ML20235N667

Rev 19 to Nuclear Program QA Manual

ML20235N667
Person / Time
Site:	Clinton
Issue date:	02/14/1989
From:	ILLINOIS POWER CO.
To:
Shared Package
ML20235N659	List: ML20235N667 U-601380, Forwards 890214 Rev 19 to Licensee Nuclear Program QA Program Manual, Per 10CFR50.54(a)(3)(ii)
References
NUDOCS 8903010324
Download: ML20235N667 (138)

Text

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IP NUCLEAR PRECRAM EUALITY ACOURANCE MANUAL TABLE OF CONTENTS i

(m TABLE OF CONTENTS lk Chaater Chapter

'> [N h (j l 4 t j

l Num'aer Title ,

y ,,

i List of Effective Pages ii Policy Statement lii Introduction iv Authorization  ;

y Glossary of Terms 1 Organization 2 Quality Assurance Program

? Design Control 4 Procurement Document Control 5 Instructions, Procedttres End Drawings 6 Document Control 7 Control of Purchased Material, Equipment and Services

)

8 Identification and Control of Materials, Parts and Components 9 Control of Special Processes I

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 f 17 Quality Assurance Records 18 Audits Appendix A Revisions to IP Uuclear Program Quality Assurance Manual Appendix B Supplemental Application - IP Nuclear Quality Assurance Program I

PAGE T of C i 13 REVISION: _.

FORM N OO-177 (10-88) 3010324 s90214 M.02172 p ADOCK 05000461 PNV =

. IP NUCLEAR [PR22 RAM GUALITY ACCURANCE MANUAL 73 L )

Date: November 30, 1988 NPS No, 1 Revision 3 Page 1 of I /

ILLINOIS POWER COMPAFY N

_UCLEAR POLICY STATEMENT Quality Assurance The Illinois Power. Company (IP) Nucicar Quality Assurance Program has been developpd by IP to assure that . operation and associated activities which affect the safety related functions of the Clinton Power Station (CPS) era conducted in a safe and reliable manner in compliance with the Code- cf Federal Regulations (10CFR50, Appendix B): the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Section XI): and other applicable regulations, codes, ancf standards. Control and verification requirements specified in.

the IP Nuclear Program Quality Assurance Manual are to be applied by IP organizations and contractors participating in CPS operational activities. The required personnel and resources are to be provided to assure that the quality' assurance (QA) program is adeq!tately planned, implement 6d, and managed.

The Manager-Quality Assurance is responsible for establishing and maintaining the IP Nucicar Program Quality Assurance Manual. IP Managers and Directore are responsible for implementing the quality assurance program in accordance with the re uirements conveyed in this manual according to their assigned unctional

- /O responsibilities. The Manager-Quality Assurance has the

() organizational freedom from cost and scheduling considerations tot identify quality problems, racommend solutions, verify implementation of the solutions and control: processing, delivery, installation, or utilization of nonconforming items until propsr dispositioning has occurred.

k' hen concerns related to quality matters are not satisfactorily resolved with innediate supervision, personnel have direct access to the next higher level of management in the organization. If concerns are still not satisfactorily resolved, personnel have direct access to me for final resolution in accordance with applicable codes ar.d standards.

Anycne that intimidates or interferes with any person performing Quality Assurance functions shall be subject to disciplinary -

action. Intimidation may take many forms ranging from verbal abuse to physical harm.

Personnel subject to real or perceived acts of intimidation or interference have direct access to the Executive Vice President, who has the authority and responsibility to take appropriate disciplinary action.

APPRO 'D M ,

Chairmat. and Presidenti  !

PAGE ii REVISION: 4 1

3 FORM N100-177 (10-88)

H.02l72 l i

IP NQCLEAR PROZRAM QUALITY ACOURANCE MANUAL LIST OF EFFECTIVE PAGES l

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\~# LIST OF EFFECTIVE PAGES Revision 19

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The following pages and their indicated revision and date of issue are included in the IP Nuclear Program Quality Assurance Manual. j l

Page No. Rev. Date T of C 13 2-14-89 i-1 19 2-14-89 ii 4 2-14-89 iii 15 2-14-89 iv-1 19 2-14-89 v v-10 15 2-14-89 1 1-14 19 2-14-89 2-1-- 2-6 18 2-14-89 3-1 - 3-5 16 2-14-89

,/~T 4-1 - 4-3 15 2-14-89 5-1 - 5-2 16 2-14-89 6-1 - 6-4 16 2-14-89 7-1 - 7-5 15 2-14-89 8-1 - 8-3 14 2-14-89 2-14-89 9-1 - 9-4 16 10-1 - 10-3 15 2-14-89 11-1 - 11-3 14 2-14.-89 12-1 - 12-3 15 2-14-89 13-1 - 13-3 14 2-14-89 14-1 - 14-3 14 2-14-89 15-1 - 15-5 16 2-14-89 16-1 - 16-3 15 2-14-89 17-1 - 17-4 17 2-14-89 18-1 - 18-3 16 2-14-89 A-1 14 2-14-89 B B-11 13 2-14-89 Oh PAGE i-1 Of 1 C REVISION: 19 FORM NIDO-177 (10-88)

M 02172 I

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[ . IP NUCLEAR PRO RAM CUALITY AOCURANCE MANUAL INTRODUCTION

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• INTRODUCTION Illinois Power Company (IP), as principsl owner of Clinton Power Station (CPS), has ultimate responsibility for the quality assurance program which is applied to CPS. .

I'he 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;" and the American National Standard ANSI N18.7 (1976), " Administrative Controls and Qualit for che Operational Phase of Nuclear Power Plants'y Assurance The IP Nuclear Quality Assurance Program applies to those activities associated with or affecting the ability of the plant's structures, systems, and components to function in preventing, or mitigating the consequences of, postulated acci-dents which could cause undue risk to the health and safety of  ;

the public. These e.ativities include operating, maintaining, repairing, refueling, modifying, and other associated activities such as radiological and environmental monitoring, radioactive

, material packaging and shipping, fire protection, and security

( programs. The structures, systems, and components to which the N- activities and programs apply are delineated in Table 3.2-1 of the Updated Safety Analysis Repoli (USAR).

This manual is arranged in eighteen chapters which corre-spond with the eighteen criteria contained in 10CFR50 Appendix B  ;

and 10CFR71 subpart H. Each chapter is further broken down into three main sections which describe the purpose and scope of that chapter, a description of. the quality program, and the division of responsibilities. The Quality Assurance organization approves the distribution and is responsible for the maintenance of this manual in accordance with approved departmental procedures. Each manual holder is responsible for maintaining his copy updated in accordance with Appendix A.

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

k PAGE iii-1 of 1 REVISION: 15 FORM N100-177 (10-88)

M.02172

IP NUCLEAR PRG2 RAM

'C;UALITY AOCURANCE MANUAL AUTHORIZATION AUTHORIZATION The IP Nuclear Quality Assurance Program applies to every menber of the Company performing work related to CPS and covered by the Manual. Specific responsibilities shall be assigned by IP management and supervision, consistent with the requirements described in this Quality Assure.nce 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 e f fe c tiver.e s s , 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.

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l Approved: ,

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Mannger - Qualisty Assurance

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! PAGE iv - 1 of 1 REVISION: lo  ;

DATE: .2-14-89 FORM NIDO-177 l10-88)

M.02172 l l' L________-_- _ . - - .

l IP NUCLEAR PRERAM 1 CUALITY ACCURANCE MANUAL GLOSSARY OF TERMS

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_3 GLOSSARY OF TERMS Acceptance Criteria - Specified limits placed on characteristics of an item, process or service defined in codes, standards or other requirement documents.

Audit -

A documented act.vity d

performed in accordance with written procedures or checklists to verify, by examination and evaluation of objective ev'dence, 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 Agency (AIA) - An agency designated as such by the appropriate legal authority of a State or Municipality of the United States or a Province of Canada or an insurance company authorized to write boiler and pressure vessel insurance in that jurisdiction.

Authorized Nuclear Inservice Inspector (ANII) An authorized

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V Nuclear Inservice Inspector is an employee of an Authorized Inspection Agency who meets the requirements of ANSI N626.1<1975.

Certification - The act of determining, verifying and attesting in writing to the qualifications of personnel, processes, proce-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.

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

Certified Test Report - A written and signed document approved by 1 a qualified party that contains sufficient data and information to verify the actual properties of items and the actual results of all required tests.

Characteristic - Any propW-ty or attribute of an item, process or l

service that is distinct, describable and measurable, as conform-j ing or nonconforming to specified quality requirements. Quality n)

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IP NUCLEAR PROGRAM CUALITY A00URANCE MANUAL GLOSSARY OF TERMS p

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

Chemical Cleaning -

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

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

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

Condition Adverse to Quality - An all inclusive term used in reference to any of the following: failures, malfunctions, deficiencies, deviations, defective items and nonconformances.

Control Stamp - A stamp used to mark a unique identification of

(,) inspection er test status upon items, tags, labels, routing cards V or records traceable to an item. Control stamp impressions clearly identify the person who applied it such that traceability ,

to their authorization is provided.

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

Corrective Action - The action required to correct or resolve l 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 Instructions - Procedures or instruc-tions approved and issued within a department which provide detailed direction to personnel.

Deviation - A nonconformance or departure of a characteristic from specified requirements.

t l ( PAGE v-2 of 10 REVISION: in FORM NIDO-177 (10-88)

M.02172 l

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IP NUCLEAR PRECRAM CUALITY AOCURANCE MANUAL GLOSSARY OF TEP.MS

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Documents - Collective term used to describ5 all written or aictorial information that directs or shows how an activity is to

>e accomplished. Documents include, but are not limited to, drawings, procedures, instructions and changes thereto.

Documentation - Any writter. 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 deter-mined by :uch investigation. Examination is usually nondestruc-tive and includes simple physical manipulation, gaging and measurement.

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 orga-nizational structure.

Facility Review Group -

(FRG) -

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

V Follow-ua -

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.

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

Independent Review -

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

Inservice Inspection -

A mandatory program of examinations, testing, inspections and control of apairs and replacements to ensure adequate safety in maintaini- >he nuclear power plant and to return the plant to service in 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

/O PAGE v-3 of 10 l (-) REVISION: 1g FORM Nt00-177 (10-88)

DATE: 2-14-89 H.02t72

IP NUCLEAR PR30 RAM

( GUALITY AOCURANCE MANUAL GLOSSARY OF TERMS 1

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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 7 called an " interface" relation. One example of interface is when one organization must perform a step which is a prerequisite tc another organization accomplishing its function. Interface con also mean that several organizations accomplishing similar activi ties are under the coordination control of one organiza-tion.

Internal Audits -

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

IP - 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-7 tive action.

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Measuring and Test Ecuipment - 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.

Noncompliance - A failure to comply with a regulatory require-ment.

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

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

O PAGE v 4 of 10 REVISION: 75 _

FORM N100-177 (10-88)

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IP NUCLEAR PROSRAM FUALITY ACOURANCE MANUAL CLOSSARY OF TERMS  ;

i r3 V Objective Evidence -

Any statement of fact, information~ or {

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record, either quantitative or qualitative, pertaining to the l quality of an item or service bcaec on observations, measurements or tests which can be verified.

Operable - Operability - A system, subsyatem, train, compcnent or device shall be operable or have operability when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or ,

seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s). NOTE: Safe operation of the plant  ;

is determined by CPS licensed operators.

Permanently Installed Instrument and Control Devices -

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

Plant Staff - That organization which is directly responsible for the operation of the Clinton Power Statien. The Plant Staff includes operations, technical, maintenance, radiation protec-tion, chemistry, radwaste and support departments. i V Procedure - A document that speedfies 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 bLnding 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 itens 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.

Qualification - (Personnel) - The characteristics or abilities i 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 l component will perform satisfactorily in service.

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

PAGE v-5 nf 10 REVISION: 75 DATE: 2-14-89 i FORM N100-177 (10-88) j M.02172 1 l

I IP NUCLEAR PR2SRAM CUALITY ACCURANCE MANUAL GLOSSARY OF TERMS pJ 1.__._

Quality Control - Those quality assurance sctions which provide a means to control and measure the characteristics of an item, process or facility to established 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, chat 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).

Regulations. - Collective term used to describe the governing j directivec ~ 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 affecting safety. The resolution may contain controls or limitations that are to apply until the nonconformance is fully corrected.

Rework - The process by which a nonconforming item is made to conform to prior specified requirements by completion, 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 ab-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 Category 1, Safety Class 1, 2, 3, "Other" and Electrical Class 3E as identified in the USAR Section 3.2. {

l Scope - The area covered by a given activity or subject. i PAGE v-6 of 10 REVISION: 25 )

1 DATE, 2-14-89 FORM NdGO-177 (10-88)

M.02t72 l

IP NUCLEAR PR2 CRAM ,

CUALPTY AOCURANCE MANUAL CLOSSARY OF TERMS O

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1. - Seismic Classification - Plant structures, systems and components  ;

important to safety which are designed to withstand the effects of a safe shutdown earthquake (SSE) and remain functional if they i are necessary to assure:

a. The intcgrity of the reactor coolant pressure boundary, Or

b. The capability to shutdown the reactor and maintain it in a safe condition, or

c. The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10CFR100.

Plant structures, systems and components, including their founda-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.

Significant Condition Adverse to Quality and/or Safety -

A .

Fondition that affects or is likely to have an effect on, or I influence, the safe operation of the ' plant , the capability to (V) shut down the reactor and maintain it in a safe shutdown condi-tion or the capability to prevent or mitigate the consequences of accidents which could result in potentisl off-site exposures.

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

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 methed of implementing or performing an activity or an item of known value used for comparison.

Ptop Work - Collective term used to descrfbe the following three (3) levels of stopping work activities:

PAGE V-7 of 10 l FORM N100-177 (10-88) l M.02172

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.lP NUCLEAR PR2 CRAM I CUALITY ACEURANCE MANUAL GLOSSARY OF TERMS I p)

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a.

- 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. i l

c. A Stop 1Jork Action initiated by the Manager - Quality j Assurance.

Supplier - Ar.y individual or organization that furnishes items or services to IP under a procurement document.

f Surveillance - A review or observation of an activity , process or l' product to verify that an action has been or is being accom-plished in accordance with applicable requirements.

Survey - A dochmet.ced evaluation of an organization's ability to perform activities as verified by a determination of the adequacy of the organization's quality program and by a review of the implementation of that program at the location of work.

System Safety Classifications e Structures, systems and compo-nents are cTassified as Safety Class 1, Safety Class 2, Safety

. Class 3, Safety Class Other or Class lE in acccrdance with the

/ importance to Nuclear Safety. Equipment is assigned a specific b) safety class, recognizing that components within a system may be of differing safety importance. Definitions of the various Safety Classes are:

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

Safet'y 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, I

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FORM NIDO-177 (10-88) J M.02172

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.lP NUCLEAR PRFORAM QUALITY ACCURANCE MANUAL GLOSSARY OF TERMS o _

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f. Removing residual heat from the reactor and reactor core, or

g. Storing spent fuel.  !

Safety Class 3 - Structures, systems and components that are iiot 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. l Safety Clas s ,"Other" - Structures, systems and components used in the- power conversion or other portions of the facility which have no direct safety fonction, but which may ~

4 be connected to or influer.ced by the equipment within the Safeny 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

, , . materia) to the environment.

(v )

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

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.

I 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-sion in accordance with 10CFR50.71.

Use-As-Is - A disposition which may be imposed for a nonconfor-mance when it can be estchlished that the discrepancy will result in no adverse conditions to safety and that the item under consideration will continue to meet all engineering functional requirements including performance, maintainability, fit and safety.

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IP NUCLEAR PROGRAM QUALITY AOCURAPJCE MANUAL Gl.0SSARY OF TERMS I Verification - The act of confirming, substanti'ating cr assuring that an activity or condition has been implemented in conformance with the specified requirements.

