ML19343B651

to QA Manual

ML19343B651
Person / Time
Site:	Saint Lucie, Turkey Point, 05000355
Issue date:	09/30/1980
From:	FLORIDA POWER & LIGHT CO.
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ML17340A514	List: ML17340A513 ML19343B651
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NUDOCS 8012290326
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O QUALITY ASSURANCE MANUAL 3 NOIICE OF QUALITY ASSURANCE MANUAL stoaio4 Powen a ucar courm REVISION Page 1 of 3 TO: Holders ef the Florida DATE: Sep tember 30, 1980 Power & Light Company Quality Assurance Manual Frat: Quality Assurance Department Florida Power & Light Company pi NAME. --

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..m COPY NO: L CdC MLEl LEH. .'. . . i. id A SUMECT: OUALITY ASSURANCE MANUAL REVISION CZdC #

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Please insert the following new Topical Quality Assurance Report (TQAR) Table of Contents, revised TQR's and Appendices in your copy of the Quality Assurance Manual and destroy all superseded sections. Also, sign and return the " Notice of Receipt of Quality Assurance Manual Revision".

NOTE: The Table of Contents, Policy Statement, Introduction, TQR's 1.0, 2.0, gs 3.0, 6.0, 9.0, 13.0, 14.0, 15.0, 16.0, and Appendices A, B, C, D and E have been revised. They reflect responsibility and organizational changes

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% as of September 30, 1980. Revisions are indicated by a solid bar in the margia of the affected pages.

TITLE I EV .

NO. 10. TITLE DATE j Table of Contents 3 Table of Contents September 30, 1980 l

Policy Statement 2 Quality Assurance Program Policy September 30, 1980 Introduction 3 Introduction September 30, 1980 l g TQR 1.0 3 Organization September 30, 1980 TQR 2.0 1 Qu.slity Assurance Program September 30, 1980 TQR 3.0 2 Design Control September 30, 1980 TQR 6.0 1 Document Control September 30, 1980 l

l TQR 9.0 1 Control of Special Processes September 30, 1980 i

l TQR 13.0 1 Handling, Storage & Shipping September 30, 1980 m

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QUALITY ASSURANCE MANUAL NOTICE OF QUALITY ASSURANCE MANUAL noaioA POWER & UGMT COMPANY Page 2 of 3 TITLE REV.

TITLE NO. NO. DATE TQR 14.0 1 Inspection, Test & Operating Status September 30, 1980 TQR 15.0 3 Nonconforming Materials, Parts or Components September 30, 1980 g ) TQR 16.0 2 Corrective Action September 30, 1980 v

Appendix A 3 Organization Charts and Figures September 30, 1980 Figure 1-1 3 Organization of Departments Affecting September 30, 1980 Quality Figure 1-2 3 Quality Assurance Organization September 30, 1980 Figure 1-3 3 Project Management and Quality September 30, 1980 Assurance Interface Figure 1-4 2 Environmental and Quality Assurance September 30, 1980 Interface Figure 1-5 2 Advanced Systems & Technology and September 30, 1980 Quality Assurance Interface Figure 1-6 3 Engineering and Quality Assurance September 30, 1980 Interface Figure 1-7 3 Construction and Quality Assurance September 30, 1980 Interface Figure 1-8 2 Power Resources, Power Supply, and September 30, 1980 Quality Assurance Interf ace September 30, 1980 (y/ Figure 1-9 3 Purchasing, Inventory Resources and Quality Assurance Interface Appendix B 1 Qualification and Experience Requirements September 30, 1980 FPL Quality Assurance Personnel j Appendix C 3 Baseline Document Matrix September 30, 1980 l

Appendix D 3 Gray, Green, and Orange Book Matrix September 30, 1980 to QA Procedures

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QUALITY ASSURANCE MANUAL NOTICE OF QUALITY ASSURANCE MANUAL stonica powen a ucsr cowamy REVISION Page 3 of 3 TIILE REV.

NO. NO. TITLE DATE Appendix E 3 List of Corporate QA Procedures (QPs) September 30, 1980 m f Manager of Quality Assurance Detach Here ,

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NOTICE OF RECEIPT OF QUALITY ASSURANCE MANUAL REVISION TO: Manager of Quality Assurance Florida Power & Light Company P. O. Box 529100 Miami, Florida 33152 This acknowledges receipt of the FPL QA Manual revision listed in the transmittal letter dated November 10, 1980. In addition, all superseded procedures have been destroyed.

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TOPICAL QUALITY ASSURANt.E REPORT R w. 3 g

TABLE OF CONTENTS Date September 30,1980 8 LOA 10A Powtp & UGMT Couramy Page of REVISION SUBJECT NUMBER DATE Title Page 0 January 1976 Abstract 0 January 1976 NRC Staff Evaluation Letter Table of Contents 3 September 1980 V

I Policy Statement 2 September 1980 l Introduction 3 September 1980 l Topical Quality Requirements TQR 1.0 Organization 3 September 1980 l TQR 2.0 Quality Assurance Program 1 September 1980 l TQR 3.0 Design Control 2 September 1980 l TQR 4.0 Procurement Document Control 0 January 1976 TQR 5.0 Ir.struction, Pmcedures, and Drawings 0 January 1976 TQR 6.0 Document Control 1 September 1980 TQR 7.0 Control of Purchased Items 0 January 1976 and Services TQR 8.0 Identification and Control of 0 January 1976 Materials. Parts, and Components i TQR 9.0 Control of Special Processes 1 September 1980 l TQR 10.0 Inspection 2 June 1977 TQR 11.0 Test Control 0 January 1976 TQR 12.0 Control of Measuring and Test Equipment 0 June 1976 TQR 13.0 Handling, Storage, and Shipping 1 September 1980 TQR 14.0 Inspection, Test, and Operating Status 1 September 1980 l TQR 15.0 Nonconfor:ning Materials, Parts, 3 September 1980l or Componencr.

C TQR 16.0 Corrective Action 2 September 1980l

TOPICAL QUALITY ASSURANCE REPORT

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R w. 3 TABLE OF CONTENTS Date September 30,1980 couramy

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REVISION SUBJECT NUMBER DATE TQR 17.0 Quality Assurance Records 0 January 1976 TQP ~ (1 Audits 2 June 1977 Appendices A -

Organizations and Figures Figure 1-1: Organization of Departments 3 September 1980 Affecting Quality Figure 1-2: Quality Assurance Organization 3 September 1980 Figure 1-3: Project Management and Quality 3 September 1980 l Assurance Interface Figure 1-4: Environmental and Quality 2 September 1980 l Assurance Interface Figure 1-5: Nuclear Affairs and Quality 2 September 1970 l 1/) Assurance Interface Figure 1-6: Power Plant Engineering, and 3 September 1980 l Quality Assurance Interface Figure 1-7: Purchasing, Construction, and 3 September 1980 Quality Assurance Interface Figure 1-3: Power Resources, Power Supply, 2 September 1980 l and Quality Assurance Interface Figure 1-9: Stores and Quality Assurance 3 September 1980 Interface Figure 1-1J: Operating Plant Site 1 September 1976

'- Man 2gement Organizations B -

Qualification and Experience Requirements 1 September 1980 for QA Personnel C - Baseline Document Matrix 3 September 1980l D - Gray, Green, and Orange Book Matrix to QA 3 September 1980 Procedures (QPs) p E - List of Corporate QA Procedures (QPs) 3 September 1980 F -

Topics to be Addressed in Safety Analysis 0 January 1976 Reports w 4--, -9 + - ,- -w -

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i TOPICAL QUALITY ASSURANCE REPORT )

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nonion powim a ucar coupan QUALITY ASSURANCE PROGRAM PCLICT DateSeptember 30, 1980 Page 1 of 1 Need for Poliev To avoid undue risk to the health and safety of the public and company emplo'ees, it is necessary to design, construct, and operate nuclear power plants with a high degree of functicnal integrity, quality and reliability.

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U Statement of Poliev It is the policy of Florida Power & Light to design, construct and operate nuclear power plants of a qaality level that will meet or exceed government regulations and will merit public sstisfaction by providing electricity in a rollable, efficient, and safe manner.

Resconsibility The President of Florida Power & Light Company is responsible for the execution of

\ the Quality Assurance Program for Florida Power & Light Company nuclear power plants.

The authority for. developing and verifying execution of the Program it delegated to the Director of Quality Assurance through the direction of the Vice President 3

of Advanced Systems & Technology and the Executive Vice President - Operations.

The head of each organization performing qualj ty related activities is responsible for: identifying those activities within his organization which are quality related as defined by the QA Program; establishing and clearly defining the duties and n responsibilities of personnel withir 'rganization who execute those quality i

/ T l (w.// related activities; and planning, selecting, and training personnel to meet the requirements of the QA Program.

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TOPICAL QUALITY ASSURANCE REPORT

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1. N' INTRODUCTICN r)ateSeptember 30,198C

[m) - noaioa powta a ucwr coupasiv Page 1 of The Topical Quality Assurance Report (FPLTQAR l-76A) contains the description of the Florida Power & Light Company (FPL) Quality Assurance Program relative to its nuclear power plants. This report consists of tnree parts: The In:roduction, which delineates the purpose of the Topical QA Report, and sunnarizes its scope and applicability. The second part, Topical Quality Requirements (TQRs), which

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delineate QA program requirements and surnarizes the FPL approach to activities

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Ns) related to materials, parts, components, systegis and services included in the Quality Assurance Program. The third part, Appendices., which provide supporting statements, tabulations, and technical analys'.i. or deviations which are noc, in

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themselves, the subject of the report. f The Topi al QA Report shall be an integral part of the corporate Quality Assurance Manual (FPL-NQA-100) , and shall delineate the generic requirements and responsi-bilities by which FPL implements the corporate QA Program. Revisions and changes to this Report will be made in a':cordance with a Quality Procedure as outlined in (v) TQR 2.0. The remainder of the QA Manual is comprised of Quality Procudum (QPs) which provide the corporate interpretation of the Topical Quality Requireme its and present a common corporate position. The Quality Procedures also serva as the documents which describe how the interfacing of t.as between departments or organ-izations is achieved. The Quality Procedures also cover those technical elements which require a common corporate position for interfaces or resolution of problem areas.

In addition to the Quality Assurance Manual, Quality Instructions (QIs) are devel-O oped as required by each of the implementing plants and departments. Quality Q) Instructions describe the measures to be used to implement the quality requirements of the QA Manual. The Quality Inst)uctions describe actions and responsibilities to be performed within a department or organization and address the requirements of the apprcpriate Topical Quality Requirements, Quality Procedures and ASME requirements.

The FPL Quality Assurance Program follows the guidance of the NRC documents,

" Guidance on QualiT/ Assurance Requirements During Design and Procurement Phase sm of Nuclear Power Plants, "(Gray Book) WASH 1283, dated May 24, 1974; " Guidance on

\d Quality Assurance Requirements During the Operations Phase of Nuclear Power Plants,"

TOPICAL QUALITY ASSURANCE REPORT R ev. 3 N i INTRODUCTION DateSepmber 30.198(

socmon powen a ucar coupac Page of (Orange Book) WASH 1284, dated October 26, 1973; and " Guidance on Quality Assur-ance Requirements During the Construction Phase of Nuclear Power Plants," (Green Book) WASH 1309, dated May 10, 1974. ippendix C provides a tabulation of the documents which the QA Program addressas, n

h The requirements of this Topical QA Report apply to safety related material, parts, components, systems and structures; and to services employed for design, procure-ment, constructicn, operation, maintenance, refueling, repair, and modification.

The safety related systems for each plant are specified in the respective plant Safety Analysis Report.

The FPL Quality Assurance Program fully addresses the requirements of Appendix B to 10 CFR, Part 50. The Topical QA Report shall be applicable to all future nuclear plants and supporting FPL departments, and shall be referenced in the

~N Safety Analysis Report (SAR). The applicability of the Topical Quality Require-

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/ ments to existing FPL nuclear power plants (Turkey Point Units 3 and 4, and St.

Lucie Unit 1) will be addressed specifically for each plant in a letter report from FPL to the Nuclear Regulatory Commission. For future plants, the descrip-tion of activities, requirements, and organizational structures that are unique to a particular plant shall be addressed in the respective SAR document. Appendix F identifies the additional information which will be addressed in the QA section of the SAR documents due to the specific or unique nature of applicability to each fut4re plant.

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TOPICAL QUALITY ASSURANCE REPORT TQR 1.0

/ ORGANIZATION ca September 30, 1980

( stomo coun a ucar cowan Page 1 of 20 1.1 GENERAL REQUIREMENTS The FPL organizational structure shall be defined such that the responsibilities for establishment and implementation of the Quality aurance Program are clearly identified. The authority and duties of individuals and organizatiens performing quality assurance and quality control functions shall be described, and shall V illustrate the organizational independence and authority necessary to identify problems; to initiate, recommend, or provide solutions; and to verify implementation of solutions. In addition, the description shall illustrate that persons or groups responsible for verifying the correct performance of an activity are independent of the person or groups responsible for performing the activity.

1.2 IMPLEMENTATION The President of Florida Power & Light is ultimately responsible for the execution of the Quality Assurance Program for Florida Power & Light Company (FPL) nuclear power plants. The authority for execution of the program is delegated to the Director of Qu dity Assurance through the direction of the Vice President of Advanced Systems & Technology and the Executive Vice President. The reporting relationship of each department involved with the Quality Assurance Program is shown in Figure 1-1.

1 The head of each department or organization performing quality related activities l

l is responsible for: a) identifying those activities within his organization which are quality relater' as defined by the QA Program; b) establishing and clearly defining the duties and responsibilities of personnel within his organization who execute those quality related activities; and c) planning, selecting, and training personnel to meet the requirements of the QA Program. The responsibility, authority, and organizational relationship for performing qua18ty related activities within each organization shall be established and delineated in organizational charts and written job or functional descriptions.

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TQR 1n TOPICAL QUALITY ASSURANCE REPORT ORGANIZATION 0, 19M Da Sentenber

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A QA/QC coordinator shall be designated by the head of each department or organization, except in the Company Nuclear Review Board and the Quality Assurance Commmittee which are review and policy forming bodies (of which the s l Director of QA is a member). The_QA/QC coordinator is the prime interface for coordination of quality related matters within his department, with the QA Department, and with other departments. The interface of each Department with Quality Assurance is illustrated in the Figures of Appendix A.

The organization chart, Figure 1-1, illustrates the lines of authority and areas of responsibility for eacn of the major organizations that are involved in quality related activities. The Project Management organization shown in this figure is applicable only during design, constructrion, and modification of power plants (determined by management on a case-by-case basis) as described in Section i

s 1.2.3. Below are listed the departments and organizations that have Quality Assurance respe -sibilities. Spacific organizational responsibilites for implementation of the Quality Assurance Program are described in the corresponding section numbers.

1.2.1 Quality Assurance Committee 1.2.9 Power Resources 1.Z.2 Quality Assurance 1.2.10 Power Supply 1.2.3 Project Management 1.2.11 Inventory Resources 1.2.4 Corporate Contracts 1.2.12 Company Nuclear

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) l1.2.5 Advanced Systems & Technology Review Board 1.2.6 Power Plant Engineering 1.2.13 General Engineering 1.2.7 Purchasing 1.2.14 Fuel Resources 1.2.8 Corstruction 1.2.15 Nuclear Analysis t

1.2.1 Quality Assurance Committee The Quality Assurance Committee, chaired by the Executive Vice President, is j comprised of executive level management, as shown in Figure 1-1 and shall be l s

%, responsible for reviewing and evaluating QA Program policies and activities.

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TOPICAL QUALITY ASSURANCE REPORT TQR 1.0

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ORGAliiIZATION DateSeptember 30, 198C stoaica eowna a uc r cowam Page 3 of 20 1.2.1 (Cont'd)  !

Policy changes shall be initiated when Committee findings indicate the teessity. Quality Assurance Program status reports shall be periodically prepared by the QA Department and routed to the members of the QA O Committee for their review.

In addition, QA Commmittee meetings shall be held by the Executive Vice President to keep members appraised of conditions including significant problems that require management attention. The Quality Assurance Committee shall be the final authority for resolution of contested quality policies, differences of opinion, and stop-work or other corrective action requests when agreement cannot be reached between QA or QC and other departments, at lower levels.

yJ ) 1.2.2 Quality Assurance Department The Quality Assurance Department shall be responsible for administering the FPL Quality Assurance Program. This includes developing and verifying implementation of corporate policies, plans, requirements, and procedures. The QA Department retains responsibility for delegated portions of the QA Program by per'orming initial evaluation and subsequent pe; iodic audits of the contractors' QA Program. The Program responsibility further extends to the performance of audits within the Company to assure management that the

] established requirements and procedures are being implemented, and that the

_ ,/ Program complies with regulatory requirements. Periodic (approximately annual) audits of the QA department shall be performed by a team independent of the QA Department which is selected and approved by the Chairman of the Quality Assurance Committee. The results of this audit are presented to the QA Committee and sent to the Company Nuclear Review Board for review.

