ML20236G037

Rev 17 to Nuclear Power Operational QA Manual

ML20236G037
Person / Time
Site:	Clinton
Issue date:	10/30/1986
From:	ILLINOIS POWER CO.
To:
Shared Package
ML20236F870	List: ML20236F903 ML20236G037 U-600988, Forwards Revs 17 & 18 to Nuclear Power Operational QA Manual & Description of Changes,Per 10CFR50.54(a)
References
NUDOCS 8708040109
Download: ML20236G037 (39)

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i 4E.100 V(~T Q-06098 October 30, 1986 IP NUCLEAR POWER OPERATIONAL QUALITY ASSURANCE MANUAL (0QAM)

Revision 17 Summarv i

Revision 17 of the OQAM expanded the authority of QA I personnel to stop work when significant quality problems are identified, The definitions of Curtailment / Held in the glossary was deleted and the definition of stop work was expanded and clarified.

l Evaluation i

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'/ The changes made to the IP OQM4 do not 1) reduce the authority, independence or management reporting levels previously established for organizations performing Quality Assurance functions; or 2) reduce commitments or effectiveness of controls previously established over activities effecting quality of CPS structures, l systems, or components.

1. E this re'ciriDr c'cer nc; *(tuce c uc 11 + ' -~ctrar c orr i tr.er t r this revisier shall be submitted to the NRC during the next annual submittal. j l

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Prepared by, [ !/M M% / i N O M N l

Supervisor-QuglityTechnicaLSupport Approved by, [# /6 /J./fC

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.Page 7 of 10-ILLINOIS POWER COMPANY COKFORATE NUCLEAR FROCEDURE TITLE: NUCLEAR SAFETY REVIEWS ATTACHMENT 2 10CTR50.59 SATETY EVALUATION TORM Document Evaluated: Operational' Qu . l ity LgsLeg,(i-$

g Assurance Manual Revision 17 O

References:

CPS FSAR 17.2 D-l' NOTE: Every statere'nt or conclusion (yes or no) on this fore cust be justified in the. space provided. (Use additional paEes if necessary.)

FLOCK A .

The decutent tc vhich this.evaluatici, applies 17,vcives a; YES y NO a. Change to Clinton Tewer Station pe nanert equiptent, systems or structures. ACh, crc 2 YES _ NO b. Adescribed procedure or a change to a procedure as in the TSAR.

YES x NO c. Test not described in the TSAR.

~ YES T NO d. Experiment not described in the TSAR.

Eecause: The Operat ional OA Manual and the' CPS TSAR Chapter 17.2 are worded identically in the areas beine revised. Therefore, a chance in the OA Manual also involves a chance to the procram described in the TSAPs . 0A Manual revises the authorf t v of OA personnel to stop vork and does not c h an c e at.v facilitt eouipment/

sy s t ems / s t ruc tu r e, and does not involve any test on equipment.

.If any of the above st aterents were anrwered "YES". coeple te blocks E, C. D, and E. If all of the abcse staterents were answered "NO" a 20CTR50.59 review is not required completion of blocks P and D is optionali block C shall be completed.

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( Revisier : l Page e cf 10 l 1

ILLINOIS POWER COMPANY CORPORATE IWCLEAR FROCEDURE 1

TITLE: NUCLEAR SAFETY REVIEWS i

I ATTACFMENT 2 (Con't)

ELOCK E The de cu::e n t te which this eva; cat:ce ap;;;e s inv:.ves

~ YES ~X NO a ecdif;ca::ct to the Rad.:;eg;:a; Vas :e Tre a::en:

Eyster, as des: .ted in the TIM J

Ee:s.se: The chance i:rpact s the authority of QA personnel to l l I

l sten vork this chance does not have any f acility equipraent, syst m or st ruc ture impac t . ,

1 If the abcve staterent was answered "YES' cer;,e:c A : : a c hte r.: .:

Safe: Eva;uatic,n for Changes te Rad;cac:n e Waste Trea::en: Sys:er. )

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k YI! x NC ne dc:::ert :: wh;ch tr.a eca;.a:;r- 4:;.;,5 tr.: ves-a charge tc the T e c hr. i c a .'. 5 ; e c ; f ; c a : e r 's :: 0; era:;r; ,

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Ee :a.s e : Neither the license or the t echnical specifications i contain infor-ation relat ed to the authority of QA for the .j,

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n1 x~~ N; a. Increase th ;;cbati..*, cf et:;r:e :e :: a acc; der-prev;cusly evalue:ed ;n the TEM .

H7 x N; b. Incre ase the cetsecue :es ci at at:; der: ;; e virus ' . 3 eva. a:e: ;; :te TEM .

c. Create :he rf a l HI -x S; type ! u. . a r. n *.: .: s s ,i t ; . ;: ya.ua*eC. r e a in d ytri e '. a . a* S. a - i d e - : cf.A.d;ffere-:

YEI x NC d. Increase the p:: tat;;; ef a za:fu :::er : f equ;; ent :; :: t a r.: :c 's aic: . ;;ev;eu s ; eva;;a:ed in the TEM 1

n! x NO e. Increase the censecuences ef a za'.f;tc ;;r,0f l e c,;; pte n t ; :::: ant t: he safc - : *i.; 5.y l

i eva;uatec ;- the T S M-ns - NC f. Create the ::ssit;.;;y ef,8 r3 : ' r;; ; M ' of f

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CSP 1.09 Revision 1 Page 9 of 10 i

ILLINOIS POk'ER COMPANY CORPORATE NUCLEAR PROCEDURE TITLE: NUCLEAR SAFETY REVIEWS ATTACHMENT 2 (Con't) 1 BLOCK D (Cen'ti YIS x N0 g. Feduce the cargir. of saf e ty as de fir.ed ::. t he t asis fer any :echr.:ca; s;ec.f::a::c-Be:ause: This chance expands the authority of QA personnel to-stop work when significant quality problems are identified, nrovided the health and safety of the public or impact on the canability to safelv shut down the plant are not affected. .