Verification / inspection Point -

A point in a procedure or work ,

document at which the performer is required to notify Quality j Verification (QV) in order to plan when they will perform the l  !

verification activity. A Verification / Inspection Point shall be capable of being verified after work completion.

Wittiess Point - Point in a procedure or work document at which i the performer is required to stop and notify QV to allow for I platined inspections . Once notification has been accomplished and the agreed to time (or a reasonable amount of tirce) has passed, I the work . activity may continue. i l

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IP NUCLEAR PRO 2 RAM QUALITY AOCURANCE MANUAL l[l h CHAPTER V .

1 ORGANIZATION APPROVED BY: MANAGER-0UALITY ASSUR NCE . e ///MU 1.1 PURPOSE / SCOPE To define the requirements for and to describe the establishment of an organizational structure, functional responsibilities and levels of authority concerning the performance of activities which affect the safety-related functions of structures, systems, l or components for the Clinton Power Station.

1.2 DESCRIPTION

1.2.1 Ganeral

( ) Organizational structuring and functional responsibility assign-k/ ments are based on recognition of quality assurance as an inter-disciplinary function with quality-related activities being per-formed 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 author-ity and organizational freedom from cost and scheduling considerations to: identify qualitf problems; recommend solutions; verify implementation of the solutions; and control:

processing, delivery, installation, or utilization of j 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 approved by the Manager - Quality Assurance for QA program requirements. The CNPs are approved for use by the IP corporate efficer(s) responsible for the activities covered by the CNP. Corporate Nuclear Procedures require the development and use of departmental procedures or instructions to describe l

interfaces and accomplish the activities covered by the CNP.

f' k 1 f 14 l PAGE REVISION: 19 ,

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M.02171 L

IP NUCLEAR PROORAM QUALITY AOOURANCE MANUAL CHAPTER 1 r3 V The organizational structure and functiona'l responsibility assignments are such that: (1) attainment of quality objectives )

is by individuals assigned responsibility for specifying quality i or performing work to specifications; (2) verification of con- ,

formance to established quality requirements is by those who do l not have direct responsibility for specifying, producing, or I expediting products; and (3) personnel in key quality assurance functiois have direct access to responsible management.

Speciff Quality Assurance activities (job duties and respon-sibilities) have been identified for each section within the QA department and are based on the amount and type of activities conducted. Staffing levels are established so that the work can be accomplished in a manner supportive of plant operations and~

outages. Further, once a year the QA department manning levels are reassessed and personnel levels are revised as necessary to assure adequate and timely coverage of QA activities. This review permits recruiting and training activities to be carried out in such a manner as tc provide trained Quality Assurance personnel necessary to assure the quality of the work. Quality Assurance personnel are free from non-QA duties and provide full attention to assuring the effective implementation of the QA program. Effectiveness of the program is assured by Quality j Assurance department participation in the work planning, through i surveillance and audits, by the authority of Quality Assurance k personnel to stop specific work activities where it appears that quality may be jeopardized, and the authority of the Manager -

Quality Assurance to initiate a Stop Work Action. The Manager -

CPS has the at.thbrity to bypass a stop 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 emergencies, inspections may be performed without written pr6cedures.) 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 s verification / inspection witness, and hold points. In addition, designated QA personnel regularly attend and participate in planning, echeduling and status meetings during testing, operation.s and outages to assure (1) they are kept abreast of day-to-day projected work assignments throughout the plant and (2) that the necessary QA inspection l controls, acceptance criteria, procedural controls and qualified QA staffing is available to properly carry out the assigned tGSks. ,

l f3 yd PAGE 2 of 14 REVISION: la ,

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1.2.2 Organization and Responsibilities '

This section describes the organizational structure and individu- )

al responsibilities within IP for taan. aging and implettenting the l QA program for the operation of the CPS. Figure 1-1 shows the L organizational structure and relationships of individuals and ]

departments within 1P with management responsibility for perform-ing quality-related activities.

1.2.2.1 Chairman and Pr'esident The Chairmsn md President of IP has the overall responsibility j for the engin'ering, design, procurement, modification, testing, '

opc: ration on0 oaality assurance at CPS. Execution of these responsibilities is delegated to two Executive Vice Presidents.

1.2.2.2 Executive Vice President An Executive Vice President is responsible for the overall effec-tiveness of the Quality Assurance program and is responsible for establishing the quality assurance policies, goals and obj ec-tives. The responsibilities to establish and maintain the IP Nuclear Quality Assurance ?rogram as well as testing, startup, operations, nuclear support and engineering are delegated to a A Vice President. The Erecutive Vice President is also responsible V for assuring that annual management reviews are conducted and documented on the status, adequacy and effectiveness of the overall QA program. The Executive Vice President shall retain the responsibility for assuring that the authority and inde-pendence of Quality Assurance personnel are such that they can effectively assure the conformance to quality requirements and are independent of undue influences and responsibilities for schedule and costs.

1.2.2.3 Executive V1.ce President An Executive Vice President is responsible for quality-related activities associated with environmental affairs. The responsi-bility to establish and maintain procedures which support the 1P Nuclear Program on safety-related matters has been delegated to a Vice President.

1 1.2.2.4 Vice President A Vice President has been designated as the corporate officer responsible for the overall direction of the IP Nuclear Quality Assurance Program; the testing, nuclear support activities (including purchasing), licensing and safety, engineering and f 14 V) PAGE 3 REVISION: 19 (10-88)

DATE. 2-14-89

{ FORM NIDO-177 N.02172

L IP NUCLEAR PRSCRAM GtUALITY AOCURANCE MANUAL CHAPTER 1 pv operation of Clinton Power Station. He reporJs to an Executive Vice President and has direct access to the President.

1.2.2.5 Vice President A Vice President has been designated as the corporate officer responsible for thosa activities associated with environmental affairs. The designe.ted Vice President reports directly to an Executive Vice President. He has del.ega t ed this responsibi'ity to the Manager - Environmental Affairs.

1.2.2.6 Assistant Vice Presidant The Assistant Vice President reports to the Vice President and is responsible for assuring safe, efficient and reliable operation of the Nuclear Training, Scheduling and Outage Management and Clinton Power Station organizations.

I 1.2.2.7 Menager - Clinton Power Station The Manager - Clinton Power Station reports to the Assistant Vice l President and it responsible for the safe, reliable and efficient operation of the Clinton Power Station in accordance with the  ;

-s operating license. This includes ensuring that the IP Nuclear Quality Assurance Program, as described in subsequent sections of

[4} this manual, is incorporated in plant procedures and implemented

• by the Clinton Power Station organization.

1.2.2.8 Manager - Nuclear Station Engineering The Manager - Nuclear Station Engineering reports to the Vice President and is responsible for the developmen,t, direction and overall coordination of power plant engineering activities per-formed by the Nuclear Station Engineering Department (NSED) for the Clinton Power Station. These responsibilities include: the preparation of specifications and drawings for the accomplishment of new designs, design changes and modifications; design inter-pretation; the conduct of design checks and reviews; technical evaluation of suppliers; ensure compliance with the ASME Code and other codes and standards; control of examination and inspection of ASME components; and coordinate all interface with the Authorized Inspection Agency (AIA), including provisions for the establishment of ANI hold / witness points and access to facilities and records . The Manager - NSED ensures that these activities are performed in accordance with the requirements of the IP Nuclear Quality Assurance Program.

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- . - - - _ - - - - - - - -_ _ _ _ _ _ . _ _ _ _ ]

IP NUCLEAR PRO 2 RAM GUALITY ACOURANCE MANUAL CHAPTER 1 V 1.2.2.9 Manager - Nuclear Planning and Support The Manager - Nuclear Planning and Support reports to the Vice President and is responsible for human resources, records manage-ment, information services, materials management, budgeting, site accounting and program planning. The Manage * - Nuclear Planning and Support ensures that these activities are performed in accordance with the requirements of the IP Nuclear Quality Assurance Program.

1.2.2.10 Manager - Environmental Affairs The Manager - Environmental Affairs reports to a Vice President and is responsible for providing technical support and assistance for ensuring that Clinton Power Station operations meet estab-lished guidelines and regulations regarding the plant's radiological and non-radiological effects on the environment.

1.2.2.11 Nuclear Review and Audit Group The Nuclear Review and Audit Group (NRAG) reports to the Vice President and is responsible for the independent review function.

The NRAG functions in accordance with a written charter which delineates committee composition, responsibility and authority, subjects to be reviewed, reporting requirements and administra-V tive controls under which the group operates.

1.2.2.12 Facility Review Group An on-site committee whose function is to advise the Manager -

Clinton Power Station on matters related to nuclear safety.

1.2.2.13 Manager - Nuclear Training l The Manager - Nuclear Training reports to the Assistant Vice l President and is responsible for the direction and management of the Nuclear Training for Clinton Power Station. Duties include developing training standards, providing centralized training, ]

providing education support to Nuclear Managers / Directors and maintaining operation of the simulator. The Manager -

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

1.2.2.14 Manager - Quality Assurance The Manager - Quality Assurance reports to the Vice President and l

has direct access to an Executive Vice President. The Manager -

l Quality Assurance is responsible for IP's overall Quality Assur-PAGE 5 of 14 REVISION:_ 10 FORM N100-177 (10-88)

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l IP NUCLE AR PROORAM l QUALITY AQOURA'NCE MANUAL CHAPTER 1 I L

O ance program definition, direction, evaluati.on and approval, including the IP Nuclear Quality Assurance Program. The Manager 1

- Quality Assurance directs the Quality Assurance departmental i' activities related to the design, procurement, maintenance, modification, and operation of the Clinton Power Station. The Manager -

Quality Assurance interfaces with the Nuclear Regulatory Cornmission, and the Authorized Inspection Agency for the Quality Assurance Program. The Manager -

Quality Assurance

! or the designated alternate has the responsibility and authority to stop unsatisfactory work during plant operation, as well as during plant modification, maintenance and in-service inspection periods, provided the health and safety of the public, or impact on capability to safely operate or shut down the plant are not f' adversely affected.

The qualifications of the Manager - Quality Assurance are at least equivalent to the education and exoerience requirements of Section 4. 4. 5 of ANSl/ANS 1,1-1978, " Selection and Training of Nuclear Power Plant Personnel", Specifically, the Manager -

l Quality Assurance 'ill meet at least one of the following:

3

1. At the time of initial core louding, nr assign-ment tc the active position, the responsible person shall have six yWre experience in the h

V field of operating quality assurance, preferably at an nuclear power plant, or operations supervisory exf>eria.m e. At least one year of this six years experience shall be nuclear power plant experience in the overall implementation of the quality assurance program. (Thir experience shall be obtained within the quality assurance organization.) A minimum of one. year of this six years experience shall be related technical or academic training. A maximum of four years of this six years experience may b t. fulfilled by related technical or academic trainings or,

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

EXPERIENCE: At the time of initial core 1.oading or appointment to the activo position, the responsible person shall have four (4) years experience in the field of quality assurance, or nquivalent number of years of nuclear plant experience in a supervisory position, preferably at en operating nuclear plant, or a combination "

of the two. At least one (1) year of this four years experience shall be nuclear power plant

( PAGE 6 of 14 REVISION: lo l FORM NIDO-177 (10-88)

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(

I IP NUCLEAR.PRIORAM i

UALITY ACCURANCE . rAANUAL CHAPTER 1 l

1

/G , i Q) exper2.ence in the implementation of the quality assurance program. Six (6) months of the one year experience shall be obtained within the quality assurance organization. He must possess a thorough working knowledge of 10CFR50 Appendix B, ANSI N45.2, ANSI N18.7, familiarity with the ASME Boiler and Pressure Vessel Code end other I

applicable regulations, codes and standards.

1.2.2.14.1 Director - Quality Systems & Audits The Director - Quality Systems & Audits reports to the Manager -

Quality As6urance and is responsible for providing direction and administration of the Quality Systems and Audit's staffs in defining, establishing and verifying compliance with the IP Nuclear Quality Assurance Program. In eddition, the Audit staff is responsible for verifying the qualification of suppliers and assuring procurement documentation is acceptable.

1.2.2.14.2 Director - Quality Engineering & Verification The Directcr - Quality Engineering & Verification reports to the Manager - Quality Assurance and is responsible for direction and g management of the Quality Engineering and Quality Verification staffs for defining, establishing and verifying compl:tance with t,vJ the IP Nuclear Quality Aswrance Program.

1.2.2.14.3 Director - Operations Monitoring Programs The Director - Operations Monitoring Programs reports to the Manager - Quality Assc.rance and is responsible for providing management and implementation of the Operations Monitoring Program that supports tae safe and reliable operation of CPS.

1.2.2.15 Manager - Licensing and Safety The Manager - Licensing and Safety reports to the Vice President and is directly responsible for providing representation and interface with regulatory agencies to maintain operating licenses 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 ren ews and studies, perform safety studies and analyses, conduct of Independent Saf ety Evaluation Group (ISEG) efforts for significant operating data, provide representation to safety groups, support of the Nuclear Review and Audit Group (NRAG), management of the Emergency Preparedness Program, and the administration of tracking program fcr 10CFR21 items. The Manager - Lice.nsing and Safety ensures that these activities are A

V PAGE 7 of 14 REVISION: ,

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iP NUCLEAR PRECRAM .

QUALITY AO'2URANCE MANUAL CHAPTER 1 p

( performed in accordance with the requirements of the IP Nuclear Quality Assurance Program, 1.2.2.'6 Manager - Scheduling and Outage Management The Manager -

Scheduling and Outage Management reports to the Assistant Vice President and is responsible for management of the Scheduling and Outage Management Department personnel and resources. 'The Manager -

Scheduling and Outage Management develops schedules as required to support Nuclear Program Departments. He coordinates the planning, scheduling and preparations for plant outages and manages and directs the Maintenance Support Contractor and outage contractors. The Manager - Scheduling and Outage Management ensures that these activities are performed in accordance with the requirements of the IP Nuclear Quality Assurance Program.

1.2.2.17 Director - Nuclear Program Assessment Group The Director -

Nuclear Program Assessment Group reports to the Vice President and is directly responsible for coordinating Institute of Nuclear Power Operations (INPO) Programs, assessing nuclear programs and plant operations, conducting oversight on c radiological protection, radioactive waste and chemistry pro-( grams, and other special assignments from the Vice President.

1.2.3 Quality Assurance Department 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 include, but are not limited to, the following: '

a. Prepare and control the IP Nuclear Program Quality Assurance Manual.

b. Verify the implementation of the IP Nuclear Quality Assurance Program.

c. If significant quality problems are identified, QA personnel have the authority and responsi-bility to stop specific work activities pending satisfactory resolution of the identified prob-lem, 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.

d. Verify that quality-related training programs are developed and implemented for each company A

l U PAGE 8 of 14 REVISION: lo i

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IP NUCLEAR PRSERAM CUALITY ACCURANCE MANUAL CHAPTER 1 l

l department that has responsibility for in.plement-ing the IP Nuclear Quality Assurance 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, practices and experiences throughout the nuclear power industry.

g. Develop and implement an audit, surveillance and inspection program for quality-related activities within the scope of the IP Nuclear Quality Assur-ance Program and routinely advise management of the status of program implementation. Initiate and/or verify corrective action, as necessary, to resolve conditions adverse to quality.

h. Perform acceptance inspections related to activ-ities during startup, operation and maintenance of CPS.

1. Review the QA programs of suppliers for compli-g)

ance with regulatory requirements and the re-L quirements of the IP Nuclear Quality Assurance Program when a program is required to be submitted by the procurement document. Ensure that supplier QA program deficiencies are cor-rected.

j. Review all changes to the USAR, .with the excep-tion of Chapter 16, Technical Specifications.

k. Perform trend analysis for detecting trends adverse to quality.

