Text

Rev 9 to QA Manual Operations
	ML20236E527
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/22/1987
From:	; ARKANSAS POWER & LIGHT CO.
To:	;
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ML20236E402	List: 0CAN078706, Forwards Rev 9 to QA Manual - Operations; ML20236E527;
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l OPERATING STATUS 14-2 8

l 14-3 8

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14-4 8

l 14-5 8

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'( )

l 15.0 NONCONFORMING MATERIAL, 15 15-1 8

l PARTS OR COMPONENTS 15-2 9

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l 15-3 8

l 15-4 8

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l 16.0 CORRECTIVE ACTION 16 16-1 9

l 16-2 9

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l 17.0 QUALITY ASSURANCE RECORDS 17 17-1 8

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AUDITS 18 18-1 8

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FIGURES l

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Number Title

, Tab Page Rev.

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AP&L Corporate F-1 9

i Organization l

2 AP&L Corporate Services F-2 9

l 3

AP&L Generation Trans-F-3 9

l l

mission, Engineering l

Organization l

l 4

AP&L Nuclear Quality F-4 9

l Organization l

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l

)

5 AP&L Site Nuclear Operations F-5 9

l Organization l

l 6

AP&L Plant Operations F-6 9

l Organization l

J 7

AP&L Plant Support F-7 9

i Organization l

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____-__________m__

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1 l-TABLES l

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Number Title Tab Page Rev.

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AP&L Exceptions / Inter-T1-1 8

l pretations of Regulatory T1-2 8

l Guides and ANSI Standards T1-3 8

l T1-4 8

l l

l T1-5 8'

l T1-6 8

l l

l T1-7 8

l T1-8 8

l l

T1-9 8

l T1-10 8

i T1-11 8

l T1-12 8

l T1-13 8

l T1-14 8

l l

l T1-15 8

l T1-16 8

I 2

Quality Assurance T2-1 9

I Procedures Matrix l

l 3

Quality Program Policies, T3-1 9

i Procedures and Instruc-T3-2 9

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l tion Manuals List I

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l APPENDICES l

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Number Title M

Rev.

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4 l

A Quality Program For AA-1 8

l l

Transport Packages AA-2 9

l AA-3 9

l AA-4 8

l B

Quality Program For AB-1 8

l Fire Protection-AB-2 8

l AB-3 9

l l

AB-4 9

l AB-5 9

l l

AB-6 9

I AB-7 9

l AB-8 9

l AB-9 9

l I,

l AB-10 9

l AB-11 9

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l AB-12 9

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1 I

l ARKANSAS POWER & LIGHT COMPANY POLICY. STATEMENT l

I I

QUALITY ASSURANCE PROGRAM FOR OPERATION O

l l

1 lItisthepolicyofArkansasPower&LightCompany(AP&L),fromthe I

highest level of corporate management, that its Quality Assurance Program 1

J for Operation meet the requirements of the Code of Federal Regulations, l

l 10 CFR 50, Appendix B, with respect to operation, maintenance, refueling, l-repair and modifications, and inservice inspection at the AP&L nuclear l

l plant.

The program shall also meet the requirements of the ASME Boiler l

landPressureVesselCodeswithrespecttoitemsconstructed,repairedor I

replaced to Code requirements.

)

I l

J l

I l

Under the program, the Nuclear Operations Vice President is the final l

management authority responsible for assuring that this policy statement l

l and the Quality Assurance Program are implemented within AP&L.

The l

Engineering Vice President, and Administrative Services Vice President l

are responsible for the procedural implementation of the program within I

their assigned areas.

The Executive Director AND Site Operations is l

l responsible for the daily implementation of the Program's procedural l

)

lrequirementsattheplantsite.

l l

l 1

lTheNuclearQualityGeneralManagerisresponsibleforestablishingthe l

l Program.

Responsibility for approval of the Program shall be identified I

l within this manual.

l l

I I

Nuclear Quality personnel reporting to the Nuclear Quality General l

1 l

1 Manager are responsible for auditing the Program as necessary and l

inspecting / monitoring activities required by the Program to assure l

compliance with its requirements.

Disputes involving quality, arising l

lfromdifferenceofopinionsbetweenNuclearQualitypersonnelandother l

l personnel, which cannot be settled interdepartmentally, shall be l

I I

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I

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l presented to the Nuclear Operations Vice President for resolution.

The I

I Nuclear Quality General Manager has direct access to the Generation, Transmission, Engineering Senior Vice. President as required for items I

requiring interpretation or resolution.

I I

The Nuclear Quality General Manager through the Quality Assurance l

Superintendent is to provide for annual review of the adequacy and l

1 overall effectiveness of the Program.

Any defects in the implementation I

of either this policy or the Program that are revealed during the review l

are to be reported to appropriate levels of management together with I

appropriate recommendations.

I l

1 l

Implementation of this policy is necessary in order to achieve the I

reliability and safety required at our nuclear plant.

Each person I

involved in activities concerning our nuclear plant is to be responsible I

I for ascuring quality in his own work, and for compliance with the I

requirements of the Program.

The Quality Assurance Program policies, l

manuals, and procedures are mandatory requirements which must be l

l implemented and enforced by all responsible organizations and I

l individuals.

l ns,/

l T. G. Cariipbelff g

Nuclear Oper"ations g

Vice President g

g I

l l

l Date:

g _A6 97 l

l l

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1 l

l l

I

F l

I I

I I N3.1-1981 Selection, Qualification, and Training of l

l Personnel for Nuclear Power Plants 7

l l

lTheaboverequirementsareimplementedbycontrollingactivitiesas l

l described in this manual and by procedures referenced in this manual.

I I

I The AP&L Quality program is also designed to comply with the following l

l codes and standards, as applicable to those activities to which they are referenced within various. sections of this manual:

1 I

I I

l ASME Section III, Division 1 - 1983 Ed., Summer 84 Addenda

l l

ASME Boiler and Pressure Vessel Code - Nuclear Power Plant l

Components I

l l

i l

l ASME Section XI - 1974 Ed., Summer 75 (ANO Unit 2)**

l l

- 1980 Ed., Winter 81 (AND Unit 1) l ASME Boiler and Pressure Vessel Code - Rules for Inservice l

l

]

l Inspection of Nuclear Power Plant Components ASNT SNT-TC-1A-1980 l

Recommended Practice for Nondestructive Testing Personnel l

l Qualification and Certification l

l l

l AWS D1.1-1985 l

American Welding Society Structural Steel Welding Code l

I l

l 1

l ll Earlier editions / addenda of the Code may be specified for repair or I

replacement of components, within the rules of ASME Section XI.

l l

l Repair / replacement activities shall be to the 1980 Edition, Winter l

l 81 Addenda l

I l

l I

I l

Definitions of terms applicable to the AP&L quality program are found in l

ltheTermsandDefinitionssectionofthismanual.

l 1

1 I

I 3

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I I

l TERMS AND DEFINITIONS l

l 1

The terms used in this manual follow the definitions provided in g ANSI N45.2.10-1973, supplemented by additional terms and definitions l

l applicable to this manual.

I I

l I

I I

Approval - An act of endorsing or adding positive authorization, or both.

1 I

I I

l l

l Appurtenance - A part that is attached to a component which has been l

I I

g completed.

l 1

l' i

As-Built Data - Documented data that describes the condition actually l

l l

achieved in a product.

l l

1 l Assembly - A combination of subassemblies or components, or both, fitted 1

together to form a unit.

I I

g Audit - An activity to determine through investigation, the adequacy'of I

and adherence to, established procedures, instructions, specifications, l

codes, and standards or other applicable contractual and licensing I

requirements, and the effectiveness of implementation.

I I

I ll 1

l Basic' Component - A nuclear plant structure, system or component l

I i

g necessary to assure the nuclear safety criteria.

g j

l l

I Bid Evaluation - A formal evaluation of all proposals received in I

response to an inquiry to determine the vendor to whom the purchase order I

will be awarded.

I I

l I

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

requirements.

I l

l l

I I

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l Q

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l 1

1 I

I

1 l-I-

i l

l i

l-Certificate of Compliance - A written statement, signed by a qualified l

I party, attesting that the items or services are in accordance with I

specified requirements and accompanied by additional information to

~

-lsubstantiatethestatement.

l' l

l Certified Test Report - A written and signed document, approved by a l

l l

qualified party, that contains sufficient data and information to verify I

the actual properties of items and the actual results of all required i

tests.

I l

l 1

l

l I

l Certification - The action of determining, verifying and attesting, in I

writing, to the qualifications of personnel or material.

J l

i=

l Characteristic-Anypropertyorattributeofanitem, process,or I

service that is distinct, describable, and measurable, as conforming or l

nonconforming to specified quality requirements.

Quality characteristics I

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

I l-I l

Checks-Thetests, measurements,verificationsorcontrolsplacedonan l

activity by means of investigations, comparisons, or examinations, to l

determine satisfactory conditions, accuracy, safety or performance.

l I

l l

Cleanness-Astateofbeingcleaninaccordancewithpredetermined l

standards, and usually implies freedom from dirt, scale, heavy rust, oil l

or other contaminating impurities.

I I

Code Inspector - A qualified nuclear inspector (ANI or ANII) employed by I

a legally constituted agency of a Municipality or State of the United l

States, or Canadian Province, or regularly employed by an Authorized-l Inspection Agency and having authorized jurisdiction at the site of I

l manufacture for installation, repair, modification, and in-service l

inspection of ASME Boiler and Pressure Vessel items designated l'

l safety-related.

l l

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SECTION:

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f I ' Commercial Grade - Those items contained in Q systems and equipment that l

l are:

(1) not subject to design or specification requirements unique to g

t l

nuclear facilities or activities; (2) used in application other than l

lnuclearfacilitiesoractivities;and(3)to.beorderedonthebasisof I

specifications set forth in manufacturer's published product description.

I I

I l

Component - A piece of equipment such as a vessel, piping, pump, valve or i

i I

core support structure, which will be combined with other components to g

i form an assembly.

1 I

I l

l l

Computer Code - The application-software utilized within a digital l

l computer to accomplish a specific function or task, Computer codes I

requiring Quality Assurance are those whose satisfactory performance is l

lrequiredtopreventaccidentswhichmaycauseunduerisktothehealth I

l and safety of the public or relied upon to mitigate the consequences of l

j such accidents if they were to occur.

This involves those computer' codes d

l utilized in design and analyses of Q-list compo'nents, and those utilized I

as an active portion of Q-list components.

I l

l Contaminants-Foreignmaterialssuchasmillscale, dirt, oil, chemicals l

l and any matter than renders a fluid, solid or surface impure and unclean l

laccordingtopresetstandardsofacceptablecleanness.

I I

l Contractor-Anyorganizationundercontractforfurnishingitemsor l

I l

services.

It includes the terms Vendor, Supplier, Subcontractor, I

lFabricatorandsub-tierlevelsofthesewhereappropriate.

l l

\\

Dedication - Designating a commercial grade item for use as a basic l

l component after receipt.

This implies that all required inspections, i

l examinations, testing,anddocumentationarecompletedtoassure I

compliance with the Procurement Documents.

l l

l I

.I

.I l

Defective Material - A material or component which has one or more characteristics that do not comply with specified requirements,.

l l

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SECTION:

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1 4

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1 1

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i l

Deviation - A nonconformance or departure of a characteristic froml l-l I

I O

lspecifieprequirements.

l i

Documentation - Any written or pictorial information describing,

.l defining, specifying, reporting or certifying activities, requirements,-

l l

procedures,orresults.

I l

l Examination-Anelementofinspectionconsistingofinvestigationof l

l materials, components, supplies or services to determine conformance to l

J those specified requirements which can be determined by such investigation.

Examination is usually nondestructive and includes simple l

physical manipulation, gaging, and measurement.

l l

l Handling - An act of physically moving items by hand or mechanical'means, l

l but not including transport modes.

l 1

1 I

l l

Inquiry - A document that contains the necessary information for a vendor l

ltomakeaproposal.

An inquiry may include specifications pertaining to l

l the equipment, materials, or services proposed to be procured.

l O

l l

Inspector (0wner's) - A qualified inspector employed by the Owner whose l

duties include the verification of quality related' activities or l

installations or both.

I l

l l

Inspection - A phase of quality control which by means of examination, I

l observation or measurement determines the conformance' of materials, l

l supplies, components, parts, appurtenances, systems, processes or l

l lstructurestopredeterminedqualityrequirements.

l 1

I j

Item - Any level of unit assembly, including structure, system, l

l subsystem, subassembly, component, part or material.

I l

l I

l J

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l 1

I I

4 I

i 1

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/

I L

l l

l 1

1 I

l L----.---_-------__---_--_----___--_.--_---.---_-----.--

o

1 l

l I

I

-l Job Order (J.0.) - The Job Order is the document used for identifying and l

= administratively controlling the work effort on station equipment and j

systems.

It identifies applicable procedures and drawings; documents reviews, approvals and results of inspections and tests; and provides a l

1 mechanism for planning, scheduling and authorizing work.

l I

I i

i l

i l Manufacturer - One who constructs any class of component, part, or 1

)

appurtenance to meet prescribed design requirements.

I I

J Material - A substance or combination of substances forming components, l

l parts, pieces and equipment items.

(Intended to include such as l

1 l machinery, castings, liquids, formed steel shapes, aggregates, and l-I cement.)

l I

I I

I l Modification - A planned change in plant design or operation and l

laccomplishedinaccordancewiththerequirementsandlimitationsof l

l applicable codes, standards, specifications, licenses and predetermined I

lsafetyrestrictions.

l l

l Nonconformance - A deficiency in characteristic, document, or procedure l

l which renders the quality of an item unacceptable or indeterminate.

j l Examples of nonconformance include: physical' defects, test failures, l

l incorrect or inadequate documentation, or deviation from prescribed I

processing, inspection or test procedures.

l l

l 4

lNuclearSafetyCriteria-(1)Integrityofthereactorcoolantpressure l

l boundary; (2) Capability to shutdown the reactor and maintain it in a l

safe shutdown condition; and (3) Capability to prevent or mitigate the l

l consequences of accidents which could result in potential offsite i

l exposures comparable to those referred to in 10CFR100.11.

l l

I l

l I

I l

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[PAGE C-5 l

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l l

l I

i l

l

(

g g:

1, I

a" d

i

.)