Therefore. this chance reduces the' probability and consequences nf nn nceurrence. accident, rnal fuc ti on, and increases the margin ,

k nc e n g c,, y _

f any stateret

in thir sect;en was answerec "Yi,!'. the action ce s : itec in the eva!.a:e d d::::er: :nve;.es ar 'J :eviewe: Safe:.

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Check the applicab;e behes:

[x ] The evalua:ed dccc:ent d:es nc invc!ve a c?s.te tc the Tectrical S;e ifica:::nr c: Op e r a ::,ng *.i:ent e c: an ';r r e . : e .e d S a f t : -

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ILLINOIS POWER COMPANY PROCEDLTRE L.7 L&S PROCEDLTRE REVISION 3 ISSUED 10/10/86

' &v Progra:scatic Review Checklist 1AS leg 8:

7b Document reviewed: 'b b% k I9 ,

NOTE: Questions should be anrwered based on the as received fort, not af ter coament resolution.

i Yes No N/A 1 Does block A properly identify the reason for the safety evaluation? j

_t/ _ _ . 1.

2. Does the description in block A adequately tell what's being done or changed?

/ 3. Does block B give an adequate reason if checked No, based on TSAR system definition A _ _

or equivalent authority?

D 4 If NO, does block C give an adequate justification why the Tech Specs do not need to be changed?

5. Does block D give the reasons for the YES/NO items checked? Are they valid reasons that would stand up independently under audit?

I' 6. Have specific sections of the FSAR, Technical Specifications, and other documents used in answering the questions on the forn been referenced? -

D 7. Have the above referenced docuw nts been properly interpreted?

t/ 8. Rave applicable codes, standards, and regulations been considered?

Y 9. Are the supporting analyses (if required) attached?

_v 10, Have the supperting atalytes been perf:rmed using appr:ved methods!

g _ 11. Rase required revie'es been perferred?

The reco::cended classification on the Safety Evaluation Ter:t is acceptable.

_ _ 12.

13. Have all other areas, if required, been addressed? (list, if any)

Preblems Identified (if any)

Corrective Action I  % d [c

'J.S RevieJer /- Date ATIACHMENT 1,.7 1 e

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l IP NUCLEAR POWER '

OPERATIONAL QUALITY ASSURANCE MANUAL

^

l AUTHORIZATION The IP Nuclear Power Operational Quality Assurance Program applies to every member of the Company performing work related to CPS and covered by the Manual. Specific responsibilities shall be assigned by IP canagement and supervision, consistent with the requirements described in this Quality Assurance Manual. It is emphasized that the portion of the program assigned to the Quality Assurance organization primarily concerns verification activities, such as inspection, auditing, surveillance,'evaluat-ing and reporting ef festiveness , 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 respcnsn ilitics, this manual is given the felicwin6 DEPARTMENTAL AUTHORIZATIONS:

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Manager - Nuclear Station

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LAs.L- w Manager - Scheduling and Director - Euclear Training Out age Ma .agement f i Manager WC -

Nuclear grogram

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Tanager - Quility Assurance PAGE iY ~ 1 Of 1 REvtsl0N: '17 Form N100177 (3 83) DATE: 11/12/86

1

. lP NUCLEAR POWER OPERATIONAL QUALITY ASSURA'NCE MANUAL LIST OF EFFECTIVE PAGES O LIST OF EFFECTIVE PAGES Revision -17 i

The following pages and their indicated revision and date of  ;

issue are included in the IP Nuclear Power Operational Quality l Assurance Manual.

1 i

fI Page No. Rev. .Date 1

T of C 11 02-26-85 l 1-1 17 11-12-86 i j 11 2 02-26-85 1 iii 13 05-21-86 j iv-1 17 11-12-86 1 v v-9 13 11-12-86 {

1 1-16 17 11-12-86 1 l '2-1 - 2-21 16 05-21-86 I

' ('3 3-1 - 3-7 14 05-21-86 U 4-1 - 4-4 13 05-21-86 5-1 - 5-4 14 05-21-86 6 6-5 14 .05-21-86 1 5 13 05-21-86

, 8-1 - 8-3 12 08-15-85 9-1 - 9-4 14 05-21-86

(-1 - 10-4 13 02-06-86 11-1 - 21 - 12 06-15-05 l 12 12-4 13 02-06-86 1 13 13-3 12 08-15-85' 14 14-3 12 08-15-85 15 15-6 14 05-21-86 16 16-4 13 12-06-85 17 17-6 15 05-21-86 16 18-4 14 05-21-86 A A-2' 12 05-21-86 B B-8 11 02-26-85 C-1 11 02-26-85

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pgg, 1-1 of-1 R EVI$l0H:

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Form N100177 (3 83) 'DATE:

i

IP NUCLEAR POWER OPERATIONAL QUALITY ASSURANCE MANUAL O

GLOSSARY OF TERMS Acceptance Criteria - Specified limits placed on characteristics

'of an item, process, or service defined in codes, standards, or l

other requirement docurren t s .

Administrative or Management Control Procedures - Procedures approved and issued by the appropriate management level that specify responsibilities, requirements , and control methods to be .

. employed by those personnel engaged in an activity when that activity is within the scope of more.than one internal organiza-tion or department.

Audit - A documented activity performed in accordance with writ ten procedures or checklists to verify,' by examination and evaluation of obj ective evidence , that applicable elements of the quality assurance program have been developed, documented, and effe ctively itiplemented 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.

Auditor-in-Training - An individual who has been identified to receive.the training necessary to becoce an' auditor. Generally, W s ir n-M duci hcs ;rcvicusly ccc.uirec ti.c technice3, adtinis-rz tive , and;'er u nagerem cotpet e nc e to perfert discrete dutics l in support of the overall cudit.

l 1

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-qualifie6 party attesting that the items or services are in accordcnce with specified requirements'and accompanied by addi- J tional information to subtrantiate the statenent.

