ML20094C430
| ML20094C430 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/30/1984 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20094C423 | List: |
| References | |
| PROC-840530, NUDOCS 8408070485 | |
| Download: ML20094C430 (158) | |
Text
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Copy No.-
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QUALITY ASSURANCE MANUAL O
OPERATIONS J
SRKANSAS 3
POWER LIG H T HELPING BUILO ARKANSAS t i. u lO aar ?8 P a 8?sia P
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UNITED STATES y'
NUCLEAR REGULATORY COMMISSION
~h REGION IV
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$11 RYAN PLAZA DRIVE, SUITE 1000 M
ARLINGTON, TEXAS 79011 E 3 0 IB4 Dockets: 50-313 50-368 l'
Arkansas Power & Light Company ATTN: John M. Griffin, Senior Vice President - Energy Supply P.O. Box 551 Little Rock, Arkansas 72203
-Gentlemen:
By letter dated May 4,1984 (John R. Marshall to Richard P. Denise, "AP&L Quality Assurance Manual - Operations"), Arkansas Power and Light Company submitted Revision 6 to the Quality Assurance Manual which incorporated comments made by the NRC staff.
We have reviewed this submittal and find that it satisfies the requirements of q
10 CFR Part 50, Appendix B, and is therefore acceptable.
If you have any questions concerning the above, please contact this office.
Sincerely, W/
mf E. H. J nson, Acting Chief Reactor Project Branch 2 cc:
J. M. Levine, General Manager Arkansas Nuclear One P.O. Box 608 Russellville, Arkansas 72801 m
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RECORD OF REVISIONS l
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0 Initial Issue 6/11/74 l
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Response to AEC Questions Submitted 12/13/74 l
l 11/21/74.
Revisions to Section 2, l
l 4, and 7 as indicated.
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2 Response to NRC Questions Submitted 3/4/75 l
l 2/7/75.
Procedure Numbers 1005.xx l
l changes to 1004.xx (Number Change Only).
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3 General revision to change AEC to NRC, 9/8/76 l
l update organization, reflect NSP l
'l revisions, minor program implementation l
l changes.
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4 Eliminate Quality Assurance Committee 9/8/77 l
l Changes to Procurement Control -
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Qualification of Vendors.
Organizational l
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Changes.
Incorporate Technical l
l Specification Changes.
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5 Incorporate Organizational Changes 10/10/80 l
l and responses to subsequent NRC l
l Questions.
Incorporate Regulatory l
l Guidas and retype document in its l
l entirety in standardized format.
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6 Incorporate organizational changes, 5/30/84 l
l delete procedural references l
l throughout manual, and accurately l
l reflect current regulatory commitments l
l and QA practices related to the j
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. safe operation of AP&L nuclear plants.
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Manual has been reformated and retyped l
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TABLE OF CONTENTS TC-1 6
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-- l POLICY STATEMENT A-1 6
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l INTRODUCTION B-1 6
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5 AP&L Nuclear Plant 19 F-5 6
l Organization
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~ ARKANSAS POWER & LIGHT COMPANY POLICY STATEMENT l
. QUALITY. ASSURANCE PROGRAM FOR OPERATION
~
. It is the policy of the Arkansas Power & Light Company (AP&L), from the l
l~ highest level-of corporate management, that its Quality Assurance Program l
. 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 of AP&L Nuclear l
j' Plants.
The: program shall also meet the requirements of the ASME Boiler l
'and Pressure. Vessel Codes with respect to items constructed, repaired or
-l~ replaced tolCode requirements.
1 I
I 1
l l Under the Program the Energy. Supply Sr.- Vice President, is the final l
. management authority responsible for assuring that this policy statement l and the Quality Assurance Program are implemented within AP&L.
The l
Nuclear Operations Vice President and each Energy Supply Director is l
l responsible for the. procedural implementation of the program within his l
' assigned area.
The plant's General Manager is responsible for the daily
.O
~l -implementation of the Program's procedural requirements at the plant.
l 1
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l The Quality Assurance Manager.is responsible for establishing the l
{
Program.
The Quality Assurance Manager, Energy Supply Services Director l
-l. and the Energy Supply Sr. Vice President are responsible for approval of l
I.the Program.
I
.l-l Quality Assurance personnel reporting to the Quality Assurance Manager l are responsible for auditing the Program as necessary and monitoring l
activities ~ required by the Program to assure compliance with its l requirements.
Disputes involving quality, arising from difference of l
opinions between QA personnel and other personnel, which cannot be l-settled interdepartmentally, shall be presented to the Energy Supply l
Senior Vice President for resolution.
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STATEMENT OF POLICY lPAGE A-1 l
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l l The Quality Assurance Manager is to provide for annual review of the I
. adequacy and overall effectiveness of the Program.
Any defects in the I
implementation of either this policy or the Program that are revealed l
I during the review are to be reported to appropriate levels of management l
together with appropriate recommendations.
l l
1 I
l
.l Implementation of this policy is necessary in order to achieve the l
l l
reliability and safety required at our Nuclear Plants.
Each person I
I l
involved in activities concerning our Nuclear Plants is to be responsible l
for assuring quality in his own work, and for compliance with the l
requirements of the Program.
The Quality Assurance Program policies, l
manuals, and procedures are mandatory requirements which must be l
implemented and enforced by all responsible organizations and l
l individuals.
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I r,(/, / )Y )?? (pl,/1 1
J. Griffin
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Energy Supply Sr. Vice President I
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6 S /-81 l
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STATEMENT OF POLICY IPAGE A-2 l
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6 I
INTRODUCTION l
'O I
l I This TOPICAL report (manual) describes the AP&L quality program applied l
lbyAP&Ltoitsoperatingnuclearplants.
This manual is intended to l serve as a standard reference for final safety analysis reports to l
l fulfill the requirements of the Standard Format and Contents of Safety l
I Analysis Reports for Nuclear Power Plants Section 17, published by the l
lNuclearRegulatoryCommission.
i l-l The' objective of this program is to control those phases, as applicable, l
for the design, procurement, manufacture and fabrication, installation, l
operation, testing, refueling, repair, maintenance or modification to I
existing safety related (Q-List) structures, systems and components that l
prevent or mitigate the consequences of a postulated accident which may I
cause undue risk to the health and safety of the public.
The program is l
an outgrowth of the principle that quality assurance emanates from each I
individual contributor and that management is responsible for creating an l
lawarenessof' quality.
O g
The AP&L quality program is designed to comply with the requirements of I
10CFR50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants l
_landFuelReprocessingPlants,andtocomplywiththequalityassurance l
l requirements of the ASME Boiler and Pressure Vessel Code,Section XI for l
l repair, replacement,andinserviceinspectionofitemscoveredbythe I
Code and Licensing commitments.
