division of Purchasing functions of the Division cf Purchasing in procure-ment for nuclear power plants cs related to quality assurance activities.
ID-QAP-4.2 Procurement Document Control by This procedure defines the Division of Purchasing's the Division of Purchasing responsibilities and procedures for controlling the awarding and changing of contracts for nuclear power plants.
ID-QAP-4.3 Transfer of Items This procedure defines the responsibility and pro-cedures used for transfer of safety-related items between IVA organizations.
ID-QAP-4.4 Vendor Quality Assurance Evaluation This procedure describes the Vendor Quality Assurance Information Center Evaluation Information Center.
The information contained in the center is available for reference by any organization within TVA to assist in the preaward evaluation of potential suppliers of quality-related items or services.
Criterion VI - Document Contrc ID-QAP-6.1 Drawing Control This procedure applies to the control of Functional
,)
Configuration Control (FCC) drawings which represent the h[
as-constructed functional status of e istem in a nuclear y
r%
plant. It covers the development anc approval cf the list <
((
of FCC drawings for each system which is defined as the
- A System Configuration Control Drawing List (SCCDL). It also w covers the control of FCC crawings from the time of first transfer of equipment until licensing of the last unit.
I It also includes responsibilities fcr and a description j
cf the Drawing Information System which taintains the status of FCC drawings.
O O
9
Table 17.0-1 (sheet 3)
Criterion XI - Test Control ID-QAP-ll.1 Preoperational Testing This procedure defines the responsibilities of EN DES CONST, and P PROD with regard to preoperational testing activities.
Criterion XVII - QA Records ID-QAP-17.1 Transfer of Quality Assurance Records This procedure establistes the methad and defines the interfaces and responsibilities for the transfer of Quality Assurance Records from EN DES and CONST to P PROD.
Criterion XVIII - Audits ID-QAP-18.1 Qualification, Certification and This procedure delineates the manner in which Recertification of Quality Assurance personnel performing quality assurance audits are Audit Personnel qualified, certified, and recertified.
CO Fo ia C
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TVA BOARD OF DIRECTORS NRC I
OFFICE OF THE l
GENERAL l
MANAGER I
OFFICE OF l
~
GENERAL COUNSEL REGULATOR INCLUDING OUALITY l
ASSURANCE I
- * - - - - - - _l - - -
i r--------
I I
I OFFICE OF OFFICE OF OFFICE OFFICE OF NGINEERING NATURAL OF MANAGEMENT RESOURCES POWE R SERVICES CONS PUCTION I
i DIVISION OF l
lll TECHNICAL OCCUPATIONAL l
M A D DIVISION OF HEALTH AND WATER M
O^
SAFETY RESOURCES TECHNICAL l l lL. _ _ _ _ _qi>
4._______J DIVISION ENTS A tvd op OUALITY ll PURCHASING TECHNICAL l
REQUIRE-l l ADMINISTRATION DIVISION OF EO MENTS NATURAL
+-
INCLUDING CONTRACT k"
RESOURCE ADMINISTRATION TECHNICAL ADMINIS !
l QUALITY TR ATION INCLUDING N
SERVICES l
ASSU R ANCE OUALITY ASSURANCE l 1 r (OPE R ATION)
(DESIGN AND l
7 l
d SUPPLIERS CONSTRUCTION) 4-J L - - - - - --4>
AND CONTRACTORS N
LINES OF RESPONSIBILITY FIGURE 17.01--TVA ORG ANIZATION
_ LINES OF COMMUNICATIONS Revision 3 l
7%A-7B75-1 Fev. 3 TAEL,E 17.1A-1 CROSS INDEX CF CEDC QUALITY ASSUR ANCE PFCCEDUBES ANC BELATEC CFITERIA OF AFFENDIX E TO 10CFF50 The titles of Appendix E Cuality Assurance Criteria are listed belcw for reference purposes.
APPENDIX E TC 10CFF50 CUALITY ASSURANCE CFITEFIA No.
Title I
Crganizaticn II Cuality Assurance Progran III Design Ccntrcl IV FIccurement Docurent Ccatrol V
Instructions, Frocedures, and Crawings VI Cocument Centrol VII Control of Eurchased Materdal, Equip 5ent, and Services VIII IdEntificatiCn and CCntrC1 of Naterials, Parts, and Components IX Ccntrol cf Special Processes X
Inspecticn XI Test Ccntrol XII Centrol of Neasuring and 7est Equipment XIII Bandling, Stcrage, and Shipping XIV Inspection, 7est and Operating Status XV Ncnconforming Materials, Earts, cr Ccmponents XVI Corrective Action XVII Guality Assurance Recordo XVIII Audits 914044 8-79
TVA-TR75-1 Fev. 3 O
TABLE 17.1A-1 (Continued) 10CFF50 Appendix E Criteria TVA Procedure Paragraph No.
No.
Title No.
I OECC-CAF-1.0 Organization 17.1 A.1 CAS-QAP-1.1 Division of Cuality Assur-ance Fesponsibilities Eetween Elements of CECC CAS-CAP-1.2 Fesponsibilities and Func-tiens of CECC Cuality Assurance CAS-CAP-1.3 CECC Cuality Assurance Comaittec EN dei-CAE-1.2 Cuality Assurance Frogram Neetings EN DES-CAP-1. 6 Cualificaticn Fequirements for Peraonnel Assigned ll)
Cuality Assurance Activities CCNST-CAP-1.01 Civision of Construction Cuality Assurance / Control Crganizaticn II OECC-CAF-2.0 Quality Assurance Ercgrar 17.1A.2 CAS-QAP-4.1 Cuality Assurance Indoc-trination and Training CAS-CAP-4.3 Qualification, Certifica-tien, and Recertification of Ncndestructive Examina-tion Personnel 3
EN DES-CAF-1.7 Certificaticn of Nondestruc-tive Examination (EDE)
Personnel CONST-CAP-2.01 CONST Cuality Assurance Frogran Description CO?* ST-C AP-CObST Cuality Assurance 2.02.01 Program Description--HEP CCNST-CAP-2.03 Conformance to Regulatcry Guides and Standards og 3 r. :-
8-79 o s..' t 40
TVA-TF75-1 Fev. 3 TABLE 17.1A-1 (Continued) 10CEF50 Appendix E Criteria TVA Procedure Paragraph No.
No.
Title No.
CONST-CAF-2.04 Fre-PSAR Cuality 17.1A.2 Assurance Activities CONST-CAP-Classification of Nonde-2.05.01 structive Examination (NCE)
Perscnnel CONST-CAP-Cualification, Training, 2.05.02 and Certification Fequire-mentt for liquid Fenetrant Nonde tructive Exanination Fersonnel CCNST-CAP-Qualification, Tra2ning, 2.05.03 and Certification Require-ments for Magnetic Particle Nondestructive Exaninaticn Perscnnel CCNST-CAP-Cualificaticn, Training, 2.05.04 and Certification Require-ments for Fadiographic Nondestructive Examinaticn Personnel CCNST-CAP-Qualification, Training, 2.05.05 and Certification Require-ments for Ultrascnic Ncnde-structive Examination Perscnnel CCNST-CAP-2.07 Gualification of Inspec-tion, Examination, and Testing Personnel CCNST-CAF-2.08 Cualification of Audit Fersonnel CCNST-CAP-2.09 Qualification of Welders and Kelding Operators CCNST-CAP-2.10 Cualification of Cadweld Splicers 9140M CONST-CAP-2.11 Cualification of Frotec-tive Coating Applicators III OECC-CAP-3.0 Cesign Contrcl 17.1A.3 ID-QAP-7.0 OEDC Site Investigation for Design Purposes g_79
TVA-TF75-1 Fev. 3 O
TAELE 17.1A-1 (Continued) 10CFF50 Appendix E Criteria TVA Procedure Paragraph No.
Ec.
Title No.
EN DES-CAF-2.1 Cesign Review 17.1A.3 Col;ST-CAF-3.01 Field Change Fequests IV OECC-CAF-4.0 Frocurement Docunent 17.1A.4 Contrcl 3
EN DES-CAF-3.1 Frocurement Cuality Assurance CONST-CAP-4.01 Procurement Docusent Contrcl V
OECC-CAF-5.0 Instructions, Prccedures, 17.1A.5 and Crawings CCNST-CAF-5.01 Cuality Assurance g
Procedures CONST-CAP-5.02 Site Cuality Control 17.1A.5 Procedures CONST-CAP-5.03 SMEL Cuality Control Fracedures VI OECC-CAF-6.0 Cocument Control 17.1A.6 CAS-CAF-2.1 Freparation, Feview, and Approval of Haterial fcr the CECC Cuality Assurance Manual CAS-CAF-2.2 Maintenance of OEDC Cuality Assurance Nanual fcr Design and Construction CAS-CAF-2.3 Cuality Assurance Forms CAS-CAP-2.5 Feview of EN DES and CCNST Purchase Pequisiticns and Contracts 3
EN DES-CAF-1.1 EN DES Preparation and Processing of Cuality Assurance Procedures 914047 8-79
T VA-TB 7 5-1 Rev. 3 TABLE 17.1A-1 (Continued) 10CFF50 Appendix E Criteria TVA Procedure Faragraph Nc.
No.
Title Eo.
EN DES-CAF-1.3 Control of Cocuments Affecting Cuality CONST-CAF-3.02 Functional Configuration Crawing Centrcl for Nuclear Flants CCNST-CAP-6.01 Cocument Control CCEST-CCP-5.6 Cuality Assurance 17.1A.6 Fequirements for Materials Review Reports VII OECC-CAF-7.0 Contrcl of Furchased 17.1A.7 Material, EquipEent, and Services EN DES-CAF-4.1 Shop Surveillance of Fressure Ccntaining Compo-nents - Kestinghcuse Procured Iters (Except BPV)
EN DES-CAF-4.2 Surveillance of NSSS Vendor Inspection and Test Activities EN DES-CAF-4.3 Shop surveillance for Fres-sure Ccntaining Systems and Components (TVA Frccured)
EN DES-CAF-4.4 Shop Surveillance of Feactcr Pressure Vessels EN CES-CAF-4.5 Shop Surveillance for Steel Containeent Vessels EN DES-CAF-4.6 Shop Surveillance for Heavy Equipment Items EN DES-CAF-4.7 Shop Surveillance for 17.1A.7 Instrumentation and Contrul Components for TNA Procured Items EN DES-CAF-5.2 Felease of Naterial and 17.1A.7 Equipnent frca Ccntrac-tors' Shops EtL1018 8-79 4
TVA-TF75-1 Fev. 3 0
7ABLE 17.1A-1 (Continued) 10CFB50 Appendix E Criteria TVA Procedure Paragraph No.
Nc.
Title No.
CONST-CAF-7.01 Feceiving Haterials, Parts, and Ccupcnents CCNST-CAP-7.02 Surveillance of Site Contractors CONST-CAF-7.03 Evaluation and Selection 17.1A.7 of suppliers CCNS7-CAP-7.04 Transfer of Naterials, Parts, and Components VIII OECC-CAF-8.0 Identificaticn and Centrol 17.1A.8 of Materials, Parts, and Ccmpcnents CCNST-CAP-8.01 Identification and Marking of Materials, Parts, and lll Components CONST-CAP-8.02 Contrcl cf Haterials, Parts, and Ccuponents CONST-CAF-8.03 Centrol of Kelding Material IX OECC-CAF-9.0 Centrol of Special 17.1A.9 Frocesses CCNST-CAP-9.01 Assignment of Special Processes CCNST-CAF-9.02 Cualification of Kedling Procedures CCNST-CAF-9.03 Cualification of Cadweld Splicing Procedures CONST-CAP-9.04 Felease for Crilling, Chipping, Cutting cf, or kelding to Perma-nent Structures cr Components CONST-CAP-9.05 Nondestructive Exaninaticn O.2.'1049 8_79
TVA-TE75-1 Bev. 3 TABLE 17.1A-1 (Continued) 10CFF50 Appendix E Criteria TVA Procedure Faragraph No.
No.
Title No.
