Text

Rev 23 to QA Manual
	ML20126H511
Person / Time
Site:	Clinton
Issue date:	12/22/1992
From:	; ILLINOIS POWER CO.
To:	;
Shared Package
ML19310E780	List: ML20126H511;
References
	NUDOCS 9301050234
	Download: ML20126H511 (103)
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IP Nuclear Program Quality Assurance Manual Revision 23 10CFR50.54(a) Evaluation Summarv-Revision 23 to the IP Nuclear Program QA Manual was initiated to:

Accurately reflect the current organizational structure.

Remove Manager - Scheduling outage Management and-Manager -

Projects and Assessment.

Add the Manager -

Purchasing and Material Control and responsibilities.

Add the Quality Assurance Department Program Monitoring Section responsibilities.

Combine the responsibilities for the Quality Engineering and Verification Section.

Clarify Nuclear Station Engineering Department responsibilities regarding non-destructive examinations.

Clarify the wording and responsibility for verifying corrective. actions to internal and external audit findings.

Remove the old Illinois Power logo and forms.

Evaluation The changes to the IP Nuclear Program QA Manual do not: (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 controls previously established over-activities affecting quality of CPS structures, systems, or components.

Performed: (. f

- 4 M 6c4 l$l}50f

/M Supervisor - Quality Systems /Date Reviewed: -

<< v M/.4 Director - Quality Assurance /Date

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Approved: Yt -

Manager - Quality Assurance /Date 9301050234 921228

'PDR ADOCK 05000461

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,'.' ,lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL TABLE OF. CONTENTS Chapter Chapter-Number Title 11 List of Effective-Pages 111 Introduction iv Authorization '

v -Glossary of Terms 1 Organization 2 Quality Assurance Program 3 Design Control 4

Procurement Document Control' S

Instructions, Procedures & Drawings 6 Document Control 7 Control of Purchased Material, Equipment and Services t 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 Revisions to IP Nuclear Program Quality Assurance Manual' Appendix B Supplemental Application - IP. Nuclear

. Qual'ity Assurance Program PAGE- i REVISION: _21.

DATE: 12/28/92 4

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" -ILLINOIS POWER NUCLEAR PROGRAM-

! QUALITY ASSURANCE MANUAL- LIST OF EFFECTIVE PAGES -

-LIST OF EFFECTIVE PAGES Revision 23 The - following pages and their indicated revision and date of issue are included in the IP Nuclear Program Quality Assuranco Manual.

frcle No. Rev, Date 1 23 11 12/28/92 23 12/28/92 111 23 iv 12/28/92 23 12/28/92-v v-10 23 1 1-13 12/28/92 23 12/28/92 2 2-6 23 3 3-5 12/28/92 23 12/28/92 4 4-3 23 5 5-2 12/28/92 23 12/28/92 6 6-4 23 7 7-5 12/28/92' 23 12/28/92 8 8-3 23 9 9-4 12/28/92 23 12/28/92 10 10-3 23 ,

11 11-3 12/28/02 23 12/28/92-12 12-3 _23 12/28/92 13 13-3 23 14 14-3 12/28/92:

23 12/28/92 15 15-4 23 16 16-3 12/28/92 23 ,12/28/92 17 17-2 23 10 18-3

.'12/28/92 A-1 23_ 12/28/92 23 12/28/92 B1 -B-12 23 12/28/92 PAGE 11 REVISION: 23 DATE: 12/28/9:!_-

--.lLLINOIS POWER NUCLEAR PROGRAM' QUALITY. ASSURANCE MANUAL INTRODUCTION l

INTRODUCTION 1111nois Power Company -(IP), as principal owner of 'Clinton

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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, Part 50,- Appendix B, " Quality Assurance Criteria for Nuclear Power Plants;" Title 10 of the code of Federal Regulations ~, 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 Operational Phase of Nuclear Power Plants". . Assurance for the-The IP Nuclear Quality Assurance Program applies to those activities associated with or affecting the ability of the plant's structures, systems, and compon'onts to function .in preventing, _ or mitigating the consequences of, postulated-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 programs.

packeging and. shipping, fire protection, - and ' security The structures,-systems, and. components-to which_the activities and programs apply are delineated in Table 3. 2-l ' of -

the Updated Safety-Analysis Report (USAR)..

This manual _ is arranged in_ eightecn_ -chapters which correspond with .the -eighteen criteria _. contained in- 10CFR50-Appendi B and 10CFR71 subpart H.- Each chapter is further-broken down it o three _ main sections which describe the purpose- and '

scope of that chapter, aLdescription of the quality-program, and

.the- division of responsibilities. The'-Quality Assurance organization approves the distribution and.is responsible'for the maintenance of- this manual. in accordance' with approved'

-departmental procedures. Each manual. holder is r e s p o n s i b l e -- f o r *

maintaining his copy updated in accordance with Appendix A.

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.

PAGE 111 REVISION: 23 DATE: 12/28/92

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.lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL AUTuoRIzATION AUTHORIZATION The IP Nuclear Quality Assurance Program applies to every member of the Company performing work related to CPS and covered by the Manual. Specific responsibilities shal.1 be assigned by IP management and supervision, consistent with the requirements described in this Quality Assurance Manual. It is emphasized that the portion of the program assigned to the Quality Assurance organization primarily concerns verification activities, such as inspection, auditing, surveillance, evaluating and reporting effectiveness, and providing recommended solutions to noted problems. The major portion of the Quality Assurance program is carried out by IP departments other than Quality Assurance. In recognition of these responsibilities, each Department Manager has concurred with the contents of this manual.

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.

Approved M 12/28/92 Manager - Duality Assurance PAGE iv REVISION: 23 DATE: 12/28/92

.lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL.

GLOSSARY-OF_ TERMS GLOSSARY OF TERMS Accentance Criteria - Specified limits placed on characteristics

-of an item, process or service defined in codes, standards or-other requirement documents. '

l Aud1.t -

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: require-ments.

, 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 Inspection Aaency (AIA) - An agency designated as such by the appropriate legal authority of a State or Municipality'of the United Sates or a Province of Canada or an insurance company authorized to write boiler and pressure vessel insurance in that jurisdiction.

Authorized Nuclear Inservice Inspector (ANII) -

An authorized-Nuclear Inservice Inspector is ' an employee of an- Authorized Inspection Agency who meets the requirements of-ANSI N626.1-1982 t

' and the requirements of ANSI N626.0-1982 for Authorized Nuclear Inspector (ANI).

1- Certification - The act of determining, verifying and . attesting in writing to the qualifications of personnel, processes,-proco-dures or items in accordance with specified requirements.

' Certificate of Compliance - A written statement signed by . a qualified party. attesting that the ' items or- services are in accordance with specified requirements and accompanied by_ 'addi-tional information to substantiate the statement.

Certi fica te of Conformance -

A written statement _ signed by a i

qualified party certifying that items or services ' comply with specific requirements'.

I. Certified Test Rooort.- A written and signed = document approved by.

a qualifled . party _ that . contains aufficient data and information to verify the actual properties of items and the actual ~results

i. of all required tests, i

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ILLINOIS POWER NUCLEAR PROGRAM

. QUALITY ASSURANCE MANUAL 'cLoSSARY.OF TERMS Characteristic - Any property or attribute of__an item, process or-service that is distinct,_ describable-and measurable, as conform-ing or nonconforming to specified quality requirements. Quality-. ,

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

Chemical Cleaninci- - Refers to the use of acids and - caustic substances applied to material or product forms during manufac- ,

ture, maintenance or repair.

Codqa - Collective term used to describe all the published-codes-applicable to Clinton Power Station operations, such' as, the American Socloty Hechanical Engineers (ASME) Boiler and Pressure Vessel Code. .i 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. ,

Conditjon Adverse to Ouality -

An all inclusive' term used in reference to any of the following: failures, malfunctions, 3 deficiencies, deviations, defective items and nonconformances, 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 raquired ' 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 -

recurrences,.or both.

CPS - Abbreviation for Clinton Power Station.

. Departmental Procedures -or Instrug_tions - Procedures or~ instruc-tions - approved and issued within - a department which provide detailed-direction to' personnel'.

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL GLossAny oF TERMS poviation -

A nonconformance or departure of a characteristic from specified requirements.

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.

Documentatio.D - Any written or pictorial information describing, defining, specifying, reporting or certifying activities, re-quirements, procedures or results.

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

Extended ouality Assurance Ptocram -

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-un -

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

}Lol d Point - Point in a procedure or work document at which the performer is required to stop and notify the Quality Verification section (QV) of the Quality Assurance department to allow for planned inspections. The work activity shall not proceed without the point being signed by QV, QV being present and authorizing the activity to proceed, or the point waived / reclassified.

Indonendent 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.

PAGE v-3 of 10 REVISION: 23 DATE: 12/28/92

itLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL GLOSSARY OF TERMS

. Inservice Inspection -

A mandatory 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.

Inspection - A phase of quality control which by means of exami-nation, observation or measurement determines the conformance of materials, supplies, components, parts,. appurtenances, systems, processes or structures to predetermined quality requirements.

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 organiza-tion.

Internal Auditfi -

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 structure, system, 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 correc-tive action.

Hggsuring and Test Equinment - 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 planned change in plant design or operation and accomplished in accordance with the requirements and limitations of ' applicable codes, standards, specifications, licenses and predetermined safety restrictions.

Doncompliance -

A failure to comply with a regulatory require-ment.

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DATE: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL oLOSSARY OF TERMS Nonconformance _- A deficiency in characteristics, documentation or procedure which renders the qu4 .ty of an item unacceptable or indeterminate. Examples of nonconformances includes physical defects; test failures; 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.

Objective 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.

Operabic - 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.

Permanent 1v Installed Instrument and Control Devices - The installed plant equipment including computer points used in determining acceptanco criteria of Technical Specification surveillances (Category A Instruments).

Plant Staf f - That organization which is directly responsible for the operation of the Clinton Power Station. The Plant Staff includes operations, technical, maintenance, radiation protec-tion, and support departments.

Proceduro - A document that specifies or describes how an activi-ty is to be performed. It may include methods to be employed, equipment or materials to be used and sequence of operations.

Procurement Documents - Contractually binding documents that identify and define 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 or proposals and their acceptance which authorizes the seller to perform services or supply equipment, materials or facilities on behalf of the purchaser.

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l ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL cLossARY oF TERMS Qu.alification . (Personnel) -

The characteristics or abilities gained through training or experience or both that enable an individual to perform a required function.

Quality Assurance -

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

Quality 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.

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

Quality Related - Activities which either do or could influence 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, storing, cleaning, preserving, erecting, installing, inspecting, testing, operating, maintaining, repairing, refueling or modify-ing.

Receipt Inspection - An inspection performed by Quality Assurance Inspectors verifying that the items are in satisfactory condi-tion, 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 the Clinton Power Station operation, such as the Code of Federal Regulations.

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.

Resolution - 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 controls or limitations that are to apply until the nonconformance is fully corrected.

PAGE v-6 of 10 REVISION: 23 DATE: 12/28/92

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QUALITY ASSURANCE MANUAL GLOSSARY OF TERMS

ReworP - Th e process by.which a nonconforming item _is_made to-3 conform to prior specified requirements by-completion, remachin-ing,-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 normal operational transients or accidents. In addition, design requirements are placed upon such equipment to assure the proper performance of safety actions, when . required.-- . Safety ' related

. items are those designated Seismic Oategory 1, Safety-. Class 1, 2, 3, "Other" and Electrical Class 1E as identified in = the .. USAR Section 3.2.

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

Seismic Classification - Plant structures, systems andicomponents 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 e

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 theirEfounda-tions and supports, which are designed to- remain -functional in-the - event of an SSE are designated as ' Seismic Category I' as indicated in Table 3.2-1 of-the CPS USAR.

Sionificant Condition Adverse ~to Ouality and/or-' Safety -At-condition that affects or- is likely to have = an ef fect 1 on, or influence, the safe operation of-the plant, the capability _to-shut down the reactor and maintain-it in a safe. shutdown-condi-tion or the-capability to-prevent or mitigate the consequences off accidents which could result in potential off-site exposures, source Inspection ~ - An inspection . performed : at : the : location . of -

itom procurement, - supply- or manufacture .for the purpose- of verifying that the item meets specified requirements.

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- QUALITY. ASSURANCE MANUAL GLOSSARY-OF TERMS ;

Special 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 efforts 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 Atom of known value used for comparison. -

Ston Work - Collective term used.to describe the following three (3) levels of stopping work activities:

a. The stopping of a single or specific work activity by Quality Assurance personnel, 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 Assurance.

Supplier - Any individual or organization that furnishes items or services to IP under a procurcment dccument.

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. ,

survey - A documented evaluation of an--organization's-ability-to perform activities as verified by a-determination of the adequacy.

of the organization's quality program and1 by a . review of the implementation of.that program at the location of work.-

System - Safety Classifications - Structures, systems and compo-l nents are _ classified as Safety Class-1, Safety Class 2, Safetyf Class 3, Safety Class Other _ or Class 1E in accordance :with the importance to --Nuclear _ Safety. Equipment -- is assigned a specific- -

safety class, recognizing that' components within a-system may be of ' differing safety- importance. . Definitions -of the various-Safety. Classes are:

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-ILLINOIS POWER NUCLEAR PROGRAM-QUALITY ASSURANCE MANUAL GLOSSARY _OF TERMS- ,

Safety Clasa_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, systems - 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 from the reactor and reactor Core, or

g. Storing _ spent fuel.

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 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..

Safety 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 maf be connected to or influenced by.the equipment within the Safety Classes 1, 2 or 3.

Class 1E . The safety' classification of the electric equip-ment 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 class'ifications

-and related Quality Assurance Program requirementsfclassif1-cations are summarized in Table 3.2-1 of the USAR.)

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" ILLINOIS POWER' NUCLEAR PROGRAM LQUALITY ASSURANCE MANUAL- GLOSSARYLOF TERMS __

Technical -- Specifications - 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 operations. !

Traceability - The ability to identify the origins of-a'particu-!

lar item when required by adopted codes or standards.