l 1
I l-1 l
l l
The AP&L quality program is also designed to comply with the NRC l
positions contained in the following regulatory guides, subject to I
specific exceptions noted in Table 1 of this manual:
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1 SECTION:
INTRODUCTION lPAGE B-1 l
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l 1.8, rev. 1-R Personnel Selection and Training (5/77) l 1.28, rev. 1 QA Program Requirements-Design and l
Construction (3/78) l l
1.30 QA Requirements for Installation, l
Inspection and Testing of Instrumentation l
I g
and Electrical Equipment (8/72) l 1.33, rev. 2 QA Program Requirements-Operations (2/78) l 1.37 QA Requirements For Cleaning of Fluid l
Systems and Associated Components of Water l
Cooled Nuclear Power Plants (3/73) l l
1.38, rev. 2 QA Requirements for Packaging, Shipping, l
Receiving, Storage and Handling of Items l
l For Water Cooled Nuclear Power Plants l
(5/77) l 1.39, rev._2 Housekeeping Requirements For Water Cooled l
Nuclear Power Plants (9/77)
-l 1.58, rev. 1 Qualification of Nuclear Power Plant l
l' Inspection, Examination and Testing l
l
\\g Personnel (9/80) l J'
1.64, rev. 2 QA Requirements For the Design of Nuclear l
l Power Plants (6/76) l 1.74 QA Terms and Definitions (2/74) l
- l 1.88, rev. 2 Collection, Storage, and Maintenance of l
Nuclear Power Plant Quality Assurance l
l Records (10/76) l 1.94, rev. 1 QA Requirements for Installation, l
Inspection and Testing of Structured l
Concrete and Structural Steel During the I
l Construction Phase of Nuclear Power Piints l
(4/76)
I l
1.116, rev. 0-R QA Requirements For Installation, l
Inspection and Testing of Mechanical l
l Equipment and Services (5/77) l 1
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INTRODUCTION lPAGE B-2 l
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l 1.123, rev. 1 QA Requirements For Control of Procurement l
[[
-l of Items and Services For Nuclear Power
'l' Plants (7/77) l l
1.144, rev. 1 Auditing of Quality Assurance Programs for l
the Nuclear Power Plant (9/80) 1
-1.146~
Qualification of Quality Assurance Program l
l Audit Personnel For Nuclear Power Plants l
(8/80) l 1
I g
Based upon compliance to these regulatory guides, the AP&L quality I
I lprogramalsocomplieswiththefollowingAmericanNationalStanda l
Institute (ANSI) standards subject to exceptions noted in Table 1 of this 1 manual:
I l
l l
l l'
N45.2-1977 Quality Assurance Program Requirements for Ncclear l
l Facilities l
l lN45.2.1-1973 Cleaning of Fluid Systems and Associated I
l Components During the Construction Phase of I
l Nuclear Power Plants l'
l lN45.2.2-1972 Packaging, Shipping, Receiving, Storage and
,l Handling of Items for Nuclear Power Plants (During I
the Construction Phase) l I
lN45.2.3-1973 Housekeeping During the Construction Phase of l
Nuclear Power Plants l
1 1
I I
I N45.2.4-1972 Supplementary Quality Assurance Requirements for l
l Installation, Inspection and Testing of l
'l Instrumentation and Electric Equipment During the l
Construction of Nuclear Power Generating Stations l
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INTRODUCTION lPAGE B-3 l
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I N45.2.5-1974 Supplementary Quality Assurance Requirements for l
p l
Installation and Testing of Structural Concrete
?'
l and Structural Steel During the Construction Phase l
of Nuclear Power Plants I
I I
lN45.2.6-1978 Qualifications of Inspection, Examination and l
Testing Personnel for Nuclear Power Plants l
1 I
I I
l N45.2.8-1975' Supplementary Quality Assurance Requirements for l
l Installation, Inspection and Testing of Mechanical l
l Equipment and System for the Construction Phase of l
Nuclear Power P1, ants l
l N45.2.9-1974 Requirements for Collection, Storage and l
l Maintenance of Quality Assurance Records for l
Nuclear Power Plants l
l N45.2.10-1973 Quality Assurance Terms and Definitions I
I r3 Cl N45.2.11-1974 Quality Assurance Requirements for the Design of l
l Nuclear Power Plants l
l l
l l
l N45.2.12-1977 Requirements for Auditing of Quality Assurance l
l Programs for Nuclear Power Plants I
l
~
N45.2.13-1976 Quality Assurance Requirements for Control of l
l Procurement of Items and Services for Nuclear l
,I Power Plants I
l N45.2.23-1978 Qualificatfor of Quality Assurance Program Audit l
Personncl for Nuclear Facilities i
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l N18.1-1971 Selections and Training of Nuclear Power Plant l
Personnel l
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INTRODUCTION lPAGE B-4 l
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o l-1 I
I l N18.7-1976 Administrative Controls and Quality Assurance for i
.(y the Operational Phase of Nuclear Power Plants I
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The above requirements are implemented by controlling activities as l
[ described in this manual and by procedures referenced in this manual.
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l l Definitions of terms applicable to the AP&L quality program are found in I
.ltheTermsandDefinitionssectionofthismanual.
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l TERMS AND DEFINITIONS l
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I l The terms used in this manual follow the definitions provided in l
ANSI N45.2.10-1973, supplemented by additional terms and definitions l applicable to this report.
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I l Approval - An act of endorsing or adding positive authorization, or both.
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l -Appurtenance - A part that is attached to a component which has been l
completed.
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As-Built Data - Documented data that describes the condition actually l achieved in a product.
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1 l Assembly - A combination of subassemblies or components, or both, fitted l
together to form a unit.
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Audit - An activity to determine through investigation, the adequacy of l
_,q l and adherence to, established procedures, instructions, specifications, l
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codes, and standards or other applicable contractual and licensing l requirements, and the effectiveness of implementation.
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I l Bid Evaluation - A formal evaluation of all proposals received in l
I response to an inquiry to determine the vendor to whom the purchase order l will be awarded.
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l l Certificate of Conformance - A written statement, signed by a qualified l
party, certifying that items or services comply with specific l
l requirements.
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Certificate of Compliance - A written statement, signed by a qua~iffied l
party, attesting that the items or services are in accordance with l
specified requirements and accompanied by additional information to l
I substantiate the statement.
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_l-Certified Test Report - A written and signed document, approved by a l
p lqualifiedparty,thatcontainssufficientdataandinformationtoverify
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-l l_the actual properties of items and the actual results of all required l
tests.
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I I Certification - The action of determining, verifying and attesting, in I
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l-writing, to the qualifications of personnel or material.
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l l. Characteristic - Any property or attribute of an item, process, or l
- service that is distinct, describable, and measurable, as conforming or l
l nonconforming to specified quality requirements.
Quality characteristics l
laregenerallyidentifiedinspecificationsanddrawingswhichdescribe l
l the. item, p ocess, or service.
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I l Checks - The tests, measurements, verifcations or controls placed on an I
activity by means of investigations, comparisons, or examinations, to l
.l - determine satisfactory conditions, accuracy, safety 'or perfo.mance.
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Cleanness - A state of being clean in accordance with predetermined l
standards, and usually implies freedom from dirt, scale, heavy rust,.il l
1 or other contaminating impurities.
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' l Code Inspector - A qualified nuclear inspector (ANI or ANII) employed by I
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a legally constituted agency of a Municipality or State of the United l
l States, or Canadian Province, or regularly employed by an Authorized l
Inspection Agency and having authorized jurisdiction at the site of l msnufacture for installation, repair, modification, and in-service l
linspectionofASMEBoilerandPresssureVesselitemsdesignated l
safety-related.
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I l Commercial Grade - Those items contained in Q systems and equipment that l
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L (1) not subject to design or specification requirements unique to are:
I nuclear facilities or activities; (2) used in application other than l
lnuclearfacilitiesoractivities;(3)tobeorderedonthebasisof I specifications set forth in manufacturer's published product description; I
!g and (4) not associated with a loss of safety function.
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' Component - A piece of equipment such as a vessel, piping, pump, valve or I core support structure, which will be combined with other components to l
form an assembly.
l l
'lComputerCode-Theapplicationsoftwareutilizedwithinadigital l computer to accomplish a specific function or task.
Computer codes I
requiring Quality Assurance are those whose satisfactory performance is l
l required to prevent accidents which may cause undue risk to the health I
and safety of the public or relied upon to mitigate the consequences of l
l such accidents if they were to occur.
This involves those computer codes I
utilized in design and analyses of Q-list components, and those utilized I as an active portion of Q-list components.
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l Contaminants - Foreign materials such as mill scale, dirt, oil, chemicals l
and any matter than renders a fluid, solid or surface impure and unclean l
l according to preset standards of acceptable cleanness.
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I l Contractor - Any organization under contract for furnishing items or l
services.
It includes the terms Vendor, Supplier, Subcontractor, l Fabricator and sub-tier levels of these where appropriate.
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l l Defective Material - A material or component which has one or more l
characteristics that do not comply with specified requirements.
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1 Deviation '- A nonconformance or departure of a characteristic from l
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.g specified requirements.
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l:. Documentation - My written or pictorial information describing, l
I defining, specifying, reporting or certifying activities, requirements, l
l'. procedures,orresults.