CONST-CCP-5.2 Cuality Assurance Fequire-ments for Concrete Mixture Propertiening X
OECC-CAF-10.0 Inspection 17.1A.10 CCNST-CAF-10.01 Inspection 17.1A.10 CONST-CCF-5.3 Cuality Assurance Fequire-rent fcr Soil Investiga-tion Prior to Construction XI OEDC-CAF-11.0 Test Centrol 17.1A.11 CONST-CAP-11.01 Test Centrcl CCNST-CCP-5.4 Quality Assurance Beguire-ments for latoratory Test-ing cf Protective Coatings CONST-CCP-5.5 Cuality Assurance Pequire-ments for Nechanical Testing of Netals 3
XII OECC-QAF-12.0 Control of Neasuring and 17.1 A.12 Test Equipment CONST-CAP-12.01 Centrol of Neasuring and Test Equipment CCNST-CCP-5.1 Calitration of Latcratory Neasuring and Test Equipnent XIII OECC-CAF-13.0 Bandling, Storage, and 17.1A.13 shipping CONST-CAF-13.01 Storage and Preservaticn of Naterials, Corpcnents, and Systems CONST-CAP-13.02 Bandling Nuclear Ccaponents XIV OECC-CAF-14.0 Inspection, Test, and 17.1A.14 Operating Status 8-79 bl.40fiO
TVA-TF 7 5-1 Fev. 3 0
1AELE 17.1A-1 (Ccntinued) 10CEF50 Appendix E Criteria TVA Procedure Faragraph No.
No.
Title Eo.
CONST-CAP-14.01 Inspection and test Status 3
XV O ECC-CA F-15. 0 Noncenforming Haterial, 17.1A.15 Farts, cr Components CAS-CAF-4.2 Cuality Problem Analysis System EN DES-CAF-1.5 Reporting cf Deficiencies in Design and Construction of Nuclear Fower Plants EN DES-CAF-1.10 Deternining and Feporting hFC-CIE Feportable Ccnditiene EN DES-CAF-5.3 Handling of Contractor lll Nonccnformances and Deviations CCNST-CAP-15.01 Control of Nonconferning Items XVI OECC-CAF-16.0 Corrective Action 17.1A.16 CCNST-CAF-16.02 NBC - CIE Feplies XVII OEDC-CAF-17.0 Cuality Assur;nce Fecords 17.1A.17 O ECC-CAP-17.1 Cuality Assurance Fecords for Cesign and Ccnstructico EN DES-CAF-5.1 Preparation, Feview, and Distribution cf Inspection Feports EN DES-CAF-5.4 Cuality Compliance Fecords and Fecords Control for TVA Frecured Itens EN DES-CAF-5.5 Cuality Compliance Fecords and Records Centrcl for NSSS tendor Frocured g
Items W
3.t4051 CONST-CAP-17.01 Cuality Assurance Fecords 8-79
TVA-TE75-1 Fev. 3 1ABLE 17.1A-1 (Continued) 10CFF50 Appendix E Criteria TVA Precedure Paragraph No.
No.
Title No.
XVIII CEDC-CAE-18.0 Audits 17.1A.18 CAS-CAP-3.1 CEEC Cuality Assurance Audits CAS-QAP-3.2 NRC-Cffice of Inspecticn 17.1A.18 and Enforcenent Activities CAS-CAF-3.3 Scheduling CEEC Cuality Assurance Audits EN DES-CAE-1.4 Internal EN DES Cuality Assurance Audit Frcgram EN DES-CAF-3.2 Vendor Quality Assurance Audit Prcgram CCNST-CAP-18.01 Auditing Ccnstruction Activities 0$$05$?>
8-79
TVA-TB75-1 Fev. 3 TAELE 17.1A-2 PUFFCSE ANC SCOFE OF TVA CUALITY ASSUEAhCE FFCCEEUBES SECTION A - OFFICE CF ENGINEERING CES':S AND CCNSTBUCTION CUALITY ASSURANCE JECCECUBES (Criteria I through XLIII) - Titled similar to the 18 Criteria OEDC-CAF-1 through OEEC-CAP-18 (These are a series of 18 quality assurance procedures with each procedure defining the method TVA uses to couply with cne cf the 18 criteria.
They assign specific respcnsibilities fcr each of the 18 criteria.)
SECTICN E - OEEC NANAGER'S CFFICE CUALITY ASSURANCE STAFF GCALITY ASSURANCE FFCCEDUFES S
(Criterion I)
- rivision of Cuality Assurance QAS-CAP-1.1 Fesponsibilities Eetween Elenents of CEEC (This procedure defines the responsi-bilities ancog the OEDC Cuality Assurance Staff, CEE, and the Project Construction Engineer.)
(Criterien I)
- Fespcnsibilities and Functions of QAS-QAF-1.2 OEEC Cuality Assurance (This procedure outlines the responsi-tilities and function of each unit of the OEDC CA Staff.)
(Criterien I)
- CEDC Cuality Assurance CcamittE(
GAS-CAE-1.3 (This procedure descrites the purpose of the meeting, nethod used to select members, schedule cf meetings, and the preparation of the agenda and the minutee of the seetings.)
O suosa 8-79
TVA-TE75-1 Fev. 3 TAELE 17.1A-2 (Continued)
(Criterion VI)
Freparation, Feview, and Approval CAS-CAP-2.1 of Material for the CECC Cuality Assurance Manual (CCh)
(This procedure defines the responsi-bilities fcr preparation, review, and approval of all gaterial which is part of the CEDC Cuality Assurance Nanual.)
(Criterion VI)
- Naintenance of OEDC Cuality QAS-CAF-2.2 Assurance Nanual for Design and Ccnstructicn (This procedure defines the responsi-bility and procedures for the maintenance and distribution of the OECC Cuality Assurance Manual for Cesign and Ccnstruction.)
(Critericn II)
- Cuality Assurance Form CAS-CAF-2 3 (This procedure defines the nethcd for the development and centrol of forms and documents used by Cuality Assurance and Cuality Control grcups of OECC.)
(Critericn VI)
- Beview of EN CES and CCNST Furchase QAS-QAP-2.5 Fequisitions and contracts (This procedure descrites CECC CA Staff responsibilities for reviewing EN DES and CCNST purchase requisitions and contracts for nuclear safety-related items or services to ensure that they ccntain the necessary quality assurance.equirenents.)
(Criterion XVIII)
- CECC [uality Assurance Audits CAS-QAP-3.1 (This procedure defines the responsi-bilities and procedures for planning, conducting, reporting, and follow-up of audits by the CECC Cuality Assur-ance Frogram of the Divisicos cf Engineering Design and Construction.)
814054 8-79
TVA-TP75-1 Fev. 3 O
TAELE 17.1A-2 (Continued)
NRC-Office of Inspection and (Critericn XVIII)
QAS-CAF-3.2 Enforcement Activities (This procedure defines the responsi-tilities and procedure fcr the coordination of EFC-CIE inspections and reports in accordance with Title 10, Code of Federal Fegulations, Part 2, Subpart E.)
(Critericn XVIII)
- Scheduling CECC Cuality Assurance QAS-CAF-3.3 Audits (This procedure defines the respCusi-tilities and procedure fcr developing OEEC Cuality Audit Schedules and assures that audits will te performed in a timely manner and are associated with the impleuentation cr enactuent cf important activities that affect quality.)
lll (Criterien II)
- Cuality Assurance Indoctrinatien and CAS-CAF-4.1 Training (This procedure establishes a guide for the training and certification of OEEC personnel engaged in quality assurance activi-ties.
The procedure defines the overall plan of action for assuring that qualificaticnc and responsitili-ties are properly natched.
Guide-lines necessary to implement this plan are detailed.)
(Critericn XV)
- Cuality Froblem Analysis System CAS-CAF-4.2 (This procedure assures that a unified, controlled plan cf acticn is fcllowed in recti-fying quality problems in areas of CEEC activities related to nuclear safety.
This procedure defines such a plan of acticn and describes methods and technigres tc te fcllowed in inplementing it.)
O anow 8-79
TVA-TF75-1 Fev. 3 TAELE 17.1A-2 (Con tinued)
(Criterion II)
_ualification, certification, and QAS-QAP-4.3 Recertificaricn cf Nondestructive Examinatlon Perscnnel (This procedure specifies the nanner in which perscnnel perforning nonde-structive examination sh711 te quali-fled, certified, and recertified.)
SECTICN C - DIVISICN OF ENGINEEBING ti..GN
$0ALITY ASSCBANCE PFCCEDUFES (Critericn VI)
- EN DES Preparaticn and rrocessing of EN DES-CAF-1.1 Cuality Assurance Frecedures (This procedure defines the responsi-tilities and methods fcr preparatica, review, distribution, and naintenance of EN DEC procedures which prescrite quality assurance activities.
It establistes the fcInat tc te fcllowed in f reducing procedures and review and approval responsibilities.)
(Criterion I)
- Cuality Assurance Frogram Meetings EN DES-CAF-1.2 (This procedure defines the general requirements for periodic neetings to disseninate quality assurance informa-tion and to discuss related prchlems.)
(Criterion VI)
- Centrcl of Documents AffectiDQ EN DES-QAF-1.3 Suality (This prccedure defines
? general methods fcr the ccetrol
(-
design documents issued formally _y the Division of Engineering Design to define requiren.er4ts that are used in decign, prccuremont, fabricaticn, installation, erection, ccnstruction, quality assurance, operatico, ari naintenance of those structure sys-tems, and conponents that nust meet requirenents of the cuality Assurance 31405G 8-79
TVA-TF7S-1 Fev. 3 O
TAELE 17.1A-2 (Continued)
Plan cf the Ereliminary and Final Ssfety Analysis Feports for nuclear plants.
This procedure applies to the identificaticn, preparation, review, approval, issue, distribution, and revision of design criteria docu-ments, design drawings, requisiticns (including specificaticns), formal written procedures, and EN EES ccnstruc-tien specificaticns.)
(Criterion XVIII)
- Internal _EN DES Quality Assu5ance Audit EN DES-CAF-1.4 Prccram (This procedure defines the general requirements for auditing the quality assurance activities of EN EES for com-pliance with the requirenents cf the Quality Assurance Frogran of the Office of Engineering Cesign and Ccnstruction.
It includes the requirenents fcr checklists, sched-ulec, reports, and follow-up audits llg where corrective action is required.)
(Critericn XV
- Fercrting and Handling of benccnfor-
- 50. 5 5 (e) of 10CFR50) mances in EN DES EN DES-QAF-1.5 (This procedure applics to the reporting cf nonconformances by EN CES personnel.
It also describes the handling of non-conformance reports that are generated by EN DES, CCbST, cr suppliers.)
(Criterion XV
- Ferorting and Handling of Nonccnfor-
- 50. 55 (e) of 10CFB50) mances in EN DES (This procedure applies to the reporting cf nonconforrances by EN DES personnel.
It also describes the handling cf ncn-confernance reports that are generated by EN DES, CCNST, or suppliers.)
814057 8-79
TVA-TR75-1 Rev. 3
{)
TAELE 17.1A-2 (Continued)
(Criterion I)
- gualification Requirements for EN DES-QAP-1.6 Personnel Assigned guality Assurance Activities (This procedure. defines the minimum acceptable requirenents for perscnnel assigned quality assurance activities such as checking, auditing, or other-wise verifying to provide adequate confidence that specify quality requirements are suf ficient, will te achieved, and are verified.
This establishes a mininum tase line standard for the qualificatienc cf personnel engaged in quality assurance activities within the tranches, design projects, and divisicn staf f.)
(Criterion II)
- Certification of Ncndestructive EN DES-QAP-1.7 Examination (NDE) Perscnnel (This procedure specifies the nanner in which perscnnel associated with nondestructive testing and examina-tion shall te qualified and certified.
It is applicable to qualification and certificaticn of personnel asscciated with nondestructive testing and examination to fulfill the require-ments of the Division of Engineering Design (EN DES) and applicable codes and standards.)
(Lriterion XV
- Deternining and Reporting NRC-CIE 50.55e of 10CFR50)
Reportable Ccnditicns EN DES-CAF-1.10 (This procedure applies to the determina-tion of reportability to the Nuclear Regulatory Commission - Office of Inspec-tion and Enforcenent (bRC-CIE) of those nonccnformances identified in the design and ccnstruction of nuclear power plants which have been determined tc te signifi-a cant conditions."
This procedure also applies to the rescrting cf those conditions which have teen determined to te reportable to NFC-OIE).
(Criterion III)
- Cesign Review EF DES-CAF-2.1 (This procedure defines design reviews withir EN DES which are perforned during 8-79 814058
TVA-TF75-1 Fev. 3 O
TAELE 17.1A-2 (Continued) two phases.
Phase I comprises the preliainary design, definiticn of plant and equipment paraneters, estah-lishing basic design criteria, identi-fication of regulatcry requirerents, codes, and standards and preparation and submittal of the Prelininary Safety Analysis Report.
Phase II is the detail design ef fort of preparing construction documents and drawings and procurement of equiprent nct completed during Phase I.)