USAR - Abbreviation for the Updated Safety Analysis Report, which is the document submitted by IP.to the Nuclear Regulatory Commis-L .

sion-in accordance with 10CFR50.71.

Use-As-Is - A disposition which may be imposed for a nonconfor-mance when it can be established.that the discrepancy will result; in no adverso 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.

Verification /Insnection Point -

A-point in a procedure or: work document at which the performer is required to notify Quality Verification (QV) in order to plan when -- they will perform the-verification activity. A Verification / Inspection Point shall be-capable of being verified after. work completion.

Witness Point; - Point in a procedure or work document at which '

-the performer' is- ~ required .to stop'and notify .QV 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.

PAGE V-10 of 10 REVISION: 23 DATE: _12/.,8/92

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 1

ORGANIZATION 1

m i APPROVED BY: MANAGER-QUALITY ASSURANCE 12/28/92

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1.1 PURPOSE / SCOPE

To define the requirements for and to describe the establishment-ofl an organizational structure, functional responsibilities and levels of authority concerning the performance of activities which affect the safety-related functions of structures, systems, or components for the Clinton Power Station.

1.2 DESCRIPTION

1.2.1 General Organizational structuring and functional 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.

The authorities and responsibilities of persons ; and organizations performing. quality-related-activities are established, assigned and documented.- Those persons 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 utilization of nonconforming-items until-proper dispositioning has occurred.

Corporate Nuclear Policy Statements are formalized in Corporate-Nuclear Procedures (CNP) as described.in this manual. Each CNP-is reviewed =and concurred with by the Manager - QualityJAssurance for-QA- program requirements. -The CNPs are approved - forLuse by'the IP corporate officer (s) responsible for the activities covered by - the CNP. Corporate' Nuclear Procedures require the development and use of departmental procedures or instructions - to describe interfaces 4

and accomplish the activities covered by the CNP.

The organizational structure and functional responsibility assignments are-such that: (1) attainment of quality objectives PAGE 1 of 13 REVISION: 23

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'lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 1 is by individuals assigned responsibility for specifying quality or p9riorming work to specifications; (2) verification of conformance to entablished quality requirements in by those who do not have direct responsibility for specifying, producing, or expediting producto; and (3) personnel in key quality accurance functions have direct access to responsible management.

Specific Quality Assurance activities (j ob dutica and renponsibilities) have been identified for each section within the QA department and are based on the amount and type of activition conducted. Staffing levels are established so that the work can be accompliched in a manner supportive of plant operations and outagec. Further, once a year the QA department manning levels are reaccessed and personnel levels are revised as necessary to assure adequate and timely coverage of QA activitico. This review permits recruiting and training activities to be carried out in such a manner as to provide trained Quality Assurance personnel necessary to aucure the quality of the work. Quality Anaurance personnel are free from non-QA dutica and provide full attention to assuring the effective implementation of the QA program. Effectiveness of the program is accured by Quality Annurance department participation in the work planning, through surveillance and audits, by the authority of Quality Assurance personnel to stop specific work activition where it appears that quality may be jeopardized, and the authority of the Manager - Quality Assurance to initiate a Stop Work Action. The Vice President and Manager -

Clinton power Station has the authority to bypass a atop work to place the plant in a safe and stable condition.

Inspectors are provided with approved inspection procedures and instructions prior to performing inspection operations. (During plant operations emergencien, inspections may be performed without written procedures.) To further assure that inspections are done in a timely manner, the QA organization identifies specific inspection points in the work documents and makes provisions for notification of verification / inspection witness, and hold points.

In addition, dtoignated QA personnel regularly attend and participate in planning, scheduling and status meetings during testing, operations and outages to assure (1) they are kapt abreast of day-to-day projected work assignments throughout the plant and (2) that the necessary QA inspection controls, acceptance criteria, procedural controla and qualified QA staffing is available to properly carry out the assigned tachs.

1.2.2 9D1mligltt ion aILd Reqpomlhilitien This cection describes the organizational structure and individual responsibilities within IP for managing and implementing the QA program for the operation of the CPS. Figure 1-1 shows the PAGE 2 of 13 REVISION: 23 DATE: 12/28/92_.

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llLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chaptor 1 organizational structure and relationships of individuals and departments within IP with management responsibility for performing quality-related activities.

1.2.2.1 Chairman, President and Chief Executive Officer The Chairman, President and Chief Executive officer of IP han the overall responsibility for the engineering, design, procuromont, modification, testing, operation and quality assuranco at CPS.

Execution of those responsibilition is dologated to a Vice President.

1.2.2.2 Senior Vice President The Senior Vico President is responsible for the overall of fectivonoss of the Quality Assurance Program and is responsible for establishing tho quality assuranco policios, goals and objectivos, as well as testing, maintenanco, operations, nuclear support, and engineering. The Senior Vice President is also responsible for assuring that annual management reviews are conducted and documented on the status, adGquacy and offectivences of the overall QA program. The Senior Vice President is responsible for assuring that the authority and indopondence of Quality Assuranco personnel are such that they can offectively assure the conformance to quality requirements and are independent of unduo influences and responsibilition for schedulo and costa.

1.2.2.3 Vice President and Manager - Clinton Power Station The Vice President and Manager - Clinton Power Station reports to the Senior Vice President and is responsible for the safe, reliable and of ficient operation of the Clinton Power Station in accordance with the operating license. This includes onsuring that the IP Nuclear Quality Assuranco Program, as described in subsequent sections of this manual, is incorporated in plant procedures and implomonted by the Clinton Power Station organization.

1.2.2.4 Manager - Nucloar Station Engincoring The Manager -

Nuclear Station Engineering reports to the Senior Vice President and is responsible for the development, direction and overall coordination of power plant engincoring activities performed by the Nuclear Station Engincoring Department (NSED) for the Clinton Power Station. Those responsibilities include: the preparation of specifications and drawings for the accomplishment of now designs, design changes and modifications; design interpretation; the conduct of design checks and reviews; technical evaluation of suppliers; ensure compliance with the ASME Codo and other codes and standards; control of examination and inspection of PAGE 3 of 13 REVISION: 23 DATE: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 1 ASMC componontal and coordinato all interface with the Authorized Inspection Agency (AIA), including provisions for the establishment of ANI hold / witness points and accous to facilities and records.

The Manager - NSED onsures that those activities are performed in accordance with the requirements of the IP Nuclear Quality Assuranco Program.

1.2.2.5 Manager - Nuclear Planning and Support The Managar - Nuclear Planning and Support reports to the Senior Vice President and is responsible for providing direction of nuclear plant services organizations for planning, resource management, executivo plans, fitness for duty, medical services, material support services, receiving and warehousing, records management, document control, industrial safety, Nuclear Program staffing, compliance to federal regulation of personnel activities, and for corporato and plant intograted in those functional support disciplinos. The Manager - Nuclear Planning and Support is responsible for controlling the Nuclear Program procedures governing the procuromont activitics. The Manager - Nuclear Planning and Support ensures that those activities are performed in accordance with the requirements of the IP Nuclear Quality Assuranco Program.

1.2.2.6 Nuclear Roview and Audit Group The Nuclear Review and Audit Group (NRAG) reports to the Senior Vico President and is responsible for the indopondent safety review function. The NRAG functions in accordance with a written charter which delinoates committoo composition, responsibility and authority, subjects to be reviewed, reporting requirements and administrativo controla under which the group operates.

1.2.2.7 Facility Review Group An on-sito committoo whose function is to advise the Vice President and Manager - Clinton Power Station on matters related to nuclear safoty.

1.2.2.8 Manager - Nuclear Training The Manager - Nuclear Training reports to the Vice President and Manager -

Clinton Power Station and is responsible for the direction and management of the Nuclear Training for Clinton Power

, Station. Duties include developing training standards, providing contralized training, providing education support to Nuclear Managers / Directors and maintaining operation of the simulator. The Manager -

Nuclear Training onsures that those activities are PAGE 4 of 13 REVISION: _2)_.

DATE: 12/28/92 i

II.LINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 1 performed in accordance with the requirements of the IP 11uclear Quality Assuranco Program.

1.2.2.9 Manager - Quality Assurance The Manager -

Quality Assurance reports to the Senior Vice President and is responsible for IP's overall Quality Assuranco Program definition, direction, ovaluation and approval, including the IP lluclear Quality Assurance Program. The Manager -

Quality As.,uranco directs the Quality Assuranco departmental activition related to the design, procuromont, maintenanco, modification, and operation of the Clinton Power Station. The Manager -

Quality Assuranco interfaces with the 14uclear Regulatory Commission, and the Authorized Inspection Agency for the Quality Assuranco Program.

The Manager - Quality Assurance or the designated altornato 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 and health and safoty of the public, or impact on capability to safely operato or shut down the plant are not adversely affected.

The qualifications of the Manager - Quality Assurance are at least equivalent to the education and experienco requirements of Section 4.4.5 of AllSI/ Alls 3.1-1978, "Soloction and Training of Nuclear Power plant Personnol". Specifically, the Manager -

Quality Assurance will meet at least one of the following:

1. At the time of initial coro loading, or assignment to the activo position, the responsible person shall have six years experience in the field of quality assurance, proforably at an operating nuclear power plant, or operations supervisory experience. At least ono year of this six years experience shall be nuclear power plant experience in the overall implementation of the Quality Assuranco Program. (This experience shall be obtained within the quality assurance organization.) A minimum of one year of this six years experienco shall be related technical or academic training. A maximum of four years of this six years experience may be fulfilled by related technical or academic trainingi or,

2. EDUCATION: Bachelor Degroo in Engineering or related science.

I EXPERII'14CE: At the timo of initial core loading or appointment to the activo position, the responsiblo person shall have four (4) years experience in the. field -

of quality assurance, or equivalent number of years of nuclear plant experience in a supervisory position, PAGE 5 o f -

1_)__ REVISION: 23 DATE: 12/28/92 I

,y_ _ - ,..r -

i

!LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chaptor 1 proforably at an operating nuclear plant, or a combination of the two. At least one (1) year of this four years experience shall be nuclear power plant experience in the implementation of the Quality Assuranco Program. Six (6) months of the one year experience shall be obtained within the quality assurance organization.

11 0 must possess a thorough working knowledge of 10CFR50 Appendix B, ANSI N45.2, AllSI N18.7, familiarity with the ASME Boiler and Prosauro Vossol Codo and other applicablo regulations, codes and standards.

1.2.2.9.1 Director - Quality Assurance The Director - Quality Assuranco reports to tho Manager - Quality Assurance and is responsible for providing direction and administration of the Quality System and Audit staffs in defining, establishing, and verifying compliance with the IP Nuclear Quality Assuranco Program. In addition, the Audit staff is responsible for verifying the qualification of suppliers and as uring procuromont documentation is acceptable.

1.2.2.10 Manager - Licensing and Safety The Hanager -

Licensing and Safety reports to the Senior Vice President and is directly responsible for providing representation and interface with regulatory agencies to maintain oporating 1iconses and permits for CPS, management of the USAR, and the Environmental Report (ER), including amendment submittals, management of the resolution of licensing issues, conduct of licensing reviews and studies, perform safety studios and analyses, conduct of Independent Safety Evaluation Group (ISEG) efforts for significant operating data, provide representation to safety groups, management of the Emergency Preparedness Program, and the administration of tracking program for 10CFR21 items. The Manager Licensing and Safety ensures that these activities are performed in accordance with the requirements of the IP Nuclear Quality Assuranco Program.

1.2.2.11 Manager - Purchasing and Material Control The Manager - Purchasing and Material control reports to the Vice President (Headquarters) and is responsible for assuring that suppliers are selected from the Qualified Supplier List as required, preparing, and issuing purchase orders and ensuring that they include necessary technical, quality and commercial terms and conditions, assuring technical reviews, classifications and Quality Assuranco reviews are accomplished prior to release of a purchase ordor. The Manager - Purchasing and Material Control ensures that PAGE 6 of 13 REVISION: 23 DATE: 12/28/92 j l

i l'LLINOIS POWER NUCLEAR PROGRAM i QUALITY ASSURANCE MANUAL chaptor 1 those activities are performed in accordance with the requironents ,

of the IP Nuclear Quality Assuranco Program.

1.2.3 Quality Angurance Denartment The Quality Assurance organization structure -is shown in Figure 1~

2. General responsibilities of the department with regard to the

QA Program for the CPS includo, but are not limited to, the followingt !

a. Preparo and control the IP Nuclear Program Quality i Assuranco Manual.

b. Verify the implementation of the IP Nuclear Quality Assuranco Program. -

c. If significant quality problems are identified, QA personnel have .the authority and responsibility to ,

stop specific work activities pending satisfactory 1 resolution of the identified problem, provided the '

health and safety of the public or . impact on the capability to safely operate or shut down the plant i are not adversely affected~.

j

d. Verify that quality-related training programs are devoloped and implemented for. each company' department that .has responsibility for implementing. '

the IP Nuclear Quality Assuranco Program.

e. Review quality-related procurement requisitions and, as specified, condition reports, . procedures, instructions and other quality-related documents.

f. Maintain awareness of QA requirements, practicos and experiences throughout the nuclear power industry.

g. Develop and implement an audit, survoillanco and j inspection program for_ quality-related . activities within the scopo of-the IP Nuclear Quality Assurance Program and routinely advise management of' the !

status of program implementation. Initiato and/or verify corrective action, as necessary, to . reso.lve ,

conditions adverse to quality. _

~

h. Perform acceptance inspections related to' activities' <

during operation and maintenance of CPS.

1. Review the QA programs of suppliers - for compliance with regulatory requirements and the requirements of PAGE 7 of 13 REVISION: 23 DATE: 12/28/92 i 3

- _ _ . . . . _ .. _ ....,,-a - . - - - , - , _ _ . . .

L I ILLINOIS POWER NUCLEAR' PROGRAM -

l QUALITY ASSURANCE MANUAL chaptor i i

the Ip Huclear Quality Assurance Program when a i program 'is required to be submitted by the '

procurement document. Ensure that supplier QA >

program deficiencies are corrected. i

-) . Roview all changes to the USAR, with the exception l of Chapter 16, Technical Specifications. o

k. perform trend analysis for detecting fronds adverso to quality. ,

1. Extend portions of,the IP Huclear Quality Assurance I Program to solocted equipment' important to rollable r station oporation but not included in the compliance based Quality Assurance Program as directed by QA management.