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

Certified Test Rep ort - A written and signed document approved by O. e see 111ee Pert 7 thet c =teime eurricieet eete eme imr rmetiom  ;

f' 9 I PAGE i

' R E VISION: -

form N100-1U (3 83) ' DATE: 11/12/86

IP NUCLEAR POWER GLOSSARY OF TERMS OPERATIONAL QUALITY ASSURANCE MANUAL to verify the actual properties of items and thc actual results-of all required tests.

Characteristic - Any property or attribute of an item,, process,  !

or. service that is distinct, describable, and measurable, as.  !

conforming or nonconforming to specified quality requirements. .

Quality characteristics are generally identified in specifica- I tions 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 Feuer Station operations, such as the American Scciety Mechanical Engineers (ASME) boiler and Pre ssure  !

' es sel Cecc .

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 bcsis of the O

manufacturer's published specifications or descriptions. l Condition Adverse to Quality - An all inclusive term used in reference to any of the following: failures, malfunctions, deficiencies, d'efective items, and nonconformances. A signifi-cant condition adverse-to quality is one which, if uncorrected, cculd have a serious effect on safety'or oper' ability.

Centractc: - Ar: organ:;ction under centract fer furnishing itcr.s-or services to IP. It includes .the terms vender, supplie r ,

sub-contractor, fcbricator, and sub-tier levels of these where 3 appropriate.

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

Corrective Action - The action required to correct adverse ,

conditions in equipment, material, processes, procedures, or '

activities when noted. Action taken may be remedial action to-correct the specific conoition, generic action to preclude recurrences, or both, p)

(- CPS - Abbreviation for Clinton Power Sta tion.  !

1 U 9 PAGE"~ g m - m, %m m 11/12/86 l

IP NUCLEAR POWER GLOSSARY OF TERMS -

OPERATIONAL QUALITY ASSURANCE MANUAL O

Departmental Procedures cr Instructions - Procedures or instruc-tions approved and issued within a department which provide more detailed direction to personnel.

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

Documents - Collective term used to describe all written or

">ictorial information that directs or shows how an activity-is.to ]

se accomplished.- Documents include, but are not limited to, )

i drawings, procedures, instructions, and changes'thereto.

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

Examinatier - An clerent cf inspection consisting of investiga-tion of materials, components, supplies, or services to determine -

conformance to those specified requirements which can be deter . .-

mined by such investigation. Examination.is usually nonde'struc- )

tive and includes simple physical manipulation, gaging, and.

measurement.

i O externe 1 tudits - Audite ef these Portione ef centrectors .

vendors' and suppliers' quality assurance program activities not retained under IP's direct control and not within the IP orga-l nizational structure.

Facility Review Group -

(FRG) - An on-site committee whose function is to advise the Power Plant Manager on catters related

nuc M r safen Findinc - An observation or cerdition which is of sufficient concern to merit submittal to the responsible organization in- 1 writing and requires a written response.

Follow-up - Action involving direct communication with the responciole organization to cssure a timely written respense to findings, adequacy of the response, and corrective action accom- q plishment as scheduled.  !

l FSAR - Abbreviation for the Final Safety Analysis Report, which -l is the document submitted by IP to the Nuclear Regulatory Commis- ]

sion to obtain an Operating License (OL).

Hold Point - An inspection point in a procedure, activity, or  !

process-at which the performer is required to stop to allow an inspector to accomplish certain predesignated / planned inspec-tions. The procedure, activity, or process shall not proceed PAGE v-3 of 9 R EVl510N:

Form N100177 (3 83) DATE: 11/12/86 l J

IP NUCLEAR POWER GLOSSARY OF TERMS OPERATIONAL QUALITY ASSURANCE MANUAL O

L) past the hold pcant without the QC inspector being present and ,

authorizing to proceed.

Inspection - A phtse of quality control which by means of exami-nation, observation, or measurement determines the conformance of  !

ma terials , supplies , components, parts, appurtenances, systems, processes or structures to predetermined quality requirements.

Inspection Point - Those points or steps in a procedure, activi-ty, or process which requires some type of QC verification action.

Int erf ace - 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 1 called an " interface" relation. One example of interface is when c.n e organ;; et ion mu s t perforn a step which is a prcrequis;;c to another organization accomplishing its function. Interface can l

also mean that several organizations accomplishing similar l activities are under the coordination control of one organiza-tion.

l l Int ernal Audit s - Audit s of those portions of IP's Quclity

(-)T

(_ Assurance program activities retained under direct Company control and within the IP organizational structure.

1 I_P - Abbreviation for Illinois Power. 1 Item - Any level of unit assembly, including structure, system, sub-system, sub a s sembly , componen t , part, or material.

Les6 ica_,:r - An individual c,ttlifiec :c ccrtified tc crgc-irc j ind cdrect an audit, report audit fincings, and evaluate correc-

~ '

tive action.

Mea suring and Test Equipment - Equipment used to quantitatively l l generate or measure physical parameters with a knosm degree of ac curacy for the purpose of calibration, inspeetion, test, or repair of plant mechanical, electrical, or instrument / control l i

equiptent. (This does not include installed plant equiptent.)

Modification - A planned, engineered, and approved change in ,

plant design or operation 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-e- ment. Items of noncompliance are categorized into these three

(_)s categories of severity: violations, infractions, and deficien-cies.

PAGE"~4 Of 9 13 R EVl510N:

_ _ _ _ ggm gg g

IP NUCLEAR POWER '

f GLOSSARY OF TERMS OPERATIONAL QUALFTY ASSURANCE MANUAL O

Nonconformance - A deviation 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.

i NRAG - Abbreviation for Nuclear Review and Audit Group.