1.2.3.1 Quality Engineering Section The Quality Engineering Section is supervised by the Supervisor -

Quality Engineering who reports to the Director - Quality Engi-neering & Verification. The Quality Engineering Section assures documents, including on-site supplier documents, involving the following activities conform to the applicable QA program re-quirements of regulations, standards, codes and other specific commitments: Operations, Maintenance, Plant Support, Technical, Chemistry, Radioactive Waste, Radiation Protection, Fire Protec-O (j PAGE 9 of 14 REVISION: lo l

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IP NUCLEAR PREGRAM CUALITY ACOURANCE MANU'AL CHAPTER 1 jy -

l This' section performs tion, Securit{ication, quality veri Modifications planningand forTesting.

these activities, as appli-cable.

If significant quality problems are identified that warrant immediate action, Quality Engineering Section personnel have the authority and responsibility to stop the specific work activity l pending satisfactory resolution of the identified problem, ,

providad the health and safety of the public or impact on the  !

capability to safely operate or shut down the plant are not adversely affected.

1.2.3.2 Quality Verification Section The Quality Verification Section is supervised by the Supervisor Quality Verification who reports to the Director - Quality Engineering & Verification. The Quality Verification Section is responsible for scheduling, conducting and reporting the appli-cable inspection, verification, surveillance and nondestructive examination of quality-related items, processes, . functions and activities associated with operations, testing, main.tenance, modification, nuclear fuel, receipt, receipt documentation, and plant support activities performed by IP which affect quality.

The Quality Verification Section is alao responsible for initiating reports of nonconforming it. ems or conditions

(

discovered during inspection activities. The section is respon-sible for advising management as to the effectiveness of quality assurance program implementation for those specific functions surveilled.

If significant quality problems are identified that warrant immediate action, Quality Verification Section 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 safely operate or shut down the plant are not adversely affected.

1.2.3.3 Quelity Systems Section The Quality Systems Section is supervised by the Supervisor -

Quality Systems who reports to the Director - Quality Systems &

Audits. The Quality Systems Secticn is responsible for period-ically assessing departmental effectiveness in implementing the IP Nuclear Quality Assnrance Progrnm, trending of conditions adverse to quality, coordination of Quality Assurance reviews and  ;

approvals or QA program requirements associated with the USAR, IP Nuclear Program Quality Assurance Manual and Corporate Nuclear 10 of 14

/]

C PAGE REVISION: 19 FORM N100-177 (10-88)

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IP NUCLEAR PRECRAM OUALITY AOCURANCE MANUAL CHAPTER 1 OV

, Procedures, and advising management on matters related to l establishment of quality programs and procedures for Clinton Power Stacion. 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 Nuclear Quality Assurap.ce Program, such as the IP Nuclear Program Quality Assurance Manual and QA departmental procedures. The Quality Systems Section coordinates l QA reviews and approvals of QA program requirements associated with the procedures of other Nuclear departments supporting Clinton Power Station, including, but not limited to: '

Nuclear Training Department, aclear Station Engineering Department, Nuclear Planning & Support Department, Licensing & Safety Department, Scheduling & Outage Management Department, and Nuclear Programs Assessment Group.

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 saciefactory resolution of the identified problem, provided the health and safety of the public or impact on the cepability to safely operute 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 - Quality Systems & Audits. The Audit Section is responsible for the planning of internal and external IP audits. The Audit section assures that procurement documents contain the QA requirements of the USAR, evaluates suppliers' QA programs for meeting the USAR commitments, performs audits and surveys at suppliers' facilities, processes procurement related nonconformances, and performs source surveillance. The section ensures timely and responsive corrective action to IP audit findings and advises management as to the effectiveness of Quality Assurance program implementation for those specific functions audited.

If significant quality problems are identified that warrant immediate action, Quality Audito Section 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 pubidc or impact on the capability to safely operate or shut down the plant are not adversely affected.

PAGE - 11 of 14 REVISION: 10 FORM NIDO-!77 (10-88)

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IP NUCLEAR PROCRAL1 CUALITY ADOURANCE MANUAL. CHAPTER 1 i

P

)

2 U 1.2.4 Organizational Interfaaes Activities affecting the quality of safety-related systems, serurtures and components are performed by, or under the cogni-zance 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 / certified, and these work activities are performed to the same (or similar) proceduras and instructions. Problems associated with meeting the require-ments of the Quality Assurance program, or disagreements and/or disputes between members of those organizations shall be brought to the attention of appropriate levels of management, including the Chairman and President, as necessary to obtain resolution.

Work may be delegated to qualified outside organizations by contract for such activities as design, special processes, inspections, etc. Selected work may be delegated to qualified outside organizations by the Nuclear Station Engineering Depart-ment, CPS P1Lnt Staff and the Quality Assurance department. The responsibility for exercising engineering control rests with Nuclear Station Engineering, operational controls with CPS Plant Staff and qualicy assurance with the Quality Assurance depart-ment. Prior to initiation of work, the qualified individual (s) or organizational elements within IP have their responsibilities

(*

A identified for the control and quality of delegated work.

1.2.5 Clinton Power Station Organization ,

FIGURE 1-1 illustrates Clinton Power Station organizations having I

QA program responsibilities and interfaces.

l FIGURE 1-2 illustrates the Quality Assurance. Organizational Chart.

1 I I

O v

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IP NUCLEAR PRSCRAM lM1 CUALITY ACCURANCE MANUAL

?l CHAPTER V .

2 QUALITY ASSURANCE PROGRAM

- e APPROVED BY: MANAGER-OUALITY ASSURANC.E rd' M Y f 87

/

2.1 PdRPOSE/ SCOPE The IP Nuclear Quality Assurance Program applies to those activities such as design, procurement, fabrication, installation, modif?. cation, maintenance, repair, refueling, operation, in-spection, and tests related to those systems, structures, and ccmponents aa identified by the letter "B" or "H" in the Quality .

Assurance Requirements column in USAR Table 3.2-1. This table of systems, structures, and components is kept current sud 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, I such as the pressure boundaries of rac' waste augmented D systems, k portions of the fire protection system, securit.y system, environ-mental monitoring, and package and transportation of radioactive material.

2.2 DESCRIPTION

2.2.1 General Illinois Power Company'c Nuclear Qnality Assurance Program is based upon 10CFR50, Appendix B, "Qsality Assurance C:iteria for Nuclear Power Plants nnd /uel Reprocessing Plants." The require- J ments of 100FR71, subpart H, " Quality Assurance for Packaging and  !

Transportation of Radioactive Material" sre aloo included. l Addit ion".11y , in USAR section 1.8, Illinois Power is committed to )

carrying out the provisions of various NRC regulatory guides and I industry ctandards which further define Quality Assurance program j As used in this chapter, "Ouality Assurance" requirements.

comprises all thoce planned and systematic actions necassary to provide adeauate confidenca that a Clinton Power Station strue-ture, system, or component will perform satisfactorily in service. ]

Quality Assurance includes qualit" control which comprises those O 1 PAGE 1 of 6 RW ISION: in FORM N100-176 (10-88) -

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IP NUCLEAR PRECRAM l QUALITY AOCURANCE MANUAL CHAPTER 2 physical characteristics of a material, struct'ure, componene, or system which provide a means to control the quality of the materi-al, structure, component, or system to predetermined requirements.

2.2.2 Quality Assurance Program Implementation The IP Nuclear Quality Assurance Program was implemented as systems, structures, and components were turned over or transferred to IP. A Freoperational 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 receives ongoing reviews and is revised in accordance with Appendix A as necessary to assure its continued effectiveness. Changes made to the IP Muclear Program Quality Assurance Manual which: 1) change or affect authority, independence, or management reporting levels previously Is established for organizations performing quality assurance func-tions; 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 Manus 2 changes which do not reduce the Quality Assurance program's commi.tments 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 100FR50.54(a). The change

.submitts1 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 j criteria of 10CFR50 Appendix B and the Safety Analysis Report quality assurance program description commitments previously accepted by the NRC.

2.2.3 Quality Assurance Program Documentation The IP Nuclear Quality Assurance Program is established and supported by three tiers of documents; each successive tier transmits requirements from a higher level of authority to the next successive lower document level. l 3 PAGE 2* ef_6 f

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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ __ ______..____.______J

1P NUCLEAR PRECRAM.

CUALITY AOCU' LANCE MANUAL CHAPTER 2

,n ,

t k a. Nuclear Policy Statements are ddcument.s issued by l

Corporate Management t.o promulgate authoritative management directives establishing and defir.ing Quality Assurance policies within the Illinois Power Company Nuclear Program.

b. IP Nuclear Program Quality Assurance Manual describes the objectives, requirements, interface relationships, and assignment of responsibilities for ,

accomplishing activities which affect the safety- '

related functions of systems, structures, or compo-nents. It contains the trinimum requirements to be applied by IP and suppliers. The manual i9 approved and maintained current by the Manager - Quality Assurance. Managers and Directors of ort nizations perforaing activities within the scope of the program designate their acknowledgement of responsibilities and authorization for use within their organization by signature prior to approval of the manual by the Manager - Qunlity Assurance. The company manage-ment s endorsement of the 1P Nuclear Program Quality Assurance Program is signified in the " Policy State-ment" portion of the manual.

b.2 Procedures are cocuments

[b Corporate direction Nuclear and policy (CNP) developed, approved, and issued ~to provide corporate pertaining to appropriate Nuclear Program Activities. CNPs are reviewed oy the Manager - Quality Assurance for compliance with quality assurance requirements and are approved by corporate level management, b.3 CPS Records Management Standards provide direction in  !

the areas of records identification, preparation, 1 collection / review, turnover / transfer, storage, preservation, and maintenance, b.4 Inservice Inspection (ISI) Program Manual describes the ISI requirements for' CPS and serves as the site standard for all CPS ISI Program activities.

c. Departmental Procedures or Instructions are devel-oped, approve 2 7and issued within each organization

~

to further implement the requirements of Corporate Nuclear Procedures and the IP Nuclear Program Qu$lity Assurance Manual. These departmental procedures or instrnetions provide more detailed direction to IP personnel engaged in Nuclear Program related activities. Table 2-1 identifies those IP Nuclear PAGE 3 of 6 V REVISION: _

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.lP NUCLEAR PROCRAM l OUALITY. ATURANCE MANUAL CHAPTER 2 m -

Program Quality Assurance manual ' chapters !. hat are applicable to the IP Nuclear Program Departments wichin their scope of responsibility.

2.2.4 Training Each Manager or Director is responsible for the proper qualifica-tion of assigned personnel performing activities related to CPS.

This includes establishing and maintaining documented training l programs to ensure that personnel performing activities affecting quality are appropriately trained in the principles and techniques of the activity being performed; are instructed as . to purpose, scope, and implementation of governing documents; and that they maintain required proficiency. Programs are formulated to provide training based on individual employee experience and position and fulfill regulatory requirements, where applicable. Training records are maintained for each employee. Departmental training procedures / instructions require that indoctrination end training l programs include objectives, contenc of program, attendees, and date of attendance. Applicable departmental procedures /-

instructions require that the proficiency of personnel performing and verifying activities affecting quality is maintained by ,

retraining, re-examining, and/or decertifying, as determined by management or program commitment.

L 2.2.5 Qug_ity Assurance Program Evaluations Regular management reviews of the QA program to assess the scope, status, adequacy,. compliance, and overall effectiveness are performed under the direction of an Executive Vice President.

, This review function consists of meetings with key QA personnel, l as well as review of QA department audit and status reports, and the performance of a 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 Cuality Assurance organization for compliance with applicable rules, regula' cions, and IP Muclear Program Quality Assurance Manual ae set forth in the contract dccument. Approval of such programs in activities related to CPS is documented.

1

[ PAGE 4 of 6 REVISION: 1R FORM N100-177 (10-88)

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IP NUCLEAR PR2DCRAM .

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i

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2.3 RESPONSIBILITIES 2.3.1 Executive Vice President

a. Directs reviews for overall' effectiveness of the Quality Assurance prograra on a regular basic.

2.3.2 Nuclear Program Departments

a. Implement and comply with the IP Nuclear Quality Assurance Program,

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

2.3.3. CPS Plant Staff

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

2.3.4 Nuclear Station L'ngineering

a. Establish and maintain a site document for implement-ing the ASME Section XI Inservice Inspection Program, b 2.3.5 Nuclear Training

a. Establish, maintain and implement a licensed operator training program.

2.3.6 Quality Assurance

a. Develop, approve, and maintain the IP Nuclear Program Quality Assurance Manual.

b. Review, approve, and audit suppliers' quality assur-ance 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. Evaluate the IP Nuclear Program Quality Assurance Manual changns for commitment reduction,

e. Submit IP Nuclear Program Quality Assurance Manual changes to the NRC as defined in Paragraph 2.2.2 of this chapter and in accordance with 10CFR50.54

/~3 PAGE 5 of 6

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_ - - - _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ ___ ._ . _ _ _ - - _ __ ____________________--______a

IP NUCLEAR PROORAM CHAPTER 2 QUALITY ADOURANCE MANUAL TABLE 2-1

, , -~\

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TABLE 2-1 This table identifies e t '- IP Nuclear Program Quality Assurance nanual chapters that are applicable to the IP Nuclear Program-Departments. These organizations are responsible for develcping and maintaining precedures/ instructions to the extent and detail within the scope of their responsibilities. The Quality Assurance Department shall review selected departmental procedures /

instructions that implement the QA Program.

Nuclear Program Departments IP Nuclear Program QA Manual Ch.?ptors 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 CPS Plant Staff x x x x x x x x x x x x x x x x x x l

Nuclear Station Engineering x x x x x x x x x x x x x x x x g- gt Nuclear Planning & Support x x x x x x x x x x x x x

\j Nuclear Trainir.3 x x x x x x x x x x x Scheduling & Outage Management x x x x x x x x x x x Licensing 6 Safety x X X X X X X x x x x x Environmental Affairs x x x x x x x x x n x x x Quality Assurance x x x x x x x x x x x x x x x x x x Nuclear Program Assessment Group x x x x x x x x x x x j l

t'uclear Review & Audit Group x x x i

)

j 1

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IP NUCLEAR PROORAM M1 CUALITY AOOURANCE MANUAL CHAPTER (Q/ .

3 l

l DESIGN CONTROL APPROVED BY: MANAGER-0UALITY ASSURANCE

/

[ A ff 3.1 PURPOSE / SCOPE To establish the requirements, responsibilities and control measures for assuring that design bases and regulatory requirements are cor-rectly translated into design documents. The scope of design control covers all phases of engineering design, including: conceptual design selections; identification of design inputs (criteria and bases);

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

3.2 DESCRIPTION

Design control measures are established to assure modifications and

'" design changes meet the appropriate performance and quality require-ments. These design control measures are commensurate with those applicable to the original design and assure that modifications are designed and implemented in accordance with applicable codes, stan-dards and regulatory commitments.

The Nuclear Station Engineering Department has overall responsibility for design control activities at Clinton Power Station. These design control activities are managed within the context of the Nuclear Program Configuration Management Program, which also includes provi-sions for controlling hardware and software items (procedures, 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 / dcsign change documents under this program ensures appropriate participation and awareness by CPS organizations throughout the design development and installation process.

Provisions of this program also ensure that each modification or design change receives a thorough safety evaluation, that meets regulatory commitments or ensuren that the basis for not performing the safety evaluation is documented. If the change is determined to constitute "an unreviewed safety question", or to alter commitments contained in approved Safety Analysis Reports or the CPS Technical O

PAGE 1 nf s REVISION: 7g DATE: 2-14-89 FORM N100-176 (10-88)

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IP NUCLEAR FROORAM .

QUALITY ACCURANCE MANUAL CHAPTER 3 i

'i Specifications, it shall be evaluated by established safety review

,I committees and submitted for regulatory approval prior to implementa-tion.