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- l. Examination-Anelementofinspectionconsistingofinvestigationof l materials, components, supplies or services to determine conformance to I
_ those specified requirements which can be determined by such l
l investigation.
Examination is usually nondestructive and includes simple l
physical manipulation, gaging, and measurement.
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, Handling - An act of physically moving items by hand or mechanical means, l
l but not including transport modes.
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Inquiry - A document that contcins the necessary information for a vendor 1
to make a proposal. An inquiry may include specifications pertaining to l
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the equipment, materials, or services proposed to be procured.
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I Inspector (Owner's) - A qualified inspector employed by the Owner whose l
ldutiesincludetheverificationofquality-relatedactivitiesor l
l installations or both.
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l Inspection - A phase of quality control which by means of examination, l
lobservationormeasurementdeterminestheconformanceofmaterials, l
l supplies, components, parts, appurtenances, systems, processes or I
structures to predetermined quality requirements.
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l Item-Anylevelofunitassembly,includingstructure, system, l
l subsystem, subassembly, component, part or material.
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l l Job Order (J.0.) - The Job Order is the document used for identifying and l
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administrative 1y controlling the work effort on station equipment and V
l systems.
It identifies applicable procedures and drawings; documents l
reviews, approvals and results of inspections and tests; and provides a
[ mechanism for planning, scheduling and authorizing work.
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l l Manufacturer - One who constructs any class of component, part, or l
appurtenance to meet prescribed design requirements.
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Material - A substance or combination of substances forming components, l parts, pieces and equipment items.
(Intended to include such as l
l machinery, castings, liquids,formedsteelshapes, aggregates,and l cement.)
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l l Modification - A planned change in plant design or operation and l
accomplished in accordance with the requirements and limitations of l applicable codes, standards, specifications, licenses and predetermined l
l safety restrictions.
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Nonconformance - A deficiency in characteristic, document, or procedure l
l which renders the quality of an item unacceptable or indeterminate.
l l Examples'ofnonconformanceinclude: physical defects, test failures, l
incorrect or inadequate documentation, or deviation from prescribed l
processing, inspection or test procedures.
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Objective Evidence - Any statement of fact, information, or record, l either quantitative or qualitative, pertaining to the quality of an item l
or' service based on observations, measurements, or tests which can be l verified.
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l l Operation - The total of administrative, maintenance and monitor l
activities necessary to sustain the power generating capabilities of the l plant af ter initial start-up.
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l Owner - The person, group, company or corporation who will have or has I
ltitletothefacilityorinstallationunderconstruction.
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l Package - A wrapping or container including its contents of materials or l
l equipment.
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Packaged Unit - An assembly of items and parts which can be disassembled l
lwithoutdestroyingtheintegrityoftheindividualparts.
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l Part - An item which has work performed on it and which is attached to l
l and becomes part of a component before completion of the component.
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Plant - The equiment, piping, structures, buildings and property that I
comprise an installation or facility.
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l Procedure-Adocumentthatspecifiesordescribeshowanactivityisto l
l be performed.
It may include methods to be employed, equipment or l
lmaterialstobeusedandsequenceofoperations.
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lProcurementDocuments-Contractuallybindingdocumentsthatidentifyand i define the requirements that items or services must meet in order to be l
considered acceptable by the purchaser.
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l Project - A planned series of activities including all actions necessary l
l to provide, utilize, and maintain a facility or portion thereof.
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Proposal - A bid, usually written by a vendor in response to an inquiry, l
which provides the issuing party with the vendor's proposed compliance to l
l the inquiry and the cost.
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Purchase Order (or Contract) - A document authorizing a vendor to provide i
equipment, material or services in accordance with stated terms and l
l conditions.
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l Purchaser -. The organization or organizations responsible for issuance l
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l and administration of a contract, subcontract, or purchase order.
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g Q-List - A list which wecifically identif ies those st ructures, systems l and components whose tailure could cause an uncontrolled release of l
radioactivity, or those essential for the safe shutdown and immediate and I
I long-term operation following a Loss of Coolant Accident.
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-l Qualification (Personnel) - The characteristics or abilities gained l
,through training or experience or both that enable an individual to I
- 1. perform a required function.
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1 l -Qualified Party - A person or organization competent and recognized as l
knowlegeabl.e to perform certain functions.
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i Qualified Procedure - A procedure which incorporates all applicable codes I and standards, manufacturer's parameters, and engineering specifications i
and has been proven adequate for its intended purpose.
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Qualified Vendor List - A listing of vendors having quality assurance
,I l programs consistent with the requirements of applicable portions of I
l10CFR50, Appendix 8.
l-i Quality Assurance - All those planned and systematic actions necessary to l
l provide adequate confidence that an item or a facility will perform l
satisfactorily in service.
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1 Quality Control - Those quality assurance actions which provide a means I to control and measure the characteristics of an item, process, or I
lfacilitytoestablishedrequirements.
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Receivino - Taking delivery of an item at a designated location.
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l Repair - The process of restoring a nonconforming characteristic to a 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 I
original requirement.
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l Report-Something(document)thatgivesinformatiorforrecordpurposes.
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Review-Anelementofinspectiontodetermineconformancetospecified L
l requirements, which can be determined by examination of documents and l
l activities.
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Rework-Theprocessbywhichanonconformingitemismadetoconformto I
a prior specified requirement by completion, remachining, reassembling or l
lothercorrectivemeans.
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l Safety-Related - The term " safety-related", as used in this program, l
/3 l
refers to those materials, parts, components, systems, structures and i
U consumeable ite:ns classified as "Q" and so identified on the Q-list l
l applicable to each nuclear plant.
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Source Surveillance - A review, observation, or inspection for the I
purpose of verifying that an action has been accomplished as specified at l
l the location of material procurement or manufacture.
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Specification - A concise statement of a set of requirements to be I
satisfied by a product, material or process indicating, whenever I
appropriate, the procedure by means of which it may be determined whether I
the requirements given are satisfied.
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Standard - The result of a particular standardization effort approved by l
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a recognized authority.
Storage - The act of holding items at the construction site or in an area l
other than its permanent location in the plant.
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Subsystem - A group of assemblies or components or both combined to l
performed a single function.
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Surveillance - The continuing analysis and evaluation of records, methods l
and procedures, including the act of verification, to assure conformance l
with technical requirements.
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I System - A group of subsystems united by some interaction or l
interdependence, performing many duties but functioning as a single unit.
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System Performance Test - A test performed on a completed system l
lincludingelectric, instrumentation, controls,fluidandmechanical l
']
l subsystems under normal or simulated normal process conditions such as l
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temperature, flow, level, and pressure.
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Testina - The determination or verification of the capability of an item l
to meet specified requirements by subjecting the item to a set of l
physical, chemical, environmental or operating conditions.
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Titles - Titles of individuals, such as Quality Assurance Manager, when l
used in the TOPICAL report assigns the responsibility of performing the l
requirement to the noted individual or his appointed designee.
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' Transit - The state of being conveyed or transported from one place to l
another.
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.l Transit Carrier (0 pen) - Trucks, trailers, railroad cars, barges, 1
aircraft or ships which do not afford items protection from the l environment.
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l l Transit Carrier (Closed) - Trucks, trailers, railroad c.ars, barges, l
aircraft or ships which provide protection of items from the environment l by nature of their closed design.
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l l-l l Use-As-Is - A disposition which may be imposed for a nonconformance when l
I it can be established that the discrepancy will result in no adverse l conditions and that the item under consideration will continue to meet I
all engineering functional requirements including performance, l
l maintainability, fit and safety.
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l l Vendor - Any organization under contract for furnishing items or l
l services. It includes the terms Contractor, Subcontractor, Supplier, I
-l l'ebricator and sub-tier levels of these where appropriate.
l l
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i 7^'s l Verification - An act of confirming, substantiating and assuring that an I
activity or condition has been implemented in conformance with the l specified requirements.
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l l Work Instructions - Written instructions used to transmit detailed I
information on the specific measures necessary to comply with the l requirements of quality assurance procedures or any complex or difficult l
l quality-relatedtask.