1.2.3.1 Quality Engineering and Verification Section '

The Quality Engincoring and Vorification Section is supervised by the Supervisor - Quality Engincoring and Verification who reports ;

to the Manager - Quality Assuranco. The Quality Engineering - and_ i Verification Section assures selected documents, including on-site supplier documents, involving the following activities conform to applicablo QA program requirements of regulations, standards, the ;

codes and other specific commitments: Operations, Maintenanco, !

Plant Support, Technical, Chemistry, Radioactive Wasto, _ Radiation Protection, Firo Protection, equipment included in the axtended ;

Quality Assurance Program, Security, Modifications,- Testing, Engineering ' activities, and USAR changes. This section performs !

quality verification planning for ' those activities, as ! ' applicable. - 1 This section ensures timely and responsivo correctivo actions ;to_ a audit findings initiated during internal audits.

The ' Quality. Engineering _and Verification Section ~is _ also- [

responsible for scheduling, conducting and reporting the applicable-- -

inspection, verification, and- nondestructivo .oxamination- of quality-related items, processos, functions- and activities associated = with operations,- testing, maintenance, : modification, nuclear fuel, _ and plant support ' activities performod by: IP - which affect quality. The ; Quality -Engineering and' Verification Section -

is_also responsible for ' initiating _ reports of nonconforming items' or conditions discovered during verification activities.

If significant . quality problems are identified that- w arrant immediato action,-_ Quality Engincoring and- Vorification Section-personnol- havo~ tho _ authority and _ responsibility- to_ stop the specific; work activity pending satisfactory resolution =:of the -

identified problem, provided tho health and safety ofltho public or PAGE 8 of 13 REVISION: 23 DATE:- '12/28/92

ILLINOIS POWER NUCLEAR PROGRAM

! QUALITY ASSURANCE MANUAL Chapter 1 irapact on the capability to safely operate or shut down the plant are not adversely affected.

1.2.3.3 Quality Systems Section The Quality Systems Section is supervised by the_ Supervisor -

Quality Systems wh> reports to the Director -

Quality Assurance.

The Quality Systems section is responsible for periodically assessing departmental effectiveness in implementing the IP lluclear Quality Assurance Program, trending of conditions adverse to quality, coordination of Quality Assurance reviews and approvals of QA program requirements associated with the IP lluclear Program Quality Assurance Manual and Corporate lluclear Procedures, and advising management on matters related to establishment of quality programs and procedures for Clinton Power Station. The section is also responsible for the coordination and administration of QA training programs for department personnel and development and control of documents associated with the IP lluclear Quality Assurance Program, such as the IP lluclear Program Quality Assurance Manual and QA departmental procedures. The Quality Systems Section coordinates QA reviews and approvals of QA program requirements associated with the procedures of other lluclea r departments supporting Clinton Power Station, including, but not limited to:

fluclear Training Department, fluclear Planning & Support Department and Licensing & Safety Department.

If significant quality problems are identified that warrant immediate action, Quality Systems section personnel have the authority and responsibility to stop the specific work activity pending satisf actory resolution of the identified problem, provided the health and safety of the public or impact on the capability to safely operate or shut down the plant are not adversely affected.

1.2.3.4 Audit Section The Audit Section is supervised by the Supervisor -

Audits, who reports to the Director - Qualit'/ Assurance. The Audit Section is responsible for the planning and performance of internal and external IP audits. *fhe Audit section assures that procurement documents contain the QA requirements of the USAR, evaluates suppliers' QA programs for mooting the USAR commitments, porforms audits and surveys at suppliors' facilities, processes procurement related nonconformances, performs source surveillances and performs receipt inspections. The section advises management as to the effectiveness of Quality Assurance Program implementation for those specific functions audited. The section also ensures timely and responsive corrective action to audit findings initiated during external audits.

PAGE p_ _of 33 REVISION: 23 DATE: _1.2/28/97 .

'lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chaptor i If significant quality problems are identified that warrant immediato action, Quality Audits Section personnel have the authority and responsibility to stop the specific work activity pending satisfactory resolution of tne identified problem, provided the health and safoty of the public or linpact on the capability to safely operato or shut down the plant are not adversely affected.

1.2.3.5 Program Monitoring Section The Program Monitoring Section is supervised by the Supervisor -

Program Monitoring, who reports to the Director -

Quality Assuranco. The Supervisor - Program Monitoring is responsible for providing management and irnplomontation of the Operations Monitoring Program that supports the safe and rollable operation of Clinton Power Station. The Program Honitoring Section is responsible for the planning, coordination and performanco of Quality Assurance surveillancos. The section is responsible for advising management as to the offectiveness of Quality Assuranco Progrart irnplomontation for those specific functions surveilled.

If significant quality problems are identified that warrant immediato action, the Program Honitoring personnel have the authority and responsibility to stop the specific work activity pending satisfactory resolution of the identified problem, provided the health and safety of the public or impact on the capability to safety operato or shut down the plant are not adversely affected.

1.2.4 Organizational Interfacen Activitios affecting the quality of safety-related systems, structures and components are performed by, or under the cognizance of various IP organizations. Other sections of QA may perform some of the functions of another QA section provided that personnel are adequately trained, qualified /cortified, and those work activities aro performed to the samo (or similar) procedures and instructions.

Problems associated with mooting the requirements of the Quality Assuranco Program, or disagrooments and/or disputes'botween members of the:.o organizations shall be brought to the attention of appropriato lovcis of management, including the chairman and CEO as necessary to obtain resolution.

Work may bo dologated to qualified cutside organizations by contract for such activities as design, special processes, inspections,. etc. Selected work may be dologated to qualified outside organizations by Nuclear Program departments. The -

responsibility for exorcising engineering control rests with Nuclear Station Engincoring, operational controls with CPS Plant Staf f and quality assurance with the Quality Assurance department.

Prior to initiation of work, the qualified individual (s) or PAGE 10 of 13 REVISION: 23 DATE: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM

-QUALITY ASSURANCE MANUAL chaptor 1__ ,

organizational oloments within IP - have their responsibilition identified for the control and quality of dologated work.

-1.2.5 lhtclear Program Orcanization i

FIGURE 1-1 111ustratos lluclear Program organizations having QA program responsibilition and'intorfaces.

. i FIGURE 1-2 Illustrates the Quality Assurance organizational ;

chart.

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l PAGE 11 of 13 REVISIO!O 23 DATE:. 12/28/92 l.

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k ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL >

CHAPTER i 2 :

QUALITY ASSURANCE PROGRAM APPROVED BYt MANAGER-QUALITY ASSURANCE b 5 12/28/92

{

2.1 PURPOSE / SCOPE The IP Nuclear Quality 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 "H" in the Quality Annurance Requirements column in USAR Table 3.2-1. This table of<

systems, structures, and componenta is kept current and is revised

and distributed as a controlled document in accordance with approved procedures. Appendix "B" to. the IP - Nuclear Program Quality Assurance Manual describes and specifies a graded application of the IP Nuclear Quality _ Assurance Program to certain other activities, systems and items at the Clinton Power Station, such as the pressure boundaries of radwaste augmented D systems, portions of the fire protection system, security system, environmental monitoring, and package and transportation of radioactive material.

2.2 DESCRIPTION

2.2.1 General Illinois Power Company's Nuclear Quality Assurance Program is based -

upon 10CFR50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing _ Plants. " The requirements _of -

10CFR71, subpart H, " Quality Assurance :for Packaging. and Transportation of Radioactive- Material" :are also included.

Additionally, in USAR section 1.8,1 Illinois Power is committed to carrying out the provisions of various NRC regulatory guides- and industry standards which further define - Quality Assurance program

-requirements. As =used in this--chapter, --" Quality- Assurance" comprises-- all- those planned and -- systematic _-actions necessary . . to provide adequate-confidence that-aLClinton Power Station structure, system, or component will perform satisfactorily .in- service.

Quality Assurance includes quality- control which - comprises . those physical characteristics of a - material, structure, component, or-system'.which provide a means to control the -quality of- the PAGE 1 of 6 -REVISION: 2]_

DATE: 12/28/92-

i l

l ILLINOIS POWER NUCLEAR PROGRAM

QUALITY ASSURANCE MANUAL Chapter 2 i

material, structure, component, or system to prodotermined requirements.

2.2.2 Qtlality__. A s a u rn ng e_Er_qgraarLDpp l e m e nt a t i o n The IP lluclear Quality Assurance Program was implemented as systems, structures, and components were turned over or transferred to IP. A Preoperational Test Program was established and implemented to assure that necessary inspection and testing of the transferred system, structure, or component was performed and properly evaluated, and to confirm that the system, structure or component will perform satisfactorily. The program coverage was ~-

gradually expanded until all applicable systems, structures, and components for the unit were turned over and were encompassed within the scope of the IP Nuclear Quality Assurance Program. The program has been fully implemented and will be maintained throughout the operating life of the plant.

The program rocciveu ongoing reviews and is revised in accordance with Appendix A as necessary to assure its continued effectiveness.

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 controls previously established over activities affecting quality of CPS structures, systems, or components shall be submitted and approved by the NRC prior to change implementation. Quality Assurance Manual changes which do not reduce the Quality Assurance program's commitments shall be submitted to the NRC for review on an annual basis. Editorial changes or personnel reassignments of a non-substantive nature do not require NRC notification. Submittal to the NRC of a change to the IP Nuclear Program Quality Assurance Manual shall be in accordance with 10CFR50.54 (a) . The change submittal shall include all pages affected by that change and must be accompanied by a forwarding letter identifying the changes, the reason for the change, and the basis for concluding that the revised program incorporating the change continues to satisfy the criteria of 10CFR50 Appendix B and the Safety Analysis Report quality assurance program description commitments previously accepted by the NRC.

2.2.3 Qu_nlity_ Assurance Prociram Documentation The IP Nuclear Quality Assurance Program is established and supperted by three tiers of documents; each successive tier transmits requirements from a higher lOvel of authority to the next successive lower document level.

PAGE 2 of 6 REVISION: 23 DATE: 12/28/9L

ILLINOIS POWER NUCLEAR PROGRAM

' QUALITY- ASSURANCE MANUAL Chapter 2

a. Nuclear Policy StatemerttJ2 are documents issued by Corporate Management to promulgato authoritative management directivos establishing and defining Quality Assurance policios within the-Illinois Power company Nuclear Program.

b.1 IP Nucicar Pro _qram Ouality Assuranco Mamtal describes -

the objectivos, requirements, interface relationships, and assignment of responsibilities for accomplishing activities which affect the safety-related -functions of systems, structures, or components. It contains the minimum requirements to be- applied by IP and.

suppliers. The manual is approved and maintained current by the Manager - Quality Assurance. Managers ,

and Directors of organizations performing activities- !

within the scopo of the program designate their -

acknowledgement of responsibilities and authorization for use within their organization by signaturo _ prior to approval of the manual by the Manager - Quality Assurance. .

b.2 Rognorate Nuclear Proceduros_ (CNP) are documents developed, approved, and- issued to provido corporate direction and policy portaining to appropriate Nuclear.

t Program Activities. CNPs are reviewed _by the Manager t Quality Assuranco for complianco with : quality- ,

assurance requirements and ~ are approved by corporato ;

level management.

b.3 CPS Records Manacoment- Standards provido_ direction in_ I the areas of- records identification, preparation,L collection / review, turnover /transfor, storago, prosorvation,.and maintenance. u b.4 Insoryico Inspection (ISI) ~ Proaram Manual describes the ISI requirements for CPS and serves- as the e sito standard for.all CPS ISI Program activities.

c. Departmental Proceduros or Instructions are developed, approved, and issued for cach organization _ to1 further implomont the requirements _ of-- Corporate Nuclear Proceduros _and- the IP Nuclear Program- _ Quality.'

Assuranco Manual. These; departmental-procedures:or-instructions provide more detailed . direction to: I P-personnel engaged _ in _ Nuclear-- Program- related #

activities. Tablo 2-1 identifies ' those LIP Nuclear Program- Quality.- Assurance manual- chapte'rs that: .are-applicable to _ the Departments within ' their _ scope of- nL responsibility.

J PAGE- 3 of 6 REVISION: 23 DATE: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chaptor 2 2.2.4 Training Each Manager or Director 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 purposo, scope, and implementation of governing documentst and that they maintain required proficiency. Programs are formulated to provide training based on individual employco experience and position and fulfill regulatory requirements, where applicable.

Training records are maintained for each employeo. Departmental training procedures / instructions require that indoctrination and training programs include objectives, content of program, attendees, and date of attendance. Applicable departmental proceduros 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.

2.2.5 1P_Litiglear Ouality Apsurance Procram Evaluationg Regular management reviews of the IP Nuclear QA Program to assess the scopo, status, adequacy, compliance, and overall effectivonoso are performed under the direction of the Senior Vico president.

This review function consists of meetings with key.QA personnel, as well as review of QA department audit and status reports, and the performance of a IP Nuclear QA 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 by IP Quality Assurance. Independent audits of other organizations performing activities related to quality are accomplished regularly under the direction of the Manager - Quality Assurance.

Suppliers' Quality Assurance programs are reviewed, approved, and audited by the IP Quality Assuranco organization for compliance with applicable rules, regulations, and IP Nuclear Program Quality Assurance Manual as not forth in the contract document. Approval of such programs in activities related to CPS is documented.

2.3 HESPONSIBILITIES 2.3.1 figDior Vice Erosident

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

PAGE 4 of 6 REVISION: 23 DATE: 12/28/92

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

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 2 2.3.2 thlglear PragIAID Deftartmenta

a. Implomont and comply with the IP Nuclonr Quality Assuranco Program.

b. Train and qualify /cortify, as requirod, personnel who perform quality activities associated with CPS.

2.3.3. CPS Plant Staff

a. Operato and maintain CPS in a safo, rollable, and officient modo of operation.

2.3.4 intclear Stnt;j_gn_ Engineering

a. Establish and maintain a sito document for implomonting the ASME Section XI Inservico Inspection Program.