(Criterion IV)
- Frocurement Cuality Assurance EN DES-CAF-3.1 (This procedure delineates the procedures used by EN CES to procure safety-related itens.)
(Criterion XVIII)
- Vendor Cuality Assurance Audit Program EN DES-CAF-3.2
[This procedure establishes a EN DES program of quality assurance audits llg of vendors in conpliance with the requirements of Appendix E 10CFP50 and NFC Fegulatory Guide 1.28 (ANSI-545. 2). ]
(Criterion VII)
- Shop Eurveillance cf Pressure EN DES-CAF-Containing Components - kestinchcuse 4.1 Procured Itens (Except RFV)
(This procedure defines the general methcds and requirements for stop surveillance by TVA inspectors of pressure containing congenents which are procured by Kestinghouse fcr the Sequoyah and Katts Bar Nuclear Plants and which are within the scope of the Quality Assurance Flan.)
$)40 b g
8-79
1NA-TR75-1 Fev. 3 TAELE 17.1A-2 (Ccntinued)
(Criterion VII)
- Surveillance of NSSS Vendor Inspection EN DES-CAP-and Test Activities 4.2 (These procedures define the general methcds and requirements for stop surveillance by TVA inspectors of primary system cceponents which are procured by the ESSS (Nuclear Steam Supply Syster) vendor for a TVA nuclear plant and which could frevent or mitigate the ccnsequences of a postulated accident that cculd cause undue risk to the health and safety of the public.
These procedures are alsc guides and contain minimum requirements tc he used by the TVA inspectors to provide necessary assurance to TVA that the NSSS vendor and the third party inspection agency (where applicable) are perforning shop surveillance as described in the NSSS vendor's quality assurance plan and as required by the purchase order.)
(Criterico VII)
- Shop Surveillance for Fressure EN DES-QAF-Ccntaining Systers and Ccarcnents 4.3 JTVA Frecured)
(This procedure defines the general methcds and requirements fcr shop surveillance of safety-related pres-sure containing conponents which are prccured by TVA for nuclear plants.)
(Critericn VII)
- Shop Surveillance cf Feacter Fressure EN DES-CAF-Vessels 4.4 (This procedure defines the general methods and requirements fcr shop surveillance by TVA inspectors of reacter pressure vessels which are procured by the ESSS vendcr.)
SMD60 8-79
TVA-TF75-1 Fev. 3 TAELE 17.1A-2 (Continued)
(This procedure is a guide and con-tains minimum requirements tc te used by the TVA inspectors to provide necessary assurance to TVA that the ESSS vendor and the third party inspection agency are perforning shop surveillance as required by the Code.)
(Criterion VII)
- Shop Surveillance for Steel Centain-EN DES-CAF-ment vessels 4.5 (This procedure defines the methods and requirements for stop surveillance of the structural steel ccntainrent vessels for all nuclear plants.)
(This procedure elaborates on the requirements of the cuality Atsurance Plan and is a guide to te used by the Inspection and Testing Eranch for surveillance at vendor plants where any ccaponent of each vessel is teing g
manu f actured.)
(Critericn VII)
- Shop Surveillance for Beavy Equirnent EN DES-QAP-Items 4.6 (This procedure assists the TVA Inspector in his surveillance of heavy equipnent items at centractors' plants.)
(Criterion VII)
- Shcp Eurveillance for Instrunentation EN DES-CAF-and Centrol Corrcnents for TVA 4.7 Procured Iters (This procedure defines the general methcds and requirements for stop surveillance of instrunents and con-trol components cr systers fcr nuclear plants which are within the accpe of the 1NA Quality Assurance Plan.
This procedure is a guide to te used by the inspector for his surveillance of vender plants where applicable ccapo-nents cr systems are teing manufac-tured or assembled.)
914061 8-79
TVA-TF75-1 Fev. 3
$h TABLE 17.1A-2 (Continued)
(Criterion XVII)
- Preparation Feview, and Eistribution 2
EN DES-QAP-of Inspection Rercrts 5.1 (This procedure outlines the acre sig-nificant consideraticos and acticns required of the inspector in preparing a comprehensive inspectico rescrt for nuclear plant materials and equipnent requiring quality assurance docunenta-tion.)
(Criterion VII)
- Release of Naterial and Equirnent EN DES-QAP-frca Centracters' Shops 5.2 (This procedure defines the meched for release cf material and equip-ment from contractcrs' shops subject to source inspecticn.
Frcvisicns apply equally to the contractors' suppliers.)
(Critericn XV)
- Handling of Contractor Nonccnform-EN DES-QAP-ances and Eeviaticos 5.3 (This procedure defines the method fcr handling deviaticne and ncnccnfornances in vendors' and subvendors' plants to assure that they are identified and reported and that adequate corrective action is taken.)
(Criterion XVII)
- Cuality Compliance BeCords and Records EN DES-QAP-Contrcl for TVA Procured Items 5.4 (Thi procedure defines the nethods by which reccrds are centrclled for TVA procured material which nust meet the requirements of the Guality Assurance Plan as contained in Safety Analysis Fepcrts.)
31406?.
8-79
TVA-TF75-1 Fev. 3 O
TABLE 17.1A-2 (Continued)
Cuality Compliance Fecords and Records (Criterion XVII)
EN DES-QAF-Control for NESS Vendor Procured 5.5 Naterial (This procedure defines the methods by which records are handled fcr safety-related items furnished by the Nuclear Steau Supply Systers vendor.
This procedure applies tc all records required tc furnish prcof cf ccmpli-ance with procurement docuaents.
This precedure applies to all TVA nuclear plants except Ercuns Ferry.)
SECTICN C - CIVISION CF CCNSTbUCTICE 3
OUALITY ASSUFANCE EFCCEC0FES (Criterion I)
- Civision of Ccnstruction Cuality CCNST-CAP-
- Assurance /Ccntrcl Crqanizaticn 1.01 (This procedure delineates the authority, responsibilities, and qualifications of the nanagement structure charged with the develcy-sent and inplementation of the Civision of Construction cuality Assurance Frogran.
The procedure further defines channels of ccumuni-cation tetween interfacing CA crgani-zaticns.
The prccedure applies cnly to Hartsville Nuclear Flant.)
(Criterion II)
- CONST Cuality Assurance Ercqran CCNST-CAE-2.01 Description (This procedure descrihes the Eivision of Construction Quality Assurance Erogram and how the Fregran is struc-tured to satisfy Appendix E tc 10CEF50 and the Cf fice of Engineering Cesign and Ccnstruction cuality Assurance Erogran.
The Eivisicn of Construction Cuality Assurance Pro-gram applies to those constructicn quality-affecting activities involv-g ing those structures, systens, and W
compcnents that prevent cr sitigate the ccnsequences cf postulated acci-dents that cculd cause undue risk to 814063 8-79
TVA-TF75-1 Fev. 3 TAELE 17.1A-2 (Continued) the health and safety cf the public.
The procedure applies to all TNA Nuclear Plants except Ercwns Ferry.)
(Criterion II)
- CONST Cuality Assurance Frogran CCEST-CAF-Cescription - HNF 2.02.01 (This procedure lists the " Quality Assurance Items" of those structures, systens, and components that prevent or mitigate the consequences of postulated accidents that cculd cause undue risk to the health and safety of the public.
The procedure applies only to Hartsville Nuclear Plant.)
(Criterion II)
- Ccnformance to Requlatcry Guides and CCNST-GAF-Standards 2.03
[This procedure describes the func-tions perforned by the Divisicn cf Construction (CONST) in the review of Division 1 Euclear Regulatcry Commis-sion (ERC) Fegulatory Guides (BG's) and the establishnent of the CCNST position concerning the degree of conformance cf each TVA nuclear power plant to any applicable FG.
The prccedure further defines the obligations of CCNET in corplying with the Office of Engineering Eesign and Construction (OEEC) positions as contained in the centrolled sets of RG's maintained ty the Civisicn cf Engineering Eesign (EN CES) Nuclear Licensing Section (NES).
This procedure applies to all TNA nuclear plants except Browns Ferry. ]
32.10/34 8 -"
TVA-7E75-1 Fev. 3 9
TAELE 17.1A-2 (Continued)
(Criterion II)
- Fre-PSAR Ouality Assurance Activities CCNST-CAP-2.04 (This procedure delineates the quality assurance activities per-formed by the Civision of Construc-tion (CONST) pricr tc the subnittal of the Preliminary Safety Analysis Feport (PSAR) to the Nuclear Eegula-tory Commission (NFC) for propcsed TVA nuclear power plants.
Frcceiures that govern these quality assurance activities are identified in this procedure.
The prccedure applies only to pre-PSAR activities perfcrred by CONST elements such as early requi-sitiening cf hcth reinforcing steel and site soil investigations.
This procedure applies to all TNA nuclear plants except Browns Ferry.)
(Critericn II)
- Classificaticn cf Eondestructive CCNST-CAP-2.05.01 Examination (NDE ) Ferscnnel (This procedure defines the various levels of classification fcr ncnde-structive examination personnel.
It applies to those CCNST perscnnel engaged in performing nondestructive examina-tion during the ccnstruction phase of TVA Nuclear Flants except Ercu r.s Ferry.)
(Criterion II)
- Cualification, Training, and Certi-CCNST-CAP-2.05.02 fication Requirenents for Liquid Penetrant Nondestructive Exaninaticn Fersconel (This procedure defines the qualifi-cation and training requirenents for Liquid Penetrant Examination person-nel certification.
The prccedure applies to all TVA nuclear plants except Browns Ferry.)
O 8-79 314CM
TVA-TF75-1 Fev. 3 TAELE 17.1A-2 (Continued)
(Criterion II)
- Cualification, Training, and Cer:j-CCNST-CAP-2.05.03 fication Requirenents for Naqnetic Particle Nondestructive Exaninaticn Ferscnnel (This procedure defines tre qualifi-caticn and training requirenents for Magnetic Particle bondestructive Examination perscnnel certificaticn.
The procedure applies to all TVA nuclear plants except Erchns Ferry.)
(Criterion II)
- Cualification, Training, and Certi-CCNST-CAP-2.05.04 fication Requirenents for Fadic-grachic Nondestructive Examinaticn Ferscnnel (This procedure defines the qualifi-caticn requirenents for Fadiographic Fondestructive Exanination personnel certification.
The prccedure applies to all TVA Nuclear Plants except Erowns Ferry.)
- Cualificaticn, Training, and Certi-(Criterica II) fication Requirenents for Ultrasonic CONST-CAF-2.05.05 Nondestructive Exanination Fersonnel Crhis procedure defines the qualifi-cation and training requirenents for Ultrascnic bondestructive perscnnel certificaticn.
The prccedure applies to all TVA nuclear plants except Erowns Ferry.)
(Criterion II)
- Cualification of Inspection, Exacina-CCEST-CAF-tion, and Testinq
- Personnel 2.07 (This procedure defines the qualifi-caticn and training prcgran fcr certi-fying Inspection, Examination, and Testing Perscnnel.
The procedure is applicable to thoce perscnne] per-forming quality control functicne during the ccnstruction phase cf TVA nuclear plants except fcr Ercuns Ferry.)
3140GG 8-79
TVA-TF75-1 Fev. 3 O
TAELE 17.1A-2 (Continued)
(Criterion V)
- Cualification of Audit Fersonnel CONST-CAF-2.08 (This procedure defines the system by which personnel perfcrairg Cuality Assurance Audits shall be qualified, certified, and recertified.
The pro-cedure is applicable to personnel performing audits within their respective responsibilities of the Guality Assurance Frogran and to the Division Auditor Examiner appointed certify auditor qualificatens.
The procedure applies to all TVA nuclear plants except Ercuns Ferry.)
(Critericn II)
- Cualification of Kelders and Kelding CCNST-CAP-2.09 Cperators (This procedure assigns the responsi-tility and defines the sequence cf actions to te accomplished in the qualification, certificaticn, and lll recertification cf welders and weld-ing operators.
The procedure applies to all TVA nuclear plants except Erowns Ferry.)
(Criterion II)
- Qualification of Cadweld Splicers CCNST-CAF-2.10 (This procedure assigns the responsi-bilities and defines the sequence of acticns to te acccmplished in the qualification or requalificaticn of Cadweld splicers utilizing the Cad-weld process en Category I ccncrete structures.
The procedure applies to all TNA nuclear plants except Ercwns Ferry.)
(Criterion II)
- Cualificaticn cf Protective Coating CCNST-CAF-2.11 Arrlicators (This procedure assigns the responsi-tilities and defines the sequence of acticne to te accomplished in the qualificaticn or requalificaticn of Frotective Coating Applicators for Class I service levels.