Objective Evidence - Any statement of fact, information, or record,

.I

^l l

'g either quantitative or qualitative, pertaining to the quality of an item j

or service based on observations, measurements, or tests which can be l-

, verified.

l l

'/

1, i-s ;

l a

j Operation - Tiie total of administrative, maintenance and monitor g

i activ'ities necessary o sustain the power generating capabilities of the l

.j g

[

plant afl;er initial start-up.

j,/ { g 0;\\ w.:ner - The person, group, company or corporation who will have or has r

x l

l I

title to the facility or installation under construction.

1 I

I I

I l

Package - A wrapping or container ' including its contents of materials or l

l l

equipment.

t l

.f J.

l Packaged Unit - An assembly of items and parts which can be disassembled l

without destroying the integrity of the individual parts.

l l

l

)

As t

i I

l Part - An item which has ' work performed on it aM 'whfch is attached to l

l and becomes part of a component lefore completi6n of the component.

l I

l hi l

\\

l l

Plant - The equipment, piping, stru tures, buildings and property that y

l l ' comprise an installation or facility.

I I

l 9

l I

?

I l

Procedure - A documeed that specifies or'cescribes how an activity is to l

l l

be performed.

It may include methods to be employed, equipment or I

materials to be used and sequence of operations.

l I

I t'

L l

l

)

'g l

Procurement Documents - Contractually binding documents that identify and I

i I

I define the requirements that items or.. services must meet in order to be I

e I

(

l censidered acceptable by the purchaser.

1 l

A l

L l

.. s c.

l

^

I, Project - A planned series of activities including all actions necessary I

to provide, utilize, and maintain a facility or portion thereof.

I

\\

l l

._ _.1_._

___ l O

I l.

l l

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I L

i i

. j' l

I o

s,)

I i

I l

+

,v Q

q 1

[

t

l l

t I

Proposal - A bid, usually written by a vendor in response to an inquiry, I

I which provides the issuing party with the vendor's proposed compliance to the inquiry and the cost.

l 4

l l

l Purchase Order (or Contract) - A document authorizing a vendor to provide l

l equipment,materialorservicesinaccordancewithstatedtermsand l

l conditions.

I j

l l

Purchaser - The organization or organizations responsible for issuance l

I and administration of a contract, subcontract, or purchase order.

I I

i Q-List - A list of safety-rela +ed structures, systems, and components -

l l

that is, those structure, sys. ems, and components that are relied upon to l

remain functional during and following design basis events to ensure that 4

l the Nuclear Safety Criteria are satisfied.

l I

I I

I l Qualification (Personnel) - The characteristics or abilities gained I

through training or experience or both that enable an individual to i

perform a required function.

l l

l Qualified Party - A person or organization competent and recognized as l

lknowledgeabletoperformcertainfunctions.

I I

i Qualified Procedure - A procedure which incorporates all applicable codes l

and standards, manufacturer's parameters, and engineering specifications l

landhasbeenprovenadequateforitsintendedpurpose.

I I

I Qualified Vendor List - A listing of vendors having quality assurance l

l programs consistent with the requirements of applicable portions of l

10CFR50, Appendix B.

For vendors supplying ASME Code items, they shall l

I also have a quality program consistent with the requirements of I

l applicable portions of ASME Section III, Division 1, subsection NCA.

l l

1 I

l 1

1 1

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L l

l l

1 I

I

l l

l Quality Assurance - All those planned and systematic actions necessary to l

I I

provide adequate confidence that an item-or a facility will perform satisfactorily in service.

I I

l Quality Control - Those quality assurance actions which provide a means l

l to control and measure the characteristics of an item, process, or l

facility to established requirements.

l l

l

.I j

l I

i l

Receiving'- Taking delivery of an item at a designated location.

l i

I j

i l

l Repair - The process of restoring a nonconforming characteristic to a l

l condition such that the capability of an item to function reliably and l

l safely is unimpaired, even though that item still may not conform to the l

original requirement.

I l

1 Report - Something (document) that gives information for record purposes.

)

l 1

l Review - Ar. element of inspection to determine conformance to specified l

1 l

requirements, which can be determined by examination of documents and I

i l

activities.

l l

1 Rework - The process by which a nonconforming item is made to conform to I

a prior specified requirement by completion, remachining, reassembling or i

other corrective means.

I I

Safety-Related (Q) - Safety-related structures, systems, and components l

are those that are relied upon to remain functional during and following j

design basis events to ensure that the Nuclear Safety Criteria are l

satisfied.

l l

l I

I l

Source Surveillance - A review, observation, or inspection for the l

purpose of verifying that an action has been accomplished as specified et I

the location of material procurement or manufacture.

l 1

l l

l 1

I I

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i l

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1 I

I

l-l I

l l Transit - The state of being conveyed or transported from one place to l

I I

another.

Transit Carrier (0 pen) - Trucks, trailers, railroad cars, barges, l

l aircraft or ships which do not afford items protection from the l

environment.

I I

lTransitCarrier(Closed)-Trucks, trailers,railroadcars, barges, I aircraft or ships which provide protection of items from the environment I

by nature of their closed design.

l 1

Use-As-Is - A disposition which may be imposed for a nonconformance when I

it can be established that the discrepancy will result in no adverse l

l conditions and that the item under consideration will continue to meet l

all engineering functicial requirements including performance, I

maintainability, fit and safety.

I I

I Vendor - Any organization under contract for furnishing items or l

services.

It includes the terms Contractor, Subcontractor, Supplier, l

l O

I I

Fabricator and sub-tier levels of these where appropriate.

Q g

i l

Verification - An act of confirming, substantiating and assuring that an l

I activity or condition has been implemented in conformance with the I

specified requirements.

l l

1 l

Work Instructions - Written instructions used to transmit detailed I

information on the specific measures necessary to comply with the i

requirements of quality assurance procedures or any complex or difficult l

l quality-related task.

l l

l l Work Package - A work package is a collection of applicable documents, l.

such as procedures, cleanliness control forms, inspection and test forms, I

hold card forms, Ignition Source Permits, drawings, technical manuals, I

letc.,neededtoperformthejob.

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1.0 ORGANIZATION l

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1.1 SCOPE I

I l

i l

i l This section describes the AP&L organizational structure and l

I responsibilities for establishing and executing the Quality Assurance l

l Program for AP&L's operational nuclear plant in compliance with 10CFR50, l

Appendix B and applicable licensing commitments identified in the l

Introduction.

It also includes a description of the interfaces with l

lotherorganizationswhomaybedelegatedtheworkofestablishingand l executing portions of the Quality Assurance Program.

The AP&L Corporate l

l Organization relevant to the operation of its nuclear plant is shown in l

l Figure 1.

l l

l' l

I l

1.2 GENERAL RESPONSIBILITIES I

l l

l 1

l The ultimate responsibilities for an operational nuclear plant within l

l AP&L, including quality assurance, lies with the Nuclear Operations Vice j President.

He provides management assessment of the Quality Assurance l

l Program through review of Nuclear Quality audit reports and reports of l NRC activities.

l l

1

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l l

l 1.3 ADMINISTRATIVE SERVICES l

l l

l Administrative Services, headed by the Administrative Services Vice l

l President is involved in contract administration, procurement and human l

resource activities requiring execution of the Quality Assurance Program.

l-The Administrative Services organization is noted in Figure 2.

The l Administrative Service Vice President provides technical direction and l

l administrative guidance to the:

I g

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l a.

Corporate Services Executive Director l

b.

Human Resources Executive Director l

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l 1.3.1 CORPORATE SERVICES l

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l The Corporate Services Executive Director, who reports to the.

l Administrative Services Vice President, is responsible for contract-l l

administration, the procurement of materials, parts and components l

requested by Little Rock General Office (LRGO) personnel and for j

supporting the procurement activities at the plant.

l l

I l

I I

I The General Manager, Procurement & Materials Management reports to the l

l Corporate Services Executive Director and is responsible for the l

following duties and activities:

l I

1.

Provides technical direction and administrative guidance to l

the:

l l

l I

i l

a.

Manager of Procurement l

b.

Manager of Contract Administration l

l l

l 2.

Prepares purchase orders based upon receipt of reviewed and l

approved Purchase Requisitions.

l l

1 I

l l

3.

Assist responsible individuals in the initiation and I

development of a contract packages and provides for the j

administration of approved contracts.

l I

I l

l l

4.

Performs the commercial interface functions between AP&L and l

vendors / contractors.

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5.

Assure that quality documentation prepared by AP&L personnel is l

included in appropriate procurement documents.

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j 1.3.2 HUMAN RESOURCES l

I I

The Human Resources Executive Director, who reports to the Administrative Services Vice President, is responsible for the administration of the l

j l

training and development effort for LRG0 personnel.

The Human Resources l

Executive Director provides technical direction and administrative l

l guidance to the Training Manager.

l l

l I

I l

1.4 GENERATION, TRANSMISSION, ENGINEERING ORGANIZATION l

l I

I l

l This Organization, headed by the Generation, Transmission, Engineering l

Senior Vice President is responsible for activities related to the l

operation of the AP&L nuclear plant.

These activities include as a l

minimum:

design, operation, maintenance, inservice inspection and test, I modification and those additional activities discussed in Sections 2 l

through 18 of this manual.

Within this organization, the Nuclear l Operations and Engineering departments are involved in activities l

requiring execution of the Quality Assurance Program (See Figure 3).

I I

1.4.1 NUCLEAR OPERATIONS l

l Nuclear Operations is under the direction of the Nuclear Operations Vice l

President who reports to the Generation, Transmission, Engineering Senior l

Vice President and is responsible for the formulation, licensing, l

l implementation and discharge of operating policies and procedures i

relative to nuclear plant operations, nuclear quality and nuclear fuel I management.

His duties include the following:

l l

1.

Provide technical direction and administrative guidance to the:

l l

a.

Executive Director AN0 Site Operations l

b.

Nuclear Services General Manager l

c.

Nuclear Quality General Manager l

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2.

Assure conformance to the Quality Assurance Program by l

I instituting the necessary procedures and instructions within I

the Nuclear Operations Department.

I I

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l 3.

Provide for review arid approval of design and engineering l

)

performed for the operating nuclear plant.

l l

4.

Provide for review and approval of procurement documents for l

equipment, material and services.

l l

l 4

1 l

5.

Provide for liaison between AP&L and applicable regulatory l

agencies.

(

l 6.

Provide and maintain a qualified and suitable staff to carry l

]

l out required departmental functions.

[

l 1

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l 7.

Provide for procurement and design review of nuclear fuel.

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l 8.

Overall responsibility for the fire protection, emergency l

1 l

planning and radiatian protection programs implemented at the I

nuclear plant.

l I

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I l

1.4.1.1 Nuclear Quality General Manager j

j l

l l

The Nuclear Quality Organization (NQO) as shown in Figure 4 is under the j

direction of the Nuclear Quality General Manager who reports to the l

Nuclear Operations Vice President.

The NQ0 performs reviews, l

surveillance, inspection and audit functions during the operational phase l

of AP&L's nuclear plant.

The NQ0 is also independent of plant operations l

and has sufficient independence from cost and schedule when opposed to l

safety considerations.

The Nuclear Quality General Manager shall have l

I direct access to management levels, which assures his staff the ability I

I I

l to:

identify quality problems; initiate, recommend or provide solutions-l lthroughdesignatedchannels;andverifyimplementationofsolutions.

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l The qualification requirements of the Nuclear Quality General Manager are l

l I

established within his job description which includes the following l

I prerequisites:

I l

l I

I i

1.

Possess a degree from an accredited school in engineering or a l

related scientific discipline or equivalent; l

l l

l 2.

Possess a minimum of four years e.xperience in the field of l

l quality assurance / control with at least two years in the l

l nuclear field or equivalent number of' years of nuclear plant l

)

l experience in a supervisory position with at least one year l

l experience in the implementation of the quality assurance l

j I

program.

l l

l 1

l 3.

Exhibit the ability to plan, schedule and direct the activities I

of others assigned to or functioning within the NQO.

l I

I Duties and responsibilities of the Nuclear Quality General Manager l

I include the following:

l

/,D l

l I

O I

I l

i 1.

Provide technical direction, administrative guidance and l

l supervision to the Quality Assurance Superintendent and Quality l

l Control Superintendent.

l I

l l

l 2.

Approval of the QA Manual Operations and revisions thereto.

l I

i l

I l

3.

Approval of QA/QC procedures and revisions thereto as i

established within NQA procedures.

l I

I 1.4.1.1.1 Quality Assurance Superintendent I

l l

The Quality Assurance Superintendent reports directly to the Nuclear l

l Quality General Manager.

Duties and responsibilities of the Quality i

Assurance Superintendent include the following:

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1.

Develop Quality Assurance Program requirements for operation, I

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maintenance, and modification activities related to p

I I

t, I

safety-related (Q-listed) systems, structures, and components.

I I

I i

l 2.

Audit of the quality activities as described in Section 18 of I

l

]

this manual.

I I

3.

Review, approval and verification of the quality assurance I

requirements placed upon contractors or vendors that provide l

j equipment, material, or services fo'r the AP&L nuclear plant.

1 l

4.

Authority to stop work where conditions exist that prohibit l

l effective quality programs, or if faulty materials, incorrect l

l workmanship or procedures are detected.

l 1

l S.

Review, approval, distribution and control of vendor QA Manuals l

and QA Procedures and revisions thereto.

l 1

I I

l l

6.

Review and approval of QA programs for outside organizations l

l participating in the AP&L QA program.

I I

J 7.

Provide and maintain a qualified and suitable trained staff to l

l carry out required staff functions, i

l l

l 8.

Formulate programs for maintaining the professional competence I

of personnel within the QA Section and provide assistance in QA l

l training and indoctrination programs for management, l

engineering and plant personnel whose activities affect l

quality.

l l

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9.

Provide technical direction and guidance to the Quality l

Engineering Supervisors and their staff.

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i 10.

Inspect, audit or review practices, records, files, I

I instructions, directions or documents concerned with all areas affecting quality.

I I

I 11.

Schedule and coordinate audits or surveillance efforts in the I

areas assigned, document findings, and report results to the i

Nuclear Quality General Manager and the Manager of the audited I

area.

I I

12.

Provide to the Nuclear Quality General Manager on an annual I

basis the results of a review of the quality program to l

l l

determine the effectiveness and proper implementation of the l

program.

l l

1.4.1.1.2 Quality Control Superintendent l

I I

l The Quality Control Superintendent reports directly to the Nuclear Quality General Manager and is responsible for verifying the l

implementation of the Quality Control program at the nuclear plant.