2.3.5 puolear Training

a. Establish, maintain and implomont a licensed oporator training program and a General Employeo Training program.

2.3.6 Qatalj_ty_]ippu rancg

a. Develop, approvo, and maintain the IP Nuclear Program Quality Assuranco Manual,

b. Review, approve, and audit suppliorc' quality accuranco programs for compliance with applicable rules, regulations, and this manual as set forth in the contract document,

c. Review all changes to the USAR, with the exception of Chapter 16, Technical Specifications.

, d. INaluate the IP Nuclear Program Quality Assurance l Manual changes for commitment reduction.

o. Submit IP Nuclear Program Quality Assuranco Manual changos to the NRC as defined in Paragraph 2.2.2 of this chapter and in accordanco with 10CFR50.54.

PAGE 5 of 6 REVISION: _]3 i

DATE: 12/28/92

ILLINOlG POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 2 TABLE 2-1 TABLE 2-1 This tabic identifion the IP Nuc1 car Program Quality Assurance Manual chaptors that are applicable to the IP Departments. Those organizations are responsib10 for developing and maintaining procedurou/inntructions to the extent and detail within the scopo of their responsibilition. The Quality Anourance Department shall review I colected departmental procedures / instructions that implement the QA I Program.

Nuclear Program Departnents IP Nuclear Program QA Marual Chapters 1 2 3 4 $ 0 7 8 9 10 11 12 13 14 i$ 16 17 18 CP$ Plant Staff X X X X X X X X X X X X X X X X X X buclear $tation [ngineering X X X X X X X X X X X X X X X X

)

Nuclear Planning & St44mrt X X X X X X X X X X X X X Nuclear training X X X X X k X X X X X licensing & Safety X X X X X X X X X X X X 1

Quality Assurarce X X X X X X X X X X X X X X X X X X Nuclear Review & Au1(t X X X X Purchasing & Material Control X X X X X X X X X X X l

l l

PAGE 6 of 6 REVISION: 21 DATE:

= - - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _

l

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lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL ,

CHAPTER 3 ;

DESIGN CONTROL i

APPROVED BY MANAGER-QUALITY ASSURANCE 12/28/92 3.1 PURPOSE / SCOPE l To establish the requirements, responsibi'ities and control measures for assuring that design bases and regulatory requirements are correctly translated into design documents. Tho scope - of design control covers all phases of enginacring design, including conceptual design selections; identification of design- inputs ;

(critoria and basos); identification and control of design l production of design documents, and interfacost calculations analysos; procuromont-rolated engincorings design verification; and installation engineering support.

3.2 DEERIPIIDH Design control measures are established to assure modifications and design changes moot -the appropriato performance and quality

-roquirements. These design control measures are commensurate with those applicable to the original design and assure that-modifications are designed and implomonted in accordance with applicable codos, standards and regulatory commitments, n The Nuclear Station Engineering Department has overall_ respon-t sibility for design control activities at Clinton power Station.

l- Thoso design control activities are managed within the context of the- Nuclear Program Configuration Management Program, which also includes provisions for controlling hardware and sof tware items (proceduros, training, etc.) which comprise the configuration of Clinton Power Station and final design approval of changes or-modifications for incorporation into -the plant. _ Processing of ~ a modification,. and the associated design / design chango documents under this program onsures appropriate participation and awareness *

-by CPS organizations throughout the design development and instal'-

-lation proCoss.

i Provisions of this program also ensure that each modification or

, dosign change rocoivos a thorough - safoty evaluation, . that moots l regulatory commitments or ensures that the basis'for not performing the safety evaluation is documented. .If the change is determined to -constituto "an unroviewed safety question", or to alter PAGE 1 of 5 REVISION: _23 S DATE: 12/28/92 l

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I ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter a commitments contained in approved Safety Analysis Reports or the CPS Technical Specifications, it shall be ovaluated by established safety review committoos and submitted for regulatory approval prior to implementation.

Now design or design changes shall be defined by drawings, specifications, chango noticos or other documents as proscribed in design control proceduros. The organization actually performing the design work, either Nuclear Station Engincoring or a qualifiod consultant-engincor is required to includo the following considerations in the design of each modifications

a. Appropriato design bases, regulatory requirements, safety requirements, performance objectivos, design margins, special processes, natorial and testing re-quirements, and operating objectivos 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.

e. Accessibility requirements for operation, testing, maintenanco, in-servico inspection and repair are included in the design.

d. Nocessary installation or modification inspection and tost acceptanco critoria are included in the design documents or modification packages.

c. An ovaluation to datormine if the proposed design change or modification involves an "unroviewed safety ques-tion",

f. Design control measures shall include criticality physics 'and radiction shielding for radioactive material shipments,

g. Design control measures shall include provisions to assure that appropriato quality standards are specified and included in design documents and that deviations from such standards are controlled.

Additionally, the organization which produces and approves _the design / design chango documents shall maintain detailed procedures to control and document performance of the following design activities:

a. Identification and selection of design inputs.

PAGE 2 of 5 REVISION: 73 DATE: -12/28/92

ILLINOIS POWER NUCLEAR PROGRAM !

QUALITY ASSURANCE MANUAL chaptor 3 I l

b. Identification and control of intorfaces betwoon !

organizations required to mako input to, review or approvo final design products.

c. Performance of calculations or analyses ~ which demon-strato that design products satisfy the design inputs,.

including those performed using computer codos, j

d. Production, review, approval, release, distribution and revision of drawings, specifications, data shoots or ,

5.2 DESCRIPTION

Each IP department is responsible for developing, reviewing, approving, issuing and complying with formal instructions, proco-dures, drawings and related material for performing activities affecting the quality or functions ~ of _ applicable systems, structures, or components at CPS. Requirements established are:

a. Instructions, procedures,- or drawings - shall include appropriate qualitative and/or quantitative acceptance critoria 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 1 required function or task.

Each Manager, Director and Supervisor- is_ responsible for de-termining the need for issuing and revising- instructions- and l

procedures .related to each organization's scope ' of activities.

Table 2-1 identifies- those IP --Nuclear Program Quality.- Assurance manual chapters that_ are applicable- to the IP Nuclear Program Departments within their scope of responsibility.

The IP Quality Assurance department conducts periodic surveillances and audits to determine-that appropriate instructions, procedures,.

- or drawings. - exist and - to evaluate their adequacy _ and

' implementation.

PAGE 1 of 2 REVISION: _21__

DATE: -12/28/92 ,

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 5 5.3 BllWQllS T BILITIES 5.3.1 Ilucicar Prp3 ram Departments

a. Develop, approve, issue and einploy those instructions, procedures, or drawings necessary to accortplish 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.

5.3.2 Quality Asimrgngs

a. Conduct periodic surveillances and audits to verify that appropriato instructions, procedures and drawings exist and are being irnplernented in accordance with the requirements of this chapter,

b. Review selected CPS departmental procedures and instructions for QA program requirements.

I PAGE 2 of 2 REVISION: ?)

DATE: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM QUAllTY ASSURANCE MANUAL CHAPTER 6

DOCUMENT CONTROL APPROVED BY: MANAGER-QUALITY ASSURANCE ' 1//4d 12/28/92 I

6.1 PURPOSE / SCOPE To define the requirements ahd reasponsibilities for review, approval, issue and distribution of controlled documents such as instructions, procedures or drawings and changes thereto.

6.2 DESJRIPTION Controlled documents such as specifications, procedures, instruc-tions, drawings, coaputer 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:

a. nocuments, including changes, are reviewed for adequacy by appropriata1y qualified personnel, approved for issue and use by authorized personnel, and distributed to and used where the prescribed activity is performed,

b. The review and a pproval 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.

c. Temporary changes to CPS procedures required by the Technical Specifications which do not change the intent of the approved procedures shall, as a minimum, be approved by two members of the unit management staff who are knowledgeable in the areac _

affected by the procedures. At least one of these individuals shall be the supervisor in charge of the shift and hold a senior operator license. Such changes shall be documented, reviewed and approved in accordance with the CPS PAGE 1 of 4 REVISION: 23 1

DATE: 12/28/92 l

a 1

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ILLINOIS POWER NUCLEAR' PROGRAM l QUALITY ASSURANCE MANUAL Chapter 6 t

b operating License Manual, and if appropriate, incorporated in '

the next revision of the affected procedure.

d. The document control system ensures that. personnel- .or organizations are provided with current and approved documents,

e. Documents and changes thereto are controlled by procedures to.

preclude the use of outdated or inappropriate documents. ,

f. The CPS document control program provid s for periodic reviews of plant procedures to determine if e er les are necessary. or desirable.

g. Individuals or organizations responsible for preparing,-

reviewing, approving and issuing documents and changes thereto are identified,

h. The proper documents to be used in an activity are identified.

i. Current distribution lists are established and used.

Types of documents to be controlled as described above include:-

a. IP Nuclear Procram Ouality Assurance Manual which contains the basic description,. requirements and. assignment of responsibilities for the IP Nuclear Quality Assurance Program'..

The QA manual is developed, approved and maintained .by the-Manager - Quality Assurance,

b. Cornorate Nuclear Procedures ~ Which provide corporate instruction and policies pertaining- to Nuclear Program -.

activities.

c. CPS Onoratina License Manual, contains the _ technical specifications that- are an - integral part of the Clinton Power Station operating _ license,

d. Station onoratina Mantal : which contains procedures for the l l-- operation,: maintenance and testing of the plant - by the CPS

organization. These procedures are subject to a: well-defined

'and ' documented preparation, review, . approval, change control-

.and distribution process,

e. CPS Records Manaaement ' Standards which provide -' direction for records identification, ' review,-

preparation, collection /

turnover / transfer, storage, preservation and maintenance.

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DATE: ~12/28/92

fLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 6 j 1

f. Innervig_e q Insp_ection Prearam Manual which describes the ISI i requirements for CPS and serves as the site standard for all CPS ISI Program activities,

g. Other controlled documents, such as: the Nuclear Policy Statements, USAR, corrective action documents, as-built drawings, procedures and/or instructions used by IP Nuclear Program Departments.

Documents such as parts lists, vendor manuals and written correspondence used in the design, operation, maintenance or testing are controlled in accordance with departmental procedures which include the following:

a. A method of verifying and documenting receipt of transmitted documents,

b. A program for approving the receipted documents for use in activities associated with CPS by that organization.

c. A program for distribution and control.

Measures are established within each organization to assure that obsolete or superseded documents described .i n the paragraph above are replaced in a timely manner by updated document revisions.

i The IP Quality Assurance department conducts periodic surveillances l

and audits of document control systems to ensure compliance with the specified requirements.

6.3 RESPONSIBILITIES 6.3.1 Fuclear Procram Department;.s

a. Review, approve and distribute controlled documents generated in accordance with appropriate procedures, j b. Employ appropriate measures to receive, record and L re-distribute controlled documents from other l organizations.

6.3.2 Nuclear Planning and Sunnort

a. 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.

l PAGE 3 of 4 REVISION: 13 j DATE: 12/28/92 ,

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b,.

t fLLINOIS POWER NUCLEAR PROGRAM- -

. QUALITY ASSURANCE. MANUAL chapter 6f

6. 3. 3- Ouality Assuranco

a. Conduct periodic surveillances and . audits of - docu--

mont control systems to ensure compliance _.with --: the -

requirements'of this chapter. +

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j PAGE - 4 of 4 REVISION: 23 DATE: 12/28/92 h

i

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 7

CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES APPROVED BY: MANAGER-QUALITY ASSURANCE M 12/28/92 l

7.1 JL4REOSE/ SCOPE To define the requirements and responsibilities for programs that assure purchased material, equipment, and services conform to procurement requirements.

7.2 DJISCRIPTION Measures have been established to provide assurance that purchased material, equipment, and services conform to procurement document requirements. This assurance is accomplished by controlling both the selection of procurement sources and inspections of the product at the source and/or upon receipt at CPS.

IP procuroment procedures require a review of material, equipment and services requisitions for safety-related structures, systems, and components by the Nuclear Station Engineering Department. This review will identify the applicable codes, standards, technical and quality 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.

Nuclear Station Engineering is responsible for performing the necessary reviews and evaluations of the procurement source's capability to meet the technical requirements of the procurement documents.

The Quality Assurance department specifies the Quality Assurance program requirements that must be met by suppliers.- Quality Assurance is responsible for performing the necessary reviews and evaluations of the procurement source's Quality Assurance program and ability to meet the quality assurance requirements of the procurement documents. Where necessary, the determination of a supplier's acceptability includes information obtained through-audits of the supplier by the Quality Assurance organization. Such audits are performed in accordance with a written plan or checklist to determine the ability of suppliers to comply with Quality Assurance program requirements of the procurement document. The PAGE 1 of 5 REVISION: 23 DATE: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 7 determination of a supplier's acceptability may be made by means other than by audits of the supplier by Quality Assurance. 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 organizations, including architect-engineer, Nuclear Steam Systems Supplier, and other utilities that indicates the supplier has a program that meets applicable requirements of Appendix B to 10CFR50. When these means are either not available or do not permit a completo evaluation of a supplier's quality capabilities, Quality Assurance will conduct a survey or an audit of the supplier. The Quality Assurance department is responsible for maintaining the Qualified Suppliers List.

In addition to reviewing a supplier's capability to meet the commercial requirements of the procurement documents, Purchasing and Material Control is assigned the responsibility of ascertain-ing that the required technical and quality assurance reviews and evaluations have been completed satisfactorily prior to contract cward or release of the purchase order. The results of these reviews and evaluations are documented.

Following the award of the contract or placement of the purchase order, the Quality Assurance organization is responsible for performing periodic surveillances and evaluations at the supplier's facility, as necessary, to verify continued compliance with the quality assurance requirements of the procurement documents. The results of these surveillances and evaluations are documented.

Where specified in the purchase order or contract, source-inspections at the supplier's facility are accomplished by the Quality Assurance organization or qualified agent to verify that l the procured item or service is being supplied in compliance with the requirements of the procurement documents. Such inspections are accomplished in accordance with written procedures, plans, l

and/or checklists containing or referencing appropriate acceptance criteria.

Upon receipt at CPS, Nuclear Planning and Support is responsible for the control of safety-related materials, parts, and components.