The procedure applies to all TVA nuclear plants except Ercwns Ferry.)
81/10fn 8-79
TVA-7B75-1 Fev. 3 TAELE 17.1A-2 (Continued)
(Criterico III)
- Field Change Fequests CCNST-CAF-3.01 (This procedure defines the system by which Field Change Requests (ECR's) to thc Division cf Engineering Design (EN EES) are prepared, controlled, and documented.
This precedure is appli-cable to TVA and manufacturers' drawings which have been apprcved by EN DES and are used in the ccnstruc-tion of a nuclear power plant.
The procedure applies to all TVA nuclear plants except Ercuns Terry.)
(Criterion VI)
- Functional Configuration Drawing CCNST-CAP-3.02 Control for Nuclear Flants (This procedure assigns the responsi-hilities and defines the prcgran for the systematic centrol of functicnal configuraticn drawings.
The proce-dure applies to the Contrcl of Functional Configuraticn Centrcl (FCC) drawings which represent the as-ccnstructed status of nuclear plant systems.
It defines the resper.sibilities cf the Ccostruction Engineer's Crganization (CEC) in the deve cpnent cf the Systens Drawing Cert 2fication List (SCCL) and control cf FCC drawings frca a tine at or just before tentative transfer of a systen until capitalizaticn accounts are closed.
The procedure applies to all TVA nuclear plants except Ercwns Ferry.)
(Critericn IV)
- Frocurerent Cocusent Contrcl CCNST-CAF-4.01 (This prccedure assigns the respcnsi-hility and defines the sequence of actions to he accomplished by the Civision of Ccnstruction (CCNST) in the preparation, review, approval, and control of procurement documents.
This procedure applies to all prccure-nent initiated by CCNS7 for any of the follcwing categories of iteas:
Sp}{JJjg 8-79
TVA-TF75-1 Fev. 3 9
TABLE 17.1A-2 (Continued)
A.
Fermanent plant material and equipment, E.
Ccntractor services, and C.
Ccntrolled ccnstruction material.
The requirements of this procedure apply to initial or replaceaent pur-chases by CCEST.
The initial prepara-tion cf Indefinite Guantity Term Contracts (ICT) and requests fcr delivery on ICT Contracts are within the scope cf this procedure.
The procedure applies to all TVA nuclear plants except Ercuns Ferry.)
(Criterion V)
- Cuality Assurance Erecedures CCNST-CAF-5.01 (This procedure defines the system for uniform preparation, revisico, review, and apprcval of CCEST Cuality Assurance Frocedure (CCNST-CAF).
The procedure is applicable to all CONST Quality Assurance Erocedures (CCNST-l)
CAP's) prepared for use by the Division of Ccnstruction.
The pro-cedure applies to all TVA nuclear plants except Ercuns Ferry.)
Site Suality Control Procedures (Criterion V)
CCUST-QAP--5.02 (This procedure assigns the respcnsi-bility and defines the sequence cf actions to be acccmplsihed in the preparation, review, approval, revision, and control cf Site Cuality Centrcl Procedures (CCE's).
This procedure applies to QCP's prepared by the Division cf Ccnstruction (CCNST) for use at nuclear sites.
?he procedure applies to all TVA nuclear plants except Ercuns Ferry.)
(Criterico %)
- SbEL [uality Centrcl Procedures CONST-CAF-5.03 (Tais procedure assigns the respcnsi-tility and defines the sequence of acticns to te accenplsited in the preparation, review, approval, and control of quality ccntrcl prccedures 9140GS g_79
TVA-TE75-1 Fev. 3 TAELE 17.1A-2 (Continued) for use at the Singleton Materials Engineering Laboratory (SMEL CCP's).
This procedure applies to CCF's prepared by the SNEL).
(Criterico VI)
- Eccument Centrol CCEST-CAF-6.01 (This prccedure assigns the responsi-bility and specifies the quality assurance requirerents fcr the contrcl of Engineering Eccunents at the ccnstruction sites to assure the use of current informaticn at the location where the activity is tc he perfctmed.
The procedure applies to all TNA nuclear plants except Ercuns Ferry.)
(Criterion VII)
- Beceiving Naterials, Parts, and CCNST-CAP-7.01 Compor:e nts (This procedure establishes the receiving prcgran for supplier-provided materials, compcnents, parts, and appurtenances (itens).
This pro-cedure applies to all itens within the scope cf the quality assurance program received at the prcject.
Contractor items within the sccpe of the quality assurance progran are handled in accordance with centractor procedures approved by the Eivision of Engineering Design.
This proce-dure applies to all TVA nuclear plants except Ercuns Ferry.)
(Criterion VII)
- Surveillance of site Centractors CONST-CAF-7.02 (This procedure assigns the respcnsi-bilities and identifies the prcgram requirements fcr surveillance of quality control activities on quality assurance itens at the ccostruction site.
The procedure applies to all TVA nuclear plants except Ercuns Ferry.)
314070 8-79
TVA-TR75-1 Fev. 3 O
TAELE 17.1A-2 (Continued)
(Criterien NII)
- Evaluation and Selection cf Suppliers CCNST-C AP-7. 0 3)
(Thia precedure ar. signs the respcnsi-bility and defines the sequence cf acticns to te accceplished for the evaluation and selection of suppliers furnishing quality assurance itens who have not teen previously identi-fied by the Civisicn of Engineering Design.
The procedure applies to all TVA nuclear plants except Ercurs Ferry.)
(Criterien VII)
- Transfer of Materials, Parts, and CONST-CAF-7.04 Conpenents (This prccedure assigns the respcnsi-tility and defines the sequence cf acticns to he accomplished when transferring quality assurance items within the scope of the Cuality Assurance Frogran frcm one prcject lll (nuclear site) tc ancther, cr frcm another TVA divisicn to the ccustruc-tien project (nuclear site) during construction.
The procedure applies to all TVA nuclear plante except Erowns Ferry.)
(Criterion NIII)
- Identification and Marking of CCNST-CAP-Materials, Parts, and Conronents 8.01 (This precedure assigns the responsi-tility and defines the quality assurance requirerents for the identi-fication and marking of naterials, parts, and components (items) at nuclear power plants.
This procedure applies to the identi-fication and marking of TNA-purchased quality assurance items, including partially fabricated sutassemblies at nuclear plants.
It does not apply to supplier-purchased itens which are identified and marked in accordance with Civisicn of Engineering Design (EN DES) requirenents and tc g
welding materialG which are identi-W fled and marked in accordance with COEST-CAP-8.03.
The procedure applies to all TVA nuclear plants except 314071 8-79
TVA-TF75-1 Fev. 3
)
TABLE 17.1A-2 (Continued)
Erowns Ferry.)
(Criterion VIII)
- Control of Naterials, Parts, and CCNST-CAP-8.02 Components (This precedure assigns the responsi-bility and defines the prograr for the systematic control of materials, parts, and components (itens) at nuclear plants.
The procedure applies to the requisition and return of itens covered by the Civision cf Construc-tion (CONST) Quality Assurance (CA)
Program at nuclear plants.
It does not apply to centractor-installed items which are centrolled in accord-ance with contractcr prccedures approved by the Civision of Engineer-ing Design (EN DES), and to the control of welding materials and the ccntrol cf materials during field fabrication which are centro 11ed in accordance with the requirenents of CCEST-CAP-8.03 and CCEST-CAE-8.04 respectively.
The procedure applies to all TNA nuclear plants except Browns Ferry.)
(Criterion VIII)
- Contrcl of Kelding NatErial CCEST-CAE-8.03 (This precedure assigns the responsi-bility and defines the quality assurance requirenents fcr the ccn-trol cf welding material.
It applies to the receipt, identificaticn, storage, issue, drying, and retake requirements of welding naterial and, if applicable, to the use of pcrtable ovens for cnsite fabrication and erection of permanent naterial.
The procedure does nct apply tc site-centractor-centrclied welding material which is controlled in accordance with centractcr prccedures approved by the Civision of Engineer-ing Design.
The procedure applies to all TNA nuclear plants except Erowns Ferry.)
(Criterion IX)
- Assignment of special Frocesses CCEST-CAF-9.01 (This procedure defines the respcnsi-324072 8-79
TVA-TR75-1 Fev. 3 TAELE 17.1A-2 (Continued) bility and methods for assignnent of design specificaticns governing special processes.
The procedure applies to a welding, heat treatrent, nondestructive exar.ination, and allied field f abrication operaticns required during the constructicn of nuclear power plants.
The procedure applies to all TVA nuclear plants except Brcuns Ferry.)
(Criterion IX)
- Cualification of Welding Frocedures CCNST-CAF-9.02 (This procedure assigns the respcnsi-bility and defines the quality assurance requirenents for the qualification of welding procedures of the following:
Secticn IX cf the ASME Ccde or ANS Code C1.1.
The procedure applies to all TVA nuclear plants except Ercuns Ferry.)
(Criterion IX)
- Cualification of Cadweld Srlicing CCNST-CAF-9.03 Procedure (This prccedure assigns the respcnsi-tility and defines the sequence cf acticn to be accceplished in the qualificaticn or requalificaticn of Cadweld splicing procedures fcr splicing concrete reinforcing steel using the cadweld prccess.
The procedure applies tc all TVn nuclear plants except Ercuns Ferry.)
0140]Q 8-79
TNA-TB75-1 Fev. 3 fhk TAELE 17.1A-2 (Continued)
(Criterion IX)
- Nondestructive Examination CCNST-CAF-9.05 (This procedure establishes the general requirements for Nondestruc-tive Examination perferred in the construction of nuclear power plants.
The procedure applies to all TNA nuclear plants except Ercwns Ferry.)
(Criterion X)
- Inspection CONST-CAF-10.01 (This precedure assigns the respcnsi-bility and specifies the various characteristics governing inspection (quality control) activities.
The procedure applies to those inspection activities, excluding nondestructive examinations, required tc verify conformance with the documented instructions, prccedures, and draw-ings fcr acccmplishing activities affecting quality during ccnstruc-tion.
Yte procedure applies to all TVA nuclear plants except Ercuns Ferry.)
(Criterion XI)
- Test Centrcl CONST-QAP-11.01 (This procedure assigns the responsi-bility and specifies the varicus characteristics governing test (quality control) activities.
The procedure app as to those tests perfcrmed duritj ccnstructicn required to demonstrate that systems, components, and structures will perform satisfactorily in service.
The procedure applies to all TNA nuclear plants except Erchns Ferry.)
(Criterion IX)
- Belease for Drilling, Chi i
EE ng, Cut-CCNST-CAP-ting of or kelding to Fernanent t
9.04 Structures or Congenents (This procedure assigns responsibility and defines the sequence cf acticos to be accomplished for ottaining a release, and for dccumenting satis-factory work congletion fcr drilling, chipping, cutting cf, cr welding tc permanent structures or ccapcnents, O.I.4074 8-79
TVA-TR75-1 Fev. 3 O
TAELE 17.1A-2 (Continued) when such operations are not stcwn on Division of Engineering Decign (EN DES) or centracter drawings.
The procedure applies to permanent ccncrete and steel features of safety-related items.
The prccedure applies to all TVA nuclear plants except Erowns Ferry.)
(Criterion XII)
- Centrcl of Feasuring and Test Equirment CCNST-CAF-12.01 (This precedure assigns the respcnsi-tility and defines the requirenents for procedures which descrite the calibration technique and frequency, and the naintenance and centrol of all tcols, gauges, instrunents, and other neasuring and testing devices used at a construction site.
This procedure applies tc neasuring and test equipnent such as instruments, tools, gauges, fixtures, and ncnde-ggg structive test equipnent used during the acceptance and docunentaticn activities of sa fety-related struc-tures, components, or systens cf a nuclear power plant.
It also includes requirenents for reference and transfer standards, cutside calitration latoratories, and capatilities of perscnnel using or handling measuring and test equipment.
The procedure applies to all TNA nuclear plants except Ercuns Ferry.)
O s2407s 8-79
TVA-TB75-1 Fev. 3 TABLE 17.1A-2 (Continued)
(Criterion XIII)
- StoraSe and Freservation cf Materials, CCNST-CAP-13.01 Components, and systems (This describes the quality assurance requirerents necessary for inclusicn in the quality centrcl prccedure for storage and preservation of materials, compcrents, and systems to preclude damage, loss, or deterioraticn by envircnmental conditions.
Centractor material and equipnent within the scope of the quality assurance pro-gram is handled in accordance with contractor's procedures which have been approved by the Divisico cf Engineering Cesign.