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l Work Package - A work package is a collection of applicable documents, l such as procedures, cleanliness control forms, inspection and test forms, l
hold card forms, Ignition Source Permits, drawings, technical manuals, l
l etc., needed to perform the job.
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- 1. 0 ORGANIZATION I
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I This section describes the AP&L organizational structure and i
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g responsibilities for establishing and executing the Quality Assurance l
l Program for AP&L operational nuclear plants in compliance with 10CFR50, 1
Appendix B and applicable Regulatory Guides and ANSI Standards identified I
g l
in the Introduction.
It also includes a description of the interfaces l
lwithotherorganizationswhomaybedelegatedtheworkofestablishing f-'
I and executing portions of the Quality Assurance Program.
The AP&L l
Corporate Organization relevant to the operation of its nuclear plants is l
l shown in Figure 1.
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- 1. 2 GENERAL RESPONSIBILITIES l
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l The ultimate responsibilities for operational nuclear plants within AP&L, I
lincludingQualityAssurance,lieswiththeEnergySupplySeniorVice l
l-President.
He provides management assessment of the Quality Assurance l
Program through review of QA Audit Reports and reports of NRC activities.
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l lTheAdministrativeServicesVicePresidentisresponsibleforthe l
l purchasing functions affecting plant operation as described in Subsection l
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- 1. 3.
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- 1. 3 CORPORATE SERVICES l
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l Corporate Services is responsible for the procurement of materials, parts l
and components requested by Little Rock General Office (LRGO) personnel l
and for supporting the procurement activities at the plant.
Procurement l
_ organization is noted in Figure ?.
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i 1.3.2 l
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I lTheNuclearBuyerreportstotheSupervisorofPurchasingwhoreportsto l
the Manager, Purchasing and Stores and is responsible for the following l
I duties and activities:
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1.
Prepares purchase orders based upon receipt of reviewed and I
l approved Purchase Requisitions.
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Performs the commercial interface functions between AP&L and l
J contractors or vendors.
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3.
Assures that quality documentation prepared by Energy Supply l
l personnel are included in purchasing documents.
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1.4 ENERGY SUPPLY l
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l Energy Supply, headed by the Energy Supply Senior Vice President is l
l responsible for all activities related to the operation of AP&L Nuclear I
l l
l Plants.
These activities include as a minimum:
design, modification, l
maintenance, inservice inspection and test, operation and those l
additional activities discussed in Sections 2 through 18 of this manual.
l Within Energy Supply, the Nuclear Operations and Energy Supply Service l
l organizations are involved in activities requiring execution of the l
Quality Assurance Program (See Figure 3).
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1.4.1 Energy Supply Services I
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l Energy Supply Services is under the direction of the Energy Supply l
lServicesDirector,whoreportstotheEnergySupplySeniorVice l
l President.
The Energy Supply Services Director is responsible for l
l providing support to AP&L nuclear plants in the areas of quality I
assurance, administrative services, engineering services and technical I
services.
His duties include providing technical direction, l
l administrative guidance and supervision to the:
I l
I i
l l
a.
Energy Supply Administrative Services General Manager i
b.
' Engineering Services General Manager l
l c.
Technical Services General Manager l
.l d.
Quality Assurance Manager l
I 1
1.4.1.'1 Quality Assurance Manager l
l l
lTheAP&LQualityAssuranceOrganization(QAO)asshowninFigure4is l
I under the direction of the Quality Assurance Manager, who reports to the l
e l
g Energy Supply Services Director.
The QA0 performs review, surveillance, I
g l
inspection and audit functions during the operational phase of AP&L's l
l nuclear plants and is independent of Nuclear Operations, and from cost I
and scheduling considerations when opposed to safety and quality-l l
considerations.
The QA Manager shall have direct access to management l
l 1evels, which assures his ability to:
identify quality problems; I
l initiate,' recommend or provide solutions through designated channels; and l
l verify implementation of solutions.
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l l
The qualification requirements of the QA Manager are established within I
his APSL job descript' ion which includes the following prerequisites:
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1.
Possess a degree from an accredited school in engineering or a l
l related scientific discipline or equivalent; I
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2.
Possess a minimum of five years experience in the quality l
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assurance or quality control disciplines with atleast two years l
in the nuclear field; and l
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l 3.
Exhibit the ability to plan, schedule and direct the activities l
1 of others assigned to or functioning within the QAO.
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I The duties and responsibilities of the Quality Assurance Manager include l
l the following:
l 1
I l
l l
1.
Develop Quality Assurance Program requirements for l
modification, operation, and maintenance activites related to l
-l the safety related (Q-listed) systems, structures, and l
components in AP&L nuclear plants.
l l
l 2.
Audit of the quality assurance activities as described in l
l Section 18 of this manual.
l l
l
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l 3.
Review, approval and verification of the quality assurance l
I requirements placed upon contractors or vendors that provide l
equipment, material, or services for AP&L nuclear plants.
l l.
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-l 4.
Authority to stop work where conditions exist that prohibit l
effective quality control inspections, or if faulty materials, l
incorrect workmanship or procedures are detected.
l l
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S.
Review, approval, distribution and control of QA Manuals and QA l
Procedures and revisions thereto.
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l 6.
Review and approval of QA programs for outside organizations l
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-l participating in the AP&L QA program.
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l 7.
Serve as chairman of the Safety Review Committee.
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l 8.
Provide and maintain a qualified and suitable trained staff to I
carry out required sta; f f unctions.
I l
9.
Formulate progran.s for maintaining the professional competence l
of personnel within the QA0 and provide assistance in QA l
training and indoctrination programs for division management, i
engineering and plant personnel whose activities affect l
l quality.
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l 10.
Provide technical direction and guidance to the Quality l
Engineering Supervisors.
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1.4.1.1.1 Quality Engineering Supervisor l
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l The Quality Engineering Supervisor reports to the Quality Assurance Manager, supervises QA Engineers and Auditors / Inspectors as assigned, l
and assists the Quality Assurance Manager in the coordination of I
O activities within the QA Section.
The Quality Engineering Supervisor may l
l also perform duties normally assigned to Quality Assurance Engineers.
l l
l l
l l
1.4.1.1.2 Quality Assurance Engineers l
l l
l l
l The Quality Assurance Engineers (QAE's) report to a Quality Engineering l
Supervisor, as assigned.
The Quality Assurance Engineers are to be I
l familiar with the Quality Assurance Program and associated procedures, l
10CFR50 Appendix B, regulatory guides, codes, and standards that address l
quality assurance. They also possess the necessary functional l
independence and authority to:
identify quality problems, initiate, l
recommend or provide solutions through designated channels, and verify l
implementation of solutions.
Specitically:
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The QAE's are to have the authority to inspect, audit or review l
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practices, records, files, instructions, directions or l
documents concerned with all areas affecting quality.
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2.
The QAE's are to schedule and coordinate audits or surveillance l
l efforts in the areas assigned, document findings, and report i
results to the Quality Assurance Manager and the Manager of the I
l audited area.
l l
l1.4.1.1.3 Quality Assurance Auditors / Inspectors l
l lTheQualityAssuranceAuditors/InspectorsreporttotheQuality l
l Engineering Supervisor and assist him in the implementation of the l
lprogrambyperformingauditsandinspectionsasrequiredtoassureproper I
application of the Quality Assurance Program.
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1.4.1.2 Technical Services General Manager l
.I I
o l
l O
l The Technical Services General Manager reports to the Energy Supply l
l,ServicesDirectorandisresponsibleforprovidingsupporttoAP&L l
l nuclear plants in the areas of plant performance, maintenance and l
l l
availability, chemistry,environmentalmonitoring,metallurgyand l
His duties include the following:
I l
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1.
Provides technical direction and administrative guidance to:
I
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l a.
Plant Performance Evaluation Manager l
l l
b.
Plant Maintenance Manager l
c.
Availability Engineering Manager l
d.
Technical Analysis Manager l
l l
l 2.