The organizational freede.n of the QA Department is accomplished through the j

corporate structure, illustrated in Figure 1-1, which provides independence j from those departments responsible for design, procurement, engineering,

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TOPICAL QUALITY ASSURANCE REPORT TQR 1A 7 t::. R ev. 3 un 5 ORG N ADON DateSeptember 30.198C stoanoa cowaa 6 uci.t couran Page 4 of 20 1.2.2 (Cont'd) construction, and operation. With Quality Assurance as the sole function of l this organizationally independent department, the Director of QA and his staff, both on-site and off-site, are completely free from the cost and scheduling pressures of procurement, design, construction, and operation. The QA V Department has the freedom and authority to: a) identify quality problems; b) initiate, recommend or provide corrective action; ci rerify implementation of the corrective action; and d) recommend the stoppage of work or operations adverse to quality when necessary.

The Director of Quality Assurance reports to the Vice President of Advanced Systems & Technology. This level of reporting and his membership on the Quality Assurance Committee and the Company Nuclear Review Board assure

( that he and his staff have direct access to the levels of management necessary b to assure effective implementation of the QA Program. The Director of QA

directs and administers the Quality Assurance Program, including developing and verifying implementation of policies, plans, requirements, procedures, and audits which assure compliance with regulatory requirements including 10CFRSO, Appendix B. He shall also be responsible for the technical direction and the administrative control (e.g., performance appraisal, salary review, hire / fire, position assignment) of all members of the Quality Assurance l Department. The qualification requirements for the positions of Director of QA and Assistant Manager of QA are described in Appendix B. Reporting

() l directly to the Director of Quality Assurance are:

l l o Assistant Manager of QA - Engineering o Assistant Manager of QA - Procurement l

o Assistant Manager of QA - Construction o Assistant Manager of QA - Operations l

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TOPICAL QUALITY ASSURANCE REPORT TQR 1A R ev. 3 A E ORGANIZATION (v) nonio. ec. a a uc== counaw DateSeptenber 30.198C Page 5 of 20 1.2.2 (Cont'd) l Each of these four Assistant Managere shall have s.pecific functions and responsibilities which are defined in the QA Department Organization Manual (FPL-NQA-101). The duties, responsibilites, and authorities of each Assistant A

Manager and his group are described in the sections which follow. The (U J organization of the Quality Assurance Department is shown in Figure 1-2.

a. Quality Assurance Engineering Group o Develop and maintain the QA Manual, QA Department Quality Instructions, QA Department Organization Manual, and prepare and revise the Topical Quality Assurance Report and the QA portion of the SAR Documents; o Assint other departments in the development of Quality Instructions by review and comment and through interpretation of NRC and v corporate Quality Assurance requirements; o Develop anci implement a Quality Assurance indoctrination program for FPL personnel, and a trair.ic.; ;-ogram for the Quality Assurance Department; o Prepare reports on Quality Assurance Program activities for presentation to the Quality Assurance Committee by the Director of Quality Assurance; i .

o Maintain a file system for documentation of quality assura...

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) activities performed by the QA Department;

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V o Review regulatory guides, codes, and standards for impact on the

! Quality Assurance program and recommend appropriate program 1 changes; l

l o Plan and implement a comprehensive system of periodic audits of Power Plant Engineering, General Engineering, Environmental l

Engineering, Nuclear Analysis, Project Management, System Protection, and the Company Nuclear Review Board, i /n\ o Initiate, recommend or provide solutions and verify implementaiton of

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V solutions w quality problems identified; l

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TQR 1.0 TOPICAL QUALITY ASSURANCE REPORT QbSi 3 R ev.

ORGANIZATION DateSeptember 30.198C

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x' y 8Lom:0A Powtm & UGnf COMPANY Page of 1.2.2 (Cont'd) o Develop and implement a program for reviewing design-related documents to assure inclusion of appropriate quality requirements; o Develop and implement a progam for the analysis of operating defect and failure data to identify areas which require further considerations (O) or analysis in operating plants and in design for new construction; o Review documents submitted to the CNRB as requested by the QA Department CNRB member.

In addition to the above, the Quality Assurance Engineering Group provides the interface with Project General Managers and coordinates the Quality Assurance Department's support tc the project.

[mj lb. Quality Assurance Procurement Group

\'J o Assist in the development and implementation of policies, plans, requirements, and procedures for the requisition and purchase of materials, equipment and services related to nuclear power plants and to the acceptance and storage of equipment and material; o Peform appropriate surveillance of hardware during manufacture; o Plan and implement a program for auditing of supplier QA/QC l

l programs;

o Responsible for designating Quality Engineers authorized to review and approve initial FPL purchase requisitions, contracts and changes to these documents, for all nuclear safety related equipment and material, to assure that the necessary quality requirements are l imposed.

o Assist other FPL departments in the identification of quality problems associated with procurement and storage; initiate, recommend, or provide solutions; and verify implementation of solutions; o Review, approve, and periodically audit the execution of FPL fD contractor quality assurance programs;

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TOPICAL QUALITY ASSURANCE REPORT TQR 1.0 N . ~' R ev. 3 CN " '

ORGANIZATION DateSeptember 30.198C

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(v f stoaica ecwsm & ucar cousa=y 7 20 Page of 1.2.2 (Cont'd) o Perform periodic audits of the Purchasing, Fuel Resources and Corporate Contracts Departments; o Maintain a file system for documentation of quality assurance

] activities peformed by the QA Procurement group.

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,1 The responsibility of this group, in terms of phases of procurement, begins with the preparation of the procurement document, extends through bid evaluation, vendor selection, fabrication, shipment; and ends upon receipt of shipment at the FPL construciton site, operating plant, or warehouse. QA Procurement group assures that the contractor's organizations peforming QA functions have sufficient authority and organizational freedom to implement effective QA programs.

3 v) c. Quality Assurance Construction Group o Assist in the development and implementation of policies, plans, requirements, and procedures for portions of the quality assurance program related to construciton of nuclear power plants; o Ensure and verify implementation of the Quality Assurance Program during the construction phase through audits of FPL and contractor organizations; o Notify the NRC of site reportable incidents under Part 50.55(e) in accordance with the approved procedure;

{ o Maintain a log of all con truction open items identified by the NRC;

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other federal, local and state agencies; and the FPL QA Construction group; and inform appropriate FPL management when there is an indication that a commitment v.ill not be met on time; o Recommend the stoppage of work or operations adverse to quality in accordance with the appropriate Quality Procedure; o Maintain a file system at the plant site for plant construction records, and fx documentation of quality assurance activities performed by

'g the QA Construction group;

TOPICAL QUALITY ASSURANCE REPORT TQR 1.0 a

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/G ORGANIZATION DateSeptember 30, 198C

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20 1.2.2 (Cont'd) o Review construction and construction QC procedures with respect to the l FPL QA Program, SAR Document commitments, and aplicable codes, standards and regulations; (for procedure review requirements see TQR 5.0) d o Review and approve site generated FPL procurement requests and purchase orders and changes thereto, assuring that quality requirements l

have been specified where applicable.

The scope of responsibility of this group is confined to the construciton activities and begins with site exploration activities and extends until pre-operational and start-up testing. This group may also be called upon to audit plant changes and modifications *f an operating plant. The group shall be

. responsible for construction Quality Assurance activities, but the work of establishing and executing the Quality Assurance Program as applied to

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constructica or any part thereof, may be delegated to other organizations. The interface with the QA Procarement Group ends with the receipt of a shipment of nuclear safety related equipment at the construciton site. The Quality Assurance program for the shipment is then within the purview of the QA l Construction Group. The interface with the QA Operations Group is at system turnover from Ccnstruction to Power Resources.

g l d. Quality Assurance Operations Group i

v/ o Assist in the development and implementation of policies, plans, requirements, and procedures for portions of the quality assurance program related to operation of nuclear power plants; o Perform audits at nuclear power piants to identify quality problems in the area of plant operation, system turnover, modification, and maintenance including such areas as refueling, inservice inspection and testing, procurement of spare / replacement parts, material q stcrage, health physics, chemistry, and plant security; I 1 v

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TOPICAL QUALITY ASSURANCE REPORT TQR 1.n ORGANIZATION Da September 30, 198(

noaio eowin a ucar cow.c Page 9 of 20 1.2.2 (Cont'd) o Recommend stoppage of work or operations adverse to quality in accordance with the appropriate Quality Procedures; o Review and comment on Quality Instructions or equivalent quality

( related administrative procedures prior to issue, with respect to the

( requirements of the FPL Quality Assurance Program; the Final Safety Analysis Report and the plant Technical Specifications; o Assure that the status is tracked for all operating plant open items identified by the NRC; other federal, local and state agencies; and the FPL QA Operations group, and inform appropriate management when there is an indication that a commitment will not be met on time; o Maintain a file system for documentation of quality assurance l activities performed by the Operations group.

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LJ The activities of this group shall begin when the plant manager is designated and the development of procedures for preoperational testing l is started. The Operations group shall provide the assurance that an orderly and effective turnover of data packages and equipment by contractors to FPL is accomplished.

l During the operation phase, the QA Operations group responsibility begins y at the point of acceptance of a shipment of replacement / spare parts at kv, l the operating plant warehouse. The Operations group interfaces with the Plant Manager and his staff on-site for assisting in the resolution of I

quality related problems. The interface with the QA Construction group l

is at system turnover from Construction to Power Resources.

1.2.3 Project Management Department The Project Management Department, through the Project General Manager, exercises management control of assigned major projects. This management G control begins when a Project is assigned to the Project Management

TOPICAL QUALITY ASSURANCc REPORT TQR 1.0 R w. 3 g

( ORGANIZATION DateSept ember 30. 1980

\]} ncaica powna a ucar cou .e Page 10 og M l

1.2.3 (Cont'd)

Department and continues until the facility is accepted for operatiot, or the project is complete. The Project Management Department organization is shown in Figure 1-1.

O j The Director of Projects, reporting to the Vice President-Engineering, Project Management and Construciton has overall responsibility for the activities of the Project Management Department. A Project General Manager, reporting to the Director of Projects, is responsible for completing the assigned project in compliance with technical and other project specifications, and for the application of the provisions of the Quality Assurance Manual during the proj ect. The Project General Manager is responsible for obtaining corrective action from contractor managament when corrective action cannot be obtained s at the plant site management level, and when necessary, can exercise his authority to stop work on construction activities adverse to quality.

s Project Team Members are appointed by their home department heads as the departmental representative on the respective project, when reqr ited by the l Project General Manager. Team Members report functionally to the Project General Manager, but continite to receive administrative support and technical direction form their home department. Team members are responsible to the l

Project General Manager for home department support to the Project.

l l O The QA Department interface with Project Management is shown in Fig 2re 1-( )

3. The QA Department has a representative assigned to each major project, l who repcrts functionally and administratively to the Directer of Quality Assurance.

1.2.4 Corporate Contracts Department The Corporate Contracts Department is responsible for assuring that technical s and quality requirements are incorporated in company contracts as apropriate.

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j Details of the activities of the department in fulfilling this responsibility shall

TOPICAL QUALITY ASSURANCE REPORT TQR- L0 s

ORGANIZATION Da September 30, 198C

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1.2.4 (Cont'd) be delineated in the appropriate quality procedures. The Ccrporate Contracts Organization is shown in figure i-1.

f1.2.S Advanced Systems and Technology

'L l Advanced Systems and Technology is responsible fce providing management with overall guidance regarding present, planned, and jotential involvement of the Company in nuclear power generation, and for activities including the responsibility for NRC nuclear plant licensing, quality assurance, and environmental activities.

Figure 1-1 illustrates the Advanced Systems & Technology organi::ation which is comprised of three departments: Licensing and Environmental Planning,

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v' Research and Development and Quality Assurance, under the direction of the Vice President of Advanced Systems & Technology. The QA Department is described in Section 1.2.2, and the interface with the other departments within I Advanced Systems & Technology is shown in Figure 1-5.

I l Licensing and Environmental Planning is responsible for obtaining the major Federal, State, and local environmental permits required for FPL facilities and operations. For new nuclear power plants, Environmental Engineering prepares the Environmental Report, which is then coordinated within the Advanced G l Systerns & Technology Department as a part of the construction permit application to the NRC. Prior to and during operation of the nuclear power plant, Environmental Engineering maintains responsibility fer overall coordination of environmental monitoring programs. Some of the activities include: a) drafting of Environmental Technical Specifications; b) review of proposed changes to Environmental Technical Specificaiions and investigation of violations; and c) review of proposed plant changes and modifications for effect on the environmental impact evaluation when requested.

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TOPICAL QUALITY ASSURANCE REPORT l TQR 1n i ORGANIZATION Septe:nber 30,198(

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The Manager of Environmental Engineering and the Manager of Environmental Affairs reports to the Director of Licensing and Environmental Planning as l illustrated in Figure 1-1. The Director of Licensing and Environmental Planning has overall responsibility for implementation of the Environmental

\ Technical Specifications in nuclear power plants. The interface relationship with Quality Assurance is shown in Figure 1-4.

l The Company Environmental Review Group (CERG) advises the Director of Licensing and Environmental Planning and ti e Chairman of the CNRB on all matters related to environmental quality. The CERG provides a review of proposed changes to Environmental Technical Specifications, and has priue responsibility for investigation of violations, evaluation of corrective actions, p and reporting and making recommendations to the Company Nuclear Re riew

( Board on matters related to environmental quality.

1.2.6 Power Plant Engineering The Power Plant Engineering Department is responsible for power plant design throughout all phases of plant life. This responsibility extends from the initial design review functions applied to new construction as well as plant design changes and modifications during the operations phase. Activities of this department include: a) design reviews of selected contractor detail designs, engineering drawings, etc., b) review of selected nonconformance resolutions, w/ c) disposition of plant design change and modification requests, d) establishment and implementation of an FPL desiga control system, including review and approval of the system employed by contractors, and e) for construction, review of new project specifications, bids, and purchase requisitions developed by the A-E's home office, and specifications developed by NSSS vendors to verify that technical requirements for special processes and required special process documentation are specified. The Chief Engineer of

'N, Power Plant Engineering reports to the Vice President Engineering, Project nj Management and Construction as shown in Figure 1-1. The Quality Assurance interface with this department is illustrated in Figure 1-6.

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TOPICAL QUALITY ASSURANCE REPORT TQR LO 3

y R ev.

1. ORGANIZATION

. DateSeptember 30,198(

q ,) nomo4 cowin a uc r cown.,

Page 13 of 20 1.2.7 Purchasing The Purchasing Department is responsible for the pu-chase of materials and field procured services by or for FPL for nuclear power plants. Materials, services, and items for safety related application shall be purchased only from approved suppliers. During the construction of a new plant where a contractor (e.g., A/E, NSSS, et c.) initiates the purchase order, the Purchasing Department's responsibility is limited to the review and approval of purchase orders submitted by the contractor. The department performs activities such as: a) maintaining traceability of purchasing records from FPL initiation of requisitions through payment of the purchase order, b) a non-technical review of requisitions to verify that a review for quality requirements has been accomplished, and c) coordination of the review of the approved supplier's list to assure continued validity. The Director of Purchasing and Inventory

(

(/ Resources reports to the Vice President - Corporate Services as shown in Jigure 1-1. Interface with the QA Department is shown in Figure 1-9.

1.2.8 Construction The Plant Construction Department is responsible for providing quality control support activities required to assure that construction work and activities meet the requirements of plans, specifications, codes, and corporate standards. This responsibility extends from inspection of material upon receipt on-site to acceptance of the installed items by Power Resources, and includes the (dr) verification of conformance of an item or activity initiated during this period to quality requirements (e.g., records review, inspection NDE). The Superintendent - Construction Quality Control, Project Quality Control Supervisor, and Site Construction Manager have the authority to stop work or operations adverse to quality if the need arises. The organizational structure of the Construction Department is illustrated in Figure 1-1.

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TOPICAL QUALITY ASSURANCE REPORT TQR 1A ORGANIZATION Da Septembe 30, 198C

.tc. oa rossa s va~s coese Page 14 og 0 1.2.8 (Cont'd)

As a Project Team Member during the plant construction phase, the Site Construction Manager functions as the on-site representative of the Project General Manager and is responsible for Plant Construction support activities.

Implernentation of Construction QC activities is the only responsibility of the Project Quality Control Supervisor, who reports functionally to the Site Construction Manager and administratively to the Superintendent -

Construction Quality Control. The freedorn and independance of the on-site QC organization from the pressures of construction costs and scheduling, is derived from the project QC Supervisor's administrative reporting relationship to the Superintendent - Construction Quality Control as shown in Figure 1-7.

The Superintendent - Construction Quality Control is responsible for directing

['] and administering the Construction Quality Control Program for all plant V construction activities. This includes the development and irnplementation of policies, plans, codes, requirements, and procedures. He is also responsible for the technical direction and administrative control (e.g., salary review, hire / fire, position assignment) of all personnel in the Construction Quality Control organization.