Quality Assurance inspection personnel are responsible for inspect-l ing, releasing, and identifying purchased material and equipment as l_ to the inspection status as required by the purchase order.

l After receipt ir.spection, storeroom personnel of Nuclear Planning l and Support are responsible for forwarding the purchased material to a controlled storage area or releasing it for installation or PAGE 2 of 5 REVISION: 23 DATE: _12/28/92

1LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 7 further work. Personnel from other departments also perform acceptance activities such as evaluation of content of technical documents required by the purchase order, and the conduct of special tests and measurements which are identified in the purchase order. When these activities are accomplished, QA personnel verify that those acceptance activities were accomplished prior to final acceptance of an item. Receipt inspections are accomplished in accordance with written procedures and/or plans containing or referencing appropriate acceptance criteria.

Documentary evidence of conformance to procurement requirements provided by the supplier in accordance with the procurement docu-monts 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 inspec-tions, surveillance, testing of hardware, Quality Assurance audits or surveillances. Inspection and test activities verify that the hardware performs in accordance with applicable technical re-quirements and serve to demonstrato that the hardware meets the requirements stated in a certificate of conformance. The results of the source and/or receipt inspections, the acceptability of supplier furnished documentation, and the resulting determination of conformance or nonconformance are documented.

Acceptcace of contracted services such as inspection services, consultant services, installation, repair or maintenance services shall be based on one or all of the following methods, as required:

a. technical verifications.

b. surveillance / inspections.

c. review of objective evidence such as certifications or technical reports.

The Quality Assurance department conducts periodic surveillances and audits of the control measures applied to purchased materials, l equipment, and services to determine the ef fectiveness in meeting i

the specified requirements. Quality Assurance audits of suppliers evaluate the adequacy and effectiveness of suppliers' systems and procedures for preparing certificates of conformance, as well as the adequacy of supporting documentation and records.

7.3 RESPONSIBILITIES 7.3.1 Nuc1 ear Procram Departments l

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l PAGE 3 of 5 REVISION: 23 DATE: 12/28/92

1LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 7

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 ILuclear Station Engineering

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

b. Perform technical reviews and evaluations of suppliers' capabilities to meet procurement technical requirements prior to release of the purchase order or contract.

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

7.3.3 lhiclear Plannina and Support

a. Review requisitions for completeness,

b. Provide materials or equipment requiring receipt inspection to Quality Assurance for acceptance prior to issuing the material or equipment for operation,

c. Develop and implement procedures for the receiving, storing, and issuing of purchased items.

7.3.4 Purchasina 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.

7.3.5 Ouality Assurance

a. Perform source evaluations and audits, as necessary, of suppliers' quality assurance programs prior to release of the initial purchase order or award of contract.

PAGE 4 of 5. REVISION: 23 !

DATE: 12/28/92

1 ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL - chapter 7---

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b. Perform periodic- surveillances and evaluations Lab suppliers' facilities, as-necessary, to verify continued 4

compliance with- quality- requirements."of procurement-documents,

c. . conduct periodic surveillances and-audits'of-tha controll measures applied to purchased materials, equipment, and services to ensure compliance with the requirements = - of this chapter,

d. perform and- document source inspections, as necessary,-

at the suppliers'- facilities to verify that procured' items or services- are in .' compliance with the.

-requirements of the procurement-documents.

e. perform and- document receipt. inspection- 'of. . purchased items, including- verifying the required documentary-evidence of 'conformance- to procurement requirements is available at CPS and verifying activities _-of other--

groups- are accomplished prior to final.. acceptance- of an - -

item and release for usa.

f. Review purchase requisitions and specify. the; qualityy .

hasurance program requirements- for the . item (s) to : be ~

procered.

g. Perform surveillances or inspections, as required, on procured services prior to acceptance.

h. Maintain . the Qualified ' Suppliers List L current' based- on '

the results of evaluations or audits.

4 PAGE 5 of 5 REVISION: '/ S DATE: '12/28/92

i ILLINOIS POWER NUCLEAR PROGRAM l QUA!.lTY ASSURANCE MANUAL-

-CHAPTER 8 :

IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS APPROVED BY: MANAGER-QUALITY ASSURANCE M 12/28/92

/

8.1 PURPOSE / SCOPE

To define the requirements and 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

Measures have. been established which provide for the identification and control of materials, parts, and components to assure l 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-items of purchase,

b. An . inventory contro) 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 to the' intended function of the item.

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

When codes, standards, or_ specifications require traceabilityJ e . --

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.

PAGE 1 of 3 REVISION: 73

.DATE: -12/28/92

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'lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 8 Materials, parts, and components shall have appropriate identifying designation (such as serial number, part number, heat number, etc.)

in order to provide traceability to each item to inspection and test records and/or reports. Where physica: identification of an item is either impractical or insufficient, physical separation or additional procedural controls are employed.

When installed material or equipment is removed for maintenance, rapair, or modification, control measures are implemented to ensure

" roper identification markings and traceability throughout its pro-cessing. During fabrication, assembly, installation, and shipping activities at a supplier's facility, the supplier is responsible for identification and control of materials, parts, and components in accordance with the requirements of the IP purchase order.

The CPS Plant Staff is responsible for identification and control of material, parts, and components during fabrication, maintenance and modification activities performed at CPS. Nuclear Planning and Support is responsible for identification and control of material, parts, and components during receipt and storage at CPS. The IP department responsible for supplier work at CPS is responsible for insuring that identification and control of materials, parts, and components by the supplier are in accordance with applicable proco-dures.

The IP Quality Assurance Department conducts verification inspections and periodic surveillances and audits to assure that identification and control of materials, parts, and components are in compliance with program requirements.

8.3 BJIlS PONSIBILITIES 8.3.1 Nuclear Prociram 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 St_aff

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

PAGE 2 of 3 REVISION: 23 DATE: 12/28/92

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It.LINOIS POWER NUCLEAR PROGRAM QUALITY; ASSURANCE MANUAL Chapter (8 t

8.3.3 liuclear Plannina-and:Suonort i a . -- Develop and implement an inventory . control'. system - '

for the identification and ~ control- of-; materialo r parts and components.-

8.3.4 Ouality Assurance '

a. Ensure that suppliers comply with ' approved procedures.

b. Conduct verification- inspections and_ ~periodici surveillances and audits of -- the -- identification and control of itemn to- ensure compliance with- the requirements of this chapter.

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PAGE 3 of 3 REVISION: 23 DATE: 12/28/92-

" ' lLLINOIS POWER NUCLEAR PROGRAM '

QUALITY ASSURANCE MANUAL CHAPTER 9

CONTROL OF SPECIAL PROCESSES APPROVED BY: MANAGER-QUALITY ASSURANCE /

HM 12/28/92

{

9.1 EU.RPOSE/ SCOPE To define the requirements and responsibilities for assuring _ that special processes such as welding, heat treating, chemical clean-ing, nondestructive . examination (NDE) ,- pipe bending, and special coatings are performed under proper controls 7nd 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

For some . processes the required level of quality. defined in codes, '

standards, and specifications cannot be-verified _by inspection of the item only. For these processes - quality _ assurance is obtained through a. combination of inspection and reliance on personnel '

qualification and procedural control, as appropriate, for the-process- being conducted. Processes which meet the - following cri-

-teria are controlled as special processes:

a. -The process is highly dependent upon operator skill and/or procesa control.

b. The specified quality cannot be readily determined by. direct inspection or test of-the final product.

Special- processes include welding, heat . treatment, nondestructive-examination coatings.

(testing), chemical cleaning, pipe' bending,-and special Special process procedures shall specify: prerequisite - conditions, procescing steps, conditions to be maintained ' during the steps of the process,. inspection and' test requirements, personnel qualifica-tion requirements and record requirements. - Technical portions of the special process = controls are delineated or referenced in the PAGE 1 of 4 REVISION: ?S DATE: 12/28/92

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1LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 9 design or technical documents by the organization preparing the document.

Special process procedures shall be submitted to Nuclear Station Engineering for review and approval to assura technical adequacy.

Supplier process control procedures specify the methods of verifying the adequacy of processing materials, solutions, and equipment, including definitions of their associated control parameters. The control and approval of sub-supplier special process procedures are the responribility of the specific suppliers involved. Special process requirements are promulgated to suppliers by the procurement and/or design documents.

Nuclear Station Engineering specifies special processes in technical documents and procurement requisitions. The control of scheduled ISI examinations and inspections is the responsibility of the Nuclear Station Engineering Department. The control of other special processes is the responsibility of CPS Plant Staff. The control of NDE to support plant operations is the responsibility of the QA department, control measures and requirements that have been established in-clude:

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,

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,

c. Personnel performing special processes are qualified, as required in accordance with applicable codes and standards.

d. Special processes are accomplished unuer suitable controlled conditions which include the use of qualified equipment, adequate control of the environment, and establishment of proper prerequisites related to the process,

c. Application of special process procedures and personnel qualifications is verified by IP Quality Assurance personnel through audits and surveillances,

f. Records which show that special processes were performed in compliance with qualified or approved procedures and by qualified personnel and equipment are maintained.

t PAGE 2 of 4 REVISION: 23 I DATE: 12/28/92

l ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 9 The Quality Assurance department conducts inspections, surveil-lances, and audits of special processes, including qualification of processes, equipment, and pornonnel to ensure compliance with appropriate codes, standards, specifications, procedures, and the IP Nucinar Program Quality Assurance Manual.

9.3 PESPONSIBILITIES 9.3.1 CPS Plant Staff

a. Establish and maintain a program to qualify special process procedures and equipment, except NDE required for plant operations.

b. Establish and maintain a program to qualify personnel to perform special processes, except NDE required for plant operations,

c. Incorporate into Plant Staff documents the re-quirement for special processes and their controls and references to the applicable codes or standards.

9.3.2 Nuclear Station Engineering

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 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.

PAGE 3 of 4 REVISION: 23 DATE: 12/28/92

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QUALITY ASSURANCE MANUAL-

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Chapter 9

.9.3.3 Ouality AssyrADge

a. Review NDE procedures,' including those of suppliers. .

b. Establish! and maintain a. program ' to.- qualify _

procecures, equipment, and personnel for NDE. ,

c. Perform NDE to support - plant operations,; including-NDE for repairs, replacements and modifications.

d. If radiography is performed - by _ IP, maintain the--

required NRC license for radioactive source material,

e. Contracts with a su perform or-pplier 'to NDE inspection services as required.

f.

Conduct-periodic surveillances and audits'of spacial:

processes and controls, -including . qualification . of process, equipment, and-personnel, whether performed-

.by CPS Plant Staff or suppliers to ensure: compliance' j.

with approved procedures.

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-r PAGE 4 of 4 -REVISION: 23 1DATE: L_J2/28/92 1

.< < ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL

' CHAPTER 10 INSPECTION 1

APPROVED BY: MANAGER-QUALITY ASSUkANCE H4 12/28/92

(

10.1 PURPOSE / SCOPE To define the requirements and responsibilities for _ a program of-ins, action

, 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. The independent inspections performed are not intended to diminish or replace the clear responsibility of first line supervisors for the quality.of-work performed under their supervision.

10.2 DESCRIPTION

In order to assure safe and- reliable operation, programs of inspections are established at CPS which. includes' the following provisions:

a. The requirements for inspections-are identified and documented based on procedures, instructions,- drawings, and- other documents for ac activity prior to the start of the activity.

b. Inspections are accomplished _ in _ accordance with a combination -

of approved written inspection ' procedures ~ and documented instructions which contain or reference,Jas a minimum:.

1. A description of the required inspection (type, method, t-p etc.),

and, the responsibility for performing the inspection, 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; t

3. Applicable documents, drawings, and- specifications-L pertaining to the activity or item under inspection;- __

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+ H.LINOIS POWER NUCLEAR PROGRAM-QUALITY ASSURANCE MANUAL- chapter 10

4. Verification of the proper type, range, and' accuracy of inspection instrument (s) used-for each operation;

5. Appropriate quantitative- or qualitative criteria for acceptance / rejection;

6. Qualification requirements of inspection personnel; and-

7. Provisions for recording inspection data and results.--

c. Inspection personnel are qualified and certified in accordance-with the requirements-of applicable codes or standards and are persons other . than those who performed or directly supervised that activity being inspected. .The qualifications and certificationsiof--

inspection personnel are maintained current.

d. Where direct inspection or testing is impossible-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.

e. Measuring and test equipment 'used to obtain-quantitative data for' acceptance criteria shall hav_e an accuracy equal to, or greater than, the required tolerances of the measurement-being-taken.

The Quality Assurance department. 'is responsible.- for inspection ~ of plant structures, systems, and ' components. - The; Nuclear - Station -

Engineering department is responsible ' . for - scheduled ~ ISI Program; examinations and inspections. Inspections- conducted -include:

maintenance and modification inspection, . receipt inspection, 'new fuel _ inspection, inspections.-ofLsurveillance' tests, inspections of functional and preoperational tests, ISI ~ examinations and inspections, .and housekeeping _ inspection. . The - Quality Assurance:

department _is responsible for evaluating _ and determining: the acceptability -of inspection results . in accordance with specified'

. inspection criteria.- The Nuclear Station Engineering department-is:

responsible for evaluating and determining L the. acceptability . of -

scheduled ' ISI Program . examination and inspection _.results. The"

-Quality ' Assurance ' department and tlie Nuclear Station Engineering' department may use the services of other IP department personnel'or

-may' engage the services of external organizations-to'acconplish-any-inspections,-- evaluations or reviews of : inspection and- test results.

b 2 of 3 REVISION: 23

-DATE: -12/28/92

.lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 10 Suppliers are responsible for establishing and implementing inspection programs necessary to meet the requirements specified in the procurement documents. The need to invoke the requirements of ANSI N45.2.6 on cuppliers is evaluated by the Quality Assurance department and the Nuclear Station Engineering department during the review of procurement documents for items and services. The complexity of the item and the extent of source and receipt inspection are factors which are considered when determining whether or not to invoko ANSI N45.2.6.

IPQA conducts periodic surveillances and audits of the various established inspection programs and their implementation to ensure compliance with thc. provisions described in items "a" through "e" above.