Assure conformance to the Quality Assurance Program by l
l l
instituting the necessary quality-related procedures and I
l l
instructions within the Technical Services Department.
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l 3.
Provide for coordination of environmental surveillance programs l
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Direct development of programs aimed at maximizing efficiency l
and availability.
I I
S.
Provide for review and analysis of outage data and make I
I recommendations for correcting deficiencies which affect l
availability or performance.
I I
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6.
Direct the plant maintenance support activities that are
-l assigned to the LRGO.
l l
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7.
Serve as a member of the Safety Review Committee.
l 1
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8.
Provide and maintain a qualified and suitably trained staff to l-carry out required departmental functions.
l l
l 1.4.1.3 Engineering Services General Manager l
l l
]"
The Engineering Services General Manager reports to the Energy Supply l
Services Director and is responsible for LRGO design and engineering l
lactivitiesrelatedtonuclearplantoperations.
His duties include the i
following:
l l
l 1
I l
1.
Provide technical direction and administrative guidance to:
l 1
1 1
l l
a.
Mechanical Engineering Manager l
b.
Electrical Engineering Manager I
y l
c.
Civil Engineering Manager l
d.
Instrumentation and Controls Engineering Manager l
l l
.l 2.
Assure conformance to the Quality Assurance Program by l
l Instituting the necessary quality-related procedures and l
instructions within Engineering Services.
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l 3.
Provide for review and approval of LRGO design and engineering i
{]'
g activities performed by contractors, vendors, and AP&L
'~'
I personnel.
l l
1 l
I i
4.
Provide for review and approval of procurement documents for l
equipment, material and services for LRGO engineering projects, I
as appropriate.
I I
l-I l
l 5.
Provide and maintain a qualified and suitable trained staff to l
l carry out required departmental functions.
I i
- 1. 4.1. 4 Energy Supply Administrative Services General Manager l
I l
lTheEnergySupplyAdministrativeServicesGeneralManagerreportstothe l
Energy Supply Services Director and is responsible for the development of l
ladministrativeprograms,systemsandservicessupportivetomanagement.
I His duties include the following:
l l
l l
l
(^3 I
1.
Provide technical direction and guidance to:
I
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l l
I a.
Energy Supply Training Manager l
l b.
General Services Manager l
l c.
Planning, Scheduling & Cost Control Manager l
d.
Contract Administration Manager l
l l
2.
Maintain overall department fiscal direction and control, and l
provides supportive accounting functions.
l l
1 l
I l
3.
Provice contract administration and administration of I
procedures for Energy Supply Little Rock General Office (LRGO) l l
activities.
1 I
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4.
Administration of the training and development effort for l
l Energy Supply LRGO personnel.
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4%,
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,5.
Ancillary support services to Energy Supply operation sections.
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I 6.
Provide and maintain a qualified and suitable staff to carry I
l out required departmental functions.
l 7.
Serve as a member of the Safety Review Committee.
l l
i t
I l
Im 8.
Assure conformance to the Quality Assurance Program by I
f instituting the necessary quality-related procedures and I
l' instructions within Administrative Services.
I I
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I l\\ 1.4.2 Nuclear Operations I
l l
I I
i Nuclear Operations is under the direction of the Nuclear Operations Vice I
lPresidentwhoqeportstotheEnergySupplySeniorVicePresidentandis i.,
1 responsible for the formulation, licensing, implementation and discharge I
S 1g -
of operating policies and procedures relative to nuclear plant operations l
4
'c l
and for nuclear fuel management.
His duties include the following:
I I
s I
3 1
s I
s
.,q )..
I 1.
Provide technical direction and administrative guidance to the:
1
(.._ ) s I
l s
I l
I a.
Plant's General Manager I
'N l
b'.
Nuclear Services Manager l
.(
l c.
ANO Project Manager I
(
d.
Li, censing Manager l
l l
I 2.
Assure conformance to the Quality Assurance Program by I
t I
..y l
l instituting the necessary procedures and instructions within I
the Nuclear Operations Department.
l
(
l 0
1 3.
Provide for review and approval of design and engineering
}I, performed for,the operating nuclear plants.'
I 5
ft,7 l
.l l
l 4.
Provide for review and approval of procurement documents for I
equipent, materia,1adtservices.
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)
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I q..
,d I'
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l l
S.
Provide for liason between AP&L and applicable regulatocy l
'^')
l agencies.
6.
Provide and maintain a qualified and suitable staff to carry
,I l
out required departmental functions.
l l
l l
l l
7.
Provide for procurement and design review of nuclear fuel.
l 1
l 1
l l
8.
Overall responsibility for the fire protection program l
l implemented at the nuclear plants.
l l
l l '1.4. 2.1 Nuclear Services Manager l
l l
The Nuclear Services Manager reports to the Nuclear Operations Vice l President and is responsible for providing the necessary support services l
lrelatedtotheeffectiveoperationandmaintenanceoftheAP&Lnuclear l
l plants.
The duties include the following:
l l
1
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1.
Review, approval and coordination of design changes through the l
l Little Rock General Office.
l l
l 2.
Review, approval and coordination of purchase requisitions and l
contracts generated at the Little Rock General Office.
I I
I I
l l
3.
Interface with other departments to assure effective l
implementation of Regulatory and Company requirements.
l l
l 4.
Communication interface dealing with all activities at the i
nuclear plants.
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'a l
S.
Provide technical dir,ectan and administrative guidance to the l
'( )
Nuclear Fuel Supervisor, who is responsible for the y
l procurerent, design review and performance evaluation of l
.-l l
nuclear fuel and to provide support. to the plant in the areas g
l of reactor core ~parformance and assessment of core design l
I l
analysis.
l l
.j I
/
I 6.
Serve as a member of thetSafety Review Committee.
vl l
I 1.4.2.2 Licensing Manager l
l
.i s l
l The Licensing Manager reports to the Nuclear Operations Vice President l
'/3 i
l and is responsible for the coordination of all licensing documents, l
lrequirementsandrevisionstheretowhicharerequire'dtobereviewed k
l+ and/or approved by the NRC and for interfacing with the NRC. The l
l Licensing manager'is also resp sible for the review and approval of 1 Q-List changes and for the tracking of possible nuclear safety concerns l
I I
to assure timely c.loseout.
I I
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(
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1.4.2.3 Project Manager P
,g l
lTheProjectManagerreportstotheNuclearOperationsVicePresidentand l
P l is responsible for providing services at the nuclear plant for field l
construction activities and for modifications; to the control room l
l simulators usedefor operator's training..His duties include providing l
7' technicaldire[tionandadministrativeguidance'totheFieldConstruction l
l Manager and the Simulator Project Coordinator.
l l
1 l
1 l
1.4.2.3.1 Field Construction Manager l
I I
l l
l The Field Construction Manager is responsible for directing the l
I I
activities of his staff relating to work associated with plant l
l a
l ' construction and modifications.
His duties include:
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1)
Interface with other departments to assure effective l
I Q(m implementation of job assignments l
l I
I 2)
Provide cost and' schedule controls for departmental activities I
I l
3)
Provide technical and administrative guidance to the l-Construction Quality Control (CQC) Supervisor.
The CQC l
Supervisor is responsible for the surveillance and inspection l
of activities performed under the direction of the Field l
Construction Manager, and shall have sufficient authority and l
organizational freedom to:
identify quality problems; l
'I '
initiate, recommend or provide solutions through designated I
-l-s l
l channels; and verify implementation of solutions.
The CQC l
l-Supervisor is also responsible for assuring adequate inspection l
points have been assigned for the work activity, inspectors l
have been certified to ANSI N45.2.6, 'irecting the activities l
l of the inspectors, and interfacing with the Code Inspector for l
activities involved Code items.
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l
- 1. 5 PLANT ORGANIZATION I
I i
1.5.1 General Manager l
l I.' 1. 5.1.1 l
l 1
The General Manager reports to the Nuclear Operations Vice President on l the corporate level (see figure 5) and has direct responsibility for l
operating the plant in a safe, reliable and efficient manner.