Objective Evidence - Any statement of fact. .information, or record, either quantitative or qualit ative, pertaining to the quality of an item or service based on observations,

+

measure- i ments, or tests which can be verified. 2 1

l Owner - The person, group,-company, or corporation who will have l or hcs title .to the facility or installation.under construction. ]

Plant Staff - That organization which is directly responsible ior #

the operation of the Clinton Power Station. ~T he Plant Staff includes operations, technical, maintenance,(radiation protec-tion, chemistry, radwaste, and support departments.

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

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

Procurement documents include such items as contracts, letters of tr ier * , purdere crders, cr prepessls au their ecccr:sr:c V-tch cuthorites the seller tc perfcrm service s cr supply equi mcr.:,

materials, or fccilities en behalf of thc perchaser.

l 1 Qualification - (Personnel) - The characteristics or abilities gained through training or experience or both that enable an individual to perform a required function.'

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

Quality Assurance Record - Those delineated completed records which furnish documentary evidence of the quality of items and/or activities affecting quality.

Quality Control - Those quality assurance actions which provide a e-s- means to control and measure the characteristics of an item, y t process, or facility to established requirements.

I i PIGE v-5 of 9' 13 REVISION:

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.m ~m-m& mm 11/12/66

IP NUCLEAR POWER GLOSSARY. OF TERMS OPERATIONAL QUALITY ASSURANCE MANUAL Receipt Inspection - An inspection performed by Quality Assurance Inspectors verifying that the items are in satisfactory condi-

. tion, that.they match the purchase order requirements, and that required documentation accurately reflects the . item (s) received.

Visual and physical inspection will be performed as necessary to determine the acceptability of the item (s).

Records - A completed document which furnishes evidence'of the quality of items and/or activities affecting quality, or which satisfies regulatory, code, corporate, or department require-ments. Records include but are not limited to: operating logs, inspection results, test results, audit reports, material analy-sis reports, radiographs, qualification data, etc.

Regulations - Collective term used to describe ' the governing directives and laws applicable to the Clinton Power Sta tion operatier, 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 nct ccnform.to the original requirement.

() 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 - Certain structures, components, and systems of the nuclear plant which are considered important to safety beccuse they perform safety actions required to avoid. or mitignte the cc rec.uences cf ebnerral operational transients er cccidents.

In adciticr. design re quire:.:cnt s are plac e d uper. such ccuipac nt to assure the proper performance of safety actions, when re-quired.

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

Se ismic Clas sification - Plant structures, systems, and compo-nents important to sciety which are designed to withstand the effects of a safe shutdoun earthquche (SSE) and remain functional if they are necessary to assure:

a. the integrity of the reactor coolant pressure boundary, or

b. the capability to shutdown the recctor and maintain it  !

in a safe condition, or O.

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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 j foundations 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 FSAR.

Severity - Varying degrees of the significance of the adverse condition.

I Source Inspection - An inspection performed at the location of item procurement, supply, or manufacture for the purpose of {

verifying thet the iten meets specified requirements.

Special Frocesses - Term used to describe those activitits or i 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 l assurance of quality is heavily dependent upon control of the 1 process and the skills of the personnel who perform the process. j 1

Standards - Term used to describe the results of standardization ]

efforts which have been approved by recognized authorities. As I used herein, standards refer to either publications describing an i acceptable method of implementing or performing an activity, or an item of known value used for comparison.

Star Ucrk - Cel}ccrive terr nrc d to descrit c the frilcring threc  !'

i;[levc;s cf s:cpping werk c: tis; ies

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

b. A hold imposed by a Department head on a department or '

general work activity,

c. A Stop Ucrk Action initiated by the Manager - Quality l Assurance.

Supplier - Any individual or organization who furnishes items or services to IP under a procurement document.

Surveillance - A review or observation of an activity, process ,

or product to verify that an action has been or is being accom-plished in accordance with applicable requirements.

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IP NUCLEAR POWER GLOSSARY OF TERMS OPERATIONAL QUALITY ASSURANCE MANUAL.

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Survey - Same as an audit except performed prior to purchasing contract' award with' emphasis on audited organization s capability to meet requirements.

System Saf ety Classifications - Structures , systems , . and cocpo-nents are classified as Safety Class 1, Safety Class 2,. Safety Class 3, Safety Class Other or Class 1E in accordance with the .

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

Safety Class 1 - Components of the reactor coolant pressure boundary or c6re support structure whose-failure could cause a loss of reactor coolant at'a rate in excess of-the normal make-up cystem.

Saf ety Class 2 - Structures, systems, anc components, other than service water systems, that are not Safety Class 1, but are necessary to. accomplish the safety functions of: j

a. inserting negative. reactivity to shut down.the reactor,

b. preventing. rapid insertion of positive reactivity,

(])

i. c. maintaining core geometry appropriate to all plant process conditions,

d. providing emergency core cooling,

e. rrovidir.g and reintaining ccntair er.t.

f. removing residual heat from the reactor and reactor core, or q l

g, storing spent fuel.

Safety Class 3 - Structures, systems, and components that are not Safety Class I 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 rce to the vtcle body or its equiva-lent to any part of the body in accordance with Regulatory i Guide 1.26.

f Safety Class "Other" - Structures, syst'ecs, ind components )

l used in the power conversion or other portions of the l facility which have no direct.. safety function, but which may be connected to or influenced by the equipment within the-l /]

l Safety Classes.1, 2, or 3.

PAGE Y~0 Of 9 '

R EYl510H:

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i IP NUCLEAR POWER GLOSSARY OF TERMS OPERATIONAL QUALITY ASSURANCE MANUAL Class IE.- 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-ma terial to the environment. ,

( Struc ture s , systems , and component safety classifications and related Quality Assurance Program requirements classi-fications are summarized in Table 3.2-1_of the FSAR.)

