ML20203F158

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Rev 25 to Illnois Power Nuclear Program Quality Assurance Manual
ML20203F158
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/12/1998
From:
ILLINOIS POWER CO.
To:
Shared Package
ML20203F156 List:
References
NUDOCS 9802270219
Download: ML20203F158 (170)
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Text

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL

, m AUTHORIZATION The purpose of the Illinois Power Nuclear Quality Assurance Program is to provide for safe and reliable operation of the Clinton Power Station with planned and systematic actions necessary to provide adequate confidence that structures, systems, or components will perform satisf actory in service The quality assurance program has been designed to ensure the accomplishment of this objective and function in preventing or mitigating the consequences of postulated accidents which could cause undue risk to the health and safety of the public.

The quality assurance program described in this manual reflects '

Illinois Power's policy and is applicable to all personnel and activities affecting the safe operation of the Clinton Power Station. This manual has been prepared to document the systems in effect for assuring that operation of the Clinton Power Station meet or exceed quality requirements of applicable specifications, rules, and governing regulations.

The Manager-Quality Assura: :e shall have complete authority and responsibility to promulgate the quality assurance program, to ensure its implementation, and to verify compliance there with, without undue regard for cost and schedule. This includes the initiation of stop work action for activities which are not in i compliance with the requirements established by the Illinois Power V Nuclear Quality Assurance Program or when conditions exist which prevent the attainment of the required quality.

It is realized that quality can only be achieved by those personnel who perform the work. Therefore, each and every employee must conscioualy implement the requirements of the Illinois Power Nuclear Quality Assurance Program as the requirements apply to the activities being performed.

Furthermore, it is the responsibility of all departments and personnel to comply with the requirements of the Illinois Power Nuclear Program Quality Assurance manual to achieve full implementation and maintenance of this policy.

The effective date of revisions to this manual shall be thirty (30) calendar days rom the date o distribution to allow for procedure changes and training, bG V'ce Presiddnt l

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Page.i_ REVISION 26

i lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASS'IRANCE MANUAL l i

O QUALITY ASSURANCE PROGRAM i

CONCURRENCE AUTHORIZATION

! The Illinois Power Nuclear Program Quality Assurance Program (QAP) applies to l .

j every member of the company performing safety / quality related work at Clinton Power Station. Specific responsibilities shall be assigned by lilinois Power j management and supervisioil, consistent with the requirements described in the Illinois Power Nuclear Program Quality Assurance Manual. The main responsibility l for the Quality Assurance Program is carried out by IP departments in recognition of the QAP responsibilities, Illinois Power Nuclear Program Quality l Assurance Manual Revision 26 is given the followina Departmental Concurrence Authorizations:

l GLitL c tt W.D. Romberg, $4 nager Gl.. Baker, M41ager Clinton Power Sta^lon Quality Assurance

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c rfRw, Manager .@Igley, Manager /

J.F.

NuclearP'alcha(ining Tra & Support Nuclear Station Engi eris(g l A H W, K.F. John 6n, Manager f.F. Pty4Irds, Manager Purchasing and Material Control Nuclear Safety and Performance improvement i

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Page_ii REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL TABLE OF CONTENTS Chapter Chapter -

Number liALq .l

. . . .i 3 i Authorization

""" ' U 11 Concurrence Authorization iii Table of Contents iv Introduction 1 Organization 2 Quality Assuranca. Program

.3 Design Control 4 Procurement Document Control 5 Instructions, Procedures & Drawings 6 Document Control 0'

, 7 Control of Purchased Material, Equipment and Services 8 Identification and Control of Materials, Parts and Components 9 Control of Special Processes 10 Inspection 11 Test Control 12 Control of Measuring and Test Equipment 13 Handling, Storage and Shipping 14 Inspection, Test and Operating Status 15 Nonconforming Materials, Parts or Components 16 Corrective Action 17 Quality Assurance Records 18 Audits Appendix A Glossary of Terms Appendix B Supplemental Application - IP Nuclear Quality Assurance Program Page lii REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL INTRODUCTION O

V INTRODUCTION Illinois Power Company (IP), cs owner of Clinton Power l Station (CPS), has Lltimate responsibility for the quality assurance program which is applied to CPS. The program is designed to meet the requirements of Title 10 of the Code of Federal Regulations (CFR), Part 50, Appendix B, " Quality Assurt.nce Criteria for Nuclear Power Plants;" 10CFR , Part 71, Subpart H, " Quality Assurance for Packaging and Transportation of Radioactive Material" (with the exception of design, fabrication, casembly, and testing of packaging); and the American National Standard ANSI N18.7 (1976), " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants".

The IP Nuclear Quality Assurance Program applies to those activities associated with or affecting the ability of the plant's structures, systems, and components to function in preventing, or mitigating the consequences of postulated l accidents which could cause undue risk to the health and safety of the public. These activities include operating, maintaining, repairing, refueling, modifying, and other associated activities such as radiological environmental monitoring, radioactive material packaging and shipping, fire protection, and security programs. The structures, systems, and components to which the i activities and programs apply are delineated in Table 3.2-1 of V the Updated Safety Analysis Report (USAR).

This manual is arrange in eighteen chapters which correspond with the eighteen :riteria contained in 10CFR50 Appendix B and 10CFR71, Subpart H. Each chapter is broken down l into three main sections which describe the purpose and scope of that chapter, a description of the quality program, and the division of responsibilities. The Quality Assurance l organization approves the distribution and is responsible for the maintenance of this manual in accordance with approved departmental procedures.

Appendix A of this manual is a glossary of terms applicable to the Illinois Power Nuclear Quality Assurance Program.

Appendix B of this manual details the scope of its appaication with respect to activities associated with Fire Protection, Security, Envircnmental, Radwaste/ Augmented-D Systems and Packaging and Transportation of Radioactive Material.

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ILLINOIS POWCR NUCLEAR PROGRAM QUALITY A,.3URANCE MANUAL

/~'i CHAPTER V a g 1

b d7sil 8 ORGANIZATION 1.1 PURPOSE / SCOPE The purpose of this chapter is to describe the organizational l structure, functional responsibilities and levels of authority concerning the periarmance of activities which affect the safety-related functions of structures, systems, or components for the Clinton Power Station.

1.2 DESCRIPTION

1.2.1 Organizational structuring and functional l responsibility assignments are based on recognit!on of quality assurance as an inter-disciplinary function with quality-related activities being performed by many organisational components and individuals from top-level management to individual workers.

1.2.2 The authorities and responsibilities of persons andl organizations performing quality-related activities are O established, assigned and documented.

organizations assigned quality assurance functions are given Those persons and l V

appropriato and sufficient authority and organizational freedom from cost and scheduling considerations to: identify quality problems; recommend solutions; verify implementation of the solutions; and control processing, delivery, installation, or j utilization of nonconforming items until proper dispositioning has occurred.

1.2.3 The orgatilzational structure and functional responsibility assignments are such that: (1) attainment of quality objectives is by individuals assigned responsibility for specifying quality req >ireuents or performing work to specifications; and (2) personael performing the quality assurance functions of program assessment, inspection and audits have direct access to responsible management, and organizational freedom, including sufficient independence from cost and schedule when opposed to safety considerations.

1.2.4 Activities affecting s;fety related functions (job duties and responsibilities) have been identified.

Effectiveness of the program is assured through inspections, program assessments, audits and by the authority / responsibility of individuals performing these activities to stop specific work activities where it appears that quality may be jeopardized.The p Manager - Quality Assurance has the authority to initiate a Stop

(") Work Action. The Upon the initiation of a stop Work Action, the Manager - Clinton Power St ation has the authority to place the plant in a saf t. and stable condition.

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL

' chapter 1 1.2.5 Inspection personne) are provided with proceduren and instructions prior to performing inspection operations. (during plant operations emergencica, inopectiono may be performed under the direction of the duty shift supervieor .) To further aanure that inapections are done in a timely manner, upecific inspection point.n are identified in work docenents with provisions for notification of inspection, witness, and hold points. ,, l Orqapizational Interfqcfen 1.2.6 Activities affecting the quality of safety-related nyotems, otructures and components are considered quality anourance program activities and are performed cy, or under the cognizance of various IP organizations. Any department may perform these quality assurance activitien provided that pornonnel are adequately trained, qualified / certified, and these work activitica are performed in accordance with approved procedures and instructions. Problems associated with tueeting the requiremento of the Quality Assurance Program, or disagreements and/or disputes shall be brought to the attention of appropriate levels of management, including the Senior Vice President - Energy supply au necessary to obtain resolution.

1.2.7 Work may be delegated to qualified outside T organizations by contract fo: ouch activities ao design, special processen, innpections, etc. Selected work may be delegated to qualified outside organizations by Nuclear Program departmencs .

The responsibility for exercising engineering control resto with Nuclear Station Engineering, and operational controls with CPS Plant St.a f f . Prior to initiation of work, the qualified ind tvidual (a) cc organizational elements within IP have their responsibilitien identified for the control and quality .f delegated work.

1.3 REBEQ11SIBILITIES Thio section describes the organizational structure and responoibilities within IP for managing and implementing the quality asturance program for the operation of CPS. l 1.3.1 Senior Vice President - Energy Supply M

The Senior Vice President -

Energy Supply haa the overall responsibility for engineering, design, procurement, modification, testing, operation and quality assurance at CPS.

Execution of these responsibilities is delegated to a Vice President.

1.3.2 Vice President l The Vice President is responsible for maintaining and assessing

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the overall effectiveness of the Quality Assurance Program. The Vice President is responsible for assuring that the authority and independence of personnel performing quality assurance functions are auch that they can effectively assure the conformance to j Page 2 of 5 REVISION 26 l

ILLINOIS POWER NUCLEAR PROGRAM "" " " " "

QUALITY ASSURANCE MANUAL Chapter 1 O

d quality requirements and are suf ficiently independent from cost and scheduling when opposed to safety considerations.

1.3.3 Manager - Clinton Power Station l The Manager - Clinton Power Station reports to the Vice President and is responsible for the safe, reliable and efficient, operation of the Clinton Power Station in accordance with the operating license. This includes ensuring that the IP Nuclear Quality Assurance Program, as described in subsequent sections of this manual, is incorporated in plant procedures and implemented by the Clinton Power Station organization.

1.3.4 Manager - Nuclear Station Engineering l The Manager - Nuclear Station Engineering reports to the Vice President and is responsible for the development, direction and overall coordination of power plant engineering activities performed by the Nuclear Station Engineering Department (NSED) for the Clinton Power Station. These responsibilities includes coordination of all interface with the Authorized Inspection Agency (AIA), and provisions for the establishment of Authorized Nuclear Inspector (ANI) hold or witness points and access to l facilities and records. The Manager -

NSED ensures that these q activities are performed in accordance with the requirements of g the IP Nuclear Quality Assurance Program.

1.3.5 Manager - Nuclear Training & Support l The Manager - Nuclear Training & Support reports to the Vice l President and is responsible for providing direction of nuclear training, emergency planning, fitness for duty, material support, l receiving, warehousing, records management, document control, safety, and for corporate and 1:lant integration in these functional support disciplines. The lanager - Nuclear Training &

Support ensures that these activities are performed in accordance with the requirements of the IP Nuclear Quality Assurance Program.

1.3.6 Nuclear Review and Audit Group l The Nuclear Review and Audit Group (NRAG) reports to the Vice President and is responsible for the indepentent safety review function. The NRAG functions in accordance with a written charter which delineates committee composition, responsibility and authority, subjects to be review.d, reporting requirements and administrative controls under which the group operates.

1.3.7 Facility Review Group l The Facility Review Group (FRG) is an on-site committee whose l (b function is to advise the Manager - Clinton Power Station on matters related to nuclear dafety.

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ILLINOIS POWER NUCLEAR PROGRAM 0 i

QUALITY ASSURANCE MANUAL . -

Chapter 1 O

Q 1.3.0 Manager - Quality Assurance l The Manager - Quality Assurance reports to the Vice President and l 10 responsible for IP's overall Nuclear Quality Assurance Program. The Manager - Quality Assurance directs the Quality Assurance activities related to the design, procurement, maintenance, modification, and operation of the Cliiiton Power Station. The Manager - Quality Assurance interfaces with the l Nuclear Regulatory Commission, and the Authorized Inspection Agency for the Quality Assurance Program. The Manager - Quality Assurance or the designated alternate has the responsibility and authority to stop unsatisfactory work during plant operation, as well as during plant modification, maintenance and in-service innpection periods, provided the health and safety of the public, or impact on capability to safely operate or shut down the plant are not adveracly affected. l 1.3.9 Manager-Nuclear Safety & Performance Improvement (NSPI)

The Manager-Nuclear Safety & Performance Improvement Department reports to the Vice President and is responsible to ensure continued improvements ir the plant's safety performance while contjauing to safely operate the clinton Power Station. This coordination, and department in dedicated to the development,

( monitoring of site-wide improvements to elevate identified programmatic weaknesses to management for timely corrective action. The department maintains the operating licenses and managen the Updated Safety Analysis keport (USAR), '

permito, manages the Environmental Report (ER) for continued programmatic compliance, and administers a tracking program for 10CFR21 items.

The Manager-NSPI ensures that the Independent safety Engineering Group (ISEG) review function is maintained separate and independent from lina management.

The Manager-NSPI ensures that the corrective Action Group implements a Corrective Action Program (CAP) to assure conditions adverse to plant safety and/or quality are identified, evaluated, reported, corrected, reviewed and trended.

The Manager-NSPI ensures that these activities are performed in accordance with the requirements of the IP Nuclear Quality Assurance Program.

1.3.10 Manager - Purchasing and Material Control l The Manager - Purchasing and Material Centrol reports to the Senior Vice President of the Support Services Business Group

(. qualified

' (Headquarters) and is responsible for selecting suppliers, for preparing and issuing purchase orders and ensuring l that they include necessary technical, quality and commercial terms and conditions, and that appropriate reviews, are Page 4 of 5 REVISION 26 l

lLLINOIS POWER NUCLEAR PROGRAM . .

{

QUALITY ASSURANCE MANUAL i.., ;. / d d

.. chapter 1 l accomplished prior to release of a purchase order. The Manager -

, Purchasing and Material control ensures that these activities are i

! performed in accordance with the requirements of the IP Nuclear Quality Assurance Program.

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1 Page 5 of 5 REVISION 26 l.

ILLINOIS POWER NUCLl!W PROGn:AM

, QUALITY ASSURANCn MANUAL . .

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QUALITY AMW/jfG *iih4 i l

t 2.1 PURPOSE / SCOPE The purpose of this chapter is to define the IP Nuclear Quality l Assurance Program applies to those activities such as design,

, procurement, fabrication, installation, modification, maintenance, repair, refueling, operation, inspection, and tests related to those systems, structures, and components as

, identified by the letter "B" or "Ha in the Quality Assurance Requiremento column in USAR Table 3.2-1. This program shall be E documented by policies, procedures, or instructions.

2.2 DESCRIPTION

f 2.2.1 Illinoio Power Company's Nuclear Quality Assurance ,

Program comprises all those planned and systematic actions

necessary to provide adequate confidence that a Clinton Power Station- atructure, system, or component will perform antiofactorily in service. Quality assurance includes quality
control which comprises the verification of those physical
characteristico of material, atructure, component, or system which provide a means to control the quality of the material, structure, component, or ayatem to predetermined requirements.

l 2.2.2 Illinois Power Company's Nuclear Quality Assurance l Program is based upon 10CFR50, Appendix B, " Quality Assuranca Criteria for Nuclear Power Plants and Fuel Reprocessing Plants. " l The requirements of 10CFR71, subpart 11, " Quality Assurance for Packaging and Transportation of Radioactive Material" are also included. The CPS Inservice Inspection (ISI) Program Manual further definea the Quality Assurance Program for ASME Section XI Code activities. Additionally, in USAR section 1.8, Illinois Power la committed to carrying out the provisions of various NRC regulatory guides and industry standards which further define Quality Assurance Program requirements. l The Regulatory Guides are:

i e Regulatory Guide 1.8, Proposed Rev. 2, " Personnel Selection and Training";

  • - Regulatory Guide-1.26, Rev. 3, " Quality Group Classifications and -Standards for Water , Steam , and Radioactive-Waste-Containing Components of Nuclear Power Plants";
  • Regulatory Guide' l.29, Rev. 3, " Seismic Design O Classification";

Page ,_.l_; of 5 REVISION 26 -l  !

1 ILLINOIS POWER NUCLEAR PROGRAM j

'J QUALITY ASSURANCE MANUAL chapter 2

  • Regulatory Guide 1.30, Rev. O, " Quality Assurance Requirements for the Installation, Inspection and Testing oi Instrumentation and Electric Equipment";
  • Regulatory Guide 1.37, Rev. O, " Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants";
  • Regulatory Guide 1.30, Rev. 2, " Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Water-Cooled Nuclear Power Plants";
  • Regulatory Guide 1.58, Rev. 1, " Qualification of Nuclear Power Plant inspection, Examination and Testing Personnel";
  • Regulatory Guide 1.00, Rev. 2, " Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assuranca Records";
  • Regulatory Guide 1.94, Rev. 1, " Quality At,surance Requirements for Installation, Inspection and Testing of Structural O Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants";
  • Regulatory Guide 1.116, Rev. 0-R, " Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems";
  • Regulatory Guide 1.123, Rev. 1, " Quality Assurance Requirements for Control of Procurement";
  • Regulatory Guide 1.146, Rev. O, " Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants".

2.2.3 The Quality Assurance program description also includes the following sections of the CPS operational Requirements Manual (ORM). The CPS ORM contains administrative requirements which were removed from the CPS Technical Specifications with the implementation of the Improved Technical Specifications in January, 1996. The specific ORM sections are as follows:

  • ORM Section 6.5, Review and Audit;
  • ORM Section 6.8.2, Procedures and Programs -

Review and Approval;

  • ORM Section 6.8.3, Procedures and Programs - Temporary Changes and; D e ORM Section 6.10, Record Retention.

Page 2 of 5 REVISION 26 'l

ILLINol8 POWER NUCLEAR PRO 2 RAM v- J U i QUALITY ASSURANCE MANUAL Chapter 2 2.2.4 ouality Assurance Procram Revisinng l The Quality Assurance program receives ongoing reviews and is  !

revised as necessary to assure its continued effectiveness. The Quality Assurance Program Description, including the Quality Assurance Manual, is reviewad and updated in accordance with the requirements of 10CFR50.71, MAINTENANCE OF RECORDS, MAKING OF REPORTS. Changes made to the IP Nuclear Progfa'm Quality  :

Assurance Manual which: 1) change or affect authority, independence, or management reporting levels previously established for organizations performing quality assurance functions; or 2) reduce commitments or effectiveness of quality assurance functions specifically delineated in the Quality Assurance Program Descriptian shall be submitted and approved by the NRC prior to change implementation in accordance with 10CFR50. 54 (a) .

2.2.5 Trainina l Each department head is responsible for the proper qualification of assigned personnel performing activities related to CPS.

This includes establishing and maintaining documented training programs to ensure that personnel performing activities affecting quality are appropriately trained in the principles and techniques of the activity being performed; are inetructed as to O purpose, scope, and implementation of governing documents; and that they maintain required proficiency. Programs are formulated l to provide _ training based on individual employee experience and position and fulfill regulatory requirements, where applicable.

Training records are maintained for each employee. Departmental training procedures / instructions require that indoctrination and training programs include objectives, content of program, attendees, and date of attendance. Applicable departmental l procedures and instructions require that the proficiency of personnel performing and verifying activities affecting quality is maintained by retraining, re-examining, and/or recertifying, as determined by management or program commitment. l 2.2.6 IP Nuclear Ouality Assurance Pronram Evaluations l Regular reviews of the IP Nuclear Quality Assurance Program to assess the scope, status, adequacy, compliance, and overall effectiveness are performed under the direction of the Vice President. This review function consists of meetings Quality Assurance personnel, as well as review of audits with key and l reports, and _the performance of an IP Nuclear Quality Assurance Program assessment, which is preplanned and documented.

Corrective action required as a result of adverse conditions identified during the assessment are documented, tracked, and completion is verified and c'ocument ed . Independent audits of l p .other organizations performing activities related to quality are accomplished regularly under the direction of the Manager V -Quality Assurance.

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s ILLINOIS POWER NUCLEAR PROGRAM j QUALITY ASSURANCE MANUAL i, U k Chapter 2 0 2.3 BESPONSIBILITIES l l 1 2.3.1 Vice President

! a. Directs reviews for overall ef fectiveness of the ,

IP Nuclear Quality Assurance Program on "

a regular basis.

2.3.2 Huclear Procram Denartments

a. Implement and comply with the IP Nuclear Quality ,

Assurance Program. >

b. Train and qualify / certify, as required, personnel i

who perform quality activities associated with 1 CPS. l 1

c. Maintain procedures / instructions to the extent necessary to carry out activities affecting 4

quality.

2.3.3 CPS Plant Staff 4
a. Operate and maintain CPS in a safe, reliable, and efficient mode of operation.

2.3.4 Nuclear Station Enaineerina

a. Implement the design control program for CPS, including design interface control activities.

2.3.5 Nuclear Trainina & Sunnort l

a. Maintain and implement a Licensed Operator Training program, Maintenance and Technical

] Training program and a General Employee Training program,

b. Maintain a Document Control Program to control the issuance of documents, such as instructions, procedures and drawings, including changes thereto, which prescribe all activities affecting quality,
c. Establish, maintain and implement a Records Management Program including the CPS Records Storage Facilities.

2.3.6 Ouality Annurance

a. Perform activities to ensure the established quality assurance program meets requirements and is effectively executed.
  • Page 4 of 5 RhNISION 26 l

! ILLINOIS POWER NUCLEAR PROGRAM ,

l QUALITY ASSURANCE MANUAL L- ' "" _ d L chapter 2

b. Assure corrective actions for identified problems l l are effectivo.

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P lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL ,, .

p h CHAPTER e .$IE 3

DESIGN CONTROL

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3.1 PURPOSE / SCOPE The purpose of this chapter is to establish the requirements, l responsibilities and control measures for assuring that design bases and regulatory requirements are correctly translated into design documents. The scope of design control covers all phases of engineering design, including: conceptual design selections; identification of design inputs (criteria and baces);

identification and control of design interfaces; production of design documents, calculations and analyses; procurement-related engineering; design verification; and installation engineering support.

1

3.2 DESCRIPTION

, 3.2.1 Design control measures are established to assure design changes meet the appropriate performance and quality These design control measures are commensurate O' requirements.

with those applicable to the original design and assure that hardware changes are designed and implemented in accordance with l applicable codes, standards and regulatory commitments.

3.2.2 The Nuclear Station Engineering Department has overall l responsibility for design control activities at Clinton Power Station (CPS). These design control activities are managed within the context of the Nuclear Engineering Configuration Management Program, which also includes final design approval of hardware changes for incorporation into the plant. Processing of a hardware change, and the associated design / design change documents under this program ensures appropriate participation and awareness by CPS organizations throughout the design development and installation process.

3.2.3 Provisions of this program also ensure that each design change receives a thorough safety screening / evaluation, that meets regulatory commitments.

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ILLINOIS PCWER NUCLEAR PROGRAM ]

- " U I QUALITY ASSURANCE MANUAL chapter 3

(/ 3.2.4 New design or design changes shall be defined by l drawings, specifications, change notices or other documents as prescribed in design control procedures. The organization actually performing the design work, either Nuclear Station Engineering or a qualified consultant-engineer is required to include the following considerations in the design of each hardware changes ,, l

a. Appropriate design bases, regulatory requirements, safety requirements, performance objectives, design margins, special processes, material and testing requirements, and operating objectives are adequately translated into the various design documents,
b. Appropriate design analysis (e.g., physics, seismic, stress, thermal, hydraulic, radiation and accident) is part of the design process,
c. Accessibility requirements for operation, testing, maintenance, in-service inspection and repair are included in the design.
d. Necessary installation, inspection and test l g acceptance criteria are included in the design documents or modification packages.

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e. An evaluation to determine if the proposed design change involves an "unreviewed safety question". l
f. Design control measures shall include criticality physics and radiation shielding for radioactive material shipments,
g. Design control measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled.

3.2.5 The organization which produces and approves the l design / design change documents shall maintain detailed procedures to control and document performance of the following design activities:

a. Identification and selection of design inputs.
b. Identification and control of interfaces between organizations required to make input to, review or approve final design products.

(, c. Performance of calculations or analyses which demonstrate that design products satisfy the design inputs, including those performed using computer codes.

Page 1 of 5 REVISION 26 l

i ILLINOIS POWER NUCLEAR PROGRAM

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QUALITY ASSURANCE MANUAL L "' '- { j" L

chapter 3 i

I d. Production, review, approval and revision of  ;

drawings, specifications, data sheets or other

design output documents. ,
e. Classification and specification of technical j requirements for equipment or material procurements associated with the design / design  !

change. ,

f. Verification that the design inputs, interfaces, r calculations and final design products are
adequate and correct; and that the installation
satisfies all specified design reA w cents.

i 3.2.6 The form and structure of the procedureu and l instructions used to accomplish these activities may vary  ;

dependent upon the complexity of the design and the different organisations involved in the design development.  !

l 3.2.7 Design verification for the final design products will l normally be done by an independent group or person within the organization actually producing the design. When this is a

consultant-engineer organization, Nuclear Station Engineering may choose to conduct, or direct, additional independent design verifications.

3.2.8 This verification consists of a check of design l adequacy by such methods as design reviews, use of alternate calculations or- methods, .or performance of verification or qualification tenting. The method, or combination of methods, -

used to verify a design will be selected on a case-by-case basis.

> The selection will be based on consideration of such things as:

a) uniqueness of the design or application, b) complexity of the design, c) prior history of use, d) importance to safety, and e) consequences of failure. CPS operating phase design verification other than qualification testing of prototype or lead production

, unit will, where practical, be completed prior to installation 2

and operation. In those cases where this timing cannot be met,

, the design verification may be deferred, providing the '

justification for this action is documented and the unverified documents related to the design are appropriately identified and controlled. However, design verification shall be completed prior to the component, system or structure being released for operation.

3.2.9 Verification by test will normally be included _ in l

- procurement documents that require the supplier to perform the test and use the most severe design conditions as acceptance criteria. These procurement documents shall require that the test _ procedure, including acceptance criteria, be submitted to iO Illinois Power or its designee for review and approval prior to performance of the test.

3.2.10 When a verification test cannot be performed prior to l installation, proposed testing programs shall be reviewed and approved by Illinois Power to ensure that no unresolved safety Page 3 of jL REVISION 26 l

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QUALITY ASSURANCE MANUAL Chapter 3  :

questions are involved and the testing is conducted within  !

licensing limitations prior to the point when the installation i would become irreversible.

3.3 RESPONSIBILITIES l 3.3.1 CPS Plant Staff

a. Initiate or concur with design change requests for CPS and forward to Nuclear Station Engineering for review and approval. >
b. Incorporate approved design changes into CPS.
c. Employ controls which maintain the "as-built" and '

"as-modified" condition of the plant.

d. Assure that the proposed design change affecting nuclear safety and associated safety evaluation has been reviewed by the Facility Review Group.

3.3.2 Nuclear Station Encineerino

a. Implement the design control program for CPS, including design interface control activities,
b. Perform or obtain design services, such as preparation and review of design technical documen':s for all design changes. l
c. Review and approve design change requests for l incorporation into the plant,
d. Provide "as built" information to the Licensing l Department for updating the USAR to current plant conditions,
e. Determine if _the proposed design change involves  :

an "unreviewed safety question".

f. Coordinate the processing of hardware changes, assigning control numbers, recording progress, confirming procedural compliance, recommending operational readiness of affected hardware and transmit completed design change packages to Nuclear Support Services for processing, and retention,
g. Issue or coordinate issuance of data and reports which provide status of design eaanges.

3.3.3. Nuclear Safety & Performance Imorovement l

a. Review and evaluate Technical Specification changes and unreviewed safety questions identified Page 4 of 5 REVISION 26 l

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n QUALITY ASSURANCE MANUAL chapter a durilig tihe hardware change process and obtain the l necessary reviews and approvals.

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l ILLINOIS POWER NUCLEAR PROGRAM i OUALITY ASSURANCE MANUAL '1 i L";a CHAPTER 4

PROCUREMENT DOCUMENT CONTROL 4.1 PURPOSE / SCOPE -

1 The purpose of this chapter is to define the requirements and l responsibilities for the preparation, review, release, and revision of procurement specifications, purchase orders, and

! associated documents to assure the procurement of items and services are properly controlled.

4.2 DESCRIPTION

4.2.1 Measures are established for the preparation, review, l approval and processing of purchase requisitions, purchase specifications, purchase orders and revisions to these documents to ensure that materials, parts, components and services for CPS are properly specified and procured. l 4.2.2 Purcha:e requisitions are prepared in accordance withl documented proceduren that require

a. Applicable specifications, drawings, quality requirements, and related documents be included or referenced. l
b. Appropriate quality . requirements, including supplier documents and records to be prepared, submitted or retained, and made available for purchaser review or approval are included or referenced. l
c. Appropriate quality assurance program requirements be included or referenc,ed. l
d. Provisions for the purchaser's right of access to supplier's facilities and records (including sub-tier supplierc) for source inspection and audit be specified. l
e. Provisions for supplier's reporting and disposition _of nonconformances and requirements for hold points and release control are identified. clearly l
f. Suppliers extend the applicable quality require-p ments, including purchaser's access to facilities

( and records fr inspection and audit, to their sub-tier suppliers. l PAGE _1_, of 2 REVISION 26 l

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ILLINOIS POWER NUCLEAR PROGRAM L, w j t QUALITY ASSURANCE MANUAL Chapter 4 l 4.2.3 Technical and quality requirements for procurement of l items and services are specified. Purchase requisitions are approved by the Manager or Director of the organization, or designee, and forwarded for processing. originating l 4.2.4 Based on the approved purchase requisition, thel

necessary purchase orders or contract documents are prepared.