New design or design changes shall be defined by drawings, specifica-tions, change notices or other documents as prescribed in design  ;

control procedures. The organization actually performing the design work, either Nuclear Station Engineering or a qualified consultant-engineer is required to include the following considerations in the design of each modification:

a. Appropriate design bases, regulatory requirements, safety requirements, performance objectives, design margins, special processes, material and testing requirements , and operating objectives are adequately translated into the various design documents.

b. Appropriate design analysis (e.g., physics, seismic, stress, thermal, hydraulic, radiation and accident) is part of the design process.

c. Accessibility requirements for operation, testing, mainte-nance, in-service inspection and repair are included in the s design.

L d. Necessary installation or modification inspection and test acceptance criteria are included in the design documents or modification packages.

e. An evaluation to determine if the proposed design change or modification involves an "unreviewed safety question".

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

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

Additionally, the organization which produces and approves the design /

design change documents shall maintain detailed procedures to control and document performance of the following design activities:

a. Identification and selection of design inputs.

O

!') PAGE 2 of 5 16 REVISION:

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$4,02172 L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._. -

IP NUCLEAR PR3 CRAM j CUALITY~ ACCURANCE MANUAL CHAPTER 3 {

O V

b. Identification and control of interfaces between organiza-tions required to make input to, review or approve final F design products.

c. Performance of calculations or analyses which demons trate that design products satisfy the design inputs, including those performed using computer coder.

d. Prodt.c tion , review, approval, release, distribution and revision of drawings, specifications, data sheets or other design output documents.

e. Classification and specification of technical requirements for equipment or materidi procurement associated with the design / design change.

f. Verification that the design inputs, interfaces, calcula-tions and final design products are adequate and correct; and that the installation satisfies all specified design requirements.

The form and otructure of the procedures and instructions used to

. accomplish these activities may vary dependent upon the complexity of the cecign and the different organizations involved in the design x development.

Design verification for the final design products will 'normally be done by an independent group or person within the organization actu-ally producing the design. When this is a consultant-engineer organ-ization, Nuclear Station Engineering may choose to conduct, or direct, additional independent design verifications.

This verification consists 'of a check of design adequacy by such methods as design reviews , use of alternate calculations or mathe ds ,

or performance of verification or qualification testing. The method, or combination of methods, used to verify a design will be selected on a case-by-case basis. The selection will be based on consideration of such things as: a) uniqueness of the design of application, b) complexity of the design, c) prior history of use, d) importance to safety, and e) consequences of failure. CPS operating pliase design 1 verification other than qualification testing of prototype' or lead production unit will, where practical, be completed prior to instal-lation and operation. In those cases where this timing cannot be met, the design verification may be deferred, providing the justification for this action is documented and the unverified documents related to the design are appropriately identified and controlled. However, design verification shall be ccmpleted prior to the component, system or structure being released for operations. f PAGE 3 of 5 16 REVISION: ,_,

DATE, 2-14-89 70RH N100-177 (10-68? I H.02i?2 j i

i

IP NUCLEAR PROSRAM CUALITY. ACCURANCE MANUAL CHAPTER 3 O Verification by test will normally be- included 'in procurement docu-ments that require the supplier to perform the test and use the most severe design conditions as acceptance criteria. The procurement documents shall require that the test procedure, including acceptance criteria, be submitted to Illinois Power or its designee for review and approval prior to performance of the test.

When a verification test cannot be performed prior to installation, proposed testing programs shall be reviewed and approved by Illinois Power to ensure that the prcgram is conducted within licensing lini-tations prior to the point when the installation would become irre-versible, and that no unresolved safety questions are involved.

The entire design control process shall be subject to audits conducted by IP Quality Assurance, to ensure that design activities are implemented in accordance with program requirements.

3.3 RESPONSIBILITIES 3.3.1 CPS Plant Staff

a. Initiate or concur with design change requests for CPS and

,- forward to Nuclear Station Engineering for review and

( approval,

b. Incorporate approved design changes into CPS.

c -. Employ controls which maintain the "as-built" and "ar-modified" condition of the plant.

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

3.3.2 Nuclear Station Engineering

a. Develop and implement the design control program for CPS, including design interface control activities.

b. Perform or obtain design services, such as preparation and review of design technical documents for all modifications I end design changes. l i

e. Review and approve design change requests and modification j requests for incorporation into the plant.

fm 1 b PAGE 4 of 5 REVISION: 16 I

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IP NUCLEAR PR'EfRAM GUALITY ACOURANCE MANUAL CHAPTER 3 l rn .

I i l d. Providing "as btdlt" information to t'he Nuclear Licensing I I

and Safety Department for updating the USAR to current plant conditions,

e. Determine if the proposed design change involves an "un-reviewed safety question".

f. Coordinate the processing of plant modifications, assigning control numbers, recording progress , confirming. procedural compliance, recommending operational readiness of affected hardware and transmittal of completed design change pack-ages to Nuclear Planning and Support for processing, maintenance and retention in the Central File,

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

3.3.3 Licensing and Safety

a. Review and evaluate'unreviewed safety questions identified during the modification process and obtain the necessary reviews and approvals.

7 3.3.4 Quality Assurance t

A a. Review proposed design changes for systems, components and structures and ensure that the IP Nuclear Quality Assurance Program requirements are incorporated.

b. Conduct periodic audits to determine that the design control and verification activities meet the requirements of the design control program.

,m,

!U) PAGE 5 of 5 REVISION: 16 ,

FORM N100-177 (10-88)

N.02172

o q IP NUCLEAR PADERAM l n[ OUAL9TY AOCURANCE MANUAL CHAPYER

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v .

4 PROCUREMENT DOCUMENT CONTROL APPROVED BY: MANAGEP-OUALITY ASSURANCE -

E, M M f7 4.1 PURPOSE / SCOPE To define the requirements and responsibilities'for the prepara-tion, review, release, and revision of procurement specifi-cations, purchase orders, and associated documents to assure the procurement of items and services are properly controlled.

i

4.2 DESCRIPTION

i Measures are established for the preparation, review, approval '

and processing of purchase requisitions, purchase specifications, purchase orders and revisions to these documents to ensure'that 7_

materials, parts, components and services for CPS are properly specified and procured.

Purchase requisitions for materials , parts, components or ser-vices for CPS are originated by the CPS organization having a need for the material, part, component or service for the oper-ation, maintenance, refueling, repair or raodification of the plant.

Purchase requisitions are prepared in accordance with documented procedures that require:

a. Applicable ' specifications , draw!ngs, quality control requirements, and related documents be included or referenced.

b. Appropriate quality requirements, including supplier documents and records to be prepared, submitted or retained, and made available for purchaser review or approval are included or referenced.

c. Appropriate quality assurance program requirements be ,

included or referenced.

l

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PAGE 1 nf a REVISION: 3_

FORM N100-176 (10-88) DATE: 2-14-89 M.02171 l l

_ _ _ _ - _ _ _ _ - _ _ i

IP NUCLEAR PROCRAM .

QUALITY ACCUF1ANCE MANUAL CHAPTER 4 V d. Provisions for the purchaser's right of access to l

l supplier's facilities and records (including sub-tier I suppliers) for source inspection and audit be speci-fled.

e. Provisions for supplier's reporting and disposition of nonconformances and requirements for hold points and release control are clearly identified.

f. Suppliers extend the applicable quality requirements, including purchaser's access to facilities and records for inspection and audit, to their sub-tier suppliers.

Technical and quality requirements for procurement of items and services are specified by the originating organization and the Nuclear Station Engineering Departmeint. The Quality Assurance  ;

Department verifies appropriate quality requirements are speci- '

fied. Purchase requisitions are cpproved by the Manager et Director of the originating organization or his detignee and  ;

forwarded to Nuclear Planning and Support for subsequent process-ing.

Based on the approved purchase requisition, Nuclear Planning and l

] Support prepares the necessary purchase orders or contract  !

[V documents. Prior to release of the purchase order or contract,  !

Quality Assurance performs a review to ensure the requirements

("a" through "f" above) have been met. Nuclear Planning and  ;

Support places orders or contracts only with suppliers determined to be capable of meeting the procurement requirements. This determination is based on evaluations of the supplier's quality assurance program for placement on the Qualified Suppliers List ,

by QA, the supplier's technical capabilities by the Nuclear Station Engineering Department and the supplier's commercial '

ability by Nuclear Planning and Support.

Changes, revisions or amendments to requisitions and procurement documents, except as discussed below, are subject to the same requirements as was the original document. The following changes, revisions or amendments require Nuclear Planning and Support department approval only: a) quantity, b) estimated price,. c) cost codes, d) taxes, and e) format and editorial changes -(such as spelling or typing errors).

The IP Quality Assurance department conducts periodic audits to ensure that procurement activities are implemented in accordance with program requirements.

0r)

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IP NUCLEAR PRECRAM OUALITY ACCURANCE MANUAL CHAPTER 4 s

(q 4.3 ' RESPONSIBILITIES 4.3.1 Nuclear Program Departments

a. Initiate purchase requisitions for materials, parts, components or services for CPS.

4.3.2 Nuclear Planning and Support- <

1 1

a. Review purchase requisitions for completeness, j

b. Prepare purchase orders / contracts for award to quali-fled suppliers.

4.3.3 Nuclear Station Engineering

a. Specify technical and auality requirements for mater-ials, parts. components or services for CPS.

b. Review and approve design changes that result from procurement.

~

)

c. Provide specifications for procured materials, parts, components or services for CPS.

O d. Evaluate suppliers for technical ability to perform.

4.3.4 .uality Q Assurance

a. Verify appropriate quality requirements are specified  !

for materials, parts, con.ponents or services for CPS.

b. Review and approve supplier quality assurance pro-grams. I

c. Conduct periodic audits of the procurement document control program to ensure compliance with the requirements of this chapter.

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IP NUCLEAR PROORAM l[ QUALITY AOCURANCE MANUAL 7 CHAPTER (V .

5 INSTRUCTIONS, PROCEDURE $ & DRAWINGS APPROVED BY: MANAGER-0UALITY ASSURANCE _ -

%4#

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8 87 /

5.1 PURPOSE / SCOPE To define the requirements and responsibilities for . the generation and use of instructions, procedures, drawings, or related material to control activities which affect quality.

5.2 DESCRIPTION

Each IP department is responsible for developing, reviewing, approv- 1 ing, issuing and complying with formal instructions, procedures, drawings and related material for performing activities affecting the quality or functions of applicable systems, structures, or components at CPS. Requirements established are:

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

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

Each Manager, Director and Supervisor is responsible for determining the need ror issuing and revising instructions and procedures related to each organization's scope of activities. Table 2-1 identifies those IP Nuclear Program Quality Assurance manual chapters that are j applicable to the IP Nuclear Program Departments within their scope 1 of responsibility.

The IP Quality Assurance department conducts periodic surveillance I and audits to determine that appropriate instructions, proceduras, or i drawings exist and to evaluate their adequacy and implementation.

, 1 l 1

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REVISION: ,c FORM NIOO-376 (10-88)

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IP NUCE. EAR PRSORAM .

l CUALITY AOCURANCE MANUAL CHAPTER 5

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l 5.3 RESPONSIBILITIES l

l 5.3.1 Huclear Program Departments

a. Develop, approve, issue and emplo:7 those instructions, procedures, or drawings necessary to accomplish its assigned tasks and responsibilities et CPS. Er.ch depart-ment ie responsible for deireloping, obtaining approvals and complying with instructions, procedures or drawings related to its scope of effort.

5.3.2 Ouality Assurance

a. Conduct periodic surveillance and audits to verify that appropriate instructions, procedures and drawings exist and are being itaplemented in accordance with the require-ments of this chapter.

b. Review selected CPS departmental procedures and instruc-tions for QA program requirements.

in s

(n)

PAGE 2 of 2 REVISION: 76 l

l FORM N100-177 (10-88)

M.02172 l

IP NUCLEAR PROSRAM

[ OUALITY AOCURANCE MANUAL i~T CHAPTER

(.)

6 DOCUMENT CONTROL APPROVED BY.: MANAGER-OUALITY ASSURANCE r d MNN1 6.1 PURPOSE /5 COPE To define the requirements and responsibilities for review, approval.

issue and distribution cf controlled documents such as instructions, procedures or draviros and changes thereto. Controlled documents shall be dis.tributeu _ader a formal document ccntrol system.

6.2 DESCRIPTION

Controlled documents cuch as specifications, proc.edure s , instruc-g tions, drawings, computer software for safety-related applications, and other related materials which prescribe activities affecting quality or safety-related functions of systems, structures or compo-nents at CPS shall be processed in accordance with the follow 1.ng criteria:

a. Documents, including changes, are reviewed for adequacy by appropriately c,ualified personnel, approved for issue and use by authorized personnel, and dist.ributed to and used where the prescribed activity is performed,

b. The review and approval of changes which modify the intent of the document is performed by the same organizations that performed the original review and approval, unless other equivalent organizations are specifically desig-nated. Reviewing organizations will have access to pertinent background information upon which to base app.mval and have adequate understanding of the require-ments 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 remberc of the < it management staff who are knowledgeable in the areas affected by the procedures. At least one of these individuals shall be che supervisor in

/ i D) PAGE 1 of 4 REVISION: 3 8

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M.02171

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iP NUCLEAR PRECRAM CUALITY ACCURANCE MANUAL CHAPTER 6'

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charge of the shift and hold a seni'or operator license. ~

Such changes shall be documented, reviewed and approved in accordance with the CPS Operating License Manual, and if appropriate, incorporated in the next revision of the I- 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 docu-ments.

l

f. The CPS document control program provides for periodic reviews of plant procedures to determine if changes 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 iden-tified.

I

1. Current distribution lists are established and-used.

Types of documents to be controlled as described above include:

a. IP Nuclear Program Quality 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. Corporate Nuclear Procedures which provide corporate instruction and policies pertaining to Nuclear Program activities,

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

d. CPS Oper:: ting Manual which contains procedures for the operation 7 maintenance and testing of the plant by the CPS organization. These procedures are subj ec t to a well-defined and documented preparation, review, approval, change control and distribution process.

PAGE 2 of 4 REVISION: 1A ME '

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IP NUCLEAR PR3 CRAM '

OUALITY AOCURANCE MANUAL CHAPTER 6 i) l

e. CPS Records Management Standards whi'ch provide direction  !

for records identification, . preparation, collection / f and review, turnover / transfer, storage, preservation maintenance.

f. Inservice Inspection Program Manual which describes the ISI 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 correspon-dence 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 trans-mitted documents.

b. A program for approving the receipted documents for use in (g) v 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 in the paragraph above are replaced in a timely manner by updated document revisions.

The IP Quality Assurance d'epartment conducts periodic surveillance and audits of document control systems to ensure compliance with the specified requirements.

l 6.3 RESPONSIBILITIES 6.3.1 Nuclear Program Departments l

! a. Review, approve and distribute c.ontrolled documents generated in accordance with appropriate procedures.

b. 'Emp loy appropriate measures to receive, record and re-distribute controlled documents from other organizations.

PAGE 3 of 4 v REVISION: 1A FORM NIOO-177 (10-88)

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..l IP NUCLEAR PROE: RAM -  !

GUALITY ACCUMANCE MANUAL CHAPTER 6 )

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,r s .

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1 6.3.2 Nuclear Planning and Support

a. Maintain a Document Control Program to control the issu-ance of documents, such as ins tr uc tion.c , procedures and drawings, including changes thereto, which prescribe all .

activities affecting quality, j l

6.3.3 Quality Assurance

a. Conduct periodic surveillance and audits of docur.ent control systems to ensure compliance with the requirements of this chapter.

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/

PAGE 4 of 4 REVISION: 19 FORM NIDO-177 (10-88)

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IP NUCLEAR PROERAM CUALITY AOCURANCD MANUAL p

v CHAPTER 7

CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES APPROVED BY: MANAGER-OUALITY ASSURANCE

/

'd 8 2dMM 7.1 PURPOSE / SCOPE To define the requirements and responsibilities for programs that assure purchased material, equipment, and services conform to procurement requirements.