He is
~
.l responsible for operating the plant in accordance with the provisions of l
I the operating licenses, including the on-site quality program.
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l 1.5.1.2 l
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s 5
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l The General Manager has the authority to shut the plant down if required l
and has final approval of plant procedures.
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- 1. 5.1. 3 I
I i
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lTheGeneralManageristoprovidetechnicaldirectionandadministrative
,I l guidance to the:
l l
l l
l l
1)
Operations Manager l
l 2)
Maintenance Manager l
y l
3)
Administrative Manager l
4)
Engineering and Technical Support Manager l
5)
Special Projects Manager l
l 6)
Manager, Nuclear Quality Control l
l l
l 1.5.2 Operations Manager
'h l
l The Operations Manager (Figure 6) is responsible for directing the actual l
l. day-to-day operations of the plant.
He supervises the operating staff l
and interfaces with the Maintenance Manager to accomplish l
l operation-related maintenance activities.
The Operations Manager is to i
provide technical direction and administrative guidance to the:
I I
1)
Operations Superintendents l
2)
Operations Technical Staff l
1 1
I I
l 1.5.2.1 l
l l
l 1
l The Operations Superintendents report to and assist the Operations l
Manager in directing the day-to-day operation of the power plants.
They l are responsible for coordination of the daily review of operating l
surveillance tests and coordination of operation-related maintenance i
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l activities.
They are to assist the Operations Manager in the supervision l
~}
of core refueling, which includes advance planning for the outage, plant l preparation, equipment check-out and the refueling operations.
l l
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1.5.2.2 l
l l
I l
l The Shift Supervisors report to the Operations Superintendent and are l
I responsible for the actual operation of the unit and for the activities I
I l of the operators during their assigned shift.
The Shift Supervisor is to l
I be cognizant of operation activities being performed while on duty.
The I
l I
l Shift Supervisor on duty has the authority to shut down the unit if, in l
I his judgement, conditions warrant such action.
I I
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1.5.3 Maintenance Manager I
I I
I I
l The Maintenance Manager (Figure 6) is responsible for the maintenance of I
I I
l plant equipment, facilities and planning / scheduling of station work l
l activities as defined by plant maintenance program implementing I
I I
p l procedures and to assure that maintenance of equipment is conducted in l
C' I conformance with applicable standards, codes, specifications and I
I I
l procedures The Maintenance Manager is also to coordinate l
l operation-related maintenance activities with the Operations Manager and I
I I
l is responsible to make repairs on any structure, system or component l
l under his control. The Maintenance Manager is to provide technical I
I i
l direction and administrative guidance to the:
l 1
I I
I l
1.
Mechanical Maintenance Superintendent l
l l
2.
Electrical Maintenance Superintendent I
l l
l 3.
Instrument & Control Superintendent l
l 4.
Planning and Scheduling Supervisor I
r l
l l
5.
Senior Maintenance Coordinator l
l-6.
Shift Maintenance Superintendent I
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1~ 5. 4.
Engineering and Technical Support Manager i
.N l
l l-The Engineering.and Technical Support Manager (Figure-7) is responsible l
for providing plant engineering support services as well as technical and l
1 plant analysis and health physics support services to the plant staff.
l l-The'EngineeringandTechnicalSupportManageristoprovidetechnical l
l direction and administrative guidance to the:
1 I
I 1
I
.l~
1)
Technical Analysis Superintendent l
l-2)
Plant Analysis Superintendent l
I 3)
Plant Engineering Superintendent l
.l 4)
Operations Assessment Superintendent l
l 5)
Health Physics Superintendent.
l l
l I
I l
.1.5.4.1~
Technical Analysis Superintendent l
l 1
l' I
-l The Technical Analysis Superintendent maintains overall responsibility l
for radiochemistry, chemistry and environmental programs at the plant.'
l 1 The Technical Analysis Superintendent-is also responsible for maintaining l
^
lthe Station Emergency Plan and ensuring the plant staff is capable of l
implementing.the requirements delineated in the Plan and its procedures.
l l~
l i=.
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1.5.4.1.1 l
.I I
- l-I l.The Radiochemistry Supervisor reports to the Technical Analysis I
- Superintendent and is' responsible for analyzing the reactor plant water l
l conditions and providing recommendations to maintain conditions.
l l
l
'l-I l
1.5.4.1.2-l
'l:
I The Chemistry and Environmental Supervisor reports to the Technical l
lAnalysisSuperintendentandisresponsibleforestablishingwater
-ll : chemistry criteria, analyzing secondary plant water and auxiliary water i
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l-l l conditions and providing recommendations to maintain conditions within l
I acceptable limits.
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1.5.4.2 Plant Analysis Superintendent I
I I
I l
The Plant Analysis Superintendent 'is responsible for the areas of plant l performance, nuclear support and computer support.
A supervisor is l
II_ provided for each of these areas.
I I
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I 1.5.4.2.1 1
-l l
I l
l.ThePlantPerformanceSupervisorreportstothePlantAnalysis l
Superintendent and is responsible for:
evaluating equipment and system l
performance over extended periods, recommending methods of improving and l maintaining good plant efficiency, investigating and evaluating equipment l
malfunctions or failures and recommending corrective action to prevent l
recurrences, and coordinating the activities of the Inservice Testing l
I Program at the plant.
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l~ 1.5.4.2.2 l
i I
I The Nuclear Support Supervisor reports to the Plant Analysis I
I I
l Superintendent and is re:;ponsible for monitoring reactor core and Nuclear l
- Steam Supply System (NSSS) performance; conducting reactor performance l
and physics testing to assure safe and reliable operation and to provide l
current accurate information to operations; collection and transmittal of l
nuclear fuel management data to the Nuclear Fuel Supervisor in Little l
Rock and the reactor vendors as required; on-site safeguards and l
accountability of the nuclear fuel; and assisting in the planning of all l
I fuel movements including new fuel receipt and inspection, fuel shuffling I
l l
l at refueling, inspection of irradiated fuel and shipment of spent fuel.
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l 1.5.4.2.3 l
I I
i,i l
I il The Computer Support Supervisor reports to the Plant Analysis l
lSuperintendentandisresponsibleforthemaintenance,revisionand I
development of computer software for the plant monitoring computers and I
for providing technical assistance to the Nuclear Support Supervisor and l Nuclear Engineers in development and use of test apparatus for evaluation l
.loffuel,coreandNSSSperformance.
l l
l l1.5.4.3 Plant Engineering Superintendent I
I The Plant Engineering Superintendent is responsible for drawing control, l
l implementation and coordination of the Inservice Inspection Program and I
design and plant engineering activities at the plant.
The Plant i Engineering Superintendent is to provide technical direction and I
administrative guidance to the:
l l
l l
1)
Mechanical Engineering Supervisor l
f~N I
2)
Electrical Engineering Supervisor I
l' i l
3)
Drafting and Drawing Control Supervisor.
l g
l l
l1.5.4.4 Operations Assessment Superintendent l
l l
The Operations Assessment Superintendent provides the capability to l
l perform engineering evaluations of operating experiences which occur both I
at the AP&L nuclear plants and at other nuclear power plants and to l
l recommend corrective actions as a result of these evaluations to help l
plant operations personnel-in preventing or dealing with similar I ocurrences.
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ll -1.5.4.5 Health Physics Superintendent l
.,7 y l-l
~;i A"
- I.
I l ;The Health _ Physics Superintendent is directly responsible for and has the l
!. authority to implement the Health Physics program at the nuclear plant
'l-and to _ maintain radiation exposure as low as~ reasonably achievable l
(ALARA). ;The Health Physics Superintendent has.the authority to stop
,l. worktin radiation treas if he evaluates that a potential for an l
-unanticipated' excessive' exposure to plant personnel or the environment
'l may exist.
l
- l 1
- l.
l l
- 1. 5. 5 Administrative Manager l-l I
l.
I l " The -AdministrativiManager (Figure 8) reports to the General Manager and l
'laidshim'in.theadministrativeaspectsoftheplant'soperation.