Prior to release of the procurement document, a " review is l l performed to ensure the requirements ("a a through "fa above) have been met. Purchase Orders or contracts are placed only with l suppliers determined to be capable of meeting the procurement requirements. This determination is based on evaluat:,ons of the supplier's quality assurance program, the supplier's technical .

capabilities and the supplier's commercial ability.

] 4.2.5 Changes, revisions or amendments to requisitions and l procurement documents are subject to the same requirements as was the original document, except for editorial changen and i commercial terms and conditions. t i

4.3 RESPONSIBILITIES l 4.3.1 Nuclear Procram Decartments

a. Initiate and approve purchase requisitions for material, parts, components or services for CPS.

4.3.2 Nuclear Trainina (a SucDort l

a. Review purchase requisitions for QA requirements. l .

4.3.3 Purchasina and Material Control

a. Prepare procurement documents for award to l qualified suppliers.
b. Review procurement documents for completeness. l i

4.3.4. Nuclear Station Enaineerina

a. Specify technical and quality requirements for .

2 materials, parts, components or services for CPS.

b. Review and approve design changes that result from procurements,
c. Provide specifications for procured materials, parts, components or services for CPS, 4,3,5 Oual'ity Assurance l p a. Evaluate suppliers' technical abilities and
d suppliers' quality assurance programs.

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] CHAPTER 5

INSTRUCTIONS, PROCEDURES AND DRAWINGS l l

5.1 PURPOSE /SCOEE The purpose of this chapter is to define the requirements and l '

responsibilities for the generation and use of instructions, procedures, drawings, or related material to control activities l which affect quality.

5.2 DESCRIPTION

i 5.2.1 . Each IP department is responsible for developing, l reviewing, approving and complying with formal instructions, procedures, drawings and related material for performing-activities affecting the quality or functions of applicable systems, structures, or components at CPS. Requirements established ares l I

a. Instructions, procedures, or drawings shall include appropriate qualitative and/or O quantitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
b. Instructions, procedures, or drawings for maintenance, modifications, testing and operation shall contain step-by-step instructions in the degree of detail necessary for a qualified individual to perform the required function or task.

5.2.2 Each Manager, Director and Supervisor is responsible for determining the need for issuing and revising instructions l.

and procedures related to each organization's scope of activities. l ,

i 5.3 RESPONSIBILITIES l 5.3.1 Nuclear Procram Denartments

a. Develop, approve, and employ those instructions, procedures, or drawings ne assary to accomplish its assigned tasks and responsibilities at CPS.

Each department is responsible for developing, obtaining approvals and complying 9 ith instructions, procedures or drawings related to O its scope of effort.

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DOCUMENT CONTROL I

6.1 PURPOSE / SCOPE The purpose of this chapter is to define the requirements and l responsibilities for review, approval, issue and d:.stribution of controlled documents such as instructions, procedures or drawings and changes thereto.

6.2 DESCRIPTION

6.2.1 Controlled documents such as specifications, l procedures, instructions, drawings, computer sof tware fcer safety-related applications, and other related materials which prescribe activities affecting quality or safety-related functions of systems, structures or components at CPS shall be processed in accordance with the following criteria l

a. Documents, including changes, are reviewed for O adequacy approved by for appropriately qualified personnel, issue and use personnel, and distributed to and used where the by authorized prescribed activity is performed. l
b. The review and approval of changes which modify the intent of the document is performed by the same organizations that performed the original review and approval, unless other equivalent organizations are specifically designated.

Reviewing organizations will have access to pertinent background information upon which to base approval and have adequate understar. ding of the requirements and intent of the original document. l

c. The document control system ensures that personnel or organizations are provided with current and approved documents. l 4
d. Documents and changes thereto are controlled by procedures to preclude the use of outdated or inappropriate documants. l
e. The CPS document control program provides for (N periodic reviews of plant procedures to determine

() if changes are necessary or desirable. l

f. Individuals or organizations responsible for preparing, reviewing, approving and documents and changes thereto are identified. issuing l Page 1 o f ,_2 . REVISION 26 l

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QUALITY ASSURANCE MANUAL Chapter 6 ,

O g. The proper documents to be used in an activity are  !

identified. l

h. Current distribution lista are established and  :

used. l ;

6.2.2 Documents such as parts lists, vendor 'nia'huals and l l written correspondence used in the design, operation, maintenance or testing are controlled in accordtinue with departmental procedures which include the following: l

a. A method of verifying and documenting receipt of transmitted documents,
b. A program for reviewing and approving the documents received fcr ype . in activibles associated with CPS by that organization. t
c. A program for distribution and contred.

6.2.3 Measures are established within each organization t.ol assure that obsolete or superseded documents described in the paragraph above are replaced in a timely manner by updated document revisions. l O 6.3 RESPONSIBILITIES l 6.3.1 Nuclear Proaram Deoartments ll

a. Review, approve and maintain controlled docu'ni,nts generated in accordance with CPS Records Management Standards.
b. Employ appropriate measures to receive, record and <

re-distribute controlled documentn from other organizations.

6.3.2 Nuclear Trainina & Succort l a.. Maintain a Document Control Program to control the issuance of documents, such as instructions, and changes procedures drawings, including thereto, which prescribe all activities affecting quality.

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7 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES 7.I PURPOSE / SCOPE - - -

The purpost, of this chapter is to define the requirements and l responsibilities for programs that assure purchased material, equipment, and services conform to procurement requirements.

7.2 DESCRIPTION

7.2.1 Measures have been established to provide assurance l that purchased material, equipment, and services conform to procurement document requirements. This assurance is '

accomplished by controlling both the selection of procurement sources and acceptance of the product at the source and/or upon receipt at CPS.

7.2.2 IP procurement procedures require a review of material, l equipment and services requisitions for safety-related structures, systems, and components. This review will identify the applicable codes, standards, technical and quality LO requirements to assure that they are equivalent to the original requirements. When alternate requirements are imposed which are not equivalent to the original requirements, the alternate requirements will be fully evaluated and documented. The necessary reviews and evaluations of the procurement source's capability to meet the technical requirements of the procurement documents will also be performed.

7.2.3 Reviews and evaluations are performed - of the l procurement source's quality assurance program and ability to meet the quality assurance and technical requirements of the procurement- documents. Where necessary, a supplier'sl acceptability is determined by an audit of the supplier's quality assurance program. Such audits are performed in accordance with a written plan or checklist to determine the ability of the supplier to comply with the quality assurance program requirements of the procurement document. The determination of a l supplier'b acceptability may be made by means other than by audits. These means may include a) review and evaluation of ~

the supplier's quality assurance program description document, b) review and evaluation of histor2 cal supplier quality performance data, c) supplier facility surveys, d) review and evaluation of audits, surveys, and inspections conducted by other utilities, or American Society Mechanical Engineers (ASME), or e) documented information from organizations, including architect-engineer, O Nuclear Steam Systems Supplier, indicates the supplier requirements of Appendix B to 10CFR50.

has a program and other utilities -that that meets applicable When these means are either not available or do not permit a complete evaluation of a Page ,_1_. of 4 REVISION 26 l

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4 O supplier's quality capabilities, a survey or an audit will be conducted maintained.

of the supplier. A Qualified Suppliers List is l

1 7.2.4 In addition to reviewing a supplier's capability to l

meet the commercial requirements of the procurement documents, a ,

review is performed to ensure that the required technical and 3

quality assurance evaluations have been completed sat,i.ef actorily prior to contract award or release of the purchase order. The

results of these reviews and evaluations are documented. t
7.2.5 When required by the procurement document or specification, surveillances and evaluations at the supplier's l f acility are conducted to verify continued compliance with the quality assurance requirements of the procurement documents.

Source inspections at the supplier's facility are accomplished by qualified individuals or qualified agents to verify that the procurement item or service is being supplied in accordance with the requirements of the procurement documents. Such inspections are accomplished in accordance with written procedures, plans, and/or checklists containing or referencing appropriata acceptance criteria. l 1

7.2.6 Upon receipt at CPS, safety-related materials, parts, and components are controlled. Qualified inspection personnel l are responsible for inspecting, releasing, and maintaining the j O inspection status of purchased material and equipment.

7.2.7 Acceptance activities such as evaluation of content of l technical documents required by the purchase order, and the conduct of special tests and measurements which are identified in the purchase order are also ?arformed. Receipt inspections are accomplished in accordance w:.th written procedures and/or plans containing or referencing appropriate acceptance criteria. After receipt inspection, the purchased material is forwarded to a controlled storage area or released for installation or further work. l 7.2.8 Documentary evidence of conformance to procurement l requirements provided by the supplier in accordance with the procurement documents is reviewed during source and/or receipt inspections to verify compliance. The validity of a supplier's certificate of conformance is ascertained through any of the following methods: source inspection, independent inspection agency, receipt inspections, surveillance, testing of hardware, quality assurance audits or surveillances. Inspection and test activities verify that the hardware performs in accordance with applicable technical requirements and serve to demonstrate that the hardware - meet.s the requirements stated in a certificate of conformance. The results of the source and/or receipt inspections, the acceptability of supplier furnished O documentation, and the resulting determination of conformance or nonconformance are documented. l 7.2.9 Acceptance of contracted services such as inspection l services, consultant services, installation, repair or Page 2 of 4 REVISION 26 l

t M I lLLINOIS POWER NUCLEAR PROCRAM QUALITY ASSURANCE MANUAL L""~A / [' chapter 7 ,

maintenance services shall be based on one or all of the j following methods, as required:

a. technical verifications
b. surveillance / inspections
c. review of objective evidence -- such as certifications or technical reports. ,

7.3 RESPONSIl3ILITIES 7.3.1 Nuclear Procram Denartmenta

a. Ensure the control of purchased material, equipment, and services conform to procurement requirements.
b. Ensure that suppliers performing work at CPS utilize control measures compatible with those of s

. CPS Plant Staff.  ;

7.3.2 Nuclear Station Enaineerina purchase requisitions and specify the

~

a. Review 4

technical and quality requirements for the item (s) or service (s) to be procured.

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b. Review and approve supplier furnished technical data specified by the procurement document, including such items or services as process and .

test procedures, performance of test data, and heat treat charts prior to acceptance.

I 7.3.3. Nuclear Trainina & Succort l

a. Implement procedures for the receiving, storing, and issuing of purchased items,
b. Qualified inspectors perform required receipt inspection of materials or equipment prior to issuing the-material or equipment for operation.

7.3.4 Purchanina and Material Control

a. Perform reviews of suppliers' capabilities to meet commercial terms and conditions prior to release of the purchase order or contract,
b. Verify the suppliers are listed on the Qualified Suppliers List as required.

O- 7.3.5. Ouality Assurance l ,

a. Perform source surveillances and audits of ,

suppliers' quality assurance programs, or Page 3 of 4 REVISION 26 l

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QUALITY ASSURANCE MANUAL chapter 7 establish alternate controls, prior to release of l the initial purchase order or award of contract. l
b. Perform source survillances and audits at  :

suppliers' facilities to verify compliance with i the quality and technical requirements of j procurement documents. j i

- c. Maintain a database identifying qualified suppliers, i

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LLa wJ fj IDENTIFICATION AND CONTROL 01-iMTERIALS, PARTS AND COMPONENTS 8.1 PURPOSE /SCOIZ The purpose of this chapter is to define the requirements and l ,

l responsibilities for a program of identification and control of materials, parts, and components such that traceability is l assured and the use of incorrect or defective items is prevented. ,

8.2 DESCRIPTIO1{

8.2.1 Measures have been established which provide for the l  ;

identification and control of materials, parts, and components to assure that traceability is provided and the use of incorrect or defective items is prevented. These measures include the following

a. Procurement documents specify appropriate identification to be applied to purchased items. l 4
b. An inventory control system is employed for the receipt, storage or stocking, and issue of materials, parts, and components.
c. The identity of materials, parts, and components is either on the items or on records traceable to them. When physical marking is employed, the marking in clear, unambiguous, indelible, and '

applied in such a manner as to act be detrimental to the intended function of the item. l

d. Markings are not obliterated or hidden by treatment or coatings unless other means of identification are substituted.
e. When codes, standards, or specifications require traceability of materials, parts, or components to specific inspection or test records, the program is designed to provide such traceability. ,
f. When employed, identification is transferred to each part of an item prior to its being subdivided.

O 8.2.2 Materials, parts, and components shall have appropriate l i identifying designation (such as serial number, part number, heat number, etc.) in order to provide traceability to each item to Page _J_,,of 2 REVISION 26 l

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Chapter 8 l inspection and test records and/or reports. Where physical identification of an item is either impracticel or insufficient, ,

physical separation or additional procedural controls are employed. l 8.2.3 When installed material or equipment is removed for l maintenance, repair, or modification, control measures are implemented to ensure proper identification and tracb5bility is .

maintained. During fabrication, assembly, installation, and  !

shipping activities at a supplier's facility, the supplier -

conoucts verification inspections and la responsible for identification and control of materials, parts, and components in i accordance with the requirements of the IP purchase order. l t r

3 8.2.4 Material, parto, and components are identified and controlled during receipt and storage, fabrication, maintenance and modification activities performed at CPS. The IP department responsible for supplier work at CPS is responsible for ensuring that identification and control of materiala,- -parts, and i components by the supplier are in accordance with applicable procedures.

8.3 RESPONSIBILITIES l 8.3.1 Nuclear Procram Deoartmenta

n. The Nuclear Program Departments responsible for

, supplier work at CPS are responsible for ensuring that identification and control of materials, parts and components by the supplier are in accordance with applicable procedures.

8.3.2 CPS Plant Staff

a. Implement a program that provideo for the identification and control of materials, parts and components used at CPS. ,

8.3.3. Npelear Trainina & Sunoort l

a. Implement an inventory control system for the identification and control of materials, parts and componenta.

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CONTROL OF SPECIAL PROCESSES ,

9.1 PURPOSE / SCOPE t ,

and The purpose responsibilities of this forchapter is assuring to define that the special requirementssuch processes as l welding, heat treating, chemical cleaning, nondestructive examination (NDE), pipe bending, and special coatings are performed under proper contrels and that qualified procedures '

governing these processes are established in accordance with applicable codes and specifications, are implemented by qualified personnel, and results of special processes are properly documented and evaluated.

9.2 DESCRIPTION

9.2.1 For some processes, the required level of quality l defined in codes, . standards, and specifications cannot be verified by inspection of the item only. For these processes, O quality assurance is accomplished by qualified personnel using qualified procedures. Processes which meet criteria are contro11cd as special processes:

the following

a. The process is highly dependent upon operator skill and/or process control,
b. The specified quality cannct be readily determined i by direct inspection or test of the final product.

9.2.2 prerequisite conditions,Special process processing procedures shall specify: conditions to be maintained steps, the steps of the process, inspection and test requirements, personnel qualification requirements and record requirements.

Technical portions of the special process controls are delineated or referenced in th' design or technical documents by the organization preparing the document. l 9.2.3 Special process procedures shall be reviewed and l approved to assure technical adequacy. Supplier process control procedures specify the methods of verifying the adequacy of processing materials, solutions, and equipment, including-definitions of the4,r associated control parameters. The control and approval of sub-supplier special process procedures are the responsibility of the specific suppliers involved. Special l procese requirements are promulgated to suppliers by the

-O procuren.ent and/or design documents.

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i OUALITY ASSURANCE MANUAL chapter 9 O 9.2.4 Control measures and requirements that have been l established includes

a. The need for special processes and the codes or
standards applicable are identified during decign or preparation of technical documents , associated with an activity. l
b. Special processes are performed in accordance with approved written procedures applicable to the specific process and qualified in accordance with ,

applicable codes and standards. l

c. Personnel performing special processes are qualified, as required in accordance with applicable codes and standards. l
d. Special processes are accomplished under suitable controlled conditions which include the use of qualified equipment, adequate control of the environment, and establishment of proper prerequisites related to the process. l
e. Application of special process procedures and 4

i personnel qualifications is verified through k audits and surveillances. l

f. Records which show ' that special processes were '

performed in compliance with qualifted or approved

cedures and by qualified personnel and equipment are maintained. l 9.2.5 Inspections are conducted of special processes to l ensure compliance with appropriate codes, standards, specifications, procedures, and the IP Nuclear Assurance Manual. Program Quality l 9.3 RESPONSIBILITIES 9.3.1 CPS Plant Staff
a. Maintain a program to qualify special process procedures and equipment. l
b. Maintain a program to qualify personnel to perform special processes. l
c. Incorporate into Plant Staff documents the requirement for special processes and their

~N. controls and references to he applicable codes or standards.

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a. Specify special processes in techniced documents and procurement requisitions,
b. Support CPS Plant Staff in the preparation, revision and qualification of speciq,1 process procedures and personnel,
c. Review and approve special process procedures used at CPS or specified in procurement documents to verify technical adequacy.
d. Review and approve special process personnel qualification procedures and verify technical adequacy.
e. Contracts with an Authorized Inspection Agency to provide inspection services for ISI.
f. Perform scheduled ISI examinations and inspections.
g. Contracts with a supplier to perform scheduled ISI examinations and inspections as required.
h. Review NDE procedures, including those of suppliers.
i. Maintain a program to qualify procedures, equipment, and personnel for NDE.
j. Perform NDE to support plant operations, including NDE for repairs, replacements and modifications.
k. Contracts with a supplier to perform NDE or inspection services as required.

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!O CHAPTER 10 INSPECTION 10.1 EQ' POSE / SCOPE The purpose of this chapter is to define the requirements and l responsibilities for a program of inspection which provides assurance that the fabrication, installation, modification, and repair activities affecting safety-related components, systems, and structures conform to the applicable specifications, instructions, procedures, drawings, or other pertinent technical requirements. Independent inspections are not intended to diminish the responsibility of personnel performing the dCtivities for the quality of the work.

10.2 DESCRIPTION

10.2.1 In order to assure safe and reliable operation, l programs of inspections are established at CPS which include the following provisions:

a. The requirements for inspections are identified and documented based on proceduras, instructions, drawings, and other documents for an prior to the start of ine activity. activity l
b. Inspections are accomplished in accordance with a combination of approved procedures and instructions which contain or reference, as a minimum:
1. A description of the required inspection (type, method, etc.), the responsibility for performing the inspection, and, where applicable, any sampling plan to be used.

Hold / Witness points, where required, will be indicated in the appropriate documents; -

2. The discrete identity of the activity, process, or item to be inspected;
3. Applicable documents, drawings, and specifications pertaining to the activity or item under inspection;
4. Verification of proper type, range, and accuracy of inspection instrument (s) used for
each operation; 1
5. Appropriate quantitative or qualitative criteria for acceptance / rejection; Page 1 of 3 REVISION 26 l

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6. Provisions for recording inspection data and results,
c. Inspection personnel are qualified and certified in accordance with the requirements of applicable codes, standards and procedures. Inspe'ctions are l performed by persons other than those who performed or directly supervised the activity being inspected. The qualifications and certification of inspection personnel are maintained current. l
d. Where inspection or testing is impossible or l dicadvantageous, indirect control by monitoring process methods, equipment, or personnel is employed. When necessary to provide an adequate level of product quality assurance, both direct control (inspection and testing) and indirect control (process monitoring) are utilized. When sampling plans are used, their applicability is evaluated and justified in writing. l
e. Measuring and test equipment used to obtain O quantitative data for acceptance criteria shall V have an accuracy equal to, or greater than, the required tolerances of the measurement taken. being l 10.3 RESPONSIBILITIES l 10.3.1 CPS Plant Staff
a. Implement a program that provides for inspection of work operations performed at CPS.

10.3.2 Nuclear Station Encineerina

a. Specify inspection and nondestructive examination criteria and requirements in technical documents and procurement requisitions.

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b. Implement an inspection program for scheduled ISI Program examinations and inspections and perform NDE and welding inspections to support plant operations,
c. Maintain qualified and certified inspection personnel in accordance with appropriate standards.

( 10.3.3. Ouality Assurang_q l

a. Implement an inspection program for CPS. l Page 2 of 3 REVISION 26 l

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b. Maintain qualified and certified inspection personnel in accordance with appropriate standards. l 10.3.4 thLqlear Trainina & Suncort
a. Implement a receipt inspectior. program f,or CPS.
b. Maintain qualified and certified inspection personnel in accordance with appropriate standards.

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CHAPTER 11 1

TEST CONTROL 11.1 PURPOSE / SCOPE The purpose of this chapter is to define the requirements and l responsibilities for the control of a test program which will assure that the safety-related structures, systems or components being tested meet specified performance criteria.

11.2 DESCRIPTION

11.2.1 Measures have been established to address requirements l and responsibilities for establishing and conducting test programs for the following:

a. Verification tests prior to installation.
b. Surveillance testing.

(v c. Tests associated with plant maintenance, modifica-tions, repairs or procedural changes.

11.2.2 Test programs are developed to assure that the required tests are performed in accordance with approved procedures which incorporate or reference the design requirements and acceptance criteria and provide for the following, as required:

a. Statement of test objective (s) ;
b. Test prerequisites, to be fulfilled prior to the test, including requirements for calibrated inetruments, suitable environmental conditions, appropriate equipment and personnel availability; and condition of the item to be tested and condition of the test equipment;
c. Precautions to be taken in the preparation and performance of the test, including limits of parameters if variations outside the normal ranges are prescribed;
d. Mandatory inspection hold points for witness by inspection personnel;

(~ e. Instructions for performance of the test, (T) including the use of appropriate equipment and personnel; instruments,

f. Data to be acquired; and Page _J_. of 2 REVISION 26 l

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ILLINOIS POWER NUCLEAR PROGRAM , m  ; d j QUALITY ASSURANCE MANUAL Chapter 11

g. Acceptance / rejection criteria.

11.2.3 Test schedules are provided and maintained in order to l assure that necessary testing is performed and properly evaluated on a timely basis and that the safety of the plant is dependent on performance of systems which have satisfactorily passed i required tests. Testing is conducted by appropriateTy trained and qualified personnel. Test results are documented to facilitate evaluation and to provide a permanent record. Test evaluations are performed to assure that performance characteristics conform to design. Repair, rework and/or retesting are scheduled for accomplishment as identified by the test evaluation.

11.3 RESPONSIBILITIES 11.3.1 Nuclear Station Engineerina

a. Implement programs that specify and control the testing of structures, components and systems,
b. Develop and implement test schedules to ensure that tests are performed on a timely basis.
c. Ensure that test personnel are qualified and O' trained to perform their function.
d. Review and approve test procedures and results for l surveillance testing,
e. Review and approve post-maintenance test results. l 1
f. Establish test requirements and acceptance l criteria for post-modification testing.
g. Review and approve post-modification and/or l special test results.
h. Review and evaluate test results as required by l the ISI Program.

11.3.2 CPS Plant Staff

a. Implement programs for the performance of surveillance and post-maintenance tecting.
b. Ensure that post-maintenance testing and surveillance tests are performed by qualified personnel with appropriate procedural guidance.
c. Review and approve test procedures and results for surveillance testing.
d. Review and approve post-maintenance test results.

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U CHAPTER L-"

12 CONTROL OF MEASURING AND TEST EQUIPMENT 12.1 PURPOSE / SCOPE The purpose of this chapter is to define the measures and l responsibilities to assure tools, gauges, instruments, and other Measuring and Testing Equipment (M&TE) used in activities affecting quality are properly controlled, calibrated and adjusted at specified periods to maintain accuracy within specified limits. Measures shall also be defined for the control of permanently installed instrument and control devices.

12.2 DESCRIPTION

12.2.1 M&TE is equipment used to quantitatively generate or l measure physical parameters with a known degree of accuracy for the purpose of calibration, inepection, test, or repair of plant mechanical, electrical or instrument / control equipment.

b D

12.2.2 In order to assure the accuracy of measuring and test l equipment and installed instrument and control devices which require calibration or calibration check is maintained within specified limits, a written program for the control and calibration of such devices is provided. This program includes the following provisions:

a. For M&TE, the reference standards have an accuracy of at least four (4) times the required accuracy

, of the equipment being calibrated, or when this is not possible, have an accuracy that assures the equipment being calibrated will be within the required tolerance and that the basis of acceptance is documented and authorized by supervision.

b. The reference standards used for calibrations are required to be traceable to nationally recognized standards or accepted values of natural physical constants to the extent possible. When this is not possible, the basis for calibration of a reference standard is required to be documented,
c. Cal.ibration intervals for M&T2 and installed instrument and control devices are based upon the

(~ type of equipment, stability, reliability

(~,}/ characteristics, required accuracy and other conditions affecting calibration.

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 12 O d. Calibrations are performed by comparison with valid standards using approved written procedures.

e. Calibration standards are maintained and used in a controlled environment which does not adversely affect the calibration procedure or standard.
f. The calibration status, including the-tine date of next calibration of each item of M&TE, is visible through use of tags, labels or decals attached to the equipment or a statusing system,
g. M&TE and installed instrument and control devices requiring calibration are assigned identification numbers traceable to the calibration records which includes the calibration "AS FOUND" and "AS LEFT" data for the equipment calibrated at the plant.

If the equipment is calibrated by an outside service organization, a certificate of calibration complete with "AS FOUND" and "AS LEFT" calibration data is required. Such certificates and data sheets bear the assigned equipment identification numbers and the identification of the calibration standard used and are traceable to the individual calibration records, tO V h. M&TE is not used past calibration period.

the expiration of the

1. If selected installed instrument and control devices are found to be out of calibration, La evaluation concerning the validity of previous inspection and test results is performed and documented. If M&TE is found to be out of calibration, an evaluation concerning the validity of previous inspection and test results and the acceptability of items previously inspected or tested since the time of the last calibration check is made and documented. Corrective action is taken in accordance with Chapter 16 when such evaluations invalidate a previous acceptance.
j. A calibration tracking system is established to ensure that recalibration is performed in accordance with pre-established calibration frequencies.

12.2.3 A program has been implemented for the control of M&TE l and installed instrument and control devices used in operation, maintenance, test and/or inspection activities which fall within p the scope of the IP Nuclear Quality Assurane:e Program. Suppliers performing services or providing products to CPS are required to 4'J-- have comparable control programs in effect for items affecting systems, Structures and Components within the scope of the OA program.

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->d ILLINOIS POWER NUCLEAR PROGRAM ' _ d !f QUALITY ASSURANCE MANUAL Chapter 12 0 12.3 RESPONSIBILITIES l 12.3.1 CPS Plant Staff

a. Implement programs to control M&TE use at CPS.
b. Implement programs to calibrate and - recall the M&TE used at CPS.
c. Ensure the appropriate requirements for the control of M&TE are included in Plant Staff initiated technical documents and procurement requisitions,
d. Implement programs to control the use of installed instrument and control devices.

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ILLINOIS POWER NUCLEAR PROGRAM ,

QUALITY ASSURANCE MANUAL  ; u,j0 V CHAPTER 13 HANDLING, STORAGE AND SHIPPING 13.1 PURPOSE / SCOPE The purpose of this chapter is to define the requirements and l responsibilities for the control of handling, storage, shipping, packaging, cleaning and preservation of materials and equipment to prevent damage or deterioration.

13.2 DESCRIPTION

13.2.1 The IP Nuclear Quality Assurance Program includes handling, preservation, storage, cleaning, packaging and shipping requirements that are accomplished by trained individuals in accordance with procedures to prevent damage or deterioration.

The procedures provide for the control of heavy loads and safe l load paths to protect safety systems and radioactive material from damage. In addition to the handling, storage and shipping requirements imposed on suppliers by IP through appropriate t technical and procurement documents, suppliers may also be required to provide information to Nuclear Support Nrvices related to the proper handling, storage and shipping of furnished materials, parts and components. Nuclear Support Services uses this information for the development of the storage and handling procedures and instructions to be applied to an item.

13.2.2 The procedures provide for the preservation of special l items that are subject to deterioration or damage through exposure to air, moisture, temperature, or other environments and use of special handling tools and equipment.

13.2.3 Consumable materials such as chemicals, reagents and l lubricants maintained in storerooms and warehouses are controlled procedurally by an inventory control system which includes provisions for identifying storage requirements by commodity and identifying shelf life by commodity, when applicable. Disposal of commodities whose shelf life has expired is addressed and controlled by procedures.

13.3 RESPONSIBILITIE'S l 13.3.1 CPS Plant Staff

a. Implement programs to provide for the use of

(] special handling tools and equipment.

L) Implement programs to control

b. the handling, storage and shipping of materials.

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QUALITY ASSURANCE MANUAL Chapter 13 13.3.2 Nuclear Station Encineerina

a. Ensure that appropriate handling, storage and shipping requirements are identified in technical documents that are prepared or reviewed by the department.
b. Specify in procurement documents, that suppliers furnishing materials and equipment within the scope of this program implement appropriate controls for handling, shipping and storage of such items.

13.3.3. Nuclear Trainina & Suonort l

a. Ensure that suppliers furnish the required information relating to the proper handling, storage and shipping of procured items.
b. Implement programs to control the handling, storage and shipping of items to be used in CPS, including radioactive materials.

c c. Implement programs to provide for the preservation

( of items in storage that are subject to deterioration or damage through exposure to harsh environmental elements or conditions.

d. Ensure that appropriate handling, storage and shipping requirements are identified in procurement requisitions.