Reporting to the Superintendent - Construction Quality Control is a program staff of Quality Control Coordinators and the on-site quality control I

/7 organization. (The structure of the on-site QC organization shall be defined in i

V the Quality Assurance Section of the respective plant Safety Analysis Report.)

The Quality Control Coordinators provide administrative support and assistance to the Superintendent - Constraction Quality Control.

Each new nuclear project is assigned a site Project Quality Control Supervisor who reports administratively to the Superintendent - Construction Quality Control. The Project QC Supervisor has a functional reporting relationship to the Site . Construction Manager for the purpose of coordinating inspection y activities with construction work, corrective action, and scheduling direction.

TOPICAL QUALITY ASSURANCE REPORT TQR 1.0 3 R w. 3

/m 4

' ' ORGANIZATION DateSep_tembqt 30. 198C

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\ etchlOA POWl4 & UCMT CQMPW Page Ib d 20 1.2.8 (Cont'd)

The functional / administrative reporting role of the Project Quality Control Supervisor provides the necessary independence of the site Quality Control organi:ation, and yet maximize communications between the Construction Q staff and the QC staff. To clarify this dual reporting role at the site, the k following definitions are given:

Administrative reporting: The Superintendent - Construction Quality Control shall have responsibility for: a) Final authority for hiring, termination, promotion, and salary action; b) Program control (i.e.,

procedural and technical direction); c) Approval of all procedures instructions and/or checklists used by Construction Quality Control personnel, including requirements (frequency, and revision to these); d) p Final approval of dispositions of deviation from program, procedure,

( specification, or other requirements; e) Review all required reports from Project Quality Control Supervisor concerning quality conditions or progress.

Functional reporting: The Site Construction Manager shall have responsibility for: a) Day-to-day c.Lordination of inspection activities with construction work; b) Corrective action path to contractors for deficient conditions identified; c) Scheduling direction (Quality Control perscnnel may not be assigned tasks in nonquality related areas.); d)

( Request changes in personnel levels.

The Project QC Supervisor is responsible for first level verification of conformance of construciton activities to Quality Assurance requirements, codes, plans, specifications, and local, state, and Federal regulations. He directs on-site implementation of the Construction Quality Control Program which includes superviser of daily coordination of inspection activities, scheduling of QC manpower levels, and reviewing inspection results to insure effective inspection. To fulfill this function the Project Quality Control Supervisor performs the following:

TOPICAL QUALITY ASSURANCE REPORT TQR 10 ORGANIZATION Da esegtember 30. 1980

< . .> stonion powen 6 ur .r cowea=v Page 16 of 20 1.2.8 Cont'd) o Planning, supervising, and assignment of all site Quality Control personnel.

o Provides on-site management control of inspection contractors.

o Provides site resolution of quality problems.

o Review of construction and erection procedures for proper inspection U requirements and hold points.

o Prepares reports which are sent directly to the Superintendent -

Construction Quality Control.

o Reports any situations which he feels may compromise his ability to -fulfill his quality responsibilities directly to the Superintendent - Construction Quality Control.

The overall responsibility for Plant Changes and Modifications to operating p plants is defined in each plant's Technical Specifications. However, frequently the work of installation and administration of Plant Changes and Modifications is assigned to FPL Construction. In these instances, the reporting relationships I between the Site Construction Manager / Supervisor and Project Management are similar to that for new projects. Activities affecting quality may be performed by FPL or contracted. Should any of these functions be contracted, the contractor may perform the activities under his own Quality Assurance Program, which must have prior approval of FPL Quality Assurance, or the contractor may directly adopt the requirements of the FPL Quality Assurance p M anual. If the contractor implements the Quality Control functon directly to

) the FPL QA Manual requirements, the contractor's Quality Control Supervisor shall have the authority and freedom to administer the Quality Control program.

l1.2.9 Power Resources Power Resources' responsibility for the plant begins with the department's acceptance of a system or portion thereof from FPL Construction.

N Throughout the remainder of plant life, Power Resources maintains control

(. -

l of and responsibility fer the preoperational and startup testing, operation,

TOPICAL QUALITY ASSURANCE REPORT TQR 1.0 ORGANIZATION Da September 30, 198C nomo ,owie a uc r cow.c Page 17 of 20 1.2.9 Power Resources (Cont'd) tuaintenance, refueling, and rnodification of the plant in accordance with written and approved procedures.

G The organizational structure of Power Resources is shown in Figure 1-1.

\

The Vice President of Power Resources has overall responsibility for Power Resources' activities.

The plant manager *, through the Manager of Power Resources - Nuclear, is responsible for the on-site activities of the Power Resources Department.

The plant manager is additionally responsible for the establishment and implementation cf plant QC policy which implements the quality control aspects of the Quality Assurance Program.

m v

) Reporting directly to the plant manager is the plant Quality Control Supervisor who has the authority and freedom to administer the plant Quality Control program, and when necessary, for stopping activities adverse to quality. The QC Supervisor, his staff, and personnel performing QC inspection functions are required to be independent of groups or persons performing activities that they may be required to verify or inspect. QC effort includes preparation and review of plant procedures and quality related instructions, the inspection, monitoring, surveillance, and review of N plant activities to verify compliance with the provisions of the facility

, operating license and the Quality Assurance Manual. The QC Supervisor shall take corrective action for deficiencies identified, where applicable and shall follow up on corrective action taken by other organizations until close out. ,

• See Appendix A, Figure 1-10 for explanation.

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TOPICAL QUALITY ASSURANCE REPORT TQR LO gM4 ORGANIZATION 04 Septembe 30, 198C h nonio..o.inatc rcow.c Page 18 of 20 1.2.9 (Cont'd)

The Plant Nuclear Safety Committee (PNSC) or Facility Review Group (FRG) is comprised of key plant management and staff personnel as described in the plant Technical Specifications. The PNSC/FRG serves the

,/~ plant manager in a technical advisory capacity for the review of all safety V] related procedures and activities that impact on plant safety and the facility operating license.

1.2.10 Power Supply Within the Power Supply Department, only equipment and services provided by the System Protection group are subject to the requirements of the Quality Assurance Pro gram. Figure 1-1 illustrates the reporting relationship.

A System Protection is responsible for the requisitioning, post receipt test, calibration, and maintenance of certain high voltage electrical protective relays for safety related systems of the nuclear plant. During construction, this group is involved in the review of relay system drawings and specifications. Activities of System Protection include final wiring connection checks, and preoperational check-out and test of all system protection devices. The interface of Power Resources and Power Supply with Qualit7 Assurance is shown in Figure 1-8.

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Q 1.2.11 Inventory Reso arces The Inventory Resources Department is responsible for the receipt, handling, storage, shipping, and issue of items re eived at the plant site for control by Inventory Resources. This responsibility encompasses spare and replacement parts and components for plant equipment through all phases of plant life.

During operations, Inventory Resources also performs additional quality related activities such as handling and segregation for nonconforming items

/ \ received for stores control. The Inventory Resources Department and/or Nv ]

I TQR 1.0 TOPICAL QUALITY ASSURANCE REPORT ORGANIZATION N 8L0miOA Powim 6 UCuf coupasar Page of 1.2.11 (Cont'd)

Architect-Engineer, Constructor, or other contractors may perform these functions for quality controlled items intended for installation during initial construction activities. The Director of Purchasing and Inventory Resources A reports to the Vice President - Corporate Services as showr in Figure 1-1.

The interface with the QA Department is shown in Figure 1-9.

1.2.12 Company Nuclear Review Board The Company Nuclear Review Board (CNRB) reviews or directs the performance of reviews of activities concerning the technical aspects of the operating nuclear power plant insofar as they impact on plant safety; the environment; the health and safety of the public; and laws, regulations, and licensing commitments. In addition, audits of these areas are performed under the cognizance of the CNRB. Where necessary, the Board may use s consulting services to perform required reviews. Membership and the management level to which the CNRB reports is illustrated in Figure 1-1.

Involvement of the CNRB with a particular plant begins when the operating license is issued for that plant, and is limited to those systems which FPL Power Resources has accepted from the Construciton Department. Subjects within the purview of the Board are listed in the appropriate plant Technical Specifications. The CNRB has the authority to carry out its responsibilites by 3 way of written action letters, verbal direction, or minutes of meetings.

1.2.13 General Engineering General Engineering is responsible for the retention of drawings generated by both Power Plant Engineering and General Engineering, and provides drafting and related services for all egneering projects. This department is responsible for the establishment and implernentation of a control program for drawings. The Chief Engineer - General Engineering reports to the Vice 1

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President - Engineering, Project Managernent, and Construction as shown in l

U Figure 1-1.

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TOPICAL QUALITY ASSURANCE REPORT TQR 1.0 M'N 3

- ORGANIZATION a Septenber 30, 198C k{ h . no. ion no a. s ucar cow.w Page 20 o, 20 tt t

i 1.2.14 Fuel Resources The Fuel Rescurces Department has the responsibility for procuring and maintaining adequate nuclear fuel supplies and related services. The O}

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performance of this task includes:

1. forecasting FPL's nuclear fuel requirements and the availability and price of nuclear fuel;

2. determining sources of supply and evaluating alternatives;

3. making commercial arrangements for acquisition, processing and delivery of nuclear fuel and related services for the nuclear fuel cycle;

4. administering and managing contracts for nuclear fuel and related services to assure that contractual obligations are met.

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)

V Fuel Resources coordinates inputs from other FPL departments and incorporates themn into contracts; conducts contract negotiations with vendors, and serves as FPL liaison in all matters of nuclear fuel and fuel related contracts. The department reports to the Vice President of Fuel Resources and Corporate Development as shown in Figure 1-1.

1.2.15 Nuclear Analysis -

The Nuclear Analysis Department is responsible for: a) providing technical support to the Fuel Resources Department for preparing the procurement

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specifications for components of the nuclear fuel cycle, b) providing technical support to the QA Department for auditing of nuclear fuel and core components suppliers, c) reviewing core related changes to the Safety Analysis Report and Technical Specifications for completeness of technical criteria, d) providing technical support for operating nuclear power plants, e) performing safety and fuel management analyses of nuclear cores to support j plant licensing, and f) review of fuel and nuclear physics designs. The Nuclear Analysis organization is shown in Figure 1-1.

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i TOPICAL QUALITY ASSURANCE REPORT TQR 2.0 p QUALITY ASSURANCE PROGRAM September 30. 198C noaion *owna 6 ucat co**

1 g 7 2.1 GENERAL REQUIREMENTS Florida Power & Light Company has established a Quality Assurance Program which complies with the criteria of 10 CFR 50, Appendix B, and follows the O guidance referenced in Appendix C of this report. The Topical Quality Requirements and attached Policy Statement, together with the Quality Procedures and Quality Instructions document the Program and the FPL policy with regard to Quality Assurance. This Program shall be instituted for each plant site in a schedule consistent with accomplishing the required activity and shall be carried out throughout the life of FPL nuclear plants. This shall include quality related activities initiated prior to submittal of the PSAR, such as design, procurement, preparation of the PSAR, and safety related site preparation activities.

O (a) The requirements of the FPL Quality Assurance Program shall only apply to nuclear safety related structures, systems, and components as identified in the Safety Analysis Report for each nuclear unit. Additionally, the requirements of the FPL Quality Assurance Program shall apply to all FPL, contractor, or consultant organizations performing activities affecting the quality of safety related structures, systems, and components of FPL nuclear power plants.

Documented Procedures shall require and define indoctrir tion and training of

-3 personnel performing activities af.ecting quality as necessary to assure that I \

suitable proficiency is achieved and maintained.

(O)

Periodic program reviews of the status and adequacy of the FPL Quality Assurance Program shall be accomplished by the independent audit team described in Section 1.2.2 and by QA Department audits. Management of organizations outside Florida Power & Light Company participating in the Program shall be required to regularly review the status and adequacy of that part of the FPL Quality Assurance Program which they are executing. The FPL Quality Assurance Department shall review and concur in the QA Program of contractors.

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TQR  ?,.0 TOPICAL QUALITY ASSURANCE REPORT b Rw. I

\ QUALITY ASSURANCE PROGRAM Date Septenber 30. 1980

( nomoa rowna s uc r coueu.v Page I

of 7 2.2 IMPLEMENTATION 2.2.1 Coals and Objectives As stated in the Policy Statement of the President of Florida Power & Light N Company, the goal of the FPL Quality Assurance Program is to maintain g

) quality levels in an effective and efficient manner, and to assure the high degree of functional integrity and reliability of nuclear safety related structures, systems, and components. To meet this goal, the following objectives of the FPL Quality Assurance Program have been defined:

a. Define through documented procedures and instructions the quality activities that apply to the design, fabrication, procurement, construction, testing, operation, refueling, maintenance, repair and modification of nuclear power plants.

I b. Establish, assign, and document the responsibilities for these activities affecting quality of safety related structures, systems, and components.

c. Establish ccnfidence that the design, f abricati n, construction, and operation of nuclear power generation facilitier, are performed in a manner consistent with FPL policies by assuring quality related activities are performed by responsible personnel.

. d. Appraise management of unresolved problems and trends which could have a significant affect on nuclear power plant safety; and

e. Prevent schedule delays and high cost due to poor quality.

U 2.2.2 Program Documentation The Topical Quality Assurance Report which defines the policy, goals, and objectives regarding the Quality Assurance Program ahall be contained in the FPL Quality Assurance Manual, and used as guidance for the development of corporate level Quality Procedures which are also contained in the Quality Assuranca Manual. Revisions to the Topical Quality Assurance Report will be made as needed to reflect current FPL program requirements and descriptions of activities. These revisions shall be made in accordance with a Quality

TOPICAL QUALITY ASSURANCE REPORT TQR 2.0 tMir4 R ev.

] /

QUALITY ASSURANCE PROGRAM DateSep.qstpbetr 30. 1980 nonion ,owin a ucar co w w 3 7 Page of 2.2.2 Program Documentation (cont'd)

Procedure. If a program revision reflects a deviation from the baseline documents contained in Appendix C, an amendment shall be submitted to NRC 30 calendar days prior to implementation. Thirty (30) calendar days after

/'m N submittal, the NRC shall be notified of FPL's intent to begin implementation

\s of program changes identified in the amendment. In all other cases, amendments to the Topical QA Report will be submitted to NRC to reflect implemented program revisions on an annual or more frequent basis.

Quality Procedures shall be written by the department with major responsibilities for an activity or by the Quality Assurance Department.

These procedures shall be reviewed by all the departments with responsibility for some portion of that procedure, and shall be approved by the major implementing departments with co-approval by the Director of Quality

{} I Assurance. A listing of corporate level Quality Procedures is contained in Appendix E. As the QA program develops and responds to new or revised requirements and guidance, new procedures may be adopted. This listing shall be reviewed to reflect these changes on an annual basis.

Each Quality Procedure shall be written to address criteria contained in the j Topical Quality Requirements and to further define the FPL policies, plans, and program where action is required by more than one department.

l l ) Each department head shall have the responsibility for ' implementation of the Quality Assurance Program which includes Procedure requirements applicable to his department. In addition, he shall be responsible for the preparation, aproval, and distribution of Quality Instructions, operating procedures, testing i

procedures, or other instructions where further guidance is necessary for implementation of the QA Program within his department. Quality Instructions shall be reviewed by the Quality Assurance Department.

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TOPICAL QUALITY ASSURANCE REPORT TQR 2.0 x QUALITY ASSURANCE PROGRAM Dateseprgmh , 3n ionc nomo. ,owin a ucar cou,u,,

4 7 Page of 2.2.3 Structures, Systems, c i C-ruponents The requirements of the FPL Quality Assurance Program shall apply to

. nuclear u'ety related structures, systems,and components, as defined in the

~

SAR. Safety related structures, systems, and components are listed as those necessary to assure the integrity of the reactor coolant boundary, the capability to shut down the reactor and maintain it in .t safe shut down condition, or the capability to prevent or mitigate the consequences of accidents which could result in off-site exposures comparable to the guideline exposures of 10 CFR 100.

Control over activities affecting the quality of safety related tructures, systems, and components shall be to the extent consistent s ith their importance to safety. Such control shall include use of appropriate equipment, establishment of suiiable environmental conditions, and assurance that all prerequisites for a given activity have been satisfied. The Drogram shall provide for controls over special processes and skills necessary to attain the required quality, and the need for verification of quality by inspection and test.

Advanced planning is required, for the control of management and technical interfaces between FPL and contractors, during the phasecut of design and 1

O \ constructicn and during preoper=Honal testing and plant turnover. This is j

achieved through periodic mee:ings of concerned organizations and the i

development of procedure which define responsibilities and interfaces, and control the testing and turnover of plant systems to FPL.

2.2.4 Participating Organizations l The FPL organizations with responsibilities for activities affecting quality of nuclear safety related structures, systems, and components are identified to O

( TQR 1.0, which also briefly describes their assigned responsibilities.