Traceability - 'The ability to trace the development of a particu-lar item from any phase of construction, fabrication, or process to its original source. . Traceability is generally provided by.

heat numbers, serial numbers, etc. that allow retrieval of records showing verification of applicable requirements back to the cripint: rc1t, pour, er lot of raw materials.

Use-As-Is - A disposition which may be imposed for a nonconfor-mance when it can be established that the dis ~crepancy 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, Vendor - A qualified individual or organization who furnishes Items or services to IP under a procurement document.

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

Wit ne s t Fcint - An inspection peirt in a procedurc, activity, or process at which the performer is required to stop to allow an inspector to witness certain activities or accomplish certain planned inspections. If inspection personnel have been notified and the inspector is not present, the step, activity, or: process ray continue in accordance with the procedure / instruction.

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ORGANIZATION APPROVED BY: MANAGER. QUALITY ASSURANCE 1.1 PURPOSE / SCOPE To establish the' requirements for and to describe the establish-ment of an organizational structure, functional responsibilities, and levels of authority concerning the performance of activities which affec. the safety-related functions of structures. systems, or components for the Clinton Power Sta tion.

1.2 DESCRIPTION

1.2.1 General i

Organizational structuring and functional responsibility assign-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 contributors.

The austerities end responsibilities of pcrrcts and ergrriraticns pe rf errir.; c.uc i;ty-re l a:c d a c tiviti e r are estrllished cili Encd, and docutented in formal docurent systems. These persons cnd organizations assigned quality assurance functions are given appropriate and sufficient authority and organizational freedom to: identify quality problems; recommend solutions; verify imple-mentation of the solutions; and control: processing, delivery, installation, or utilization of nonconforming items until proper dispositioning has occurred.

1 Corporate Nuclear Folicy 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 j QA program requirements. The CNPs are approved for use by the IP corporate officer (s) responsible for the activities covered by the CNP. Corporate Nuclear Procedures require the development and use of departmental procedures er instructions to describe interfaces and accomplish the activities covered by the CNP.

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1 The organizational structure. and functional responsibility assignments are such that: (1) attainment of quality objectives

.is by individuals assigned responsibility.for specifying quality or performing work.to specifications; (2) verification of con-formance to established qualitp requirements is by those who do '

not have direct responsibility for specifying, producing, or expediting products; and (3) personnel in key quality assurance functions have . direct access to' responsible management.

Specific 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 i'n a manner supportive of plant operations and-ou ta ge s .~ Further, once a year the QA. department manning levels are recssessed and pcrsonnel.fevels areLrevisec as necessary to assure adequate and timely coverage of QA activities. Quality Assurance personnel are free 1from non-QA duties and provide full 1, attentioq to assuring the effective implementation of the QA program.

For shcrt- te rm planning , specific work packages consisting of O discrete schedulable activities are' evaluated by Quality Assur-ance for manpower requirements. Schedules are revised to make optimum use of available human and equipment resources. Quality Assurance activities, including inspections, are performed contiguous with the planned work activities. Murk is scheduled contingent upon the capability to verify quality. Effectiveness of the program is assured by Quality Assurance department par-ticipaticr ir the work planning. thrcugh surveill ar.ce ar d rudits ,

y the authcrity of Quality Assurence persennel t'o stop specific work activities where it appears that quality acy be jeopardized, and the authority of-the Manager - Quality Assurance to initiate a Stop Work Action. The Manager - CPS has the authority to bypass a stop work to place the plant in a safe and stable condition.

Matching of Quality Assurance department resources with work is accomplished-by the review of proj ected work forces of the plant staff and its contractors. This review l permits recruiting and training activities to be carried out in such a manner as to provide trained Quality Assurance personnel necessary to assure the quality-of the work. The ability to perform timely inspec-

,tions is a direct function of the availabilitylof inspectors.

Work to be done can be matched with available inspection manpower resources on both a short and . long-te rm ba sis .

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1 Inspectors are provided with approved inspection procedures and instructions prior to performing inspection operations. (During plant operations emergencies, inspections may be performed without written procedures.) These documents contain identifica- ,

tion of characteristics to be inspected, identification of personnel or groups performing the inspection, a description of I the method of inspection, acceptance / rejection criteria, verifi- )

cation of completion of inspection, and the results of the inspections. 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 notifica-tion of witness and hold points. The inspection program is managed er a discipline basis and inspectors are assigned daily  ;

to specific work activ;.ies.

l In addit :n, designated QA and/cr QC personne) regularly attend ,

! and participate in planning, scheduling, and status meetings l l during testing, operations, and outages to assure (1) they are i

kept abreast of day-to-day projected work assignments throughout the plant and (2) that the necessary QA/QC inspection controls, acceptance criteric, procedural controls, and qualified QA/QC staffing is available to properly carry out the assigned tasks.

p k/ 1.2.2 Organization and Responsibilities  !

This section describes the organizational structure and individu-al responsibilities within IP for managing and implementing the QA program for the operation of the CPS. Figures 1-1 and 1-2 i show the organizational structure and relationships of individu-cis and p gs withir IP vith manascrcr respcr.-ibilit y f c r periernir: quali:"-relat c d activitic s .

l.2.2.1 Chairman and President The Chairtan and President of IP has the overall responsibility i for the engineering, design, procurement, construction modifica-tien, testing, operation, and cuality assurance at CPS. Execu-l tion 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 cf 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 Power Quality Assurance Program es well as testing,

('s startup, operations, nuclear support, and engineering are dele-

! (_/ gated to a Vice President. The Executive Vice President is also 1

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responsible for assuring that annual management reviews are conducted and documented on the status, adequacy and effective-ness of the overall QA program. The Executive Vice President shall retain the responsibility for assuring that the authority and independence of Quality Assurance personnel are such that they can effectively assure the conformanet to quality require-ments and are independent of undue influences and responsibil-ities for schedule and costs.