7.2 DESCRIPTION

Measures have been established to provide assurance that pur-chased material, equipment, and services conform to procurement document requirements. This assurance is accomplished by con-trolling bcth the selection of procurement sources and inspec-tions of the product at the source and/or upon receipt at CPS.

O IP procurement 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 assurc that they are equivalent to the original requirements. When alternate require-ments 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 procure-ment 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 l 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 l 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 supaliers to comply with ,

Quality Assurance program requirements of the procurement l (VD PAGE 1 nf s REVISION: 3 DATE: 2-14-89 l FORM NIOC-176 (10-88) l M.o2i7:

IP NUCLEAR PRO 3 RAM CUALITY ACCURANCE MANUAL CHAPTER 7 A

document. The determination of a supplier's acceptability may be made by 'eans m 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, the Coordinating Agency for Supplier Evaluation (CASE), or American Society Mechanical Engineers (ASME), or e) documented l information from organizations, including architect-engineer, Nuclear Steam Systems Supplier, and other utilities that indi-cates the supplier has a program that meets applicable require-ments of Appendix B to 10CFR50. When CASE is used the documenta-tion identifies the audit used to approve the supplier. When these means are either not available or do not permit a complete evaluation of a supplier's quality capabilities, Quality Assur-ance will conduct a survey or an audit of the supplier. The Quality As.surance department is responsible for maintaining the i Qualified Suppliers List.,

In addition to reviewing a supplier's capability to meet the commercial requirements of the procurement documents, Nuclear Planning and Support is assigned the responsibility of ascer-taining that the required technical and quality assurance reviews

and evaluations have been completed satisfactorily prior to

\ contract award 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 surveillance and evaluations at the suppli-er's facility, as necessary, to verify continued compliance with the quality assurance requirements of the procurement documents.

The results of these surveillance and evaluations are document-ed. Where specified in the purchese order or contract, source inspections at the supplier's facility are accomplished by the Quality Assurance organization or qualified agent to verify that 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, and/or checklists containing or referencing appropriate accep-tance criteria.

Upon receipt at CPS, Nuclear Planning and Support is responsible j for the control of safety-related materials , aarts, and compo- 1 nents. Quality Assurance inspection personne: are responsible for inspecting, releasing, and identifying purchased material and equipment as to the inspection status.  !

O l Q PAGE 2 of 5 REVISION: 15  ;

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IP NUCLEAR PROSRAM CUALITY ACCURANCE MANUAL CHAPTER 7 A

i After receipt inspection, storeroom personnel of Nuclear Planning and Support are responsible for forwarding the purchased material ,

to a controlled storage area or releasing it for installation or l further work. Personnel from other departments also perform t 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 accomp-lished 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-ments 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 surveillance. Inspection and test activities verify that the hardware performs in accordance with applicable technical re-quirements and serve to demonstrate that the hardware meets the requirements stated in a certificate of conformance. The results O of the source and/or receipt inspections, the acceptability of d supplier furnished documentation, and the resulting determination of conformance or nonconformance are documented.

Acceptance 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 re-quired:

a. technical verifications.

b. surveillance / inspections,

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

The Quality Assurance department conducts periodic surveillance and audits of the control measures applied to purchased materi-als, equipment, and services to determine the effectiveness in ,

meeting the specified requirements. Quality Assurance audits of I 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.

PAGE 3 of 5 V REVISION: 15 FORM NIOO-177 (10-88)

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IP NUCLEAR PRECRAM ,

l CUALITY ACCURANCE MANUAL CHAPTER 7 i i j l

V 7.3 RESPONSIBILITIES l

7.3.1 Nuclear Program Departments

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

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

7.3.2 Nuclear Station Engineering l

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 suppli-ers* 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 Nuclear Planning and Support ,

a. Review requisitions for completeness.

b. Perform reviews of suppliers' capabilities to meet commercial terms and conditions prior to release of the purchase order or contract.

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

d. 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.

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IP NUCLEAR PREGRAM OUALITY ACCURANCE MANUAL CFAPTER 7

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V 7.3.4 Quality 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.

b. Perform periodic surveillance and evaluations at suppliers' facilities, as necessary, to verify con -

tinued compliance with quality requirements of pro-curement documents,

c. Conduct pet-iodic surveillance and audits of the control measures applied to purchesed 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 p items, including verifying the required documentary tu) 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 use. i

f. Review purchase requisitions and specify the quality assurance program requirements for the item (s) to be procured.

g. Perform surveillance or inspections, as required, en procured services prior to acceptance.

h. Maintain the Qualified Suppliers List current based on the results of evaluations or audits.

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(/ PAGE 5 of 5 REVISION:_ 15 FORM N100-177 (10-88)

M,02172

_ _ _ _ _ _ _ _ _ _ _ _ . - ______________.___.__________J

IP NUCLEAR PR200 RAM CUALITY AOCURANCE MANUAL l 1 f~l CHAPTER v .

8 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS APPROVED BY: MANAGER-00ALITY ASSURANCE

/

1. d# #bMF 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 that trace-

. ability is provided and the use of incorrect or defective items is prevented. These measures include the following:

(]3

a. Procurement documents specify appropriate identification to be applied to items of purchase.

b. An inventory control system is employed for the receipt, storage or stocking, and issue of materials, parts, and components,

c. The identity of materials, parts, and components is either on the items or on records traceable to them. When physi-cal 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 substi-tuted,

e. When codes, standards, or specifications require trace-ability of materials, parts, or components to specific inspection or test records, the program is designed to provide such traceability.

A PAGE 1 of 3 REVISION: ,/

DATE: 2-14-89 FORM N100-176 (10-88)

M.02171

l l IP NUCLEAR PREORAM CHAPTER 8 l QUALITY ACCURANCE MANUAL 1

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f. When employed, identification is transferred to each part of an item prior to its being subdivided.

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 record and/or reports. Where physical 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, repair, or modification, control measures are implemented to ensure proper 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 performd by 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 (V )

insuring that identification and control of materials, parts, and components by the supplier are in accordance with applicable proce-dures.

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

8.3 RESPONSIBILITIES 8.3.1 Nuclear Program Departments j J

a. The Nuclear Program Departments responsible for supplier )

work at CPS are responsible for ensuring that 1 identification and control of materials, parts and compo-nents by the supplier are in accordance with applicable ,

procedures. i 2 of 3 V(3 PAGE REVISION ,,_,

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FORM NIOO-177 (10-88)

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IP NUCLEAR PRE'2 RAM- CHAPTER 8 CUALITY ACOURANCE MANUAL

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8.3.2 CPS Plant L_aff

a. Develop and implement a program that provides for the identification and control of materials, parts and compo-nents used at CPS, 8.3.3 ~ Nuclear Planning and Support

a. Develop and implement an inventory control system for the identification and control of materials, parts and compo-nents.

8.3.4 Quality Assurance .

a. Ensure that suppliers comply with approved procedures.

b. Conduct verification inspzetions and periodic surveillance and audits of the identification and control of items to ensure compliance with the requirements of this chapter.

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l FORM N100-177 (10-88) j H.02172 l

l 1

m IP NUCLEAR PROCRAM CUALITY AGOURANCE MANUAL l

/q CHAPTER v'

9 CONTROL OF SPECIAL PROCESSES APPROVED BY: MANAGER-0UALITY ASSURANCE W V'M MfNf7 9.1 PURPOSE / SCOPE To define the requirements and responsibilities' for assuring that special processes such as welding, heat treating, chemical cleaning, nondestructive examination (NDE), pipe bending, and special coatings are performed under proper controls and that qualified procedures governing these processes are estab?ished 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

V 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 con-ducted. Processes which meet the following criteria are controlled as special processes:

I

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

b. The specified quality cannot be readily determined by )

4 direct inspection or test of the final product. l i

Special processes include welding, heat treatment, nondestructive examination (testing), and cheraical cleaning. .

Special process proceduros shall specify: prerequisite conditions, processing steps, conditions to be maintained during the steps of the process, inspection and test requirements, personnel qualification requirements and record requirements. Technical portions of the special process controls are delineated or referenced in the design or technical documents by the organization preparing the document.

[V PAGE 1 es 4 REVISION:., 3 DATE: 2-14-89 FORM N100-176 (10-88)

H.02171

IP NUCLEAR PRO] RAM CHAPTER 9 OUALITY ACCURANCE MANUAL Special process procedures shall be submitted to Nuclear Station Engineering for review and approval to assure 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 responsibility 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 include:

a. The need for special processes and the codes or standards applicable are identified dt.ing design or preparation of technical documents associated with an activity.

n

b. Special processes are performed in accordance with ap-(V) proved written procedurcs app)icable to the specific process and qualified in accordance with applicable codes and standards.

c. Persennel performing special processes are qualified, as l requir.ed in accordance with applicable codes and stan-dards. {

d. Special processes are accomplished under suitable con-trolled conditions which include the use of qualified equipment, adequate control of the environment, and estab- )

lishment of proper prerequisites related to the process,

c. Application of special nrocess procedures and personnel {

qualifications is verified by IP Quality Assurance person- I nel thrcugh audits and surveillance.

l

f. Records which show that special processes were performed ,

in compliance with qualified or approved procedures and by l qualified personnel and equipment are maintained. l 1

q

(_) PAGE 2 of 4 REVISION: 7g DATE-*

2-14-89 l FCRM N100-177 (10-88) r4.02172

)

l IP NUCLEAR PRECRAM CHAPTER 9 CUALITY AOCURANCE MANUAL (3

V The Quality Assurance department conducts inspections, surveillance, and audits of special processes, including qualification of process-es, equipment, and personnel to ensure compliance with appropriate codes, standards, specifications 3 procedures, and the IP Nuclear Program Quality Assurance Manual.

9.3 RESPONSIBILITIES 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 requirement for special processes and their controls and references to the  !

applicable codes or standards.

, 9.3.2 Nuclear Station Engineering i (V) 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 l adequacy.

d. Review and approve special process personnel qualifiention 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, q

g. Contracts with a . supplier to perform scheduled ISI i examinations and inspections as required.

1 9.3.3 Quality Assurance ,

a. Review NDE procedures. including those of suppliers.

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(" PAGE - 3 of 4 REVISION: h, FORM N100-177 (10-88)

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IP NUCLEAR PRECRAM CHAPTER 9 CUALITY AO3URANCE . MANUAL

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b. Establish and maintain a program to' qualify procedures ,

equiptaent , 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 supplier to perform NDE or inspection services as required.

f. Conduct periodic surveillance and audite of special processes and controls, including qualification of pro-cess, equipment, and personnel, whether performed by CPS Plant Staff or suppliers to ensure compliance with ap-proved precedures.

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PAGE 4 of 4 l l Rc. VISION : 1A FORM NIO3-?77 (!O-88)

M 02172

g IP NUCLEAR PRECRAM P oua'irv rocuamaC= =^=ua'

/q CHAPTER U .

10

) INSPECTION APPROVED BY: MANAGER-OUALITY ASSURANCE <

e6N A 98F 7

10.1 PURPOSE /SCOPF To define the requirements and responsibilities for a program of inspection which ~ provides assurance that the fabrication, instal-lation, modification, and repair activities effecting safety-related components, systems, and structures conform to the applicable speci-fications, 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

/~'s -

U In order to assure safe'and reliable operation, programs of inspec-tior.s are established at CPS uhich includes the following provisions:

a. The requireinents for inspections are identified and l i

documented based on procedures, instructions, drawings, and other documents for an activity prior to the start of l the cetivity.

b. Inspections are accomplished in accordance with a com- j bination of approved written inepection procedures and 1 documented instructions which contain or reference, as a minimum:

1. A desetiption of the required inspection (type, m-thod, etc.), the responsibility for performing the inspection, and, where applicable, any sampling plan to be used. Hold / Witness points, where required, will be indicated in the appropriate documents;

2. The discrete identity of the activity, process, or l item to be inspected; I

3. Applicable documents, drawings, and specifications pertaining to the actfvity or item under inspection; PAGE 1 of 3 REVISION: 75 FORM NI DO- 17e.

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IP NUCLEAR PRECRAM' QUALITY ACCURANCE MANUAL CHAPTER 10

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

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 certifications of 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 (G) evaluated and justified in writing,

e. Measuring and test equipment used to obtain quantitative data for acceptance criteria shall have 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 of surveillance tests, inspections of func-tional and preoperational tests, ISI examinations and inspections , l 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 the acceptability of scheduled ISI Program examination and inspection results. The Quality Assurance department and the Nuclear Station Engineering department may use the services of other IP department personnel or may engage the services of external organizations to accomplish any inspections, evaluations or reviews of inspection and test results.

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' PAGE 2 of 3 REVISION: 15.

FORM N100-177 (10-88)

M.02t72

IP NUCLEAR PRDC! RAM CUALITY ACOUR,ANCE MANUAL CHAPTER 10 1

,%ppliers are responsible for establishing and ' implementing inspec-tion programs necessary to meet the requirements specified in the procurement documents. The need to invoke the requirements of ANSI N45.2.6 on suppliers 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 j which are considered when determining whether or not to invoke ANSI l N45.2.6.

IPQA conducts periodic surveillance and audits of the various esta-blished inspection programs and their implementation to ensure com-pliance with the provisions described in items "a" through "e" above.

10.3 RESPONSIBILITIES 10.3.1 CPS Plant Staff

a. Develop and implement a program that provides for in-spection of work operations performed at CPS.

10.3.2 Nuclear Station Engineering

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

(

b. Specify inspection and acceptance criteria for nonde-structive examination in work documents.

c. Develop and implement an inspection program for scheduled ISI Program examinations r.nd inspections,

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

10.3.3 Quality 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 surveillance and audits that suppliers performing work at CPS are in compliance with the ap-proved inspection program.

d. Conduct periodic surveillance and audits of inspection i

programs to ensure compliance with the requirements of this chapter.

REVISION: 1s l

DATE: 2-14-89 I FORM NIOO-177 (10-88) i M.02172 l I

_ --_ ---- -- 1

g IP NUCLEAR PRD3 RAM P oua'irv accuaraos =^=ua' l

!~i CHAPTER '

O .

11 TEST CONTROL APPROVED BY: MANAGER-OUALITY ASSURANCE - <> ,#!# 9N7 11.1 PURPOSE / SCOPE To define the requirements and responsibilities for the control of a test program which will assure that the safety-related structures, systems or components being tested meet specified performance criteria,

11.2 DESCRIPTION

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.

(A) l

b. Surve111ance testing.

c. Tests associated with plant maintenance, modifica-tions, 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 requ;' red: i

a. Statement of test objective (s);

b. Test prerequisites, to be fulfilled prior to the test, including requirements for calibrated instru-ments, suitable environmental conditions, appropriate equipment and personnel availability; and condition of the item to be tested and condition of the test equipment; A

PAGE 1 nf 3 REVISION: 7 _t FORM N100-176 (10-88)

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< IP ' NUCLEAR PRSORAM .

GUALITY ACCURANCE MANUAL CHAPTER 11

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c. Precautions' to be taken in the' preparation and performance of the test, including limits of parame-ters if variations outside the normal ranges are prescribed;

d. Mandatory inspection hold points for witness by inspection personnel;

e. Instructions for performance of the test, including the use of appropriate instruments, equipment and personnels

f. Data to be acquired; and

g. Acceptance / rejection criteria.

Test schedules are provided and maintained in order to assure that necessary testing is performed and properly evalcated 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 qual-ified personnel. Test results are documented to facilitate (q ,/

evaluation and to provide a permanent record.

are performed to assure that performance characteristics conform Test evaluations to design. . Repair, rework and/or retesting are scheduled for accomplishment as identified by the test evaluation.

11.3 RESPONSIBILITIES 11.3.1L CPS Plant Staff 4

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.

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d. Perform the required tests.

i

e. Review and approve test procedures and results for t surveillance testing.  ;

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

PAGE. 2 of 3 .