The i

duties and responsibilities of the Quality Control Superintendent include l

l the fnllowing:

l l

1 l

l l

l 1.

Interface with plant staff in developing quality control I

requirements and inspection points for operation, maintenance l

l and modification activities related to safety-related l

l (Q-listed) systems, structures and components.

l l

2.

Interface with the Quality Assurance Superintendent or his l

representative for technical assistance in resolving I

l significant conditions adverse to quality.

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3.

Authority to stop unsatisfactory work and authority to place an l

I I

item in a nonconforming status when such an item is determined l

to be in violation of purchase documents, applicable codes and standards or SAP requirements.

l l

4.

Assuring surveillance, inspections and reviews of plant l

activities and documents are conducted in accordance with NQA l

and/or plant procedures.

l l

I, 5.

Provide technical direction and guidance to the QC Engineering

'l Supervisor, QC Inspection Supervisors and their staff.

I I

I l

6.

Provide and maintain a qualified and suitable trained staff to l

l carry out required staff functions and formulate programs for l

maintaining the professional competence of personnel within the l

QC section.

I l

I l1.4.1.2 Nuclear Services General Manager g

I I

The Nuclear Services General Manager reports to the Nuclear Operations l

l Vice President and is responsible for providing the necessary support l

lservicesrelatedtotheeffectiveoperationandmaintenanceoftheAP&L l

nuclear plant.

The duties include the following:

I I

I l

1.

Provide technical direction and administrative guidance to the:

l l

l 1

I l

a.

Nuclear Engineering & Licensing Manager l

l l

b.

Nuclear Programs Manager l

c.

Nuclear Services Manager i

l l

I I

l 2.

Interface with other departments to assure effective l

I implementation of Regulatory and Company requirements.

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1 4

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3.

Communication interface dealing with activities between the I

nuclear plant and LRG0.

l I

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l i

l l

1.4.1.2.1 Nuclear Engineering & Licensing Manager g

I I

The Nuclear Engineering & Licensing Manager reports to the Nuclear l

l Services General Manager and is responsible for management of nuclear l

l lengineeringandlicensingactivities.

These activities include direct l

interface with regulatory agencies on licensing requirements / regulations, I

lcontrolofregulatorycommitmentsandcorrespondence,safetyanalysesand i

evaluations, nuclear fuel management and core reload analyses to ensure l

lrequiredlicensesandpermitsaremaintained.

The Nuclear Engineering &

l l

Licensing Manager is also responsible for the tracking of possible I

l lnuclearsafetyconcernstoassuretimelycloseout.

l l

l i

l1.4.1.2.2NuclearProgramsManager i

I lTheNuclearProgramsfianagerreportstotheNuclearServicesGeneral l

l Manager and is responsible for providing offsite support to the nuclear l

4 I

plant in the areas of fire protection, emergency planning, radioactive l waste and health physics / radiation protection.

He is also responsible l

lforensuringplantstaffiscapableofimplementingtherequirementsof l

l the Emergency Plan and its procedures.

l l

l 1

I l

1.4.1.2.3 Nuclear Services Manager l

l l

1 I

I The Nuclear Services Manager reports to the Nuclear Services General l

Manager and is responsible for coordinating major nuclear power plant l

l projects and providing nuclear services, technical assistance and l

lcoordinationofmajorcapitalprojectsdirectedfromthecorporateoffice l to ensure safe and efficient generation of nuclear power with emphasis on I

plant reliability and cost effectiveness.

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1.4.1.3 Executive Director ANO Site Operations I

l i

The Executive Director ANO Site Operations reports to the Nuclear Operations Vice President on the corporate level (see figure 5) and has l

l-direct responsibility for operating the plant in a safe, reliable and I

efficient manner.

He is responsible for operating the plant in I

accordance with the provisions of the operating licenses.

I l

l I

I l The Executive Director AN0 Site Operations has the authority to shut I

the plant down if required and has final approval of plant procedures.

I I

l The Executive Director AN0 Site Nuclear Operations is to provide technical

[ direction and administrative guidance to the:

l q

l I

I I

{

l a.

General Manager Plant Operations l

l l

b.

General Manager Plant Support

)

I c.

Plant Modifications Manager I

d.

Special Projects Manager I

I 1.4.1.3.1 General Manager Plant Operations l

l The General Manager Plant Operations (Figure 6) reports to the Executive l

)

I Director ANO Site Operations and is responsible for the actual I

operation of the nuclear units, the maintenance of plant equipment and l

l facilities and the planning / scheduling of plant work activities.

The l

lGeneralManagerPlantOperationsistoprovidetechnicaldirectionand l

l administrative assistance to the:

l I

I I

l l

a.

Operations Manager l

l b.

Maintenance Manager i

c.

Work Control Center Manager l

l l

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l 1.4.1.3.1.1 Operations Manager l

I l

)

The Operations Manager is responsible for directing the actual day-to-day eperations of the plant.

He supervises the operating staff and I

interfaces with the Maintenance Manager to accomplish operation-related l

]

maintenance activities.

The Operations Manager is to provide technical l

l direction and administrative guidance to the:

l l

1 l

l l

a.

Operations Superintendents I

b.

Operations Technical Staff I

i 1.4.1.3.1.1.1 l

l lTheOperationsSuperintendentsreporttoandassisttheOperations l

l Manager in directing the day-to-day operation of the nuclear plant.

They I

are responsible for coordination of the daily review of operating.

l l

surveillance tests and coordination of operation-related maintenance l

l activities. They assist the Operations Manager in the supervision of-l core refueling, which includes advance planning for the outage, plant I

preparation, equipment check-out and the refueling operations.

I i

l 1.4.1.3.].1.2 1

I I

lTheShiftSupervisorsreporttotheapplicableOperationsSuperintendents l

l and are responsible for the actual operation of the unit and for the l

l lactivitiesoftheoperatorsduringtheirassignedshift.

The Shift l

Supervisor is cognizant of operation activities being performed while on l-duty.

The Shift Supervisor on duty has the authority to shut down the l

I g

l unit if, in his judgement, conditions warrant such action.

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l 1.4.1.3.1.2.

Maintenance Manager l

I l-The Maintenance Manager is responsible for the maintenance of plant equipment and facilities as defined by plant maintenance program l

l implementing procedures and to assure that maintenance of equipment is l

lconductedinconformancewithapplicablestandardscodes, specifications l

l and procedures.

The Maintenance Manager is also to coordinate I

operation-related maintenance activities with the Operations Manager'and I

is responsible to make repairs on any structure, system or component l

under his control.

The Maintenance Manager is to provide technical l

l direction and administrative guidance to the:

l l

1 l

a.

Mechanical Maintenance Superintendent i

b.

Electrical Maintenance Superintendent l

1 c.

Instrument & Control Superintendent l

l l

l d.

Senior Maintenance Coordinator l

e.

Shift Maintenance Superintendent l

l l

\\

l l

l 1.4.1.3.1.3 Work Control Center Manager l

O l

l 8

i The Work Control Center Manager is responsible for the l

l planning /schedulingofstationworkactivitiesandthemaintenanceofthe l

equipment history and associated reports.

He supervises the Work Control l

Center staff and interfaces with the Operations Manager and Maintenance l

l Manager to accomplish the scheduling of the outage /non-outage work l

l activities.

The Work Control Center Manager is to provide technical l

direction and administrative guidance to the:

l l

1 l

l l

a.

Planning & Scheduling Supervisors I

b.

. Work Control Center T'-hnical Staff (Engineers) l l

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1.

1.4.1.3.2 General Manager Plant Support l'

l l

The General Manager Plant Support (Figure 7)~ reports to the Executive Director AN0 Site Operations and is responsible for providing the l

necessary on-site support services for the operating nuclear plant in the I

areas of engineering, health physics, technical analysis, radwaste, i

I security, training and administrative services.

The General Manager l

Plant Support is to provide technical direction and administrative guide I

to the:

l l

l 1

I l

a.

Administrative Manager I

l b.

Training Manager l

c.

Engineering Manager l

l l

d.

Technical Support Manager l

e.

Security Superintendent l

l l

l I

l 1.4.1.3.2.1 Administrative Manager l

l l

1 I

I The Administrative Manager reports to the General Manager Plant Support l

l and is responsible for providing administrative services in support of I

plant activities.

The duties and responsibilities of the Administrative l

lManagerincludethefollowing:

l l

l

)

1.

Provide technical direction and administrative guidance'to the:

l 1

l a.

Office Services Supervisor l

lll b.

EIR Coordinator I

c.

Materials Management Superintendent l

l d.

Computer Support Superintendent l

l l

l 1

l 2.

Accumulation, storage and disposition of quality assurance l

l records related to all phases of the nuclear plant.

l l

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1 1

l l

l I

l 3.

Material management, storage of materials, parts and equipment, 1

I I

issuance of tools and test equipment and the identification of O

I I

(g l

surplus materials.

l t

I I

I l

l 4.

Personnel employment and industrial relations at the plant.

l 1

I I

I i

l 5.

Maintenance, revision and development of computer software for j

the plant monitoring and control room simulator computers and~

l for providing technical assistance to the Reactor Engineering l

l l

Supervisor and Nuclear Engineers in development and use of test I

l t

l apparatus for evaluation of fuel, core and NSSS performance.

l l

I l

l l

1.4.1.3.2.2 Training Manager l

l 1

)

l I

l l The Training Manager reports to the General Manager Plant Support and is l

1 lresponsibleforthetrainingandre-trainingofplantpersonneland l general office personnel as established by plant procedures.

The l

Training Manager directs the activities of the ANO training staff and l

l l provides technical direction and administrative guidance to the:

I I

l l

a.

Unit 1 Operations Training Supervisor l

j b.

Unit 2 Operations Training Supervisor l

l c.

Maintenance Training Supervisor l

j d.

Administrative Training Supervisor l

l e.

Technical Support Training Supervisor l

1 l

l l

1.4.1.3.2.3 Engineering Manager l

l l

1 l

The Engineering Manager reports to the General Manager Plant Support and j

is responsible for providing on-site engineering support services j

(including fire protection and prevention) to the plant staff.

The l

'I Engineering Manager is to provide technical direction and administrative I

I i

l guidance to the:

l I

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1 l

l l

l

)

I i

I a.

Reactor Engineering Supervisor l

b.

Plant Engineering Superintendent l

l c.

Engineering Services Supervisor l

d.

Operations Assessment Superintendent I

l I

l'1.4.1.3.2.3.1 l

1 l

The Reactor Engineering Supervisor is responsible for monitoring reactor l

l core and Nuclear Steam Supply System (NSSS) performance; conducting l

lreactorperformanceandphysicstestingtoassuresafeandreliable l

operation and to provide current, accurate information to operations; I

lcollectionandtransmittalofnuclearfuelmanagement.datatotheCore l

l Reload Design Sr. Engineer in Little Rock and the reactor vendors as I

required; on-site safeguards and accountability of the nuclear fuel; and I

assisting in the planning of all fuel movements' including new fuel l

receipt and inspection, fuel shuffling at refueling, inspection of l

l irradiated fuel and shipment of spent fuel.

l l

l i

l l

l 1.4.1.3.2.3.2 l

O l

l l

The Plant Engineering Superintendent is respor,sible for drawing control, I

lengineeringsupportofplantactivities,evaluatingequipmentandsystem l

l performance and plant efficiency, and investigating and evaluating l

equi ment malfunctions or failures.

I i

1.4.1.3.2.3.3 I

l The Engineering Services Supervisor is responsible for the implementation l

l and coordination of the Inservice Inspection program, site welding' l

l program, and the Inservice Testing program at the plant.

He is also l

responsible for providing engineering support to the fire protection l

program and coordination of the industrial safety and fire prevention l

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program.

This program includes conducting periodic checks to examine l

lcontrolofcombustibles,housekeepingandotherfirepreventionefforts l

as well as to provide a centralization of OSHA and plant safety l

l programs..

l l

l 1.4.1,3.2.3.4 l

l l

l The Operations Assessment Superintendent provides the capability to l

l perform engineering evaluations of equipment and system performance over l

extended periods of operating experiences which occur both at the AP&L l

nuclear plant and at other nuclear power plants and to make l

recommendations as a result of these evaluations to help plant operations l

personnel in preventing or dealing with'similar occurrences..He also l

I l

l provides technical direction and administrative guidance to the Shift l

l l

Technical Advisers.

l l

l-l l

l 1.4.1.3.2.4 Technical Support Manager l

l 1

I I

I l

The Technical Support Manager reports to the General Manager Plant j

j Support and is responsible for the establishment and impl mentation of l

the health physics, radiochemistry, chemistry and environmental j

l monitoring and radioactive waste programs at the operating plarit.

His l

duties and responsibilities include the following:

l j

l l

1 I

l l

1.

Provide technical direction and administrative guidance to the:

l I

l l

a.

Health Physics Superintendent l

l b.

Technical Analysis Superintendent I

lll l

l c.

Radwaste Supervisor l

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2.

Analyzing the reactor plant water conditions and providing l

recommendations to maintain conditions.

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Process, package, store, and ship radwaste generated at the l

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nuclear plant in accordance with plant procedures and state and l

l f ederal regulations.

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4.

Establish water chemistry criteria, analyze secondary plant 1

I water and auxiliary water conditions and provide l

I recommendations to maintain conditions within acceptable l

l limits.

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5.

Assure radiation exposure to. plant personnel is maintained as l

l low as reasonably achievable and authority to stop work in-l l

l radiation areas if it is determined that a potential for an l

unanticipated excessive exposure to plant personnel or the l

l l

environment may exist.

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i i

1.4.1.3.2.5 Security Superintendent l

I I

I The Security Superintendent reports to the General Manager Plant Support l

l l and is responsible for plant security including coordination of efforts I

of the security force and to manage the operation of the security system.

l I

1 l1.4.1.3.3PlantModificationsManager I

I The Plant Modifications Manager reports to the Executive Director ANO 1 Site Operations and is responsible for directing the activities of his i

lstaffrelatingtoworkassociatedwithplantconstructionand I modifications, interfacing with other departments to assure effective l

l implementation of job assignments and providing cost and schedule I controls for department activities.

He is also responsible for providing I

engineering support during the implementation and closeout of design l

l modifications generated from LRGO or the plant.

He provides technical ldirectionandadministrativeguidancetothe:

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a.

Construction Superintendent i

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b.