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.O_ CHAPTER 14 INSPECTION, TEST AND OPERATING STATUS 14.1 PURPOSE / SCOPE The purpose of this chapter is to define the requirements andl responsibilities for identifying the inspection, test and operating status of materials, parts, componenta and assemblies to assure that only items which have passed the required inspections and tests are installed or operated.

14.2 DESCRIPTION

14.2.1 The IP Nuclear Quality Assurance Program includes l procedures which assure the inspection, test and operating status of materials, parts and components are identified during the receiving, installation and operating processes. These procedures provide for: l

a. Clear indication of the status of inspection and O

(d tests performed upon individual items by the use of markings such as: a) stamps applied directly to the item, tags, or labels attached to the item; b) routing cards that accompany the item; or c) identification numbers which are traceable to records of the status of inspections and tests.

If control stamps are used, a record of the assignment of the control stamp is maintained; however, if a stamp is lost or if the stamp holder no longer requires the stamp, that stamp number is retired. When impression stamping is used, it conforms to the requirements of codes and applicable specifications and standards. When markings are applied directly to items, consideration is given to ensure the markings have no deleterious effect on the items. l

b. Assurance that required inspections or tests are not inadvertently bypassed. In cases where required documenting evidence is not available, the associated equipment or materials must be considered nonconforming in accordance with Chapter 15 of the Illinois Power Nuclear Program l Quality Assurance Manual. Until suitable documented evidence is available to show the A ' equipment or material is in conformance, affected

()' systems shall be considered to be inoperable and reliance shall not be placed on such systems to fulfill their intended safety functions. l Page 1 of 2 REVISION 26 l

-lLLINOIS POWER NUCLEAR PROGRAM 4 I

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QUALITY ASSURANCE MANUAL Chapter 14

c. Clear indication, by the use of a tag and/or statusing system, of the operational status of structures, systems and components when in any status other than a normal operable status to prevent inadvertent operation.

14.2.2 The test - and operating status of materials, parts, l components and assemblies is indicated at CPS. The'1nspection and test status of items in storage is also maintained.

3 Inspection personnel are responsible for the identification of the inspection status on materials, parts and components. As l imposed by the contract documents, suppliers performing activities at CPS or furnishing materials, parts, components or assemblies for use at CPS also have responsibilities for the identification of inspection, test and operating status of items under their control. The programs of suppliers performing work l at CPS are reviewed and approved to ensure compatibility with the CPS status indication system. l 14.3 RESPONSIBILITIES l 14.3.1 CPS Plant Staff

a. Implement programs to indicate inspection, test g and operating status of materials, parts, components, sub-systems and systems during ,

installation, modification, repair, testing and operation of CPS.

b. Review and approve the programs of suppliers performing work at CPS to ensure compatibility with the CPS status indication system.
c. Implement procedures to control the status of radiological samples,
d. Implemer.t programs to indicate status of nonconforming items.

14.3.2 Nuclear Traininc & Suonort l

a. Implement procedures to control the inspection and test status of items in storage.

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ILLINOIS POWER NUCLEAR PROGRAM 1 QUALITY ASSURANCE MANUAL uud8 O

V CHAPTER 15 NONCONFORMING MATERIALS, PARTS OR COMPONENTS 15.1 PURPOSE / SCOPE The purpose of this chapter is to describe the measures l catablished and implemented to control items, services or activities which do not conform to the requirements, and the measures to control further processing, to prevent inadvertent use or installation of nonconforming or defective items, 15,2 DESCRIPTION 15,2,1 The following measures have been established and l implemented at CPS:

a. Control of nonconformances is accomplished in accordance with documented procedures, l
b. Nonconformances are documented by means which also ensure that affected organizations are notified. l
c. Nonconforming items are identified and controlled.

Except for installed items, nonconforming items are placed in a segregated storage area when practical, such storage areas are identified as containing only nonconforming items, When segregation is impossible or impractical, the nonconforming item shall be identified and controlled by tagging, marking or documentation traceable to the item, including normally installed installeditems or those removed from the normally l location.

d. Further use or installation of nonconforming items is controlled in accordance with written procedures and/or instructions. l
e. The responsibility and authority for the disposition of nonconformances is defined. l
f. Permissible dispositions are a) "use as is", b)

" rework" to drawing or specification requirements, c) " repair" to an acceptable level, d) " reject" for that particular use, or e) "other" for non-hardware nonconformances. l C)N

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lLLINOIS POWER NUCLEAR PROGRAM L-"" i QUALITY ASSURANCE MANUAL Chapter 15

g. " Repair" and "reworM dispositions are implemented into the affected item in accordance with documented procedures and/or instructions. l
h. The disposition, along with its engineering analysis and any resultant reinspection and/or acceptance verification, is documented. l

=gd

1. " Rework" and " repair" actions are described, depending on complexity, by individual procedures or by instructions contained in the corresponding work control document. Each procedure or instruction details required inspections and tests. Specified inspections and tests are equivalent to original requirements. Acceptable alternatives to original inspection or test requirements may be used provided they are assessed for adequacy and the rationale documented. l 15.2.2 Inservice items that are found to be nonconforming l shall be reviewed to determine equipment operability as defined by the Technical Specifications. For items that represent significant conditions adverse to quality or safety, or require a repair or use-as-is disposition, an engineering evaluation shall

/3 be performed. The engineering evaluation shall provide support V for the initial operability decision and provide the correction or resolution for the identified nonconformances. These items

, shall be controlled in accordance with approved procedures. l 15.2.3 Installed items not in service that are nonconforming l or become nonconforming as a result of maintenance shall be corrected or resolved prior to operational reliance. These items shall be controlled in accordance with approved procedures.

15.2.4 A nonconform3 ng item may be conditionally released for l fabrication, installation or testing following an engineering evaluation to determine if such a conditional . release is not detrimental to other components or systems. Conditional released items are controlled in accordance with approved procedures. The nonconformance for the conditionally released item shall be corrected or resolved prior to operational reliance.

15.2.5 The Manager - Clinton Power Station has the authority l to conditionally release any item or installation for operation if_needed to place the plant in a safe and stable condition.

15.3 RESPONSIBILITIES l 15.3.1 All Nuclear Procram Personnel

a. All Nuclear Program personnel are responsible for d identifying and reporting nonconforming materials, parts, components, services and activities.

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' c6 apter 15 15.3.2 Nuclear Prooram DeDartments

a. All Nuclear Program Departments are responsible for establishing and implementing effective procedure (s) for identifying, documenting and controlling nonconformances within the scope of their department's activities. --

l 15.3.3. CPS Plant Staff i

a. Authorize the conditional release of items. -
b. Coordinate with NSED to evaluate and document the safety significance of nonconforming items.
c. Develop and implement procedures, instructions or work control documents for the control and correction of nonconforming items with repair or rework dispositions.

15.3.4 Nuclear Trainina & Suncort l

a. Implement an effective program for processing supplier ncnconformance reports.

15.3.5 Huclear Station Enaineerina

a. Implement a program for nonconforming items that ensures "use-as-is" or " repair" dispositions are approved by the appropriate design organization,
b. Coordinate with Plant Staff to evaluate and document the safety significance of nonconforming items.
c. Perform engineering evaluations for conditionally released items,
d. Determine acceptable alternatives to original inspection or test requirements for " rework" or

" repair" dispositions,

e. Document engineering analyses that support the disposition of nonconforming items.

15.3.6 Facility Review Groun 1

a. Review documented safety evaluations for conditionally released items in accordance with the requirements of 10CFR50.59.

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'A ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL ' * "

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CHAPTER 16 CORRECTIVE ACTION 16.1 PURPOSE / SCOPE The purpose of this chapter is to describe the measures l established and implemented to assure that conditions adverse to plant safety and/or quality are promptly identified and corrected; and that significant conditions are identified, evaluated, documented, corrected, reported and independently reviewed.

16.2 DESCRIPTION

16.2.1 Each IP organization and supplier performing activities l or supplying services, materials, parts or components applicable to this program is required to establish and implement a documented corrective action procedure (s) which assures that conditions adverse to plant safety and/or quality are promptly reported to supervisory personnel, analyzed for (q

d 4

identified, significance and corrected. Personnel identifying conditions adverse to plant safety and/or quality or organizations l have the responsibility to report such conditions to the appropriate functional organization who will promptly correct the condition. Conditions adverse to plant safety will be reported to Plant Operations personnel for assessment of operational impact. Roporting may be accomplished through various reporting documents as defined in procedures. An analysis of the significance of conditions adverse to plant safety and/or quality is performed by personnel cognizant of the condition and its resultant effects on plant safety or operability.

16.2.2 Trend analysis is performed on conditions adverse to l plant safety and/or quality to determine if a trend representing significant condition adverse to plant safety and/or quality exists. Trend analysis of conditions documented on maintenance l work documents to identify equipment failures and reliability concerns is also performed. The results of these trend analyses are documented and reported to appropriate management of the area in which the trends are identified. Reports to management include a history and analysis of the adverse conditions and trends identified. l 16.2.3 In the case of significant conditions adverse to plant l safety and/or quality, including significant adverse trends, the functional organization responsible for the significant condition

(- will analyze the condition for causes, take appropriate and timely action to preclude recurrence and implement follow-up action as appropriate to verify implementation of corrective action. The actions taken will be documented and reported to 1 appropriate levels of management.  !

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QUALITY ASSURANCE MANUAL Chapter 16 O' 16.2.4 Corrective action is evaluated to determine its l effectiveness, including steps taken to identify the cause of significant conditions adverse to plant safety and/or quality and action taker. to preclude recurrence. Documented corrective l action for significant conditions adverse to plant safety is also reviewed. These reviews are documented and are carried out in accordance with a documented program. --

16.3 RESPONSIBILITIES 1G.3.1 All Nuclear Procram Personnal

! a. All Nuclear Program personnel are responsible for identifying and reporting conditions adverse to plant safety and/or quality.

16.3.2 Nuclear Procram Denartments

a. Implement a corrective action procedure (s) which assures that conditions adverse to plant safety and/or quality are promptly identified, reported, analyzed for significance and corrected. In the case of significant conditions, the procedure (s) requires an analysis for causes, action to preclude recurrence, and follow-up verify O implementation of corrective action.

to 16.3.3. CPS Plant Staff

a. Assess conditions adverse to plant safety for operational impact.

~

16.3.4 . Nuclear Safety & Performance Imorovement DeDartment

a. Implement a Corrective Action Program (CAP) to assure that conditions adverse to plant safety and/or quality are identified, evaluated, reported, corrected, reviewed, evaluated for effectiveness, and trended.
b. Conduct root cause analyses activities.

l 16.3.5 Nuclear Review and Audit Groun

a. Review significant conditions adverse to plant safety in accordsnce with a documented program.

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v m-- u CHAPTER 17 QUALITY ASSURANCE RECORDS 17.1 PURPOSE / SCOPE The purpose of this chapter is to define the requirements and l responsibilities for collection, compilation, storage and retrieval of records necescar, to provide evidence of quality in the design, fabrication, installation, inspection, testing and

- operating activities related to the Clinton Power Station.

17.2 DESCRIPTION

17.2.1 Measures shall be established to assure that sufficient records are identifiable to the item or activity to which they apply. Records shall be filed in an orderly manner and retrievable. Records are maintained in the records storage facilities, 17.2.2 Test and inspection records shall contain the following p

Q information:

a. Identity of the inspector or data recorder;
b. Type of observation;
c. Date and results of the test or inspection (quantitative and qualitative);
d. Acceptability of the test or inspection results; and
e. Action taken and rationale to resolve any problems noted.

17.2.3 The preparation, collection, review, acceptance, l turnover / transfer, processing, transmittal, retention and retrieval of records is accomplished in accordance with documented standards and procedures. Some quality assurance records may be kept by suppliers and maintained on an available basis for a specified period of time. Such records are required to be offered to IP after the suppliers no longer plan to keep them.

17.2.4 The retention times for the various quality assurance l p)

(

records are in accordance with applicable requirements including 10CFR, and nationally recognized standards and codes. Records are maintained in the records storage facilities that provides controlled access and protection against fire, flooding, vermin and decay.

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ILLINOIS POWER NUCLEAR PROGRAM v ,, u 2d QUALITY ASSURANCE MANUAL chapter 17 O

V 17.3 RESPONSIBILITIES l 17.3.1 Nuclear Program Denartments

a. Implement Records Management Standards for preparation, collection, review, acceptance, turnover / transfer, processing, t-ransmittal, retention and retrieval of records.
b. Transfer completed quality assurance records to Nuclear Support Services, Records Management Group for processing and retention.

17.3.2 l{uclear Trainina & Sunnort l

a. Establish, maintain and implement a Records Management Program including Standards covering the preparation, collection, review, turnover / transfer, processing, retention and retrieval of records generated in performing activities within the scope of this program,
b. Receive, process (index, microfilm, etc.), and retain quality assurance records in the records i storage facilities. I n

V c. Maintain the CPS records storage facilities such that completed quality assurance records are kept in accordance with the requirements of this manual.

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_T CHAPTER 18 AUDITS

[ 18.1 EURPOSE/P&QEE The purpose of this chapter is to define the requirements and l responsibilit les for implementing the program of planned and periodic aud'ts which verify compliance with quality assurance programs r.nd determine effectiveness in meeting program objectives.

18.2 DESCRIPTION

18.2.1 IP's Quality Assurance program includes provisions for l planned and periodic audits designed to verify compliance with the requirements of the IP Nuclear Quality Assurance Program and to determine the effectiveness in implementing the program objectives. The audit program provides for the following: l g 3. Provisions are made for both internal and external audits. l

b. Audits include the full range of activities within the scope of the IP Nuclear Quality Assurance Program. These audits shall encompass:
1. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 24 months;
2. The performance, training and qualifications of unit staff at least once per 24 months;
3. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 12 months;
4. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10CFR Part 50, at least once per 24 months;

(/

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,q ILLINOIS POWER NUCLEAR PROGRAM U ' " ", y QUALITY ASSURANCE MANUAL chapter is

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5. The Emergency Plan procedures at least once per 12 months; and implementing

., 6. The Security Plan and implementing procedures at least once per 12 months; l

7. Any other area of unit operation wonsidered appropriate by the NRAG or the Vice President; l
8. The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel; l
9. The fire protection equipment and program implementation shall be performed at least once per 12 months utilizing either qualified offsite licensee fire protection engineer (s) or an outside independent fire protection consultant; l
10. An inspection and audit of th fire protection and loss prevention program shall be performed by an outside qualified fire O- consultant at intervals no greater than 36 months; l
11. The radiological environmental monitoring program and the results thereof at least once per 24 months; l
12. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; l
13. The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months, and; l
14. The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977, at least once per 24 months. l Additionally, program audits include interface between IP audited organizations and other -

affected organizations and USAR requirements. l

,. c. Provisions are made for regularly scheduling audits based upon the status and importance of the U' D activities. l

d. A qualification system is established for auditing personnel. Independent certifying agencies may be Page 2 of 4 REVISION 26 j

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,r ILLINOIS POWER NUCLEAR PRO 2 RAM i", , d E QUALITY ASSURANCE MANUAL chapter 18 used for the development and administration of lead auditor examinations. l

e. Personnel conducting audits do not have any direct responsibilities for the activities being audited. l

'f. The audit the otherteam leader audit is charged team members with instructing during audit l preparation and performance. Personnel conducting audits shall have training and/or experience with the activities being audited. l

g. Written audit plans are developed which identify the scope, requirements, activities to be audited, organizations involved, applicable documents, schedule and written procedures or checklists to be used for each audit. Audit planning may credit reviews such as assessments or inspections performed by non- Audits sections of the Quality Assurance Department when determining the scope and activities to be assessed by an audit.
h. Audit results are documented, reports are generated and retained.
i. Audit reports are distributed to- responsible

( management of the auditing organization and to the appropriate managerial level of the organization having responsibility for the area or audited, activity l J

j. Appropriate corrective action is developed. l
k. Follow-up action (including re-audit) is taken to verify that corrective action has been completed and the resolution properly documented when indicated.

18.2.2 Audits are initiated as early in the life of the activity as practical consistent with the schedule for accomplishing the activity to assure timely implementation of the quality assurance requirements. Audits may be augmented at any time based on recommendations from the Nuclear Review and Audit Group, or Nuclear Program personnel as the scope of work and other requirements for auditing an activity change.

18.2.3 Audited organizations are required to review andl provide timely written response to audit findings stating corrective action taken or planned to correct deficient areas and prevent recurrence. Follow-up action to verify corrective action has been completed, and the resolution is properly documented, shall be taken when indicated. Audit program requirements are 1U; imposed on suppliers by appropriate contract or procurement documents. l Page 3 of 4 REVISION 26 l

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l PQ ILLINOIS POWER NUCLEAR PROGRAM L4au' QUALITY ASSURANCE MANUAL chapter la O 18.2.4 Reports of internal audits are forwarded to the Nuclear l b Review and Audit Group and the Independent Safety Engineering-Group for program evaluation. Ip Management obtains independent audits of the Quality Assurance organization.

18.3 RESPONSIBILITIES 18.3.1 Nuclear Program Departments --

a. Maintain a program for determining and implementing corrective actions to audits.

18.3.2. Nuclear Review and Audit Group

a. Review reports of internal audits for program evaluation

, 18.3.3 Ouality Assurance l

a. Implement an internal audit program and audit each IP organization performing activities within the scope of the quality assurance program to verify that the requirements of this manual are met. being l p b. Implement an external audit program und audit d suppliers performing quality related activities to verify compliance with the supplier's respective quality assurance programs, contract, specifications and requirements, as defined on the procurement document. l
c. coordinate for the Nice President, the performance of independent audits of the Quality Assurance organization,
d. Implement a program for evaluating the adequacy of corrective actions to audit findings.

18.3.4 Nuclgpr Safety & Performance Impretement Denartment

a. Independent Safety Engineering Group review l reports of internal audits for program evaluation, r3 i

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V APPENDIX A v" GLOSSARY OF TERMS Accentance criteria - Specified limits placed on characteristics of an item, process or service defined in codes, standards or other requirement documents.

budit. -

A documented activity performed in accordance with written procedures or checklists to verify, by examination and evaluation of objective evidence, that applicable elements of the quality assurance program have been developed, documented and effectively implemented in accordance with specified requirements.

Auditor -

Any individual who performs any portion of an audit, including lead auditors, technical specialists, auditors-in-training and others, such as management representatives.

Authorized Insnection Aaency (AIA) - An agency designated as such by the appropriate legal authority of a State or Municipality of the United States or a Province of Canada or an insurance company authorized to write boiler and pressure vessel insurance in that (q jurisdiction in accordance with the provisions set forth in ASME N626, per the approved year / Edition.

Authorized Nuclear Inservice Insnector ( ANII) / Authorized Nuclear Insoector (ANI) - An authorized Nuclear Inservice Inspector and Authorized Nuclear Inspector is an employee of an Authorized Inspection Agency who meets the requirements of ANSI /ASME N626, per the approved year / Edition.

Certification - The act of determining, verifying and attesting in writing to the qualification of personnel, processes, procedures or items in accordance with specified requirements.

Certificate of Comoliance -

A written statement signed by a qualified party attesting that the items or services are in accordance with specified requirements and accompanied by l additional information to substantiate the statement.

Certificate of Conformance - A written statement signed by a qualified party certifying that items or services comply with specific requirements.

Cfqrtified Test Report - A written and signed document approved by a qualified party that contains sufficient data and information to verify the actual properties of items and the actual results of all required tests.

Characteristic - Any property or attribute of an ihem, process or service that is distinct, describable and measurable, as Page A-1 of 9 REVISION 26 l

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""dA APPENDx A GLOSSARY OF TERMS O conforming or nonconforming to specified quality requirements.

Quality characteristics are generally identified in-specifications and drawings which describe the item, process or service.

Chemical Cleanina -

Refers to the use of acids -and caustic substances applied to material or product forms during manufacture, maintenance or repair.

Codes - Collective term used to describe all t.he published codes applicable to Clinton Power Station operations, such as the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

Commercial Grade Classified Items -

Items which are: (1) not subject to design or specification requirements unique to NRC licensed facilities or activities; (2) used in applications other than NRC licensed facilities or activities; and (3) able to be ordered from the manufacturer / distributor on the basis of the manufacturer's published specifications or descriptions.

Condition Adverse to Ouality -

An all inclusive term used in reference to any of the following: failures, malfunctions, n deficiencies; deviations, defective items and nonconformances.

U control Stamn - A stamp used to mark a unique identification of inspection or test status upon items, tags, labels, routing cards or records traceable to an item. Control stamp impressions clearly identify the person who applied it such that traceability to their authorization is provided.

Correction - The process of bringing a nonconforming item into conformity with an approved design, i.e., implementation of a dispositioned nonconformance document.

Corrective Action - The action required to correct or resolve adverse conditions in equipment, material, processes, procedures or activities when noted. Action taken may be remedial action to correct the specific condition, corrective action to preclude recurrence, or both.

CES - Abbreviation for Clinton Power Station.

Denartmental Procedures or Instructions -

Procedures or instructions approved and isnued within a department which provide detailed direction to personnel.

Deviation -

A nonconformance or departure of a characteristic from specified requirements.

b' Documents - ' Collective term used to describe all written or pictorial information that directs or shows how an activity is to be. accomplished. Documents include, but are not limited to ,

drawings, procedures, instructions and changes thereto.

Page A-2 of 9 REVISION 26 l

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL

('L J. B B 1: u APPEnox A ssARy oF TERxS O

Documentation - Any written or pictorial information describing, I defining, specifying, reporting or certifying activities, requirements, procedures or results.

Examination -

An element of inspection consisting of investigation of materials, components, supplies or services to determine conformance to those specified requirements which can be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation, gauging and measurement.

Extended Ouality Assurance Procram -

The selected use of technical and management controls to improve the operational performance of equipment important to reliable station operation but not included in compliance based quality assurance programs, External Audits - Audits of those portions of contractors',

vendors' and suppliers' quality assurance program activities not retained under IP's direct control and t within the IP organizational structure.

Facility Review Groun (FRG) - An on-site committee whose function p is to advise the Manager -

Clinton Power Station on matters Q related to nuclear safety.

Follow-uo - Action involving direct communication with the responsible organization to assure a timely written response to findings, adequacy of the response and corrective action accomplishment as scheduled.

Hardware Chance - A plant design change that can include but is not limited to hardware, configured software or design document changes.

Hold Point - Point in a procedure or work document at which the performer is required to stop and notify inspection personnel to allow for planned inspections. The work activity shall not proceed without the point being signed by inspection personnel, or inspection personnel being notified and authorizing the activity to proceed, or the point waived / reclassified.

Independent Review -

Review completed by personnel not having direct . responsibility for the work functions under review regardless of whether they operate as a part of an organizational unit or as individual staff membe"s.

Inservice Insnection -

A mandauory program of examinations, testing, inspections and control .of repairs and replacements to

(\ ensure adequate safety in maintaining the nuclear power plant and to return the plant to service in a safe and expeditious manner in accordance with the CPS ISI Program Manual.

Page -A-3 of 9 REVISION _26 l

l lLLINOIS POWER NUCLEAR PROGRAM '} APPENDX A QUALITY ASSURANCE MANUAL _ L J OLOSNARY OF TERMS O

V Inonection -

A phase of quality control which by means of examination, observation or measurement determines the conformance of mat.erials , supplies, components, parts, appurtenances, systemt, processes or structures to predetermined quality requirements.

I Interface - When two or more organizations have respEnsibilities for accomplishing an activity, the functional relationship that one organization has to the others in completing the activity is called an " interface" relation. One example of interface is when one organization must perform a step which is a prerequisite to another organization accomplishing its function. Interface can also mean that several organizations accomplishing similar activities are under the coordination control of one organization.

Internal Audits -

Audits of those portions of IP's Quality Assurance program activities retained under direct Company control and within the IP organizational structure.

JE - Abbreviation for Illinois I ower.

Item - Any level of unit assembly, including structure, system, sub-system, subassembly, component, part or material.

G Lead Auditor - An individual qualified and certified to organize and direct an audit, report audit findings and evaluate corrective action.

Measurina and Test Equipment - Equipment used to quantitatively generate or measure physical parnmeters with a known degree of accuracy for the purpose of calibration, inspection, test or repair of plant mechanical, electrical or instrument / control equipment. (This does include permanently installed instrument and control devices.)

Noncomplianca -

A failure to comply with a regulatory requirement.

Nonconformance - A deficiency in characteristics, documentation or procedure which renders the quality of an item unacceptable or indeterminate. Examples of nonconformances include physical defects; test icilures; incorrect or inadequate documentation; or unauthorized deviations from prescribed processing, inspection or test procedures.

Nuclear Review and Audit Group (NRAG) - A committee responsible for the independent safety review function.

[) Obiective Evidence -

Any statement c,f fact, it.f ormation or V record, either quantitative or, qualitative, pertaining to the quality of an item or service based on observations, measurements or tests which can be verified.

Page A-4 of 9 REVISION _ 26 l

l ILLINOIS POWER NUCLEAR PROGRAM t. ,u J $ APPENDx A QUALITY ASSURANCE MANUAL at,OSSARY OF TERMS n

U Ooerable/Ocerability -

A system, subsystem, train, component or device shall be operable or have operability when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, coaling or seal water, lubricat. ion or other auxiliary equipment that are required for the system, subsystem, train, component .on device to perform its function (s) are also capable of performing their related support function (s). NOTE: Safe operation of the plant is determined by CPS licensed operators.

Permanently Installed Instrument and Control Devices -

The installed plant equipment including computer points used in determining acceptance criteria of Technical Specification surveillances (Category A Instruments).

Plant Chance - A change similar to that of a hardware change except that it does not impact the Design Bases, does not have major impacts and does not contain an unreviewed safety question.

Plant staff - The organization which is directly responsible for the operation of the Clinton Power station. The Plant Staff includes operations, technical, maintenance, radiation protection, and support departments.

A or describes how an Q Procedqg -

A document that activity is to be performed.

specifies It may include methods to be employed, equipment or materials to be used and sequence of operations.

Procurement Doruments - Contractually binding documents that identify and deiine the requirements which items or services must meet in order to be considered acceptable by the purchaser.

Procurement documents include such items as contracts, letters of intent, purchase orders er proposals and their acceptance which authorizes the seller to perform services or supply equipment, materials or facilities on behalf of the purchaser.

Oualification - (Personnel) - The characteristics or abilities gained through training or experience or both that enable an individual to perform a required function.

Onality Assurance - All those planned and systematic actions necessary to provide assurance that a structure, system or component will perform satisfactorily in service.

Ouality Assurance Record - Those delineated completed records which furnish documentary evidence of the quality of items and/or activities affecting quality within the scope of the IP Nuclear Quality Assurance Program.

V Ouality Control - Those quality assurance actions which provide a means to control and measure the characteristics of an item, j process or facility to established requirements.

Page A-5 of 9 REVISION 26 l

5 (LLINDIS POWER NUCLEAR PROGRAM i l APPEnox A I QUALITY ASSURANCE MANUAL ' ' ~ '81ASSARY OF TERMS O

~

puality Relateri - Activities which intluence quality of safety- l related items or work related to those systems, structures and components as identified in the USAR, Table 3.2-1, including deuign, purchasing, fabricating, handling, _ shipping, storing, cleaning, preserving, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling or modifying.

Receint Inupection - An inspection which verifies that items are in satisfactory condition, that they match the purchase order requirements and that required documentation accurutely reflects the item (s) received. Vloual and physical inspection will be performed as neccanary to determine the acceptability of the item (s) .

Rectulations - Collective term used to describe the governing directives and laws applicable to Clinton Power Station operation, such as the Code of Federal Regulat ! sno.

Repair - The process of restoring a nonconforming characteristic to a condition such that the capability of an item to function reliably and safely is unimpaired, even though that item still may not conform to the original requirement. For ASME Section XI Activities, " REPAIR" is the process of restoring a non-conforming item by welding, brazing or metal removal such that existing O design requirements are met.

Ranolution -

The process by which a nonconforming item is corrected or determined to adequately perform its design function without adversely af fecting safety. The resolution may contain crantrols or limitations that are to apply until the nonconformance is fully corrected.

Rework - The process by which a nonconforming item is made to conform to prior specified requirements by completion, remachinirg, reassembling or other corrective means.

Hafety Related - Systers, structures and compone; a which are considered important to safety because they perform safety actiono required to avoid or mitigate the consequences of abnormal operation transients or accidents. in addition, design requirements are placed upon such equipment to assure the proper performance of safety actionu, when required. Safety related items are those designated Seismic Category 1, Safety Class 1, 2, 3 "Other" and Electrical Class 1E as identified in the USAR, Section 3.2.

Scone - The area covered by a given activity or subject.

Seiemic Claap_11.1.p_at;ign - Plant structures, systems and components O important to safety which are designed to withstand the effects of a safe shutdown earthquake (SSE) and remain functional if they are necessary to assure:

Page A-6 of 9 REVISION 26 I

ILLINOIS POWER NUCLEAR PROGRAM AppEnox A QUALITY ASSURANCE MANUAL , ~GbOSSARY OF TERMS O a. The integrity of the reactor coolant pressure boundary, or

b. The capability to shutdown the reactor and maintain it in a safe condition, or
c. The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10CFR100.

Plant structures, systems and components, including their foundations and supports, which are designed to remain functional in the event of an SSE are designated as Seismic Category 1 as indicated in Table 3.2-1 of the CPS USAR.