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TOPICAL QUALITY ASSURANCE REPORT TQR 2.0 by Rev. I

^* QUALITY ASSURANCE PROGRAM DateSeptember 30,198t 8tORIDA POwtR 6 LICMt COMPANY Page 3 of 7 2.2.4 Participating Organizations (cont'd)

The Quality Assuruice Department shall be responsible for: a) the development, coordination, and control of the QA Program including coordination of Quality Procedure review' and approval; b) control and issuance of the FPL Topical Quality Assurance Report and the QA Manual as a controlled document (as described in TQR 6.0), and c) review of Quality Instructions written by other departments. For procedure revier requirements see TQR 5.0.

Florida Power & Light Company tuay delegate to other organizations, such as the Architect-Engineer, Nucle ar Steam Supply System vendor, or other contractors the work of estallishing and executing any portion of the QA Program. However, FPL shall retain overall responsibility for the Program.

The specific quality related activities performed by these contractor organizations shall be specified n; the procurement documents. The Quality Assurance Department, using qualified personnel, shall review and approve contractor Quality Assurance Programs prior to initiation of contracted activities.

The object of the contractor review shall be to verify that the contractor has an adequate QA program to meet the applicable requirements of 10 CFR 50, Appendix B and the FPL QA Program; or that an acceptable alternative is described and documented.

k In addition to the initial review, contractor QA Programs shall be periodically audited by the Quality Assurance Department to assure continued implementation of quality requirements.

During operation, FPL does not delegate a major portion of the Quality Assurance Prograrn to contractors. Contractors are delegated execution of p QA functions on a contract by contract basis. These contracts are reviewed

\ and approved in accordance with Topical Quality Requirements.

F TOPICAL QUALITY ASSURANCE REPORT TQR 2.0 gMt.

QUALITY ASSURANCE PROGRAM Da Septenbe,r 30 1 C

,tonio nowan a uc , cou,-

b 7 Page of _

2.2.5 Indoctrination and Training A program shall be established and maintained for quality assurance indoctrination, and for training which assures that the required level of personnel competence and skill is achieved and maintained in the performance v

)

of quality related activities. Quality Procedures shall delineate the requirements for an indoctrination program to assure that personnel responsible for performing quality activities are instructed in the purpose, scope, and implementation of the quality-related manuals, instructions, art.

procedures and that compliance to these documents is a mandatory requirement. The Quality Assurance Department shall be responsible for the indoctrination of supervisory personnel. Each department head is responsible for the indoctrination of non-supervisory personnel within his department who j

) perform quality related activities.

Quality Procedures shall also require the head of each department (including the QA Department) to be responsible for a training plan which assures that personnel performing quality-related activties are trained in the principles and techniques of the activity being performed. This training shall maintain l

the proficiency of personnel in the skills necessary for the quality related l activities through retraining, requalification or reexamination, as appropriate.

,- mj Quality procedures shall specify the requirements for documenting b indoctrination and training sessions, including a course description, 1

attendance, location, and date.

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l 2.2.6 Management Participation l

In additinn to the involvement of department heads in implementing the QA Program within their departments and the involvement of the Director of Quality Assurance in the development, coordination, and review of the

}

Program, the Quality Assurance Committee shall be appraised of the status l and adequacy of the Quality Assurance Program on a periodic basis.

l

TOPICAL QUALITY ASSURANCE REPORT TQR 2.0 Rev. I g

m QUALITY ASSURANCE PROGRAM DateSepte:nber 30,198(

( neaios acwin a oc r cowan Page of 2.2.6 Management Participation (cont'd)

The following actions shall be instituted to assure that the Quality Assurance Committee remains informed and meets its Program responsibilities:

" The Committee shall review the results of management level QA atad!'s a.

of FPL Department.

b. The Quality Ar.surance Depa-tment shall circulate monthly reports of quality related activities to members of the QA Committee and affected departruent heads. The monthly reports may include such items as the status of audits, a summary of audit findings, the status of development projects,and descriptions of policy matters or problems requiring management attention.

c. The Quality Assurance Committee shall review the status of the QA

\

x Program on a semi-annual basis. The review will include assessment of the Program goals, objectives, and accomplishments.

d. Periodic audits of the Q, Department and Program shall be conducted

! by an independent audit grcup under the direction of the Chairman of the Quality Assurance Cornmittee. This audit group shall employ FPL audit procedures and shall distribute the audit report to the QA Department, and to the Quality Assurance Committee for review of I findings and cetrective action, b

\ u N/ The Programs of contractor organizations that perform quality related activities shall be reviewed to assure that their management regularly reviews the status and adequacy of that part of the FPL Quality Assurance Program which they are executing.

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TOPICAL QUALITY ASSURANCE REPORT TQR 3.0 Rev. 2 O

1 DESIGN CONTROL Date Seytember 30,1980 8lossoa ponts & UGMt Couramv Page of f

3.1 GENERAL REQUIREMENTS A Quality Assurance Program for design shall be established to assure that the applicable design requirements, such as design bases, regulatory requirements, codes, technical standards and quality standards are identified in design G documents and their selection reviewed, approved and controlled in accordance with established procedures. Such controls shall include review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structures, systems, and components. Changes to and deviations frorn specified requirements shall be identified, documented and controlled. The Florida Power & Light Company (FPL) has the responsibility for design control program implementation. FPL may delegate to other organizations the work of establishing and executing the design and control program or any part

] thereof, but shall retain ultimate responsibility therefor.

{V The interface controls both internal and external, for organizations performing design work for safety-related sys' ems, structures, and cornponents shall be identified and implemented in accordance with documented procedures. This identification shall include those organizations providing criteria, designs, specifications, and technical direction.

Measures shall be applied to verify the adequacy of design. The extent of design verification shall be specified and documented by the responsible organization.

\

The depth of verification may vary depending upon the importance and complexity of the jesign, the degree of standardization, the state-of-the-art, and the similarity with proven designs. The verification process shall be performed by individuals or groups other than those who performed the original design. The design verification may be performed by the originator's supervisor provided the supervisor did not specify a singular design approach or rule out certain design considerations and did not establish the design inputs used in the design. The use m of the originator's supervisor for design verification should be restricted to special situations where the supervisor is the only individual within the design organization competent to perform the verification. Justification for such use

TOPICAL QUALITY ASSURANCE REPORT TQR 3.0 R ev. 2 y

DESIGN CONTROL O) l

\

Q 8tomiOA Powtm & LiCMT COMPahv Date September 30,1980 Page of 3.1 GENERAL REQUIREMENTS (Cont'd) should also be documented along with the extent of th's supervisor's input into the design aspect being verified. Where changes to previously verified designs have been made, design verification shall be required for the change, including g evaluation of the effects of those chciges on the overall design. Design verification may be acconsplished by testing. Testing shall demonstrate adequacy under adverse design conditions and shall consply with the requirements of TQR 11.0, " Test Control". Design errors and deficiencies which adversely effect srfety related structures, systems and componer.is in the design precess are docuuse: ted, and appropriate corrective action is taken. These design errors and deficiencies l shall be documented in accordance with the design change procedurea or as defined in TQR 15.0.

N 3.2 IMPLEMENTATION l

Power Plant Engineering Department shall be responsible for the design, design review, engineering approval of design changes, design evaluation and design control of nuclear power plants. Power Plant Engineering usay delegate to other l organizations the performance of design activities, or any part thereof, but shall l

retain responsibility for overall design. In all cases, final engineering decisions and ultimate design control of structures, systems and components related to nuclear power plants shall be the responsibility of FPL Power Plant Engineering.

I h Nuclear Analysis Department shall have the responsibility for all core related

'D safety analysis and nuclear physics design.

3.2.1 Design Process l

Design control measures shall be applied to design analyses, such as reactor physics, stress, thermal, hydraulic, nuclear radiation and accident analyses;

. compatibility of materials; accessibility for inservice inspection, i

maintenance, and repair; and delineation of acceptance criteria for inspections and tests. Measures established to control design documents are described in TQR 6.0.

TOPICAL QUALITY AS$URANCE REPORT TQR 3.0 R ev. 2 g

DESIGN CONTROL Date September 30,1980 s

nonionro* a a uc-ree w c Page of 3.2.1 Design Process (Cont'd)

Quality Program Procedures and Instrt.etions defire the FPL method for implementing design control measures. These measures shall require that applicable design requirements, such as design bases, regulatory requirements,

\ codes, and standards are translated into specifications, drawings, procedures, or instructions. Quality Instructions shall further require that appropriate quality standards are specified and included in design documents. All materials, parts, ecuipment, and processes, including standard "off the shelf" commercial or previously approved items, essential to the safety related functions shall be selected and reviewed for suitability of application. The basis for selection may include industry standards, meerial and prototype hardware testing programs, and design reviews.

3.2.2 Design Change Control Quality Procedures and Instructions governing design change control during construction, modifications to operating plants, control of discrepant or deficient design conditions, and reported unsatisfactory performance provide for the identification of the need for design changes and a documented method to control these changes. Design and specifications changes shall be l subject to design control measures commensurate with those applied during the original design.

( During the design and construction phases, an independent review and appreval of design changes shall be performed by the organization that conducted the original design reviews, unless the originating organization designates another organization to perform this function. Subject to the approval of the Chief Engineer-Power Plants, or his designee, safety-related field design changes or changes in Engineering requirements proposed by FPL may be sent directly to the Architect-Engineer. Such design changes shall be l reviewed by the Architect-Engineer for adequacy of quality requirements.

V Other safety-related design changes proposed by FPL shall be reviewed by Power Plant Engineering prior to transmittal to the Architect-Engineer.

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f TOPICAL QUALITY ASSURANCE REPORT TQR 3.0 2

y Rev.

DESIGN CONTROL f Date September 30,1980 etoaion rowna 6 oc e cewu.v Page of 3.2.2 Design Change Control (Cont'd)

During the operations phase, proposed safety related design changes / modifications shall be submitted to the operating plant management for processing and review. This review shall include the plant Quality Control N review. Power Plant Engineering is responsible for the design adequa7 and design reviews of all operating plant safety related change / modifications (PC/Ms). The safety related PC/M shall then be reviewed by the Plant Nuclear Safety Committee (PNSC) or Facility Review Group (FRG). Proposed PC/Ms which the plant manager judges to have an adverse impact on the environment shall be reviewed by the Company Environmental Review Group (CERG). Final review and approval of the design change (PC/M) shall be performed by the Company Nuclear Review Board (CNRB) when necessary.

These independent reviews shall be performed to assure that:

a. adequacy of the proposed change is determined;

b. appropriate quality criteria, standards and hold points are specified and included; and

c. nuclear safety requirements have been considered.

3.2.3 Design Interface Control Quality Procedures and Instructions provide the method for identification of design interfaces, design interface changes, and modifications affecting l drawings and documents. Power Plant Engineering is responsible for review

and coordination of design interfaces. Power Plant Engineering assures that interface problems are resolved and that all design interface changes or modifications are reviewed for interface effects prior to approval.

During plant design and construction phases, control of interfaces may be delegated to the Architect-Engineer and/or the NSSS vendor. Design

.\

) interface problems encountered during design and construction are discussed l V l among the principals such as FPL Power Plant Engineering, Architect-L

I TQR 3.0 I TOPICAL CUALITY ASSURANCE REPORT _

R ev. 2

'i bh p "* J DESIGN CONTROL

( etenio. no ia a uc r couem 5 6 Page of 3.2.3 Deign Interface Control (Cont'd)

Engineerr, NSSS vendor, and other contractors, and shall be documented.

During the operations phase, design interfaces shall be documented and p, controlled by Power Plant Engineering. Resolution of design interface questions between FPL departments shall be documented.

3.2.4 Design Verification l

Original designs and design modifications shall be reviewed for adequacy and l

the sign-off performed by a person other than the originator of design. Design reviews shall be documented in accordance with procedures or instructions.

l Simplified calculations or computer models/ codes may be utill:ed as alternate l means of design verification. When design verification is performed by

) testing, the tests shall be performed using approved procedures. Ultimate responsibility for design adequacy and evaluation is retained by Power Plant Engineering. Written 8.nstructions shall specify the authority and responsibility of design verification personnel.

The depth of a design review shall be commensurate with the significance of l the safety function performed by the item, the complexity of the design, I experience with the design, and experience with potential suppliers of the n item.

U Particular emphasis shall be placed on assuring the conformance with applicable odes, and on selecting the proper design verification or checking m ethod. Quality Procedures and Instructions provide the requirements and necessary controls for design verification. These controls include review to assure that design characteristics can be controlled, and verification that

there is adequate accessibility for inspection or test, and that inspection l

acceptance criteria are incorporated. During the operations phase.

l documentation of reviews shall be provided.

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TOPICAL QUALITY ASSURANCE REPORT TQR 3.0

~ R ev. 2

/ DESIGN CONTROL Date Septaber 30.1980 etcaica powen a ucar couean, Page of 3.2.4 Design Verification (Cont'd)

During the design and construction phases, Power Plant Engineering maintains N responsibility for the design documents generated by the Architect-Engineer, NSSS vendor and other FPL departments. The evaluation of selected documents by Power Plant Engineering may be accomplished with assistance from other FPL departments concerned with the equipment / subject covered by the document being evaluated.

Power Plant Engineering shall be responsible for the resolution of comments and the issuance of revisions to A-E, NSSS vendor, and other contractor specifications and drawings. The Power Plant Engineeril:g objective is to 1

resolve comments and to issue revisions prior to release for bids, construction, and fabrication. Power Plant Engineering shall retain a final approved copy.

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TOPICAL QUALITY ASSURANCE REPORT TQn 6.0 R ev. ,

m DOCUMENT CONTROL DateSegtember 30. 1980 stonion powen 6 ucar cowam Page 1 of 3 6.1 GENERAL REQUIREMENTS The distribution of documents such as instructions, procedures, and drawings which provide guidance, specifications, or requirements affecting the quality of nuclear safety related structures, systems, and components shall be controlled.

l (nV) These documents shall be prepared, reviewed for adequacy, and approved for release by authorized personnel i.i the affected organization. These documents shall be distributed to locations where the activity is performed.

Changes to controlled documents shall be so identified and shall be reviewed and approved by the same organization that performed the original review and approval unless otherwise specified in the implementing procedures. In addition, procedures shall provide for controlling obsolete documents to preclude the O possibility of use of outdated documents.

6.1 IMPLEMENTATION 6.2.1 Responsibility Quality Procedures shall delineate the control measures for controlled l documents including direction for the review fer adequacy, approval by t

authorized personnel, distribution of controlled documents and verification l

l that changes are promptly incorporated. These control measures shall apply 1

.3 to documents affecting the quality of nuclear safety related structures, systems, and components such as:

a. design specifications;

b. design, manufacturing, construction, and installation drawings;

c. quality program manuals, procedures, and instructions;

d. inspection, manufacturing, and test procedures and instructions;

e. plant operating and main +enance procedures;

f. plant Safety Analysis Reports and related design criteria documents.

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(j\ The requirements for control of procurement documents are contained in TQR 4.0.

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l TOPICAL QUALITY ASSURANCE REPORT TQP, 6.0-

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DOCUMENT CONTROL DateSeptember_30, 198C

\ no. o. powta a uc-r cow w Page 2 of 3

. 6.1 IMPLEMENTATION (Cont'd)

During all phases of plant life, it shall be the responsibility of each organization issuing controlled documents to use document control procedures. Procedures

,, shall document the responsibility for review, approval, maintenance and l distribution of documents including coordination and control of documents which describe interface relationships.

During the design and construction phase and for operating plant changes under their cognizance, the Architect-Engineer, Nuclear Steam Supply System vendor, and other contractors shall be responsible for assuring that all revisions required as a result of FPL comments, nonconformances, or engineering work are incorporated into revised documents.

1 6.2.2 Distribution of Controlled Documents L

Quality Procedures shall specify that controlled documents and revisions be distributen to locations where the activity is performed.

6.2.3 Drawing Control l During the design and construction phase, the Power Plant Engineering l

l Department shall be responsible for periodically issuing a master drawing list l

l eN which includes, as a minimum, those drawings newly issued or revised since f ) the last list was promulgated. During the engineering and contruction phases v

of the project, the Nuclear Steam Supply System vendor and the Architect-Engineer may be delegated the function of drawing control and shall furnish periodic status reports listing the latest revision of applicable documents l which they issue, including drawings, instructions, and procedures.

1 1

During the operations phase, the Power Plant Engineering Department shall retain responsibility for review and approval of drawings, but the General p) Engineering Department shall be responsible for the control of plant drawings and drawing changes. At plant sites, a system shall be established to provide ready access and availability of drawings.

TOPICAL QUALITY ASSURANCE REPORT TQR 6.0 R ev. 1 g

' DOCUMENT CONTROL DateSept. ember 30. 198C v neaios aowia a uc e cowan 3 ,, 3 Page 6.2.4 Instrue. tion and Procedure Control During the design and construction phase, the Nuclear Steam Supply System vender and the Architect-Engineer sh211 be responsible for control of quality related instructions and procedures issued by thern. Selected contractor o

documents are reviewed by at least one or more of the following FPL depart'.nents, depending on the nature of the document:

a. Qualtiy Assurance

b. Plant Construction

c. Power Plant Engineering During all phases of plant life, the originating FPL department shall be responsible for establishing adequate control over quality related instructions and procedures issued by them. The responsible organization shall also issue periodic status reports or revised indices listing the latest revision of applicable controlled documents issued by them.