1.2.2.3 Executive Vice President An Executive Vice Pre sident is responsible for quality-related activities associated with environmental affairs. The responsi-bi]ity to establish and maintain procedures which support the IP Nuclear Power Program on safety-related matters has been dele-  !

ccted te a Vice Fre sident.

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 Power Quality Assurance Program; the testing, startup, nuclear support

(' activities (including purchasing), engineering and commercial operation of Clinton Power Sta tion. He reports to an Executive Vice President and has direct access to the President.

1.2.2.5 Vice Pre sident .

A Vice President has been designated as the corporate officer r e s pc-ra f b'_ e for thcse activitics assec:cted with er."frorecrts2 affc.irr. The desip.2ted Vict F rc side : ~ re;c r:s dirc ctl," to ar Executive Vice Fresident. Ee has delegated this responsibility to the Manager - Environmental Affairs.

1.2.2.6 Project Manager  ;

i A Project Manager has been de signated responsible for those activities associated with construction. The Project Manatcr l report s tc an Executive Vice Pre sident.

1.2.2.7 Manager - Nuclear Program Coordination The Manager - Nuclear Program Coordination reports to the Vice President and is responsible for assisting the Vice President of the Nuclear group in meetir.i regulatory requirements, commit- -

ments, and Illinois Power Company goals and objectives as neces-sary to support construction, s ta rt -up , operation, and modifica-rT tion of the Clinton Power Station in an efficient and timely

(_/ manner.

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1.2.2.8 . Manager - Clinton Power Station The Manager - Clinton Power Sta tion reports to . the Vice President and is responsible for the safe, reliable, and efficient opera-tion of the Clinton Power Sta tion in accordance with the operat-ing license. This includes ensuring that the IP Nuclear Power Operational Quality Assurance Program, as described in subsequent sections'of this manual, is incorporated in plant procedures and implemented by the Clinton . Power Sta tion organization.

1.2.2.9 Manager - Nuclear Station Engineering The Manager - Nuclear Sta tion Engineering reports to a Vice President and'is responsible for the development, direction, and overall coordination of power plant engineering activities per-forned by thc Fuclear Stction Engineering Departnent (NSED) for the Clinton Power Sta tion. 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 l evaluation of contractors and suppliers. The Manager - NSED ensures that these activities are performed in accordance with

() the requirements of the IP Nuclear Power Quality Assurance Pro-gram.

1.2.2.10 Manager - Startup The Manager - Startup reports to a Vice President and is respons-ible for Chechout and Initial Operation (CSIO), Preoperational cud Acc e;:ance testirr , anc icr previding st r. c:ance to the Manstcr - Clinter Ic.'cr Static: for Startup tc.=:ing.

1.2.2.11 Manager - Nuclear Planning and Support The Manager - Nuclear Planning and Support reports to the Vice President and is responsible for human resources, support ser-vices, naterials management, budgeting, site accounting, and program planninE. The Manager - Nuclear Planning and Support ensures that these activities are performed in accordance with the requirements of the IP Nuclear Power Quality Assurance Program.

1.2.2.12 Manager - Environmental Aff airs 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 non-O radiological effect on the environment.

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1.2.2.13 Nuclear Review and Audit Group The= responsibilities of the Nuclear Review and Audit Group (NRAG) are described in Subsection 13.4.2 of FSAR.

1.2.2.14 Facility Review Group An on-site comnittee whose function is to advise the Manager -

Clinton Power Station on matters related to nuclear safety.

1.2.2.15 Director - Nuclear Training The Director - Nuclear Training reports to-the Vice President and is responsible for the direction and management'of the Nuclear Training' for Clinton Power Sta tion. Duties include deve' loping t rcining s t ar.derd s , providing centralized training, providing education support to Nuclear Manabers/ Directors , and maintaining operation of the simulator.

1.2.2.16 Manager - Quality Assurance The Manager - Quality Assurance reports to the Vice President and

() has direct access to an Executive Vice President. The Man aEer ' -

Quality Assurance is responsible for IP's overall Quality.Assur- q ance prograc definition, direction, evaluation, and approval, J including the IP Nuclear Power Quality Assurance Program. The Manager - Quality Assurance directs the Quality Assurance depart-mental activities related to the design, procurement, construc-tion, and operation of. the Clinton Power Sta tion. The Manager -

Purlity Asstrcnce interfaces with the Nuclea: M gulatory Cer:..is-s ion , Of f ir e cf Inspcction and Enfc.recrent, Itc t ion Ill, ari the Authorized Inspection Agency for quality assurance activities.

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 icpact on capability to safely shut dowm the plant are not affected.

The qualifications of the Manager - Quality Assurance are at I least ec,uivalent to the education and experience requirements of Sec tion 4.4.5 of ANSI /ANS 3.1-19 76., " Selection and Training of- .j Kuclear Power Plant Personnel", or Section 4.4.5 of proposed <

draft ANS 3.1-1979. Spe cifically , the Manager - Quality Assur-ance will teet at least one of the following:

1. At the time of initial-core loading, or assign- l O ment to the active position, the responsible '

person shall have six years experience in the 6 of.16 i PAGE R EVl5lOR 17 DATE:

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. field of quality assurance, preferably at an operating nuclear. power plant, or operations -

supervisory. experience. At=least one year-of-  ;

this six years experience shall be nuclear power plant experience in the-overall implementation of' the quality assurance program (This experience shall be obtained within the quality assurance-organization.) A maximum of four years of this six years experience may be fulfilled by related technical or academic training; or, l

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

. EXPERIENCE: At the tire of initial core loading or appointment te the. active position, the responsible person shall have four (4) years experience in the field'of quality assurance, or equivalent number of years of nuclear plant experience in a supervisory position', preferably at an operatinh nuclear plant, or a combination of the two. At least one (1) year of this four j years experience shall be nuclear. power plant l Q experience in the implementation of the quality l

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 E45.2, ANSI N16.7,- familiarity with the ASE Iciler and Irc ssure W ssel Code, and cther applicd le regu:ctions , codes, and standarcs. {

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

Qvality Assurance and is responsible for providing direction and administration of the Quality Systems cnd Audit's staffs in defining.. establishing, snd verifying cocpliance with the IP-Nuclear Power Quality Assurance Prograt.