10.3 RES PONSIBIIJ.T_I ES 10.3.1 CPS Plant Staff

a. Develop and implement a program that provides for inspection of work operations performed at CPS.

10.3.2 Nuclear Station Encrineering

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

b. Develop and implement an inspection program for scheduled ISI Program examinations and inspections.

c. Maintain qualified and certified inspection personnel in accordance with appropriate standards.

10.3.3 Ouality Assurance

a. Develop and implement an inspection program for CPS.

( b. Maintain qualified and certified inspection personnel in accordance with appropriate standards,

c. Verify through surveillances and audits that suppliers performing work at CPS are in compliance with the approved inspection program.

d. Conduct periodic surveillances and audits of inspection programs to ensure compliance with the requirements of this chapter.

PAGE 3 of 3 REVISION: 23

, DATE: 12/28/92 I

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lLLINOIS POWER NUCLEAR PROGRAM -

-QUALITY ASSURANCE MANUAL.

CHAPTER 11 TEST CONTROL APPROVED BY: MANAGER-QUALITY ASSURANCE h 12/28/92 L

11.1 PURPOSE / SCOPE To define the requirements and responsibilities for the control of-a test program which' will assure that the safety-related struc -

tures, systecs or components being tested meet specified perfor- -

mance criteria.

=

11.2 DESCRIPTION

The IP. Nuclear Quality Assurance Program addresses requirements and responsibilities for establishing and conducting test ' programs - for - -

the following:

a. Verification tests prior to installation,

b. Surveillance testing.

c. Tests associated -with plant maintenance,. - modifications ,--

repairs or procedural changes.

Test programs ' are - developed to assure: that. the required tests are performed in 'accordance with _ approved written 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 t est',

including requirements for -calibrated . instruments,- suitable!

environmental conditions, . appropriate J equipment and personnel availability; . and condition of the . item to be tested and condition of the-test equipment;

c. Precaut ions to . be.~ taken 'in the preparation and . performance of the test,-including-limits of parameters if variations outside the normal ranges are prescribed; PAGE 1 of 3- REVISION: 23 DATE: 12/28/92

.lLLINOIS POWER NUCLEAR PROGRAM-QUALITY- ASSURANCE MANUAL - chapter 11 .

d. Mandatory inspection- ihold points for: witness by inspecti~on -

personnel;

e. Instructions for performance of the test, including the use of appropriate instruments, equipment-and personnel; .

f. Data to be acquired; and

g. Acceptance / rejection criteria.

Test schedules are provided and L.aintained in order to 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- required tests.

Testing is -conducted by appropriately 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 CPS Plant Staff

a. Develop -and 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-trained to perform their function,

d. Perform the required' tests.

e. Review and; approve . test procedures and results --for

, surveillance testing.

l l f. Review and approve post-maintenance test results,

g. ;

Review'and approve post-modification test results.

11.3.2 Nuclear Station Encineerina

l. a. Establish test requirements and acceptance _ criteria -

for post-modification testing.

PAGE 2 of 3 REVISION: 23 DATE: 12/28/92 l~

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.. - 4LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL' Chapter 11

~ b '. Review ~ and _.. approve post-modificatsion and/or special-test results as detailed in approved procedures.-

-c. Review and evaluate test results as required by the ISI Program.

11.3.3 Ouality Assuranga_

a. -Review and-approve test. procedures ~to_ assure that QA requirements are included.

b. Approve test -results as specified in the implementing procedures.

c. Conduct periodic surveillances and: audits . "of . the-test program and to ensure the~ test program ~. complies with'the requirements of this chapter.-

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DATE: 12/28/92

l lLLINOIS POWER NUCLEAR PROGRAM QUAUTY ASSURANCE MANUAL CHAPTER 12 CONTROL OF MEASURING AND TEST EQUIPMENT APPROVED BY: MANAGER-QUALITY ASSURANCE i 12/28/92 L

12.1 P_UJ1 POSE / SCOPE To define the measures and responsibilities to assure tools, gauges, instruments, and other measuring and testing devices (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 DESCRJ PTION M&TE is procedurally defined as 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 equipment.

or instrument / control In order to assure the accuracy of measuring and test 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 supervisors.

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 type of equipment, PAGE 1 of 3 REVISION: 23 j DATE: 12/28/92

JLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL _ Chapter 12 stability, reliability characteristics, . required . accuracy ~__and other conditions affecting' calibration.

d. Calibrations are performed by comparison with valid standards -

and using approved written procedures.

o. 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 due date~ of next-calibration of each item of M&TE, is visible through use of.-

tags, labels or decals attached to tne equipment or aL statusing system,

g. M&TE and in' stalled 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 bearL the assigned equipment identification . numbers and the. identification- of the ,

calibration standard used-and are traceable to'.the individual calibration records.

h.- M&TE is not used- past the expiration -of .the ~ calibration period.

1. 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 1taken in accordance with Chapter 16 when such evaluations invalidate a.

previous acceptance..

I

j. A calibration tracking _ system is established to : ensure that-recalibration is performed in accordance with pre-established calibration frequencies.

CPS Plant Staff is assigned.the responsibility'for_ establishing and -

implementing the program. for' the control of M&TE and lastalled' L instrument. and control ' devices used- in operation, -maintenance, _ test and/or-inspection activities which fall within the. scope _of the'IP PAGE 2 of 3 REVISION: 23

.DATE: 12/28/92

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lLLINOIS POWER NUCLEAR PROGRAM i

-QUALITY ASSURANCE MANUAL _ chapter -

Nuclear Quality Ascurance - Program.

Suppliers performing services or - providing products to_- CPS are required to have comparable control programs in effect for items affecting systems, structures-and components within the scope of the QA program.

The IP Quality Assurance organization conducts ' periodic . surveil' -

lances and audits of the controls ~ applied to - measuring _ -'and test' equipment to determine compliance with the provisions described in items "a" through "j" above.

12.3 RESPONSIBILITIES 12.3.1 CPS Plant Staf f

a. Develop and implement programs _to control the use of-M&TE used at CPS.

b. Develop and 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. .i

d. Develop and implement programs to control the use of installed instrument and control devices.

12.3.2 Quality Assurance

a. Review the M&TE control program of suppliers performing-work at CPS.

b. Conduct periodic- surveillances and _ audits _ of .the controls applied .to M&TE and - installed - instrument-and control devices to determine compliance with the requirements'of this manual.

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'PAGE 3 of 3 REVISION: 23 DATE: 12/28/92

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-lLLINOIS POWER NUCLEAR PROGRAM .

QUALITY ASSURANCE MANUAL--

-CHAPTER 13 HANDLING, STORAGE AND SilIPPING APPROVED BY: MANAGER-QUALITY ASSURANCE , f 12/28/92 f >

13.1 PURPOSE / SCOPE To define the requirements and responsibilities for the control of handling, storage, shipping, packaging, cleaning an_d preservation of materials and equipment to prevent damage or deterioration.

13.2 DESCRIPTION

The IP Nuclear Quality Assurance Program includes procedures which '

assure special handling, preservation, storage, cicaning, packaging-and shipping requirements are accomplished by trained individuals-in accordance with plant procedures to prevent damage or-deterioration. The procedures will provide for ~ the control of heavy loads - and safe , load : paths to protect safety systems- and radioactive material from damage. In addition t o t h e_ handling, storage and shipping- requirements imposed -on suppliers by IP through appropriate technical .and procurement documents, suppliers may also -.be required to provide information to Nuclear planning &

Support = related. _to the proper ' handling, storage -and shipping. of-furnished materials, parts- and components. Nuclear' Planning l &

Support uses: this information for the development. of the storage and handling procedures and instructions to benapplied to aniitem.

The procedures and instructions will provide for the preservation of special items that are subject to deterioration = . or ' damage through exposure to air, moisture, temperature, or - other. environ-monts-and use of special handling tools and equipment.-

Consumabic materials such as - chemicals, ! reagents 'and -lubricants maintained in storerooms'and warehouses are. controlled. procedurally l by an inventory :contro11 system which includes' provisions- forL identifying storage requirements by commodity and' identifying shelf 11fe:by commodity,:when applicable. Disposal'of commodities _whose shelf life-has: expired is addressed and controlled by procedures.

The Quality Assurance department conducts periodic surveillances, audits-and document reviews to - determine i'f appropriate , procedures:

PAGE 1 of 3 REVISION: 23 j' _DATE:__12/28/92 l

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lLLINOIS POWER NUCLEAR PROGRAM 1 QUALITY ASSURANCE _ MANUAL chapter 13-and controls are being._ applied regarding handling,

~

storage . and shipping'of materials and equipment.

13,3-RESPONSIJILITIES 13.3.1 GPS Plant Staff

a. Develop and _ implement programs to provide' for- the use of special handling tools and equipment.

b. Develop and implement programs to control- the han-dling, storage and shipping of radioactive materials.

13.3.2 Nuclear Station Encineering

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 Planninc and Sunnort

a. Ensure that suppliers furnish the.. required:

information relating to the. proper handling, storage and shipping _of procured' items,

b. Develop and implement programs to. control the-han-dling, storage and shippingTof items to-be used'in.

~

CPS,' including radioactive materials.

c. Develop _ and 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.

PAGE 2 of 3 REVISION: 73 DATE: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM

( QUALITY ASSURANCE MANUAL chapter 13 13.3.4 Ouality Assaranca

a. Conduct periodic surveillances, audits and document reviews to verify that appropriate procedures and controls are being implemented in accordance with the requirements of this chapter.

i PAGE 3 of 3 REVISION: 23 DATE: 12/28/92

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 14

INSPECTION, TEST AND OPERATING STATUS APPROVED BY: MANAGER-QUALITY ASSURANCE 12/28/92-l 14.1 PURPOSF/ SCOPE To define the requirements and responsibilition for identifying the -i inspection, testing and operational status of materials, . parts, compononto and assemblics to assure that only items which have passed the required inspections and tests are installed or operated.

14.2 DESCRIPT(Q1{

The Ip Nuclear Quality Assuranco Program includes proceduros - which assure the inspection, test and operating status of materials, parts and components are identified during the-- rocciving, installation . and operating processes. These proceduros provido '

for:

a. Clear indication of the status of inspection and testo performed upon individual items by the uso of markings such as a) stamps applied directly to the item, tags,. or. labols 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 tho :contro11 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, considoration is given to ensure the markings have no -!

dolotorious offects on tho items,

b. Assuranco that required inspections- or tests- are not L inadvertently bypassed.~ In casos . where required, documenting ovidenco is not availabla, the associated -equipment or materials must bo considered nonconforming in accordance with Chapter 15 of the QA Manual. _Until- suitable documenting.- !

evidence _is available to show the equipment or material is in l :i 1

.PAGE 1 of 3 REVISION: 23 DATE:- 12/28/92

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4LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 14 conformance, affacted systems shall be considered to be inoperablo and relianco uhall not be placed on such systems to fulfill their intended safety functions.

c. Clear indication, by the uno of a tag and/or statusing system, of the operational status of structures, systems and compo- t nents when in any status other than a normal operablo status to provent inadvertent operation.

I CPS Plant Staff is responsible for indicating the test and oporat-ing status of materials, parts, components and assemblies at CPS.

Nuclear Planning and Support is responsible for maintaining inspection and test status of items in storage. Quality Assuranco is responsible for the identification of the inspection status on matorials, parts and components. As imposed by the contract documents, suppliers performing activities at CPS or furnishing matorials, parts, components or assemblios for use at CPS also have responsibilition for the identification of inspection, test and operating status of items under their control. CPS Plant Staff and the QA department review and approve the programs of suppliers performing work at CPS to ensure compatibility with the CPS status indication system.

Tho Quality Assuranco department conducts periodic survoillances and audits to datormine implomontation and adequacy of measures used to indicato inspection, test and operating status to moet the requirements of the IP Nuclear Quality Assuranco Program.

14.3 EESPONSIBILITIES 34,3.1 CTS _Idant Staff

a. Develop and implomont programs to indicato inspection, test and operating status of materials, parts, components, sub-systems and systems during installation, modification, repair, testing and operation of CPS.

l Review

b. and approve the programs of suppliers performing work at CPS to ensure compatibility with the CPS status indication system.

c. Establish and implomont procedures and control the status of radiological samplos, j 14.3.2 puclear Plannino apjl_Sujmgri l

pAGE 2_of 3 REVISION: 23 DATE: 12/28/92

i

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4LLINOIS POWER NUCLEAR PROGRAM l QUALITY ASSURANCE MANUAL Chapter _14 Establish and implomont procedures to - conticol the a.

inspection and test status of items in storage. !

14.3.3 Oun11ty_. Assurance f

a. Review and approve the programs of suppliers performing work at CPS to ensure compatibility with tho various status indicating systems. .,

b. Develop and implement programs to indicate - receipt inspection status of materials, -parts and compononts.

c. Develop and' implement programs to indicate status of'

nonconforming items.

d. Conduct periodic surveillances and audits of the implomontation and adoquacy of programs used to-indicato inspection, test and oporating statua to ensuro compliance with the requirements of this__ l chaptor. t W

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_DATE: 12/28/92 >

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 15 NOllColiFORMI!1G MATERIALS, PARTS OR COMPoliEllTS APPROVED IW: MAllAGER-QUALITY ASSURANCE 9 12/28/92 l

15.1 JLUREDEF/ SCOPE To describe the measures established and implemented to control items, services or activities which do not conform to requirementa, and the measures to control further processing, delivery or installation of nonconforming or dofoctive items.

15.2 DEECJtIPTIOE The following measures have been established and implemented at CPS:

a. Control of nonconformances is accomplished in accordance with documented procedures.

b. Nonconformances are documented by means which also ensure that affected organizations are notified.

c. Nonconforming items are identified and controlled. Except for installed items, they 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 items.or those removed from the normally installed location.

d. Further use or installation of nonconforming items is controlled in accordance with written procedures and/or instructions.

e. The responsibility and authority for the disposition of nonconformances is defined,

f. Permissible dispositions are: a) "use as is", b) " rework" to drawing or specification requirements, c) " repair" to an PAGE 1 of 4 REVISION: 23 l

DATE: 12/28/92 L

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4LLIN0lS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 15 acceptable level, d) " reject" forthat particular use, or e)

"other" for non-hardware nonconformances.

g. " Repair" and " rework" dispositions are implemented into the affected item f ri accordance with documented procedures and/or inctructions.

h. The disposition, along with its engineering analysis and any resultant reinspection and/or acceptance verification, are documented.