Sinnificant Condition Adverse to Ouality and/or Safety -

A condition that affects or is likely to have an effect on, or influence, the safe operation of the plant, the capability to shut down the reactor and maintain it in a safe shutdown condition or the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures.

Source Insnection - An inspection performed at the location of item procurement, supply or manufacture for the purpose of verifying that the item meets specified requirements.

Snecial Processes -

Term used to describe those activities or processes in which the end result or product quality either cannot be readily verified when the process is complete or it is not prudent to delay verification until process completion. The assurance of quality is heavily dependent upon control of the process and the skills of the personnel who perform the process.

EAmidarda - Term used to describe the results of standardization As efforts which have been approved by recognized authorities.

used herein, standards refer to either publications describing an acceptable method of implementing or performing an activity or an item of known value used for comparison.

Ston Work - Collective term used to describe the following three levels of stopping work activities: I

a. The stopping of a single or specific work activity by Quality Assurance personnel. l
b. A hold imposed by a Department Head on a department or general work activity,
c. A Stop Work Action initiated by the Manager - Quality l Assurance.

Page A-7 of 9 REVISION 26 l

ILLINOIS POWER NUCLEAR PROGRAM l APPENDX A QUALITY ASSURANCE MANUAL

~ " - - &$SARYOFTERMS O suonlier - Any individual or organization that furnishes items or services to IP under a procurement document.

Surveillance - A review or observation of an activity, process or product to verify that an action has been or is being accomplished in accordance with applicable requirements and management expectations.

Eurvey - A documented evaluation of an organization's ability to perform activities as verified ay a determination of the adequacy of the organization's qualit, program and by a review of the implementation of that program at the location of work.

System Safety Classificationn - Structures, systems and components are classif.ied as Safety Class 1, Safety Class 2, Safety Class 3, Safety Class Other or Class IF in accordance with the importance to Nuclear Safety. Equipment is assigned a specific safety class, recognizing that components within a system may be a differing safety importance. Definitions of various Safety Classes are:

Safety Class 1 - Components of the reactor coolant pressure boundary or core support structure whose failure could cause a loss of reactor coolant at a rate in excess of the normal make-up O system.

Splety Class 2, - Structures, system and components, other than service water systems, that are not Safety Class 1, but are necessary to accomplish the safety functions of:

a. Inserting negative reaet'rity to shut down the reactor,
b. Preventing rapid insertion of positive reactivity,
c. Maintaining core geometry appropriate to all plant process conditions,
d. Providing emergency core cooling,
c. Providing and maintaining containment,
f. Removing residual heat form the reactor and reactor core, or
g. Storing spent fuel.

Saf.ety Class ;). - Structures, systems and components that are not safety Class 1 or Safety Class 2, but whose function is to process radioactive fluids and whose postulated failure would result in conservatively calculated offsite doses that exceed 0.5

\ rem to the whole body or its equivalent to any part of the body in accordance with Regulatory Guide 1.26.

Page A-8 of 9 REVISION 26 l

ILLINol8 POWER NUCLEAR PROGRAM

! QUALITY ASSURANCE MANUAL

' '"" b[LoSsAny or TenMS

!O safetv class aother" - Structures, systems and components used in the power conversion or other portions of the facility which have no direct safety function, but which may be connected to -or influenced by the equipment within the safety classes 1, 2 or 3. ,

rJass 1E - The safety classification of the electric, equipment.

and systems that are essential to emergency reactor shutdown, containment isolation, reactor cora cooling and containment and reactor heat removal or otherwise are essential in preventing significant release of radioactive material to the environment.  ;

(Structures, systems and component safety classifications and reinted Quality Assurance Program requirements classifications are summarized in Table 3.2-1 of the USAR.)

} Technical snecifications - Appendix A to the operating License containing the design and performance criteria and operating limits and principles to be observed _during critical testing, startup, power operations, refueling and maintenance onc: rations.

Traceability - The ability to identify the origins of a particular item when required by adopted codes or standards.

USAR - Abbreviation for the Updated Safety Analysis Report, which

'Os is the document submitted by Commission in accordance with 10CFR50.71.

IP to the Nuclear Regulatory Use-Aq-la - A disposition which may be imposed for a nonconformance when it can be established that the discrepancy will result in no adverse conditions to safety and that the item under consideration will continue to meet all engineering functional requirements including performance, maintainability,

- fit and safety. .

yerification - The act of confirming, substantiating or assuring that an activity or condition-has been implemented in conformance with the specified requirements.

Witness Point - Point in a procedure or work document at which the performer is required to stop and notify inspection personnel to allow for planned inspections. Once notification has been accomplished and the agreed to time (or a reasonable amount of time) has passed, the work activity may continue.

1 Page- A-9 of 9 REVISION 26 l

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL -

APPENDIX B SUPPLEMENTAL APPLICATION IP NUCLEAR QA PROGRAM l I

l This appendix details in matrix form the chapters of this manual which are applicable in full or in part to ,,

Fire Protection Security Environmental Radwaste/ Augmented D Systems Packaging and Transportation of Radioactive Material )

1 10CFR50, Appendix B requires that a quality assurance program be ,

established in writing and executed for activities affecting the safety-related function of designated structures, systems and components to an extent consistent with their importance to safety. Table 3.2-1 in the Clinton Power Station USAR identifies specifically those structures, systems and components that are important to safety.

Fire Protection, Security, Environmental and Radwaste/ Augmented D systems are specifically identified in Table 3.2-1 of the CPS USAR and/or highlighted in several Regulatory Guides that define and clarify their importance to the plant.

>O Regulatory Guide 1.120, " Fire Protection Guidelines for Nuclear Power Plants", Revision 1 (November 1977) states that, "A quality assurance (QA) program is needed to identify and rectify errors in design, construction and operation (of a fire protection system) and is an essential part of defense in depth."

Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Normal Operation - Effluent Streams and the Environment", Revision 1 (February 1979), states that, "The need of quality assurance is implicit in all requirements for effluent and environmental monitoring." Regulatory Guide 1.143, Revision 0 (July 1978) states that, "

...to ensure that systems will perform their intended function a quality assurance program sufficient to ensure that all design, construction and testing provisions are met should be established and documented."

Regulatory Guide 1.17, " Protection of Nuclear Power Plcnts Against Industrial Sabotage", Revis4.on 1 (June 1973), requires programmatic controls over the design, construction, testing and operation of the security system at nuclear power plants.

10CFR Part 71, " Packaging and Transportation of Radioactive Material", Section 71.101, " Quality Assurance Requirements",

requires that licensees have a quality assurance program that has been submitted to and approved by the NRC as satisfying the provisions of Subpart H of Part 71. Subpart H requires, in part,

/7 that licensees' quality assurance programs satisfy each of the V applicable criteria specified in Section 71.101 to an extent consistent with their importance to safety. Regulatory Guide 7.10, " Establishing Quality Assurance Programs for Packaging Used

.Page B-1 of 12 REVISION 26 l

a ILLINOIS POWER NUCl, EAR PROGRAM . .. j ) APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION

' O in the Transport of Radioactive Material", Annex 2, provideu quality assurance programs applicable to Procurement, IP NUCLEAR OA PROGRAM Use, Maintenance, and Repair of Packaging Used in Transport of Radioactive Material.

The extent to which the IP Nuclear Quality Assurance Program applies to each of the four areas varies as defined funther under subsequent sections of this appendix. The attached matrix

outlines which chapters of this manual apply to Fire Protection, Security, Environmental and Radwaste/ Augmented D systems and  ;

Packaging and Transportation of Radioactive Material 1  !

1 i

A 4

h i

O Page B-2 o f ,_12 _ REVISION 26- l ,

. - . - - , - . , - = _ _ - .  :. . _-. - .- , _ _ - - . . _

1 p , 3  :

ILLINOIS POWER NUCLEAR PROGRAM L- " " "

APPENDIX B  !

QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION  ;

IP NUCfEAR OA PROGRAM MATRIX l CHAPTERS OF THE IP NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL APPLICABLE TO FIRE PROTECTION, SECURITY, ENVIRONMENTAL, AND RADWASTE/ AUGMENTED D, AND PACKAGING i I AND TRANSPORTATION OF RADIOACTIVE MATERIAL ,

i i OPERATIOlJAL FIRE SECURITY E11VIRON!4 ENTAL RADIOACTIVE PACKAGI!1G At1D QA 14ANUAL l'ROTECTION WASTE / TRANSPORTATION CllAPTER AUGl4ENTED D OF RADIOACTIVE 14ATERIAL

- 1 YES NO YES YES YES

] 2 YES NO YES YES YES YES YES

~

3 YES NO NO 4 YES NO YES YES YES 5 YES NO YES YES YES 6 YES NO YES YES YES 7 YES NO YES YES YES 8 NO NO YES NO YES 9 NO NO NO YES YES 10 YES NO NO YES YES j 11 YES NO YES YES YES 12 NO NO YES NO YES 13 NO NO YES YES YES 14 YES NO YES .YES YES 15 YES NO YES YES YES 16 YES YES YES YES YES 17 YES YES YES YES YES 18 YES YES YES YES YES NOTE: Structures, systems and components subject to the above requirements are described by USAR Table 3.2-1 and further defined by engineering specifications, drawings, procedures, instructions, other documents, etc.

Page B-3 of 1 REVISION. 26 l

.R ILLINOIS POWER NUCLEAR PROGRAM L g ;B L APPENoIx a QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION IP NUCLEAR OA PROGRAM FIRE PROTECTION Chapter 1 - Applicable I

chapter 2 - Applicable Chapter 3 - Applicable Chapter 4 - Applicable. Specification of quality assurance program requirements for suppliers of fire

,rotection a materials, equipment and services shall ae on a case-by-case basis. Commercial grade or off-the-shelf items may provide an acceptable level of quality based on the. nature of the item. This ,

determination shall ne made by Engineering personnel prior to issuance of procurement documents Chapter 5 - Applicable Chapter 6 -

Applicable chapter 7 - Applicable. Suppliers providing material, equipment i and services for fire protection shall be subject to source evaluation and surveillance. The extent of imposition of these requirements shall be determined on a case-by-case basis by the design organization responsible for review and approval of the procurement specifications. Measures shall be established, as appropriate, for examination of products upon delivery.

Chapter 8 - Not Applicable Chapter 9 - Not Applicable Chapter 10 - Applicable only to inspection of those items and activities affecting the fire protection system within the quality assurance boundaries as specified in the USAR, Table 3.2-1 and further amplified by the appropriate design drawings.

Chapter 11 - Applicable Chapter 12 - Not Applicable Chapter 13 - Not Applicable Chapter 14 -Applicable-Chapter 15 - Applicable D . Chapter 16 - Applicable Page 'B-4 of 12 REVISION 26 l

ILLINOIS POWER NUCLEAR PROGRAM .,,,IhAPPFNoIxa QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION IP NUCLEAR OA PROGRAM O Chapter 17 - Applicable to documents designated as Quality Assurance Records generated in the implementation of the Fire Protection program and consistent with the requirements identified in Chapter 10 above.

Records are prepared and maintained to furnish evidence that the applicable criteria discussed herein are being met for activities affecting the Fire Protection prograrr.

Chapter 18 - Applicable. Audits shall be performed and documented to verify compliance with the Fire Protection program, including design and procurement documents, instructions, inspection and test activ' procedures

. ties. and drawings and O

O Page B-5 of __12_. REVISION 26 l

t

, e

3 ILLINOIS POWER NUCLEAR PROGRAM - g ; ,, a G APpEnoIx a i QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION IP NUCLEAR OA PROGRAM [

Chapter 1 - Not Applicable Chapter 2 - Not Applicable i Chapter 3 - Not Applicable ,

Chapter 4 - Not Applicable Chapter 5 - Not Applicable Chapter 6 - Not Applicable Chapter 7 - Not Applicable Chapter 8 - Not Applicable e

Chapter 9 - Not Applicable Chapter 10 - Not Applicable Chapter 11 - Not Applicable Chapter 12 - Not Applicable Chapter 13 - Not Applicable Chapter.14 - Not Applicable Chapter 15 - Not Applicable Chapter 16 - Applicable Chapter 17 - Applicable to those records required by the CPS Physical Security Plan.

Chapter 18 - Applicable to the physical security of CPS and designated records.

Page _B-G_ of _1liL, REVISION 26 l

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

,, v

j C,_;F.y I

ILLINOIS POWER NUCLEAR PROGRAM j i i APPENDIX B l QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION IP NUCLEAR QA PROGRAM i ElWIRONMENTAL Chapter 1 - Applicable Chapter 2 -

Applicable Chapter 3 - Not Applicable f Chapter 4 -

Applicable to procurement of monitoring services to 1 be performed by contractors providing services '

dealang with radiological data and to radionuclide reference standards used for calibration of radiation measurement systems.

l Chapter 5 - Applicable to all activities related to carrying out  ;

I the radiological monitoring program including:

sample collectioni packaging, shipment and receipt of samples for offsite analytisi procurement, maintenance, storage and use of radioactivity ,

reference standards; calibraticn and checks of radiation and radioactivity measurement systems; and reduction, evaluation and reporting of data.

  • Chapter 6 - Applicable to procedures and instructions required by Chapter 5.

Chapter 7 - Applicable to radionuclide reference standards used for calibration of radiation measurement systems and to radiological monitoring activities (services) provided by contractors.

Chapter 8 -

Applicable only to radiological samplo collection,

. identification, packaging, shipping, receiving, storage and analysis. >

Chapter 9 - Not Applicable Chapter 10 - Not Applicable Chapter 11 - Applicable to radioactivity measurements of samples, instrument backgroundo, replicate samples and analytical blanks; data reduction and verificationi computer program documentation and verification.

Chapter 12 - Applicable to laboratory instruments for radiation '

and radioactivity measurement, continuous radiological effluent monitoring systems and flowrate measuring devices associated with radiological effluent monitoring systems.

Chapter 13 - Applicable to radiological samples only.

Chapter 14 - Applicable to continuous radiological effluent monitoring systems equipment only.

Page. B-?" of ._1?,_. REVISION 26 l ,

-_ ._._________.__a.__._ . - _ . . . _ _ _ . _

m.

>b ILLINOIS POWER NUCLEAR PROGRAM ." -

EA "~uoIx a QUALITY ASSURANCE MANUAL SUPPLEMENTAL APP: , TION Chapter 15 - Applicable Chapter 16 - Applicable  !

I Chapter 17 - Applica1>1e to personnel training and qualification; field and in-plant collection of sampless,pontinuoue offluent monitoring; sample receipt and laboratory i identification; sample preparation and radiochemical processing; . radioactivity measurements of samples, '

instrument backgroundo and analytical blanks; data reduction and verification; instrument calibration and calibration standards; computer program j documentation; audits; and corrective action.

Chapter 18 - Applicable i

i O

l 1

1 4

i Page B-8 o f __12_. REVISION 26 l

p 15 lLLINOIS POWER NUCLEAR PROGRAM J "*" "3 I' APPENDIX B {

QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION i 1

IP NUCLEAR OA PROGRAM  !

RADIOACTIVE WASTE / AUGMENTED "D"  ;

l' Chapter 1 - Applicable Chapter 2 - Applicable Chapter 3 - Applicable Chapter 4 - Applicable. Specification of quality assurance program requirements for suppliers of radioactive  !

wasto/ augmented D materials, equipment and services shall be on a case-by-case basis. Commercial grade or off-the-shc1f items may provide an acceptable level of quality based on the nature of the item.

This determination shall be made by Engineering personnel prior to issuance of procurement documents.

Chapter 5 - Applicable Chapter 6 - Applicable Chapter 7 - Applicable. Suppliers providing material, aquipment and services foi radioactive waste / augmented D shall C be subject to source evaluation and surveillance.

The extent of imposition of these requirements shall be determined on a case-by-cace basis by the design organization responsible for review and approval of the procurement specifications. Measures shall be established, and appro for examination of products upon delivery. priate, Chapter 8 - Not Applicable Chapter 9 - Applicable to the qualification of welders and welding procedures (ASME Section IX) for Radwaste/ Augmented "D system. ) Pressure boundaries only.)

Chapter 10 - Applicable only to inspection of those items and activities affecting Radwaste/ Augmented D systems within the quality assurance boundaries as specified in the USAR, Table 3.2-1, and further amplified by the appropriate design drawings.

Chapter 11 - Applicable .

Chapter 12 - Not Applicable Chapter 13 - Applicable

%j Page B-9 of A REVISION 26 l

1 i s ILLINOIS POWER NUCLEAR PROGRAM  !,,, 2 w a ' *! APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION IP N1! CLEAR OA PROGRAM O Chapter 14 - Applicable i Chapter 15 - Applicable l

Chapter 16 - Applicable l

Chapter 17 - Applicable .. ,

Chapter 18 - Applicable O

A Page B-10 of .liL. REVISION 26 l

l l

ILLINOIS POWER NUCLEAR PROERAM I. ' j [ kAPPENDIx a QUALITY ASSURANCE MANllAL SusbLEMENTAL APPLICATION IP NUCf SAR OA l'ROGRAM PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL i

Chapter 1 - Applicable Chapter 2 - Applicable Chapter 3 - Applicable, design activities are ncit normally f performed by Clinton Power Station for radioactive material packaging however, audits of suppliers .

establish that the design was accomplished under  !

control of an NRC approved QA program. ,.

Chapter 4 -

Applicable Chapter 5 - Applicable Chapter 6 -

Applicable l

Chapter 7 - Applicable, measures such as source surveillance and -

audits of records should be taken as appropriate to ensure that the design and fabrication of packaging were performed under the control of an NRC-approved i QA program.

, Chapter 8 -

Applicable Chapter 9 - Applicable, special processes such as welding or nondestructive testing are not normally performed by ,

Clinton Power Station. However, if packaging requires major repairs necessitating use of special processes, e.g., welding or heat treating, measures shall be established to ensure that the special processes are controlled.

Chapter 10 - Applicable, visual inspections shall be performed upon receipt of packaging to ensure compliance with certificates of compliance.

Chapter 11 - Applicable

' Chapter 12 - Applicable Chapter 13 - Applicable, all conditions identified in a certificate of compliance when using packages shall be adhered to.

Chapter 14 - Applicable Chapter 15 - Applicable Page B-11 of .12_ REVISION 26 l

____..__2_ . - _ . - _ .

i ILLINOIS POWER NUCLEAR PROCRAM i , J APPENDIX D QUALITY ASSURANCE MANUAL duppneriet$rA APPLICATION

, IP NUCLEAR OA PRoGBAM l

__ Chapter 16 - Applicable, measures are established or obtaining corrective actions from suppliers and for ensuring i that follow-up is documented to verify that j

corrective actions were implemented and effective. ,

Chapter 17 - Applicable, records showing evidence of delivery of packages to a carrier and proof that all NRC and DOT requirements have been satisfied shalI' also be 4

retained.

? l Chapter 18 - Applicable, audits are performed on the supplier of '

packaging to ensure compliance with the certificate of compliance.

1 l

4 0 .

Page B-12 of 1 REVISION _ 26 .l

-. _- - . _ . _ . . - - . .-, . ~ . - . - . . - . . - - _ . . _

twos Power Company (

Cinon Power Stanon  ;

. P O. Bon 678 Clinton, il 61727 O 7el 217 935 8881 c

P(WWER January 12, 1998 l f

To Whom It May Concern:

Enclosed is a review copy of Revision 26 of the Illinois Power Nuclear Program Quality Assurance Manual. This copy is intended for the Reviewer's use only. Deletions from Revision 25 of the Illinois Power Nuclear Program Quality Assurance Manual are identified by red text, including strikethrough of the text. .

Additions to Revision 26 of the manual are identified in blue or purple, bolded text. Those portions of the manual that have not been changed are identified in black text.

Pagination of this review copy is not correct. Format of the individual chapters (i.e., headers and footers) is not consistent, and spacing of the text is not correct. The intent of the document is to aid the reviewer in distinguishing changes.

The approval copy of the manual is correctly paginated and formatted.

O V The review copy of the manual does not include authorization signatures. The approval copy of Revision 26 of the Illinois Power Nuclear Program Quality Assurance Manual does include all approval signatures.

Page numbering in the associated Illinois Power Nuclear Program Quality Assurance Manual Revision 26 Matrix of Changes corresponds to the pagination of the approval copy; not the pagination of this review copy.

If you have any questions, please contact me at (217)935-8881, extension 3144, or at E-mail address dan _basham@illlinova.com.

fey W Dan V. Basham Supervisor-Quality Systems DVD/mmk Enclosure O

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL h AVIIIORIIATJDH The purpose of the Illinois Power Nuclear Quality Assurance Program is to provide for safe and reliable operation of the Clinton Power Station with planned and systematic actions nacissary to provide adequate confidence that structures, systems, or components will perform satisf actory in service. The quality assurance program has been designed to ensure the accomplishment of this objective and function in preventing or mitigating the consequences of postulated accidents which could cause undue riak to the health and safety of the public.

The quality assurance program described in this manual reflects Illinois Power's policy and is applicable to all personnel and activities affecting the safe operation of the Clinton Power Station. This manual has been prepared to document the systems in effect for assuring that operation of the Clinton Power Station meet or exqeed quality requirements of applicable specifications, rules, and governing regulations.

The Manager-Quality Assurance shall have complete authority and responsibility to promulgate the quality assurance program, to ensure its implementation, and to verify compliance there with, without undue regard for cost and schedule. This includes the initiation of stop work action for activities which are not in 77 compliance with the requirements established by the Illinois Power V Nuclear Quality Assurance Program or when conditions exist which prevent the attainment of the required quality.

It is realized that quality can only be achieved by those personnel who perform the work. Therefore, each and every employee must consciously implement the requirements of the Illinois Power Nuclear Quality Assurance Program as the requirements apply to the activities being performed.

.rthermore, it is the responsibility of all departments and personnel to comply with the requirements of the Illinois Power Nuclear Program Quality Assurance manual to achieve full implementation and maintenance of this policy.

The effective date of revisions to this manual shall be thirty (30) calendar days from the date of distribution to allow for procedure changes and training.

Vice President / Dato O(m .

Page_L REVISION 16_

ILLINOIS POWER NUCLEAR PROGRAM i

QUALITY ASSURANCE MANUAL

,O QUALITY ASSURANCE PROGRAM 9_QNCURRENCE AUTHORIZATION i

The lilinois Power Nuclear Program Quality Assurance Program (QAP) applies to l j every member of the company performing safety / quality related work at Clinton

! Power Station. Specific responsibilities shall be assigned by lilinois Power i

management and supervision, consistent with the requirements described in the ,

lilinois Power Nuclear Program Quality Assurance Manual. The main responsibility i

i for the Quality Assurance Program is canied out by IP departments in recognition of the QAP responsibilltios, Illinois Power Nuclear Program Quality l ,

Assurance Manual Revision 26 is given the following Departmental Concurrence Authorizations:

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W.D. Romberg, Manager G.L. Baker, Manager j Clinton Power Stetion Quality Assurance

! J.F. Palchak, Manager L.S. Wigley, Manager

Nuclear Training & Support Nuclear Station Engineering l K.F. Johnson, Manager R.F. Phares, Manager Purchasing and Material Control Nuclear Safety and Performance improvement

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, Page_il REVISION 16

ILLINOIS POWER NUCLEAR PROGRAM ,

QUALITY ASSURANCE MANUAL TABLE OF CONTENTS i O Chapter Chapter

[htsbar Tit 1e i Authorization Table of Contsnts 11 Concurreuce Authorization introduction 111 Table of Contents Authorization iv&++ Introduction 1 Organization 2 Quality Assurance Program 3 Design Control 4 Procurement Document Control ,

5 Instructions, Procedures & Drawings l 6 Document Control l

7 Control of Purchased Material, Equipment and O Services 8 Identification and Control of Materials, Parts and Components 9 Control of Special Processes 10 Inspection 11 Test Control 1 12 Control of Measuring and Test Equipment 13 Handling, Storage and Shipping 14 Inspection, Test and Operating Status 15 Nonconforming Materials, Parts or Components

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16 Corrective Action 17 Quality Assurance Records 18 Audits

(} Appendix A Appendix B Glossary of Tenns Supplemental Application - IP Nuclear Quality

. Assurance Program Page lii REVISION 26

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ILLINOIS POWER NUCLEAR PROERAM .

QUALITY ASSURANCR MANUAL INTRODUCTION O INTRODUCTION Illinois Power Company (IP), as thei ie+ t owner of Clinton l Power Station (CPS), has ultimate responsibility for the quality assurance program which is applied to CPS. The program is designed to meet the requirements of Title 10 of the Code of Federal Regulations (CFR), Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants;" M+e 10CFR of the Ccdc of Pederal Rcgulations, Part 71, Subpart H, " Quality Assurance for Packaging and Transportation of Radioactive Material" (with the exception of design, fabrication, assembly, and testing of packaging); and the American National Standard ANSI N18.7 (1976), " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants".

The IP Nuclear Quality Assurance Program applies to those activities associated with or affecting the ability of the plant's structures, systems, and components to function in preventing, or mitigating the consequences ofr postulated l accidents which could cause undue risk to the health and safety of the public. These activities include operating, maintaining, repairing, refueling, modifying, and other associated activities such as radiological environmental monitoring, radioactive material packaging and shipping, fire protection, and security programs. The structures, systems, and components to which the O activities and programs apply are delineated in Table 3.2-1 of the Updated Safety Analysis Report (USAR).

This manual is arranged in eighteen chapters which correspond with the eighteen criteria contained in 10CFR50 Appendix D and 10CFR71, Subpart H. Each chapter is further l broken down into three main sections which describe the purpose and scope of that chapter, a description of the quality program, and the division of responsibilities. The Quality Assurance Nuclear Assessment organization approves the distribution and is responsible for the maintenance of this manual in accordance with approved departmental procedures.

Appendix A of this manual is a glossary of terms applicable to the Illinois Power Nuclear Quality Assurance Program.

Appendix B of this manual details the scope of its application with respect to activities associated with Fire Protection, Security, Environmental, Radwaste/ Augmented-D Systems and Packaging and Transportation of Radioactive Material.

Centralized Coa.mitment Tracking numbcrs arc located directly af ter the applicabic scntcncc or paragraph in thc manual . These numbcrs arc in thc format (CCT XXXX; and providc a link to the eiesing documcatsr Page iv REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER O 1 CRGANIZATION l i

4 l 1.1 PURPOSE / SCOPE The purpose of this chapter is To-def inc thc rc qui rcmc nt-s for and--t o describe the organizational structure, functional responsibilities and levels of authority concerning the ,

performance of activities which affect the safety-related '

f unctions of structures, systems, or components for the Clinton

. Power Station.

1.2 DESCRIPTION

1.2.1 organizational structuring and functional l responsibility assignments are based on recognition of quality

assurance as an inter-disciplinary function with quality-related activities being performed by many organizational components and individuals from top-level management to individual workers.

1.2.2 The authorities and responsibilities of persons and l organizations performing quality-related activities are Those persons l O established, ass:.gned and documented. (CCT 0300) and organizations assigned quality assurance functions are given appropriate and sufficient authority and organizational freedom from cost and scheduling considerations to identify quality

, problems; recommend solutions; verify implementation of the solutions; and control-- processing, delivery, installation, or l utilization of nonconforming items until proper dispositioning has occurred. ( CCT 0 3 07 )-

Corporstc Nuclear Proccdurcs (CNP) spccify thc msnagement-policics for carrying out thc Illinois Poscr Company Nuclear Program-i n sccordancc with reguistory scquircmcnts sad the

!!1inois Powcr Company commitments to rcgulatory sgcncics.(CCT OMO ) --Ba c h CNP is reviewed snd concurrcd with by rcsponsibic depsrtmcnt msnagcmcat for incorporstion of quality asstreenee progrsm scquircmcnts. (CCT 0300) Thc CN Ps -- e rc spprovcd for use by thc IP corperstc officcr(s) rcsponsibic for thc <-ctivitics covered by the-ENP, Corporstc Nuclear Proceduras requi:c the dcvclopment-end usc of dcpartmcatsi proccdurcs or instructions to describc irterf scas -and-necomplish the activitics coverca by the eNik-1.2.3 The organizational structure and functional l responsibility assignments are such that (1) attainment of quality objectives-is by individuals assigned responsibility for specifying quality requirements or performing work to specifications; (CCT 0100) and (2) personnel performing the

'j quality assurance functions of vcrification, .;urvcillanccprogram assessment, inspection and audits have direct access to responsible management, and organizational freedom, including Page 1 of 5 REVISION 26

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER h aufficient independence f rom cost and schedule when opposed to safety considerations.

1.2.4 Activities affecting safety related functions (job duties and responsibilities) have been identified. (CCT 030^)  ;

Effectiveness of the program is assured through  !

inspec tionsva ri f icat4 ens , surveillances, program assessments, l audits and by the authority / responsibility of individuals performing these activities to stop specific work activities where it appears that quality may be jeopardized., and the authority of tThe Manager - Quality AssuranceNuel-ear-Assessment has the authority to initiate a Stop Work Action. (CCT 01';2) The Upon the initiation of a Stop Work Action, the Manager - Clinton Power Station has the authority to bypass a stop work to --place the plant in a safe and stable condition.

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l ILLINOIS POWER NUCLEAR PrtOGRAM  !