REVISION: _

1A l

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' DATE: 2-14-89  !

rons wico-ir/ :so.ss) '

H.02172 u_________._._____._ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ ._ . _ _ _ _ _ _ _ _ _ . _ _ _ __ _ _l

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lP NUCLEAR PREORAM C2UALITY ACCURANCE MANUAL CHAPTER 11 ,

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-g. . Review and approve post-modification test results. -

11.3.2 Nuclear Station Engineering

a. Establish test requirements and acceptance criteria f for post-modification testing,

b. Review and approve post-modification and/or special test results as detailed in approved procedures.

1

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

l 11.3.3 Quality Assurance

a. Review and approve test '3rocedures to assure that l QA/QC requirements are inc:.uded,

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

c. Conduct periodic surveillance and audits of the test program and to ensure the test program complies with

(- the requirements of this chapter.

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REVISION: 7 r.

FCRM NIOO-177 (10-88)

M.02172 j

IP NUCLEAR PRECiRAM y[ CUALITY AOCURANCE MANUAL h CHAPTER l v .

12 I CONTROL OF MEASURING AND TEST EQUIPMENT APPROVED BY: MANAGER-OUALITY ASSURANCE r

- d[#

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MfNP 12.1 PURPOSE / 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 perma-nently installed instrument and control devices.

12.2 DESCRIPTION

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 or instrument / control equipment.

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 equip-ment being calibrated, or when this is not possible, have i

an accuracy that assures the equipment being calibrated I will be within the required tolerance and that the basis of acceptance is documented and authorized by super-visors.

, b. The reference standards used for calibrations are I required to be traceable to nationally recognized stan-dards 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

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( PAGE 1 nr 1 REVISION: 3 FORM N100-176 (10-88)

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IP NUCLEAR PRDERAM CUALITY ACCURANCE MANUAL CHAPTER 12 q

k ') c. Calibration intervals for M&TE and' installed instrument and control devices are based upon the type of equipment, stability, reliability characteristics, required accuracy and other conditions affecting calibration.

d. Calibrations are performed by comparison with valid standards and using approved written procedures,

e. Calibration standards are maintained and used in a controlled environment which does not adversely affect the calibration procedure or standard.

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

g. M&TE and installed instrument and control devices requir-ing calibration are assigned identification numbers traceable to the calibration records which includes the calibration "AS FOUND" and "AS LEFT" data for the equiament calibrated at the plant. If the equipment is calibrated by an outside service organization, a certificate of calibration complete with AS FOUND" and O "AS LEFT" calibration data is required. Such

(,) certificates and data sheets bear the assigned equipment-identification numbers and the identification of the calibration standard used and are traceable to the individual calibration records,

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

i. If selected installed instrument and control devices are found to be out of calibration, an evaluation concerning the validity of previous inspection and test results is performed and documented. If M&TE is found to be out of calibration, an evaluation concerning the validity of previous inspection and test results and the acceptability of items previously inspected or tested since the time of the last calibration check is made and documented. Corrective action is taken in accordance with Chapter 16 when such evaluations invalidate a

' previous acceptance.

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

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IP NUCLEAR PROORAM-CUALITY ACCURANCE M ANUAL CHAPTER 12 n i CPS Plant Staff is assigned the responsibility' for establishing and implementing the program for the control of M&TE and installed instrument and control devices used in operation, maintenance, test and/or inepection activities which fall within the ecope of the IP Nuclear Quality Assurance Program. Suppliers performing services or providing products to CPS are required to have comparoble 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 surveillance and audits of the controls applied to measuring and test equipment to determine compliance with the provisions described in items "a"

, through "j" above. i 12.3 RESPONSIBILITIES 12.3.1 CPS Plant Staff

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.

7

c. Ensure the appropriate requirements for the control of M&TE are included in Plant Staff initiated technical i documents and procurement requisitions.

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 i work at CPS.

b. Conduct periodic surveillance 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: l 75 i DATE: 2-14-fs9  !

FORM NICO-177 (10-88) )

M.02172 l

I P1 oua'Pirv NUCLEAR accua^ PREERAM ace =^=ua' 7 CHAPTER d' .

13 HANDLING, STORAGE AND SHIPPING APPROVED BY: MANAGER-OUP i 'Y ASSURANCE -

Mk

/

289 /f 7 13.1 PURPOSE / SCOPE To define the requirements and responsibilities for the control of handling, storage, shipping, packaging, cleaning and preservation ,

of materials and equipment to prevent damage or deterioration. l

13.2 DESCRIPTION

The IP Nuclear Quality Assurance Program includes procedures which assure special handling, preservation, storage, cleaning, 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 g heavy loads and safe load paths to protect safety systems and

)

b radioactive material from damage. In addition to the 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 i furnished materials, parts and components. Nuclear Planning &

Support uces this information for the development of the storage and handling procedures and instructions to be applied to an item.

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

Consumable materials such as chemicals, reagents and lubricants maintained in storerooms and warehouses are controlled procedur-ally by an inventory control system which includes provisions for identifying storage requirements by commodity and identifying shelf life by commodity, when applicable. Disposal of commodities  !

whose shelf life has expired is addressed and controlled by j procedures.

i l

REVISION: ,t FORM N100-476 (10-88)

M.02171

IP' NUCLEAR PROGRAM ,

CUALITY ACOURANCE MANUAL CHAPTER 13 Q

V The Quality Assurance departmint conducts periodic surveillance, audits and document reviews to determine if appropriate procedures and centrols are being applied regarding handling, storage and shipping of materials and equipment.

1 13.3 RESPONSIBILITIES 13.3.1 CPS 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 Engineering

a. Ensure that appropriate handling, storage and shipping requirements are identified in technical documents that are prepared or reviewed by the department,

b. Specify in procurement documents that suppliers furnishing materials and equipment within the scope of f-~ this program implement appropriate -controls for

'g handling, shipping and storage of such items.

13.3.3 Nuclear Planning and Support

a. Ensure that suppliers furnish the required information relating to the proper handling, storage and shipping of procured items.

h. Develop and implement pregrams to control the han-dling, storage and shipping of 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 requisi-tions.

13.3.4 Quality Assurance l

a. Conduct periodic surveillance, audits and document reviews to verify that appropriate procedures and PAGE 2 of 3 REVISION: 1A /

FORM NIDO-177 (10-88)

M.02172

_ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ . _ _ ._ .J

IP NUCLEAR PREORAM CUALITY AOCURANCE MANUAL CHAPTER 13

/~T __

'V controls are being implemented in accordance with the o requirements of this chapter.

13.3.5 Environmental Affairs

a. Develop, implement and maintain procedures for the handling, storage and transfer of radiological sam-ples.

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1 PAGE 3 of 3 REVISION: 1 /,

FORM NIDO-177 (10-88) ,

H.02172 l 1

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l lP NUCLEAR PROORAM CUALITY AOCURANCE MANUAL 4 h CHAPTER V

14 INSPECTION, TEST AND OPEP.ATING STATUS l APPROVED BY: MANAGER-0UALITY ASSURANCE ** # b 9Yf 14.1 PURPOSE / SCOPE To define the requirements and responsibilities for identifying the inspection, testing and operational status of materials, parts, components and assemblies to assure that only items which have passed the required inspections and tests arc installed or operated.

14.2 DESCRIPTION

The IP Nuclear Quality Assurance Program includes procedures which assure the inspection, test and operating s ta t* ts of materials, parts and components are identified durlng the receiving,

• installation and operating processes. These procedures provide (d for:

a. Clear indication of the statim of insp.ection and tests performed upon individual items.by the use of' markings such as: a) stamns applied directly to the item, tags, or labels attached to the item, b) routing cards that accompany the item, or c) identification numbers which are traceable to records of the status of inspections and tests. If control stamps are used, a record of the assignment of the control stamp is j 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 applic-able specifications and standards. When markings are applied directly to items, consideration is given to ensure the markings have no deleterious effects on.the items,

b. Assurance that required inspections or tests are not inadvertently bypassed, In cases where required documenting evidetne is not available, the associated equipment or materials must be considered nonconforming in accordance with Chapter 15 of the QA PAGE 1 no3 REVISION: 7A DATE: 2-14-89 FORM Nt00-176 (10-88)

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'IP NUCLEAR PRECRAM CUALITY ACCURANCE MANUAL CHAPTER 14 l

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d(3 ' Manual. Ut.til suitable document'ng i evidence is .

available to show the equipment or. material is in conformance, affected systems shall be considered to be inoperable and reliance shall not be placed on such systems to fulfill their intended safety functions.

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

CPS Plant Staff is responsible for indicating the test and operati-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 Assurance is responsible for the identification of the inspection status on materials, parts and comp As imposed by the contract documents, suppliers per f or,onen ming ts .

activities at CPS or furnishing materials, parts, components cr assemblies for use at CPG also have responsibilities for the identification of inspection, test and operating statuc of items u nder their control. CPS Plant n Staff and the QA department review and approve the programs of suppliers performing work at CPS to ensure compatibility with the (O CPS ocatus indication system.

The Quality Assurance department - conducts periodic surveillance and audits to determine implementation and adequacy of mecsures used to indicate inspection, test and operating status to meet the requirements of the IP Nuclear Quality Assurance Program. ,

i 14.3 RESPONSIBILITIES 14.3.1 CyS Plant Staff

a. Develop and implement programs to indicate innpection, j test ar.d operating status of materials, parts, compo- )

nents, sub-systems and systems during installation, 1 modification, repair, testing and operation of CPS.

b. Review and approve the programs of suppliers  ;

performing work at CPS to ensure compatibility with l the CPS status indication system.  ;

c. Establish and implement procedures to control the status of radiological samples. ,

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IP NUCLEAR PROGRAM .

QUALITY AOCURANCE MANUAL CHAPTER 14 V 14.3.2 Nuclear Planning and Support

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

14.3.3 Environmental Affairs

a. Establish and implement procedures to control and establish the status of radiological'l samples.

14.3.4 Ouality Assurance

a. Review and. approve the programs of suppliers performing. work at CPS to ensure compatibility with the various status indicating sy'tems.

s L. Develop and implement programs to indicate receipt inspection status of materials, parts and components.

c. Develop and implement programs to. indicate status of nonconforming items.

d. Conduct periodic surveillance and audits of the implementation and adequacy of programs used to  ;

[^) indicate inspection, test and operating status to Ns ensure compliance with the requirements of this chapter.

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g iP NUCLEAR PRO'3 RAM a: 34'irv aooua^ ace =ANUAL PI

e H i CHAPTER V .

15 NONCONFORMING MATERIALS, PARTS OR COMPONENTS APPROVED BY: MANAGER-0UALITY ASSURANCE _ ,

de'M #MV//F 15.1 PURPOSE /SCCPE To describe the measures established and implemented to control items, services or activities which do not conform to r e q .2ir e -

ments, and the measures to control further processing, del',very or installation of nonconforming or defective items.

15.2 DESCRIPTION

The following measures have been established and implemented at CPS:

a. Control of nonconformances is accomplished in accor- .

dance with documented procedures, i

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 arca 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 3 documentation traceable to the item, including normally installed items or those removed from the  !

normally installed location. j

d. Further use or installation of nonconforming items I

is controlled in accordance with written procedures and/or instructions.

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

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. IP NUCLEAR-PRERAM j CUALITY ACCURANCE MANUAL CHAPTER 15

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f. Permissible dispositions are: a)* "use' as is", b) ]i

" rework" to drawing or specification requirements, c) " repair" to an acceptable level, d) " reject" for i that particular use, or e) "other" for non-hardware  ;

nonconformances.

g. " Repair" and " rework" dispositions are implemented  !

into the affected item in accordance with documented procedures and/or instructions,

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

i. " Rework" and " repair" actions are described, depend-ing'on complexity by individual procedures or by in-structions 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 7, documented and reviewed by the Quality Assurance Department.

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j. Reports documenting nonconforming items are reviewed by the Quality Assurance department prior to close-out 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 i l conditions adverse to quality or safety, or require a repair or use-as-is disposition, an engineering evaluation shall be performed. The engineering evaluation shall provide support for j the initial operability decision and provide the correction or l resolution for che 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, 2

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IP NUCLEAR PROORAM  ;

QUALITY ADOURANCE MANUAL CHAPTER 15 l

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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 rele'ased items are controlled in accordance with approved procedures. The nonconformance for the conditionally released item shall be corrected or resolved prior to operational reliance. l The Manager - Clinton Power Station has the authority to condi-tionally release any item for installation or operations if needed to place the plant in a safe and stable condition.

Procurement documents require that suppliers have similar nea-sures established for the identification, control, and disposi-tioning of nonconformances and that recommended dispositions of "use-as-is" or " repair" must be reported to IP for approval.

The IP Quality Assurance department conducts periodic surveil-lances and audits of the programs instituted for the identifica-tion and control of nonconformances to ensure compliance with the  !

requirements of the IP Nuclear Quality Assurance Program.

7 15.3 RESPONSIBILITIES

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15.3.1 All Nuclear Program Personnel

a. All Nuclear Program personnel are responsible for  !

identifying and reporting nonconforming materials, parts, components, services and activities.

15.3.2 Nuclear Program Departments j

a. All Nuclear Program Departments are responsible for establishing and implementing effective procedure (s) for identifying, documenting and controlling noncon-formances within the scope of their departments  ;

activities as described in this chapter of the QA manual. l 15.3.3 CPS Plant Staff

a. Authorize the conditional release of items. l

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

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IP NUCLEAR PROCRAM i- CUALITY ACCURANCE MANUAL CHAPTER 15

c. Develop and implement proce(ares,' ins truct-ions or work control documents for the correction cf noncon- 1 forming items with repair or reark dispositions.

15.3.4 Nuclear Planning S Support l a. Establish and implement an effective program for <

l processing supplier nonconformance reports.

1 15.3.5 Nuclear Station Engineering  :

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

" repair" dispositions are approved by the appropri-ate design organization. 4

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

c. Perform enginee-ing evaluations for conditionally released items.

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d. Determine acceptable alternatives to original

,, inspection or test requirements for " rework" or l " repair" dispositions.

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e. Document engineering analyses that support the i disposition of nonconf'cming items.

15.3.6 Quality Assurance

a. Establish and implement a program for verifyin, e acceptable di: position implementation as required by j the disposition of nonconformances. l

b. Establish and implement programs for the rev! e.w of nonconformances to verify effectiveness in meeting j the requirements of this chapter. j

c. Perform review of conditional release justifications.

d. Ensure that procurement documents require suppliers ,

to establish a nonconformance program consistent '

I with this chapter.

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e. Conduct periodic surveillance / audits of the Noncon-formance Program at CPS to ensure compliance with the requirements of this chapter.

15.3.7 "a_cility Review Group

a. Review documented safety evaluation for condition-ally released items in accordance with the require-ments of 10CFR50.59.

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l DATE: 2-14-89 F 00-177 (10-88) i

IP NUCLEAR PRO 5 RAM M QUALITY AOCURANCE MANUAL h CHAPTER 1

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16 CORRECTIVE ACTION l

APPROVED BYi MANAGER-0UALITY ASSURANCE ,

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16.1 PURPOSE / 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 DESCRIPTION

Each IP organization and supplier performing activities or supplying f services, materials, parts or components applicable to this program (3'l i is required to establish and implement a documented corrective action procedure (s) which assures that conditions adverse to plant safety and/or quality are promptly identified, reported to supervisory personnel, analyzed for significance and corrected. 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 safety or operability.

The IP Quality Assurance Department performs trend analysis on I 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 idantify 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,

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IP NUCLEAR PRO 2 RAM CUALITY ADCURANCE MANUAL CHAPTER 16 i<3 s V In the case of significant conditions adverse to' plant safety and/or quality, including significant adverse trends, the functional organi- i zation responsible for the significant condition will analyze the condition for causes, take appropriate and timely action to preclude recurrence and implement follow-up action as appropriate to verify implementation of corrective action. The actions taken will be documented cnd reported to appropriate levels cf management.