The procedure applies to all TVA nuclear plants except Erowns Ferry.)
(Criterion XIII)
- Bandling of Euclear Courcnents CCNST-CAP-13.02 (This procedure defines the CCNST quality assurance requirenents fcr handling nuclear safety-related components during fatrication, pre-ventive maintenance, inspecticr, and usage at the construction site.
The procedure applies to testing and inspec-tion of major nuclear safety-related com-nents that require special handling in-structions due to their weight, size, susceptibility tc shock danage, high nil ductility transition temperatures, or any other conditicns that warrant special instructions.
The procedure applies to all TVA nuclear plants Erowns Ferry.)
(Criterion XIV)
- Inspection and Test Status CCNST-CAF-14.01 (This procedure assigns the responsi-bility and defines the requireuents to indicate current insta11aticn, inspection, and test status of quality assurance items.
This procedure applies tc these inspecticns and tests perferred cn quality assurance structures, systems, and ccmponents (items) during the construction phase of nuclear power plants.
The procedure applies tc all TVA nuclear plants except Ercuns Ferry.)
- ~
f}2.407(;
TVA-TE75-1 Fev. 3 TAELE 17.1A-2 (Continued)
(Critericn XV)
- Control of Nonconforming Items CCNS7-CAF-15.01 (This procedure assigns the responsi-tility and defines the sequence cf acticns for the systematic contrcl (identification, segregaticn, and disposition) cf nonccnforming items and verification of corrective action to resolve ncnconformances.
The procedure applies to all activities, materials, structures, ccmponents, or systems, (iters) within the scope cf the Division cf Ccnstructicn (CCNS1) Quality Assurance Ercgran.
The procedure applies to all TVA nuclear plants except Ercwns Ferry.)
(Critericn XVI)
- NBC-CIE Feglies CCEST-CAF-16.02 (This procedure defines the systen of centrcl by which responses to Nuclear ggg Regulatory Ccamission - Cffice of Inspection and Enforcement (NFC-CIE)
Eulletins and NRC-CIE InspectiCn Report "Enfcrcement Items" are pre-pared by responsible elegents cf CONST and transmitted to the appropriate eleFents of EN DES.
The procedure applies to all fcrmal requests for information made by the Eesign Prcject Managers to the Constructicn Froject Managers for use in respcnding tc NBC-CIE Eulletins and NBC-CIE Inspec-tion Reports.
The procedure applies to all TVA nuclear plants eXCept Ercwns Ferry.)
O
,J r.' t O 4 8 8-79
TVA-TF75-1 Fev. 3 TABLE 17.1A-2 (Continued)
(Criterion XVII)
- Suality Assurance Fecords CCNST-CAF-17.01
(" Sis prccedure assigns the respcnsi-tility and defines the prcgram for the identificaticn, retrievability, and retention of quality assurance records.
The prccedure applies to quality assurance records generated by or in the possession cf the Eivision of Construction and speci-fies the program fcr the preparation, collection, filing, storage, nainte-nance, and dispositicn of quality assurance records during the cen-struction phases cf nuclear plants.
The procedure applies to all nuclear plants except trcuns Ferry.)
(Critericn XVIII)
- Auditing Ccnstruction Activities CCNST-CAE-18.01 (This procedure describes the process for ccnducting cceprehensive audits of ccnstruction activity tc verify that applicatle elements of the quality assurance progran have been developed, documented, and effectively implenented in acccrdance with speci-fied requirenents.
This Frocedure applies to the auditing cf those CCNET (inte rnal), contracting, and/or service (external) organizaticns at the ccnstruction site that perfcra safety-related activities.
Eten directed by the Chief, CA Staff, CONST, this procedure applies to the audit-ing cf offsite organizaticns that support constructicn activities.
This procedure alsc applies to audit deficiencies at the ccostructicn site for which EN DES has responsibility and provides to repcrting these defi-ciencies to the Chief, CA Staff, CCNST, for his resoluticn in cocrdinaticn with the Chief, CA Staff, EN EES.
The procedure applies to all TNA nuclear plants except Ercuns Ferry.)
814078 8-79
TVA-TE75-1 Bev. 3 O
TAELE 17.1A-2 (Continued) l3 SECTION E - DIVISION CF CCESTFUCTION
$UALITY CCNTEOL PRCCEEUEES (Criterion XII)
- Calibration cf Laboratory Neasuring CCNST-CCF-5.1 and Test Equirnent (This procedure describes the nethods to te utilized tc ensure that the accuracy of laboratory measuring and test equipnent is naintained.)
(Criterien IX)
- Cuality Assurance F_equirenents fcr CCNST-CCP-5.2 Concrete Mixture Prororticning (This procedure descrites the respon-sitility of the Naterials Engineering Laboratory to prcvide the necessary resources in terns of perscnnel, equirnent, and services to inglenent mixture design prcgrams.)
(Critericn X)
- Quality Assurance Fequirenents fcr g
CCNST-CCP-5.3 Soil Investigaticn Prior tc Construction CIbis procedure describes the respcn-sitility of the Naterials Engineering Laboratory to prcvide the necessary resources in terns of perscnnel, equipnent, and services in order to implement these requirenents in ccm-pliance with regiasts issued by the Division of Engineering Design.)
(Criterion XI)
- Cuality Assurance Fequirenents for CCNST-CCP-5.4 Latoratory Testing cf Protective Coatincs (This procedure specifies rethods and procedures for the latcratcry inspec-tion, testing, and verificatico cf protective coating materials applied surfaces for nuclear facilities of Class I and II Service Levels.)
(Criterion XI)
- Quality Assurance Bequirenents fcr CCNST-CCP-5.5 Mechanical Testing of Netals (This procedure specifies the netnods h
and procedures fcr latcratcry test-ing, inspection, and verification of metals.
The procedure applies to all TVA nuclear plants except Browns Ferry.)
314073 8-79
TVA-TR75-1 Fev. 3 TABLE 17.1A-2 (Continued)
(Critericn NI)
- Cuality Assurance Fequirerents for CCNST-CAP-5.6 Naterials Feview Reccrts (This procedure assigns the respcnsi-tility and defines the sequence cf actions to be accceplished in the preparation, review, and ccntrcl of Naterials Review Feports of all materials tested by Singleten Naterials Engineering Latcratory.
The procedure applies to all 1NA nuclear plants except Ercwns Ferry.)
- ~ "
814080
TVA-TR75-1 Rev. 3 (3) Performs technical reviews for compliance with regulatory requirements of thos. licensing documents supporting the license applications isscribed in item (1).
( 4) Acts as liaison with the NRC and coordinates representation in meetings with the NRC, licensing hearings, public meetings, and other discussions of proposed licensing actions with other organizations participating as required.
(5) Coordinates for the Office of Power correspondence related to compliance with regulatory requirements or in the case of operating nuclear genercting facilities, reviews such correspondence to ensure compliance requirements are met.
17.2.1.1.4 Division of Fuels (FUELS).
The Division of Fuels plans the supply of f uel resources to serve TVA's power demand forecasts.
It defines requirements for nuclear fuels, participates with the Division of Purchasing in preparing and negotiating contracts for the procurement and processing of nuclear fuel materials.
2 Nuclear Fuels Planning Branch (NFPE)
The Nuclear Fuel Planning Branch of the Division of Fuels is responsihle for:
(1) Developing and maintaining the Nuclear Fuel Quality Assurance
- Program, (2) Feviewing changes to fuel designs, and (3) Providing technical management of nuclear fuel including review or preparation of core and fuel specifications surveillance of related vendor quality assurance progr,ars and fahrication facilities, and evaluation of core and fuel performance.
The status and adequacy of the Nuclear Fuel Quality Assurance Program shall be reported to the Director of FUELS and the Quality Assurance Manager through surveillance reports written at 3
the completion of each surveillance trip.
17.2.1.1.5 Manager, Power Operations.
The Manager, Power Operations, Division of Power System Operations. supervises the Division of Fower Production He reports directly tc the Manager of Power as shown on Figure 17.2-1.
17.2-7 G
s u o s.t 8-79
TVA-TR75-1 Fev. 2
- 17. 2. 1. 1. 6 Division of Power Production (P PROD).
The Division lf or Power Production operates and realntains all TVA electric generating plants, including nuclear plants.
Director ot Power Production The Director of Power Production is responsible for quality assurance in plant operation and maintenance and determines the area of responsibility assigned to each tranch in t he division.
He is responsible f or maintaining tre Operational Quality Assurance Manual for each operating plant.
He assures that responsibilities for quality assurance are clearly defined and understood by the respective tranch chief s and that each organization is adequate to accomplish its tas':.
He is intormed of significant problems or occurrences relating to safety or quality assurance and participates directly in their resolution as required.
Power Plant Maintenance Eranch T.ie Power Plant Maintenance Branch ( PPMB) provides assistance and guidance to plant supervisors on maintenance planning and on ditricult or unusual maintenance problems.
Figuro 17.2-2 is an organizational chart for the PPMB.
The Technical Support and Planning Group of the Power Plant Maintenance Branch has the following responsibilities in g
executing this plan:
1.
Furnisning NDI examiners (ultrasonic, magne _ic part icle, and dye-pene tra nt) for generating plant inspections.
2.
Administering contracts with outside inspection agencies for ASME Section XI preservice baseline and in-service inspection or nuclear plant components.
3.
Recommending welding and heat treating practices to all plants and establishing qualifications of procedures and personnel tor welding.
2 The qualification requirements for the Supervisor, Technical Su-ort and Planning Group are as follows:
He should be a gi _.aate engineer or equivalent witn several years of experience in operation and maintenance of mechanical equipment in nuclear power stations.
He should have a thorougn knowledge of the principles and practices of the operation, maintenance, and improvement or generating plant equipment; a thorough understanding or TVA's organization tor development and operation 17.2-8 0
8-78 SM082
TVA-TR75-1 Rev. 3 core components are to be operated or positioned in a nonstandard manner.
3.
Performs reviews of modification of nuclear plant computer sof tware and maintains documented and approved sof tware records.
Quality Assurance Sta f f The Director of Power Production has delegated the responsibility for quality assurance within the division to the 2
s upervisor, Quality Assurance Staff.
His priieary responsibility is to assure that the P PROD quality assurance program for operation and maintenance of TVA nuclear plants fulfills the NRC and the Of fice of Power requirements for quality assurance.
The Quality Assurance Staff supervisor shall annually review the status and adequacy of the operational quality assurance program 3
and shall report the rerults of these reviews to the Director of P PROD and the Quality Assurance Manager.
The Supervisor, Quality Assurance Staff is required tc he a graduate engineer or equivalent with at least seven years' experience in nuclear plant maintenance, operation, or quality a ssurance, or a combination therecf.
Experience in the
( velopment, implementation, and evaluation of quality assurance programs is also required.
He will be assisted in carrying out his responsibilities by an Administrative Officer, a Coordinator of Field Support, and a Coordinator of Materials and Procurement Support as follows:
2 1.
Administrative Officer--Is respcnsible for the documentation, coordination, and distribution of nuclear quality assurance communications for P PROD.
He also cv.cdinates the formal review of operating experience reports, new and revised codes and standards, and other matters pertaining to quality assurance.
The Administrative Of ficer is required to have a general knowledge of nuclear plant Federal regulations, codes, and guides; quality assurance requirements; and P PROD and TVA policies for inplementing the regulations, codes, and standards.
Should have a college education or approximately two years' experience in a position where the emphasis has been on compiling technical information r;1ating to operational aspects of nuclear plant procedures and reports.
2.
Coordinator of Field Support--Is responsible for providing sate quality assurance engineering and quality control 17.2-11 3.MOS3 s_79
TVA-TR75-1 Rev.2 inspection services tc the plant staf f during majcr l
modifications, refueling cutages, or cther tine of unusual activity at plant sites.
He wcrks through the plant CA staff tc provide such services as reviewing quality contrcl plans, inspection precedures and instructions, and wcrk plane; performing quality assurance engineering, inspectico, ard surveillance of field work; ar.d reviewing ccmpleted work packages and cocunentation.
The Coordinatcr of Field Support is required to be a graduate engineer or equivalent with at least five years experience e
related to power plant design, ccnstruction, maintenance, 2
operation, or quality assurance, or a ccatiration therecf.
3.
Coordinator of Naterials and Procurerent Surrert--Responsible for reviewing purchase doccTents for nuclear safety-related items not purchased by part nuater cr specific standards cr whose failure would violate the reactor ecclant pressure tcundary.
He is also responsible for the review of supplier and centractor quality assurance prcgrans.