QUALITY ASSURANCE MANUAL chapter 1 l 1.2.5 Inspection personnel are provided with procedures and instructions prior to performing inspection operations. (dBuring ,

plant operations emergencies, inspections may be performed under the dicaction of the duty shift supervisor whheut written procedures.) 4CCT 0%H- To further assure that inspections are  ;

done in a timely manner, specific inspection points are identified in work documents with provisions for notification of inspection, witness, and hold points. -feet 0300 l l OrganizationaLInterlates 3.2.6 Activities affecting the quality of safety-related systems, structures and components are considered quality assurance program activities and are performed by, or under the cognizance of various IP organizations. Any department may perform these quality assurance activities provided that personnel are adequately trained, qualified / certified, and these work activities are performed in accordance with approved procedures and instructions. Problems associated with meeting the requirements. of the Quality Assurance Program, or disagreements and/or disputes shall be brought to the attention of appropriate levels of management, including the Senior Vice

President - Energy Supply as necessary to obtain resolution.

1.2.7 Work may be delegated to qualified outside organizations by contract for such activities as derign, special O processes, inspections, etc. Selected work may be delegated to qualified outside organizations by Nuclear Program departments.

The responsibility for exercising engineering control rests with Nuclear Station Engineering, and operational controls with CPS Plant Staff. Prior to initiation of work, the qualified individual (s) or organizational elements within IP have their responsibilities identified for the control and quality of delegated work.

1.3 1.2.2 Organtention and--RESPONSIBILITIES This section describes the organizational structure and responsibilities within IP for managing and implementing the quality assurance program for the operation of the-CPS . (CCT MM+

4 1.3.1 Senior Vice President - Energy Supply The executivesenior Vice President -

Energy Supply has the overall responsibility for the-engineering, design, procurement, modification, testing, operation and quality assurance at CPS.

Execution of these responsibilities is delegated to a Vice '

presidenti 1.3.21.2.2.2 Vice President l The Vice President is responsible for maintaining and assessing the overall effectiveness of the Quality Assurance Program, and for assuring cyc rs4 9 ht-of the quality assurance program for effcctivencss. The _ Vice President is responsible for assuring Page 3 of 5 REVISION 26

I lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter i that the authority end independence of personnel performing O- quality assurance functions are such that they can effectively assure the conformance to quality requirements and are sufficiently independent from cost and scheduling when opposed to safety considerations.

1. 3 . 3 ; . 2 . 2 . ': Manager - Clinton Power Station l The Manager - Clinton Power Station reports to the Vice President and is responsible for the safe, reliable and efficient operation of the Clanton Power Station in accordance with the operating license. This includes ensuring that the IP Nuclear Quality Assurance Program, as described in subsequent sections of this manual, is incorporated in plant procedures and implemented by the Clinton Power Station organization.

1.3.41.2.2.4 Manager - Nuclear Station Engineering l The Manager - Nuclear Staticn Engineering reports to the Vice President and is responsible for the development, direction and overall coordination of power plant engineering activities performed by the Nuclear Station Engineering Department (NSED) for the Clinton Power Station. These responsibilities includes coordination of all interface with the Authorized Inspection Agency (AIA) , and provisions for the establishment of Authorized Nuclear Inspector (ANI) hold orf witness points and access to l O f acilities and records. The Manager - NSED ensures that these activities are performed in accordance with the requirements of the IP Nuclear Quality Assurance Program.

1.3.51.2.2.5 Manager - Nuclear Training & Support Ocrvicca l The Manager - Nuclear Training & Support services-reports to the l Vice President and is responsible for providing direction of nuclear training, emergency planning, par.t acrvicca emian+ensions- for-fitness for duty, material support, receiving, warehousing, records management, document control, safety, compliance to federa+-regulation of-personnel activitica, and for l corporate and plant integration in these functional support disciplines. The Manager - Nuclear Training & Support Cervices l ensures that these activities are performed in accordance with the requirements of the IP Nuclear Quality Assurange Program.

1.3.61.2.2.0 Nuclear Review and Audit Group l The Nuclear Review and Audit Group (NRAG) reports to the Vice President and is responsible for the independent safety review function. The NRAG functions in accordance with a written charter which delineates committee composition, responsibility and authority, subjects to be reviewed, reporting requirements and administrative controla under which the group operates.

n d' 1.3.71.2.2.7 Facility Review Group l Page 4 of 5 REVISION 26

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 1 The Facility Review Group (FRG) is Aan on-site committee whose l

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function is to advise the Manager - Clinton Power Station on matters related to nuclear safety.

1.2.2.0 knager---Hueteer Training Ph M anager Nuelear-Prain4 n u . w ,e-ee--the-hnager 01inten Power-Oto t4en-end-4c -respon sibi e fcr thc dirccticn and-management of the - Noelear Training-for-el4nton Pcwar Stat 4en-and-managetoene of-the--Emargency - Prcparedness Prcgram. The-Manage r Nue4 ear Praining---ensures thet--thene--eet iv i t i ea - 1rrc perfermed in neeerdanec with thc re qui rcme nt a = ef--the- .+--Nuclear--Cma+ity Atmurance-Programr 1.3.04.2.2.0 Manager - Quality AssuranceNuelear-Assessmand l The Manager - Quality AssuranceNuelear -Assessment reports to the l Vice President and is responsible for IP's overall Nuclear Quality Assurance Program. The Manager -

Quality A s su ranceNue+ ear-Assessment directs the Quality AssuranceNue4 ear Assessment activities related to the design, procurement, '

maintenanco modification, and operation of the Clinton Power Station. (CCT 0109F The Manager - Quality AssuranceNue4 ear Assessmene interfaces with the Nuclear Regulatory Commission, and the Authorized Inspection Agency for the Quality Assurance v Program.= (COT OM9F The Manager -

Quality AssuranceNuelear Assessment or the designated alternate has the responsibility and authority to stop unsatisfactory work during plant operation, as well as during plant modification, maintenance and in-service inspection periods, provided the health and safety of the public, or impact on capability to safely operate or shut down the plant are not adversely af fected. (CCT 0170) The-Manager Nucicar hesessmend-n-lee-ensurc a that thc Independent Safcty Pnginccring Givue functions nrc maintained acparate-and independent frcm the quality aseurancc f unc t ions-but-wi-th-app scpri ade-inter f a cc .

1.2.2.10 Di re c t or--bicensingl . 3 . 9 Manager-Nuclear Safety &

Performance Improvement (NSPI) s The Manager-Nuclear Safety & Performance Improvement Department reports to the Vice President and is responsible to ensure continued improvemente in tt ' plant's safety performance while continuing to safely operat. .he Clinton Power Station. This department is dedicated to the development, coordination, and monitoring of site-wide improvements to elevate identified programmatic weaknesses to management for timely corrective action. The department maintains the operating licenses and permits, manages the Updated safety Analysis Report (USAR),

manages the Environmental Report (ER) for continued programmatic compliance, and administers a tracking program for 10CFR21 items.

The Manager-NSPI ensures that the Independent Safety Engineering Group (ISEG) review function is maintained separate and independent from line management.

Page 5 of 5 REVISION 26

ILLINOIS PCWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 1 S The Man M r-NSPI ensures that the Corrective Acticn Group implements a Corrective Action Program (CAP) to assure conditions adverse to plant safety and/or quality are identified, evaluated, reported, corrected, reviewed and trended.

The Manager-NSPI

  • aures that these activities are performed in accordance with .ho requirements of the IP Nuclear Quality Assurance Program.

1.2.2.le Diteeter Licensing The-Dheeter Licensing raports tc the Vicc Pres ident-and is direet47--reapetwelc for prcyitif ng rc prc saatat ion and-intertnee with-regttheory-agencic s tc m24 nt ai n opc ra t-ieg--4 feenses-and permita for CPO, managemant-of--thc Updated -Cafc ty Analysis Rcpore HUGAR), t he--Envi ronmc nte l--Re, ort- ( C R ) , and thc admintetrat4en-of the-treeking-program f or 100FH21 i tems--The--Bi r c c t o r Liccnsing ensures that-thene-ac t i vi t ies-erc perfor d in accordancc with the requi-rements-et-thc I P IJuc 1 c a r Qua4-i-ty- Assuranc c P rog ram :-

1.3.101.2.2 it Manager - Purchasing and Material Control l The Manager -

Purchasing and Material Control reports to the Senior Vice President of the Support Services Business Group q (Headquarters) and is responsible for selecting qualified Q suppliers, arc aefteted from the% tali f icd Oupplier Li-st-as requhetfr-for preparing and issuing purchase orders and ensuring tnat they include necessary technical, quality and commercial terms and conditions, and that appropriate reviews, are accomplished prior to release of a purc'sse order. The Manager -

Purchasing and Material Control ensures that these activities are performed in accordance with the requirements of the IP Nuclear Quality Assurance Program.

1.2.3  !?uc 1 c a r_linsessment-Darmetmant I Geneea4-respensi bi1 i t its of the-depa r t me n t uith rcgard tc the Qua44ey-Assu enncc Program f cr C1i nton Powc r Otn+4en-4cehdc , but arc not limited tc, the followimgr

a. Prcpare-and-control the IP -!!ueleer Program Quality Assurenee-+4anual . (CCT 0311)
b. Vcrify thc impicmentatica of thc IP  !;uc1 car Quality Assurancc Program. (CCT 0101)-
c. If significant quality probicms arc identificdr

!?uclear Assessment pc rsonnel-havc thc - autheerty and rc spon s ibi-1-i t y tc stop spccific werk activitics pcnding sat +stnetcry rcaciut ion _ of thc identifica prcbicm, providcd t-hc hcalth and safcty

(~_] cf thc public cr impact en thc capability to v safely operatc cr shut acwn thc plent a r e -- n o t adversely affcctcd. (CCT 0104)

Page 6 of 5 REVISION 26

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  • de6e L 03 S M3AISION 29

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL n CHAPTER U 2 QUALITY ASSURANCE PROGRAM 2.1 PURPOSE / SCOPE The purpose of this chapter is to define Tthe IP Nuclear Quality l Assurance program applies to those activities such as design, procurement, fabrication, installation, modification, maintenance, repair, refueling, operation, inspection, and tests related t.o those systems, structures, and components as identified by the letter "B" or "H" in the Quality Assurance Requirements column in IISAR Table 3.2-1. (CCT 0335) This program shall be documented by policies, procedures, or instructions.Thts t-abi c of systcms, structurcs, and compor mts is kcpt cue ent and

+s" cvised and distributcd as a controlica documcnt in accordancc with approved proccdurcs. (CCT 0337) Appcndix "O" to thc IP Ntte4ea r Program Quality Assttrancc "anual describcs and spccifics a graded application of thc IP Nuclcar 'uality Assurancc Program to c e rte 21 n othcr activitics, systcm; and itcm3 at thc Clinton Powcr Otation, such as thc prcasurc boundarics of radweste attgmen t ed 0 systcms, portions of thc firc protcction systcm, sccurity systcm, cnviroi.mcntal monitoring, thc packaging and transportation of radioactivc matcrial. (CCT 0330) y

2.2 DESCRIPTION

i 2.2.1 Illinois Power Company's Nuclear Quality Assurance Program comprises all those planned and systematic actions necessary to provide adequate confidence that a Clinton Power Station structure, system, or component will perform satisfactorily in servico. Quality assurance includes quality control which comprises the verification of those physical characteristic- of material, structure, component, or system which provide a means to control the quality of the material, structure, component, or system to predetermined requiremente.

2.2.2 Illinois Power Company's Nuclear Quality Assurance l Program is based upon 10CFR50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants. "

(CCT 0010) The requirements of 10CFR71, subpart H, " Quality l Assurance for Packaging and Transportation of Radioactive Material" are also included. (CCT 30532) The CPS Inservice Inspection (ISI) Program Manual further defines the Quality Assurance Program for ASME Section XI Code activities.

Additionally, in USAR section 1.8, Illinois Power is committed to carrying out the provisions of various NRC regulatory guides and industry standards which further define Quality Assurance o Pprogram requirements. As uscd in this chaptcr, " Quality

(") Assttrancc" compriscs all thosc planned and systcmatic actions ncccssary to providc adequatc confidencc that a Clinton Powcr section structurc, systcm, or componcnt will pcrform estisfactorily in scrvicc. (CCT 0332) Quality assurancc includcs Page _L, of _1 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER quality control which compriscs thosc physical characteristics-of a atct4al, structurc, component, or systcm which providc a meetts to control thc quality of thc matcrial, structurc, componcnt, or aystcm to prcdctermined rcquircmcnts. (CCT 3333)

The Regulatory Guides are:

  • Regulatory Guide 1.26, Rev. 3, " Quality Group Classifications and Standards for Water , Steam , and Radioactive-Waste-Containing Components of Nuclear Power Plants";
  • Regulatory Guide 1.29, Rev. 3, " Seismic Design Classification";

D Page _.2_ of 5 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 2 G

Q

  • Regulatory Guide 1.30, Rev. O, "Qualjty Assurance Requirements for the Installation, Inspection and Testing of Instrumentation and Electric Equipment";
  • Regulatory Guide 1.37, Rev. O, " Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants";
  • Regulatory Guide 1.38, Rev. 2, " Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Water-Cooled Nuclear Power Plants";

e Regulatory Guide 1.58, Rev. 1, " Qualification of Nuclear Power Plant Inspection, Examination and Testing Personnel";

e Regulatory Guide 1.74, Rev. O, " Quality Assurance Terms and Definitions";

  • Regulatory Guide 1.88, Rev. 2, " Collection, Storage, and l Maintenance of Nuclear Power Plant Quality Assurance Records";

l O

V

+ Regulatory Guide 1.94, Rev. 1, " Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants";

  • Regulatory Guide 1.116, Rev. 0-R, "Quali ty Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems";
  • Regulatory Guide 1.123, Rev. 1, " Quality Assurance Requirements for Control of Procurement";
  • Regulatory Guide 1.146, Rev. O, " Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants".

2.2.3 The Quality Assurance program c'escription a'lso includes the following sections of the CPS Operational Requirements Manual (ORM). The CPS ORM contains administrative requirements which were removed from the CPS Technical Specifications with the implementa*.icn of the Improved Technical Specifications in January, 1996. The specific ORM sections are as follows:

  • ORM Section 6.5, Review and Audit;
  • ORM Section 6.8.2, Procedures and Programs -

Review and

% Approval;

  • ORM Section 6.8.3, Procedures and Programs - Temporary Changes and; Page _2_ of 5 REVISION 26

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 2

  • ORM Section 6,10, Record Retention. l 2.2.42.2.2 Ouality Assurance Program Revisions l The Quality Assurance program receives ongoing reviews and is revised as necessary to assure its continued effectiveness, The Quality Assurance Program Description, including the Quality Assurance Manual, is reviewed and updated in accordance with the requirements of 10CFR50.71, MAINTENANCE OF RECORDS, MAKING OF REPORTS. Changes made to the IP Nuclear Program Quality Assurance Manual which: 1) change or affect authority, independence, or management reporting levels previously established for organizations performing quality assurance functions; or 2) reduce commitments or effectiveness of quality l assurance functions specifically delineated in this manual in the i

Quality Assurance Program Description shall be submitted and approved by the NRC prior to change implementation. Quality Assurancc tiemual changcs which do not scducc thc Quality Assurancc program's commitmcnts in this manual shall bc submittcd i to the N"O for rcvxw on an annual basis. Caitorial changcs-or l personncl rcassignments of a non substantivc naturc do noe

\

n 1-- n, net n.. , nu_

u. n. m umm.

- - - s .e .: m u u mu . -. embm .u, n. nm v.r u l .wu..m . i m m m. umu, mmu. -mv mum ebengc to thc I" Nucicar Prcgram Quality Assurancc tianual shall O be in accordance with 10CPR50.54 (a) ,

1 2.2.3 Ouality Assurance Proaram Documcntation Phc IP Nucicar Quality Assurancc Program is catablishcd and supported by threc ticra at--doc umc nt s , cach succcasivc ticr t transmits rcquircmcats from a highcr icvci of authority to the i

ncxt successivc lowcr documer t 1 cycl. 'CCT 0330)

a. Policy Documcnt2-1-es"*cd by Corporatc "anagcmcat to promulgecc atthoritativc managcmcnt dircctivcs

, cstablishing -end dcfining Qtrality Assurance policics within ,mmm the Illinois Powcr Company Nucicar n ._vu_ _ u_ _. . . . . ,.mm,m1

. vu n b.1 I" Nucicar Proaram Ouality Assurancc 'innual dcacribcs thc objcctivcs, rcquircmcats, intcrfacc sciationships, and assignmcat of responsibilitics for accomplisning activitics which affcct thc safcty-rclatcd functions of systcms, structurcs, or ccmponcats. It contains thc minimum rcquircmcnts tc b; applicd by IP and supplicrs.

Thc manual is approved and maintaincd current by thc "anagcr . Nucicar Asscasmcnt. Ocpartmcnt hcads of organications pcrfcrming activitics within thc scopc of thc program acsignatc thcir v) acknowicdgmcnt

-..a-_:

uuuuv&

. .uw vu um of

.r v.- _ ..-_..: as-vu rcsponsibilitics u mu a_

-____: -:-u..

v.3uummuu vu uy and signaturc prior tc approval of thc manual by the Managcr Nucicar Asscssmcnt. 'CCT 00040)

Page _3_ of _5_ REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALIT/ ASSURANCE MANUAL crapter 2 O b.2 Corocratc nucIcar proccdures dcyclopcd, approvcd, and (OnP; arc sc,cumcats issued to providc corporatc dircction and policy pcrtaining to appropriatc Nucicar Program Activitics. CNPs nrc rcvicwcd by rcaponsibic dcpartmcat managcmcnt and approvcd by corporatc 1cyc1 managcmcnt. (CCT 40047) b.3 CPO Rccords t'anagcmcnt Otandards provid; dircction in thc arcas of rccords identification, prcparation, collcction/rcvicW, turnoscr/transfcr, storagc, prcscrvation, and maintcnance, b.4 Inservicc Insncction (ICI) Proaram tianual dcscribcs thc ICI requircmcats f or Cf'O and scrvcs as thc sitc standard for all CPC ICI Program activitics.

c. Occartmcntal Pro.g c du rc s or Instructicna arc dcvc10pcd, approvcd, and issucd for cach organization to furthcr impicacnt thc-rcquircmcnts of thc uppcr tics documcats listcd in acction 2.2.3a & b abovc. Thcsc dcpartmcntal proccdurcs or instructions providc morc dctailcd dircction to IP pcssonnci cagagcd in Nucicar Program rcleted activitics. (CCT 40040)

O 2.2.50-9:4 Iraining Each department head is responsible for the proper qualification of assigned personnel performing activities related to CPS. This includes establishing and maintaining documented training programs to' ensure that personnel performing activities affecting quality are appropriately trained in the -principles and techniques of the activity being performed; are instructed as to purpose, scope, and implementation of governing documents; and that they maintain required proficiency. (CCT 0341) Programs are l formulated to provide training based on individual employee experience and position and fulfill regulatory requirements, where applicable. Training records are maintained for each employee. Departmental training procedures / instructions require that indoctrination and training programs include objectives, content of program, attendees, and date of attendance. (CCT 24341) Applicable departmental procedures and instructions require that the proficiency of personnel performing and verifying activities- affecting quality is maintained by retraining, re-examining, and/or recertifying, as management or program commitment. (CCT 24342) determined by l 2.2.62.2.5 IP Nuclear Ouality Assurance Program Evaluations l Regular reviews of the IP Nuclear Quality Assurance Program to O

V assess the scope, status, adequacy, compliance, and overall ef f ectiveness' are performed under the direction of the Vice President. This review function consists of meetings Quality AssuranceNucicar Assessmcne personnel, as well as with key review l of audits and reports, and the performance of an IP Nuclear Page 4 of _5_ REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 2

, Quality Assurance Program assessment, which is preplanned and

' documented. Corrective action required as a result of adverse conditions identified during the assessment are documented, tracked, and completion is verified and documented. (CCT 0342) l Independent audits of other organizations performing activities related to quality are accomplished regularly under the direction 4 of the Manager - Quality AssuranceNucicar Assessment. (CCT 0107) l Oupplicrs' quality assurancc programs arc rcvicwcd, approvcd, and audited by th; Nucicar Asscasmcnt organization or authorizcd agcat for compMancc with applicabic rulcs, rcgulations, and IP Nucicar Program Quality Assurancc Manual as sct forth in the contract documcat. Approval of such programs related to CPC is

, documented. (CCT 0343) 2.3 RESPONSIBILITIES 2.3.1 Vice President

a. Directs reviews for overall effectiveness of the IP Nuclear Quality Assurance Program on a regular basis.

2.3.2 Nuclear Procram Decartments V a. Implement and comply with the IP Nuclear Quality Assurance Program.

b. Train and qualify / certify, as required, personnel who perform quality activities associated with CPS. (CCT 0341+ l
c. Maintain procedures / instructions to the extent necessary to carry out activities affecting quality.

2.3.3 CPS Plant Staff

a. Operate and maintain CPS in a safe, reliable, and efficient mode of operation. .

2.3.4 Nuclear Station Engineering

  • a. Implement the design control program for CP3, including design interface control activities.

2.3.5 Nuclear Trainina & Succort l

a. Maintain and implement a Licensed Operator Training program, Maintenance and Technical O)-

\._ Training program and a General Employee Training a program.

Page ji of _5_ REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 2

b. Maintain a Document Control Program to control the C issuance of documents, such as instructions, procedures and drawings, including changes thereto, which prescribe all activities affecting quality.
c. Establish, maintain and implement a Records Management Program including the CPS Records Storage Facilities.

2.3.69-3-6 Quality AantangnNuc1 car Asscasmcnt

a. Perform activities to ensure the established quality assurance program meets requirements and is effectively executed,
b. idcntify quality probicas and -- Aassure corrective actions for identified problems are effective.

O Page 6 of _5_ REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM l QUALITY ASSURANCE MANUAL I

de CHAPTER 3

DESIGN CONTROL 3.1 PURPOSE / SCOPE The purpose of this chapter is tPo establish the requirements, l responsibilities and control measures for assuring that design bases and regulatory requirements are correctly translated into design documents. The scope of design control covers all phases of engineering design, including: conceptual design selections; identification of design inputs (criteria and bases);

identification and control of design interfacesi production of design documents, calculations and analyses; procurement-related engineering; design verification; and installation engineering support.

3.2 DESCRIPTION

3.2.1 Design control measures are established to assure modifications and design changes meet the appropriate performance and quality requirements. These design control measures are O

V commensurate with those applicable to the original design and assure that modifications hardware changes are designed and l implemented in accordance with applicable codes, standards and regulatory commitments.

3.2.2 The Nuclear Station Engineering Department has overall l responsibility for design control activities at Clinton Power Station (CPS). These design control activities are managed within the context of the Nuclear Engineering Program Configuration Management Program, which a4sc includcs provision for controlling hardwarc and softwarc itcms (procedurcs, training, etc.) which compriac thc configuration af CPS and also includes final design approval of hardware changes at modifications for incorporation into the plant. Processing of a modificationhardware change, and the associated design / design change documents under this program ensures. appropriate participation and awareness by CPS organizations throughout the design development and installation process.

3.2.3 Provisions of this program also ensure that each modificatica or design change receives a thorough safety screening / evaluation, that meets regulatory commitment s . --er cnsurcs that the basis for nct pcrforming thc safety cvaluatica is documcatcd.

O V

1 l

Page __1_ of 5 REVISION 26

j ILLINOIS POWER NUCLEAR PROGRAM l QUALITY ASSURANCE MANUAL Chapter 3 G

(d 3.2.4 New design or design changes shall be defined by drawings, specifications, change notices or other documents as prescribed in design control procedures.

l The organization actually performing the design work, either Nuclear Station Engineering or a qualified consultant-engineer is required to include the following considerations in the design of each modifica Monhardware change: l

a. Appropriate design bases, regulatory requirements, safety requirements, performance objectives, de s i,;.1 margins, special prccesses, material and testing requirements, and operating objectives are adequately translated into the various design documents.
b. Appropriate design analysis (e.g., physics, seismic, stress, thermal, hydraulic, radiation and accident) is part of the design process.
c. Accessibility requirements for operation, testing, maintenance, in-service inspection and repair are included in the design,
d. Necessary installation, or modification l inspection and test acceptance criteria are included in the design documents or modification y,, packages,
e. An evaluation to determine if the proposed design change or modification involves an "unreviewed l safety question".
f. Design control measures shall include criticality physics and radiation shielding for radioactive material shipments.
g. Design control measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled.

3.2.5 Additionally, Tehe organization which produces and l approves the design / design change documents shall maintain detailed procedures to control and document performance of the following design activities:

a. Identification and selection of design inputs,
b. Identification and control of inter" aces between organizations required to make input to, review or 3 approve final design products.

(G

c. Performance of calculations or analyses which l demonstrate that design products satisfy the l Page __2__ of _1_. REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 3

/ design inputs, including those performed using 0~ computer codes.

d. Production, review, approval' and revision of drawings, specifications, data sheets or other design output documents.
e. Classification and specification of technical requirements for equipment or material procurements associated with the design / design change.
f. Verification that the design inputs, interfaces, calculations and final design products are adequate and correct; and that the installation satisfies all specified design requirements.

3.3.6 The form and structure of the procedures and l Instructions used to accomplish these activities may vary dependent upon the complexity of the design and the different organizations involved in the design development.

3.2.7 Design verification for the final design products will l normally be done by an independent group or person within the

organization actually producing the design. When this is a consultant-engineer organization, Nuclear Station Engineering may choose to conduct, or direct, additional independent design verifications.

3.2.8 This verification consists of a check of design l adequacy by such methods as design reviews, use of alternate calculations or methods, or performance of verification or qualification testing. The method, or combination of methods, used to verify a design will be selected on a case-by-case basis.

The selection will be based on consideration of such things as:

a) . uniqueness of the design or application, b) complexity of the design, c) prior history of use, d) importance to safety, and e) consequences of failure. CPS operating phase design verification other than qualification testing of prototype or lead production unit will, where practical, be completed prior to installation

.and operation. In those cases where this timing cannot be met, the design verification may be deferred, providing the justification for this action is documented and the unverified documents related to the design are appropriately identified and controlled. However, design verification shall be completed prior to the c,mponent, system or structure being released for operation.

3.2.9 Verification by test will normally be included in l procurement documents that require the supplier to perform the test and use the most severe design conditions as acceptance criteria. These procurement documents shall require that the L test procedure, including acceptance criteria, be submitted to Illinois Power or its designee for review and approval. prior to performance of the test.

Page _L J.,_ REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MAML'.^L Chapter 3 3.2.10 When a verification test cannot be performed prior to l installation, proposed testing programs shall be reviewed and approved by Illinois Power to ensure that no unresolved safety questions are involved and the testing is conducted within licensing limitations prior to the point when the installation would become irreversible.

Hic cntirc design control-proccas-shall bc sut,gc t to audits and survcillanccs to cnsurc that design activitics arc impicmcatcd in accordancc with program rcquircmcats. (CCT 034M 3.3 RESPONSIBILITIES 3.3.1 CPS Plant Staff

a. Initiate or cc'ncur with design change requasts for CPS and forward to Nuclear Station Engineering for review and approval,
b. Incorporate approved design changes into CPS.
c. Employ controls which maintain the "as-built" and "as-modified" condition of the plant,
d. Assure that the proposed design change affecting nuclear safety and associated safety evaluation has been reviewed by the Facility Review Group.

V 3.3.2 Nuclear Station Engineering

a. Implement the design control program for CPS, including design interface control activities.
b. Perform or obtain design services, such as preparation and review of design technical documents for all modifications and design l changes.
c. Review and approve design change requests and modification rc queses-f or incorporation into the plant,
d. Provide +ng "as built" information tot the Licensing l Department for updating the USAR to current plant conditions.
e. Determine if the proposed design change involves an "unreviewed asfety question".
f. Coordinate the processing of plant modificationshardware changes, assigning control numbers ,--ehe recording-et progress, confirming pd procedural compliance, recommending operational readiness of affected hardware and transmit completed design change packages to Nuclear Support Services for processing, and retention. 1 1

Page 4 of _jL. REVISION 26

ILUNOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 3

, g. Issue or coordinate issuance of data and reports which provide status of design changes.

3.3.3. Englgar Safety & Performance ImprovtmentLiccnsira l

a. Review and evaluate Technical Specification changes and unreviewed safety questions identified during the modification hardware change process l and obtain the necessary reviews and approvals.

3.3.4 Nuc1 car Assessment

a. Conduct audits and survcillanccs to detcrminc that thc dcsign control and ec14f ication activitics m:ct thc requircmcats of the design control program-O O

Page 5 of _E_ REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 4

PROCUREMENT DOCUMENT CONTROL-4.1 P_QBPOSE/ SCOPE The purpose wt this chapter is Pto define the- requirements and l responsibilities for the preparation, review, release, and revision of procurement specifications, purchase orders, and associated documents to assure the procurement of items and services are properly coat: rolled.

4.2 DESCRIPTION

4.2.1 Measures are established for the preparation, review, l approval and processing of purchase requisitions, purchase specifications, purchase orders and revisions to these documents to ensure that materials, parts, components and services for CPS are properly specified and procured, (CCT 0:49+ l Ptwehaec rcquisitions for matcrials, parts, componcats or services arc originatcd for thc opcration, maintcnancc, rcfucling, repair or modification of thc plant. (CCT 0350)

O' 4.2.2 Purchase requisitions are prepared in accordanco with documented procedures that require:

a. Applicable specifications, drawings, quality requirements, and related documents be included or referenced. (CCT 0351) l
b. Appropriate quality requirements, including supplier documents and records to be prepared, submitted or retained, and made available for purchaser review or approval are included or referenced. (CCT 0351) l
c. Appropriate quality assurance program requirements be included or referenced.-(CCT 0351) l
d. Provisions for the purchaser's right of access to supplier's facilities and records -(including sub-tier suppliers) for source inspection and audit be specified. ( C C T 0 3 : 1-F l
e. Provisions for supplier's reporting and disposition of nonconformances and requirements for hold points and release control are identified. (CCT 0351) clearly l
f. Suppliers extend the appliccble quality require-ments, including purchaser's access to facilities and records for inspection and audit, to their sub-tier suppliers. (CCT 0251) l PAGE _1_ of _2_ REVISION 26

-1 ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 4 S 4.2.3 Technical and quality requirements for procurement of l items and services are specified. Purchase requisitions are approved by the Manager or Director of the originating organization, or designee, and forwarded for processing. (CCT 40052) 4.2.4 Based on the approved purchase requisition, the l necessary purchase orders or contract documents are prepared.