The l ' Administrative Manager directs.the activities of the administrative staff l
.llandprovidestechnicaldirectionandadministrativeguidancetothe:
I e-1
-l l
' l-l)
Office Services Supervisor I
y g
- p
- l
-2)
Material Management Supervisor l
M 3)
~ Human Resources. Supervisor
-l-4)
Training Superintendent l
I' 5)
Plant Controller I
-l-I l'
l s
I
'1.5.5.1 I
-l l
l 1
7 The.0ffice' Services-Supervisor is responsible for administration of the l clerical staff activities ~and the accumulation and disposition of quality l
I. assurance _. records related to all phases of the nuclear plant.
+-
I l-1 1
I
?I "1.5.5.2 I
I i
l l
' jThe. Material Management Supervisor is responsible for plant procurement, I
l storage of= materials, parts and equipment, issuance of tools and test 1
equipment and the disposal of-surplus materials.
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1.5.5.3 l
l
- (./ '
l I The Human Resources Supervisor is responsible for employment, industrial l
lrelationsindustrialsafetyandfirepreventionandsecurity. Reporting I
to him are the Safety and Fire Prevention Coordinators, the Security l
- l. Coordinator,andtheEmploymentandIndustrialRelationsCoordinator.
I l
l1.5.5.3.1 l
l l
.The Safety and Fire Prevention Coordinators are responsible for l
l conducting periodic checks to examine control of combustables, l
housekeeping and other fire prevention / protection efforts as well as to l
l provide a centralization of OSHA and plant safety programs.
l 1
l l
l l
1.5.5.3.2 l
1 i
l l
I The Security Coordinator is responsible for coordination of the efforts l
of the security force and to manage the operation of the security system.
l O
l l
l 1.5.5.4 I
1 The Training Superintendent is responsible for the training and I
retraining of plant personnel and of Little Rock General Office personnel l
lasestablishedbyPlantprocedures.
l 1
l l
1.5.6' Manager, Nuclear Quality Control l
-l l
lTheManager,NuclearQualityControl(Figure 5)isresponsiblefor l
l verifying the implementation of the Quality Control Program at the plant l
l and reports to and receives direction from the General Manager.
The l' Plant Quality Control department shall have sufficient authority and l
l organizational-freedomto:
l identify quality problems; initiate, l
recommend or provide solutions through designated channels; and verify I
implementation of solutions.
His duties include the following:
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l_
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l l
1)
Provide technical direction and administrative assistance to l
I the:
/
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g Quality Control Engineering Supervisor I
a.
l b.
Quality Control Supervisor l
l c.
Quality Control Engineers l
l d.
Quality Control Inspectors l
l l
1 l
l 2)
Interface with the Quality Assurance Manager or his l
representative for technical assistance in resolving l
significant conditions adverse to quality.
l
~l l
I l
l 3)
Authority to place an item in a nonconforming status when such l
an item is determined to be in violation of purchase documents, l
l applicable codes and standards or FSAR requirements.
l l
l l
l l
4)
Assuring surveillances, inspections and reviews of plant l
. activities and documents are conducted in accordance with plant
/^
l procedures.
l
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1.5.7 Special-Projects Manager l
1 l
1:
l l
The Special Projects Manager is responsible for the administration and l
I. control of special' projects pertaining to plant operations, maintenance l
l and administration and is to provide technical direction and l
administra'.ive guidance to a staff of Special Project Coordinators.
l Additional duties include:
l l
l 1
l l
1)
Serving as chairman of the Plant Safety Committee l
l l
1 l
l 2)
Interfacing with onsite regulatory agencies l
l l
l l
l 3)
Providing evaluations and recommendations to regulatory l
I requirements and meeting regulatory commitments.
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1.0 ORGANIZATION lPAGE 1-20 l
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- 1. 6 INDEPENDENT REVIEW ORGANIZATIONS l
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In addition to the responsibilities of key individuals within the AP&L l
. organization who are involved with the overall quality program, AP&L has
! established the following committees as a management tool to I
independently review activities occurring during the operational phase of I
a nuclear plant.
I l
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1.6.1 Safety Review Connittee (SRC) l I
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The SRC reports to the Nuclear Operations Vice President and is I
responsible for providing of f-site independent reviews, and/or audits l
l relating to:
the Safety Analysis Report, Technical Specifications, I
Procedures and changes thereto; unreviewed safety quer.tions; violations, l
I deviations and reportable events; and any other matter involving safe I
operation of the nuclear plant which the committee deems appropriate or g
l 1s 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
A]s
(
l Committee.
l l
l l
l 1
1.6.2 Plant Safety Committee (PSC) l ll l
1 l
l The PSC reports to the plants' General Manager and is responsible for l
reviewing activities specified in the Administrative Technical l
l Specifications for the purpose of:
l l
l l
l l
1)
Rendering determinations in writing with regard as to whether i
or not an unreviewed safety question (defined by 10CFR50.59) is I
involved; and l
I I
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I 2)
Furnishing written recommendations to the plants' General l
Manager for approval of disapproval.
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1.0 ORGANIZATION IPAGE l-21 1
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l These activities include changes to plant procedures and Technical l
^
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i Specifications, proposed modifications to plant systems, changes to I
j I
l plant security and emergency plans, and review of facility l
I operations to detect potential nuclear safety hazards.
I I
I I
I I
- 1. 6. 3 Committee Structure I
l l
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I The organization structure and administrative requirements specific to l
I i
j each committee are described in the plant's Technical Specifications and l
I in internal procedures / documentation.
I I
I l
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- 1. 7 ORGANIZA'IONAL INTERFACES AND RESPONSIBILITIES I
I I
l~
l II As owner and operator, AP&L assumes full responsibility and authority for I
l the plant including action to assure that the plant is operated in l
~lI accordance with sound engineering practices, Licensing requirements and l
I l applicable codes, specifications and procedures.
l 1
1 I
I
~ (]
l Each supplier of equipment, material or services and each maintenance or l
I modification contractor is responsible for administering the applicable I
I I
l quality control functions as required by AP&L.
The Quality Assurance and l
l Quality Control organizations are responsible for assuring by I
I I
l surveillance, inspection, audit or review of objective evidence (e.g.,
l I
audit reports conducted by others, etc.) that these functions are l
I I
l accomplished for systems and structures that affect the safety and l
I integrity of the plant.
I I
I I
I I
Visits to manufacturer's shops by Quality Assurance organization I
I I
l personnel are conducted, when deemed necessary, based upon safety l
I significance, complexity, method of acceptance and past history of the I
l l
l vendor, to establish product quality and to assure that quality assurance l
I and quality control programs function in accordance with AP&L I
I i
l requireinents.
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I
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1.0 ORGANIZATION lPAGE 1-22 l
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I
.i l
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I I The AP&L Energy Supply Organizational Chart (Figure F-3) shows the l
(~'T-I
- g' 1
reporting relationships and the lines of communication established I
I I between the Quality Assurance and Quality Control organizations.
These l
l lines!of communication are established between the various quality l
1 organizations in order to provide assistance and/or information, when I
requested, in verifying satisfactory implementation of the quality I program and in resolving significant conditions adverse to quality.
I I
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I-I ff')
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TOPICAL REPORT lREV.
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I 1 SECTION:
1.0 ORGANIZATION lPAGE 1-23 l
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l12.0 QUALITY ASSURANCE PROGRAM l
1 j-l I
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-l 2.1 ' SCOPE l
l l
I l
l-This quality program is to assure that AP&L nuclear plants are operated l
l in a sa'fe, reliable and efficient manner and in accordance with NRC
-l regulations, applicable industrial standards and codes and applicable l
l.Companypolicies,. rules,proceduresandlicensingdocuments.
,I A matrix of
-l QA Procedures cross-referenced to each criterion of 10CFR50, App. 8, is l
lincludedinTable2.tothismanual.
l-l
- 2.2 GENERAL I
I I
-l-2.2.1'
,I
- I I
lg 'This quality program is applie'd to those safety related structures, l'
systems _and components and to those expendable and/or consumable items
- l whose satisfactory performance is required to prevent accidents which may fy l.