The Cccrdinatcr of Materials and Procurement Support is required to be a graduate engineer, or equivalent, with at least five years' experience related to power plant design, ccnstruction, maintenance, operation, cr quality assurance; or manuf acturing quality assurance; or a conbinat'.cn thereof.
Nuclear Flant Superintendent
,7te prinary responsibility and authority for reactor operatica and safety at each plant is vested in the superintendent.
It is the responsibility of the superintendent to assure that construction has been satisfactorily ccapleted and that established acceptance criteria are satisfied before accepting plant systems and conponents for cperation.
It is also his respcnsibility tc verify that nodifications or revisicns nade subsequent to the orig!"al design and ccnstruction of the project are authorized and carried out in accordance with establisted pro cedures and are reflected in the as-tuilt drawing. and spec 15ica*icns, and that ctjectives and performance defined during the design and construc mmn phase are not degraded during subsequent phases cf the project.
Plant quality assurance and quality contrcl are direct responsibilities of the superintendent.
Through assignments to his secticn supervisors he assures that operaticnal instructicns, wcrk instructicns, and checklists are prepared in accordance with established quality assurance Eclicies and requirenents; that 17.2-12 O
9MOS4 a-78
1VA-1R75-1 work is perf ormed in accordance with these apprcved documents; and that results are documented and proper reccrds naintained.
The superintendent is also responsible fcr the adequacy and ccmpleteness of operating and raintenance logs, and the training and qualification of giant personnel.
Plant Cperations Feview Ccmmittee (PORC1 The ECFC serves in an advisory capacity tc the superintendent in matters related to safety in plant operaticn.
It meets at regular monthly intervals and for special meetings called by the superintendent.
Nestership includes the superintendent (chairman), assistant superintendent (alternate chairaan), health physicist, maintenance superviscr, results supervisor, cperaticns supervisor, and the plant quality assurance staff supervisor.
The rinutes cf each reeting are recorded.
Fespcnsibilities of the FCFC include the following:
1.
Review of all standaru and energency creration and raintenance instructions and any proposed revisions thereto, vith principal attentica to previsions for safe operaticn.
2.
Feview cf proposed changes to the technical specificaticns or license.
3.
Beview cf propcsed chunges to equipnent or systems having safety significance, or which may constitute aar unreviewed safety qucaticn," pursuant to 10 CFB 50.59.
4.
Investigation of reported or suspected incidents involving safety questices, violaticns of the technical specifications, and violaticns of plant instructions pertinent te nuclear safety.
5.
Beview of reportable cccurrences, unusual events, operating ancualies, and ahncrmal perfornance of plant equipaent.
6.
Feview cf plans fcr special fuel-handling and plant maintenance operations.
Feview of tests cr experiEents which may invc1ve special safety considerations and the results thereof where applicatle.
7 Peview of adequacy of the plant quality assurance progran and recorrendation of appropriate changes.
17.2-13 3.1.40SE.
8-78
7%A-7B75-1 Rev. 2 8.
Review cf inplencnting procedures of the Fadiological lh Energency Plan and the Industrial Security Frcgran cn an anntial tasis.
9.
B(view of adequacy of employee training programs and reconnendation of changes.
Plant Cuality Ansurance Staff The plant quality assurance staff assists the plant superintendent in developing, planning, initiating, and directing a comprehensive nuclear plant quality assurance / quality ccntrcl program which implements the Civisicn of Pcwer Production quality assurance program as detailed in the procedures of the plant crerational Cuality Assurance Manual.
The quality assurance staf f performs quality assurance functicns relative to plant operations and provides quality control inspections and verificaticn of thoce activities.
It evaluates the effectiveness of the program and nakes reccamendations to the plant superintendent regarding its inpleaentaticn.
It verifies that operational instructicns contain applicable quality assurance requirements and that employees are fellowing the approved instructions.
The quality assurance staff reviews and reccamends approval cf plant instructions ccncerning the CSSC (such as inspection plans; test, calibration, special prccess, maintenance, modification, and repair procedures and instructions; drawings; specificaticns; and changes theretc) and g
shall sign of f prior to their use attesting tc the fact trat the format and content are in compliance with quality assurance rcquirements for the plant.
The staff will also te respcnsible for the in-plant CA/CC training prcgram, certifying plant perscnnel who perform receiving inspections, and verifying qualificaticns of cther personnel performing CC functiCns.
The plant quality assurance staff shall review all purchase requisitions for CSSC items and services prepared by the plant staff to ensure they have teen prepared, reviewed, and apprcvEd in accordance with quality assurance program requirenents.
Personnel who perform this review shall te trained in FICCureFent document control requirements in the in-plant CA/CC training prograr.
7te quality assurance staff is also responsible fcr developing and inplementing a CC inspecticn or surveillance program ccvering operations, maintenance, repairs, and testing of 2
CSSC items and for reviewing plant activities and keeping the plant superintendent advised cf failure of plant equipaent to 17.2-14 O
SMOSG s-78
TVA-TR75-1 Fev. 3 The quality assurance staff is also responsible for develcping and inplementing a CC inspection or surveillance program covering operations, maintenance, repairs, and testico of CSSC items and for reviewing plant activities and keeping tra plant superintendent advised of failure cf plant equipnent to technical specification requirements or cther noncericy. ming meet aspects of operaticns.
The plant quality assurance staff supervicor is a neater cf the PCFC.
Ee represents the plant superintendent in meetings with TVA auditors and NFC inspectors and is recponsible fcr the preparation of all rcrorts to NFC required by the radic1cgical and nonradiological technical specificaticns and for respences to plant audits.
Khen quality assurance problers occur, the plant quality assurance staff supervisor has the responsibility and authcrity to take the necessary corrective action, including teraination of an activity through the plant superintendent, when ranufacturing, maintenance, repair, refueling, operation, or acdification work fails to conply with approved specificaticns and plane.
Should the plant superintendent fail tc fcllow the recommendation of the plant quality assurance staff supervisor, the supervisor has the authority tc report directly tc the Nuclear GeneratiCn EranCh Chief.
9 The supervisor of the plant quality assurance staff snall have seven years of responsible pcwer plant experience cr applicalle quality assurance experience of which a ninimun cf two years shall be nuclear power plant experience.
He sbculd be a graduate with a degree in engineering.
A naximum of two years of the remaining five years of power plant or quality assurance experience way be fulfilled by satisfactory ccepletior cf academic or related training on a cne-for-one tasis.
17.2.1.1.7 Division of Power Systen Crerations (FSC).
The Divisicn cf Power System Cperations operates the transmission and communication systen network to deliver power from sources cf supply to delivery points serving power contractors; deternines systen loading; and pcrforms dispatching.
It provides relayirg, protection, test, gaintenance, and calitration services for safety-related electrical systers.
17.2.1.1.8 Divisicn cf Occupational Health and Safety.
The 3
Division of Occupational Health and Safety is responsible fcr developing and applying the engineering and health physics aspects of radiological health services required in the planning and operation of TVA's nuclear plants.
The pertinent requirements of the Operational Quality Assurance Program shall be applied to these activities.
3 1
17.2-15 8-"
3140S7
TVA-1875-1 Fev. 2 17.2.2 crerational Ouality Assurance Prcqram This quality assurance prcgram contains the of fice of FoWer's quality assurance requirenents.
Ubis program shall te ccntained in the Of fice of Fower quality Assur_ance Manual which stall be maintained and distributed to all responsible organizations by the cuality Assurance Manager.
The Manager of Power has established a Quality Assurance and Audit Staff which is sufficiently independent of operational pressures and has assigned to it the respcnsibility for defining and monitoring the quality assurance prcgran.
The cuality Assurance Nanager shall te reepensible for the develognent cf the Of fice of Ecwer Quality Assurance Erogram and the Manager cf Power shall have the final approval.
This program shall include procedural centrcle for assuring the operation of TVA's nuclear plants without undue risk to the health and safety of the public or employees.
It is directed at providing the appropriate contrcl cr quality in relaticn tc the inportarce of the activity or iten.
Technical interfaces, such as transfer of equipnent and records tetween organizations, are covered by interdivisicral procedures which are approved by the division directors.
O Each cf the 18 criteria of 10 CFR 50, Appendix E,
is addressed in this quality assurance progran.
The requirenents of these criteria shall te implenented throughout the operating life of each TVA nuclear plant and shall te inplemented through written procedures and instructions.
The quality assurance requirements during operation shall be at least equal tc ttcse during original design and ccnstruction.
The Assistant Manager of Pcwer shall te regularly advised en the status and ef fectiveness of the quality assurance program by 2
the Quality Assurance Nanager.
The implenentation and ef fectiveness of this program shall te regularly assessed thrcugh audits.
These audits shall te reported to the Fanager of Ecwer, plant superintendents, and other apprcpriate levels of managenent.
Critical structures, systens, and components (CSSC) covered by the operational quality assurance prcgram are identified in the Final Safety Analysis Feport fcr the plant.
The CSSC list shall include the safety-related structures, systems, and components identified during the design and construction phases and may be expanded in detail as required by operations.
17.2-16
TVA-7R15-1 Rev. 3 The requirenents of the Of fice of Fower Cuality Assurance Frogram also apply to instrunents
.d devices used in the measurenent of 3
the of ficial personnel radiation dcse and to the equipFent used to ca11trate them.
The Cuality Assurance Manager shall develop, raintain, and document a quality assurance indoctrination and training pregram 2
for central office ("cf f site") perscnnel whc perfcrm quality-a f fecting f unctions.
This training program shall provide seminars to present TNA's quality assurance program internally and industry-sponscred training ccurses cr schocls to train and maintain the proficiency of quality assurance personnel.
This program shall cover the follcwing areas:
CA history and indoctrination Fegulations and industry standards 7VA requirements ASME codes The Director of Fower Producticn shall develop, maintain and document a training and retraining progran for plant staf f personnel ("onsite") Eerforming quality-affecting-activities.
These training and indoctrination programs will assure that:
(a)
Fersonnel respcnsible for performing quality-affecting activities are instructed as tc the purpose, scope, and inplenentation of the quality-related manuals, instructions, and procedures.
(t)
Fersonnel perfcraing quality-affecting act
.ies are trained and qualified in the principles and techniques of the activity teing performed.
(c)
The scope, the objective, and the method of implementing the indoctrination and training progran are documented.
(d)
Froficiency of personnel perfcrming qual.ity-affecting activities is gaintained by retraining, reexamining, and/or recertifying.
(e)
Methods are provided for dccunenting training sessions describing content; who attended; when attended; and the results of the training sessicn.
Certain quality assurance-related activities and records beccme the responsibility of the Cf fice cf Poker with the 17.2-17 Sl/ii)SS 9-79
TVA-TR75-1 Rev. 2 issuance of a formal cperating license and shall be ccntrclied with procedures.
Tatle 17.2-1 shows the structure, scope, and respcnsibility for the CA nanuals required for this quality assurance prcgran.
Table 17.2-2 is a listing cf centrclied implementing procedures and instructions.
These manuals and procedures contain the mandatcry requirements which rust be isplemented ty responsible organizations and individuals.
Table 17.2-3 lists the procedures which inplerent this quality assurance prcgram and cross-references the 10 CFR 50, Appendix E, requirenents.
The Directcr of Fuels shall develop and maintain a quality 2
assurance program for nuclear fuel.
The design, fatrication, and associated quality assurance requirements are generally delegated to qualified fuel suppliers.
However, the Cffice of Fower has overall responsibility for assuring that nuclear fuel installed in TV7 reactors meets applicable criteria to assure safe and rellatle cperation.
This responsitility is executed thrcugh a planned and systematic program of quality surveillance of nuclear fuel suppliers.
Disputes arising tetween CA/CC personnel and personnel in organizaticns (such as operations, procurement, or saintenance) lll which cannot te resolved locally are referred tc the apprcpriate level of higher management for resciution.
If disputes cannot he resolved at this level, they would utlimately be resolved by the Manager of Eower.
17.2-18 O
sumo
TVA-TR75-1 Rev. 3 17.2.3 Modification Control 17.2.3.1 General.
Modi fications, additions, and replacements to the CSSC af ter issuance of an operating license shall be controlled to assure that nas-built" quality is not degraded.
P PROD is responsible for control of modifications to safety-related systems and components af ter the receipt of an operating license.
This includes:
specifying or making provision for quality assurance requirements in design documents; providing control of deviations from these requirements; specifying or reviewing materials, parts, equipment, and processes; and specifying or reviewing verification inspection and testing.
17.2.3.2 As-Built Verification.
Before accepting plant systems or equipment for operation, the plant superintendent assures that con struction is complete and meets established acceptance criteria.