6.2.5 Obsolete Documents Controls established by Quality Procedures or Instructions shall assure that outdated copies of controlled documents are not inadvertantly used.

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l TOPICAL QUALITY ASSURANCE REPORT R ev. 1 C\ CONTROL OF SPECIAL PROCESSES

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5 DateSeptember 30,198C 8Lonica ponte 6 UGaf CQu'am? ,

Page of 9.1 GENERAL REQUIREMENTS Measures shall be established to assure that special processes such as welding, heat treating, nondestructive examination, and nuclear cletning are controlled and j accomplished by qualified personnel using qualified procedures in accordance with V applicable codes, standards, specifications, criteria, and other special requirements.

9.2 IMPLEMENTATION The Power Plant Engineering Department shall assure that documents and procedures submitted for approval related to construction and modification of safety related items are properly reviewed to verify adequate identification of special processes and documentation requirements. Special processes used during (G operations shall be the responsibility of the plant manager who shall assure that procedures and personnel are qualified.

9.2.1 Procedure Qualification and Control Qualilty Procedures specify that written process control procedures shall be used and qualified as required by applicable specifications, codes, or standards.

Where FPL assigns work to outside contractors, the contractors shall make l their procedures and personnel qualifications available to FPL prior to the Q

1 start of work. The Architect-Engineer, Nuclear Steam Supply System vendor or other organization designated by FPL shall be responsible for the evaluation and acceptance of on-site contractor special process procedures and shall interface with the appropriate FPL department as necessary to l resolve review comments with the contractor. The contractor shall also be responsible for the control and approval of sub-contractor procedures.

The review of special process procedures used during construction shall be (n}

' coordinated by the Plant Construction organization.

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TQR 9.0 TOPICAL QUALITY ASSURANCE REPORT R ev. 1

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CONTROL OF SPECIAL PROCESSES DateSeptembe,r 30,198C

(/ *tonion eown a oce cowa=, ,

Page of 9.2.2 Personnel Qualification and Certification Procedures or Instructions shall specify personnel qualification / certification requirements. Personnel responsible for the performance and verification of special processes shall be trained, tested, and certified as required by

/m applicable specifications, codes and standards. Requirements for the period

\ of certification, retesting, and recertification of personnel shall also be specified. Centractors shall qualify personnel and maintain records of qualified personnel in accordance with applicable codes, st andards, specification and contract or procurernent document requirements.

During construction, the Plant Construction organization which includes the Construction QC organization, shall be responsible for: The certification or qualification, as appropriate, of personnel performing special processes; and to control, rnaintain and calibrate equipment used for special processes. The QA Department is responsible to usure, by audit, that current records are

' roaintained on-site for work performed by or for FPL. During operations, the plant manager or his designee shall be responsible for these records.

9.2.3 Special Process Records Records shall provide objective evidence that special processes were performed ,.. compliance with approved procedures by qualified personnel, and that when required, by procedures, specifications, and codes, such performance was verified. Results of nondestructive examinations shall be p\

(' recorded in accordance with applicable specifications, codes and standards.

These records shall be retained by the vendor or supplied to FPL as required l

by contract or purchase orders. If records are to be retained by the vendor, the contract or purchase order shall specify the retention period and instructions for final disposition of such records.

During construction, the Construction Qua"ty Control organization is responsible for the eview of nondestructive examination documents for acceptance, and for assuring that documents for special processes utilized (n ,

i during construction are properly collected, reviewed, accepted arc transmitted for retention. During operations, the plant manager is responsible l

for the review and retention of records.

TOPICAL QUALITY ASSURANCE REPORT TQR _13.0 Rev. 1

] FLCasca ecwte & uGNt couramy s

HANDLING, STORAGE AND SHIPPING DateSeptenber 30,198(

Page I d A 13.1 GENERAL REQUIREMENTS Written instructions or procedures shall be established and implemented for the cleaning, shipping, storage, preservation, packaging, and handling of specified

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/ \ items. These instructions and procedures shall delineate measures which prevent Ns degrading an item through damage or deterioration. When necessary for particular products, special protective environments such as inert gas atmosphere, specific moisture content levels, and temperature levels shall be specified and provided.

13.2 IMPLEMENTATION 13.2.1 General n Instructions or procedures shall be written to define the requirements and responsibilities for the cleaning, packaging, preservation, handling, storage, and shipping of equipment and materiaJ, and shall require implementation of the established design and specification requirements by personnel having appropriate qualifications. FPL may delegate any portion of the responsibility for handling, storage and shipping of material and equipment, but shall retain ultimate responsibility. Where any of the functions in the l

section which follow is delegated to a contractor, the contractor shall be required to adhere to the FPL requirements stated herein.

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During the operations phase, consideration shall be given to the need for special requirements in the preparation and review of procurement documents (see TQR 4.0). Procedures and instructions shall be prepared and implemented for spe.- : on-site handling or storage requirements. The receiving department st til be responsible for on-site implementation of the

( special handling, shipping, and storage requirements for items received and controlled by their organization.

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TOPICAL QUALITY ASSURANCE REPORT TQR _13.0

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( HANDLING, STORAGE AND SHIPPING DateSepte:hber 30.198C

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Page of 13.2.2 Establishment of Handling, Storage, and Shipping Requirements Special handling, preservation, storage, cleaning, packaging, and shipping requirements shall be specified, as appropriate, in the design documents or purchase orders. The requirements established in the design documents or purchase orders shall be consistent with industry accepted standards, the importance of equipment of material to nuclear safety, and the material or equipments's sensitivity to damage. The preparation of these design documents or purchase orders may be delegated by FPL to other organizations. The preparation and control of design documents and purchase orders is described in TQR 3.0 and 4.0.

13.2.3 Handling, Storage, and Shipping Procedures Materials and equipment which are to be incorporated into a safety related O system of a nuclear power plant shall be handled, stored, and shipped in accordance with written procedures where necessary to implement the design document and purchase order requirements. These procedures shall assure that cleaning, handling, storing, packaging, shipping, and preserving m aterials, components and systems will preclude damage, loss, or deterioration by environmental conditions such as temperature or humidity.

The preparation and/or implementation of these procedures may be delegated to other organizations, but FPL shall retain the ultimate (d I responsibility for proper material handling, storage, and shipping.

13.2.4 Verification of Proper Handling, Storage, and Shipping.

The Quality Assurance Department shall be responsible for verification of l

proper handling, storage and shipping at vendor facilities and on the construction site during the constructicn phase. Power Resources and the QA Department shall be responsible for verification of proper handling, storage, and shipping at the plant during the operations phase.

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TOPICAL QUALITY ASSURANCE REPORT TQR 14.0 c

R ev. 1 N O INSPECTION, TEST, DateSeptenber 30,198C s stomo. .owie a oc e coue w AND OPERATING STATUS 3 Page of 14.1 GENERAL REQUIREMENTS Measures shall be established to indicate by the use of markings such as stamps, tags, labels, routing cards or other suitable means, the status of inspections and tests performed on material, equipment, or systems during the construction and

(/ operations phases of nuclear power plants. These measures shall provide for the identification of items which have satisfactorily passed required inspections and tests. Measures shall also be established for indicating the operating status of structures, systems and components to prevent inadvertent operations.

14.2 IMPLEMENTATION 14.2.1 General During the construction phase, the Construction Department is responsible 1

i for establishment and maintenance of a suitable system for identifying the inspection, test, and operating status of materials, equipment, systems, and co mponents. The system shall be established, implemented and maintained in accordance with written Quality Procedures and Instructions. The Architect-Engineer or Constructor shall develop and implement procedures to comply with contractual responsibilities, and applicable codes, standards, specifications, and criteria governing the status identification of procurement items being tested, installed, or fabricated. The Architect-Engineer (where applicable), suppliers and contractors shall be required to N

maintain a system for identifying the inspection, test and processing status of materials, parts, and components. Elements of this system require that suppliers and contractors have a controlled manufacturing and test operation in order to preclude the inadvertent bypassing of processing, inspections or test, and to provide a positive identification of component status throughout all phases of manufacturing, testing, and inspecting by means of tagging, routing cards, stamping, manufacturing or test reports, labeling or other appropriate methods.

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TOPICAL QUALITY ASSURANCE REPORT TQR 14.0 gM4 R ev,

% y vy INSPECTION, TES'I, DateSeptember 30.198C v stonion poca a ucar cow.m AND OPERATING STATUS Page 2 of 2 14.2.1 General (cont'd)

During the operations phase, the Power Resources Department shall be responsible for assuring that on-site inspection, test, and operating status requirements are implemented per written Quality Procedures and

(% Instructions.

The Construction, Power Resources and Quality Assurance Departments shall verify adequacy of the controls established and implemented.

14.2.2 Status Identification and Control Quality Procedures and Instructions shall describe control of the application and rernoval of markings such as stamps, tags, labels, routing cards, and other suitable rneans to indicate the status of nonoperational,

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(s ~ nonconforming, or malfunctioning safety related structures, systems and cornponents to prevent inadvertent operation, and to prevent omission of inspections, tests, or other critical operations. These Procedures and Instructions shall delineate the requirements, methods and responsibilities for indicating the status of the affected items. These procedures will clearly delineate the individuals or groups responsible for application and removal of status indicators.

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TOPICAL QUALITY ASSURANCE REPORT TQIl 15.0 NONCONFORMING MATERIALS, (N embu 0. Iw nomo. ,owen a uce counn PARTS OR COMPONENTS Page I M 3 15.1 GENERAL REQUIREMENTS Measures shall be established to control materials, parts, or components which do not conform to requirements in order to prevent their inadvertent use or installation. These measures shall include, as appropriate, procedures for

()\l identification, documentation, segregation, disposition, and notification to affected organizations. Nonconforming items shall be reviewed and accepted, rejected, repaired er reworked in accordance with documented procedures.

15.2 IMPLEMENTATION 15.2.1 Program Quality Procedures and Instructions shall define the responsibilities and methods for identifying, documenting, segregating and dispositioning p nonconforming uems. For procedure review requirements see TQR 5.0.

( Each depa cment shall be responsible for the identification, control, and disposition of nonconformances with the scope of their departmental responsibilities.

Throughout plant life, FPL may delegate any portion of the identification and control of nonconforming items and services to an Architect-Endneer (A/E), constructor, NSSS vendor or other contractors. In any case, FPL retains the responsibility for assuring that requirements are met, and shall assure that the contractor's actions conform to requirements set by FPL.

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15.2.2 Documenting and Controlling Nonconformances l

All nonconformances in safety related items shall be documented and reported for corrective action. Measures shall be delineated in Quality Procedures and Instructions which control further processing, installation, or operation of nonconforming items. These mear.res shall include:

a. Physical identification of the item as nonconforming.

b. Segregation of nonconforming items until properly dispositioned.

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TOPICAL QUALITY ASSURANCE REPORT TQR 15,0 N .

NONCONFORMING MATERIALS, DateSep.tenber 30.198C stoa oa o.a. 6 tic-r co... . PARTS OR COMPONENTS of 3 Page 15.2.2 Documenting and Controlling Nonconformances (cont'd)

Where physical segregation is not practical, suitable tags, : narking and documentation shall be used to assure control 15.2.3 Documentation v Docurnentation of the nonconforming item shall: identify the item; describe the nonconformance; show disposition of the nonconformance and inspection requirements; and include the signature of the person approving the disposition.

15.2.4 Evaluation and Disposition The FPL Power Plant Engineering Department shall assure that engineering evaluations of nonconfor: nances are performed, as necessary, and shall r~T selectively review engineering evaluations and dispositions developed by I

\g) contractor engineering organizations.

An evaluation to determine the disposition cf nonconforming items shall be performed. The evaluation shall determine whether an item is to be accepted as-is, repaired, reworked, or rejected. A technical evaluation shall be performed when an itern is accepted as-is or is repaired to an acceptable condition. Records of the disposition of these items shall be made part of the nonconformance report. This evaluation shall assure that the final p condition does not adversely affect safety, operabiuty cr maintainability of l ( m the item, or of the component or system in which it is installed.

l

, The A/E, or other contractors on site shall be required *.o inform the FPL 1

l Construction or Power Resources Departments prior to use or installation of l

l a nonconforming item. The nature and extent of a nonconformity and the reason for proposing its use or installation shall be justified. Nonconforming items dispositioned " accept as-is' or repaired to an acceptable condition shall be so identified. Nonconformance reports for those items shall be tnade part of the item records and forwarded with the materal to FPL.

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TOPICAL QUALITY ASSURANCE REPORT TQR 15.0 NONCONFORMING MATERIALS, DateSep_tsger 30. 1980 Q etomoa aowin a uc r cou,.=, PARTS OR COMPONENTS Page 3 of 3 15.2.4 Evaluation and Disposition (cont'd)

The determination of the need and the advisability of releasing nonconforming material or items, is made by the Power Plant Engineering, Construction, or Power Resources Departments. The following factors may

[] be appropriate considerations in making this determination:

bl a. Effect on the orderly progress of work if material or iterns are released;

b. Safety of personnel;

c. Suitabili:y of material or items in "as-is" conditin, i.e., probability of eventual satisfactory resolution of the nonconformity without repair rework, or replacernent;

d. Accessibility of material or items after release;

e. Cost of removal and repair of replacement should material or items eventually have to b2 removed, repaired, or replaced;

f. Impact on plant safety.

Items shall be reworked or repaired in accordance with documented procedures and shall be verified by reinspecting the item as originally inspected or by a documented method which is at least equal to the original inspection method.

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Quality personnel shall periodically review nonconformance reports to m identify quality trends. The results of these analyses shall be reviewed with l ) appropriate members of upper level management.

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TOPICAi. QUALITY ASSURANCE REPORT TQR 16.0 g

R ev. 2 8 = CORRECTIVE ACTION DateSeptember 30,198C 1

Q soaica covna a ucar counac Page 1 of 3 16.1 GENERAL REQUIREMENTS Documented measures shall be used to assure that conditions adverse to quality such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances, are promptly identified and corrected as soon as practicable. In the case of significant conditions adverse to quality, the cause of the condition shall be determined and action taken to preclude repetition. The identification of significant conditions adverse to quality, the cause of the condition, and the corrective action taken shall be documented and reported to appropriate levels of management.

16.2 IMPLEMENTATION 16.2.1 Corrective Action and Follow-Up Quality Procedures and Instructions shall define responsibilities and methods f for identifying and correcting conditions adverse to quality. When an adverse O condition is detected, a determination shall be made by plant supervision or Quality personnel as to whether immediate or routine corrective action is required.

a. "Immediate Corrective Action" applies to conditicas which pose a threat to plant safety or to the health and safety of the public, which could result in major equipment and material damage, or could, if not corrected, produce defects of significantly greater consequences than those immediately resulted from the condition. "Immediate Corrective Action" is accomplished through stop work requests / orders to v appropriate levels of management, requiring that work be stopped, the plant be shut t . 7 or other appropriate actions be taken.

b. " Routine Correc e Action" applies tc conditions which do not reqeSe immediate correct.ve action. Routine corrective action is assured through the distribution and disposition associated with inspection reports, surveillance reports, nonconformance reports, and audit reports; and the investigation analysis and action associated with reportable conditions.

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TOPICAL QUALITY ASSURANCE REPORT TQ1L 16.0 R w. 2 g

CORRECTIVE ACTION DateSeptember 30. 1980 L L/ / stoniOA POwin & LICHf compass?

Page A of 3 16.2.1 Corrective Action and Follow-Up (Cont'd)

Follow-up to verify implementation of corrective action and close-out of corrective action documentation is acecmplished by the QA or QC organization responsible for verifyi'g the corrective action. The Quality 7

( Assurance Department shall track, follow-up, and close-out open items N

identified by QA Department audits and vendor surveillances, and shall assure the tracking of unresolved items and violations identified by NRC inspections. Each department shall be responsible for follow-up and close-out of corrective action resulting from their departmental inspections, tests, or operations.

If corrective action is inadequate or not timely, the follow-up organization shall request corrective action from management as delineated in

[ procedures. The Quality Assurance Committee is the final authority in the D) event that agreement is not reached at lower levels regarding stop work requests or other corrective action.

Where corrective action is required of contractor personnel, FPL shall define in procedures and contracts the corrective activ interface between FPL and i the contractor. FPL shall require the A-C, NSSS vendor, constructor and other suppliers of safety related materf als and services to have a documented l corrective system.

6.2.2 Recurrence Control It is the responsibility of the organization which identifies the condition adverse to quality (i.e., issues the NCR, Deficiency Report, audit report) to verify that corrective action not only corrects the immediate condition, but also prevents the condition from recurring. The organization (s) that provide (s) the corrective action disposition is responsible to assure that the corrective action taken not only corrects the immediate condition but also prevents the fh i l adverse condition from recurring.