1. "Rowork" 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 and reviewed by the Quality Assurance Department.

j.

Reports documenting nonconforming items are reviewed by the Quality Assurance department prior to closcout to verify that the nonconformances were properly documented, dispositioned, corrected and inspection and/or acceptance verification is completed.

Inservice items that are found to be nonconforming shall be reviewed to determine equipment operability as defined by the Technical Specifications. For items that represent significant conditions use-as-lo adverse to quality or safety, or require a repair or disposition, an engineering evaluation shall be performed. The engineering evaluation shall provide support for the initial operability decision and provide the correction or resolution for the identified nonconformance. These items shall be controlled in accordance with approved procedures.

Installed items not inservice that are nonconforming 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.

A nonconforming item may be conditionally released for 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.

PAGE 2 of 4._ REVISION: 23 i

DATE: 12/28/92

'lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 15 The Vice President -

Clinton Power Station has the authority to conditionally release any item for installation or operations if needed to place the plant in a safe and stable condition. i Procurement documents require that suppliers have similar measures established for the identification, control, and dispositioning of i nonconformances and that recommended dispositions of Huse-as-is" or

" repair" must be reported to IP for approval.

The IP Quality Assurance department conducts periodic surveillances and audits of the programs instituted for the identification and l control of nonconformances to ensure compliance with the !

requirements of the IP Nuclear Quality Assurance Program. l 1

15.3 RESPONSIBILITIHS 15.3.1 All Nuclear Program Personnel

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

15.3.2 Lutclear Pro 9EDm Denartments

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 departments' activities as described in this chapter of the QA manual.

15.3.3 CPS Plant Staff

a. Authorize the conditional release of items,

b. Evaluate and document, together with -NSED, the safety significance of nonconforming items.

c. Develop and implement procedures, instructions or work control documents for the correction of noncon-forming items with repair _or rework dispositions.

15.3.4 ILug1 par Plannina & Support

a. Establish and implement an effective program for processing supplier nonconformance reports.

PAGE 3 of 4 REVISION: 23 DATE: 12dN_22_.

(LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 15 15.3.5 lluclear Statiorl_ Engineering

a. Establish and implement a program for dispositioning nonconforming itema that ensure "use-as-is" or

" repair" dispositions are approved by the appropriate design organization.

b. Evaluate and document, together with Plant Staff, the safety significance of nonconforming items.

c. Perform engineering evaluations for conditionally released items.

d. Determino 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 2pality Assuranqq

a. Establish and implement a program for verifying acceptable disposition implementation as required by the disposition of nonconformances.

b. Establish and implement programs for the review of nonconformances to verify offectiveness in meeting the requirements of this chapter.

c. Perform review of conditional release justifications,

d. Ensure that procurement documents require suppliers to establish a nonconformance program consistent with this chapter.

e. Conduct periodic surveillances/ audits of the Nonconformance Program at CPS to ensure compliance with the requirements of this chapter.

35.3.7 f_acility Revi,ew Groun

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

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PAGE 4 of 4 REVISION: 23 DATE: _12/28/92

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ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL CHAPTER 16 CORRECTIVE ACTION APPROVED BY: MANAGER-QUALITY ASSURANCE ~

M b 12/20/92 l

16.1 11WEQSE/ SCOPE To describe the measures 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 DESIRLITIQli Each IP organization and supplier performing activities or supply-ing uervices, materials, parts or components applicable to this program is required to establish and implement a documented correc-tive 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.

Personnel or 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 documented 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 safetf or operability.

The IP Quality Assurance Department performs trend analysis on conditions adverse to plant safety and/or quality to determine if a trend representing a significant condition adverse to plant safety and/or quality exists. Nuclear Station Engineering performs trend analysis of conditions documented on maintenance work documents to identify equipment failure and reliability concerns. 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 condi-tions and trends identified.

PAGE 1 of 3 REVISION: 23 DATE: 12/28/92

4LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL chapter 16 .

In the caso of significant conditione adverso to plant safety and/or quality, including significant adverso trends, the func-tional organization responsible for the significant condition will l analyze the condition for causes, take appropriato and tinoly 4

action to procludo recurrence and implomont follow-up action as appropriate to verify implementation of corrective action. The actions taken will be documented and reported to appropriato icvols

of management.

Corrective action is ovaluated b Quality Assurance Department to determine its effectiveness, y theincluding steps taken to identify the cause of significant conditions adverso to plant safoty and/or quality and action taken to preclude recurrence. Documented correctivo action for significant conditions adverso to plant safety is also reviewed by the Nuclear Review and Audit Group.

These a documented reviews are documented and are carried out in accordance with program, 16.3 IH;11EQUSIBILITILS 16.3.1 All Nuclear Program Perspnnel

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

16.3.2 ILyglear Program Department;n

a. Establish and implomont a correctivo action proce-dure (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 followup to verify implementation of correctivo action.

16.3.3 Elant Staff a.

Assess conditions adverso to plant-safety for opera-tional impact.

16.3.4 Qt.Lql.it;v Assyrnnqq

a. Establish and administer a trend analysis program for conditions adverso to quality.

plant safety and/or PAGE 2 of 3 REVISION: _2}_,

DATE: 12/28/92 ,

4LLINOIS POWER NUCLEAR PROGRAM QUAll! Y ASSURANCE MANUAL chaptor 16

b. Evaluato corrective action to datormine its offectivonoso,

c. Conduct periodic curveillances and audits of the correctivo action program to ensure compliance with the requirements of this chaptor.

16.3.5 lluclear Station Enninoering

a. Perform trend analysis of conditions documented on Maintenanco Work Roquests to identify equipment failure and reliability.

16.3.6 Iluglgar Review and hudit Groun

a. Review significant conditions adverso to plant safety in accordance with a documented program.

C PAGE 3 of 3 REVISION: _2]_

DATE: 12/28/92

.. e ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL i CHAPTER i 17 1 QUALITY ASSURANCE RECORDS >

APPROVED DY: 12/28/92 MANAGER-QUALITYASSURANCEhd ]/1

't f

17.1 PURPOSE /SCQEE To define the requirements and responsibilities for _ collection, compilation, storage and retrieval of records necessary to provide evidence of quality in the design, fabrication, installation, inspection, testing and operating activities related to the Clinton '

Power Station.

17.2 DESCRIPTIOlJ Sufficient records, identifiable to the item.or activity to which they apply, filed in an orderly manner and retrievable are main-tained by Nuclear Planning and Support Department, Records Manage-mont Group, in-the records storage facilities.-

Test and inspection records shall contain the- following 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.

Departments generating records or departments receiving records i from other departments or suppliers transfer ~them_ to Nuclear

- Planning and Support, Records Management-Group,.for retention. 'The-Records Management Group' processes (indexes, microfilms, etc. )' - and t maintains the records- for- retention in' the records" storage facilities. The preparation, collection, review, ' acceptance,-_

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 of fered . to ' IP .

after the suppliers no longer' plan to-keep them.

_PAGE 1 of 2_ REVISION: .. 23 .

.DATE: 12/28/92

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.lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter 17 The retention times for the various quality assurance records are in accordance with app]icablo requirements including 10CFR50, Technical Specifications and nationally recognized standards end codes. Records are maintained in the records storage facilities that provides controlled access and protection against fire, flooding, vermin and decay. Nuclear Planning and Support is responsible for the definition and implementation of activities related to records.

The Quality Assurance department conducts periodic audits of records systems to ensure compliance in meeting the IP Nuclear Quality Assurance Program requirements.

17. 3 BESPONSI15ILITIES 17.3.1 ((qclear Proctram Departments

a. Develop and implement departmental procedures or instructions for records preparation, collection, review, turnover /trans fer, recolpt, retention and retrieval which implement the Records Management Program and Standards.

b. Transfer completed Quality Assurance records to Nuclear Planning and Support Records Management Group for processing, maintenance and rotontion.

17.3.2 Nuclear Planning and Support

a. Establish, maintain and implement a Records Manage-ment Program including Standards covering the prepa-ration, collection, review, turnover / transfer, processing, retention and retrieval of records generated in performing activities within the c ope of this program.

b. Receive, process (index, microfilm, etc.), maintain and retain QA records in the records storage facilities,

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

17.3.3 Ouality Assurance

a. Conduct periodic audits of records systems to ensure compliance with the requirements of this chapter.

PAGE 2 of 2 REVISION: 23 DATE: 12/28/92

o o ILLINOIS POWER NUCLEAR PROGRAM !

QUALITY ASSURANCE MANUAL CHAPTER 18 i

AUDITS APPROVED BY: MANAGER-QUALITY ASSURANCE _, 9/II4 12/28/92 i

i 18.1 PURPOSE / SCOPE To define the requirements and responsibilities for implementing the i program of planned and periodic audits which shall- verify compliance '

-with the quality assurance program and determine the effectiveness in- ,

meeting program objectives.

18.2 DEEQRIPTION IP's Quality Assurance program includes provisions for planned . and _ >

periodic audits-designed to verify compliance with the requirements of the IP Nuc1 car Quality Assurance Program and to determine the effectiveness in implementing the program objectives. .The I? Quality +

Assurance organization has the responsibility for implementing the-QA audit program. The audit program provides for.the followings

a. Provisions are made'for both internal-and external audits,

b. Audits include the full range of activities within the = scope of - .

the IP Nuclear Quality Assurance l Program. Additionally,- QA program audits include indoctrination and training _ programs;.

interface control between IP, the-audited organizations and other affected organizations; USAR commitments; .

and Technical- ,

Specification requiremants.

c. Provisions are made for regularly scheduling audits based = upon the status and importance.of the activities. ~

i

d. A qualification sy' stem is established for - auditing ' personnel. -

Independent certifying agencies may ' be used for the - development and administration of-lead auditor examinations.

e. Personnel conducting- audits do' not -have .any direct responsibilities for the activitics being audited.

l i

PAGE . 1_.o. f 3 REVISION: 73 t

.DATE: 12/28/92-i' i ~.c. . ..__._..__.._.____.~...-_.,._,.;; _ , _ . - - _ _ . . . . _ - - . . . . . , _ _ . . . - ,

, ,,, ,. _ _ . L a ,.

4LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Chapter la

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

g. Written audit plans are developed which identity the scope, requirements, activities to be audited, organizations involved, applicable documents, schedule and written procedures or checklists to be used for each audit.

h. Audit results are documented, reports are generated and retained.

1. Audit reports are distributed to responsibic management of the auditing organization and to the appropriate managerial level of the organization having responsibility for the area or activity audited.

j. Appropriate corrective action is developed.

k. Followup action (including re-audits) is taken to verify that corrective action has been completed and the resolution documented.

Within the Quality Assurance organization, the Supervisor - Audits has the responsibility for maintaining and implementing an audit plan which verifies that applicable elements of the Quality Assurance program have been developed, documented, and implemented in accordance with the requirements of this manual. Audits will be initiated as early in the life of the activity as practicable consistent with the schedule for accomplishing the activity to assure timely implementation of the quality assurance requirements.

The plan is reviewed periodically to insure that it is current and-may be augmented at any time based on recommendations from thu Nuclear Review and Audit Group, or Nuclear Program personnel as the scope of work and other requirements for auditing an activity change.

Audited organizations are required to review and provide timely written response to audit findings stating corrective action taken or planned to correct deficient areas and prevent recurrence.

Audit program requirements are imposed on suppliers by appropriata contract or procurement documents.

Reports of internal audits are forwarded to the Nuclear Review and Audit Group and the Independent Safety Engineering Group for program evaluation. IP Management obtains an independent audit of the IP Quality Assurance organization on an annual basis.

PAGE 2 of 3 REVISION: 23 DATE: 12/28/92

l l

.. ,lLLINOIS POWER NUCLEAR PROGRAM !

QUALITY ASSURANCE MANUAL chapter 18 l 18.3 FIHEQiiSIBILITIEE 18.3.1 Fuclear Program DepJrtments

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

18.3.2 Licensina and Safety

a. Independent Safety Engineering Group review reports of internal audits for program ovaluation.

18.3.3 ((yclear Review and Audit Groun

a. Review reports of internal audits for program evaluation.

18.3.4 Quality Assurance

a. Implement an internal audit program and audit each IP organization performing activities within the scope of the QA program to verify' that the requirements of this manual are being met.

b. Implement an external audit program and audit suppliers performing activities within the scope of the IPQA program to verify compliance with the suppliers' respective quality assurance programs, contract, specifications and requirements,

c. Coordinate for the Senior Vice President the performance of independent audits of the QA organization.

d. Implement a program for evaluating the adequacy of corrective actions to audits.

PAGE 3 of 3 REVISION: 73 DATE: 12/28/92

+ 4LLIN0lS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL. Appendix A APPENDIX A REVISIONS TO THE IP NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Revisions to the IP Nuclear Program Quality Assurance Manual may be issued by either, or a combination of two ways: whole page replacements, or directions to manual holders to make pen and ink changes. Revisions are noted by a sequential number (the original lauue in designated REVISION O with subsequent issues as REVISIONS 1, 2, 3, etc.) and by the DATE of issue in the lower right hand corner of the page.

The Quality Assurance department shall approve distribution of the IP Nuclear Program Quality Assurance Manual and all revisions thereto. Manuals may be distributed as either controlled or uncontrolled copies. Controlled manual holders will receive all revisions to the manual. Revisions will not be routinely sent to holders of uncontrolled manuals. Persons assigned custody of controlled copies of the manual are responsible for maintaining the manual in accordance with the following:

1. For each revision issued, the manual holder will receive the revised material, an updated List of Effective pages and an accompanying transmittal letter providing.

instructions for the recipient to follow in updating the manual and reporting receipt and compliance with updating.

instructionn.