Project Engineering' Superintendent l

c.

Field Engineering Supervisor y

d.

Project Controls Supervisor l

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1.4.1.3.4 Special Projects Manager j

i I

The Special Projects Manager reports to the Executive Director AND Site l

l Operations and is responsible for on site Licensing activities I

l I

g and the administration and control of special projects pertaining to l

l plant operations, maintenance and administration.

The Special Projects I

Manager is to provide technical direction and administrative guidance to I

the:

l l

l I

I 1

(

l a.

Plant Projects Supervisor I

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b.

Plant Licensing Supervisor g

I c.

Plant Controller 1

)

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l Additional duties include:

1 O

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l 1.

Serving as chairman of the Plant Safety Committee l

l 1

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I 2.

Interfacing with on-site regulatory agencies and the Nuclear i

l l

Engineering & Licensing Manager pertaining to Licensing and l

l regulatory matters.

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3.

Providing evaluations and recommendations in meeting regulatory l

l commitments.

I i

1.4.2 ENGINEERING I

I I

I g

LRGO Engineering is under the direction of the Engineering Vice President g

I who reports to the Generation, Transmission, Engineering Senior Vice I

I I

President.

The Engineering Vice President is responsible for providing l

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technical support to the AP&L nuclear plant in the areas of generation l

I I

engineering and technical support services.

He provides technical g

(

l direction, administrative guidance and supervision to the:

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l 4

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I a.

Generation Engineering General Manager i

b.

Technical Support Services General Manager 1

I I

I 1.4.2.1 Generation Engineering y

I I

The Generation Engineering General Manager reports to the Engineering l

l Vice President and is ' responsible for LRGO design and engineering l

l activities related to nuclear plant operations.

His duties include the 1

following:

l l

l 1

l I

l l

l 1.

Provide technical direction and administrative guidance to; I

l l

l a.

Mechanical Engineering Manager l

I i

b.

Electrical Engineering Manager l

l c.

Civil Engineering Manager l

l d.

Instrumentation and Controls Engineering Manager l

l 2.

Assure conformance to the Quality Assurance Program by l

l instituting the necessary quality-related procedures and I

l l

instructions within Generation Engineering.

l l

l 3.

Provide for review and approval of design and engineering l

l l

activities performed by contractors, vendors, and LRGO l

personnel for Generation Engineering projects.

l l

1 1

4.

Provide for review and approval of procurement documents for l

equipment, material and services for LRGO engineering projects, 1

l as appropriate.

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l 5.

Provide and maintain a qualified and suitable trained staff to I

l carry out required departmental functions.

l

_O l1.4.2.2 l

Technical Support Services General Manager l

g I

I The Technical Support Services General Manager reports to the Engineering l Vice President and is responsible for providing support to the AP&L l

nuclear plant in the areas of plant performance, maintenance and l

l l

availability, planning and scheduling, chemistry, environmental l

l monitoring, metallurgy and nondestructive examination.

His duties 1

include the following:

l I

I I

l-l 1.

Provide technical direction and administrative guidance to:

l I

I I

a.

Production Services Manager

'l b.

Technical Services Manager I

c.

Planning, Scheduling and Cost Control Manager i

I I

d.

Technical Analysis Manager

)

l I

l 1

2.

Assure conformance to the Quality Assurance Program by l

instituting the necessary quality-related procedures and 1

instructions within the Technical Support Services Department.

l l

3.

Provide for coordination of environmental surveillance programs I

l 4.

Direct development of programs aimed at maximizing efficiency l

l and availability.

l 1

l' I

I I

5.

Provide for review and analysis of outage data and make l

l recommendations for improving availability or performance.

1 I

i 6.

Provide project control systems, methods and reporting formats I

to support managerial requirements.

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7.

Direct the plant maintenance support activities that are l

l l

I assigned to the LRGO.

O l

l g

Provide and maintain a qualified and suitably trained staff to l

8.

l carry out required departmental functions.

I I

I l

9.

Administration of LRG0 first tier procedures in support of the l

QA Manual Operations.

I I

I 1.5 INDEPENDENT REVIEW ORGANIZATIONS I

I In add'ition to the responsibilities of key individuals within the AP&L l

j l

organization who are involved with the overall quality program, AP&L has I

established the following committees as a management tool to I

independently review activities occurring during the operational phase of I

lanuclearplant.

I i

l

1. 5.1 Safety Review Committee (SRC) i I

The SRC reports to the Nuclear Operations Vice President and is l

responsible for providing off-site independent reviews, and/or audits I

relating to:

the Safety Analysis Report, Technical Specifications, l

Procedures and changes thereto; unreviewed safety questions; violations, I

Ig deviations and reportable events; and any other matter involving safe I operation of the nuclear plant which the committee deems appropriate or I

is referred to them by the on-site operating group.

The SRC is also to I

review the reports and meeting minutes generated from the Plant Safety l

Committee.

I i

l1.5.2 Plant Safety Committee (PSC) l I

l The PSC reports to the Executive Director AND Site Operations and is I

responsible for reviewing activities specified in the Technical i

l I

Specifications for the purpose of

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1 L- - -- -------------

i i

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i 1.

Rendering determinations in writing with regard to whether or

_l I

I not an unreviewed safety question (defined by 10CFR50.59) is l

involved; and I

I I

I l

2.

Furnishing written recommendations' to the Executive' Director i

AN0SiteOperationsforadprodal.

l l

1 These activities include changes to plant procedures and Technical l

l Specifications, proposed modifications to plant systems, changes to l

plant security and emergency plans, and review of facility l

operations to detect potential nuclear safety hazards.3 l

l l

a I

I i

l 1.5.3 Committee Structure I

h I

I l

I I

l The organization structure and administrative requirements specific to l

each committee are described in the Technical Specifications for each l

l operating unit and in internal procedures / documentation.

l l

1 l

I l

1.6 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES l

O I

l l

I l

As owner and operator, AP&L assumes full responsibility and authority for l

l the plant including action to absure that the plant is operated in i

accordance with sound engineering practices, Licensing requirements and l

lapplicablecodes,specificationsandprocedures.

1 l

I Each supplier of equipment, material or services and each maintenance or l

modification contractor is responsible for administering the applicable l

lqualitycontrolfunctionsasrequiredbyAP&L.

NQ0 is responsible for l

assuring by surveillance, inspection, audit or review of objective l

I I

evidence (e.g., review audit reports conducted by others,.etc.) that I

I l

these functions are accomplishes for systems, structures and services l

lthataffectthesafetyandintegrityoftheplant.

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l Visits to manufacturer's shops by Quality Assurance personnel'are l

I conducted, when deemed necessary, based upon safety significance, complexity, method of acceptance and past history of the vendor, to I

establish product quality and to assure that quality assurance and I

quality control programs function in accordance with AP&L requirements.

l l

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I O

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2. 0 QUALITY ASSURANCE PROGRAM l

1 l

l 2.1 SCOPE l

I I

l l

I This quality program is to assure that AP&L's nuclear plant is operated i

in a safe, reliable and efficient manner and in accordance with NRC

[

regulations, applicable industrial standards and codes and applicable l

Company policies, rules, procedures and licensing documents.

A matrix of l

quality procedures cross-referenced to each criterion of 10CFR50, App. B, l

lisincludedinTable2tothismanual.

l l

2.2 GENERAL l

l-

{

2.2.1 i

l I

This quality program is applied to those safety-related structures, I

systems and components and to those expendable and/or consumable items

l whose satisfactory performance is required to prevent accidents which may l

cause undue risk to the health and safety of the public or to mitigate I

l the consequences of such accidents if they were to occur.

These l

structures, systems, and components are identified in the summary level l

l and component level Q-lists f each nuclear unit.

The Summary Level l Q-Lists (SLQL) are located in the SAR's and information for the component l

l 1evel Q-lists (CLQL) are maintained current in the Station Information i Management System (SIMS) for each nuclear unit.

When structures, systems l

landcomponentsasawholeareontheSLQLorCLQL,portionsnotassociated I with a loss of safety function as determined by Engineering are to be l

considered Non-Q, unless otherwise dispositioned by Engineering.

I I

Expendable and/or consumable items are to include, as a minimum:

l nuclear fuel, weld rods, boric acid, and diesel fuel.

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t

~

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l 2.2.2 I

I I

f~

l l

,(,

I Expendable and/or consumable items where quality is necessary for the

}

performance of Q-listed structures, systems and components are. identified

_g I

and controlled in accordance with plant Technical Specifications and/or.

l

'a procedures.

,I h

f.j-The following expendable ard/or consumable items are to be controlled in 4

g g

i the.following manner to assure service quality:

l I

I i

1 l

1.

Diesel Fuel - Service quality is assured by applicable i

l I

l provisions / tests required by the Technical Specification for l-l l

each operating nuclear unit.

I I

l l

I

'l

.r.

Welding Rod - Service quality is assured by procurement from an i

evaluated source, requiring material test results when l,

I specified by the ASMF. Code or applicable design document, and l

l controllingtherodon'-siteprj;cv'touse,toprevent l

[

degrads t.i.in.

l O

l

~

ll l

3.

Boric R id - Service quality is assured by procurement from an

-l ev.rWated source, requiring a batch analysis to assure i

I conformance with our specification requirements, and on-site l

l control prior to use, to prevent degradation.

I i

l 2.2.3 l

l The quality pyogram for transport packages containing radioactive I

uterials is midrassed in Appendix A of this manual, and implemented I

l through appropriate LRGO and dlant procedures.

The effectiveness of this l

rdogram is verified througIsshequied audits conducted by the NQ0, under l

lthecognizanceoftheSRC.

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1.

i

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1 d

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l 2.2.4 l

l l

i The quality program for fire protection is addressed in Appendix B of lthismanualandintheapplicablesectionof.theSARandTechnical l

l Specifications for each operating nuclear unit, and implemented through l

lappropriateLRGOandplantprocedures.

The effectiveness of the fire l

protection program is verified through scheduled audits conducted by the l

NQO, under the cognizanco of the SRC.

l l

2.2.5 I

lTheSLQL(aspartoftheSAR)isunderthecontroloftheNuclear l

l Engineering & Licensing Manager.

The Nuclear Engineering & Licensing I

l Section maintains an up-to-date list of personnel issued a copy of the l

l l

SAR for each nuclear unit and assures that reviews, approvals, I

ldistributionsandchangestheretoareperformedinaccordancewith l

ll approved procedures.

Changes to the SLQL require review / approval by the l

lapplicableEngineeringManager,QualityAssuranceSuperintendentand i Nuclear Engineering & Licensing Manager.

I l

I 2.2.6 l

1 I

I l

I l The CLQL is maintained on a computer data base (SIMS) and is controlled l

linaccordancewithLRGOandplantprocedures.

Generation Engineering is l

responsible for the technical adequacy of the CLQL and assigned l

lindividualswithintheWorkControlCenterareresponsibleforthe I

administrative controls on the CLQL within SIMS.

Evaluations, reviews I

and approval to changes to the CLQL are performed in accordance with I

applicable LRGO and plant procedures, l

I l

i I

I 2.3 RESPONSIBILITIES I

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l 2.3.1

]

1 I

l 1

- 'q l AP&L recognizes that quality assurance is an interdisciplinary function l

involving many organizational groups, encompasses many functions and l

l activities and extends to various levels in all participating l

l organizations (fromtheExecutiveVicePresidentstoallworkerswhose I

activities may influer.ce quality).

This quality program designates I

responsibilities and duties of specific individuals, which may be l performed by their appointed designees.

l 1

l l

2.3.2 l

I I

l This quality program assigns the responsibility for quality to the I

departments performing the work and includes as a basic requirement that l

l individuals responsible for verification of conformance are qualified and l

ldonotperformordirectlysupervisethework.

Additionally, independent l

l reviews, audits and surveillance are provided by individuals not l

l reporting to the groups responsible for performing the work.

l 1

l l2.3.3 l

1 I

This quality program also includes provisions that require suppliers, g

I contractors, subcontractors, consultants, etc. to maintain and use

]

quality assurance programs reviewed and approved by the Quality Assurance l

k l

Superintendent.

Audits or surveillance by the NQ0 provide assurance of l

lcompliancewithapplicableprocedures.

I I

l2.3.4 l

l l

I The Core Reload Design Sr. Engineer within the Nuclear Engineering &

l I

Licensing section and the Reactor Engineering Supervisor are responsible

]

for the assurance that nuclear fuel used in AP&L nuclear plar.ts is l

l designed, procured, manufactured, and utilized in accordance with I

regulatory requirements, and related industrial codes and standards.

I I

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l

I I

l On-site quality control of nuclear fuel is implemented through the.use of.

l plant administrative procedures.

These procedures include the receipt, l

I inspection, handling, storage, and accountability of Special Nuclear l

l Material (SNM).The Reactor Engineering Supervisor maintains a listing l

l of those individuals qualified to perform receipt inspections, l

I I

l 2.4 PROCEDURES l

1 I

I i

l 2.4.1 l

1 I

I I

l Activities which affect quality are defined in appropriate procedures, I

l which are developed to cover AP&L administration and control.

The l procedures state the policies and instructions necessary to fulfill the I

intent'of the program.

Procedures provide for standard forms, lists, and I check-offs used in. documenting the inspections, certifications, reviews, I

surveitlances and audits.

Programs and procedures are modified or i

supplemented from time to time as.the need for change arises during the l

llifeoftheplant.

Quality program policies, procedures and instructions I

are contained in the' documents listed in Table 3.

l O

l l

l 2.4.2 i

I I

l Procedures assure that activities affecting quality are performed under I

suitably controlled conditions.

Controlled conditions include the use of I

appropriate equipment; suitable environmental conditions for performing l

the activity such as adequate cleanness; and assurance that required l

l prerequisites for the given activity have been satisfied.

Administrative l

procedures also assure that the need for special controls, processes, I test, and equipment to attain the required quality and the need for l

verification of quality by inspections, evaluation or test is taken into I

account.

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2.4.3 l

1 1

l l

Other AP&L organizations outside of Generation, Transmission,' Engineering lmayestablishwrittenprocedurestocontrolsupportactivitiesaffected l

l by the requirements of this quality program.