This is accomplished through a formal transfer procedure involving inspection and testing to verify ccnformance to drawings and specifications.
The plant superintendent verifies that modifications or revisions to original designs are reflected in as-built drawings and that objectives and performance criteria are not degraded during subsequent phases of the project.
17.2.3.3 Modification.
Proposed modifications to the safety-related CSSC (except nuclear fuel and fuel-related components) shall be forwarded to EN DES for review and approval.
EN DES has a design control system covered by written procedures which complies with the requirements of 10 CFR 50, Appendix E (See 17.1 A. 3).
Proposed modifications to fuel related components shall be reviewed by both the Division of Fuels and the Division of Power Production.
Proposed modifications to nuclear fuel 2
shall be approved by the Division of Fuels and proposed modifications to fuel related components shall be approved by the Division of Power Production.
After receipt cf the operating license, all modifications shall be reviewed by the PCRC and approved by the plant superintendent prior to implementation.
Modification proposals which involve the revision of TVA drawings, equipment manuals, or vendor drawings require the issuance of a numbered Design Change Request (DCR) or Field Change Request (FCR) as shown in Figures 17.2-5 and 17.2-7.
3 Modifications to fuel-related components are processed as shown in Figure 17.2-6.
17.2-19 0.$ & 5 $
0-79
TVA-TR75-1 O
Procedures and instructions shall be developed and implemented to assure that the design, construction, installation, inspection, and testing of modifications to the CSSC meal quality assurance standards at least equal to those of the original in s ta llat ion.
The testing assures system integrity and provides for evaluation of performance prior to system operation.
Procedures and instructions related to equipment or systems that are modified shall be reviewed and updated to refloct the modi f ica ti on.
Modification work will normally be perforn.d by P PROD personnel.
In cases involving ma jor modifications or requiring specialized personnel or equipment, the TVA Division of Construction (CONFT) or an outside contractor may be used.
P Pron retains ultimate responsibility for ensuring appropriato quality assurance standards of materials, equ ipme nt, and workmanship.
The plant superintendent shall approve all design change requests bef ore performance of the work.
The Plant Operations Review Committee has the final responsibility to verify that:
1.
All requirements of the review and approval process have been satisfied.
2.
All prerequisites to s af ety have been met.
I) 3.
Required drawings and installation instructions are approved and available.
4.
Quality assurance controls have been incorporated in the modification.
17.2-20 314092
TVA-TR75-1 17.2.4 Procurement Cocument Centrol Procurement document control applies to documents used to obta in materials, parts, components, and services required to modify, maintain, re pa i r, testy inspect, or operate nuclear generating facilities.
The quality of purchased replacement materials, components, and spare parts shall be equal to or better than the original item.
Control of procurements shall be accomplished primarily through the purchase requisition.
The originating organization shall be responsible for including or referencing regulations, codes, standards, design bases, or other provisions necessary to assure adequate quality assurance requirements in the documents for procurement of materials, parts, components, and services.
Purchase requisiticns shall include the following as applicable:
1.
Basic technical requirements, including drawings, test and specification requirements, special instructions, applicable codes, and industrial standards.
2.
Requirements for supplier surveillance and inspection, including provisions f or TVA's access to its plant and records.
3.
Requirements that the supplier provide a description of his 9
quality assurance prog ram including a discussion of how applicable requirements of 10 CFR 50, Appendix B, will be satis fied.
4.
Documentation requirements, including records to be prepared, maintained, submitted, or made available for review, such as drawings, specifications, procedures, procurement documents, inspection and test records, qualifications, chemical and physical test results, and instructions for ultimate disposition of the records.
TVA utilizes recognized standards for the purchase of standardized items such as bearings, V-belts, ca pa c it ors,
resistors, trcanistors, lubricating oils.
Other items are purchased by part number or recommendations supplied by the original manufacturer or vendor.
Items which are covered by industry codes or standards (e.g., welding rod, pressure boundary materials, e tc. ) a re purchased in accordance with the applicable codes and standards.
17.2-21 i
S.14093
TVA-TR75-1 Rev. 3 The plant quality assurance staff shall review all purchase requisitions for materials, components, spare parts, and services to ensure they have been prepared, reviewed, and 3
approved in accordance with quality assurance program requirements.
The P PFOD QA Staff shall review purchase requisitions for safety-related services and CSSC items not purchased by part 2
number or specific standard to ensure that quality assurance requirements are correctly stated, inspectable, and controllable and that there are adequate acceptance and rejection criteria.
Procurement documents shall include all quality-related purchase requisition requirements and these shall not he changed without the review and approval of the originator and the responsible quality assurance organizations.
O 17.2-22 314094 0
8-79
TVA-TR75-1 Rev 2 17.2.8 Identification and Control of Materials, Parts, and Components The identification and control of materials, pa rt s, and components shall be accomplished in accordance with written requirements and apply to materials, parts, or components in any stage of fabrication, storage, installation, or use.
Materials, parts, and components identified as nonconforming shall be handled in accordance with subsection 17.2.15 of this plan.
Identification and control requirements cover such items as traceability to associated documents (s peci fica t ion s, purchase orders, manuf acturing test data and inspection documents, and physical and chemical mill test re port s) ; specification of the degree of identification and control necessary; location and method of identification to preclude a degradation of the item's functional capability or quality; and the proper identification of materials, parts, and components before release for manufacturing, shipping, construction, and installation.
Materials, parts, and components manuf actured or modified by TVA shall be similarly identified, documented, and controlled.
The Director of Power Production shall provide procedures for identification and control of items of CSSC received, stored, installed, used at the plant site, permanently transferred to or purchased by the Division of Power Production, or transferred between operating plants.
The plant superintendent shall provide instructions for identification and control of materials, parts, or components received, s to red, installed, modified, and used at the plant site.
The plant quality assurance staf f shall ensure that proper documentation accompanies safety-related materials, parts, and 2
components be fore their use or installation by surveillance of receipt activities and documentation maintained by the Power Stores Unit.
In the event traceability is lost for a specific item, it will be handled as nonconforming material and treated in accordance with subsection 17.2.15.
17.2-31 0
314095 a-78
1VA-1R75-1 Rev. 3 17.2.9 Ccntrol of Special Frccesses h
Special processcs, including welding, heat treating, and ncndestructive testing, shall be identified and centrclled to ensurt they are acccmplished according tc approved written q ualified Frucedures.
Prccedures are qualified in aCCcrdance with applicable ccdes and standards or, where nc appropriate standards exist, to TNA requirements.
As required ty applicable codes and standards, perscnnel performing these special prccesses shall te qualified and their qualifications shall be docunented.
Applicable codes, standards, specificaticos, criteria, and cther special requirenents shall be identified and used in qualifying procedures and personnel used tc accomplish special prcCesses.
The Division cf Fcwer Producticn shall ensure that perscnnel
'toth internal and external tc TVA) performing special prccesses under their ccgnizance are qualified and are using prccedures qualified tc neet applicable codes, specifications, and standards.
Special prccess procedures submitted by outside centractors in accordance with prccurement docunents and all TVA special process procedures stall be reviewed and approved by F FFCC.
Instructions for performing special prccesses shall te prepared when it tecenes necessary to apply a specific special prccess in the maintenance, repair, or modification cf some portion of the lll CSSC.
The plant quality assurance staff shall review prcccdures and instructions controlling special processes to verify that quality assurance requirenents and acceptance criteria are inccrpcrated.
They shall verify that the special prccesses are perforned ty qualified personnel.
The current qualificaticn records cf any l
plant special process instructicns and plant equipment shall te maintained by the responsible plant supersisor and reviewed by the plant quality assurance staf f.
Evidence of the qualification 3
of plant perscnnel performing special processes will te maintained by the responsible plant supervisor.
The reccrds cf special prccess prccedures controlled by central of fice (cf f site) organizations and the reccrds of central cf fice peraccrel performing special prccesses at the plant shall te maintained by the responsible central of fice superviscr (s).
Plant and central office records are audited by the Cffice of Power Quality Assurance and Audit Staff.
17.2-32 9L1036 O
8-79
TVA-TR75-1 Rev. 3 17.2.18 Audits The Quality Assurance Manager is responsible for a system of planned and periodic audits of the Of fice of Power's assigned responsibilities.
These audits shall be conducted on both a scheduled and unscheduled basis.
Objectives of the audit system are:
(1) to ensure that the Office of Power Quality Assurance Program is defined and dccumented; (2) to verify on a regular basis by examination and evaluation of objective evidence that established requirements. methods, procedures, and instructions are being implemented; (3) to assess the ef fectiveness of the office of Power Quality assurance Program; (4) to identify program weaknesses and nonconformances; and (5) to verify correction of identified unsatisf actory conditions.
The Quality Assurance Manager has the authority and organizational freedom (see Section 17. 2.1) to schedule and perform both internal and external audits to ensure proper corrective action.
As a minimum, the audit system under his direction shall be designed to comply with regulatory requirements.
Audits shall be conducted by the Quality Audit Section as s cheduled.
Special audits shall be conducted when a need is indicated.
The Quality audit Supervisor, who reports to the Quality Assurance Manager, is responsible for planning, scheduling, and implementing the audits and analyzing audit data for quality trends and ef fectiveness of quality arsurance.
He is responsible for generating the required audit rec ras, which include the audit plans, reports, associated correspondence, open item status reports, and other supporting documentation.
He is also responsible for providing teams comprised of qualified auditors and for preparation of audit reports, within 30 working days of audit completion.
Audits shall be conducted in accordance with a formal audit schedule which shall be updated at least every six months.
The schedule for audits of the Of fice of Power Quality Assurance Program shall comply with the requirements of regulatory position 3
C.4 of Pegulatory Guide 1.33.
Functions which are performed on a routine schedule basis, such as preventive maintenance, surveillance testing, and calibration, shall te audited for compliance on a f requency determined by their schedule.
One-of-a-kind projects, such as major modifications, shall be audited as required.
Unscheduled audits may be conducted in any area at any time on a randomly selected aspect of the program or to document conditions related to an abnormal or unscheduled event.
17.2-47 3.L40B?
8-79
TVA-TR75-1 Within the scope of the Of fice of Power Quality Assurance Program, both TVA and supplier / subcontractor organizations shall be subject to audit under this system.
Audits conducted on organizations within TVA are designated internal audits, and audits of suppliers and subcontractors are designated external audits.
Audits shall te conducted using written plans and checklists prepared in accordance with audit procedures which require evaluation of work areas, activities, processes, goods, se rvices, and the review of documents and records for quality-related practices, procedures, and instructions to determine the effectiveness of the implementation of the Office of Power Quality Assurance Program and compliance with 10 CFB 50, Appendix B.
In preparing for audits, the Quality Audit Section shall review applicable procedures, instructions, and manuals (see Table 17.2-2) in the area to be audited.
Any conflicts in requirements identified in this review shall be reported as audit findings to the Quality Assurance Manager.
For the performance of audits, an audit team consisting of one or more qualified persons shall be selected by the Quality Audit Supervisor.
A designated leader shall be assigned in advance to te responsible for the written plans, checklists, team o rien tation, audit notification, preaudit conference, audit per formance, postaudit conference, reporting, records, and followup audits to assure that unsatisfactory conditions are (lh resolved.
The audit team will be comprised of personnel from the Quality Assurance and Audit Staf f, but specialists may be assigned from other TVA organizations.
In no case shall a team member be assigned to audit an area in which he has work responsibility.
Audit procedures require that upon completion of an audit all findings shall be reported to responsible management of the organization being audited.
Any audit finding which requires immediate resolution shall be reported without delay to appropriate supervision.
Other findings may be reported in an exit interview or ty submitting a written summary of audit findings to responsible supervision.
Formal audit reports shall be transmitted by the Quality Assurance Manager to the responsible TVA supervisor or outside organization (correspcndence with suppliers is normally through TVA Procurement channels).
It is the responsibility of the cognizant supervisor, or the person in the outside organization specifically designated as responsible, to review the audit report and to ensure that corrective action is accomplished in a 17.2-48 O
3240as
TVA-TR75-1
~,
Rev 2 t imely manne r.
The audit team leader in responsible for followup action (ircluding rea ud i t s) as required to ensure that corrective action has heen taken.
Audit findings shall te documented in the audit report, and all corrective actions and reaudits shall be documented with reference to the original audit.
Audit records.shall be maintained which indicate audits, organizations audited, subject, and number of noncompliances identified during the audit.
These records shall be periodically I
revicwed for quality trends and overall program effectiveness.
Results of these reviews shall be reported to appropriate maragement in periodic summary reports of audit act iv it ies.