Prior to release of the procursment documentpurchasc ordcr or contract, a review is performed to ensure the requirements ("a" through "f" above) have been met.- (CCT 0347) Purchase Orders or contracts are placed only with suppliers determined to be capable of meeting the procurement requirements. This determination is based on evaluations of the supplier's quality assurance program, the supplier's technical capabilities and the supplier's commercial ability.

4.2.5 Changes, revisions or amendments to requisitions and procurement documentsvexccpt as discusscd - bclow,- are subject to the same requirements as was the original document, except for-Thc following changcs revisions or amendmcats rcquirc Purchasing and "atcrial Control departmcnt approval only, al quantity, b) e-stimated pricc, c) cost codcs, di taxca, c) format and editorial changes -(such as -spc11ing or typing crrors) and commercial terms and conditions.

Audits and sarvcillancca arc conducted to casurc that procurcm:nt activitics arc impicmcntcd in accordancc with program requircmcat:,, s CCT O MM-4.3 RESPONSIBILITIES 4.3.1 Nuclear Procram Departments

a. Initiate and approve purchase requisitions for material, parts, components or services for CPS.

4.3,2 Nuclear Train _1.Do & Succort Ocrviccs l

a. Review purchase requisitions for complctcncasQA requirements.

4.3.3 Purchasino and Material control

a. Prepare procurement documentspurchase ordera/contracta for award to qualified suppliers.

~

b. Review procurement documents for completenesspurchasc ordcrs/ contracts for quality assurancc program rcquircmcata.

4.3.4. Nuclear Station Engineerina

a. Specify technical and quality requirements for materials, parts, components or services for CPS, PAGE _2_ of ._2_ REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 4 g b. Review and-approve design changes that result from procurements.

c. Provide specifications for- procured materials,-

parts, components or services for CPS.

4.?.5 Quality AggurgngeNucicar Assessmcnt l

a. Evaluate suppliers' technical abilitiesy and approvc suppliers' quality assurance programs.

'CCT 0347)

b. Conduet audits and survcillanccs of the procurcmcnt documcnt control program to casurc compliancc with thc rcquircmcats of this chaptcrr 4CCT 0340) 1 1

t.

~l V

PAGE 3 o f _2__ REVISION 26

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 9 5 INSTRUCTIONS, PROCEDURES AND DRAWINGS 5.1 PURPOSE / SCOPE The purpose of this chapter is tTo define the requirements and l

[ responsibilities for the generation and use of instructions, procedures, drawings, or related material to control activities which affect quality.

5.2 DESCRIPTION

! 5.2.1 Each IP department is responsible for developing, l reviewing, approving and complying with formal instructions, procedures, drawings and related material for performing activities affecting the quality or functions of applicable systems, structures, or components at CPS, Requirements established are: (CCT 0277) l

\ a. Instructions, procedures, or drawings shall include appropriate qualitative and/or quantitative acceptance criteria for determining O that important activities have been satisfactorily accomplished,

b. Instructions, procedures, or drawings for
maintenance, modifications, testing and operation
j. shall contain step-by-step instructions in the d degree of detail necessary for a qualified individual to perform the required function or task.

5.2.2 Each Manager, Director and Supervisor is responsible l ,

for determining the need for issuing and revising instructions and procedures related to each organization's scope of activities. (CCT OMe+ l Curvc111anccs and audits arc conductcd to detcrminc that appropriatc instructions, procedurca, or drawings ca st and to cvalustc thcir adequacy and impicmentation. (CCT 0202) 5.3 RESPONSIBILITIES 5.3.1 Nuclear Program Decartments

a. Develop, approve, and employ those instructions, procedures, or drawings necessary to accomplish its assigned tasks and responsibilities at CPS.

Each department is responsible for developing, obtaining approvals and complying with instructions, procedures or drawings related to its scope of effort.

Page _1 of _L., REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL h 5.3.2 Nuc1 car Asscasmcnt-

a. Conduct survcillanees and audits to icrify that appropriatc instructions, proccdurcs and drawiegs cxist, arc adcquatc and arc bcing impicmcated in aceerdancc with thc rcquircmcats of this chaptcr (CCT 02^2)- ,

i O

O Page _1 of 1 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL O CHAPTER 6

DOCUMENT CONTROL 6.1 PURPOSE / SCOPE

! The purpose of this chapter is tTo define the requirements and l responsibilities for review, approval, issue and distribution of controlled documents such as instructions, procedures or drawings and changes thereto

6.2 DESCRIPTION

6.2.1 Controlled documents such as specifications, l procedures, instructions, drawings, computer software for safety-related applications, and other related materials which prescribe activities affecting quality or safety-related functions of systems, structures or components at CPS shall be processed in accordance with the following criteria: (CCT 0170) l

a. Documents, including changes, are reviewed for adequacy by appropriately qualified personnel, tO approved for issue and use personnel, and distributed to and used where the by authorized prescribed activity is performed. (CCT 0200) l
b. The review and approval of changes which modify the intent of the document is performed by the same organizations that performed the original review and approval, unless other equivalent organizations are specifically designated.

Reviewing organizations will have access to pertinent background information upon which to base approval and have adequate understanding of the requirements and intent of the original document. (CCT 0200) l

c. The document control system ensures that personnel or organizations are provided with current and approved documents. (CCT 0077) l
d. Documents and changes thereto are controlled by procedures to preclude the use of outdated or inappropriate documents. (CCT 0077) l
e. The CPS document control program provides for periodic reviews of plant procedures to determine if changes are necessary or desirable. (CCT 0070) l
f. Individuals or organizations responsible for preparing, reviewing, approving and issuing Page _1_ of _2_ REVISION 26

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de6a T og T B3AISION 29

.- . _ = . ._ _ - . ._ - .- -. --

lLt.lNOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 6

b. A program for reviewing and approving the documents received for use in activities associated with CPS by that organization.
c. A_ program for distribution and control.

, 6.2.3 Measures are established within each organization to l assure that obsolete or superseded documents described in the paragraph above are replaced in a timely manner by updated docuwnt revisions. (CCT 0001) l Gttrvc illanccs and audits arc conductcd of documcat coattel-systcms to casurc compliancc with thc spccifica rcquircmcats.

iCCT 0203) 6.3 RESPONSIBILITIES 6.3.1 Nuclear Procram Deoartments

a. Review, approve and maintain controlled documents generated in accordance with CPS Records Management Standards-appropriatc proccdurcs.
b. Employ appropriate measures to receive, record and re-distribute controlled documents from other p organizations.

O 6.3.2 Nuclear Tr3inino & Suoport Ccrvicca l

a. Maintain a Document Control Program to control the issuance of cocuments, such as instructions, procedures and drawings, including changes thereto, which prescribe all activities affecting quality.

G.3.3. Nuclcar Assessmcnt-

e. Conduct survcillancca and audits of documcnt control systcms to casurc compliancc with thc rcquircmcats of this chaptcr. (CCT 0203)

O Page _'L of _L REVISION 26

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 9 7 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES 7.1 PURPOSE / SCOPE The purpose of this chapter is tPo define the requirements and l responsibilities for programs that assure purchased material, equipment, and services conform to procurement requirements.

7.2 DESCRIPTION

7.2.1 Measures have been established to provide assurance l that purchased materf.al, equipment, and services conform to procurement document requirements. This assurance is accomplished by controlling both the celection of procurement sources and acceptance inspcctions of the product at the source and/or upon receipt at CPS. (CCT 0350) 7.2.2 IP procurement procedures require a review of material, l equipment and services requisitions for safety-related structures, systems, and components. This review will identify the applicable codes, standards, technical and quality C's requirements to assure that they are equivalent to the original V requirements. When alternate requirements are imposed which are not equivalent to the original requirements, the alternate requirements will be fully evaluated and documented. The necessary reviews and evaluations of the procurement source's capability to meet the technical requirements of the procurement documents will also be performed.

7.2.3 Reviews and evaluations are performed of the l procurement source's quality assurance program and ability to meet the quality assurance and technical requirements of the procurement documents. (CCT 0354) Where necessary, a supplier's l acceptability is determined by an audit of the supplier's quality assurance program. Such audits are performed in accordance with a written plan or checklist to determine the ability of the supplier to comply with the quality cssurance program requirements of the procurement document. (CCT 0355) The l determination of a supplier's acceptability may be made by means other than by audits. These means may include: a) review and evaluation of the supplier's quality assurance program description document, b) review and evaluation of historical supplier quality performance data, c) supplier facility surveys, d) review and evaluation of audits, surveys, and inspections conducted by other utilities, or American Society Mechanical Engineers (ASME), or e) documented information from r~s organizations, including architect-engineer, Nuclear Steam i~) Systems Supplier, and other utilities that indicates the supplier has a program that meets applicable requireme ts of Appendix B to 10CFR50. When these means are either not available or do not permit a complete evaluation of a Page _1_ of 4 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 7 e supplier's quality capabilities, a survey or an audit will be conducted of the supplier.

maintained. (CCT 0350)

A Qualified Suppliers List is l

7.2.4 In addition to reviewing a supplier's capability to l meet the commercial requirements of the procurement documents, a review is performed to ensure that the required technical and quality assurance evaluations have been completed satisfactorily prior to contract award or release of the purchase order. The results of these reviews and evaluations are documented.

7.2.5 When required by the procurement document or l specification, surveillances and evaluations at the supplier's facility are conducted to verify continued compliance with the quality assurance requirements of the procurement documents.

Source inspections at the supplier's facility are accomplished by qualified individuals or qualified agents to verify that the procurement item or service is being supplied in accordance with the requirements of the procurement documents. Such inspections are accomplished in accordance with written procedureo, plans, and/or checklists containing or referencing appropriate acceptance criteria. (CCT 7007) l 7.2.6 Upon receipt at CPS, safety-related materials, parts, l and components are controlled. Qualified inspection personnel are responsible for inspecting, releasing, and maintaining the O inspection status ofidentifying purchased material and equipment.

V sa to thc laspection status. (CCT 0357) 7.2.7 Acceptance activities such as evaluation of content of l technical documents required by the purchase order, and the conduct of special tests and measurements which are identified in the purchase order are also performed. Receipt inspections are accomplished in accordance with written procedures and/or plans containing or referencing appropriate acceptance criteria. After receipt inspection, the purchased material is forwarded to a controlled storage area or released for installation or further work. (CCT 0100) l 7.2.8 Documentary evidence of conformance to procurement l requirements provided by the supplier in accordance with the procurement documents is reviewed during source and/or receipt inspections to verify compliance, The validity of a supplier's certificate of conformance is ascertained through any of the following methods: source inspection, independent inspection agency, receipt inspections, surveillance, testing of hardware, quality assurance audits or surveillances. Inspection and test activities verify that the hardware performs in accordance with applicable technical requirements and serve to demonstrate that the hardware meets the requirements stated in a certificate of conformance. The results of the source and/or receipt p)

(

inspections, the acceptability of supplier documentation, and the resulting determination of conformance or furnished nonconformance are documented. (CCT 0100) l Page _2_ of 4 REVISION 26

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 7 7.2.9 Acceptance of contracted services such as 9 services, consultant services, installation, maintenance services shall be based on one- or all of the inryection l repair or following methods, as required:

a. technical verifications
b. surveillance / inspections
c. review of objective evidence such as certifications or technical reports.

Curveillancca and audits arc conductcd of the control mcasures applica to purchascd matcrials, cquipmcat, and scrviccs to determinc the cffcctivcness in mccting thc spccifi'.d rcquircments. Audits of supplicra cvaluet; the adcquacy and effcctivcncas of supplicrs' systcms and procedurcs for preparing ccrtificatcs of confcemancc, as wcil na thc adcquacy of supporting documentation and rccords. (CCT 0350) 7.3 RESPONSIBILITIES 7.3.1 Nuclear Procram Decartments

a. Ensure the control of purchased material, equipment, and services conform to procurement

/

, requirements.

b. Ensure that suppliers performing work at CPS utilize control measures compatible with those of CPS Plant Staff.

7.3.2 Nuclear Station Engineerino

a. Review purchase requisitions and specify the technical and quality requirements for the item (s) or service (s) to be procured.

(CCT 017400) l

b. Review and approve supplier furnished technical data specified by the procurement document, including such items or services as process and test procedures, performance of test data, and heat treat charts prior to acceptance.

7.3.3. Nuclear Trainino & Sunport Cervicca j

a. Implement procedures for the receiving, storing, and issuing of purchased items.
b. Qualified inspectors perform required receipt inspection of materials or equipment prior to issuing the material or equipment for operation.

O V 7.3.4 Purchasina and Material Control Page 3 of 4 REVISION 26

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 7 h a. Perform reviews of suppliers' capabilities to meet V commercial terms and conditions prior to release of the purchase order or contract.

b. Verify the suppliers are listed on the Qualified Suppliers List as required.

7.3.5 Quality AssuranceNucicar ".ssessment- l

a. Perform source surveillances and audits of suppliers' quality assurance programs, or establish alternate controls, prior to release of the initial purchase order or award of contract.

(CCT O Z4)

b. Perform source survillances and audits at suppliers' facilities to verify compliance _ with the quality and technical requirements of procurement documents.
c. Conduct survcillan;cs and audits of thc control acasurcs applicd to purchascd matcrial, equipm;nt, and- scrvices to casurc compliancc with the rcquircments of this chaptcr,
d. Pcrform and document sourcc survcillancca at the O

b supplicrs' facilitics to verify that procurcd itcms or scrviccs arc in compliancc with t hc-rcquircmcnts of thc procurcmcat do;umcats. (CCT 7007) ce. Maintain a database identifying qualified suppliers.thc Qualificd Cupplicrs List currcnt bascd on the results of thc surycillancca and audits.

d

't Page 4 of 4 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 9 8 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS 8.1 PURPOSE / SCOPE The purpose of this chapter 's tPo define the requirements and

. l responsibilities for a program of identification and control of materials, parts, and components such that traceability is assured and the use of. incorrect or defective items is prevented.

8.2 DESCRIPTION

8.2.1 Measures have been established which provide for the l identification and control of materials, parts, ..,d components to assure that traceability is provided and the use of incorrect oref defective items is prevented. (CCT 0171) These measures l include the following:

a. Procurement documents specify appropriate identification to be applied to purchased items.

iCCT 0204)

b. An inventory cone.rol system is employed for the
receipt, storage or stocking, and issue of materials, parts, and components.
c. The identity of materials, parts, and components is either on the items or on records traceable to them. When physical marking is employed, the marking is clear, unambiguous, indelible, and applied in such a manner as to not be detrimental 4

to the intended function of the item. (CCT 0204) l

, d. Markings are not obliterated or hidden by treatment or coatings unless other means of identification are substituted,

e. When codes, standards, or specifications require traceability of materials, parts, or components to specific inspection or test records, the program is designed to provide such traceability,
f. When employed, identification is transferred to each part of an item prior to its being subdivided, p 8.2.2 Materials, parts, and components shall have appropriate l (J

identifying designation (such as serial number, part number, heat number, etc.) in ord6r to provide traceability to each item to Page _1_ of 2 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 8 f inspection and test records and/or reports. Where physical identification of an item is either impractical or insufficient, physical separation or addicional procciural controls are e.nployed . ( ccT 0 2 0s+- l 8.2.3 When installed material or equipment is removed forl maintenance, repair, or modification, control measures are implemented to ensure proper identification mw%mgs and traceability is maintainedtimghout its proccas hg. During fabrication, assembly, installation, and shipping activities at a supplier's facility, the supplier conducts verification inspections and is responsible for identification and control of materials, parts, and components in accordance with the requirements of the IP purchase order.-met 0200) l 8.2.4 Material, parts, and components are identified and controlled during receipt and storage, fabrication, maintenance and modification activities performed at CPS. Matcrial, parts, and componcnts arc also idcntificd and- contrclicd during rcccipt and-st o rag c at CPO. The IP department responsible for supplier work at CPS is responsible for ensuring that identification and control of materials, parts, and components by the supplier are in accordance with applicable procedures.

Ourvcillancca and audits arc conductcd to assurc that p Mentificatica and contral of matcrials. parts, and componcnts Q arc in-compliancc with program rcquircmcnts. (CCT 0200+

8.3 RESPONSIBILITIES 8.3.1 Nuclear Program Departments

a. The Nuclear Program Departments responsible for supplier work at CPS are responsible for ensuring that identification and control of materials, parts and components by the supplier are in accordance with applicable procedures.

8.3.2 CPS Plant Staff

a. Implement a program that provides for the identification and control of materials, parts and components used at CPS.

8.3.3. Nuclear Tuininct & Succort Scrvicca l

a. Implement an inventory control system for the identification and control of materials, parts and components.

0.3.4 Nuc1 car Assassment

('i a. Conduct survcillancca and audits of the V identification and control of items to casurc ccmpliancc with program rcquircacnts. (CCT 02001 Page 2 of _2_ REVISION 26

i ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL N CHAPTER 9

CONTROL OF SPECIAL PROCESSES 9.1 PURPOSE / SCOPE The purpose of th;., chapter la tPo define the requirements and l responsibilities tur assuring that special processes such as welding, heat treating, chemical cleaning, nondestructive examination (NDE), pipe bending, and special coatings are performed under proper controls and that qualified procedures governing these processes are established in accordance with applicable codes and specifications, are implemented by qualified personnel, and results of special processes are properly documented and evaluated.

9.2 DESCRIPTION

9.2.1 For some processes, the required level of quality l defined in codes, standards, and specifications cannot be verified by inspection of the item only. For these processes, quality assurance is accomplished by qualified personnel using qualified proceduresebtened through a combination of inspcction and rclinncc on pcraonnel qualification and proccdural control, aa appropriatc, for thc proccas bcing conducted. Processes which meet the iallowing criteria are controlled as special processes:

-4CCT 0104 ) l

a. The process is highly dependent upon operator skill and/or process control.
b. The specified quality cannot be readily determined by direct inspection or test of the final product.

9.2.2 Special process procedures shall specify: prerequisite l conditions, processing steps, conditions to be maintained during the steps of the procees, inspection and test requirements, personnel qualification requirements and record requirements.

Technical portions of the special process controls are delineated or referenced in the design or technical documents by the organization preparing the document. (CCT 40053) l 9.2.3 Special process procedures shall be reviewed andl altroved to assure technical adequacy. Supplier process control p rcedures specify the methods of verifying the adequacy of processing materials, solutions, and equipment, including definitions of their associated control parameters. The control

~w (d and approval of sub-supplier special process procedures are the responsibility of the specific suppliers involved. (CCT 0;'70; l Special process requirements are promulgated to supplicrs by the procurement and/or design documents.

1 Page __L of 3 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANC7 MANUAL Chapter 9 9 9.2.4 Control measures and requirements that have been l catablished include

a. The need for special processes and the codes or standards applicable are identified during design or preparation of technical documents associated with an activity.-fCCT 0000) l
b. Special processes are performed in accordance with approved written procedures applicable to the specific process and qualified Ln accordance with applicable codes and standards. (CCT 0&e6+ l
c. Personnel performing special processes are qualified, as required in accordance with applicable codes and standards.--(CCT 0006+ l
d. Special processes are accomplished under suitable controlled conditions which include the use of qualified equipment, adequate contre' of the environment, and establishment of proper prerequisites related to the process.-(CCT 0000) l
e. Application of special process procedures and personnel qualifications is verified through 9 audits and surveillances.--(CCT 0066+ l
f. Records which show that special processes were performed in compliance with qualified or approved procedures and by qualified personnel and equipment are maintained. (CCT 0000) l 4

9.2.5 Inspections r-surveM-knee-and-nudhe are conducted of '

special processes, includhg qualification af prceessesy equipment, and personne to ensure compliance with appropriate codes, standards, specifications, procedures, and the IP Nuclear Program Quality Asburance Manual.: (CCT N 6+ l 9.3 RESPONSIBILITIES 9.3.1 CPS Plant Staff

a. Maintain a program to qualify special process procedures and equipment, cxccpe-NDB-ce iui rca f or phnt operat4 ens.
b. Maintain a program to qualify personnel to perform special processes, cxcept NDO required for plant operneiens .

c.

(]-

\~

Incorporate requirement into for Plant special Staff processes documents the and their controls and references to the applicable codes or standards.

Page _2_ of _3_ REVISION 26

. _ - _ _ _ _ = _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _

1 lLLINOIS POWER NUCLEAR PROGRAM ,

OUALITY ASSURANCE MANUAL Chapter 9 I

S 9.3.2 Nuclear Station Engineerinct i

a. Specify special processes in technical documents and procurement requisitions,
b. Support CPS Plant Staff in the preparation, revision and qualification of special process procedures and personnel.
c. Review and approve special process procedures used at CPS or specified in procurement documents to verify technical adequacy. .
d. Review and approve special process personnel qualification procedures and vertfy technical adequacy. ,
e. Contracts with an-Authorized Inspection Agency to provide inspection services for ISI. >
f. Perform scheduled ISI examinations and inspections.

1

g. Contracts with a supplier to perform scheduled ISI examinations and inspections as required.
h. Review NDE procedures, including those of suppliers,
i. Maintain a program to qualify procedures, equipment, and personnel for NDE.
j. Perform NDE to support plant operations, including NDE for repairs, replacements and modifications.

e k. Contracts with a supplier to perform NDE or inspection services as required.

0.2.2  !?ucicar Asses ncnt-

s. Conduct surveillancca and audits -of epccial processcs and controls, including qualification c5 process, cquipmcat, and personncl, whet 4rer performcd by CPC Plant Staff. ?!OCO or sttpplicra to casurc compliancc with approvcd proccdurcs, (CCT M \

l P a g e _. L o f 3 REVISION 26

-1

i lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL 3 l

h CHAPTER 10 INSPECTION 10.1 p*gf 'QSE/ SCOPE The purpot, of this chapter is tTo define the requirements and l responsibilities for a program of inspection which provides assurance that the fabrication, installation, modification, and repair activities affecting safety-related components, systems, and structures conform to the applicable specifications, instru~tions, procedures, drawings, or other pertinent technical requirements. The--I+ndependent inspections pe r f ormc d - -a re not intended to diminish er reinsee-the elear-responsibility of &we W e-supervisara-for the quality of warie-personnel performing the activities for the quality of the work.pe rf ormcd - under thcir

, super Asient

10.2 DESCRIPTION

10.2.1 In order to assure safe and reliable operation, l programs of inspections are established at CPS which include the following provisions:

a. The requirements for inspections are identified and documented based on procedures, instructions, drawings, and other documents for an prior to the start of the activity. (CCT 0&M+ activity l
b. Inspections are accomplished in accorda.ce with a combination of approved written procedures cod documented instructions which contain or reference, as a minimum -(CCT 0200)
1. A description of the required inspection (type, method, etc.), the responsibil:.ty for performing the inspection, and, where 4

applicable, any sampling plan to be used.

Hold / Witness points, where required, will be indicated in the appropriate dccumentsi

2. The discrete identity of the activity, process, or item to be inspectedi
3. Applicable documents, drawings, and specifications pertaining to the activity or item under inspection;

, 4. Verification of proper type, range, and

( accuracy of inspection instrument (c) used for each operation; Page __1 of __1 REVISION _26

1 ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL i

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.) 5.

CHAereR Appropriate quantitative or qualitative 1

l criteria for acceptance /rojection; i

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 10 i 4

6. Provisions for recording inspection data and results.

l 1 c. Inspection personnel are qualified and certified in accordance with the requirements of applicable codes, standards and written procedures. l .

Inspections are performed by persons other than those who performed or directly supervised the ,

activity being inspected. The qualifications and  ;

4 certification of inspection personnel are maintained current. ( CCT 2 MH+ l

d. Where dircct inspection or testing is impossible l or disadvantageous, indirect control by monitoring
process methods, equipment, or personnel is employed. When necessary to provide an adequate level of product quality assurance, both direct control (inspection and testing) and indirect control (process monitoring) are utilized. When

, sampling plans are used, their applicability is -

evaluated and justified in writing.-(CCT 0070) l 4

e. Measuring and test equipment used to obtain quanti; stive data for acceptance criteria shall have an accuracy equal to, or greater than, the required tolerances of the measurement

, taken.-(CCT OsM+ being l Ouppliers arc scaponsibic for cstablishing and impicmenting hapcction programs accessary to mcct the rcquircments spccificd h--thc procurement documents. The accd to invokc the rcqui rcmcate- of ANOI N45. 2. 0 1970, " Qualifications of Inspcction,

. Onemhtation, and-Tcsting Pcrsonnel for Nuclcar Powcr Plants", on suppHera-+s-evahatcd during the revicw of procurcm:nt documcnts for itcms and scrviccs. Thc compicxity of thc itcm and the extent-of thc sourcc and rcccipt inspection arc factors which are eensidcrca -when detcrmining whethcr or not to invokc AN95 N45,2.0. (CCT 0010)

Ourvciilenccs and-audita arc conductcd of thc various establishcd inspecti-on progrems and thcir ir,1cmcatsd on to casu::c compliance with thc provisions described n itcma "a" through "c" abovc.

(00T 0000&

10.3 RESPONSIBILITIES 10.3.1 CPS Plant Staff

a. Implement a program that provides for inspection of work operations performed at CPS.

10.3.2 Nuclear Station Encineerina Page 2.,_of 3_ REVISION 26

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter to  ;

a. Specify inspection and nondestructive examination criteria and requirements in technical documents and procurement requisitions.

--RCT 0010 ) l

b. Implement an inspection program for scheduled ISI Program examinations and inspections and perform NDE and welding inspections to support plant operations,
c. Maintain qualified and certified inspection personnel in accordance with appropriate standards.

10.3.3. QMAlA_ty_AE3MIAngeNuc1 car Assessmant l

a. Implement an inspection program for CPS.y ewehrdiwy-mat c ri al rcccipt, ICI, ND", and wcidiwy

+nspcction. (CCT 0021)

b. Maintain qualified and- certified inspection personnel in accordance with appropriate standards. (CCT 24343) l
c. "crify through survcillancca and attdi t a that stepplicra pcrf orming work at Cl'O arc in compliance with an approvcd inapcction prog m mt
d. Condttet surved-l lancc a and audita of inapcctica prognma to cnettic compiiancc with the
rcquircmcnts of this chapter. (CCT 0000) 10.3.4 Hucinar_IrAining_i_Aupnert
a. Implement a receipt inspection program for CPS.
b. Maintain qualified and certified inspection personnel in accordance with appropriate standards.

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E ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL f

O csAeTER  :

11 TEST CONTROL J

11.1 PURPOSE / SCOPE The purpose of this chapter is tPo define the requirements and l responsibilities for the control of a test program which will assure that the safety-related structures, systems or components being tested meet specified performance criteria.

11.2 DESCRIPTION

11.2.1 Measures have been established toThe IP Nuc1 car ^uality Asmmmcc Program addresses requirements and responsibilities for

establishing and conducting test programs for the following
a. Verification tests prior to installation.
b. Surveillance testing.

i

c. Tests associated with plant maintenance, modifica-tions, repairs or procedural changes.

11.2.2 Test programs are developed to assure that the required l tests are performed in accordance with approved writtcn ,

procedures which incorporate or reference the design requirements and acceptance criteria and provide for the following, as required:

l a. Statement of test objective (s);

b. Test prerequisites, to be fulfilled prior to the test, including requirements for calibrated instruments, suitable environmental conditions, appropriate equipment and personnel availability; and condition of the item to be tested and condition of the test equipment;
c. Precautions to be taken in the preparation and performance of the test, including limits of parameters if variations outside the normal ranges are prescribed;
d. Mandatory inspection hold points for witness by inspection personnel; D e. Instructions for performance of the test,

\ including the use of appropriate instruments, equipment and personnel;

f. Data to be acquired; and Page ._1_ of _2_ REVISION 26

i

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 11 O g. Acceptance / rejection criteria.

11.2.3 Test schedules are provided and maintained in or' der to l assure that necessary testing is performed and properly evaluated on a timely basis and that the safety of the plant is dependent on performance of systems which have sar.isfactorily passed l l required tests. Testing is conducted by appropriately t raine.d and qualified personnel. Test results are documented to facilitate evaluation and to provide a permanent record. Test evaluations are performed to assure that performa..ce characteristics conform to design. Repair, rework and/or j retesting are scheduled for accomplishment as identified by the ',

test evaluation.

i 11.3 RESPONSIBILITIES j 11.3.1 Nuclear Station Enaineerina

, a. Implement programs that specify and control the testing of structures, components and systems.

b. Develop and implement test schedules to ensure that tests are performed on a timely basis.

and

O c. Ensure that test personnel are trained to perform their function, qualified
d. Pcrform the rcquircd tests.

de. Review and approve test procedures and results for surveillance testing, ef. Review and approve post-maintenance test results. l fg. Establish test requirements and acceptance l criteria for post-modification testing.

gh. Review and approve post-modification and/or l ,

special test results.

h+. Review and evaluate test results as required by l the ISI Program.