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TOPICAL QUALITY ASSURANCE REPORT TQR 16.0 R ev. 2 CORRECTIVE ACTION DateSeggs;:tber 30. 198(

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Page 3

of 3 16.2.3 Incidents and Reportable Occurrences Reporting During construction, significant deficiencies shall be documented as to cause wid corrective action, and shall be reported to the Nuclear Regulatory Commission (NRC) and FPL management as required by 10CFR50.55(e). In all cases when a determination is made that an-item is reportable, the NRC will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after that determination and by written report within 30 days.

Operating Reportable Occurrences and reports of incidents shall be investigated, documented as to cause and corrective action, and reported to the NRC in accordance with the applicable plant Technical Specifications.

Reportable Occurrences and reports of incidents that result in damage or are otherwise safety related, shall be forwarded to the Company Nuclear Review Board (CNRB) for review. Conditions adverse to quality are reported to

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L/ operating plant management through: Distribution of QA audit reports, QC inspection reports, corrective action requests, and the investigation and reperting of Reportable Occurrences in accordance with plant Technical Specifications.

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PRESIDENT i

r EXECUTf /E VICE PRE! JDENT I l COMPANY NUCLE AR QUALITY ASSURANCE REVIEW BOARD VICE PRESIDENT ADV SYS & TECH COMMITTEl Chairman. VP Adv. Sys &

Cha.rmen E necutiw, VP um Ch.ef Eng. . Power Ptants VP Povver Res. 8'"'.*' YP Manager of Pwr. Res. Nuc VP Pow Hesources

/" Dir of Quahty Assurance VP Adv Sys & Tech

/ EPP Eng. Supervesor Director of Licensing Der of Quaesty Assur.

Coord Dwector of EPP Eng. Supervisor R&D & Enwr. Plannmg VP System Planning si Quahtw Assurance VP Engr., Prce. Mgt., &

Participants:

Const.

Dir. of Purchasing and Plant Mgr4non-voting) Inv. Resources Consultants-InorHrotmg) VP Fuel Res., Corp.

E xec. Sec. CNR B- (non- Dev.

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- Manager of _

Asst. Manager Enwr Affairs Engmeering ,

4 Manager of Envir. -

Amst. Manager Chief E Technical Sves. Procurement Gen E ,

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F Company Anst. Manager ,

E nvironmental Rowew Group Construction (

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( ORGANIZATION OF DEPARTMENTS <

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I o . . TOPICAL QUALITY ASSURANCE 3EPORT Appendix A QUALITY ASSURANCE E Date Sept. 30, 1980-noaioa powen a ucar courany ORGANIZATION Figure 1-2 Page 2 of 10 4 2m z.!

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                        ,                                                                                    ***   #*E *-          ' l nonica nowo 6 ucar ecue =,                       QUALITY ASSURANCE INTERFACE Figure 1-4                               Page     -4       of 10 Pet Pruessons

[ , $ .- Execuove Vice Pressoant r 1 e 3 s ( J vice Pressoent way

                                  ' A_cy, $YS.                   Anmerones
                                     & Tecn.                     Cm s

Cirector '  ; Q"**W Oirector of l Assurance Lcanseng & Enver Affatr$ 8 Asst. Meneger ' m i i (~ _ N'""""9 Comoany n rM Enwr Manager of Enwronenentas Enver Affairs Review Grouo Tecn Services _ ^"' "mo^

                                                                                                     - QA/QC Asst. Manager                                                   Coorcinator
                                -            a           -                                    l Coerstion AWL Menseer QA Ceestrussen OPP 487E I i
                                                                                                    .N43TE

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l l TOPICAL QUALITY ASSURANCE REPORT Appendix _A l' R ev. 2 l g ADVANCED SYSTDiS & TECENOLOGY Date Sept.,30, 1980 noaio* aowna 6 ucar ecueam QUALITY ASSURANCE INTERFACE Figure 1-5 Page 5 of 10

                                                                                                       .e Pft ESIDENT l                                                                       '                                  '

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Executrve Vice President a Ceccany edustw CA Commdtes .

                                                                                                                     "'"** 8**'d WTm Di"' Of                   Oirector of         Coord.

Lxensing & Qualaw A&O Envir. Ptanning A smrance s' $ QA/CC Coord. Asst. Manager of Asst. Manager of Asst. Manager of Asst. Manager of CA Engineenng QA Procurement CA Construction QA Operations i - , L Miami Staff L MiamiStaff

                                                            - Onsite Staff             - Casite Staff l

5 L J

r. ~ ..- ., __ - - - , , _ _ , _ . , . .

TOPICAL QUALITY ASSURANCE REPORT Appendix _A ENGINEERING AND

   \                                                                                                                                      Date      Sept.,30, 1980 stoaica aowna a uc t c      w..,,                       QUALITY ASSURANCE INTERFACE Figure 1-6                                            Page          6       of   10 ret.

Premdent i , (C Execuuve v'ece Prosacent

                         ,                                                                   I                                ,
                         '                                                                                                     3 I                                  l v.c. Pres.oent                          ,,         ,,,

Adv. Sys. g,, and Tech. r 4 vice Prosedent Quality Assurance Engr., PM. Mgt., Director I , I I# Ass't Manager CA Chief Engineer l Chief Engr.

                            ~

Engineenng Pwr, Plants Gen. Engr.

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                                                                                                                                            ,         l       ,

Ass't. Manager CA CA/CC l

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Procurement . Coordinator

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                                 . Ass't. Manager         -                                Manager                  -   M cnanecai/Nucteer Apolications                                        ( Engineenng) l Electreal/l&C
                            ~

aw - QA Constructen l [ _ t., cons ng Civil OFFSITE CA Ooerating P' ants Aeores nrative 1 k CA Construction

                                                                                                                  'Only ass:gned for new 5                                                                       Site Engineer *  -               Constructioa protects j                         Representatrve u            A

TOPICAL QUALITY ASSURANCE REPORT Appendix A

                                            '      ~                                                                                                   R ev.          3
 /'                                                                                                                                                                                       i CONSTRUCTION AND etcaio* ,owen a uC-r cou, n,                        QUALITY ASSURANCE INTERFACE
                                                                                                                                                       '*?*              '

figura 1-7 PMSIDENT Executive vice pres.oent C

        ~                    l Vice President           Quality Assurance Adv. Svs. & Tecn.            Committee vp. Engr Pros.

Met. & Const.

                                                                                                         's Cirector                         l         Qirector of Gua!!ty Assurance                              Construction s                                 i e                                              e
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l Mmbistrative & Functional Reporung i Functonal Reparung Only Asst. Manager CA , suot Gen Construction * * * * * - Admiristrative Reporting Onty Procurement ,

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l Ass't. Manager CA l r f Engineering J > l I [ suoerintencent (" Ass t. uanager CA Coerstes I Construction Quassey Contros

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TOPICAL QUALITY ASSURANCE REPORT Appendix A POWER RESOURCES, POWER SUPPLY, AND Date Sept._30, 1980 etomoa powin a ucar cow,any QUALITY ASSURANCE INTERFACE Figure 1-8 Page 8 of 10 t i i l

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                                }                      }

Vice Presdent Adv. Sys & Taca.

                      /
                       /

Qitecter . ('. ( Quality Assurance Oltester of Purchasing in l in,enterv a.soor es I I Mgr. of PUrthasang Asst. Manager QA Procurement QA/QC Manager of Coordinator

                                       ~

Inventory Men. Ass't. Manager CA g Engineenne g Mgr. of Pwr. Mant Const & Oper. Stores k' Asst. Manager QA _ Construction Asst. Manager QA _ qajac Coerations Coerainator OFF SITE ON4tTE l QA Construction Area Stores Area Stores

• R epresentative Supervisor Supen.sor i i g

( m ' I sto,,a st.as [ } Q A . ),erating L ---4 so , s., s.ner uor Piants  ! I R Joresentative I . ,m t 1 1-- ,- .. _ __ _ _

APP'" dix A TOPICAL QUALITY ASSURANCE REPORT R ev. 1 CPERATING PLANT SITE One Sept.,15, 1976 stomon powem 6 ucar conepany MANAGEMENT ORGANIZATIONS Page 10 of 10 Figure 1-10 PLANT MANAGER PLANT MANAGER ( OUAUTY CUAUTY N CONTROL CONTMOL SUPERVISOR SUPERVISOR t' 1 PLANT PLANT SUPERINTENDENT. SUPERINTENDENT. FOS $1L NUCLEAR I PLANT PLANT ({ NUCLEAR SAFETY NUCLEAR SAFETY ', I - CCMMITTEE . COMMITTEE

                                                                               ~

l STApp STAFF TYP1 CAL FOS $1UNUCLEAR NUCLEAR StTE MANAGEMENT SITE MANAGEMENT Florida Power & Light designates a Plant Manager for all plant sites. For those sites which contain both fossil and nuclear power plants, Plant Superintendents are designated as illustrated in the figures above. The Quality Control Supervisor, in all cases, shall report to the Plant Manager, I while the Plant Nuclear Safety Committee reports to the individual who exercises direct control over the nuclear plant operation. This individual may be either the nuclear Plant Manager of the Plant Superintendent - Nuclear, de-I pending on the type of plant site. Throughout the text of the Topical Report, glant m_anager (spelled in lower case letters) shall be used to signify the individual with responsibility for direct l l control over operating nuclear power plant activities. This is done for brevity and ease of reading, and should be interpreted to mean Plant Manager or Plant Superintendent-Nuclear, as appropriate.

Appendix. B TOPICAL QUALi'iY ASSURANCE REPORT R ev. 1 g A i QUALIFICATICN AND EXPERIENCE REQUIREMENTS DateSeptember 30,198C (w flostDA PCWE A & UGnf COMPANY

                                                                                           ~ ~ ~ ~ ~

FPL QUALITY ASSURANCE PERSCNNEL py, 7 g TITLE EDUCATION

• AND BACKGROUND EXPERIENCE 3l Director of Quality Shall satisfy the requirements for the position of Assurance Assistant Manager of Quality Assurance and have a minimum of five years of managerial experience in industry.

Y Assistant Manager of Shall satisfy one of the following sets of require-Quality' Assurance ments: Graduate of a four year accredited engineering or science college or university, plus seven years of industrial experience including three years in posi-tions of leadership, such as lead engineer, prcject engineer, audit team leader, etc. At least two years of this experience should be associated with nuclear facilities. A masters degree in engineer-

                                         .ing or business management is considered equiva-lent to two years of experience.

( Completion of college level work leading to an as-L sociates degree in a related discipline plus fif-teen years of industrial experience including three years in positions of leadership, such as project engineer, audit team leader, supervisor, etc. At least five years of this experience should be as-sociated with nuclear facilities. High school graduate, plus twenty years of indus-trial experience, including three years in positions of leadership, such as project engineer, audit team leader, supervisor, etc. At least five years of this experience should be associated with nuclear facilities.

  )

V T ,1"j

• The education and experience requirements should not be treated as absolute when similar training or an outstanding record will provide reasonable assurance that a person can perform the required tasks.

                                                   )

l TOP CAL QUALITY ASSURANCE REPORT APP:ndix C

   }                                        BISELINE DOCUMENT MATRIX               Da eSennb    30. 1980 j     nonica cowsm a ucwt couramv The FPL Quality Assurance Program described in this Report follows the guidance provided in the NRC documents:

o " Guidance on Quality Assurance Requirements During Design O- and Procurement Phase of Nuclear Power Plants" WASH-1283 Rev.1 May 24,1974 o " Guidance on Quality Assurance Requirements During the Operations Phase of Nuclear Power Plants" WASH-1284 October 26,1973 o " Guidance on Quality Assurance Requiremene Requirements During the Construction Phase of Nuclear Power Plants" k WASH-1309 May 10,1974 This topical report contains the program requirements for Florida Power & Light Company's Quality Assurance Program. The Quality Assurance Program is described in detail in the Florida Power & Light Company Quality Assurance Manual. The Regulatory Guides, codes, and standards specifically listed in the matrix of this appendix (on page 2) represent the baseline guidance used in the preparation of FPL's QA Manual and this topical report. These guidance documents, therefore, provide the basis for the FPL QA Poogram, but they are not considered to be part of the QA Program unless specifically addressed in the applicable SAR, technical specifications, etc. The FPL Quality Assurance Program generally meets the intent of the documents referenced in this appendix. Any exceptions taken to the intent of a guidance document, and equivalent FPL alternatives to such exceptions are stated on pages subsequent to the second page of this appendix. l O

TOPICAL QUALITY ASSURANCE REPORT BASELINE DOCUMENT MATRIX Da September 30, 1980

    .tomoa aowin 6 ucwe couam Page 2 of     6 REFERENCE INDUSTRY    DRAFT REV.

GOVERNMENT DOCUMENT DATED STANDARAD ISSUED DATE 10 CFR PART 50, APPENDIX B 2/19/75 ANSI-N4 5.2 1971 10 CFR PART 50.55(e) 10 CFR PART 50.55a ASME B&PV Code Specified in the Section III & SAR document of XI the respective plant Regulatory Guide 1.8 Rev.1 9/75 ANSI-N18.1 1971 Regulatory Guide 1.28 6/7/72 ANSI-N45.2 1971 Regulatory Guide 1.30 8/11/72l ANSI-N45.2.4 1972 Regulatory Guide 1.33 11/3/72 ANSI-N18.7 1972 ( Regulatory Guide 1.37' 3/16/73 ANSI-N45.2.1 1973 Regulatory Guide 1.38 3/16/73 ANSI-N45.2.2 1972 Regulatory Guide 1.39 Rev. 2 9/77 l ANSI-N45.2.3 1973 Regulatory Guide 1.54 6/73 ANSI-N101.4 1972 Regulatory Guide 1.58 8/73 ANSI-N45.2.6 1973 Regulatory Guide 1.64 Rev.1 2/75 ANSI-N45.2.11 1974 Regulatory Guide 1.68 11/73 Regulatory Guide 1.70.6 7/74 Regulatory Guide 1.70.11 12/74 Regulatory Guide 1.74 2/74 ANSI-N45.2.10 1973 Regulatory Guide 1.94 4/76 l ANSI-N45.2.5 1974 Regulatory Guide 1.116 6/76 l ANSI-N45.2.8 1975 l I Regulatory Guide 1.88 *Rev 2 10/76 ANSI-N45.2.9 1974 (j ANSI-N45.2.12 Draft 3 Rev. 4 2/74 l Regulatory Guide 1.123 Rev 1 7/77 ANSI-N45.2.13 1976 l

l TOPICAL QUALITY ASSURANCE REPORT BASELINE DOCUMENT MATRIX socaio powea s ec r cow" p 3 g 6 Florida Power & Light Company position regarding conflicting guidance and exceptions: ANSI N45.2.6-1973 s I The Florida Power & Light Company position on the scope of ANSI N45.2.6-1973 is that d personnel participating in testing who take data or make observations, where special training is not required to perform this function, need not be qualified in accordance with ANSI N45.2.6 but need only be trained to the extent necessary to perform the assigned function. For operational tests performed by operating personnel, FPL considers that training and qualification to the requirements of ANSI N18.1-1970 are equivalent to ANSI N45.2.6 and that qualification to ANSI N45.2.6 is unnecessary and redundent. Operational tests will be supervised by qualified testing personnel. Regulatory Guide 1.70.6 Regulatory Guide 1.70.6, Paragraph 17.1.12 states that the "PSAR should describe measures which assure that the error of calibration standards is less than the error of the production measuring and test equipment. For projects with limited work authorizations for construction l and for plants with operating licenses prior to May,1976, FPL has chosen an " equal to or better" requirement for calibration standards as stated in TQR 12.0. t 9 ANSI N45.9-1974 d ANSI N45.2.9-1974, Paragraph 5.6 requires that records be " classified for fire protection purposes as National Fire Protection Association Class I and as such should be afforded the equivalent protection of a NFPA Class A, four hour minimum rated facility." FPL will meet the requirements of the NFPA Code, utilizing those portions which indicate that insulated protection equipment with a rating below Class A may be used if certain building and occupancy conditions are met.