Corrective action is evaluated by the Quality Assurance Department to determine its effectiveness, including steps taken to identify the cause of significant conditions adverse to plant safety and/or quality and action taken to preclude recurrence. Documented correc-tive action for significant conditions adverse to plant safety is also reviewed by the Nuclear Review and Audit Group. These reviews are documented and are carried out in accordance with a documented program.

16.3 RESPONSIBILITIES 16.3.1 All Nuclear Program Personnel 1

a. All Nuclear Program personnel are responsible for identi-fying and reporting conditions adverse to plant safety f'1 and/or quality.

(. 16.3.2 Nuclear Program Departments

a. Establish and implement a corrective action procedure (s) which assures that conditions adverse to plant safety and/or quality are promptly identified, reported, anal-yzed 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 corrective action.

16.3.3 Plant Staff

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

16.3.4 Quality Assurance

a. Establish and administer a trend analysis progran for conditions adverse to plant safety and/or quality.

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F IP N~UCLEAR PR20 RAM OUALITY ACCURANCE MANUAL CHAPTER 16 (d

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b. Evaluate corrective action to deter %ine its effective-ness.

c. Conduct periodic surveillance and audits of the correc-l tive action program to ensure compliance with the re-quirements of this chapter.

16.3.5 Nuclear Station Engineering

a. Perform trend analysis of conditions documented on Main-tenance Work Requests to identify equipment failure and reliability.

16.3.6 Nuclear Review and Audit Group

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

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l IP NUCLEAR PROORAM i

rP cua'irv accua^ ace =^=ua' CHAPTER V

17 QUALITY ASSURANCE RECORDS APPROVED BY: MANAGER-OUALITY ASSURANCE , W dbN 17.1 PURPOSE / SCOPE To define the requirements and re sponsi'oilities 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 DESCRIPTION

Sufficient records, identifiable to the item or activity to which i they apply, filed in en orderly manner and retrievable are main-tained by Nuclear Planning and Support Department, Records Manage- i e ment Group, in the records storage facilities. These records j include, but are not limited to: 4

a. Preoperational and startup testing records, including procedures, data and results obtained, logs and reviews thereof and problems and their resolutions.

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b. Rece ds of design changes and modifications to applicable structures, systems or components.  !

c. Plant radiation and contamination monitoring and/or survey records,

d. Personnel radiation exposure records.

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e. Records of radioactive gaseous and liquid releases, I waste disposal and shipments.  !

f. Nuclear fuel inventory, transfer and assembly bur $1 up history records. ]

g. Records of training, qualification, certification, l experience and re-training of appropriate personnel.  !

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h. Off-site radiation and environmental monitoring i records.

1. Procurement records, including specifications, purchase requisitions, purchase orders, contracts, evidence of supplier evaluations, and source and receipt inspection records.

j. Maintenance and operating histories on applicable instrumentation, electrical and mechanical equipment and systems.

k. Radiochemistry records and reports.

1. Records of special processes affecting applicable systems, structures and components.

m. Periodic testing and surveillance records..

n, Pre-service and in-service inspection records,

o. Operating records and logs and results of reviews thereof.

rm,, p, Special testing or demonstration records.

L) q. Maintenance and repair records.

r. Minutes of the Nuclear Review and Audit Group Independent Safety Engineering Group, and Facility Review Group meetings,

s. Records of abnormal occurrences,

t. Operating procedures and records of changes made,

u. Quality Assurance audit and surveillance reports and the associated corrective action responses and eval-uations.

v. Maintenance, repair and modification inspection records,

w. Equipment calibration records.

x. Records of suppliers' qualifications.

y. Copies of drawings and vendor documents.

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z. Corrective action records.

aa. Material certification, inspection and test data, bb, Records of "as-built" or "as-modified" conditions, including material certification and test data for traceability and quality verification; reports of inspections, examinations and test results for conformance verifications; specifications, drawings and records nonconformance and their resolutions, cc. Design and construction records, dd. Copies of reports of CPS activities sent to the NRC.

ee. Records concerning radioactive material package fabrication and shipment.

ff. Records identified in Section 6.0 of the Technical Specifications.

Test and inspection records shall contain the following information:

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() a. Identity of the inspector or data recorder;

b. Type of observation;

c. Date and results of the test or inspection (quantita-tive 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 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 maintains the records for retention in the records storage facilities. The preparation, collection, review, eceptance, 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 ta be offered to IP after the suppliers no longer plan to keep them.

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o 1 The retention times for the various quality assdrance records are i in accordance with applicable requirements including 100FR50, j Technical Specifications and nationally recognized standards and codes. Records are maintained in the records storage facilities l that provides controlled access and protection against fire, ficoding, varmin and decay. Nuclear Planning and Support is I responsible for the definition and implementation of activities related to records. ,

1 Thc Quality Assurance department conducts periodic audits of records systems to ensitre compliance in meeting the IP Nuclear Quality Assurance Program requirements,.

17.3 RESPONSIBILITIES 17.3.1 Nuclear Program Departments

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

p b. Transfer completed Quality Assurance records to

('ja Nuclear Planning and Support Records Management Group for processing, maintenance and retent. ion.

17.3.2 Nuclear Planning and Support

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

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

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

17.3.3 Quality Assurance, _

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

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[ OUALITY AOCURANCE MANUAL l

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18 i AUDITS APPROVED BY: MANAGER-OUALITY ASSURANCE V./M 2/e/// l i

18.1 PURPOSE / SCOPE To define the requirements and responsibilities for implementing the program of planned and periodic audits which shall verify compliance l with the quality assurance program and determine the effectiveness  ;

in meeting program objectives.

18.2 DESCRIPTION

IP's Quality Assurance program includes provisions for planned and periodic audits designed to verify compliance with the requirements of the IP Nuclear Quality Assurance Program and to determine the effectiveness in implementing the program objectives. The IP ig)

Quality Assurance organization has the responsibility for implement-ing the QA audit program. The. audit program provides for the following:

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 Program. 4 Additionally, QA program audits include indoctrination and training programs; interface control between IP, the audited organizations and other affected organization'c; USAR commitments; and Technical Specification require-  ;

ments.

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

d. A qualification system 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 responsibi'.ities for the activities being audited.

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f. The audit team leader is charged w.ith instructing the other members during audit preparation and performance.

Personnel conducting audits shall have training and/or experience with the activities being audited.

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g. Written audit plans are developed which identify the  ;

scope, requirements, activities to be audited, organiza- ,

tions involved, applicable documents, schedule and written procedures or checklists to be used for each  !

audit, i 1

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

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1. Audit reports are distributed to responsible management of the auditing organization and to the appropriate managerial level of the organization having responsibil-ity for the area or activity audited.

j. Appropriate corrective action is developed. j i

k. Followup action (including re-audits) is taken to verify .

that corrective action has been completed and the  !

q resolution documented. I D

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 sche,dule for accomplishing the activity to assurc timely implementation of the quality assurance requirements.

The plan is reviewed periodically to insure that it to current and may be augmented at any time based on recommendations from the Nuclear Review and Audit Group, or Nuclear Program personnel as the i scope of work and other requirements for auditing an activity 4 change.

Audited organizations are required to review and provide timely written response to audit reports stating corrective action taken or planned to correct deficient areas and prevent recurrence. Audit program requirements are imposed on suppliers by appropriate con-tract or procurement documents.

Reports of internal audits are forwcrded to the Nuclear Review and Audit Group and the Independent Safety Engineering Group for program I

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IP NUCLEAR PRERAM QUALITY ACCURANCE MANUAL CHAPTER 18 i, ,) -

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evaluation. IP Manageme.nt obtains an independent audit of the IP Quality Assurance organization on an annual basis.

18.3 RESPONSIBILITIES 18.3.1 Nuclear Program Departments

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

18.3.2 Licensing and Safety

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

18.3.3 Nuclear Peview and Audit Group

a. Review reports of internal audits for program evaluation.

18.3.4 Quality Assurance p\ a. Implement an internal audit program and audit et ch IP organization performing activities within the scope of U 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 I?QA program to verify compliance with the suppliers' re-spective quality assurcnce programs., contract, speci-fications and requirements.

c. Coordinate for the Executive Vice President the performance of independent audits of the QA organization. j l

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

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IP NUCLEAR PRO'] RAM APPENDIX A CUALITY ACCURANCE MANUAL

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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 issue is designated REVISION 0 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 thcreto. 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:

l A

(') 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 compli-ance with updating instructions.

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

3. Requests for copies of the IP Nuclear Program Quality Assurance Manual or recommendations for revisions or I 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.

Propoaed revisions to the IP Nuclear Program Quality Assurance Manual will be sent to affected department managers and/or directors for their review prior to issuance by the Manager -

Quality Assurance.

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IP NUCLEAR PRECRAM OUALITY AO'"'URANCE MANUAL APPENDIX B

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./ APPENDIX D 4

SUPPLEMENTAL APPLICATION IP NUCLEAR QUALITY ASSURANCE PROGRAM This appendix details in matrix form the chapters of this mr.nual which are applicable in full or in part to:

Fire Protection  !

Security Environmental Radwaste/ Augmented D Systems Package and Transportation of Radioactive Material 10CFR50 Appendix B requires that a quality assurance program be established in writing and executed for activities affecting the safety-related function of designated structures, systems and compo-nents to an extent consistent with their importance to s a f e ty..

Table 3.2-1 in the Clinton Power Station USAR identifies specif- ,

,3 ically those structures, systems and components . that are important

) to safety.

Fire Protection, Security, Environmental and Radwaste/ Augmented D systems are specifically identified in Table 3. 2-1 of the CPS USAR and/or highlighted in several Regula;:ory 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 4.15,

" Quality Assurance for Radiological Monitoring Programs (Normal  ;

Operations) - Effluent Streams and the Environment," Revision 1 I (February 19791, states that, "The need of quality assurance is implicit in all requirements for effluent and environmental monitor-ing." 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 t es tir.g provisions are met should be established and documented." Regulatory Guida 1.17, " Protection of Nuclear i Power P). ants Against Industrial Sabotage," Revision 1 (June 1973),

V)

/

PAGE __B,- 1 o f 11 REVISION: 13 FORM N100-l?7 (10-88)

H.02872

IP NUCLEAR PRECRAM OUALITY ACCUR;ANCE MANUAL APPENDIX B f

(^) ..

v req 2 ires programmatic controls over the dAsign, construction, tes t.ing and operation of the security system at nuclear power plants.

The extent to which the IP Nuclear Quality Assurance Program applies to each of the four areas varies as defined further under subsequent sections of this appendix. The attached matrix outlines which chapters of this manual apply to Fire Protection, Security, Environmental and Radwaste/ Augmented D systems and Package and Transportation of Radioactive Material.

I i

.C

(.

I i

1 I

PAGE B-2 of 11 REVISION: 17 ,

I

^ 8

~

FORM N100-177 (10-88)

M,02172

---_-____-____________ _ _- _ _ j

.. IP NUCLEAR PROORAM i QUALITY ACCURANCE MANUAL APPENDIX B

,e _

MATRIX CHAPTERS OF THE IP NUCLEAR PROGRAM QUALITY ASSURANCE MANUAL APPLICABLE TO FIRE PROTECTION, SECURITY, ENVIRONMENTAL, AND RADWASTE/ AUGMENTED D, AND PACKAGE AND TRANSPORTATION OF RADI0 ACTIVE MATERIAL PACKAGE AND OPERATIONAL RAD'i9 ACTIVE TRANSPORTATION QA MANUAL FIRE WASTE / OF RADI0 ACTIVE CHAPTER 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 TES YES

6. YES NO YES YES YES i j 7. YES NO YES YES YES

8. NO NO YES WO YES

9. NO NO NO YES YES

10. YES NO NO YES YES

11. YES NO YES YES YES

12. NO NO YE9 'NO YES

13. NO NO YES 7ES YES

14. YES NO YES YES YES

15. YES NO YE3 YES YES

16. YES YES Yh3 YFS YES j 17 YES YES YES YES YES IPs . YES YES YES YES YES l

NOTE: Structures, systems and components subject to the above re-quirements are described by USAR Table'3.2-1 and further 3 defined by engineering specifications, drawings, procedures,  !

instructi6ns, other documents, etc.  !

j (O_./ PAGE B-3 of 11 REVISION: g l

l DATE: 2-14-89 (10-88)

o g oo-177

IP NUCLEAR PROSRAM .

QUALITY AOCURANCE MANUAL APPENDIX B O

• FIRE PROTECTION Chapter 1- Applicable Chapter 2- Applicable Chapter 3- Applicable Chapter 4- Applicable. Specification of quality assurance program requirements for suppliers of fire protection materials, equipment and services shall be on a case-by-case basis. Commercial grade or off-the-shelf items may provide an acceptable 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 procurement documents. .

Chapter 5- Applicable Chapter 6- Applicable Chapter 7- Applicable. Suppliers providing material, equipment

()

N/

and services for fire protection shall be subject to source evaluation and surveillance. The . extent of imposition of these requirements shall be determined on a case-by-case basis by the design 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 Applicable Chapter 9- Not Applicable Chapter 10 - Applicable only to inspection of those items and activities affecting the fire ptotection system within the quality assurance boundaries as specified in the USAR, Table 3.2-1 and further amplified by the appropriate design drawings.

Chapter 11 - Applicable Chapter 12 - Not Applicable Chapter 13 - Not Applicable i

PAGE B-4 of 11 REVISION: 19 FORM NIDO-177 (10-88) '

N.02172 i

i

___ _ _ _ _ _ _ . _ l

IP NUCLEAR PRESRAM CUALITY ACOURANCE MANUAL APPENDIX B (D

Chapter 14 - Applicable Chapter 15 - Applicable Chapter 16 - Applicable Chapter 17 - Applicable to documents designated as Quality Assur-ance Records generated in the implementation of the Fire Protection program and consistent with the requirements identified in Chapter 10 above. Records i 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, instruc-tions, procedures and drawings and inspection and test activities. ,

l iO

%)

,n h PAGE B-5 of 11 REVISION: ,9 i

{

FORM NIDO-177 (f0-88)

M,02172

IP NUCLEAR PR2 CRAM . .

l. QUALITY ACCURANCE MANUAL APPENDIX B n '

SECURITY i

Chapter 1- Not Applicable Chapter 2- Not Applicable Chapter 3- Not Applicable Chapter 4- Not Applicable Chapter 5- Not Applicable Chapter 6- Not Applicable Chapter 7- Not Applicable Chapter Nut Applicable Chapter 9- Not Applicable l

Chapter 10 - Not Applicable Chapter 11 - Not Applicable

/3,

'\_/ Chapter 12 - Not Applicable Chapter 13 - Not Applicable Chapter 14 - Not Applicable (

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

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

l

)

i d PAGE B-6 of 11

~

REVISION: la__ _

DATE, 2-14-89 (

(10-88?

FORM NIOO-177 M oai?2

_ o

IP NUCLEAR PRO 2 RAM QUALITY ACOURANCE MANUAL APPENDIX B

, )

(O ENVIRONMENTAL Chapter 1- Applicable Chapter 2- Applicable Chapter 3- Not Applicable Chapter 4- Applicable to procurement of nonitoring services to be performed by contractors providing services dealing with radiological data and to radionuclides reference standards used for calibration of radiation measure-ment systems.

Chapter 5- Applicable to all activities related to carrying out the radiological monitoring progran including: sample collection; packaging, shipment and receipt of samples I for off-site analysis; procurement, maintenance, stora6e and use of radioactivity reference standards; calibration and checks of radiation and radioactivity measurement systems; and reduction, evaluation and reporting of data.

O Chapter 6- Applicable to procedures and instructions required by  !

d Chapter 5.

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

Chapter 8- Applicable only to radiological sample collection, identification, packaging, shipping, receiving, storage and analysis.

Chapter 9- Not Applicable Chapter 10 - Not Applicable Cbapter 11 - Applicable to radioactivity measurements of samples, instrument backgrounds, replicate samples and analyti-cal blanks; data reduction and verification; computer program documentation and verification.