Procedures developed by l

q I

such organizations are prepared and reviewed for technical adequacy g

l within the cognizant organization, reviewed by the Quality Assurance l

)

Superintendent and approved by the cognizant organization's department l

I head.

l I

I I

I l

2.5 PROGRAM REVISION AND CONTROL I

I l

l I

I 2.5.1 l

l 1

l l

l 1

Program revision and control shall be the responsibility of the Nuclear I

Quality General Manager.

l l

1 l2.5.2 i

I gQ lProposedchangestotheQualityAssuranceManualOperationsaretobe

_l l

submitted by the Quality Assurance Superintendent to affected LRGO and l

plant management personnel for review and comment prior to approval and i

l transmittal to the Nuclear Regulatory Commission.

After resolution of l

comments, changes are to be approved by the Quality Assurance l

l Superintendent, Nuclear Quality General Manager and the Nuclear l

j lOperationsVicePresident.

I I

2.5.3 I

I lTheNuclearRegulatoryCommissionistobenotifiedofchangestothis l

quality program annually for those changes that do not reduce the i

j l

commitments in the program description previously accepted by the Nuclear l

l Regulatory Commission.

Changes to the program description that reduce l

the commitments are to be submitted and approved by the Nuclear l

l I

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Regulatory Commission prior to implementation.

The Nuclear Quality l

I General Manager is to determine if changes do. or do not reduce the commitments of this quality program.

I I

I l

i 2.6 PERSONNEL l

l l

l 2.6.1 l

l l

Employees whose duties and responsibilities are related to the quality l

l program activities at or in support of the nuclear plant are to l participate in appropriate indoctrination and training programs to assure I

that suitable proficiency is achieved and maintained in the work they are I

performing.

Such training shall include, as a minimum:

plant security-l (badged personnel only); discussion of the overall Company policies, l

l procedures and instructions which estaolish the quality program; an i

explanation of the AP&L quality organization; and a discussion of those l procedures which implement the quality program related to'the employee's I

specific job-related activity.

l 1

I l2.6.2 l

1 I

The education, experience and responsibility requirements of individuals l

l involved in this quality program are documented in job descriptions which 1

J are approved and periodically reviewed by management.

Requirements for I

education, experience and proficiency levels are commensurate with the I

degree of importance of the job assignment.

Experience and training i requirements for plant staff personnel are to meet the requirements of I

ANSI N18.1-1971 and Regulatory Guide 1.8 (9/75), unless otherwise noted I

in Table 1.

Personnel whose qualifications do not meet those specified I

l linANSIN18.1-1971, and who are performing inspection, examination and l

l testing activities during the operational phase of the plant, are to meet l

ltherequirementsofANSIN45.2.6-1978, unless otherwise noted in Table 1.

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I I

l 2.6.3 1

I i

q l

l l

Personnel performing inspection and examination activities are to be l

indoctrinated and trained to assure they are aware of the requirements l which govern their activity.

Inspection and examination personnel are to l

be qualified according to the applicable codes, standards, l

specifications, regulatory requirements and LRGO and plant procedures.

I Personnel performing inspections on those activities occurring during the l

l operational phase that are comparable in nature and extent to related I

activities occurring during initial plant design and construction are to i

meet the provisions of Regulatory G., % 1.58, rev. 1 (9/80) and ANSI l

l N45.2.6-1978, in lieu of ANSI N18.1-1971.

l l

2.6.4 l

l lPersonnelinvolvedwithweldingofmaterials,systemsorcomponentsare l

to meet the appropriate qualification requirements of the ASME Boiler and l

Pressure Vessel Code, Sections III and XI, or for structural welds, the i American Welding Society (AWS) Structural Steel Code 01.1.

Personnel l

O l

l Q

involved with nondestructive examination of materials, components or I

systems are to meet the qualification requirements of the American l

l Society Nondestructive Testing Standard SNT-TC-1A, or ASME Section III l

l and XI for ASME Code materials, components or systems.

Personnel are to I

be certified to perform these tasks in accordance with these codes and I

standards.

l l

1 I

I l

2.6.5 l

1 1

I I

i Personnel performing audits of the quality program are to meet the l

i l

experience, training and qualification / certification requirements of l

ANSI N45.2.23-1978, and regulatory guide 1.146 (8/80), unless otherwise l

lnotedinTable1.

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l 2.6.6 I

I I

Personnel appointed to the SRC shall collectively have the experience l

landcompetencerequiedbyANSI/ANSN3.1-1981.

Personnel appointed to I,

I the PSC shall collectively meet those requirements identified in the i

Technical Specification applicable to each nuclear unit.

l l

2.6.7 l

l Training records are to be maintained in accordance with AP&L approved l

l procedures.

For formal training programs, documentation is to include l

ltheobjective,contentoftheprogram, attendees,anddateofattendance.

I I

l 2.7 PROGRAM REVIEW I

1 l

2.7.1 l

l l

The Nuclear Quality General Manager through the Quality Assurance l

Superintendent is responsible for a raiew of this program on an annual l

j p

l V basis to determine the effectiveness and proper implementation of the l

l quality program.

I l

l 1

I i

l 2.7.2 l

l l

1 l

Management reviews of the status and adequacy of the quality program are I

accomplished through regular reports and presentations by the NQ0 and l

through reviews of quality assurance audit reports.

Quality Assurance l

l reports supply data on the status of outstanding audit and corrective l

l action items and may identify the status of other significant quality l

program activities as requested by management.

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3.0 DESIGN CONTROL 1

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1.

3.1 SCOPE l

)

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j Design activities are tc be controlled to assure that proposed plant l

changes to the structures, systems, equipment and components conform to l

applicable regulatory requirements and that design bases are correctly l

I translated into appropriate design documents.

Design Control. activities l

are to be in accordance with the requirements of Regulatory Guide 1.64 -

l l

Rev. 2 (6/76) unless otherwise noted in Table 1.

l 1

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l 3.2 GENERAL 1

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3.2.1 l

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Generation Engineering, Project Engineering and Plant Engineering l

are responsible for the continued upgrading and modification of plant

-]

I design.

Design documents (drawings, specifications, procedures and l

instructions) originating or released through these departments are to j

)

be based upon the required re;;ulatory requirements, licensing based.

l documents, functional requirements, quality standards and design bases l

I I

in accordance with NRC licensing requirements.

Design activities may l

l l

include calculations, analyses, materials selection, equipment l

arrangement and layouts, accessability for inservice inspection, and the j

specification of test and inspection criteria.

Those design activities l

l I

l performed by individuals within Generation Engineering, Project I

l Engineering and Plant Engineering are controlled by the use of plant l

]

I i

I modification process (PMP) control procedures and by applicable LRG0/ plant I

I l administrative and departmental procedures.

These procedures include j

l l controls to assure that verified computer codes are certified for use and l

l l that their use is specified.

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Design work performed by organizations outside of AP&L is to recefve a

~

documented review and approval by engineering personnel in accordance l

l l with PMP control procedures and as applicable, LRG0/ plant departmental l

I I

I procedures, j

g I

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3.5 DESIGN CHANGE l

I l3.5.1 l

l l

{

Methods for the preparation, review, approval and. implementation of l

l design changes, including field changes, are documented in PMP control l

)

procedures and departmental procedures for Generation Engineering, l

l Project Engineering and Plant Engineering.

Design changes are subject to l

l l

review and verification by the same organization which reviewed and i verified the original design unless otherwise specified in departmental l

procedures for design control.

If changes'to an approved design are l

required to meet plant requirements or conditions, Field Change Requests Q

g (FCR) may be issued or otherwise documented by a cognizant engineer and g

I transmitted with the changes for review and approval in accordance with l

lPMPcontrolproceduresandapplicableLRG0/plantdepartmentalprocedures.

l l

l3.5.2 l

l l

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Changes from specified design inputs, such as design bases, regulatory l

l requirements, codes and standards (including quality standards) are to be i

identified, approved, documented and controlled through PMP control l

l procedures and applicable LRG0/ plant departmental procedures.

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l 3.5.3 I

.I l

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l During preparation of a design change, the responsible er.gineering l

l organization is to perform a safety and environmental review per l

l 10CFR50.59 to verify compliance with the Safety Analysis Report and to l

determine if NRC approval of the design change is required.

The I

review is to be documented, reviewed by the PSC and approved by the l

Executive Director AND Site Operations.

l l

I l

3.5.4 1

l Design changes are also to be submitted to the QC Superintendent prior to l

plant implementation to verify the use of appropriate quality codes, l

standards and inspection requirements in the design documents.

I I

l 3.6 CORRECTIVE ACTIONS I

I I

lWhendesignchangesaremadeasaresultofdesigndeficienciesor l

errors, corrective actions (for significant conditions) are to be taken l

linaccordancewithSection16.0,todeterminethecauseandtoinstitute l

l l

appropriate changes in the design process and/or Quality program to l

}

prevent recurrence.

When a significant design change is necessary l

because of an incorrect design, the design process and verification l

lproceduresshallbereviewedandmodifiedasnecessary.

l l

l I

I 3.7 DESIGN RECORDS t

I l

i l

l The plant Administrative Manager is responsible for maintaining permanent l

J lrecordsofthedesign,documentsfortheconstructionandtestingphases.

l In addition, he shall be responsible for maintaining records of the I

upgrading or modification of these documents as described in this j

section.

The controls for maintaining these records are established by l

specific procedures described in Section 17 of this manual.

These I

records provide the historic reference necessary for the safe and l

l reliable operation of the plant.

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(

l 4.0 PROCUREMENT DOCUMENT CONTROL 1

)

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1 4.1 SCOPE I

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Requirements for the procurement of items and services are to be clearly l

l stated and documented to assure that applicable regulatory requirements, 1

design bases, technical requirements and quality assurance criteria are l

included or referenced in the procurement documents, whether procured by l

8 l

LRGO or plant procurement groups.

Procurement document control I

activities are to be in accordance with LRGO and/or plant procurement l

l procedures and are to meet the provisions set forth in NRC Regulatory l

Guide 1.123, rev. 1 (7/77) unless otherwise noted in Table 1.

I I

i 4.2 PROCUREMENT DOCUMENTS I

l 4.2.1

)

l I

The procurement of materials, parts and components are generated through l

]

l the preparation of a Purchase Requisition (PR) and subsequent issuance of l

i O

l a Purchase Order (PO), or when additional services from the Vendor is l

Q g

y I

required, through the preparation and issuance of a Contract.

The l

I I

procurement of services is initiated through the preparation and issuance g

l of a Contract.

The preparation, review, approval and issuance of these

-l procurement documents is to be in accordance with applicable procurement l

and contract administration procedures.

Purchase Orders for items are I

issued through the AP&L Procurement Section and Contracts for items and/or I

services are issued through the AP&L Contracts Administration Section.

l l

I 1

4.2.2 l

l l

I l

l Procurement documents are to include or reference specific design l

specifications for the items or services to be procured which define l

l specific codes, standards, tests, inspections, environmental l

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4.0 PROCUREMENT DOCUMENT CONTROL lPAGE 4-1 l

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l 4.4 CHANGES TO PROCUREMENT DOCUMENTS I

I I

n i

I Q

l. Changes to procurement documents are to have the same degree of control I

and review as imposed on the original documents.

Changes such as I

inconsequential editorial corrections or changes to commercial terms and i

conditions may be made by Procurement or Contract Administration 1

personnel, as appropriate, after concurrence from the originator or i

organization which originated the document.

l l

i I

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4.0 PROCUREMENT DOCUMENT CONTROL IPAGE 4-3 l

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l determine that important activities have been satisfactorily l

l accomplished. Each procedure is to be sufficiently detailed so that a I

l qualified individual may perform the required function (s) without direct l

supervision and is to include measures to document the activity'being l

performed.

l l

l 1

I l

5.2.2 l

j l

l

{

l 1

l To assure the accomplishment of activities in accordance with approved j

instructions, procedures and drawings, each supervisor is responsible for l

quality compliance of his personnel.

Verification that activities are l

I accomplished in accordance with approved instructions, procedures and I

a l

l l

l drawings is obtained through various levels of surveillance and l

inspection by Quality Control personnel and through periodic surveillance l

and audits by QA personnel.

[

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5.3 REVIEW 0F INSTRUCTIONS, PROCEDURES AND DRAWINGS l

1 l

l l

l 5.3.1 l

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Instructions, procedures and drawings are prepared, reviewed and approved l

l in accordance with applicable LRG0/ plant administrative procedures.

I I

l 5.3.2 I

j l

I l

t i

I Plant procedures identified in the Technical Specifications for each unit I

l l

l and changes thereto which describe activities required to implement this l

quality program are to be reviewed by the PSC prior to submittal of the l

l procedures to the Executive Director AN0 Site Operations for approval l

l I

and subsequent issuance.

Plant Administrative procedures (1000.XX l

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Series) l l

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5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-2 l

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l AND ORAWINGS I

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l

)

l

I I

I_

l l are also reviewed by NQ0 to verify compliance to AP&L's quality program l

l requirements.

LRGO Generation, Transmission & Engineering (GT&E) procedures describing activities required to implement this quality l program are to be reviewed and approved by a procedures task force l

I committee and NQ0 to assure compliance to AP&L's quality-program l

I I

requirements prior to submittal of the procedures to the Department Head l

i responsible for implementation, for approval and subsequent issuance.

I I

I l

5.3.3 I

I I

i i

Plant and LRGO procedures and instructions are to be reviewed no less I

l I

than every two years to determine if changes are necessary to meet NRC l

l commitments and current AP&L practices.

Applicable procedures (i.e.

l lthosethatrelatetotheincidentcause)aretobereviewedfollowingan I

unusual incident such as an accident, unexpected transient, significant l

l l

l operator error or equipment malfunction.

Applicable procedures are also I

to be reviewed following any modification to a plant system.

I I

l 1

5.3.4 I

O l

l Drawings related to plant changes and modifications are controlled as l

ldescribedinSection3and6ofthismanual.

l l

l5.4 l

\\

CHANGES TO PROCEDURES I

l

)

l5.4.1 l

I l

Changes or revisions to approved instructions, procedures and drawings l

l l

are to be reviewed and approved by the same organizations or groups that l

I I

j l

performed the original review unless otherwise noted in specific AP&L l

l procedures and controlled in the same manner as the original.

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5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-3 I

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l AND DRAWINGS l

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l 5.4.2 l

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l Temporary changes (interim approval) to approved plant procedures which l

do not change the intent of the procedure may be made provided such l

l changes are approved by two members of the plant management staff, at l

lleastoneofwhomholdsaseniorreactorsoperatorslicenseontheunit l

affected.

The change is to be documented, reviewed by the PSC, and l-approved by the Executive Director AN0 Site Operations within 14 days I

of implementation.