11.3.2 CES Plant Staff
a. Implement programs for the performance of '.

surveillance and post-maintenance testing.

b. Ensure .that post-maintenance testing and surveillance tests are performed by qualified ,

personnel with appropriate procedural guidance.

c. Review and approve test procedures and results for surveillance testing.
d. Review and approve post-maintenance test results.

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s ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 11

, u . : . .: .  :;uclea- , asea;; cat

a. Conduct survciliances and audita of thc tcat pr 3 ram to ensurc the test prc ram complies with

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL O CHAPTER .

12 CONTROL OF MEASURING AND TEST EQUIPMENT 12.1 PURPOSE / SCOPE The purpose of this chapter is tPo define the measures and l responsibilities to assure tools, gauges, instruments, and other Measuring and Testing Equipment (M&TE) used in activities affecting quality are properly controlled, calibrated and adjusted at specified periods to maintain accuracy within specified limits. Measures shall also be defined for the control of permanently installed instrument and control devices.

12.2 DESCRIPTION

12.2.1 M&TE is precedm ally dcfincd as equipment used to l quantitatively generate or measure physical parameters with a known degree of accuracy for the purpose of calibration, inspection, test, or repair of plant mechanical, electrical or instrument / control equipment.

12.2.2 In order to assure the accuracy of measuring and test l equipment and installed instrument and control devices which require calibration or calibration check is maintained within specified limits, a written program for the control and calibration of such devices is provided. This program includes the following provisions:

a. For M&TE, the reference standards have an accuracy of at least four (4) times the required accuracy of the equipment being calibrated, or when this is not possible, have an accuracy that assures the equipment being calibrated will be within the required tolerance and that the basis of acceptance is documented and authorized by supervision,
b. The reference standards used for calibrations are required to be traceable to nationally recognized standards or accepted values of natural physical constants to the extent possible. When this is not possible, the basis for calibration of a reference standard is required to be documented,
c. Calibration intervals for M&TE and installed instrument and control devices are based upon the equipment, O type characteristics, of conditions affecting calibration.

required stability, accuracy reliability and other Page~._1_ of _1_ REVISION- 26

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 12 1

O d. Calibrations are performed valid standards using approved written procedures.

by comparison with j

e. Calibration standards are maintained and used in a  !

j controlled environment which does not adversely )

affect the calibration procedure or standard.

f. The calibration status, including the due date of next calibration of each item of M&TE, is visible '
through use of tags, labels or decals attached to  !

the equipment or a statusing system. i

g. M&TE and installed instrument and control devices requiring calibration are assigned identification numbers traceable to the calibration records which ,

includes the calibration "AS FOUND" and "AS LEFT" data for the equipment calibrated at the plant.

the . equipment is calibrated by an outside If service organization, a certificate of calibration complete with "AS FOUND" and "AS LEFT" calibration data is required. Such certificates and data sheets bear the assigned equipment identification 4

numbers and the identification of the calibration standard used and are traceable to the individual calibration records.

l h. M&TE is not used past the expiration of the calibration period,

i. If selected installed instrument and control devices are found to be out of calibration, an evaluation concerning the validity of previous inspection and test results is performed and documented. If M&TE is found to be out of calibration, an evaluation concerning the validity of previous inspection and test results and the

^

acceptability of items previously inspected or tested since the time of the last calibration ,

check is made and documented. Corrective action

~

is taken in accordance with Chapter 16 when such evaluations invalidate a previous acceptance.

j. A calibration tracking system is established to ensure that recalibration is performed in accordance with pre-established calibration frequencies.

12,2.3 A program has been implemented for the control of M&TE l  ;

and installed instrument and control devices used in operation, maintenance, test and/or inspection activities which fall within ,

the scope.of the IP Nuclear Quality Assurance Program. Suppliers performing services or providing products to CPS are required to

' O. s have comparable control programs in effect for items affecting systems, structures and components within the scope of the. QA program.

Page ,_2_. of 1 REVISION __26

ILLINOIS POWER NUCLEAR PROGRAM  !

QUALITY ASSURANCE MANUAL chapter 12  :

Otsrvci!!ancca and-atsdita are conduetcd of thc controla applied to meant $ri ng and tcat cqttipm nt to determ Mc compliancc with the prov+sions deseribcd-in itcma "a" through "j" abovc. (CCT 70001-12.3 RESPONSIBILITIES 12.3.1 CPS Plant Staff

a. Implement programs to control M&TE use at CPS.
b. Implement programs to calibrate and recall the M&TE used at CPS.
c. Ensure the appropriate requirements for the control of M&TE are included in Plant Staff initiated technical documents and procurement requisitions.
d. Implement programs to control the use of installed instrument and control devices.

42.'.2 lig;har-Aaressmant .

t

a. Ocaditc t survcillancca and audita of thc controla applica to t% T" and-hstelicd in s t rismcat and contrci dcvicca tc dcterminc compliancc with the ,

requircmcata of this manttal . (CCT 7000) 1, s

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL O CsAeTER 13 HANDLING, STORAGE AND SHIPPING 13.1 PURPOSE / SCOPE The purpose of this chapter is tPo define the requirements and l responsibilities for the control of handling, storage, shipping, packaging, cleaning and preservation of materials and equipment to prevent damage or deterioration. ,

13.2 DESCRIPTION

13.2.1 The IP Nuclear Quality Assurance Program includes spee+a4-handling , preservation, storage, cleaning, packaging and shipping requirements that are accomplished by trained individuals in accordance with procedures to prevent damage or deterioration. The procedures will-- provide for the control of l heavy loads and safe load paths to protect safety systems and radioactive material f rom damage. In addition to the handling, storage and shipping requirements imposed on suppliers by IP through appropriate technical and procurement documants, suppliers may also be required to provide information to Nuclear Support Services re"ated to the proper handling, storage and shipping of furnished materials, parts and components. Nuclear Support Services uses this information for the development of the storage and handling procedures and instructions to be applied to an item.

13.2.2 The procedures and instructions will provide for the l preservation of special items that are subject to deterioration or damage through exposure to air, moisture, temperature, or other environments and use of special handling tools and equipment.

13.2.3 Consumable materials such as chemicals, reagents and l lubricants maintained in storerooms and warehouses are controlled procedurally by an inventory control system which includes provisions for identifying storage requirements by commodity and identifying shelf life by commodity, when applicable. Disposal of commodities whose shelf life has expired is addressed and controlled by procedures.

4 Ottrvc-illsacc s and audits arc condttc tc d to dctcrminc if appropriatc proccdurcs and controls arc being applied regarding handling, storagc and shipping of matcrials and-cquipmcnt. (CCT 0007;13.2 13.3 -RESPONSIBILITIES 13.3.1 CPS Plant Staff Page _1 ,of _2_ REVISION 26

)

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL  !

l O a.

CHAPTER Implement programs to provide for the use of '

i special handling tools and equipment. *

b. Implement programs to control the handling, '

otorage and shipping of materials. .

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 13 13.3.2 Nuclear Station Engineering

a. Ensure that appropriate handling, storage and shipping requirements are identified in technical documents that are prepared or reviewed by the department.
b. Specify in procurement documents, that suppliers furnishing materials and equipment within the scope of this program implement appropriate controls for handling, shipping and storage of ,

such items.

P 13.3.3. Nuclear TIAlning_& Support Oervicea l i a. Ensure that suppliers furnish the required information relating to the proper handling, storage and shipping of procured items.

i

b. Implement programs to control the handling, storage and shipping of items to be used in cps, including radioactive materials.
c. Implement programs to provide for the preservation p cf items in storage that, are subject to deterioration or damage through exposure to harsh environmental elements or conditions. i
d. Ensure that appropriace handling, storage and shipping requirements are identified in procurement requisitions.

i3.3.4 Nuclea e-Assessment

s. Conduet survci1Vnces and audita to verify that ,

appropriate procedurca and-cont rol a arc being impicmcated-in acccedanee--wi & the rcquircmcata of th+s-chaptcr. (CCT 000%

O Page 3 of ,_2_ REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL  !

i O CHAPTER 14 INSPECTION, TEST AND OPERATING STATUS 14.1 PURPOSE / SCOPE 1

The purpose of this chapter is tPo define the requirements and l responsibilities for identifying the inspection, test and operating status of materials, parts, components and assemblies to assure that only items which have passed the required inspections and tests are installed or operated.

14.2 DESCRIPTION

14.2.1 The IP Nuclear Quality Assurance Program includes l procedures which assure the inspection, test and operating status ,

of materials, parts and components are identified during the 4

receiving, installation and operating processes. These j procedures provide for -4CCT Oss u l

a. Clear indication of the status of inspection and tests performed upon individual items by the use of markings such as a) stamps applied directly to the item, tags, or labels attached to the item; b) routing cards that accompany the item; or c) identification numbers which are traceable to records of the status of inspections and tests.

If control stamps are used, a record of the assignment of the control stamp is maintained; however, if a stamp is lost or if the stamp holder l no longer requires the stamp, that stamp number is retired. When impression stamping is used, it conforms to the requirements of codes and applicable specifications and standards. When markings are applied directly to items, consideration is given to ensure the markings have no deleterious offeet on the items,=(CCT 0002F l

b. Assurance that required inspections or tests are not inadvertently bypassed. In cases where required documenting evidence is not available, the associated equipment or materials must be considered nonconforming in accordance with Chapter 15 of the Illinois Power Nuclear Program l Quality Assurance Manual. Until suitable docunented evidence is available to show the equipment or material is in conformance, affected systems shall be considered to be inoperable and reliance shall not be placed on such systems to fulfill their intended safety functions. (CCT ,

ess&

Page _1_, of _2_. REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM

QUALITY ASSURANCE MANUAL Chapter 14
c. Clear indication, by the use of a tag and/or
statusing system, of the operational status of structures, systems and components when in any i status other than a nor nal operable status to prevent inadvertent operation.

l 14.2.2 The test and operating status of materials, parts, l  !

components and assemblies is indicated at CPS. The inspection and test status of items in storage is also maintained.

i Inspection personnel are responsible for the identification of the inspection status on materials, parts and components. (CCT M90F As imposed by the contract documents, suppliers performing activities at CPS or furnishing materials, parts, components or assemblies for use at CPS also have responsibilities for the identification of inspection, test and operating status of items under their control. (COP-eeen The programs of suppliers l performing . work at CPS are reviewed and approved to ensure compatibility with the CPS status indication system.--(CCT 0004) l .

out vehnees and audits arc conducted -to dctcrmina '

j' 4mpemenent4 cn and-adettacy of mcasures used to i-ndhate 4 trepec t ion, test and sperating status to mcct thc requircmcats of thc IP Nueienta-Qttality - Assut ancc Program. (CCT 799%

14.3 RESPORSIBILITIES 14.3.1 CPS Plant Staff I

a. Implement programs to indicate inspection, test

. and operating status of ma t e r:.al s , parts, l components, sub-systems and systems during installation, modification, repair, testing and

] operation of CPS.

f

b. Review and approve the programs of suppliers performing work at CPS to ensure compatibility with the CPS status indication system.
c. Implement procedures to control the status of radiological samples,
d. Implement programs to indicate status of nonconforming items.

1 14'.3.2 Nuclear TIAining.& Sucport Oervices l

a. -Implement procedures to control tl.e inspection and test status of items in storage.

14.3.3 Nucicar Assessment l O a. Conduct survc ill-ances and audits of the V impicmentatica and adcquacy of programs used ta h d i-e a t e inspection, test and cpcrating status to cnsurc compl i-ancc with t-he requircmcats of thi-s chaptcr. (CCT 7000) ,

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i lLLINOIS POWER NUCLEAR PROGRAM 3 QUALITY ASSURANCE MANUAL l

@ CHAPTER 15 NONCONFORMING MATERIALS, PARTS OR COMPONENTS 15.1 PURPOSE / SCOPE The purpose of this chapter is tPo describe the measures l established and implemented to control items, services or activities which do not conform to the requirements, and the measures to control further processing, to prevent inadvertent usedeHvery or installation of nonconforming or defective items.

15.2 DESCRIPTIQ1{

15.2.1 The following measures have been established and l implemented at CPS:

a. Control of nonconformances is accomplished in accordance with documented procedures.-(CCT 00&l+ l
b. Nonconformances are documented by means which also er.sure that af fected organizations are notified.

(CCT-000 n

c. Nonconforming items are identified and controlled.

Except for installed items, nonconforming items are placed in a segregated storage area when practical. Such storage areas are identified as containing only nonconforming items. When segregation is impossible or impractical, the nonconforming item shall be identified and controlled by tagging, marking or documentation traceable to the item, including normally installed location.--4CCT items or those removed Osen from the normally l

d. Further use or installation of nonconforming items is controlled in accordance with written procedures and/or instructions. (CCT OteM l
e. The responsibility and authority for the disposition of nonconformances is defined. (CCT seen
f. Permissible dispositions are a) "use as is", b)

" rework" to drawing or specification requirements, c) " repair" to an acceptable level, d) a reject" for that particular use, or e) "other" for non-O- hardware nonconformances.-(CCT 0002F l Page _1_. of _3.,_- REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 15

/N g. " Repair" and " rework" dispositions are implemented V into the affected item in accordance with '

documented procedures and/or instructions. (CCT essiH- t

h. The disposition, along with its engineering analysis and any resultant reinspection and/or acceptance verification, isere documented. (CCT essiH-
1. " Rework" and " repair" actions are described, depending on complexity, by individual procedures '

or by instructions contained in the corresponding work control document. Each procedure or instruction details required inspections and  !

tests. Specified inspections. and tests are  ;

equivalent to original requirements. Acceptable alternatives to original inspection or test requirements may be used provided they are assessed for adequacy and the rationale documented.- (CCT 40054) l 15.2.2 Inservice items that are found to be nonconforming l shall be reviewed to determine equipment operability as defined by the Technical Specifications. For stems that represent significant conditions adverse to quality or safety, or require a repair or use-as-is disposition, an engineering evaluation shall l be performed. The engineering evaluation shall provide support for the initial operability decision and provide the correction or resolution for the identified nonconformances. These items shall be controlled in accordance with approved procedures.---(CCT 0103) 15.2.3 Installed items not in service that are nonconforming l or become nonconforming as a result of maintenance shall be l corrected or resolved prior to operational reliance. These items

! shall be controlled in accordance with approved procedures.

l 15.2.4 A nonconforming item may be conditionally released for l fabrication, installation or testing following an engineering evaluation to determine if such a conditional release is not detrimental to other components or systems. Conditional released items are controlled in accordance with approved procedures. The nonconformance for the conditionally released item shall be corrected or resolved prior to operational reliance.

15.2.5 The Manager - Clinton Power Station has the authority l to - conditionally . release any item or- installation for operation-if needed to place the plant in a safe and stable condition.

Procurca nt documents rcquirc that suppliers havc similar

, meneures catablished for thc itic nt i f icat ion , control and

' s diapositioning of nonconformances and that rccommendcd d+epositiona of "uac-aa-ia" or "rcpair" must bc scported to IP j 1er approval, (CCT 0004+

Pag e ,_2_. o f L., - REVISION 26 i

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 15 15.3 RESPONSIBILITIES 15.3.1 All. Nuclear Procram Personngl

a. All Nuclear Program personnel are responsible for identifying and reporting nonconforming materials, parts, components, services and activities.

15.3.2 Nuclear Procram Departments

a. All Nuclear Program Departments are fesponsible for establishing and implementing effective procedure (s) for identifying, documeating and controlling nonconformances within the scope of their department's activities =as describcd ir. this i chaptcr c,f thc OA tur.nal.

15.3.3. CPS Plant Staff

a. Authorize the conditional release of items.
b. Coordinate with NSED to evaluate and document the safety significance of nonconforming items.

O c. Develop and implement procedures, instructions or work control documents for the control and correction of nonconforming items with repair or rework dispositions.

15.3.4 Nuclear TrAiDino & Suoport Cervices l

a. Implement an effective program for processing supplier nonconformance reports.

15.3.5 Huclear Station Encineerino

a. Implement a program for nonconforming items that ensures "use-as-is" or " repair" dispositions are approved by the appropriate design organization,
b. Coordinate with Plant Staff to evaluate and document the safety significance of nonconforming items,
c. Perform engineering evaluations for conditionally released items.
d. Determine acceptable alternatives to original inspection or test requirements for " rework" or

" repair" dispositions.

e, Document engineering analyses that support the disposition of nonconforming-items.

S.3.0 Nuclear Asscssme l Page ._L of 3 REVISION 26

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 15

\

a. Condttct su rvc i liance s and audita of the nonconformancc control program at CPC to c netwe compliancc with thc rcquircmcata of thc IP Nuelear Quality Aseteancc Program. (CCT 001^'

15.3.64 Facility Review Group l ,

a. Review documented safety evaluations for conditionally released items in accordance with the requirements of 10CFR50.59.

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ILLINOIS POWER NUCLEAR PROGRAM

QUALITY ASSURANCE MANUAL O CHAerER 16 CORRECTIVE ACTION 16.1 PURPOSE / SCOPE The purpose of this chapter is tTo describe. the measures l established and imp /or lemented to assure that conditions adverse to plant safety and quality are promptly identified and corrected; and that significant conditions are identified, evaluated, documented, corrected, reported and independently reviewed.

16.2 DESCRIPTION

16.2.1 Each IP organization and supplier performing activities l or supplying services, materials,' parts or components applicable to this program is required to establish and implement a documented corrective action procedure (s) which assures that conditions adverse to plant safety and/or quality are promptly identified, reported to supervisory personnel, analyzed for significance and corrected. . (CCT BGM+ Personnel or l O' organizations identifying conditions adverse to plant safety and/or quality have the responsibility to report such conditions to the appropriate functional organization who will promptly correct the condition. Conditions adverse to plant safety will be reported to Plant Operations personnel for assessment of operational impact. Reporting may be accomplished through various reporting documents as defined in procedures. An analysis of the significance of conditions adverse to plant safety and/or quality is performed by personnel cognizant of the condition and its resultant effects on plant safety or operability.

16.2.2 Trend analysis is performed on conditions adverse to plant safety and/or quality to determine if a trend representing l significant condition adverse to plant safety and/or quality exists. (CCT 0014) Trend analysis of conditions documented on l maintenance work documents to identify equipment failures and reliability concerns is also performed. The results of these trend analyses are documented and reported to appropriate management cf the area in which the trends are identified.

Reports to management include a history and analysis of the adverse conclitions and trends identified. (CCT 001M l 16;?--3 In the case of.significant conditions adverse to plant l safes r an# , quality, including significant adverse trends, the

(

funct.onal erg nization responsible for the significant condition will ana1>t, .he condition for causes, take appropriate and timely action to preclude recurrence and implement follow-up action as appropriate to verify implementation of corrective Page _1_ of _2 REVISION 26

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL O action.

CHAPTER The actions taken will be documented and reported to appropriate levels of management.

i O

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 16 16.2.4 Corrective action is evaluated to determine effectiveness, including steps taken to identify the cause of its l significant conditions adverse to plant safety and/or quality and action taken to preclude recurrence. (CCT 004-M Documented l corrective action for significant conditions adverse to plant safety is also reviewed. These reviews are documented and are carried out in accordance with a documented program.

16.3 RESPQUSIBILITIES 16.3.1 All Nuclear Program Personnel

a. All Nuclear Program personnel are responsible for identifying and reporting conditions adverse to plant safety and/or quality.

16.3.2 Nuclear Program Deoartments

a. Implement a corrective action procedure (s) which assures that conditions adverse to plant safety and/or quality are promptly identified, reported, analyzed for significance and corrected. In the case of significant conditions, the procedure (s) requires an analysis for causes, action to preclude recurrence, and follow-up to verify g implementation of corrective action.

16.3.3. CPS Plant Staff

a. Assess conditions adverse to plant safety for operational impact.

16.3.4 HucLgat_S Ately & Perlornancq_Jpprpygment_pigpAtiment

a. Implement a Corrective Action Program (CAP) to assure that conditions adverse to plant safety and/or quality are identified, evaluated, reported, corrected, reviewed, evaluated for effectiveness, and trended.
b. Conduct root cause analyses activities.

E.3.4 Nuclear Assesme

a. "valunta corrcctivc action to determine its effcctivenesar
b. Conduct survcillances and sudits of thc corrcctivc action prog ram to ensurc compilance with the requircmcnte of this chapter (CCT 0012) 16.3.5 Nuclear Review and Audit Group
a. Review significant conditions adverse to plant safety in accordance with a documented program.

Page 3 of _2 REVISION 26

1 l

i lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL O CHAPTER 17 I

QUALITY ASSURANCE RECORDS 17.1 PURPOSE / SCOPE The purposw of this chapter is tTo define the requirements and l responsibilities for collection, compilation, storage and I retrieval of records necessary to provide evidence of quality in i the design, fabrication, installation, inspection, testing and operating activities related to the Clinton Power Station.

17.2 DESCRIPTION

17.2.1 Measures shall be established to assure that seufficient recorder are identifiable to the item or activity to l

which they apply.y Records shall be filed in an orderly manner and retrievable. Records are maintained in the records storage facilities.

17.2.2 Test and inspection records shall contain the following information s- (CCT Oes4+

lO l a. Identity of the inspector or data recorder; b- Type of observation;

c. Date and results of the test or inspection (quantitative and quali".ative);
d. Acceptability of the test or inspection resultar and l

I

e. Action taken and rationale to resolve any problema noted.

, 17.2.3 The preparation, collection, review, acceptance, j turnover / transfer, processing, transmittal, retention and retrieval of records is accomplished in accordance with documented standards ~ and procedures. Some quality assurance records may be kept by suppliers and maintained on an available basis for a specified period of time. Such records are required to be offered to IP after the suppliers no longer plan to keep them..

17.2.4 The retention times for the various quality assurance l reco. ds are in accordance with applicable requirements including p 10CFR, and nationally recognized standards and codes. Records are maintained in the records storage facilities that provides controlled access and protection against fire, flooding, vermin and decay.

Page _1_ of _2__ REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 17 Durveillancca and-sudi t a arc conduc ted-o f re corde-syst cms to ensucc compliancc in meeting - the !P Nuclea W.tuality Assurance Program icquircm.nta. (CCT 0020) 17.3 RESPONSIBILITIES 17.3.1 Nuclear Program Departments

a. Dcvalop and I+mplement Records Management  :

Standards--departmental proccdures or instructions for veeerde-prepa ration, collection, review, acceptance, turnover / transfer, processing,  !

transmittal, rcccipt, retention and retrieval which impicmcnt t he--o f rRecords .--Managemend  !

Prgram-and - Ot s nda rd s .=

b. Transfer completed quality assurance records to Nuclear Support Services, Records Management Group ,

for processing and retention.

17.3.2 Nuclear Training _ti Succort Cervices l  ;

a. Establish, maintain and implement a Records Mar.4gement Program including Standards covering the preparation, collection, review, turnover / transfer, processing, retention and 1

O. b.

retrieval of Receive, process records generated activities within the scope of this program.

(index, microfilm, etc.), and in performing retain quality assurance records in the records storage facilities.  !

c. Maintain the CPS records storage facilities such that completed quality assurance records are kept in accordance with the requirements of this manual.

47.3.3. Nuc1 car-Assessmen.:

a. Conduct surveillanccs and audits of rccords systcma to cnsurc compliancc with the rcquircmcats of this-chapeer. (CCT 0020) 1 4

\

Page __2_. of __;L. REVISION 26

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i ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL O CnAereR 18 AUDITS 18.1 PURPOSE /SCOEE The purpose of this chapter is tPo define the requirements and l responsibilities for implementing the program of planned and periodic audits which verify compliance with quality acsurance programs and determine effectiveness in meeting program objectives, 18.2 DESCRI PTIQ1{

id.2.1 IP's Quality Assurance program includes prov.4 91ons for l planned and periodic audits designed to verify compliance with the requirements of the IP Nuclear Quality Aelurance Program and to determine the effectiveness in implementing the program objectives. met OseM The audit program provides for thel following:

a. Provisions are made for both internal and external O b.

audi t a . H CCT - 000%

Audits include the fu'.1 range of activities within l

the scope of the IP Nuclear Quality Assurance Program. These audits shall encompass:

1. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 24 months;
2. The performance, training and qualifications of unit staff at least once per 24 months;
3. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 12 months;
4. The performance of activities required by the Operational Qualicy Assurance Program to meet the criteria of Appendix B, 10CFR Part 50, at least once per 24 months; O

Page ,_1_ of 4 REVISION 26

! ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 18

5. The Emergency Plan and implementing procedures at least once per 12 months;
6. The Security Plan and implementing procedures at least once per 12 monthsiv l
7. Any other area of unit operation considered appropriate by the NRAG or the Vice Presidentiv l
8. The fire protection programmatic controls including the itplementing procedures at least once per 24 months by qualified licensee QA personneliv l
9. The fire protection equipment and program implementation shall be performed at least once per 12 months utilizing either qualified offsite licensee fire protection engineer (s) or an outside independent fire protection consultantiv l
10. An inspection and audit of the fire protection and loss prevention program shall

. be performed by an outside qualified fire O' consultant at intervals no greater than 36 monthes l

11. The radiological environmental monitoring program and the results thereof at least once per 24 W months;- l
12. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 monthest l
13. The PROCESS CONTROL PRO 'MM and implementing procedures for solidific .on of radioactive wasten at least once per 4 months, andsv l
14. Tne peeformance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977, at least once per 24H months. l Additionally, program audits include interface between IP audited organizations and other affected organizations and USAR requi rement s eemnittm*me . (CCT 0105) l (q

~)

c. Provisions are made for regularly audits based upon the status and importance of the scheduling activities. (CCT 0100) l Page ,_2_, of 4 REVISION 26

ILLINOIS POWER NUCLEAR PROORAM QUALITY ASSURANCE MANUAL Chapter 18 o d. A qualification system is established for auditing (d personnel. Independent certifying agencies may be used for the development and administration of lead auditor examinations. (CCT 24 Z0) l

e. Personnel conducting audits do not have any direct responsibilities for the activities being audited.

(CCT 0010)

f. The audit the otherteam leader audit teamis charged members with instructing during audit l preparation and performance. Personnel conducting audits shall have training and/or experience with the activities being audited. (CCT 00101 l
g. Written audit plans are developed which identify the scope, requirements, activities to be audited, organizationn involved, applicable documents, schedule and . .tten procedures or checklists to be used for each audit. Audit planning may credit reviews such as assessments or inspections parformed by non-Audits secticns of the Quality Assurance Department when determining the scope and activities to be assessed by an audit,
h. Audit results are documented, reports are O

QJ generated and retained.

i. Audit reports are distributed to responsible management of the audicing organization and to the appropriate managerial level of the organization having responsibility for the area or audited. (CCT 24 Z7) activity l
j. Appropriate corrective action is developed. (CCT 0011)
k. Follow-up action (including re-audit) is taken to verify that corrective action has been completed and the resolution properly documented when indicated. (CCT 0011) 18.2.2 Audits are initiated as early :n the life of the activity as practicalh4e consis;ent wita the schedule for accomplishing the activity to assure timely implementation of the quality assurance requirements. Audits may be augmented at any time based on recommendations from the Nuclear Review and Audit Group, or Nuclear Program personnel as the scope of work and other requirements for auditing an activity change.

18.2.3 Audited organizations are required to review and l p) provide timely written response to audit findings stating corrective action taken or planned to correct deficient areas and prevent recurrence. (CCT 0200) Follow-up action to verify corrective action has been completed, and the resolutior. is ,

properly documented, shall be taken when indicated. Audit l

=

Page 3 of 4 REVISION 26

l l

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 18 program requirements are imposed on suppliers by appropriate 9 contract or procurement documents. (CCT 0300) l 18.2.4 Reports of internal audits are forwarded to the Nuclear l Review and Audit Group and the Independent Safety Engineering Group for program evaluation. (CCT 0301) IP Management obtains independent audits of the Quality AssuranceNucicar Asscssment i organization. (CCT 0302) 19.d liS PONSIBILITIES 18 2.1 Nuclear Procram Decartments

a. Maintain a program for detarmining and implementing corrective actions to audits.

18.3.2. Nuclear Review and Audit Grouo

a. Review reports of internal audi ts for program evaluation.

18,3.3 Quality AngurancqNucicar Asscssment l

a. Implement an internal audit program and audit each IP organizatior performing activities within the scope of the quality assurance program to verify O that the requirements of this manual are met. (CCT 0022) being l
b. Implement an external audit program and audit suppliers performing quality related activities to ved fy compliance with the supplier's respective quality assurance programs, contract, specifications and requirements, as defined on the procurement documentpurchasc rcquisition. (CCT ess9t
c. Coordinate for the Vice President, the performance of independent audits of the Quality AssuranceNucicar Asscasmcnt organization. (CCP 0+0%f
d. Implement a program for evaluating the adequacy of corrective actions to audits findings. (CCT 0011) 18.3.4 Hugliar Safety & Perform _pnce Imorovement Department ae. Independent Safety Engineering Group review l reports of internal audits for program evaluation.

Oi U

Page 4 of 4 REVISION 26

l lLLINOIS POWER NUCLEAR PROGRAM l QUALITY ASSURANCE MANUAL APPENDIX A GLOSSARY OF TERMS Acceotance Criteria -

Specified limits placed on characteristics of an item, process or service defined in codes, standards or other requirement documents.

Audit -

A documented activity performed in accordance with written procedures or checklists to verify, by examination and evaluation of objective evidence, that applicable elements of the quality assurance program have been developed, documented and effectively implemented in accordance with specified requirements.