TOPICAL QUALITY ASSURANCE REPORT App::ndix C R ev. 3 O 5

 /    \

(' BASELINE DOCUMENT MATRIX DateSeptember 30.198C 40PIOa PowtR & UGHT COMPANY Page 4 of 6 ANSI N45.12, Draft 3. Rev. 4 ANSI N45.2.12, Paragraph 3.4.2, requires that " applicable elements of the Quality Assurance l Program shall be audited at least annually or at least once within the life of the activity, whichever is shorter." ANSI N18.7-1972, Paragraph 4.4 (endorsed by Regulatory Guide 1.33) states in part; " Audits of selected aspects of plant operation shall be performed with a frequency commensurate with their safety significance and in such a manner as to assure that an audit of safety-related activities is completed within a period of two years." FPL has chosen a two year cycle for auliiting elements of the intemal and on-site QA Program during the operation phase of plant life following initial fuel loading. FPL's position is that the two year cycle: (1) allows more indepth and meaningful audits in each regularly scheduled d area, (2) permits more audits of ongoing activities, and (3) in conjunction with the planning and scheduling requirements of TQR 18.0 provides for a comprehensive audit program. The audit frequency requirements of ANSI N45.2.12 will be followed during other plants phases. l In the case of suppliers, an annual evaluation of quality performance history shall be performed to determine reaudit requirements. Reaudit requirements for suppliers shall be based on the quality performance and the complexity and criticality of the equipment or service being procured. A facility evaluation (audit) will be performed at least every three years and l conducted in accordance with Quality Procedures and Instructions for supplier evaluation. l D ANSI N45.2.12, Paragraph 4.3.1 states: "A brief pre-audit conference shall be conducted at the audit site with cognizant organization management. The purpose of the conference shall be to confirm the audit scope, present the audit plan, introduce auditors, meet counterparts, discuss audit sequence and plans for the post-audit conference, and establish channels of communication." FPL will not require the pre-audit conference for audits of limited scope and of specific site activities conducted by the Construction and Operations Groups. This conference is omitted because the day-to-day contact of the auditors and plant management, s the awareness on the part of plant management that these audits are conducted without pre-audit conferences, and the limited scope of the audits meet the intent of a pre-audit conference.

TOPICAL QUALITY ASSURANCE REPORT APPtndix C g BASELINE DOCUMENT MATRIX D September 30. 198C sto io. ,owan a uc r cowan ANSI N45.2.13-1976 Section 8.2 of ANSI N45.2.13 identifies those nonconformances which shall be submitted to the s Purchaser. Florida Power & Light's (FPL) position regarding the nonconformances to be reported is as follows: Suppliers (including A-E's and Contractors) shall submit all nonconformances which consist of one or more of the following:

1) Technical or material requirements are violated.

m 2) Requirement in supplier documents which have been approved by the Purchaser is violated.

3) Nonconformances which would affect the quality of the item in regard to function of safety-related features. In cases where the supplier cannot make this determination, they shall be submitted to the Purchaser for evaluation.

This policy assures that all nonconformances affecting safety-related functions will be reviewed and approved by FPL. In all cases, the supplier's documentation on nonconformances is available for FPL's review. O ANSI N45.2.4-1972 ANSI N45.2.4-1972, Paragraph 2.5.2 requires that equipment be " suitably marked to indicate date of next required calibration". In lieu of marking equipment, FPL has chosen to control calibration of installed instrumentation and control equipment by maintaining records for each piece of equipment by instrument tag number (or equivalent) to show that established schedules and procedures for calibration have been followed. v

TOPICAL QUALITY ASSURANCE REPORT APP:ndix C BASELINE DOCUMENT MATRIX Da eseptember 30. 198C Q ,tonio. ,owia a uce cowam Page 6 of 6 ANSI N45.2.11-1974 ANSI N45.2.11-1974, Paragraph 11.4 requires that " audits shall include an evaluation of design quality assurance policies, practices, procedures and instructions . . . ." FPL's design quality assurance (and all other QA elements) policies, procedures and instructions are included in FPL's Quality Assurance Program documentation. The Quality Assurance Department evaluates all of this documentation in reviews performed during its development and revision. Accordingly, FPL does not require subsequent (and redundant) evaluations of these Quality Assurance Program policies, procedures and instructions during audits. FPL audits will include evaluations of the adequacy of the practices which are the implementation of these policies, procedures and instructions. ANSI N45.2.2-1972 ANSI N45.2.2-1972, Paragraph 7.4 requires that an inspection program be established for handling equipment and rigging, including methods for identifying acceptable and nonconforming it ems. In lieu of having a program of periodic, documented inspections cf rigging and handling i i equipment, FPL's practice is to have the individual user determine the equipment's acceptability prior-to each use. This prior-to-use inspection is exactly the same as that required during periodic inspections, and uses criteria identified in ANSI N45.2.2-1972, Paragraph 7.4. This practice also precludes the need for a system to indicate the acceptability of rigging and i handling equipment. Implementation of this prior-to-use inspection will be assured through periodic surveillances and audits performed by Quality Assurance and Quality Control. Cranes l are inspected on a periodic basis and will not be subjected to this prior-to-use inspection.

APPENDIX D TOPICAL QUALITY ASSURANCE REPORT Rev. GRAY, GREEN, AND ORANGE BOOK MATRIX TO QA PROCEDURES DateSegtembet 30. 198C

 \            stonioi cowin a uc r couram Page     1  of  8 FPL QUALITY ASSURANCE PROCEDURES GRAY BOOK - PRINCIPAL ELEMENTS                         NUMBER          TITLE

1. ANSI N45.2-1971 " Quality QP 2.2 Quality Assurance Program Assura sce Program Requirements thru 2.9 for Nuclear Power Plants"

2. ANSI N45.2.11 " Quality QP 3.1 Design, Review, Evaluation Assurance Requirements for thru 3.6 and Control the Design of Nuclear Power Plants

3. NRC Extracts from ANSI QP 4.1 Procurement Criteria N45.2.13 " Supplementary thru 4.4 Quality Assurance Requirements for Control of Procurement of QP 7.1 Receipt Inspection for Equipment Materials and Operating Plants services for Nuclear Power Plants" QP 7.2 Receipt Inspection for Plants Under Construction

4. ANSI N45.2.12 " Requirements QP 18.1 Auditing for Auditing of Quality & 18.2 Assurance Programs for Nuclear Power Plants"

5. ANSI N45.2.9 " Requirements QP 17.1 Retention of QA Records for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants" O 6. ANSI N45.2.10 " Quality Glossary Terms and Definitions Assurance Terms and Definitions" p - - -, y,e p. - . _.-,,., ,. ,v.-- p.,. ,- y .-,, , . , , y e - ,

APPENDIX D TOPICAL QUALITY ASSURANCE REPORT R ev. E GRAY, GREEN, AND ORANGE BOOK b MATRIX TO QA PROCEDURES DateSeptember 10. 19RC (' eto. oa nowt= a uc r co w my Page 2 of 8 FPL QUALITY ASSURANCE PRCCEDURES GREEN BOOK - PRINCIPAL ELEMENTS NUMBSR TITLE

1. Appendix B to 10 CFR Part 50 - Appendix E identifies and describes the

             " Quality Assurance Criteria for            quality procedures employed in support l

O Nuclear Power Plants and Fuel Reprocessing Plants" of 10 CFR 50, Appendix B , 2. Paragraph 50.55a, " Codes and QP 4.1 Procurement Criteria ! Standards", of 10 CFR Part 50, thru 4.4

             " Licensing of Production and Utili=ation Facilities" (ASME               QP 7.4            Source Surveillance of Boiler and Pressure Vessel                                    Off-Site Contractor's Code, Sec. III)                                               Facility l                                                         QP 10.5           Preoperational (Baseline)

Quality Audits Conduct of QA Department f 5 QP 18.1 Quality Audits L QP 18.2 Scheduling of QA Department Audit Activities

3. Regulatory Guide 1.28 (formerly QP 2.2 Quality Assurance Program Safety Guide 28) " Quality thru 2.9 Assurance Program Requirernents (Design and Construction)"

(ANSI N45.2)

4. Regulatory Guide 1.30 (formerly QP 10.2 Inspection Safety Guide 30) " Quality thru 10.5 Assurance Requirements for the Installation, Inspection and Q P 5.1 Instructions & Procedures Testing of Instrumentation and Electric Equipment" QP 12.1 Calibration and Control of (ANSI N45.2.4) Plant Inspection, Measuring

                                                                           & Test Equipment QP 12.2         Calibration Control of Installed Plt _nt Instrumentation
                                                                           & Control Equiprnent

                                                                                                                       )

1 TOPICAL QUALITY ASSURANCE REPORT R ev.

                         "        GRAY, GREEN, AND ORANGE BOOK MATRIX TO QA PROCEDURES                                  DateSeptenber 30,198C    ;

noaioa powta a uc r coman j Pge 3 of 8 l l FPL QUALITY ASSURANCE PROCEDURES GREEN BOOK - PRINCIPAL ELEMENTS NUMBER TITLE (Cont'd) I

5. Regulatory Guide 1.37 - Q P 2.3 Preparation & ReIrision of

      " Quality Assurance Requirements                                               Quality Procedures (QP's) for Cleaning of Fluid Systems and Associated Components of                   QP 2.4                          Preparation & Revision of Water-Cooled Nuclear Power                                                     Quality Instructions (QI's)

Plants" (ANSI N45.2.1) Q P 2.8 Cleanliness Control Methods Q P 2.7 Classification of Material

                                                                                     & Equipment QP 16.1~                        Corrective Action

6. Regulatory Guide 1.38 - QP 8.1 Identification & Control of

       " Quality Assurance Requirements                                              Material, Equipment & Services for Packing, Shipping, Receiving Storage & Handling of Items for                QP 13.1                         Handling, Storage & Shipping Water-Cooled Nuclear Power                                                     of Materials, Parts & Equipment Plants" (ANSI N45.2.2)                                                         During Plant Operation QP 13.2                         Handling, Storage & Shipping of Materials, Parts, &

Equipment During Plant Operation

7. ReguLtory Guide 1.39 - Q F 2.8 Cleanliness Control Methods

       " Housekeeping Requirements for Water-Cooled Nuclear                      QP 2.10                         Housekeeping Power Plants" (ANSI N45.2.3)

8. Regulatory Guide 1.54 - QP 9.1 Control of Special Processes

       " Quality Assurance Requirements                                              of Construction for Protective Coatings Applied to Water-Cooled Nuclear Power                 QP 9.2                          Control of Special Processes Plants" (ANSI N101.4)                                                         During Operating Phase

9. Regulatory Guide 1.58 - QF 2.5 Quality Assurance

       " Qualification of Nuclear                                                    Indoctrination & Training Power Plant Inspection, Examination & Testing                         Q P 2.9                         Qualification of QA Audit and Personnel" (ANSI N45.2.6)                                                     QC Inspection Personnel QP 9.1                          Control of Special Processes for Construction

APPENDIX D TOPICAL QUALITY ASSURANCE REPORT 0 R ev. E GRAY, GREEN, AND ORANGE EOOK N MATRIX TO QA PROCEDURES DateSeptabei: 30. 198C f t,Q AI0a POwin & OGMT COMPA8sv Page 4 of 8 FPL QUAIJTY ASSURANCE PROCEDURES GREEN BOOK - PRINCIPAL ELEMENTS NUMBER TITLE (Cont'd)

10. Regulatory Guide 1.74 - Glossary w " Quality Assurance Terms &

Definitions" (ANSI N45.2.10)

11. Draf t Standard N45.2.5-1974 - QP 9.1 Control of Special Processes

                     " Supplementary Quality                                    for Construction Assurance Requirements                     QF 11.1        Test Control- Construction for Installation, Inspection
                     & Testing of Structural                    QP 11.4        Test Program Control Steel During the Construction Phase of Nuclear Power Plants"             QP 18.1        Conduct of QA Department Quality Audits QF 10.2        Inspection of Plant Constructior.

12. Draft Standard N45.2.8-1974 - QP 8.1 Identification & Control of

                     " Supplementary Quality Assurance                         Items Prior to Installation Requirements for Installation, Inspection & Testing of                     QP 9.1         Control of Special Processes Mechanical & Systems for                                   for Construction Construction Phase of Nuclear Power Plants"                       QP 10.2        Inspection l                                                                & 10.5 QP 11.1        Test Control l                                                                thru 11.4 1

QP 12.1 Calibration & Control of Plant Inspection, Measuring, & Test Equipment QP 15.1 Control of Nonconforming Material, Parts or Components

13. Draf t Standard N45.2.9-1974 - QP 17.1 Retention of Quality Assurance "Requirernents for Collection, Records l

Storage & Maintenance of Quality Assurance Records for Nuclear Power Plants"

14. Draf t Standard N45.2.13-1974 - QP 4.1 Procurement Criteria l N " Quality Assurance Requirements thru 4.4 I s for Control of Procurement of

( V Items & Services for Nuclear QP 7.1 Control of Purchased l Power Plants" Material and Services

TOPICAL QUALITY ASSURANCE REPORT

                                                                                              ~
                       '                                                                        I I

y Rev.

• GRAY, GREEN, AND ORANGE BOOK etonion no.in 6 uc r coune Pme 5 of 8 FPL QUALITY PROCEDURE GREEN BOOK - PRINCIPAL ELEMENTS NUMBER TITLE (Cont'd) i

15. Draf t Regulatory Guide 1.70.xx - Requirements implemented as )

           " Additional Information -                             Chapter 17 of the SAR Quality Assurance During                               SAR Document Design & Construction" l

O O

APPENDIX D TOPICAL QUALITY ASSURANCE REPORT R ev. [ GRAY, GREEN, AND ORANGE BOOK j MATRIX TO QA PROCEDURES DateSeptember 30, 198C j atoaion noma a ucar cou..=, Page 6 of 8 FPL QUALITY PROCEDURE ORANGE BOOK - PRINCIPAL ELEMENTS NUMBER TITLE

1. Appendix B to 10 CFR Part 50 - Appendix E identifies and describes the

                  " Quality Assurance Criteria for            quality procedures ernployed in support of Nuclear Power Plants and Fuel               10 CFR 50, Appendix B.

O 2. Reprocessing Plants" Regulatory Guide 1.33 (formerly QP 2.2 Quality Assurance Program Safety Guide 33 - thru 2.7

                  " Quality Assurance Program Requirernents (Operation)"                  QP 5.1          Instructions, Procedures, and Drawings

3. 10 CFR Part 55 " Operators' Q P 2.5 Quality Assurance Licenses", and its Appendix A - Indoctrination and Training "Requalification Programs for Licensed Operators of Production and Utilization Facilities" v } 4. Regulatory Guide 1.8 (formerly Safety Guide 8) " Personnel Q P 2.5 Quality Assurance Indoctrienation and Training Selection and Training" (ANSI N18.1)

5. Regulator Guide 1.58 - QP 2.5 Quality Assurance "Ot 6tRation of Nuclear Indoctrination and Training Po. er Inspection, Examination, and Testing Personnel" l 6. Paragraph 50.55a, " Codes and QP 10.3 Inspection Standards", of 10 CFR Part 50, thru 10.6

                  " Licensing of Production and l                  Utilization Facilities" (ASME               QP 4.1           Control of Requisitions &

j Boiler and Pressure Vessel Submittal of Purchase Orders Code Section XI,1971 Rules for ! Inservice Inspection of Nuclear QF 7.1 Control of Purchased Material l Reactor Coolant Systems) & Services QP 7.2 Receipt Inspection QP 8.1 Identification & Control of Items Prior Installation QP 11.2 Test Control A thru 11.4 i ( QP 12.1 Calibration

                                                              & 12.2

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TOPICAL QUALITY ASSURANCE REPORT

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R ev. GRAY, GREEN, AND ORANGE BOOK MATRIX TO QA PRCCEDURES DateSep_ggbet 30. 198C 8LoniOA POWE A 6 LIGwf ConsP4mv Dage 7 of g FPL QUALITY ASSURANCE PROCEDURES ORANGE BOOK - PRINCIPAL ELEMENTS NUMBER TITLE (Cont'd)

7. Regulatory Guide 1.30 - QP 10.2 Inspection

                  " Quality Assurance Require-                  thru 10.6 N                ments for the Installation, Inspection, and Tes:ing of Instrumentation and Electric Equipment" (ANSI N45.2.4)

8. Regulatory Guide 1.37 - Glossary

                  " Quality Assurance Requrements for Cleaning of Fluid Systems                 QP 2.2       Revision of the Topical and Associated Components of                               Quality Assurance Report Water-Cooled Nuclear Power Plants" (ANSI N45.2.1)                        Q P 2.3      Prepart. tion and Revision of x

Quality Procedures (QP's) v ) Q F 2.4 Preparation and Revision of Quality Instructions (QI's) Q P 2.7 Classification of Material and Equipment QP 16.1 Corrective Action

9. Regulatory Guide 1.38 - QP 7.1 Control of Purchased Material,

[ Quality Assurance Requirements Equipment, and Services for Packaging, Shipping, Re-ceiving, Storage, and Handling QP 7.2 Receipt Inspection i n of Items for Water-Cooled ! / Nuclear Power Plants" (ANSI QP 8.1 Identification & Control of

 \                N45.2.2)                                                   Items prior to Installation

, QP 13.1 Handling, Storage, & Shipping l of Material, Parts, and Componments at the Site During Construction QP 13.2 Handling, Storage & Shipping of Material, Parts & Equipment During Plant Operation I ['N

  \

10. Regulatory Guide 1.39 -

                  " Housekeeping Requirements Q P 2.8      Cleanliness Control Methods for Water-Cooled Nuclear Power Plants" (ANSI N45.2.3) 1 1