Temporary changes to approved plant procedures which l

change the intent of the procedure may be made provided such changes are l

l reviewed by the PSC and approved by the Executive Director ANO Site l

l l

Operations prior to implementation.

Temporary changes to approved plant l

procedures are to specify the period of time during which they may be l

l used and made readily available to affected members of the plant staff.

l In the event of an emergency not covered by an approved procedure, l

I, operations personnel may take action, without obtaining approvals, so as l

to minimize personnel injury and damage to the facility and to protect l

lhealthandsafety.

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5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-4 l

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l AND DRAWINGS l

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'l i

l approved historical plant documents, and the storage of historical l

I drawing records.

The plant Engineering Manager is responsible for the I

control and issuance of drawings and revisions thereto to assure that-l they reflect the as-built conditions of the plant.

l I

l l6.2.4 l

l 1

lTheTechnicalSupportServicesGeneralManagerisresponsiblethrough l

l the Technical Services Manager for the control and issuance of LRGO I

Generation Transmission & Engineering procedures, and revisions thereto, l

l to assure distribution in accordance with departmental procedures.

I I

I l

l 6.3 IDENTIFICATION l

I I

l l

I I

Documents are to be identified by a title descriptive of their purpose or i

applicability and marked or stamped as to their current status (Draft, I

For Information Only, Void, etc.) per departmental procedures.

Revision l

lstatusofdocumentistobeidentifiedindocumentregisters, I

distribution lists and/or within the revision record page/ block of the l

l l

document.

I I

H l6.4 l

DISTRIBUTION l

1 l

lDistributionlistsand/ordocumentregistersaretobemaintainedbythe I

organization responsible for issuance of the document.

These lists are l

l to identify the revision status of the document and are to be reviewed I

and updated periodically by the responsible organization to maintain them i

in a current status.

These lists are available to individuals using the I

document to assure they are in receipt of the current document.

These I

measures are to preclude the possibility of using outdated or I

inappropriate documents.

I I

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(1) Source survey by AP&L to verify compliance to applicable 10CFR50, l

I I

Appendix B requirements or to applicable ASME Section III Quality q

l l

Q l

Assurance program requirements.

(This is not applicable to ASME l

l Procurement unless justified in accordance with the AP&L ASME l

l Section XI Repair and Replacement Program.)

l l

1 I

l l

(2)' Evaluation and acceptance of source surveys performed by others l

(ex. CASE, other utilities, NSSS suppliers, and prime contractors) l l

j l

indicating a program meeting the appropriate requirements of l

10CFR50, Appendix B.

(This method is not applicable for ASME l

procurement.)

l I

I l

(3) A review of the vendors / contractors current quality records l

supported by evidence of documented qualitative and quantitative l

information which can be objectively evaluated.

This includes l

review and approval of the vendor's/ contractor's quality assurance l

l program, marval and procedures, when available.

(This method is not l

l applicable for ASME procurement).

l l

l (4) Evaluation of the vendor's/ contractor's history of providing a l

product / service which performs satisfactorily in actual use.

l Evaluation information includes:

experience of users of identical l

or similar products / services of the prospective vendor / contractor; I

and/or procurement records that have been accumulated in connection l

l l

with previous procurement activities and operating experiences.

l j

(This method is not applicable to ASME procurement).

l I

l(5) l Verification that a vendor is a nolder of an ASME Certificate of l

Authorization issued as a result of an ASME survey.

(This method is l

applicable for both ASME and 10CFR50, Appendix B procurement.)

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7. 0 CONTROL OF PURCHASED lPAGE 7-2 l

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l MATERIAL, EQUIPMENT AND SERVICES I

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I l

performed in accordance with plant procedures for receipt inspection.

I l

I i

7.4.2 l

l l

1 l

Receipt inspection activities are to be documented and include, as a I

minimum:

examination of material or equipment for shipping damage, i

proper identification, and quantity; and the review of vendor I

documentation to verify compliance with the procurement document.

In l

addition, if material and equipment received at the plant were not I

inspected at the vendor's facility by AP&L, an inspection is to be l

l performed by a Quality Control inspector at the point of receiving to l

verify that the material or equipment conform to the inspection l

requirements identified in the procurement documents.

l 1

l l

7.4.3 l

l 1

I I

l Vendors are to furnish documentation as required by the procurement l

documents for objective evidence that the material or equipment conforms j

to the procurement requirements.

Review and acceptance of this l

i ldocumentationistobeperformedbyQualityControlpersonnelpriorto l

l installation or use of such material or equipment and the results l

l documented unless otherwise specified in plant procedures.

l Certificates l

of Conformance may be required by procurement documents which identify l

ltherequirementsmetbythevendor.

The validity of the vendor's l

l certification program is to be periodically verified through scheduled l

f source surveillance and audit activities or through independent testing l

l of the item by AP&L.

l I

l l

7.4.4 l

l l

l Accepted material and equipment is released, identified as to its l

inspection status and forwarded to a controlled. storage area or released i

for installation per applicable plant procedures.

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l MATERIAL, EQUIPMENT AND SERVICES I

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l 3)

Identification of any special equipment and tools required to I

perform the inspection (when accuracy requirements for l

l inspections exceed the accuracy of normally available process I

or measuring and test equipment, such additional accuracy l

I requirements are to be specified within those inspection l

i I

procedures);

l l

4)

A step-by-step description of the method of inspection, l

)

l examination, measurement or test to be performed; and l

1 5)

Identification of those inspection results to be documented.

I 1

i l

I Inspection forms or checklists are to be used as an aid in j

]

g I

documenting the inspection activity to assure quality l

l l

g requirements have been met, g

l l

J l10.3.2 l

l l

l Operational inspections are to be performed by qualified individuals l

I other than those who performed or directly supervised the activity being l

)

l inspected.

Construction inspections are to be performed by qualified l

l individuals other than those who performed or directly supervised the I

activity being inspected and do not report directly to the immediate l

l supervisors who are responsible for the activity being inspected.

l l

l

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l 10.3.2.1 l

l 1

i l

I l

Operational inspections may be performed by second-line supervisory I

l l

personnel or by other qualified personnel not assigned first-line I

supervisory responsibility for conduct of the work.

.I i

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i l

l l

l 10.3.2.2 l

J l

i I

I I

Construction inspections are to be conducted in a manner similar to that I

associated with construction phase activities in accordance with l

l applicable plant and departmental procedures, l

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[PAGE 10-'3 I

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'10.4.2 1

1 I

l l

Inspection hold points are inserted in procedures based upon safety significance, complexity of the item or activity, degree of l

standardization of the item or activity, past performance of the item or l

)

activity and the ability to verify quality by jobsite testing.

l I

l 10.4.3 I

I I

I Inspection responsibilities, requirements, information and acceptance I

l i

i criteria for the work activity are to be identified in appropriate, l

approved documents (e.g. procedures, checklists, etc.)

l l

l l10.4.4 l

l l

lForworkinvolvingthemodification, repair,replacementorin-service l

l inspection of ASME Code materials, parts and components, the work l

lpackagesaretobemadeavailabletotheCodeInspectorpriorto l

commencing work for his review and assignment of inspection = hold points.

l l

lThedepartmentresponsiblefortheworkactivityisresponsiblefor l

notifying the Code Inspector when the hold point is reached.

Work is not l

to proceed past a Code Inspector's inspection hold point until signed or l

waived by the Code Inspector.

l l

10.5 DOCUMENTATION l

l l

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l 10.5.1 l

1 I

I I

I i

l Inspections and process monitoring activities are to be performed and the results documented in accordance with approved procedures or l

instructions.

Records are to:

provide objective evidence that the l

inspections and monitoring activities were performed in compliance with' l

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L

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j l procedures, instructions or drawings to verify design requirements; show l

1 I' compliance with acceptance criteria or identify the cause of rejected I

items; and identify the appropriate inspection personnel approving the

]

lresults.

l l

l10.5.2 l

l 1

lRecordsaretobemaintainedinaccordancewithapprovedwritten i procedures and Section 17 of this manual.

Inspection results on ASME l

Code items are available to the Code Inspector for his review.

I l

i l

10.5.3 l

1

-l

]

The results of inspection and monitoring activities are periodically l

l evaluated per approved procedures and the results documented to determine I

whether the individual inspection programs demonstrate that the plant can l

be operated safely and as designed.

I l

l 1

l l

l 10.6 NONCONFORMANCES I

l D I

l l

Nonconforming items found as a result of inspection and monitoring l

lactivitiesareidentified,segregatedanddispositionedinaccordance l

l with approved written procedures and Section 15 of this manual.

Rework, i

repair or replacement performed after completion of inspections are to I

require reinspection to the extent necessary to determine acceptability l

ltoestablishedcriteria.

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1

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i 11.3.2.2 l

l l

Inservice inspections required to meet the requirements of ASME Boiler landPressureVesselCode,SectionXI,aretobeidentifiedinthe l

In-Service Inspection (ISI) Programs applicable to each unit at the l

l plant.

Engineering Services is to establish and maintain an ISI plan for l

l each unit.

The plan specifies the inspection items, inspection l

procedures, inspection intervals and type of inspections.

Engineering l

l Services is to coordinate the implementation of the ISI plans at I

appropriate scheduled outages.

The plans are also to be made available l

for review by the Code Inspector.

l l

l 11.3.3 l

I I

J l

l I

l Tests following plant modifications, repairs, maintenance, or significant l

changes in operating procedures, are to be conducted to confirm that they l

l are not detrimental to the safe and efficient operation of the plant and l

)

lthatthecomponentsorsystemsdemonstratesatisfactoryperformance.

I I

11.3.4 I

I Requirements for the given test to be performed are to be identified in l

l the test procedures / instructions.

Evidence is to be available to assure l

I the following minimum requirements are met:

I I

l I

I a) test equipment and measuring devices are calibrated in accordance with the requirements of Section 12 of this manual

]

and are functioning properly; i

b) test personnel have been qualified to perform the test in l

accordance with the requirements of Section 2 of this manual; l

l c) appropriate witness and hold point notifications have been l

provided; I

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m I

I I

I l documents and furnished to the plant prior to or upon receipt of the item j

I I

O lattheplant.

l l

13.3 SHIPPING CONTROLS 1

I i

l 13.3.1 l

1 lShippingrequirementsaretobespecifiedintheprocurementdocuments, I

l Suppliers compliance to these requirements'are to include controls to l

lassurethatitemsarecompleteandassembledasrequired;itemshavebeen

1. preserved and packaged in accordance with the procurement documents; l

items have been marked and identified in accordance with specifications and procurement documents; items have been loaded for shipment in such a j

manner as to prevent damage; and required documentation is complete and l

furnished in accordance with the procurement documents.

I l

l I

I I

13.3.2 I

I I

l l

l Special nuclear material and sources are to be shipped and stored as I

specified in the AP&L operating license and other appropriate regulatory k

l documents.

The Health Physics Superintendent is responsible for assuring l

that radioactive sources and instruments containing radioactive sources l

l are stored.and handled per these requirements and plant procedures.

The l

lRadwasteSupervisorisresponsibleforassuringthatlowlevelwaste l

l material is stored and shipped per these requirements and plant procedures.

I l

lTheReactorEngineeringSupervisorisresponsibleforassuringthat I

special nuclear material (SNM), as defined in plant procedures, is l

l shipped,storedandhandledpertheserequirementsandplantprocedures.

l l

l 13.4 RECEIVING I

I l

13.4.1 l

l Materials and equipment are to be received at the plant per plant l

l procedures and subjected to a receipt inspection in accordance with I

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l l SECTION:

13.0 HANDLING, STORAGE AND lPAGE 13-2 l

l L

l SHIPPING l

l l

1 l

l

)

l I

I l'

l for control of radioactive sources, Low Level waste material and SNM) to l

I identify those items currently in storage arid to facilitate inspection i

and maintenance planning.

Issuance of items from storage for-installation or use are to be documented and controlled in accordance l with plant procedures.

I l

1 I

I I

13.5.4 I

I l

l l

l Items identified as requiring maintenance during storage are to be 1

maintained in accordance with a documented maintenance program.

I l

i l13.5.5 l

l l

Storage areas are to be monitored by individuals responsible for the i

storage areas so that the integrity and security of stored items is l

leffectivelymaintained.

Inspections and examinations under the control l

l of the Quality Control Superintendent are to be performed and documented l

lonaperiodicbasistoassurethattheintegrityoftheitemsandtheir I

containers are being maintained.

Periodic audits under the control of l

n()

ltheQualityAssuranceSuperintendentarealsoperformedtoassure l

l compliance to storage requirements.

I l

l l

13.6 HANDLING CONTROLS l

l l

13.6.1 l

l 1

I I

l Special handling requirements are to be specified in the procurement l

documents and plant procedures to protect the quality of items l

susceptible to handling damage.

Special tools and equipment are to be l

provided to handle these items and are to be controlled and maintained I

per written procedure to assure safe and adequate handling.

I I

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l l SECTION:

13.0 HANDLING, STORAGE AND lPAGE 13-4 l

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l SHIPPING l

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1 I

I

i i

f I

I l

-15.2.3 l

I 1

Nonconformance reports are to identify the group responsible for I 'dispositioning the nonconformance.

Thei esigned individual-within the I

j responsible group is to evaluate the nonconformance and confer, as l

l l

appropriate, with interfacing groups to determine a recommended l

disposition.

The disposition for materials, parts, components and as l

l

. applicable, services (including computer codes), which may be reject, l

l rework, repair or use-as-is, and any actions taken/ required to be taken l

lasaresultofthedispositionaretobedocumentedonthereport.

l l

l l15.2.4 I

I lReviewofthedispositionforconcurrenceistobeperformedbythe j

i individual / group identified within LRGO or plant procedures.

If the l

llthedisposition,theExecutiveDirectorANDSiteOperation review group or individual cannot agree with the assigned individual on l

l l

l lplantortheNucNarOperationsVicePresidentatLRGOistodecide.

For I

a repair or use-as-is disposition, a cognizant individual knowledgeable l

l r

l in the design requirements for the affected item is also to review the l

g l

report for concurrence of the disposition.

Written justification for the I

design change, repair or deviation that has been accepted is to be j

documented to denote the as-built condition and is to be made a part of l

the report.

I l

l I

-l 15.2.5 1

l l-The acceptability of rework or repair of materials, parts, components, l

systems and structuren are to be verified by reinspecting the item as l

originally inspected or by a inethod which is at least equal to the I

original inspection method.