Auditor - Any individual who performs any portion of an audit, including lead auditors, technical specialists, auditors-in-training and others, such as management representatives.

Authorized Insoection Agency (AIA) - An agency designated as such by the appropriate legal authority of a State or Municipality of the United States or a Province of Canada or an insurance company authorized to write boiler and pressure vessel insurance in that jurisdiction in accordance with the provisions set forth in ASME N626, per the approved year / Edition.

C' Authorized Nuclear Inst:rvice Insnector ( ANII) /Authqrized Nuclqar Inagettor (ANIL - An authorized Nuclear Inservice Inspector and Authirized Nuclear Inspector is an employee of an Authorized Inspection Agency who meets the requirements of ANSI /ASME N626.1

+9M , per the approved year / Edition -and the rcquircmcnts of ANS+

NC20.0 1903 for Authorincd Nucicar !napcctor 'ANI).

Certification - The act of determining, verifying and attesting in writing to the qualification of personnel, processes, procedures or items in accordance with specified requirements, certificate of Comoliance - A written statement signed by a qualified party attesting that the iteme or services are in accordance with specified requirements and accompaniedaccomplished by additional information to substantiate l the statement.

Certificate of conformance - A written statement signed by a qualified party certifying that items or services comply with specific requirements.

Certified Test Recort - A written and signed document approved by a qualified party that contains sufficient data and information to verify the actual properties of items and the actual results

/] of all required tests.

(") Characteristic - Any property or attribute of an item, process or service that is distinct, describable and measurable, as Page _A-l._ of 9 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM APPENDX A QUALITY ASSURANCE MANUAL GLOSSARY OF TERMS

.U (0 conforming or nonconforming to specified quality requirements.

Quality characteristics are generally identified in specifications and drawings which describe the item, process or service.

Chemical cleanina -

Refers to the use of acids and caustic substances applied to material or product forms during manufacture, maintenance or repair.

Codes - Collective term used to describe all the published codes applicable to Clinton Eower Station operations, such as the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

Commercial Grade classified Items -

Items which are: (1) not subject to design or specification requirements unique to NRC licensed facilities or activities; (2) used in applications other than NRC licensed facilities or activities; and (3) able to be ordered from the manufacturer / distributor on the basis of the '

manufacturer's published specifications or descriptions.

condition Adverse to Ouality -

An all inclusive term used in reference to any of the following: failures, malfunctions, deficiencies, deviations, defective items and nonconformances.

G

,fj Control Stamo - A stamp used to mark a unique identification of inspection or test status upon items, tags, labels, routing carde or reccrds traceable to an item. Control stamp impressions clearly identify the person who applied it such that traceability to their authorization is provided.

Correction -

The process of bringing a nonconforming item into conformity with an approved design, i.e., implementation of a dispositioned nonconformance document.

corrective Action -

The action required to correct or resolve adverse conditions in equipment, material, processes, procedures or activities when noted. Action taken may be remedial action to correct the specific condition, corrective action to preclude recurrence, or both.

CPEL- Abbreviation for Clinton Power Station.

DeDartmental Procedures or Inst ructions -

Procedures or instructions approved and issued within a department which provide _ detailed direction to personnel.

Deviation -

A nonconformance or departure of a characteristic from specified requirements.

  1. Documents -

Co?'ective term used to describe all written or pictorial information that directs or shows how an activity is to be accomplished. Documents include, but are not limited to ,

i drawings, procedures, instructions and changes thereto.

Page A-2 of 9 REVISION 26

1 ILLINOIS POWER NUCLEAR PROGRAM APPENDX A QUALITY ASSURANCE MANUAL GLOSSARY OF TERMS p

Documentation - Any written or pictorial ? ;. formation describing, defining, specifying, reporting or cortifying activities, requirements, procedures or results.

Examination -

An element of inspection consisting of investigation of materials, components, supplies or services to determine conformance to those specified requirements which can 4 be determined by such investigation. Examination is usually nondestructive and includes simple physical manipulation, gauging and meaaurement.

Extended Ouality Assurance Proaram -

The selected use of technical and management controls to improve the operational performance of equipment important to reliable station operation but not included in compliance based quality assurance programs.

External Audits -

Audits of those portions of contractors',

vendors' and suppliers' quality assurance program activities not retained under IP's direct control and not within the IP organizational structure.

Facility Review Groun (FRG) - An on-site committee whose function is to advise the Manager -

Clinton Power Station on matters related to nuclear safety.

Follow-uo -

Action involving direct communication with the responsible nrganization to assure a timely written response to findings, adequacy of the response and corrective action accomplishment as scheduled, llaTJ1WAIg__ Change - A plant design change that can include but is not limited to hardware, configured software or design document changes.

Hold Point - Point in a procedure or work document at which the performer is required to stop and notify inspection personnel to allow for planned inspections. The work activity shall not proceed without the point being signed by inspection personnel, or inspection personnel being notified and authorizing- the activity to proceed, or the point waived / reclassified.

Indeoendent Review - Review completed by personnel not having direct responsibility for the work functions under review regardless of whether they operate as a part of an organizational unit or as individual staff members.

Inservice Insoection -

A mandatory program of exam nations, testing, inspections _and control of repairs and replace.nents to p ensure adequate safety in maintaining the nuclear power plant and V)

/' to return the plant to service in a safe and expeditious manner in accordance with the CPS ISI Program Manual.

Page A-3 of 9 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM APPENDX A QUALITY ASSURANCE MANUAL GLOSSARY OF TERMS

! )

V" Insoection -

A phase of quality control 'which by means of examination, observation or measurement determines the conformance of materials, supplies, components, parts, appurtenances, systems, processes or structures to predetermined quality requirements.

Insp:ction Point A point in a proccdurc or work documcat a e-which the pcrformer is rcquircd to notify inspcction pcrsonnc1 in ordcr to plan --;'hcn thcy .;ill pcrform thc vcrification activity An-Fnspcction Point chall bc capabic of bcing vcrificd aftcr wot4e complction.

Interface - When two or more organizations have responsibilities for accomplishing an activity, the functional relationship that one organization has to the others in completing the activity is called an " interface" relation. One example of interface is when one organization must perform a step which is a prerequisite to another organization accomplishing its function. Interface can also mean that several organizations accomplishing similar activities are under the coordination control of one organization.

Internal Audits -

Audits of those portions of IP's Quality Assurance program activities retained under direct Company control and within the IP organizational structure.

IE - Abbreviation for Illinois Power.

Item - Any level of unit assembly, including structu.1, syst; sub-system, subassembly, component, part or material.

Lead Auditor - An individual qualified and certified to organize and direct an audit, report audit findings and evaluate corrective action.

tipasurina and Test Eauioment - Equipment used to quantitatively generate or measure physical parameters with a known degree of accuracy for the purpose of calibration, inspection, test or repair of plant mechanical, electrical or instrument / control equipment. (This does include permanently installed instrument and control devices.)

Modification A planncd changc in plant dcsign or opcration and accomplished in accordance .;ith thc rcquircmcats and limitations of applicabic codes, standards, spccifications, liccascs and prcdctcrmincd ;;fcty scstricticas.

Noncomoliance -

A failure to comply with a regulatory requirement.

Nonconformance - A deficiency in characteristics, documentation e or procedure which renders the quality of an item unacceptable or indeterminate. Examples of nonconformances include physical defects; test failures; incorrect or inadequate documentation; or unauthorized deviations from prescribed processing, inspection or test procedures.

Page A-4 of 9 REVISION 26

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/

ILLINOIS POWER NUCLEAR PROGRAM APPENDX A

-QUALITY ASSURANCE MANUAL GLOSSARY OF TERMS 3 Nuclear Review and Audit Group (NRAG) - A committee responsible for the independent safety review function.

Obiective Evidence -

Any statement of fact, information or record, either quantitative or qualitative, pertaining to the quality of an item or service based on observations, measurements or tests which can be verified.

Operable / Operability -A system, subsystem, train, component or device shall be operable or have operability when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform- its function (s) are also capable of performing their related support function (s). NOTE: Safe operation of the plant is determined by CPS licensed operators.

Permanently Installed Instrument and Control Devices -

The installed plant equipment including computer points used in determining acceptance criteria of Technical Specification surveillances (Category A Instruments).

. IOJ Plant Changa -

A change similar to that of a hardware change except that it does not impact the Design Bases, does not have D major impacts and does not contain an unreviewed safety question.

Plant Staff - The organization which is directly responsible for the operation of the Clinton Power Station. The Plant Staff includes operations, technical, maintenance, radiation protection, and support departments.

Procedure -

A document that specifies or describes how an activity is to be performed. It may include methods to be employed, equipment or materihls to be used and sequence of operations.

Procurement Documents -

Contractually binding documents that identify and define the requirements which items or servi:es must meet in order to be considered acceptable by the purchaser.

Procurement documents include auch items as contracts, letters of intent, purchase orders or prisposals and tF c acceptance which authorizes the seller to perform services or supply equipment, materials or facilities on behalf of the purchaser.

Qualification - (Personnel) -

The characteristi . or abilities gained through training or experience or both .nat enable an individual to perform a required function, m

Ouality Assurance -

All those planned and systematic actions

.(

V J necessary to provide assurance that a structure, system or component will perform satisfactorily in service.

Page A-5 of 9 REVISION 26

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lLLINOIS POWER NUCLEAR PROGRAM APPENDX A QUAllTY ASSURANCE MANUAL GLOSSARY OF TERMS m

-[vA Ouality Assurance Record - ihose delineated completed records which furnish documentary evidence of the quality of items and/or activities affecting quality within the L: ope of the IP Nuclear Quality Assurance Program.

Quality control - Those quality assurance actions which provide a

, means to control and measure the characteristics of an item.

process or facility to established requirements.

Quality Related - Activities which cithcr do or could -influence l quality of safety-related items or work related to those systems, structures and components as identified in the USAR, Table 3.2-1, including design, purchasing, fabricating, handling, shipping, stcring, cleaning, preserving, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling or modifying.

Recelot Inspection - An inspection which verifies that items are in satisfactory condition, that they match the purchase order requirements and that required documentation accurately reflects the item (s) received, Visual and physical inspection will be performed as necessary to determine the acceptability of the item (s).

Reculations -

Collective term used to describe the governing

[ directives and laws applicable to Clinton Power Station operation, such as the Code of Federal Regulations.

Reoair - The process of restoring a nonconforming characteristic to a condition such that the capability of an item to function reliably and safely is unimpaired, even though that item still may not conform to the original requirement. For ASME Section XI A :: tivi tie s , " REPAIR" is the process of restoring a non-conforming item by welding, brazing or metal removal such that existing design requirements are met.

Resolution - The process by which a nonconforming item is corrected or determined to adequately perform its design function without adversely affecting safety. The resolution may contain controls or limitations that are to apply until the nonconformance is fiilly corrected.

EnoIk - The process- by which a nonconforming item is made to conform to prior specified requirements by completion, remachining, reassembling or other corrective means.

Safety Related -

Systems, structures and components which are considered important to safety because they perform safety actions required to avoid or mitigate the consequences of

, abnormal operation transients or accidents. In addition, design

( j requirements are placed upon such equipment to assure the proper

'V -performance of safety actions, when required. Safety related items are those designated Seismic Category 1, Safety Class 1, 2, Page A-6 of 9 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM APPENDX A QUALITY ASSURANCE MANUAL GLOSSARY OF TERMS (m

/

V) 3, "Other" and Electrical Class 1E as identified in the USAR, Section 3.2.

'I Scope - The area covered by a given activity or subject.

Seismic classification - Plant structures, systems and components important to safety which are designed to withstand the effects of a safe shutdown earthquake (SSE) and remain functional if they are necessary to assure:

a. The integrity of the reactor coolant pressure boundary, or
b. The capability to shutdown the reactor and maintain it in a safe condition, or
c. The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10CFR100.

Plant structuras, systems and components, including their foundations and supports, which are designed to remain functional in the event of an SSE are designated as Seismic Category 1 as indicated in Table 3.2-1 of the CPS USAR.

C' significant condition Adverse to ouality and/or Safety -

A condition that affects or is likely to have an effect on, or influence, the safe operation of the plant, the capability to shut down the reactor and maintain it in a safe shutdown condition or the capability to prevent or mitigata the consequences of accidents which could result in potential 2 site exposures.

Source Insoection - An inspection performed at the location of item procurement, supply or manufacture for the purpose of

-verifying that the item meets speified requirements.

Soecial Processes - Term used to describe those activities or processes in which the end result or product quality either cannot be readily verified when the process is complete or it is not prudent to delay verification until process completion. The assurance of quality is heavily dependent upon control of the process and the skills of the personnel who perform the process.

Standards --Term used to describe the results of standardization ef forts which have been approved by recognized authorities. As used herein, standards refer to either publications describing an acceptable method of implementing or performing an activity or an item of known value used for comparison.

I'c) v' Ston Work - Collective term used to describe the following three 0; levels of stopping w'rk activities: l Page A-7__ of 9 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM APPENDX A QUALITY ASSURANCE MANUAL GLOSSARY OF TERMS N._/ a. The stoppin[ of a singleAsacssmcat Quality AssuranceNucicar or specific work activity personnel. by l

b. A hold imposed by a Department Head on a department or general work activity.
c. A Stop Work Action initiated by the Manager - Quality As suranc eNtte+ ear-Assessment .

Supplier - Any ine'.ividual or organization that furnishes items or services to IP under a procurement document.

Surveillance - A review or observation of an activity, process or product to verify that an action has been or is being accomplished in accordance with applicable requirements and management expectations.

Survev - A documented evaluation of an organization's ability to i

perform activities as verified by a determination of the adequacy of the organization's quality program and by a review of the implementation of that program at the location of work.

i System Safety Clat>sifications - Structures, systems and components are classified as Safety Class 1, Safety Class 2, f3,/ Safety Class 3, Safety Class other or M ass 12 in accordance with t, the importance to Nuclear Safety. ';quipment is assigned a specific safety class,- recognizing :'at components within a system may be a differing safety importance. Definitions of various Safety Classes are:

Safety Class 1 -

Components of the reactor coolant pressure boundary or core support structure whose failure could cause a loss of reactor coolant at a rate in excess of the normal make-up system.

Safety Class 2 -

Structures, system and components, other than service water systems, that are not Safety Class 1, but are necessary to accomplish the safety functions of:

a. Inserting negative reactivity to shut down the reactor,
b. Preventing rapid insertion of positive reactivity,
c. Maintaining core geometry appropriate to all plant process conditions,
d. Providing emergency core cooling,
e. Providing and maintaining containment,

(

f. Removing residual heat form the reactor and reactor core, or
g. Storing spent fuel.

Page A-8 of 9 REVISION 26

i ILLINOIS POWER NUCLEAR PROGRAM APPENDX A )

QUALITY ASSURANCE MANUAL GLOSSARY OF TERMS G

Safety _ Class 3 - Structures, systems and components that are not safety class 1 or Safety class 2, but whose function is to process radioactive - fluids and whose postulated failura would result in conservatively calculated offsite doses that exceed 0.5 .

rem to the whole body or its equivalent to any part of the udy d

in accordance with Regulatory Guide 1.26.

fafety class other" - Structures, systems and components used in the power conversion or other portions of the facility which have no direct safety function, but which may be connected to or influenced by the equipment within the Safety classes 1, 2 or 3.

CIAaa_U - The safety classification of the elactric equipment and systems that are essential to emergency reactor shutdown, containment isolation, reactor core cooling and containment and reactor heat removal or otherwise are essential in preventing significant release of radioactive material to the environment.

(Structures, systems and component safety classifications and related Quality Assurance Program requirements classifications are summarized in Table 3.2-1 of the USAR.)

Technical SoecificatJong -

Appendix A to the Operating License A containing the design and performance criteria and operating

.f limits and principles to be observed during critical testing, startup, power opeYations, refueling and maintenaOCe operations.

Traceability -

The ability to identify the origins of a part'cular item when required by adopted codes or standards.

ILSAh - Abbreviation for the Updated Safety Analysis Repnrt, which is the document submitted by IP to the Nuclear agulatory Commission in accordance with 10CFRSO.71.

Use-As-la - A disposition which may be imposed for a nonconformance when it can be established that the discrepancy will result in no adverse conditions to safety and that the item under consideration will continue to meet all engineering functional requirements including performance, maintainability, fit and safety.

Verification -

The act of confirming, substantiating or assuring that an activity or condition has been implemented in conformance with the specified requirements.

Witness Point -

Point in a procedure or work document at which the performer is required to stop and notify inspection personnel to allow for planned inspections. Once notification has been accomplished and the agreed to time (or a reasonable amount of f time) has passed, the work activity may continue.

L/

I Page A-9 of 9 REVISION 26

.I

lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL APPENDIX B O SUPPLEMENTAL APPLICATION IP NUCLEAR QA PROGRAM This appendix details in matrix form the chapters of this manual which are applicable in full or in part to:

Fire Protection Security Environmental Radwaste/ Augmented D Systems Packaging and Transportation of Radioactive Material 10CFR50, Appendix B requires that a quality assurance program be established in writing and executed for activities affecting the safety-related function of designated structures, systems and components to an extent consistent with their importance to safety. Table 3.2-1 in the Clinton Power Station USAR identifies specifically those structures, systems and components that are '

important to safety.

Fire Protection, Security, Environmental and Radwaste/ Augmented D systems are specifically identified in Table 3.2-1 of the CPS USAR and/or highlighted in several Regulatory Guides that define and clarify their importance to the plant.

A Q Regulatory Guide 1.120, " Fire Protection Guidelines for Nuclear Power Plr.nts", Revision 1 (November 1977) states that, "A quality assurar.ee (QA) program is needed to identify and rectify errors in design, construction and operation (of a fire protection system) and is an essential part of defense in depth."

Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Normal Operation - Effluent Streams and the Environment", Revision 1 (February 1979) , states that, "The need of quality assurance is implicit in all requirements for effluent and environmental monitoring." Regulatory Guide 1.143, Revision 0 (July 1978) states that, " ...to ensure that systems will perform their intended function a quality assurance program sufficient to ensure that all design, construction and testing provisions are met should be established and documented."

Regulatory Guide 1.17, " Protection of Nuclear Power Plants Against Industrial Sabotage", Revision 1 (June 1973), requires programmatic controls over the design, construction, testing and

+

operation of the security system at nuclear power plants.

sCFR Part 71, " Packaging and Transportation of Radioactive Material", Section 71.101, " Quality Assurance Requirements",

requires that licensees h ve a quality assurance program that has been submitted to and approved by the NRC as satisfying the provisions of Subpart H of Part 71. Subpart H requires, in part, g that licensees' quality assurance programs satisfy each of the l

v} applicable critcria specified in Section 71.101 to an extent consistent with their importance to safety. Regulatot - Guide 7.10, " Establishing Quality Assurance Programs for Packagiag Used Page B-1 of 12 REVISION 26

ILLINOIS POWER NUCLEa R PROERAM APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION A IP NUCLEAR OA PROGRAM V in the Transport of Radioactive Material", Annex 2, provides quality assurance programs applicable to Procurement, Use, Maintenance, and Repair of Packaging U9ed in Transport of Radioactive Material.

The extent to which the IP Nuclear Quality Assurance Program applies to each of the four areas varies as defined further under subsequent sections of this appendix. The attached matrix outlines which chapters of this manual apply to Fire Protection, Security, Environmental and Radwaste/ Augmented D systems and Packaging and Transportation of Radioactive Material.

J (D

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Page B-2 of 12 PEVISION 26

( ILLINOIS POWER NUCLEAR PROGRAM APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION IP NUCLEAR OA PROGRAM CHAPTERS OF THE IP NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL APPLICABLE TO FIRE PROTECTION, SECURITY, ENVIRONMENTAL, AND RADWASTE/ AUGMENTED D, AND PACFAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL OPERATIONAL FIRE SECURITY ENVIRONMENTAL RADIOACTIVE PACKAGING AND QA MANUAL PROTECTION WASTE / TRANSPORTATION CHAPTER AUGMENTED D OF PADIOACTIVE MATERIAL 1 YES NO YES YES YES 2 YES NO YES YES YES 3 YES NO NO YES YES 4 YES NO YES YES YES 5 YES NO YES YES YES 6 YES NO YES YES YES .

7 YES NO YES YES YES 8 NO NO YES NO YES 9 NO NO NO YES YES 10 YES NO NO YES YES 11 YES NO YES YES YES 12 NO NO YES NO YES O 13 14 15 NO YES YES NO NO NO YES YES YES YES YES YES YES YES YES 16 YES YES YES YES YES 17 YES YES YES YES YES 18 YES YES YES YES YES NOTE: Structures, systems and components subject to the above requirements are described by USAR Table 3,2-1 and further ( ifined by engineering specifications, drawings, procedures, instructions, other documents, etc.

O Page B-3 of 12 REVISION 26

lLLINOIS POWER NUCLEAR PROGRAM APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION A IP NUCLEAR OA PRQGEAM

('~') FIRE PROTECTION Chapter 1 -

Applicable Chapter 2 - Applicable Chapter 3 - Applicable Chapter 4 - Applicable. Specification of quality assurance program requirements for suppliers of fire protection materials, equipment and services shall be on a case-by-case basis. Commercial grade or off-the-shelf items may prc. vide an acceptable level of quality based on the nature of the item. This determination shall be made by Engineering personnel prior to issuance of procurement documents Chapter 5 - Applicable ,

Chapter 6 - Applicable Chapter 7 - Applicable. Suppliers providing material, equipment and services for fire protection shall be subject to

~ source evaluation and surveillance. The extent of

/3 imposition of these requirements shall be determined b on a case-by-case basis by the design organization responsible for review and approval of the procurement specifications. Measures shall be established, as appropriate, for examination of products upon delivery.

Chapter 8 - Not Applicable Chapter 9 - Not Applicable Chapter 10 - Applicable only to inspection of those items and activities affecting the fire protection system within the quality assurance boundaries as specified in the USAR, Table 3.2-1 and further amplified by the appropriate design drawings.

Chapter 11 - Applicable Chapter 12 - Not Applicable

_ Chapter 13 - Not Applicable Chapter 14 - Applicable

_n. Chapter 15 - Applicable

! I k/ Chapter 16 - Applicable Page E-4 of _12_ REVISION 26 _

ILLINOIS POWER NUCLEAR PROGRAM APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION

^

IP NUCLEAR OA PROGRAM Chapter 17 - Applicable to documents designated as Quality Assurance Records generated in the. implementation of the Fire Protection program and consistent with the requirements identified in Chapter 10 above.

Records are prepared and maintained to furnish evidence that the applicable criteria discussed herein are being met for activities affecting the Fire Protection program.

Chapter 18 - Applicable. Audito shall be performed and '

documented to verify compliance with the Fire Protection program, including design and procurement documents, instructions, procedures and drawings and inspection and test activities.

O n

Page B-5 of 12 REVISION 26

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lLLINOIS POWER NUCLEAR PROGRAM APPENDIX E QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION

,q IP NUCLEAR OA PROGRAM SECURITY Chapter 1 -

Not Applicable Chapter 2 - Not Applicable Chapter 3 - Not Applicable Chapter 4 - Not Applicable Chapter 5 - Not Applicable Chapter 6 - Not Applicable Chapter 7 - Not Applicable Chapter 8 - Not Applicable Chapter 9 - Not Applicable Chapter 10 - Not Applicable Chapter 11 - Not Applicable (N Chapter 12 - Not Applicable

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Chapter 13 - Not Applicable Cnapter 14 - Not Applicable Chapter 15 - Not Applicable Chapter 16 - Applicable Chapter 17 - Applicable to those records required by the CPS Physical Security Plan.

Chapter 18 - Applicable to the physical security of CPS and designated records.

()1 Page B-6 of 1 REVISION 26

ILLINOIS POWER NUCLEAR PROERAM - APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION IP NUCLEAR OA PROGRAM ENVIRONMENTAL Chapter 1 -

Applicable Chapter 2 - Applicable Chapter 3 - Not Applicable Chapter 4 - Applicable to procurement of monitoring services to be performed by contractors providing services dealing with radiological data and to radionuclide reference standards used for calibration of radiation measurement systems.

Chapter 5 - Applicable to al: activities related to carrying out the radiological monitoring program including:

sample collection; packaging, shipment and receipt of samples for offsite analysis; procurement, maintenance, storage and use of radioactivity reference standards; calibration and checks of radiation and radioactivity measurement systems; and reduction, evaluation and reporting of data.

Chapter 6 - Applicable to procedures and instructions required by Chapter 5.

Chapter 7 - Applicable to radionuclide reference standards used for calibration of radiation measurement systems and to radiological monitoring activities (services) provided by contractors.

Chapter 8 - Applicable only to radiological sample collection, identification, packaging, shipping, receiving, storage and analysis.

Chapter 9 - Not Applicable Chapter 10 - Not Applicable Chapter 11 - Applicable to radioactivity measurements of samples, instrument backgrounds, replicate samples and analytical blanks; data reduction and verification; computer program documentation and verification.

Chapter 12 - Applicable to laboratory instruments for radiation and radioactivity measurement, continuous radiological effluent monitoring systems and flowrate measuring devices associated with radiological effluent monitoring systems, f

v Chapter 13 - Applicable to radiological samples only.

Chapter . . - Applicable to continuous radiological effluent monitoring systems equipment only.

Page B-7 of 12 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION Chapter 15 - Applicable Chapter 16 - Applicable Chapter 17 - Applicable to personnel training and qualifications field and in-plant collection of samples; continuous effluent monitoring; sample receipt and laboratory identificationi sample preparation and radiochemical processing; radioactivity measurements of samples, instrument backgrounds and analytical blankst data reduction and verification; instrument calibration and calibration standards; computer program documentation; audits; and corrective action.

Chapter 18 - Applicable O

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Page B-8 of 12 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION eN IP NUCLEAR OA PROGRAM RADIOACTIVE WASTE / AUGMENTED "D" Chapter 1 -

Applicable Chapter 2 - Applicable Chapter 3 - Applicable Chapter 4 - Applicable. Specification of quality assurance program requirements for suppliers of radioactive waste / augmented D materials, equipment and services shall be on a case-by-case basis. Commercial grade or off-the-shelf items may provide an acceptable level of quality based on the nature of the item.

This determination shall be made by Engineering personnel prior to issuance of procurement documents.

Chapter 5 - Applicable Chapter 6 - Applicable Chapter 7 - Applicable. Suppliers providing materi ,, equipment and services for radioactive waste / augmented D shall be subject to source evaluation and surveillance.

(Q) The extent of imposition of these requirements shall 4

be determined on a case-by-case basis by the design organization responsible for review and approval of the procurement specifications. Measures shall be eatablished, and appropriate, for examination of products upon delivery.

Chapter 8 - Not Applicable Chapter 9 - Applicable to the qualification of welders and welding procedures (ASME Section IX) for

, Radwaste/ Augmented "D: system. ) Pressure boundaries only.)

Chapter 10 - Applicable only to inspection of those items and activities affecting Radwaste/ Augmented D systems within the quality assurance boundaries as specified in the USAR, Table 3.2-1, and further amplified by the appropriate design drawings.

Chapter 11 - Applicable Chapter 12 - Not Applicable

- _ Chapter 13 - Applicable V

Page B-9 of 12 REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM APPENDIX B QUALITY ASSURANCE MANUAL SilPPLEMENTAL APPLICATION Chapter 14 - Applicable Chapter 15 - Applicable Chapter 16 - Applicable Chapter 17 - Applicable 4

Chapter 18 - Applicable 1

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Page B-10 of liL. REVISION 26

ILLINOIS POWER NUCLEAR PROGRAM APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION IP NUCLEAR OA PROGRAM PACKAGING AND TRANSPORTATION OF RADIOACTIVE MATERIAL Chapter 1 -

Applicable Chapter 2 - Applicable Chapter 3 - Applicable, design activities are not normally performed by Clinton Power Station for radioactive material packaging however, audits of suppliers establish that the design was accomplished under control of an NRC approved QA program.

Chapter 4 -

Applicable Chapter 5 - Applicable Chapter 6 - Applicable Chapter 7 - Applicable, measures such as source surveillance and audits of records should be taken as appropriate to ensure that the design and fabrication of packaging were performed under the control of an NRC-approved QA program.

(T Chapter 8 - Applicable Chapter 9 - Applicable, special processes such as welding or nondestructive testing are not normally performed by Clinton Power Station. However, if packaging requires major repairs necessitating use of special processes, e.g., welding or heat treating, measures shall be established to ensure that the special processes are controlled.

Chapter 10 - Applicable, visual inspections shall be performed upon receipt of packaging to ensure compliance with certificates of compliance.

Chapter 11 - Applicable Chapter 12 - Applicable Chapter 13 - Applicable, all conditions identified in a certificate of compliance when using packages shall be adhered to.

Chapter 14 - Applicable Chapter 15 - Applicable Page B-11 of 12 REVISION 26

. . - _ =___ . _ _ . _

lLLINOIS POWER NUCLEAR PROGRAM APPENDIX B QUALITY ASSURANCE MANUAL SUPPLEMENTAL APPLICATION IP NUCLEAR OA PROGRAM O Chapter 16 - Applicable, measures are established for obtaining corrective actions f rom suppliers and for ensuring that follow-up is documented to verify that corrective actions were implemented and effective.

Chapter 17 - Applicable, records showing evidence of delivery of packages to a carrier and proof that all NRC and DOT requirements have been satisfied shall also be retained.

Chapter 18 - Applicable, audits are performed on the supplier of packaging to ensure compliance with the certificate of compliance.

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U Page B-12 of 12 REVISION 26

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