[V) PAGE B-7 of 11 REVISION: 13 '

~

FORM NIDO-177 (10-88)

H.02172

IP NUCLEAR PRECRAM .

GUALITY ACCURANCE MANUAL APPENDIX B 4

./%s .

L) Chapter 12 - Applicable to laboratory instruments for radiation and radioactivity measurement, continuous radiological effluent monitoring systems and flow-rate measuring devices associated with radiological effluent monitor-ing systems.

Chapter 13 - Applicable to radiological samples only.

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

Chapter 15 - Applicable Chapter 16 - Applicable Chapter 17 - Applicable to personnel training and qualification; field and in-plant collection of samples; continuous effluent monitoring; sample receipt and laboratory identification; sample preparation and radiochemical processing; radioactivity measurements of samples, instrument backgrounds and analytical blanks; data reduction and verification; instrument calibration and calibration standards; computer program documentation; audits; and corrective action.

Chapter 18 - Applicable NOTE: The title of this appendix should not be construed to imply that the designated chapters are applicable to the Environmental Affairs Department only. Rather, applica-bility is for the entire Illinois Power Company.

Specifically affected departments or groups are called out in each chapter.

l I

i i

(3/

f PAGE B-8 of 11 REVISION: 13 q FORM N100-177 (10-88)

N.02172 l

IP NUCLEAR PR2 CRAM- ,

QUALITY AOCURANCE MANUAL APPENDIX B G RADIOACTIVE WASTE / AUGMENTED "D" Chapter 1- Applicable Chapter 2- Applicable Chapter 3- Applicable Chapter 4- Applicable. Specification of quality assurance program requirements for suppliers of radioactive waste /. augmented D materials , equipment and services shall be on a case-by-case basis. Commercial grade or off-the-site items may provide an acceptable level of quality based on the nature of the item. This deter-mination shall be made jointly by Engineering and Quality Assurance personnel prior to issuance of procurement documents.

Chapter 5- Applicable Chapter 6- Applicable Chapter 7- Applicable. Suppliers providing material, equipment T and services for radioactive waste / augmented D shall O be subject to source evaluation and surveillance. The extent of imposition of these requirements shall be determined on a case-by-case basis by the design and quality assurance organizations responsible for review and approval of the procurement specifications. Mea-sures shall be established, as appropriate, for examination of products upon delivery.

Chapter 8- Not Applicabl'e Chapter 9- Applicable to the qualification of welders and welding rocedures (ASME Section IX) for Radwaste/ Augmented p'D" sys tem. (pressure boundaries only). )

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

Chapter 11 - Applicable Chapter 12 - Not Applicable l l

f

! PAGE B-9 of 11 REVISION: p FORM NIDO-177 (10-88)

H.02(12

IP NUCLEAR PROSRAM .

QUALITY AOCURANCE MANUAL

~

APPENDIX B

(~ . ,

V' Chapter 13 - Applicable Chapter 14 - Applicable Chapter 15 - Applicable Chapter 16 - ' Applicable Chapter 17 - Applicable  !

Chapter 18 - Applicable l

O I

O- PAG,E B-10 of 11 REVISION: 13 DATE 2-14-89  !

[0gg,yjoo-177 (10-88) l f

i___________j__________ _ . . _ . _ i

1 IP NUCLEAR PROCRAM J QUALITY ACCURANCE MANUAL APPENDI.X B

.i

,cx l s

) ' FACKAGE AND TRANSPORTATION OF RADIOACTIVE MATERIAL .

i Chapter 1- Applicable Chapter 2- App.'.icable Chapter 3- Applicable

)

Chapter 4- Applicable Chapter. 5- Applicable Chapter 6- Applicable Chapter 7- Applicable Chapter 8- Applicable  !

Chapter 9- Applicable Chapter 10 - Applicable Chapter 11 - Applicable

, Chapter 12.- Applicable Chapter 13 - Applicable Chapter 14 - Applicable Chapter 15 - Applicable Chapter 16 - Applicable Chapter 17 - Applicable Chapter 18 - Applicable r~%

(_,) PAGE B-11 of 11 REVISION: 19

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'L Justification This was_ replaced'with "'... shall he corrected Jor resolved

+ prior to operational reliance." The correction of a noncon-forming item is defined as "The process of bringing a nonconforming item into conformity'with an approved design."

The resolution of a nonconforming item is defined as "The process by which a nonconforming item is corrected.or deter-mined . to adequately perform its design- function without '

adversely affecting ' safety. - -The resolution may contain-controls or limitations that are to apply until the.noncon-formance is fully ' corrected."

These definitions have been added to the glossary nection of the-QAM, revision-19.

B.. In the event 'it is necessary to operate the nonconforming item, an engineering evaluation will be performed indicating operations-can safely proceed. -If the - engineering evalua-tion indicates that'a safety evaluation.per 100FR50.59, and the review will be documented.

Justification-.

Reference justification for item 1.C.

)

C. "The Manager - Clinton Power Station authorizes operations of the item."

Justification Reference justification for item-1.D.

(BLANKE)

L

_____.____.--_______.__._m_ _ _ _ _ _ _ _ _ _ - _ _ _ . _ - _ _ _ . _ . _ _ . _ m_ . _ _ _ ._

Jj;f -

s. 1 N -

1

'1 SAFETY EVALUATION FORM. )

a. :l

~ IP e!uclear-Program Document Evaluated: Quality Assurance Manua_1. R/19 L&S Log g 96-0397 1

References:

Technical Specification. Section 6.0

]

'l Corocrate Nucinar Proceduroc j ANSI N18.7 - 1976 s

NOTE: Each block (including the lines provided for a written response following the YES/NO questions) must be completed.

Describe the basic document or system and the changes being made.

Include the interface / impact on other systems.

The IP' Nuclear Proaram OA fianual describes the cuality nroaram reouirezeats.

and associated ' Nuclear Proaram departmental responsibilities. The 6hances_ {

e nade were to reflect current Nuclear Proaram organization structure and _

responisbilities. incorporate NRAG comments from revision 183L1he CA j

n flanual . and incorporate NRC comments from revision 18 of the OA Manual . 1 These chances imoact the USAR Chanter 17.7 and Chantor 'i.FL A2 A% e ~ o k <J ea k c Lw <- i.s o r s u rdsl) ~h n dv GA nedbrig s C h a pa-1 4 e w ye.s. n 12/2afd -p ,j BLOCK A - 10CFR50.59 APPLICABILITY Answer the question corresponding to the type of change being made (i.e., question "a" for modifications question "b" for procedures; question "c" for tests . and q' uestion For "d" for experiments). Mark all other questions N/A". any auestion(s) not marked "N/A", provide an explanation for your imswer.

YES NO X N/A a. Is this a change to the facility as described in thc- FSAR7 x YES NO N/A b. Is this a new procedure or a change to a procedure as described in the FSAR?

YES NO y N/A c. Is this a test not described in the FSAR?

YES NO X N/A d. Is this an experiment not described in the  ;

FSAR?

Y /? dascrW'M of ch ~, as ~ta n&GA mus ~c ~Sm FC6 rcaea

& cyf rous e m / f.3 ['( a re. n tkWA .

Page 1 of _

____.__i.____ _m .._____.______..__..m_ _ . _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ . - . _ . _ . _m__._ . _ _ _ _ _ _ __ _ _ _ _ . _ _ . _ _ _- _

Safety Evaluation 88-0397 ,

Descrip_t,_ipn_of i Changes 1 The following changes were made to the Illinois Nuclear Program QA Manual after Safety Evaluaticn 88-0397 was reviewed and approved by FRG on 1/3/S9.

The description of the changes are as follows:

Chapter 1 Sections 1.2.,2.13, 1.2.2.15, and 1.2.2.16 were revised to include the statement that the department manager is responsible to ensure activities are performed in accordance with the QA Program.

This change was made to be consistent with other department managers' descriptions in Chapter 1.

Section 1.2.3.2 was revised to delete reference to surveillance findings. Condition Reports are issued to document deficiencies identified during a surveillance.

Chapter 2 Section 2.1 was revised to delete reference to the Manager -

QA approving changes to USAR Table 3.2-1. This requirement is covered by Chapters 1 and 2, sections

') . 2 . 3 . j an d 2 . 3 . 6 . c . The requirement was considered to be redundant.

)

Chapter ,4_

Section 4.2 and 4.3.4.c was re'iised to delete reference to surveillance. QA performs limited scoped audits on Chapter 4 activities versus surveillance.

Chapter l' Section 7.3.4.d was revised to add "as necessary" for the performance of source inspections at suppliers' facilitics, This change was made to be consistent with tha same requirement described in section 7.2.

Chapter 8 Section 8.2.f was revised to replace "Whenever possible" l with "When employed" t, be consistent with ANSI N18.7.

1

~ ~

h(!) i/.sol[4

_ -- 1

O, o, b ,

I Section 8.3.4 was revised to delete what was section 8.3.4.a Review and approve supplier procedures for the identification and control of items. This requirement ,

is covered under Chapters 4 and 7, sections 4.3.4b and 7.3.4.b.

Chapter 10 Section 10.2 was revised to add "in accordance with specified insoection criteria". This change clarifies

.QA's responsibility for evaluating and determining the acceptability of inspection results.

Chapter 14 Sections 14.3.1.b and 14.3.4.a were revised to make the requirements consistent with the same requirement described in section 14.2.

Chapter 17 Sections 17.2 and 17.3.3 were revised to delete reference to rurveillances. QA performs limited scoped audits. on Chapter 17 activities versus surveillance.

Chapter 18 Section 18.2 was revised to clarify the Supervisor - Audits responsibilities and to be consistent with ANSI N45.2.12.

Section 18.3.was revised to add the responsibilities for Licensing and Safety and NRAG as described in section 18.2.

The above changes were evaluated as not reducing previous commitments accepted by the NRC.

Safety Evaluation 88-0397 has been re-evaluated and no changes were identified.

$ '/3slff' 1

i l

s SAFETY EVALUATION FORM (Con't) ,

1 BLOCK A - 10CFR50.59 APPLICABILITY (Con't)-

Explain the reason for the YES/NO Answer:

The IP Nuclear Proaram 0A Manual is the USAR Chapter 17.2 by reference.

Chapter 1.8 of the USAR, IP cositions for Rea. Guides 1.33 and 1.123 will reauire revision uoan aooroval of the OA Manual to reflect the chances ninte,'

l to Cha NOTE. pter 15 of the QA Manual regardina conditional release.If any of the questions in Bl 10CFR50.59 applies to the change or activity, and it will be reported to the NRC in the annual report.

BLOCK B - RADWASTE TREATMENT SYSTEMS YES X NO The proposed activity involves a modification to the Radiological Waste Treatment Systems described in Chapter 11 of the FSAR.

Because: The chances are programmatic in nature and do not imoact facility equipment, systems or structures.

~

If the above statement was answered YES, complete CNP 1.09 Attachment 3, " Safety Evaluation for Changes to Radioactive Waste Treatment System"

{

BLOCK C - TECH. SPEC. / LICENSE IMPACT l l

r I

YES X NO The proposed activity involves a change to any i

' ~ - ~

part of the Operating License, including the ]

Technical Specification and Appendix B. <

i Because: No change to the Operating License, NPF-55 or Appendix A, Techni-  !

i cal Specifications is required. The OL/TS reference the OA Manual and do _

not contain the avality proaran retirements / responsibilities.

BLOCK G - UNREVIEWED SAFETY QUESTION Implementation or performance of the proposed activity will:

__YES X NO a. Increase the probability of occurrence of an accident previously evaluc.ted in the FSAR.

YES x NO b. Increase the censeauences of an accident previously evaluated in the FSAR.

Page 2 of _

y l .

i

'6. -

j j

i i

SAFETY EVALUATION FORM (Con't) l 3 LOCK D - UNREVIEWED SAFETY OUESTION (Con't) l 1

i YES X NO c. Create the possibility of an accident of a different type than any already evaluated in i the FSAR. (

YES X NO d. Increase the probability.of a malfunction of  !

equipment importent to safety previously l evaluated in the FSAR. {

i YES X NO e. Increase the consequences of a malfunction of equipment important to safety previously evaluated in tae FSAR. 4 YES X N0 f. Crente the possibility of a malfunction of equipment important to safety different than previously evaluated in the FSAR.

YES 1 NO g. Reduce the margin of safety as defined in the basis for any technical specification.

/

Provide the written bases for your answers to the YES/NO 1 questions. Include discussions of the system / procedural d functions and the effect of the change on these functions, operating characterisi.ics , hazards analyses , radioactive releases, and interfacing systems. (Use additional pages if necessary)

Achanges tc the IP Nuclear Program 0A Manual do not affect the desian functions, characteristics, confj2uration, or analysis of comoonents.

systems, or structures cover 6d by the IP Nuclear 0A Procram. The bqEi s is the IP Nuclear QA Proaram provides' tSe nroarammatic administrative controls and associated deJ artmental responsibilities for implemer, tina the GA Procram  !

at CPS. Additionally, in accordance with 10CFR50.54(a), the chances made to the QA Manual have been evaluated as not reducina nreyious commitments J accepted by the NRC. _

If any statement in this block was answered YES, the action described in the evaluated document involves an Unreviewed Safety Question Page 3 of _

,6, .

9, , r, s. <

),o, .b

i S'FETY' A EVALUATION FORM ;(Con't)' f BLOCK E -

SUMMARY

Check.the applicable. boy.es

[X) The valuated document does not involve .a' change to the Technical Specifications', Operating License, or an- _

f Unreviewed Safety Question. Proceed with implementation. )

[.- ] - The evaluate d document involves a change to the Technical' Specifications .or the Operating Licer.se. NRC approval is required- before impler:.entation.

() The evaluated document imiolves .an Unreviewed . Safety Questien. NRC approval is required bef e implementation.

k //Jo/re/

ORIGINATOR JoL /3/ lee Print Name

- M 2 e' % A . Le t Si na ur,e/Date j

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Page 4 of _

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Safety Evaluation -

t Programmatic Review Checklist I

- tu tog n 68-o39 7 Dcicu.aert reviewed: 'CP NUC'd4E FRoGrzhu cpvwrtt ASSurzwCE MA~uAL , /2/49  ;

NOTE: Questions should be ansvered based on the as received fore, not af ter coc:sent resolutton.

7cs Ne N/A

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1

/ 1. Has the docuxnt or activity evaluated been properly identified?

g _ _ 2. Does the description adoquately tell vhat's being done or changed?

d _ _ 3. ]

Is block A properly filled out, is it consistent with hRC h.terpretations, and 1 is there adequate justification?

V' 4 Does bicek E give an adequate reason if checked NO, based on FSAR cystem definition or equivaient authority?

[ _ _ 5. If ho, does block C give an adequate justification shy the Tech Specs, including er.vironmental Tech Specs and Operating License do not need to be changed?

6. If YES, does block C provide a reference to either the Proposed Tech Spec Change Package number or the Proposed 1.icense Change nu:ber?

/ 7 Does block D give the reasons for the YES/NO itecs checked! Are they valid reasons that vould stand up Independently under audit? Is the full ocope of the description covered?

/ 6 Have specific cections of the TSAR, Technical Specifications, and other documents used in answerir.g tb questions on the fin been referenced?

n/ _ _ 9. Have the above FSAR 6 Technical Specification reference.; been properly interpreted, and do the other references appeat appropriate? 4

/ 10. Have applicable codes, standards, and reEular.icns been considered?

7 11. Are the supporting analyses (if requirei, sttached?

_ _ g 2. Eave the suprorting anslyses been properly documented end de they cover the approriate scope?

7 13. Eave requir-d reviews been perforted?

. / 14 It the HSED 7echnical Review Checklist attached?

/ l?. The correct response is checked in Eleck E.

d6 Have all other areas, if icquired, been addressed? (list, if any) j Prob 1 cts Identified (if any)

' $ GW W

,Y Wt Corrective Action w - . e gevg u

1Date

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