1.2.2.16.2 Director - Quality Engineering 6 Verification The Director -- Quality Engineering & Verification reports to the j Manager - Quality Assurance and is responsible for direction and- i management of the Quality Operations and Maintenance, Quality j Control, and Quality Technical Support staffs for defining, 1 establishing, and. verifying compliance with the IP Nuclear Power  !

Quality Assurance Program.

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.O 1.2.2.16.3 Director - Operations Monitoring Programs The Director - Operations Monitoring Programs reports to the Manager - Quality Assurance. Hc is responsible for providing assistance to the Manager - Quality Assurance in the development and implementation of Quality Assurance Operations Monitoring Programs that meet regulatory requirements, commitments, and

, support the safe and reliable operation of CPS.

1.2.2.17 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 obtain operating licenses f or CPS, management of the FSAR and the ER, including certifica-tien'and amendmen* rubmittals, manager *nt cf the resciution of I licensing issues, conduct of licensing reviews and studies, perform safety studies and analysis, conduct of Independent Safety Evaluation Group (ISEG) efforts for significant operating l data, provide representation to safety groups, support of the l Nuclear Review and Audit Group (NRAG), and the administration of tracking programs for 10CFR21 and 10CFR50.55(e) items.

O 1.2.2.18 Manager - Scheduling and Out age Management i

)

I The Manager - Scheduling and Outage Management reports to the Vice President and is responsible for management of the Schedul-ing and Outage Management Department personnel and resources. .d l

The Manager - Scheduling and Out age Managerent develops schedules l ns recuirt' to su pcrt tuelect Irc ;rar Depcriment s. He cccrdi-netcs the :_rnning, schtculing anc freparatient for picnt cutages snd manages and directs the Maintenance Support Contractor. He is responsible for managing and staffing the Project Control i Center (PCC). i 1.2.2.19 Director - Nuclear Program Assessment Group The Director - Nuclear Program Assessnent Group reports to the-Vice President End is directly responsible for coordinating- i Institute of Nuclear Pover Operations (INPO) Programs, assessing nuclear programs and plant operations, conducting oversight on radiological protection, radioactive waste, and chemistry pro-grams, and other special assignments from the - Vice Pre sident.

3.2.3 Quality Assurance Department The Quality Assurance organization structure is shown in Figure-(} 1-3. General responsibilities of the department with regard-to 8 of 16 PAGE R EVISION: 17' <

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the'QA program for the CPS include, but are not limited to, the f oll owing:

a. Prepare and control the IP Nuclear PowerL0pera-tional Quality Assurance Manual.

b. Verify the implementation of the IP Nuclear Power Operational Quality Assurance Program, i l c. If significant quality problems are identified, QA personnel have the authority and responsi-i 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 shut down the plant are not affected.

d. Verify that quality training programs.are devel-oped and implemented for each company department that has responsibility for implementing the 1P Muclear Power Operational QA Progres.

Review procurement requisitions, safety-related I

({) c6 and, as specified, nonconformance reports, procedures, instructions, and other quality-related documents.

f. Maintain awareness of QA requirements, practices, and experiences throughout the nuclear power ir.dustry.

g. Develop and implement an audit, surveillance, and inspection program for quality-related activities within the scope of the IP Nuclear Power Opera-tional Quality Assurance Program, and routinely -

advise management of the status of program implementation. Initiate.and/or verify correc-tive action, as necessary, to resolve conditions adverse to quality.

I

h. Perform acceptance inspe ctions related to activ-ities performed by IP Plant . Staff during startup, operation, and maintenance of CPS.

i. Review the QA programs of suppliers for~compli-ance with regulatory requirements and the re-quirements of the IP Nuclear Power Operational

()

r Quality Assurance Program when a program is 9 of '16 PAGE R EYlSION:

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required to be submitted by the procurement document. . Ensure that QA program deficiencies q are corrected.

j . Review and approve changes to the quality classi-fication assignment to systems, equipment, and components as identified in Table 3.2-1 of the FSAR. Review all changes to'the FSAR, with the exception of Chapter 16, Technical Specifica-tions.

k. Detect trends adverse to quality.

1.2.3.1 Quality Operations and Maintenance Section j The Quality Operations cnc Maintenance Secticn is supervised by the Supervisor - Quality Operations and Maintenance who reports to the Director - Quality Engineering & Verification. The Quality Operations and Maintenance Section assures documents involving the following activities conform to the applicable QA program requirements of regulations, standards, codes, and other i specific commitments: operations, maintenance, fire protection,

(} and security. The section establishes quality control inspection points in the aforementioned documents, as applicable.

i The Quality Operations and Maintenance Section is responsible for q planning and performing surveillance on the aforementioned I i

activities, as applicable, including assuring timely and respon-sive corrective action to IP surveillance findings , and for i a dvising ransgetent as te the effectiveness cf quclity assurance progran irplementntier for thosc specific fu.ctions survei'_ led.

If significant quality prob 1cos are identified, Quality Opera-tions and Maintenance Section personnel have the authority and responsibility to stop specific work activities pending satis-factory resolution of the identified problem, provided the health and safety of the public or inpact on the capability to safely shut down the plant are not affected.

1.2.3.2 Quality Control Section The Quality Control Section is supervised.by the Supervisor -

Quality Control who reports to the Director - Quality Engineering 1

6. Verification. The Quality Control Section is responsible for J conducting and reporting inspections.and nondestructive examina-tion of items or processes associated with startup, testing, a maintenance, modification, nuclear fuel,fand plant support O

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activities performed by IP which affect quality. The Quality Control Section is also responsible for initiating reports of-nonconforming items or conditions discovered during inspections.