The rework and repair inspection records are l

ltobedocumentedandbecomepartofthepermanentrecordsfortheitem.

I i

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I I

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l A

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i l SECTION:

15.0 NONCONFORMING MATERIAL, lPAGE 15-2 I

I L

I PARTS AND COMPONENTS l

l l

1

i i

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1 l

l 16.0 CORRECTIVE ACTION l

l l

16.1 SCOPE l

l l

l I

l A corrective actions system is to be established to assure that l

conditions adverse to plant safety, such as failure, malfunctions, i

deficiencies, deviations, defective material and equipment, abnormal l

occurrences and nonconformances are promptly identified and corrected.

I In the case of significant conditions adverse to safety, this system is l

to assure that the cause of the condition is determined and corrective l

action taken is documented and reported to appropriate levels of l

management for independent review.

I I

l16.2 GENERAL l

l I

l16.2.1 I

i lWhendeviations, deficiencies, malfunctions,r,onconformancesorother l

abnormal occurrences or conditions are encountered, they are to be l

O I

I

()

reported to responsible authorities for review and disposition in I

accordance with applicable LRG0/ plant procedures.

l I

l l

16.2.2 l

l I

I l

l Cognizant supervisors are to review discrepancies discovered during the l

lcourseofstationoperationsandtakeappropriateactiontoresolvethe i

discrepancies and evaluate their safety significance.

For conditions l

l adverse to safety, they are to initiate corrective action to prelude l

recurrence.

For significant conditions adverse to safety, they are to l

I initiate action to identify their causes and take necessary corrective l

action to prelude repetition.

l l

1 I

I I

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SECTION:

16.0 CORRECTIVE ACTION lPAGE 16-1 l

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I 4

_____..___..___.___i__

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I i

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I

)

l 16.2.3 l-I l-I I

p g

l Evaluation of the corrective action is to be performed by the l

individual / group identified within LRGO or plant procedures to determine l

I l

its adequacy and completeness and to assure the need for additional l

lcorrectiveaction.

If the corrective action is acceptable, follow-up l

action to verify implementation, documentation and close out of the l

corrective action commitments is to be performed per LRGO or plant l

l procedures.

l j

l l

i I

i l

i 16.2.4 l

l l

I l

1 l

If the resolution cannot be agreed upon, it is to be referred to the next l

llevelofmanagementforresolution.

l l

l 16.3 SUPPLIER DEFICIENCIES l

l 1

l When vendors furnish products or services that do not conform to the l

requirements of the applicable purchase contract and, in the opinion of l

)

ltheQualityControlSuperintendent,thevendorwarrantsconsiderationfor l

reappraisal, the Quality Control Superintendent is to submit a vendar I.

reappraisal request to the Quality Assurance Superintendent for l

determination of action to be taken.

Results of the reappraisal, l

1 together with a request for specific corrective actions, are to be l

l transmitted to the vendor.

If the vendor does not improve his quality l

lassurancesystemandproductsasrequested,theQualityAssurance l

Superintendent is to remove the vendor from the Qualified Vendor List l

l(QVL)inaccordancewithdepartmentalprocedures.

I I

I l

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SECTION:

16.0 CORRECTIVE ACTION lPAGE 16-2 l

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1f, j

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J l

1 16.4 SIGNIFICANCCONDITIONS I-s 1

I l

l l

Significant conditions adverse to safety are to include, as a minimum, I

the following:

l l

l (1) Conditions that have a direct adverse effect on the safety of l

the plant per the plant Operating License and Technical l

l Specifications l

(2) Cond1'tions that have caused the uncontrolled release of l

I I

radioactive materials (liquid, solid, gaseous or air i

//

I 1

l particulate) to the environs l

(3) Adverse quality trends which could lead,to unsafe plant l

l operations i

l l

1 l

l l

i 16.5 REPORTABLE OCC(GRENCES I

l c

j i

.e l

l 16.5.1 l

l t

l l

l s

l Wnen significant conditions adverse to safety are discovered, the l

responsible supervisor and department head are to evaluate the condition l

{

and determine if it is a reportable occurrence.

l i

l I

I j

i 16.5.2 l

l a

I i

.t l

J,'h.

l l

Adverse conditions which are detusined to be reportable per the l

l Technical Specifications to the,1NCad to be documented by the l

j' initiator per plant, procedurbs, reviewed by the responsible supervisor l

f,andforwardedtotile-SpecialProjectsManagdrsotheappropriatereport I

.I.

I can be prepared.

^,

I l

,(

l I

l l

i l

I l

l l

8 1

/

l l

i I

l l

l Q

l 1

."~

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9 l

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'[

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(

'i '

'SECTION:

16.O CORRECTIVE l ACTION iPAGE 16-3 l

l l

L l

l l

1 I

I l

/

4

'h

l l

l 16.5.3 l

l l

l Upon disposition of the report by the responsible group, the PSC reviews l

the report for concurrence and possible assignment of additional l

l corrective actions and forwards the report to the Executive Director ANO l

Site Operations for final approval.

]

l l'

l 16.5.4 l'

I l

The LRGO Nuclear Engineering & Licensing section is to be responsible for l

transmitting approved reports to the NRC within the time period specified l

j lintheTechnicalSpecificationsandLicensingprocedures.

l l

16.6 VERIFICATION-I I

Verification by surveillance or audit of the effective implementation of l

corrective actions is to be periodically performed and documented by l

lQualityAssurancepersonnel.

Audits are to be performed in accordance l with Section 18 of this manual.

l I

I L

I l

1 I

I I

I l

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l 1

SECTION:

16.0 CORRECTIVE ACTION lPAGE 16 l l

L l

l l

l 1

l l

l with Section 17 of this manual.

l l

l 18.6 NUCLEAR FUEL AUDITS I

l I

I l Arkansas Power & Light Company delegates to System Services Inc. (SSI)

I I

a wholly owned subsidiary of Middle South Utilities, Inc., the I

responsibility for performing those quality assurance functions necessary I

l to assure that its nuclear fuel is desigr.

and fabricated in accordance l with regulatory. requirements and accepted codes, standards and l

i l

specifications.

The SSI Quality Assurance section monitors the design I

and fabrication of the fuel through a program of audits of the fuel i

fabricator, including both design review audits and fuel fabrication l

l audits.

SSI also conducts audits of component suppliers as deemed l

lnecessarybytheManager,QualtiyAssurance(551),toensurethe-quality l

l of the fuel.

Formal audit reports are issued by SSI to document their l

audit activities and to identify nonconformances or other items requiring l

l action by the fuel fabricator.

Resolution of nonconformances or other l

items requiring action is verified by SSI and documented in follow-up l

I reports.

The AP&L Quality Assurance Superintendent is on distribution l

for all audit and follow-up reports.

These audit reports are to be l

l fowarded to the plant and stored in accordance with Section 17 of this l

l manual.

I I

i i

l l

I I

l l

1 1

I I

l l

l 1

l l

I I

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18.0 AUDITS lPAGE 18-6 l

l L

I l

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l FINANCIAL APO l

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I I

l l

G I

I I

I Q

l A

l QA MANUAL OPERATIONS lREV.

9 l

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l I

FIGURE 2:

AP&L CORPORATE SERVICES lPAGE F-2 l

1 L

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TABLE 3 l

1 I

l QUALITY PROGRAM POLICIES, PROCEDURES AND INSTRUCTION I

I MANUALS LIST l

1 I

I I

l 1.

Quality Assurance Manual Operations l

l l

)

1 I

l The Quality Assurance Manual Operations establishes the policies and 1

l guidelines of the AP&L quality assurance program for its operating l

l nuclear plant.

This program is to be followed by all organizations I

t involved in safety-related work applicable to the operating nuclear I

plant.

l l

l j

l 1

I l

I 2.

Generation, Transmission & Engineering Procedures Manual, I

l I

I I

I l

l Little Rock General Office (LRG0) employs a system r. procedures l

designated as Generation, Transmission & Engineering Procedures l

l (GT&E) in order to implement Program requirements for the control of l

I design, engineering, nuclear fuel, licensing,' training and l

procurement activities in support of the operating plant.

l i

O' l

l l

1 l

The GT&E's and revision thereto are prepared by LRGO personnel, l

l reviewed and approved by the Nuclear Quality General Manager, the l

l LRGO Procedures Task Force and the responsible department head.

l l

1 I

I l

3.

Nuclear Quality Administrative Procedures I

o l

l l

l 1

l The Nuclear Quality Organization employs a system of procedures l

l developed to assure proper implementation of this quality program, i

These procedures provide technical and administrative instructions I

I to the Nuclear Quality staff to aid in implementing their I

responsibilities within the quality program.

These procedures are l

l reviewed / approved by the applicable QA or QC Superintendent and the I

Nuclear Quality General Manager.

1 I

I l

l l

l 1

1

]L l

l 1

l l'

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QA MANUAL OPERATIONS lREV.

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l 1 SECTION:

TABLE 3 lPAGE T3-1 l

l L

I l

l l

l

1 I

l l

l 4.

Overall Plant Administrative' Procedures Manual l

l l

l 1

I (G) 1 The plant operation organization employs a system of procedures l

designated as Overall Plant Administrative Procedures.

These l

procedures implement Quality Assurance Program requirements and I

1 control on site activities.

Overall Plant Administrative Procedures I

and changes thereto are prepared by the plant staff, reviewed by the l

q Plant Safety Committee and approved by the Executive Director ANO Site l

Operations.

The procedures and revisions are also reviewed l

by the Quality Control' Superintendent to assure that Quality l

Assurance Program commitments are met.

l l

l 1

l 5.

Departmental Plant Administrative Procedures l

-l l

l l

I l

Each department (operations, maintenance, engineering and technical I

support, training, etc.) at the plant has developed procedures in I

support of the Overall Plant Administrative Procedures and this l

l Quality Assurance Program.

These procedures provide technical and l

l 1

I administrative instructions to the various departments to aid in l

implementing their responsibilities within the quality program.

l Each department head is responsible to perform a review of their l

I procedures to assure conformance with the Quality Assurance Program.

l l

These procedures are reviewed by the Plant Safety Committee and l

l approved by the Executive Director AND Site Operations.

Plant l

Modification Process procedures (6000.XX Series) which stipulate i

I activities for LRGO Generation Engineering are also reviewed and g

I approved by the Generation Engineering General Manager.

l I

I I

l l

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l l

I l

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i QA MANUAL OPERATIONS IREV.

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SECTION:

TABLE 3 lPAGE T3-2 l

l L

I l

l 1

I i

l

i I

l l

ATTACHMENT A l

l 10 CFR 71 Appendix H l

O l

l J

The following section of the mcst currently approved revision of the QA l

Manual Operations will be applied as stated below (Note specific l

lll paragraphs are to rev. 9 paragraph numbers which could change during l

l subsequent revisions).

l 1

l l

Section 1 - Applicable l

I l

I I

l Section 2 - Applicable l

I I

l l

l Section 3 - Not applicable..AP&L will use only licensed packaging l

l which has been designed under a QA program which has been l

submitted to the NRC for approval.

l l

I l

1 l

Section 4 - Applicable l

l 1

i l

I l

Section 5 - Applicable l.

I i

l l

I l

Section 6 - Applicable l

l l

l Section 7 - Applicable l

l l

l Section 8 - Generally applicable, except for paragraph 8.2.2 and 8,2.3.

l l

Due to size, uniqueness, low volume, and the method of-l supplier identification of each package, AP&L tagging of l

l each package is not necessary.

l 1

i I

Section 9 - Not applicable; we do not consider this subject as a i

"Special Process" in the context of 10 CFR 71, Appendix H l

Section 71.119 which is a restatement of 10 CFR 50, I

l Appendix B Criterion 9.

l 1

l l

1 l

l I

I l

1 I

I l

A l

QA MANUAL OPERATIONS lREV.

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1 SECTION:

APPENDIX A - QUALITY PROGRAM IPAGE AA-2 l

l L

1 TRANSPORT PACKAGES l

l-l I

I l

1 I

I I

I Section 10 - Applicable l

I 1

Section 11 - Not applicable; AP&L will not be testing the package in the context of 10 CFR 71, Appendix H, Section 71.123 which is a i

restatement of 10 CFR 50, Appendix B Criterion 11.

l l

l I

I l

Section 12 - Generally applicable except for paragraph 12.3.4.

This I

paragraph only applies to Health Physics measuring and l

l testing eauipment that is used to calibrate other devices l

]

(used as a standard).

Health Physics survey equipment are l

l response checked prior to each use.

l l

l

)

l I

1 1

Section 13 - Generally applicable except for paragraph 13.5.

AP&L does l

1 I

not " store" package, therefore the storage section does not I

apply.

I I

I l

i I

l Section 14 - Not applicable; see Section 11 comments above.

l l

1 l

Section 15 - Generally applicable, except for references to the various I

types of dispositions in paragraphs 15.2.3 to 15.2.5.

-l d

I l

Nonconforming material or equipment will be returned to the l

l vendor or will be replaced.

I I

l Section 16 - Applicable 1

l lSection17-Applicable l

I I

lSection18-Applicable l

I I

i l

l I

I I

I

^/'

I I

l l

l A

I QA MANUAL OPERATIONS IREV.

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APPENDIX A - QUALITY PROGRAM lPAGE AA-3.

l I

L I

TRANSPORT PACKAGES l

l l

l

l l

1.6 The above requirements are implemented by controlling l

I I

activities as described in this manual and appendix and by procedures referenced in this manual and appendix.

l l

l I

l l

l2.0 ORGANIZATION l

l 1

2.1 The organizational structure and responsibilities of key l

personnel associated with the administration, implementation l

l and evaluation of the fire protection program are described in l

l l

Section 1.0 of this manual and as follows:

l l

l I

I

{

l 1.

The Nuclear Operations Vice President is the offsite l

I l

managemenc position which has the responsibility for the j

l l

development, implementation, ani assessment of the l

l effectiveness of the fire protection program.

He reports l

directly to the Generation, Transmission, Engineering l

l l

Senior Vice President.

l 1

i l

2.

Reporting to the Nuclear Operations Vice President is the l

l Nuclear Services General Manager.

Under his direction is l

the Nuclear Programs Manager, who has responsibility for l

I l

development and implementation of the fire protection I

program.