Peqular audit team members (no rma lly from the Quality Assurance and Audit staf f) shall be trained ir accordance with the quality assurance tra ining progrcin.
Members of audit teans who are nct regular auditors shall be indoctrinated or trained sufficien*1y to perform the specific audits to which they are assigned.
,Thi.s, audit system, shall te designed to satisfy the audit requirements of 10 CFF 50, Appendix B, and TVA nuclear plant t ec hp i.ca l specificaticns.
In regard to audit function, the Assistant Manager, Cffice of Power, has delegated to the Quality 2
Assurance Manager the responsibility to conduct audits of activities cf the Cffice of Power and activities of inter f aci ng o rgan izat,ico s a ssocia ted with safety-related systems.
A repres enta t ive list of the areas to be audited to ensure compliance with the Office of Power Quality Assurance Program is presented helow:
1.
DIVISICI, CF POWEP PROCUCTION 1.1 Nuclear Generation Branch 1.1.1 Cosign Control 1.1.2 Procurement Control
.1.1.
3 Training 1.1.4 Document Control
.,,].1.5 Corrective Action 1.1.6 Modi fication Centrol i
1.1.7 Fecords Control 1.2 Plant Engineering Branch 1,2.1 Document Ccntrcl 1.2.2 Training 1.2.3 Cesign Control
- 17. 2-49 314059
TVA-TP75-1 Rev 3 1.2.4 Corrective Action lll
].2.5 Fecords Control 1.3 Power Plant Naintenance Franch 1.3.1 Dccument Ccntrol 1.3.2 Training 1.3.3 Maintenance Control Jmaintenance, modification, rework, and repair) 1.3.4 Special Process Control Jwelding, heat treating, NDE, etc.)
1.3.5 Fecords Control
].1.6 In-Service Inspection 3
1.4 Cuality Assurance Staff 1.4.1 Cocument Control 1.4.2 Procurement Control 1.4.3 Pecords Control 2.
NUCLEAP PLANTS 2.1 Cperating Staff 2.1.1 Frocedure/ Technical Specifications Compliance with respect to:
2.1.1.1 Administrative Functions JTach Specs) 2.1.1.2 Fuel Handling 2.1.1.3 Cperations 2.1.1.4 Maintenance, Rework, Repair, g
Modifications 2.1.1.5 Design 2.1.1.6 Health Physics /Cheristry 2.1.1.7 Environmental Monitoring 2.1.1.8 Surveillance Testing 2.1.2 Cocument Contrcl 2.1.3 Training 2.1.4 Corrective Action 2.1.5 Procurement Control
].1.6 Material Handling, Storing, Issuing, Cleaning, Freserving, etc.
2.1.7 Calibration of Measuring and Iest Equipment 2.1.8 Padiological Emergency Plan 2
2.1.9 Fire Protection Frogram
- 2. 2 Plant Quality Assurance Staff 2.2.1 Cocument Contrcl
].2.2 Corrective Act ion 2.2.3 Training (Ouality Assurance)
.2.4 Feceiving Inspection
- 17. 2-50 8-79 I
S14100
TVA-TR75-1 Bev 3
_2.2.5 Plant Operation and Maintenance Inspection 2.2.6 Site Contractor Surveillance Control 3.
DIVISICN CF POWER SYSTEM OPER ATIONS 3.1 Cocument Control
- 3. 2 Corrective Action 3.3 Modification Control 3.4 Identificaticn and Control of Materials, Parts, and Components 3.5 Inspection and Test Control 3.6 Centrol of Measuring and Test Equipment 3
DIVISION CF FUEIS 31 Nuclear Fuel Quality Assurance Program 32 Cocument Control 5.
DIVISION OF CCCUPATIONAL HEALTH AND SAFE *Y 3
5.1 Cocument Control 5.2 Fecords 5.3 Environmental Radiological Monitoring 5.4 Pad iological Emergency Plan 5. 5 Nuclear Plant Health rhysics Prograr and supporting Activities 6.
DIVISICN CF PUFCHARING 2
6.1 Procurement Control 7.
DIVISICN OF WA"ER RESCURCES 3
7.1 Meteorological Monitoring Program 8.
REGULATC9Y STAFF 8.1 Cocument Control 9.
PCFC
- 10. MAJCB CCNTRACTCPS AND SUPPLIEFS 17.2-51 "o 1'"t A D-
8-79
TVA-TR75-1 TABLE 17. 2-1 OFFICE OF POWER - OA MANUAIE CHART Identi fi ca t ion Description Approval 1.
Of fice of Power Quality A manual consisting of the Of fice As noted below.
Ass"rance Manual of Power QA Plan and Of fice of Power QA Procedures.
a.
Of fice of Power Policy Plan by the Manager of' TVA's Of fice of Power QA Plan Power describing the quality QA Plan and all revisions assurance efforts that shall be thereto shall be approved applied to all operational by the Manager of Power attributes of TVA's nuclear or his designat ed power plants.
representative.
b.
Office of Power A s et of controlled procedures, All Office of Power QA QA Procedures issued by the Of fice of Power Procedures and all to control QA-related activities revisions thereto shall th roug hout the Office of Power.
Le approved by the These procedures assign Manager of Power or his responsibilities to various designated represent a-segments within the Office of tive.
Power and to other organizations within TVA and specif y the required actions to be taken for activities listed in the Office of Power QA Procedures Index.
2.
Quality Assurance and A set of procedures prepared, All Quality Assurance and Audit Staff Procedures controlled, and issued by the Audit Staff Procedures Quality Assurance and Audit and revisions thereto
- Staff, These procedures are shall be approved by the governing documents for Quality Assurance Mana-(O the internal activities of the ger or his designated ks Quality Assurance and Audit representative.
Lyn Staff with respect to the QA h, g, responsibilities t hat it has been assigned.
D) 4 I
I t
4
TN A-TR7 5-1 Psey. 3 TABLE 17.2-1 (Continued)
Identification Description Approval 3.
Cperat ional cuality A manual consisting of a set of All procedures mittin Assurance Manual procedures prepared, controlled, this ranual and all and issued by t he Division of revisions thereto shall Power Production. This Fanual te reviewed by the implements the requirements of Quality Assurance and the Office of Power Quality Audit Staff.
In addi-Assurance Plan with respect to tion, procedures and the activities associated with revisions involving tte the operation of ivA's nuclear assistance of other power plants.
TVA of fices or divisions shall be reviewed and concurred to by that office or division that is involved.
Final approval of all procedures and revi-sions to this manual is by the Director cf Power Production or his designated represent-ative.
4.
Nuclear Fuel Quality A manual consisting of a set All procedures wittin Assurance Manual of procedures prepared, controlled, this manual and all and maintained by the Nuclear revisions thereto shall Fuels Planning Branch of be reviewed and approved by 2
the Division of Puels.
the Quality Assurance and This manual serves as the govern ing Audit Staff.
In a ddi-doc ument for implementing the tion, procedures and cffice of Power Quality revisions involving the Assurance Plan with respect to assistance of other the design, fabrication, and TVA offices or divisions other related activities shall be reviewed and associated with the production and concurred to by and reprocessing of nuclear that of fice or division fuel for TVA's nucinar power that is involved.
plants.
Final approval of all procedures and revisicns to this manual is ty the Director of Fuels or his $clegate.
(D
>J 5.
Interdivisional QA A manual consisting of a All procedures wit hin this manual N
Procedures Manual set of QA procedures covering and all revisions thereto shall (see Table 17.0-1) interdivisional interface areas.
Le reviewed and approved by 3
.f* 7 af f ected organizat icn, the OEDC
(.D QA M an a ge r, and the FCWEP QA Manager.
(j
TVA-TF75-1 Fev. 3 TABLE 17.2-7 (Sheet 5)
TOPIC COwMFNT N.
Pequlatory_Guido 1.116, Revision O-R - " Supple-entary TVA takes no exceptions tc ttcse require-Quality Assurance Requirements for Installation, ments of N45.2.8 that are artlicable to Inspection, and Testing of Mechanical Equipment and plant molifications or repairs during the Systems for tim Con st ruct ion Phase of Nuclear Power operating phase.
Plants" (Endorses N4 5. 2. 8-197 5)
O.
ANSI N43 2.12 (Praft 3,
Nev.
4-Fe b r ua r y 1974)
TV4 takes exceptien to the following "Pequirements for Au fit ing of Cuality Assurance paragraphs:
P rog rams for Nuclear Power Plants a
- 2. 3, Training - Tec h nic a l crecialists who assist in perfurming auilt s in their ared of special expertire will not te trained in auditing techniques: however, they will always accorranted by a trained, quali-fied audit or.
3.4.2,
_nctefuling - The a rrlicarle clerent s of the operational quality assurance prograr will te audited in accordance wi t h t he requirer.e nt of FOSitioe C 8 of 3
Pegulatory Guide 1.33.
- 4. 3. 3, Post Aujit Conference past audit liscussion of all audit observaticns will te held and an unierstandirq of these otservat ions will t e reacted tut a d o cu men t of Lnierstan.fing will not be prepared and signed.
The (j) written response t c t he audit findinqs pg will serve to docurent this under-standing.
W pb
- 5. 2 Auilt Pecords - Audit Fecords will he
- [)
ma in tai ned in accordance wit h sect icn 5 of
)
. -)
AN91 N45.2.12-1977.
V.
1% A-T p15-1 Fev. 2 1ABLE 17.2-7 (Eheet 6)
TOPIC COMMENT P.
Requlatory Guide 1.123, (Revision 1), July 1977 -
No exceptions 2
" Quality Assurance Requirerents for Ccntrol of Procurerent of Equipment, Materials and Services for Nuclear Power Plants" (Endorses N45.2.13-1976)
Q.
Regulatory Guide 1.88 (Fevisicn 2), Cctober 1976 -
TVA takes excepticn to the r Equire-Fent ( ANS I N45.2.9, Secticn 5.6) that
" Collection, Storage and Maintenance of Nuclear Power Plant Quality Assurance Records" (endorses N45.2. 9) terparary record storage facilities shall te a four tour minipur rated facility.
Non-FerFanent reco rd s loCateC in teF[orary storage facilities will te stcred in 1-tour fire rat ed file catinets.
R.
Pelulatory Guide 1.94, (Revision 1), April 1976 -
For modif ications or repairs tc structurer within "cuality Assurance Requirements for Installation, the scope of N45.2.5-i974, the 1%A operaticns division Inspection, and testing of Structural Concrete and would refer back to the desien division fcr any Structural Steel Curing the Ccnstruction Phase of design analyses and refer to the ccnstruction Nuclear Power Plants" (Endor ses N45. 2.5-1974) division for actual work perfctrance.
TVA will comply with N45. 2.5-1974 except as indicated in sect ion 3.8. 3.6.1 of the Yellow Creek FSAP.
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u A. t a 8-79
Office of Power quality Assurance and Audit Staff Y
C"3 C"3 PC3 c=3 PC3 cr3 m
Quality Planning Quality Audit and Engineering P
Section Section Central Office Nuclear Plant $ites CD pa Quality Assuranc.
M Coordinators
)6 OO cICURE 17.2-.
Office of P m r Oualit'. Assurance and Audit Sta:f Organization Chart i 7evision 2-8-78 O
O O
Origin Origin Origin Plant P PROD Central Other TVA Office Divisions V
Plant Supt.
Review & Approval v
?!GB I?cview & Approval V
E!! DES Fornal Review v
PORC V
Plant Superintendent V
Performance of work O
Figure 17.2-5 FLOW DI AGRN1 - DFSIGti CIIAliGE REQUESTS Rev. 3 3 1'11.1.0 e_79
Origin Nuclear Plant if Origin Origin Origin P PROD Central Other TVA FUELS Divisions D C if FUELS /P PROD Formal Review OEDC For FUELS For 3r Non-Fue] Drawing Fuel Drawing Modification Modification if PORC if Plant Superintendent if Performance of Work FIGURE 17. 2-6 Flow Diagram - Design Change Request for Core Component g
Rev. 3 b1'I11_)
8-79
Initiation of FCR
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Cognizant Engr.
Contacts EN DES V\\
Efi DES
!!O Submit Concurrence DCR If of FCR Aeolicable YES 5
FCR YES FORC 6
Safety-Concurrence Related
!;0 V YES Plant Sutait
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Approval g cable YES V
Drawings Perfomance 4
Transmitted of 'n'ork To EN DES FIGURE 17.2-7 FLOW DIAGRAM - FIELD CHA!!GE REQUESTS Rev. 3 8-79 b1'$$.12.