2. When revised material is provided, the obsolete - material shall ta removed and destroyed by the manual holder.

3. Requests for copics of the IP Nuclear Program Quality Assurance Manual or recommendations for revisions or corrections should be directed to the Manager - Quality Assurance in writing from the manager of the requesting organization. The precise change or revision and the reason / justification for the recommendation should be addressed.

Proposed revisions to the IP Nuclear Program Quality Assurance Manual will be sent to affected department managers and/or-directors Quality Assurance.

for their review prior to issuance by the Manager -

i i PAGE A-1 of 1 REVISION: 23 DATE: 12/28/92

i t

o +1LLINOIS POWER NUCLEAR PROGRAM !

QUALITY ASSURANCE MANUAL Appendix B !

APPENDIX B-SUPPLEMENTAL APPLICATION IP NUCLEAR QUALITY ASSURANCE l>l(00 RAM -

This appendix details in matrix form the chapters of this manual which are applicable in full or in part tot '

Fire Protection l Security Environmental Radwasto/ Augmented D Systems Packaging and Transportation of Radioactive Material i 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.

Tabic 3.2-1 in the Clinton Power Station USAR -identifies specif- '

ically those structures, systems and components that are important --

to safety. <

Fire Protection, . Security, Environmental and Radwaste/ Augmented--- D 1 systems are specifically identified in Table 3. 2 of the CPS USAR and/or highlighted in several Regulatory Guides that define and-clarify their importance to the plant.

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 i

4.15, " Quality ' Assurance for. Radiological Monitoring. Programs (Normal Operations) - -Effluent Streams and the Environment,"-

Revision 1 -(February 1979), states that, _"The need - of quality ;

assurance is implicit in all requirements 'for of fit ent 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 ymet- ;

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 idesign, construction, testing and operation of the security system t

at nuclear power plants.

10CFR Part 71 , " Packaging and Transportation of' Radioactive Material," Section 71.101, " Quality Assurance Requirements," t

[

PAGE 'B-1 of 12 REVISION:_ 23 DATE: 12/28/92-

. = , :a = _. - u -- . : u,- .-- =.-.a-.-.. _ . - . - - . = _ . - . . . . - . . _ - . --

-ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix Il '

1 i

requires that licensees have a quality assuranco program that has boon submitted to and approved by the liRC as satisfying the i

provinions of Subpart 11 of Part 71. Subpart !! requireta, in part, that licensoos' quality assurance programs satisfy each l of the applicabic critoria specified in Section 71.101 to an extent conslutont with their importance to safety. Regulatory Guido 7.10,

" Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactivo Material", Annex 2, providos quality assuranco programs applicable to Procurement, 000, Maintenance, and Repair of Packaging Used in Transport of Radioactivo Material.

The extent to which the IP liuclear Quality Assuranco Program applies to each of the four arono varios 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 Radwasto/ Augmented D systems and Packaging and Transportation of Radioactivo Material.

PAGE J1-2_91_ R REVISI0li: 23 DATE: -12/28/92

4LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix a MATRIX CIIAPTERS OF TIIE IP NUCLE,tR PROGRAM !

QUALITY ASSURANCE MANUAL APPLICABLE TO FIRE PROTECTION, SECURITY, ENVIRONMENTAL, AND RADWASTE/ AUGMENTED D, AND PACl%GE AFD TRANSPORTATION OF RADIOACTIVE MATERIAL I PACEACE AND OPERATIONAL RADI0 ACTIVE TRANSPORTATION QA MANUAL PIRE WASTE / OF RADI0 ACTIVE CllAPTER PROTECTION SECURITY ENVIRONMENTAL AUGMENTED D 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 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 engincoring specifi-cations, drawings, procedures, instructions, other documents, etc.

PAGE E-3 of 12 REVISION: 23 DATE: 12/28/92

l WLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix B FIRE PROTECTION Chapter 1- Applicable Chapter 2- Applicable Chapter 3- Applicable Chapter 4 -

Applicable. Specification of quality assuranco program requirements for suppliers of fire protection materials, equipment and services shall be on a caso-by-caso basis. Commercial grado or off-the-shelf items may provido 'an acceptablo level of quality based on the the nature of _the item. This determination shall be made jointly by Engineering and Quality Assurance personnel prior to issuance of procuromont-documents.

Chapter 5- Applicable Chapter 6- Applicablo Chapter 7- Applicabic. Suppliers providing material, equipment and services for fire protection shall bo subject to source ovaluation and surveillance. The extent of imposition of these requirements shall be determined on a case-by-caso basis by the design and quality assurance organizations responsiblo for review and approval of the procurement specifications. Measures shall be established, as appropriato, for-examination of products upon delivery.

Chapter 8- Not Applicable Chapter 9- Not Applicablo 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.

Chaptor 11 - Applicablo Chapter 12 - Not Applicable Chapter 13 - Not Applicable PAGE 1)-4 of 12 REVISION: 2)__

DATE: 12/28/92 4

d

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix a Chapter 14 - Applicable Chapter 15 - Applicable Chapter 16 - Applicable Chapter 17 - Applicabic to documento designated as Quality Aucur-ance 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. Audits 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.

PAGE D-5 of 12__ REVISION: 23 DATE: 12/28/92

a 1LLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix B SECURITY Chapter 1- llot Applicable Chapter 2 -

Not Applicablo Chapter 3 -

Not Applicable Chapter 4 -

liot Applicable Chapter 5- Not Applicable Chapter 6 -

Not Applicablo Chapter 7- Not Applicable Chapter 8 -

Not Applicable Chaptor 9- Not Applicablo Chapter 10 - Not Applicablo chapter 11 - Not Applicablo Chaptor 12 -

Not Applicable Chapter 13 -

Not Applicable Chapter 14 -

Not Applicablo Chapter 15 - Not Applicable Chapter 16 - Applicablo Chapter 17 - Applicable to those records required by the CPS Physical Security Plan.

Chapter 18 -

Applicable to the physical security of CPS and desig-nated records.

PAGE B-6 of 12 REVISION: 1 DATE: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix a ElfVIRoliMEliTAL Chaptor 1- Applicablo Chaptor 2 -

Applicable Chaptor 3 -

liot Applicablo Chapter 4- Applicabic to procuromont of monitoring services to be performed by contractors providing services dealing with radiological data and to radionuclido reference standards used for calibration of radiation measuromont systems.

Chapter 5- Applicable to all activities related to carrying out the radiological monitoring program includingt sample collection; packaging, shipment and rocolpt of samples for off-sito analysis; procurement, maintenanco, storage and use of radioactivity reference standardst calibration and checks of radiation and radioactivity measuromont systems; and reduction, evaluation and reporting of data.

Chaptor 6- Applicable to procedures and instructions required by Chaptor 5.

Chapter 7- Applicable to radionuclido referenco standards used for calibration of radiation measurement systems and to radiological monitoring provided by contractors.

activitics (services)

Chapter 8 -

Applicable only to radiological sample collection, identification, packaging, shipping, receiving, storago and analysis.

Chapter 9- Not Applicable Chapter 10 - Not Applicable Chapter 11 -

Applicablo_to radioactivity measurements of samples, instrument nackgrounds, replicate samples and analytical blanks; data reduction and verification; computer program documentation-and verification.

Chapter 12 - Applicable to laboratory instruments for rad:!ation and radioactivity measurement, continuous radiological offluent monitoring _ systems and flow-PAGE-7 of 12 REVISION: 23 DATE: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix n rato measuring devices associated with radiological offluent monitoring systems. Chapter 13 - Applicable to radiological samplos only. Chaptor 14 - Applicable to continuous radiological offluent moni-toring systems equipment only, chapter 15 - Applicablo Chaptor 16 - Applicablo Chaptor 17 - Applicable to personnel training and qualification; field and in-plant collection of samples; continuous offluent monitoring; sample recolpt and laboratory identification; samplo preparation and radiochemical processing; radioactivity measurements of samplos, instrument backgrounds and analytical blanks; data reduction and verificationt instrumont and calibration calibration standards; computer program documentation; audits; and correctivo action. Chapter 18 - Applicablo s PAGE B-8 of 12 REVISION: 23 DA'. ':: 12/28/92

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix B RADIOACTIVE WASTE / AUGMENTED HD" Chapter 1 - Applicable Cnaptor 2 - Applicablo Chaptor 3 - Applicablo Chapter 4- Applicable. Specification of quality assurance program requirements for suppliers waste / augmented D materials, equi of radioactive shall be on a case-by-case basis. pment and services Commercial grade or off-tho-shelf items may provido an acceptable level of quality based on the nature of the item. This determination shall be made jointly by Engineering and Quality Assurance personnel prior to issuance of procurement documents. 1 Chaptor 5- Applicablo Chapter 6- Applicable Chapter 7 - Applicable. Suppliers providing material, equipment and services for radioactive waste / augmented D shall be subject to source evaluation and surveillanco. The extent of imposition of these requirements shall be determined on a case-by-case basis by the design and quality assurance organizatiens responsible for review and approval of the procurement specifications. appropriate, Measures shall be established, as for examination of products- upon delivery. Chapter 8 - Not Applicable Chapter 9- Applicable to the qualification of welders welding procedures and , (ASME Section IX) for Radwaste/ Augmented "D" system. (prossuro 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 i PAGE B-9 of 12_ REVISION: _2]_,_ DATE; 12/28/92 c [

I lLLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL. Appendix B PACKAGING AND TRANSPORTATION OF RADI0 ACTIVE MATERIAL Chapter 1- Applicablo Chapter 2- Applicable { Chaptor 3 - Applicable, design activities are not normally performed by Clinton Power Station for radioactive matorial packaging however, audits of- suppliers establish that the design was accomplished under control of an NRC approved QA program. Chapter 4- Applicable Chaptor 5- Applicablo 1 Chapter 6- Applicable Chaptor 7 - Applicablo, measures such as sourco surveillance and ' audits of records should be taken as appropriato to ensure that the design and fabrication of- packaging woro performed under the control of - an NRC-approved. , QA program. Chapter 8- Applicablo Chapter 9 - Applicable, special processes such as. welding ~ or nondestructivo testing-are not normally performod.by Clinton Power Station. .However, if. packaging . ; requires major repairs necessitating uso of special ' processes, e.g., welding or heat treating, : measures shall be ostablished to ensure that the- special i processes are controlled. Chaptor lo - Applicable, visual inspections - shall be . performed upon recolpt of packaging to ensuro . compliance with cortificates of complianco. -

     -Chapter 11 -       Applicablo Chapter 12 -       Applicablo
     -Chaptor 13    .- Applicable,        all- . conditions    identifiod-      in . -a-cortificate .of- complianco when : using; packages shall y

be adhered'to. i Chapter 14 - Applicablo

1 1

PAGE D-11 of 12 REVISION: 23 '

                                                                     -DATE:     12n8/92 -

L , { , 'T .. -. .

ILLINOIS POWER NUCLEAR PROGRAM QUAllTY ASSURANCE MANUAL Appendix n Chaptor 15 - Applicablo Chaptor 16 - Applicable, measures are established for obtaining correctivo actions from suppliers and for onsuring that followup is documented to verify that correctivo actions were implomonted and offectivo. Chapter 17 - Applicable, records showing evidence of delivery of packages to a carrior and proof that all NRC and DOT requirements have boon satisflod shall also be retained. Chaptor 18 - Applicable, audits are performed on the supplier of packaging to ensure compliance with the cortificate of complianco. PAGE B-12 of 12 REVISION: 23 I DATE: _12/28/92 :. L Kmu. -, -- - . - - - - - - - - - - - - - - - - - - - - - + _--.-_-.--,-w_ - - _ _ _ - _

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix n RADIOACTIVE WASTE / AUGMENTED "D" Chapter 1- Applicable Chapter 2 - Applicable Chapter 3 - Applicablo 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 grado c or off-tho-shelf items may provido an acceptable level of quality based on the nature of the item. This determination shall be mado jointly by Engineering and Quality Assuranco personnel prior to issuance of procurement documents. Chapter 5- Applicablo chapter 6 - Applicable Chapter 7- Applicable. Suppliers providing material, equipment and services for radioactive wasto/ augmented D shall be subject to source evaluation and surveillance. The extent of imposition of those requirements shall be determined on a case-by-case basis by the design and quality assurance organizations responsible for review and approval of the procurement specifications. Measures shall be established, as appropriate, for examination of products upon delivery. Chapter 8- Not Applicablo Chapter 9- Applicable to the qualification of welders and welding procedures (ASME Section IX) for Radwaste/ Augmented "D" system. (pressure boundarios only). Chapter 10 - Applicablo only to inspection of those items and activities affecting Radwasto/Augmer.tod 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 l PAGE D-9 of 12 REVISION: 23 DATE: _.12/28/92 .

e., -

            ~ ILLINOIS POWER NUCLEAR PROGRAM-
 ., _          QUALITY ASS.URANCE MANUAL                   . Appendix _a-

. Chaptor 12- - Not Applica'blo

            ' Chapter 13 - -Applicable
                                                                                .j Chaptor 14--      Applicable nter 15 -' Applicablo~

r s 16.-- Applicable ; c.: ap r 17 - APflicable .

                           ~
             ^5     er 18 -
                                                                                 ~

Applicable p r t PAGE 'B-10 of 12 REVISION: 23 DATE:4 '17/28/92i-

ILLINOIS POWER NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL Appendix a 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 y Chapter 6- Applicable

n "

y 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.

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 i k PAGE B-11 of 12 REV1310N: 23 DATE: 12/28/92

g er, A

               -iC      ILLINOIS POWER NUCLEAR PROGRAM:
                      . QUALITY ASSURANCE MANUAL                                               ~ Appendb. a:               3
                                                                                                                           .i
                      -Chapter'15 --        Applicable
                      . Chapter 716
                                         --Applicable, measures are established for - obtaining .

corrective ~ actions from 1 suppliers . and for ensuring 2 ' that followup is documented - to - verify' that-corrective actions were impicmented and effec + 've. 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 - Applicabic, audits are performed on the supplier of. packaging to ensure complianceLwith the certificate of compliance. e t - # i l=

l. .

1. PAGE. E-12 of 12 REVISION: ~ 23

    .g                                                                                         .DATE:      12/28/92
    , ..                  _      .. .                                      .    . _                 _              .}}

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