Under his direction is the Nuclear Operations l

l l

Fire Protection Specialist whose responsibilities include:

l providing guidance and technical support to the nuclear l

plant in the area of fire protection; assuring that l

l applicable regulatory requirements are included in the i

fire protection program, AP&L commitments regarding fire l

protection are identified and tracked; safety evaluations l

l (10 CFR 50.59) and design reviews for fire protection l

l modifications are performed and evaluations / assessments of I

the fire protection program are performed and reported to l

AP&L Management.

The Nuclear Operations Fire Protection l

l Specialist also has responsibility for maintenance and l

l revision of the Fire Protection Program Manual.

1 I

I I

I

'O I

I I

I V

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l QA MANUAL OPERATIONS lREV.

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APPENDIX B - QUALITY PROGRAM IPAGE AB-3 l

l L

l FOR FIRE PROTECTION l

l l

l

l l

l 3.

The Executive Director AND Site Operations is the l

I I

on-site manager responsible for the overall administration and implementation of plant operations in accordance with I

the fire protection program.

He reports directly to the

]

l Nuclear Operations Vice President.

I I

l l

4.

The plant Engineering Manager is responsible for the l

l establishment and monitoring of fire prevention aspects of l

the program at the plant including control of l

l l

combustibles, ignition sources, and postings.

He is also l

responsible for the fire protection aspects of the program l

l at the plant, such as evaluation of fire detection and I

suppression equipment, fire barriers, and alternate

[

shutdown equipment protection.

He reports directly to the l

l General Manager Plant Support.

Reporting to the plant l

l Engineering Manager is the Engineering Services l

l Supervisor.

Under his direction are the plant Safety and l

)

Fire Prevention Coordinators and the plant Fire Protection I

eg i

Specialist.

The Safety and Fire Prevention Coordinators l

l are responsible for implementing, maintaining and l

assessing th,e fire prevention aspects of the program as l

defined in plant procedures.

The plant Fire Protection l

l Specialist is responsible for providing support and l

technical assistance to Engineering design and review I

activities, performing fire protection evaluations, I

developing inspection and surveillance criteria, and l

coordinating ANI Fire protection inspections at the plant.

l The plant Fire Protection Specialist also monitors the i

fire protection program at the plant and provides input l

I for maintenance of the Fire Protection Program Manual.

I I

l l

\\

l l

I I

I l

1 l

l

(

l l

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l QA MANUAL OPERATIONS lREV.

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l 1 SECTION:

APPENDIX B - QUALITY PROGRAM lPAGE AB-4 l

l L

l FOR FIRE PROTECTION l

l l

l

I I

l 1

l 5.

The Nuclear Quality General Manager is responsible for i

l assuring that the fire protection program is implemented l

g l

in accordance with the QA Manual Operations, plant I

Technical Specifications, and applicable procedures.

This I

is accomplished by the performance of audits and other 1

provisions of the QA Manual Operations.

He shall assure i

that corrective action, when necessary, is taken.

He i

reports directly to the Nuclear Operations Vice President.

l l

l 6.

The Nuclear Engineering & Licensing Manager is responsible l

l for providing other responsible organizations with l

l regulatory information and interpretations on regulatory l

l issues related to fire protection.

He is also responsible I

for providing interface with the NRC on fire protection l

matters, Engineering evaluations and analysis of fire l

protection systems, as related to regulatory commitments l

l and control of license-based documents relating to fire I

protection.

He reports directly to the Nuclear Services l

i General Manager.

l l

t l

I l

I I

l 7.

The Generation Engineering General Manager is responsible l

I, for assuring that the technical requirements specified in i

the plant Operating License, Technical Specifications, and I

other design basis documents, with respect to fire I

protection, have been satisfied in design modifications.

l l

and design documents affecting the nuclear plant.

He I

reports directly to the Engineering Vice President.

I I

I l

3. 0 QUALITY ASSURANCE PROGRAM l

l l

i I

l 3.1 This quality program is to ensure that the fire protection I

systems for safety-related areas (as defined in paragraph 1.2 l

l of this Appendix) are controlled in accordance with applicable l

NRC regulations, industrial standards and codes and AP&L I

I I

I O/

I I

l A

l QA MANUAL OPERATIONS lREV.

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APPENDIX B - QUALITY PROGRAM lPAGE AB-5 l

l L

l FOR FIRE PROTECTION l

l 1

l l

1 a

l I

I I

I l

l policies, rules, procedures and licensing documents.

The l

quality program is implemented through appropriate LRGO and

(/

l plant procedures.

The effectiveness of the fire protection l

program is verified through surveillance and scheduled audits l

conducted by the QA organization, under the cognizance of the l

j I

SRC.

General requirements for this program are also described I

l l

l in subsections 2.4 through 2.7 of this manual, except that l

personnel performing inspections need not be certified to ANSI l

N45.2.6, when inspections are performed on equipment not listed j

I I

on the Q-list.

i l

l I

I 3.2 Employees whose duties and responsibilities are related to this l

fire protection program at or in support of the nuclear plant l

j are to participate in appropriate training programs to assure l

that suitable proficiency is achieved and maintained in the' l

I l

I work they are performing.

l l

1 I

I l

l 3.3 Fire protection training for plant personnel is included as I

l l

1 I

)

l l

part of industrial safety in the General Employee Training l

j

(

I Program.

Personnel are periodically retrained in industrial I

l I

l l

safety in accordance with plant procedures.

Personnel assigned l

I to the plant Fire Brigade are to receive additional I

I i

l indoctrination and training to assure their capability to fight l

l I

fires is established and maintained.

The Safety and Fire I

l I

l l

l Prevention Coordinators have the overall responsibility for l

these training programs.

.j l

l l

4.0 DESIGN CONTROL I

I I

l i

I I

4.1 Section 3.0 of this manual is applicav'e for design control l

l l

l activities pertaining to the fire protectica system.

l l

1 l

l l

1 I

l l

l i

O)

I I

I l

l

(,

l A

l QA MANUAL OPERATIONS lREV.

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l lDATE 7/22/8/

I l

I SECTION:

APPENDIX B - QUALITY PROGRAM IPAGE AB-6 l

l L

i FOR FIRE PROTECTION l

l l

l

I I

l 5.0 PROCUREMENT DOCUMENT CONTROL l

l l

5.1 The control of procurement documents for fire protection l

related materials, parts and components is described in Section l

4.0 of this manual with the exception of paragraph 4.2.3, when I

j l-these items are not associated with the Q-list.

The l

procurement document is to include the requirement that items l

l be U.L. listed or F.M. approved for fire protection use, where l

)

l applicable, in accordance with LRGO and plant procedures.

I 1

l l

)

l l

l 6.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS l

l 1

1 I

l 6.1 Inspections, tests, administrative controls, fire drills and l

training that govern the fire protection program are prescribed I

by documented instructions, procedures and drawings and are l

)

accomplished in accordance with these documents.

A listing and l

brief description of procedures relating to fire protection l

l activities is provided in the AP&L Fire Protection Program l

Manual.

Instructions, procedures and drawings are prepared, l

Ox reviewed, approved and revised in accordance with applicable l

l LRGO and plant procedures.

l l

I I

I l

7.0 DOCUMENT CONTROL l

l I

l l

l 7.1 Section 6.0 of this manual is applicable for the control of l

quality program documents related to fire protection.

I l

8.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES l

l l

The control of purchased fire protection related materials, l

l equipment and services is described in Section 7.0 of this manual, l

l with the following exception related to subsections 7.2, 7.3 and I

l 7.5.

For the procurement of fire protection related items or l

l services not associated with the Q-list, the vendor / contractor l

l l

O I

I l

l

' h l

A I

QA MANUAL OPERATIONS lREV.

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l l SECTION:

APPENDIX B - QUALITY PROGRAM lPAGE AB-7 l

l L

1 FOR FIRE PROTECTION l

l l

l

l l

l I

l qualification criteria (including periodic reassessment of their I

I program), is not required.

Nonconformances dispositioned repair or l

use-as-is by the vendor are to be submitted to and accepted by AP&L l

only when so designated on the procurement document.

I l

l l8.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES l

l l

The control of purchased fire protection related materials, I

equipment and services is described in Section 7.0 of this manual, l

with the following exception related to subsections 7.2, 7.3 and l

7.5.

For the procurement of fire protection related items or l

l services not associated with the Q-list, the vendor / contractor i

l qualification criteria (including periodic reassessment of their l

program), is not required.

Nonconformances dispositioned repair or l

)

l use-as-is by the vendor are to be submitted to and accepted by AP&L l

l only when so designated on the procurement document.

l l

9.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS l

l l

9.1 Section 8.0 of this manual is not applicable for the identification and control of materials, parts and components l

)

l related to the fire protection system.

No particular I

requirements for this Section have been identified in BTP-APCSB l

l 9.5-1, Rev. 2.

The identification and control of materials, I

parts and components are conducted in accordance with existing l

l procurement and materials management procedures and practices.

l l

l 1

I l

10.0 CONTROL OF SPECIAL PROCESSES

(

l l

10.1 Section 9.0 of this manual is not applicable for the control of l

special processes, as applicable to fire protection systems.

I No particular special process controls have been identified by l

BTP-APCSB 9.5-1 Rev. 2.

The control of special processes for l

the maintenance of the fire protection system are performed in l

l accordance with applicable plant procedures and practices.

l I

I l

l l

A l

QA MANUAL OPERATIONS lREV.

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l P

l lDATE 7/22/87 l

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APPENDIX B - QUALITY PROGRAM lPAGE AB-8 l

l L

I FOR FIRE PROTECTION l

l l

l

I I

i 11.0 INSPECTION l

l I

h l

l V

l 11.1 Inspection activities applicable to the fire protection system i

are described in Section 10.0 of this manual with the exception l

l of paragraphs 10.2.2 and 10.3.2.3, when inspections are l

' he l

l performed on equipment not associated with the Q-list.

T I

4 I

Regulatory Guides referenced in paragraph 10.2.2 are not l

l applicable to the fire protection system.

Individuals outside l

the QA and QC organizations who perform inspections only need l

to meet paragraphs 10.3.2 and 10.3.2.1.

l l

l 1

l In addition to the provisions of this manual, inspections and I

surveillance are provided for in applicable portions of the l

)

Fire Protection Program Manual and the Technical Specifications l

l for each nuclear unit.

l l

l 1

i l

l l

l 12.0 TEST CONTROL l

l 1

I l

l l

I 12.1 A test program is to be established and implemented to ensure l

f3 l

that testing is performed and verified on applicable systems l

l and components to demonstrate'conformance with design and l

l I

system readiness requirements.

The tests are to be performed g

l in accordance with written test procedures and test results l

l evaluated for conformance to the test objectives.

l l

l 12.2 The control of testing activities is described in Section 11.0 l

l 1

of this manual.

Surveillance testing requirements are l

l l

identified in the Technical Specifications for each nuclear i

unit.

l I

l 1

l l

l 13.0 CONTROL OF MEASURING AND TEST EQUIPMENT l

1 l

I l

l 13.1 Section 12.0 of this manual is not applicable for the control l

of measuring and test equipment.

No particular measuring and l

l 1

l l

A l

QA MANUAL OPERATIONS REV.

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APPENDIX B - QUALITY PROGRAM lPAGE AB-9 l

l L

l FOR FIRE PROTECTION l

l l

l I

I

I l

l l

l test equipment controls have been identified in BTP-APCSB9.5-1, l

I I

Rev. 2.

Measuring and test equipment is controlled in accordance with applicable plant procedures and practices, i

l l

14.0 HANDLING STORAGE AND SHIPPING l

l l

1 I

I l

14.1 Section 13.0 of this manual is not applicable for the handling, I

)

storage and shipping of fire protection related materials and l

l equipment.

No particular requirements for this Section have i

been identified in BTP-APCSB 9.5-1, Rev. 2.

Handling, storage I

and shipping activities are controlled in accordance with l

. applicable plant procedures and practices.

I I

i l

15.0 INSPECTION TEST AND OPERATING STATUS l

l l

15.1 Measures are established to provide for the identification of l

I items that have satisfactorily passed required inspections and l

tests and are documented per approved instructions or procedures.

l

\\

l l

1 15.2 Section 14.0 of this manual is applicable for identifying the l

inspection, test and operating status of the fire protection I

system.

1 I

I l

1 l

16.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS l

l I

I I

l 16.1 The control of nonconforming materials, parts and components l

related to the fire protection system is described in Section 1

l 15.0 of this manual, with the exception of paragraph 15.3, when I

l the item is not associated with the Q-list.

Vendor l

nonconformances are to be submitted to AP&L only when so l

designated on the procurement document.

l l

1 l

l 1

I l

1 A

l QA MANUAL OPERATIONS lREV.

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APPENDIX B - QUALITY PROGRAM lPAGE AB-10 l

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l FOR FIRE PROTECTION l

l l

I I

l

l l

l 17.0 CORRECTIVE ACTIONS l

l l

17.1 A corrective action system is to be established to ensure that conditions adverse to fire protection, such as failures, g

i malfunctions, deficiencies, deviations, defective components, I

l uncontrolled combustible materials and nonconformances, are l

l promptly identified, reported and corrected.

I I

I l

17.2 Correctiva action activities are controlled as described in l

l Section 16.0 of this manual, with the following exception l

I related to paragrapn 16.3.

Vendors furnishing fire protection l

l items not associated with the Q-list are not required to be l

j l

listed on the QVL.

I I

I l

l i

18.0 QUALITY ASSURANCE RECORDS 1

I I

I 1

l 18.1 Records which furnish evidence that the criteria enumerated in l

I this program are being met for activities affecting the fire i

protection program are to be prepared and maintained as O

l I

i described in Section 17.0 of this manual.

A listing of I

documents and records (including calculations, test reports, I

I I

code reports and design change packages) relating to fire I

protection is included within the AP&L Fire Protection Program I

l Manual.

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l19.0 AUDITS I

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19.1 Audits are to be conducted and documented to verify compliance I

with the fire protection program, including design and i

procurement documents, instructions, procedures and drawings l

I and inspection and test activities.

Section 18.0 of this I

I manual is applicable for the control of audits related to the j

I fire protection program.

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19,2 As a minimum, audits of the fire protection program are to be I

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scheduled at specified frequencies in accordance with the Technical Specifications applicable to each nuclear unit.

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l QA MANUAL OPERATIONS lREV.

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IDATE 7/22/87 l

l 1 SECTION:

APPENDIX B - QUALITY PROGRAM lPAGE AB I l

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FOR FIRE PROTECTION I

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