APPENDIX D TOPICAL QUALITY ASSURANCE REPORT

                              ~

R n. E GRAY, GREEN, AND ORANGE BOOK MATRIX TO QA PROCEDURES DateSeptegtbgr 30. 108C eteniaa owan a ocar cowaw Page 8 of 8 FPL QUALITY ASSURANCE PROCEDURES ORANGE BOOK - PRINCIPAL ELEMENTS NUMBER TITLE (Cont'd)

11. Regulatory Guide 1.64 - QP 3.1 Design Review, Evaluation

                  " Quality Assurance Require-                             and Control ments for the Design of Nuclear Power Plants"                       QP 3.2       Identification & Control of (ANSI N45.2.11)                                          Design Interfaces

12. Draf t Regulatory Guide 1.63 - QP 11.3 Test Control - Preoperational "Preoperational and Initial and Startup Tests Startup Test Programs for Water-Cooled Power Reactors"

13. Extracts from ANSI N45.2.8 - QP 8.1 Identification and Control of

                  " Supplementary Quality                                  Items Prior to Installation Assurance Requirements for Installation, Inspection,                                Control of Special Processes

{ and Testing of Mechanical Q F 9.1 for Construction Equipment and Systems for the Construction Phase of Nuclear QP 10.3 Inspection of Maintenance Power Plants" Activities - Operational Phase QP 11.1 Test Control - Construction l QF 11.3 Test Control - Preoperational and Startup Tests QP 11.4 Test Program Control

      'i J

V l 3 i

TOPICAL QUALITY ASSURANCE REPORT App:ndix E 3 E LIST OF CORPORATE QUALITY m a ASSURANCE PROCEDURES DateSeptember 30,198C v stoaioa rowsa 6 ucar cowea=v Page 1 of 9 QP NUMBER / TITLE SECTION DESCRIPTION 1.1 CANCELLED O 2.1 CANCELLED (Terms and Definitions contained in the QA Manual Glossary) 2.2 REVISION OF THE TOPICAL QUALITY Provides instructions for the revision of ASSURANCE MANUAL the Florida Power & Light Company Topical Quality Assurance Report (FPLTQAR) 2.3 PREPARATION AND REVISION Describes the instructions and methods QUALITY PROCEDURES used for establishing, preparing, issuing, i Ci revising and controlling Qu:111ty Procedures employed in supporting quality requirements. i 2.4 PREPARATION AND REVISION OF Provides the responsibilities, guidelines QU ALITY INSTRUCTIONS and methods used for developing and revising Quality Instructions, based upon QP's, that inv' .ve quality activities within a department or organization and are unique to that activity. l 2.5 s QUAIITY ASSURANCE INDOCTRINATION Describes the requirements for the AND TRAINING indoctrination and training of personnel who perform, or are responsible for, activities that affect quality. 2.7 CLASSIFICATION OF MATERIAL AND Defines five different quality groups and EQUIPMENT assigns responsibilities for the classification of material, systems, and structures within these groups. O

TOPICAL QUALITY ASSURANCE REPORT App;ndix E 3 35 LIST OF CORPORATE QUALITY

 /'m t
        \

ASSURANCE PROCEDURES DateSeptember 30.198C

                                                                                                 '~

stonion Powan 6 ucur coupac Page 2 of g QP NUMBER / TITLE SECTION DESCRIPTION 2.8 CLEANLINESS CONTROL METHODS Provides criteria for securing good house-n keeping. Assigns responsibilities for assuring that the cleanliness of material, systems and structures. 2.9 QUALIFICATION OF QA AUDIT AND QC Describes the personnes qualifications that INSPECTION PERSONNEL are required to assure that competent QC inspectors and QA auditors perform these respective functions. 2.10 HOUSEKEEPING Describes the responsibilities and controls OPERATING PLANTS for housekeeping at nuclear power plants in operations. 2.11 V HOUSEKEEPING Describes the responsibilities and controls CONSTRUCTION PLANTS for housekeeping at nuclear power plants during construction. 2.12 FPL QA PROGRAM APPLICABILITY Identifies the applicability of the FPL FOR FIRE PROTECTION SYSTEMS Quality Assurance Program for Fire Protection Systerns. 3.1 EVALUATION OF CONTRACTOR Establishes the methods to evaluate the DESIGN design and analysis of electrical,

       %                                                     mechanical, structural and nuclear related
     - )                                                    systerns and components. It further establishes the documentation of the control and evaluation to be recorded and maintained.

3.2 IDENTIFICATION AND CONTROL OF Describes measures employed for DESIGN INTERFACES identifying and controlling design interfaces, changes in design interfaces, and modifications that affect documents, pI 3.4

 ,V       PLANT CHANGES AND MODIFICATIONS FOR               Establishes measures for controlling OPERATING PLANTS                                  design changes or me,difications in operating nuclear power plants.

TOPICAL QUALITY ASSURANCE REPORT APP:ndix E_ Rs. 3

                      'l j {-       LIST OF CORPORATE QUALITY ionio 6 na uc re   ..

Page 3 of 9 QP NUMBER / TITLE SECTION DESCRIPTION 3.S DESIGN CONTROL AT THE CONSTRUCTION Defines the responsibilities and methods SITE employed for the initiation, review, evaluation, approval and disposition of O' field initiated design changes and miscellaneous design documents such as field sketches and isometrics. 3.6 CONTROL OF FPL ORIGINATED Covers the preparation, review, and DESIGN approval of design input documents, design analysis specifications, and design verification for safety-related design work originated by FPL. 4.1 CONTROL OF REQUIS!TIONS AND Provides a system to assure that the A THE ISSUANCE OF PURCHASE ORDERS appropriate technical and quality require-FOR SPARE PARTS, REPLACEMENT ments are placed upon suppliers who ITEMS AND SERVICES provide materials, equipment, and services for operating nuclear plants. 4.2 ( EVALUATION OF CONTRACTOR'S BIDS Provides the basic evaluation factors for TECHNICAL technical evaluations of contractor's bids to supply material, equipment, or services to FPL or FPL's Architect-Engineer. 4.3 CANCELLED 4.4 s REVIEW OF REQUISITION OF PURCHASING Applies to all FPL issued purchase orders AGENT FOR ITEMS AND SERVICES OTHER and contracts relating to a nuclear power THAN SPARE PARTS plant, except those originated by operating plant personnel. 5.1 OPERATING PLANT PROCEDURES Describes measures which er2ure that instructions and procedure', used in Operating plants are ide .tified, prepared, reviewed, approved, iwed and revised in accordance with regulatory and FPL requirements.

TOPICAL QUALITY ASSURANCE REPORT APP:ndix E_ h LIST OF CORPORATE QUALITY ASSURANCE PROCEDURES DateSeptembe,r 30. 198C loa 0A powtm & Licnf coupasiv Page 4 of 9 t JP NUMBER / TITLE SECTION DESCRIPTION 6.1 CONTROL OF CONSTRUCTION PROJECT Defines responsibilities and methods for CONTRACTOR DRAWINGS, SPECIFICATIONS the control and issue of contractor AND PROCEDURES drawings, specifications and procedures to [my} be used during the construction phase of nuclear power plant. 6.2 CONTROL OF DOCUMENTS ISSUED BY Instructions are provided for controlling FLORIDA POWER & LIGHT COMPANY documents issued by FPL which prescribe actietties affecting the quality of safety-related items. 6.3 CANCELLED o 6.4 FPL DRAWING CONTROL Describes the tneans to prepare, control, revise and issue engineering drawings, make changes to vendor drawings, and to maintain a master drawing file. 6.S PTP DRAWING CONTROLS Provides instructions governing the review, approval, release, distribution, and revisions of drawings of Turkey Point Plant nuclear safety-related structures, systems, and cornponents. 7.1 p RECEIPT INSPECTION OF NUCLEAR Provides instructions for receipt i SAFETY-RELATED MATERIALS, PARTS inspection of materials, parts and l AND COMPONENTS FOR OPERATING PLANTS cornponents which have been obtained for use in nuclear safety applications at the operating plant site. 7.2 RECEIVING, INSPECTION AND STORAGE Provides the quality requirements l OF NUCLEAR SAFETY-RELATED MATERIAL, for receiving, receipt inspection and j PARTS AND COMPONENTS FOR PLANTS disposition of nuclear safety related ! UNDER CONSTRUCTION material, parts, and cornponents received at the plant site or designated off-site storage facility.

TOPICAL QUALITY ASSURANCE REPORT APPCndix E_ m R ev. 3 3: LIST OF CORPORATE QUALITY (Oj) s 8 LORICA Powtm & UCMT CouPAmy ASSURANCE PROCEDURES DateSeptember 30,198C Page 5 of 9 QP NUMBER / TITLE SECTION DESCRIPTION 7.3 CANCELLED 7.4 EVALUATION OF SUPPLIERS OF SAFETY Provides standards, measures, and guide-RELATED ITEMS OR SERVICES lines for the evaluation of QP Programs of contractors or suppliers supplying items or services. 7.6 ACCEPTANCE OF ITEMS & SERVICES Describes the responsibilities and requirements for accepting nuclear safety-related items on services that are being procured for nuclear power plants. R W AND DISPOSITION OF Describes the responsibilities and SUPPLIER DEVIATION NOTICE requirements for the review and disposition of nonconformances identified within a supplier's facility which have resulted or will result in an item which does not fully comply with the FPL procurement document quality and technical requirements. 8.1 IDENTIFICATION & CONTROL OF Delineates measures for assuring trace-MATERIALS, PARTS AND COMPONENTS ability, identification and control of AT THE PLANT SITE items from the time they are received through usage at operating plants. d 8.2 IDENTIFICATION & CONTROL OF Provides guidance for assuring that MATERIALS, PARTS AND COMPONENTS contractors provide for identifying and AT THE SITE DURING CONSTRUCTION controlling materials, parts, and components, including traceability, from receipt through usage during all phases of construction. 9.1 CONTROL OF SPECIAL PROCESSES Delineates the responsibilities of organ-fs CONSTRUCTION izations and personnel, and the control and

    \                                                        documentation of special processes that

( are applied to safety-related items.

TOPICAL QUALITY ASSURANCE REPORT Apptndix E 3 E LIST OF CORPORATE QUALITY Y O

 ,                                                 ASSURANCE PROCEDURES                      DateSeptember 30. 1980 840R104 *CwtA & UCMf COMPANY Page         6 of         9 QP NUMBER / TITLE                                    SECTION DESCRIPTION 9.2 CONTROL OF SPECIAL PROCESSES DURING                  Describes measures to assure adequate OPERATING PHASE                                      control over special processes applied to

[s safety-related items during the operating phase of nuclear power plants. 10.1 MOVED TO 7.2 10.2 INSPECTION OF PLANT CONSTRUCTION Defines the responsibilities and requirements for the planning, performance and documentation of inspection. 10.3 INSPECTION AND SURVEILLANCE OF Delineates responsibilities and MAINTENANCE ACTIVITIES, OPERATIONS requirements for the inspection and

 \        AND FUEL HANDLING                                    surveillance of safety-related plant maintenance activities, operation of safety-related systems, and fual handling activities.

10.4 CANCELLED 10.5 PREOPERATIONAL (BASELINE) EXAMINATION Describes the means for assuring that the physical properties and characteristics of pressure retaining components are tested and measured; and, the recorded, analyzed I and evaluated results (baseline data) are retained for the life of the plant. I 10.6 INSERVICE INSPECTION (ISI) Describes the means for assurng that the physical characteristics of safety-related items and systems are inspected in accordance with the provisions of the ASME and that the B&PV Code-Section XI, results are documented at specified times during the operating life of the p plant. ( v

                                                     , - , -                --e-, y p,--,n--      ,- w.---       +-e v   -+

TOPICAL QUALITY ASSURANCE REPORT APPnndix E

                          'yh LIST OF CORPORATE QUALITY ASSURANCE PROCEDURES                 DateSentaber 10. 19RC no io. ,owna a ocar cowan Page      7 of     9 QP NUMBER / TITLE                            SECTION DESCRIPTION 11.1 TEST CONTROL - CONSTRUCTION                  Establishes measures to assure that S'                                               contractor testing of safety-related material during the plant construction phase is controlled, accomplished, and documented.

11.2 TEST CONTROL - OPERATION A description of the procedures and practices employed by FPL to control testing of plant functions and material that are within the scope of the QA Program during the plant operational phase. 11.3 O TEST CONTROL - PREOPERATIONAL AND START-UP TESTS Defines the procedures and practices employed to demonstrate the capabilities of a nuclear plant to satisfy safety-related performance specifications. l l 11.4 CONTROL PROGRAM Defines the measures for control of proof test prior to installation, construction I tests, preoperational tests, startup tests, ! operational tests and retests following repairs, replacements or modifications for nuclear safety-related systems, structures, and components. 12.1 CALIBRATION AND CONTROL OF Delineates the responsibilities for MEASURING AND TEST EQUIPMENT implementing the described program for maintenance, calibration and control of l rueasuring and test equipment (M&TE). 12.2 CALIBRATION CONTROL OF INSTALLED Describes the calibration program, PLANT INSTRUMENTATION AND CONTROL delineates responsibilities, and EQUIPMENT establishes procedures for control over the calibration of installed instrumentation and plant control equipment.

TOPICAL QUALITY ASSURANCE REPORT APP:;ndix E Y"E LIST OF CORPORATE QUALITY 3 ASSURANCE PROCEDURES DateSeptember 30,198C

   ,     8toniOA PCwin & LIGHf CouPamy Page       3 of     9 QP NUMBER / TITLE                                 SECTION DESCRIPTION 13.1 HANDLING, STORAGE AND SHIPPING OF                 Establishes responsibilities and procedures
     ,)   MATERIAL, PARTS AND COMPONENTS AT THE SITE DURING CONSTRUCTION to assure that measures are employed by contractors to: (1) control the handling, s  f                                                    shipping and storage of material; (2) protect the quality of material by using proper handling, shipping, and storage techniques; (3) effectively control the disposition of discrepant items.

13.2 HANDLING, STORAGE AND SHIPPING OF Specifies the respective responsibilities of MATERIAL, PARTS AND EQUIPMENT DURING FPL personnel and the measures employed PLANT OPERATION for controlling the handling, shipping and storage of materials during the plant's operational phase. w

       )  13.3
   %)     CONTROL OF RESERVED CENTRALLY STORED             Provides the requirements for the issuance ELECTRICAL CABLE                                 and controls of centrally stored electrical cable for use in all operating nuclear power plants.

14.1 INSPECTION, TEST, AND OPERATING Specifies the respective responsibilities STATUS DURING PLANT OPERATION of FPL personnel and the measures ( employed for identifying the status l (Inspection-Test-Operation) of plant I structures, systems and components. bNTROL OF NONCONFORMING MATERIAL, Spe;ifies the responsibilities of FPL PARTS, OR COMPONENTS PLANTS UNDER de. artments and the process for CONSTRUCTION e.ercising control over material, l I structures, or activities that do not conform to specifications so that inadvertant use or installation does not occur. 15.2 l CONTROL OF CONFORMING MATERIAL, Defines the objectives and responsibilities PARTS, OR COMPONENTS - OPERATING for centrolling nonconforming items or em \ PLANT services, in order to prevent their l inadvertent use, installation or application to operating nuclear power plants. 1 l l l

TOPICAL QUALITY ASSURANCE REPORT APP:ndix E_ Tl y Rm 3 LIST OF CORPORATE QUALITY

     )                             *
        ,(Q A10A POwt A & UGMT COMPANY ASSURANCE PROCEDURES                 DateSegggmber 30.198C Page      9 of      9 QP NUMBER / TITLE                                    SECTION DESCRIPTION 16.1 CORRECTIVE ACTION FOR DEPARTMENT                     Establishes the respective responsibilities AUDITS                                               of FPL personnel and the procedure for assuring that conditions identified by the NRC or by the FPL QA Department as being adverse to quality, are corrected.

16.2 CANCELLED (Combined with 16.1) 16.+ EVALUATING AND REPORTING OF Specifies the raeasures and responsibilities SUBSTANTIAL SAFETY HAZARDS IN within Florida Power & Light to insure ACCORDANCE WITH 10 CFR PART 21 compliance to 10 CFR Part 21. 16.6

     .h REPORTING OF 10 CFR 50.55(e)                         Specifies measures and responsibilities DEFICIENCIES                                         for the identification and reporting of 10 CFR 50.55(e) type deficiencies to the NRC during the plant construction phase.

17.1 l THE COLLECTION AND STORAGE OF Identifies records and documents required l QUALITY ASSURANCE RECORDS FOR to substantiate quality; and, describes NUCLEAR POWER PLANTS measures employed for their maintenance, retention and retrieval. 18.1 CONDUCT OF QUALITY ASSURANCE Provides instructions for conducting DEPARTMENT QUALITY AUDITS audits of FPL Quality Assurance Program I O 18.2 activities. SCHEDULING OF QUALITY ASSURANCE Provides the responsibilities and DEPARTMENT AUDIT ACTIVITIES instructions for planning and scheduling audits to be conducted by the FPL Quality Assurance Department. 1 V

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