If significant quality problems are identified, Quality Control Section personnel have the authority and responsibility to stop specific work activities pending satisfactory resolution of the identified problem, provided the health and safety of the public or impact on the capability to safely shut down the plant are not affected.

1.2.3.3 Quality Technical Support Section The Quality Technical Support Section is supervised by the Supervisor - Quality Technical Support whc reporte to the Direc-tor - Qut".ity Engineering 6 Verification. The Quality Technical Sup por t Section assures that documents involving the following activities conform to the applicable QA program requirements of .

regulations, standards, codes, and other specific commitments:  !

startup, engineering, rndiation protection, and chemistry. The section establishes quality control inspection points in the aforementioned documents, as applicable. .

The Quality Technical Support Section is responsible for planning and performing surveillance on the aforementioned activities , as applicable, including ensuring timely and responsive corrective j action to IP surveillance findings, and for advising management as to the effectiveness of quality assurance program implementa-tion for those specific functions surveilled. ]

l If signif_:an; quality prcblers are identified, Quality Technical )

Support Section personnel have the authority and responsibility j to stop specific work activities pending satisfactory resolution J of the identified problem, provided the health and safety of the public or impact on the capability to safely shut down the plant l are not affected.

1.2.3.4 Quality Systems Section )

1 The Quality Systems Section is supervised by the Supervisor -

Quality Systems who reports to the Director - Quality Systems &

Audits. The Quality Systems Section is responsible for period- )

ically assessing departmental effectiveness in implementing the IP Nuclear Power Operational Quality Assurance Program, trending l of conditions adverse to quality, and coordination of Quality L Assurance reviews and approvals of QA program requirements associated with the QA manual and Corporate Nuclear Procedures.

The section is also responsible for the coordination and adminis-

.O_ tration of QA/QC training programs for corporate and department II of 16 PAGE R EVISIO& 17 r.m moo.m p s3) DATE: 11/12/86- ]

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personnel, and control for distribution and issuance of documents associated with the IP Nuclear Power Quality Assurance Program, such as QA Manuals, departmental procedures and instructions..

If significant quality problems are identified, Quality Systems Section personnel-have the authority and responsibility to stop specific work activities pending satisfactory resolution of the .

identified problem, provided the health and safety of'the.public 1 or . impact on the capability to safely shut down the plant are not i af fected. .l 1.2.3.5 Audit Section The Audit Section is supervised by the Supervisor - Audits, who R reports to the Director - Quality Systems & Audits. The Audit j Section is responsible for the planning of internal and cxternal IF audits. 'lhe 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.

1 l If significant quality problems are identified, Quality Audits Section personnel have the authority and responsibility to stop specific work activities pending satisfactory resolution of the identified problem, provided the health and safety of the public or impact on the capability to safely shut down the plant are not affected.

3.2.3.6 Procurement Quality Assurance Section The Precurerent Qut'ity Assurance Sectien is supervise d by the Superviser - Procurement Quality Assurcnce who reports to the j

, Manager - QA. The Procurement Quality Assurance Section assures 'i that procurement documents contain the.QA requirements of the FSAR, evaluates suppliers' QA programs for meeting the FSAR ,

commitments, performs surveys at suppliers' facilities, processes l procurement related nonconformances, performs source surveil- j lances, pcrforms receipt inspections, and reviews and approves vendor we ching procedures. .

If significant quality problems are identified, Procurement {

Quality Assurance Section personnel have,the authority and j responsibility to stop specific work activities pending satis-factory resolution of the identified problem, provided the' health' and saf ety of the public or impact on the capability to. safely shut down the plant are not.affected.

O 12 of 16 PAGE R EVISION: 17'

__m h ga. 11/12/86- ]

IP NUCLEAR POWER CHAPTER 1 l OPERATIONAL QUALITY ASSURANCE MANUAL j

(-) l l

1.2.3.7 Construction Quality Assurance Section The Construction Quality Assurance Section is described in the IP Nuclear Power Construction Quality Assurance Manual.

1.2.4 Organizational Interfaces  ;

\

I Activities affecting the quality of safety-related systems, s t ru cture s , and components are performed by, or under the cogni-zance of various IP organizations. Other sections of QA may perfore some of the functions of another QA section provided that personnel are adequately qualified, certified, and trained, and these work activities are performed to the same (or similar) procedures and instructions. Quality problems, problems associ- I ated with ceeting the requirements of the Quality Assurance l progrcn, or disagreements end/or disputes betweer members of these organizations shall be brought to the attention of appro-priate levels of management, including the Chaircan and Presi-dent, as necessary to obtain resolution.

Work may be delegated to qualified outside organizations by r- contract for such activities as design, special processes,

(_j) inspections, etc. Selected work may be delegated to qualified j outside organizations by the Nuclear Sta tion Engineering Depart- I ment, CPS Plant Staff, and the Quality Assurance department. The )

responsibility for exercising engineering control rests with j Nuclear Station Engineering, operational controls with CPS Plant l Staff, and quality assurance with the Quality Assurance depart- l ment. Prior to initiation of work, the qualified individual (s) or c.r g ari z a t ion t ) eierents vi:hin IP have their esponsibil; ics identi:ied for thc control anm cutlity cf delera:e c vert ( c x c e t> t when it is necessary te piccc the plant in a safe and stable  !

condition). J 1.2.5 Clinton Power Station Organization F IGURE 1-1 illustrates key positions of the Clinten Power Station i organization having QA progran responsibilities.

PIGURE 1-2 illustrates Clinton Fower Station organizatienel in t er f a c e s .

PIGURE 1-3 illustrates the Quality Assurance Organizational Chart.

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