D cause undue risk to the health and safety of the public or to mitigate l
the-consequences'of such accidents if they were to occur.
These l
structures, systems, components and consumable items are identified in l
_ltheQ-listwithintheFSARforeachnuclearunit.
When structures, l
systems and components as a whole are on the Q-list, portions not l
associated with'a loss of safety function as determined by Engineering l
l are to be considered Non-Q, unless otherwise dispositioned by l
-Engineering.
l
- 1 I
I
- Expendable and/or consumable items are to include, as a minimum:
I l
nuclear-fuel,weldrods,boricacid,anddieselfuel.
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2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-1 l
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l
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2.2.2 l
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q j)'
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l l
The quality program for fire protection is addressed in the applicable l
section of the FSAR for each operating nuclear unit, and implemented l
through appropriate LRGO and plant procedures.
lhe effectiveness of the l
fire protection program is verified through scheduled audits conducted by l
the QA organization, under the cognizance of the SRC.
l l
l l
l 2.2.3 l
l
-l I
l l
l The Q-list is under the control of the Licensing Mar.ager.
The Licensing l
Section maintains an up-to-date list of personnel issued a copy of the l
Q-list and assures that reviews, approvals and distributions of the l
l Q. list and changes thereto are performed in accordance with approved I procedures.
Changes to the Q-list require review / approval by the l
. discipline Engineering Manager,, Quality Assurance Manager and Licensing i Manager.
l l
l 1
I o
l 2.2.4 L) l l
l The following expendable and/or consumable items are to be controlled in l
the following manner to assure service quality:
I i
1.
Diesel Fuel - Service quality is assured by applicable l
l provisions / tests required by the Technical Specification for l
each operating nuclear unit.
l l
I 2.
Welding Rod - Servica quality is assured by procurement from an l
evaluated source, requiring material test results, and I
controlling the rod on site prior to use, to prevent I
degradation.
l l
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2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-2 l
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1.
3.
Boric Acid - Service quality is assured by procurement from an l
_g
(
}
evaluated source, requiring a batch analysis to assure I
I I
I conformance with our specification requirements, and on-site l
control prior to use, to prevent degradation.
I I
I I
- 2. 3 RESPONSIBILITIES I
I I
l I
I 2.3.1 I
I I
I 1
lAP&Lrecognizesthatqualityassuranceisaninterdisciplinaryfunction l
l involving many organizational groups, encompasses many functions and I
activities and extends to various levels in all participating l
l organizations (from the. Energy Supply Senior Vice President to all I
workers whose activities may influence quality).
This quality program l
designates responsibilities and duties of specific individuals, which may I
be performed by their appointed designees.
I I
l 2.3.2 g
g This quality program assigns the responsibility for quality to the l
l departments performing the work and includes as a basic requirement that i
I g
individuals responsible for verification of conformance are qualified and l
do not perform or directly supervise the work.
Additionally, independent I
reviews, audits and surveillances are provided by individuals not l
l reporting to the groups responsible for performing the work.
I I
I
-l I
l 2.3.3 l
i I
I I
_l This quality program also includes provisions that require suppliers, I
contractors, subcontractors, consultants, etc. to maintain and use I
g
.l quality assurance programs reviewed and approved by the Quality Assurance l
Manager.
Audits or surveillances by the QA0 provide assurance of I
compliance with applicable procedures.
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2.0 QUALITY ASSURANCE PROGRAM IPAGE 2-3 l
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2.3.4 I
I l
3,
)
l l
l l
The Nuclear Fuel Supervisor within Nuclear Operations is responsible for l
the assurance that nuclear fuel used in AP&L nuclear plants is designed, l
procured, manufactured, and utilized in accordance with regulatory l
requirements, and related industrial codes and standards.
On-site l
quality control of nuclear fuel is implemented through the use of plant l
~ administrative procedures.
These procedures include the receipt, l
inspection, handling, storage, and accountability of Special Nuclear l
Material (SNM).
The Nuclear Support Supervisor maintains a listing of l
those individuals qualified to perform receipt inspections.
l l
l l
l 2.4 PROCEDURES l
l l
l l
l 2.4.1 l
1 l
l I
l l
Activities which affect quality are defined in appropriate procedures, l
which are developed to cover AP&L administration and control.
The n.
l procedures state the policies and instructions necessary to fulfill the l
intent of the program.
Procedures provide for standard forms, lists, and l
check-offs used in documenting the inspections, certifications, reviews, l
I surveillances and audits.
The program and the procedures shall be l
modified or supplemented from time to time as the need for change arises l
during the life of the plant.
Quality program policies, procedures and I
l instructions are contained in the documents ~ listed in Table 3.
l I
l l
I l
2.4.2 l
l l
l 1
'l Procedures assure that activities affecting quality are performed under l
suitably controlled conditions.
Controlled conditions include the use of I
-l appropriate equipment; suitable environmental conditions for performing l
the activity such as adequate cleanliness; and assurance that required I
g I
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1 I
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I
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2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-4 l
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i I
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I I
I e
.I I
I l
I prerequisites for the given activity have been satisfied.
Administrative I
procedures also assure that the need for special controls, processes, I
I v
I test, and equipment to attain the required quality and the need for l
lverificationofqualitybyinspections,evaluationortestistakeninto I
account.
I l-l I
I I
2.4.3 I
I I
I I
l Other AP&L organizations outside of Energy Supply may establish written l
lprocedurestocontrolsupportactivitiesaffectedbytherequirementsof I
this quality program.
Procedures developed by such organizations are l
prepared and reviewed for technical adequacy within the cognizant
'I organization, reviewed by the Quality Assurance Manager and approved by I
the cognizant organization's department head.
1 I
2.5 PROGRAM REVISION AND CONTROL I
I l
2.5.1 g
(]
l I
4 Program revision and control shall be the responsibility of the Quality l
l Assurance Manager.
1 I
l l
I I
2.5.2 l
1 I
I l
l Proposed changes to the Quality Assurance Program for Operations are to l
lbesubmittedbytheQualityAssuranceManagertoaffectedLRGOandplant l
l management personnel for review and comment prior to approval and l
l transmittal to the Nuclear Regulatory Commission.
After resolution of l
I comments, changes are to be approved by the Quality Assurance Manager, I
l Energy Supply Services Director, and the Energy Supply Senior Vice l
l President.
1 I
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2.0 QUALITY ASSURANCE PROGRAM IPAGE 2-5 l
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'l. 2.5.3 I
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L l
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l The Nuclear Regulatory Commission is to be notified of changes to this l
l I
quality program annually for those changes that do not reduce the I
.l commitments in the program description previously accepted by the Nuclear l
l Regulatory Commission.
Changes to the program description that reduce j
the commitments are to be submitted and approved by the Nuclear l
Regulatory Commission prior to implementation.
The Quality Assurance I
l Manager is to determine if changes do or do not reduce the commitments of l
I
.this quality program.
I l
I i
l l
2.6 PERSONNEL I
I l
l l
l 2.6.1 I
I l
J l
lEmployeeswhosedutiesandresponsibilitiesarerelatedtothequality l
l program activities at or in support of the nuclear plant are to l
participate in appropriate indoctrination and training programs to assure
.,o l
that suitable proficiency-is achieved and maintained in the work they are l
l performing.
Such training shall include, as a minimum:
plant security; l
l-discussion of the overall Company policies, procedures and instructions l
which establish the quality program; an explanation of the AP&L quality l
organizations; and a discussion of those procedures which implement the l
quality program related to the employee's specific job-related activity.
l l
1 2.6.2 l
1 1
I The education, experience and responsibility requirements of individuals l
_ involved in this quality program are documented in job descriptions which l
are approved and periodically reviewed by management.
Requirements for I
l education, experience and proficiency levels are commensurate with the l
1 l
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TOPICAL REPORT lREV.
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2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-6 l
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.l degree of importance of the job assignment.
Experience and training l
(]
requirements for plant staff personnel are to meet the requirements of l ANSI N18.1-1971 and Regulatory Guide 1.8 (9/75), unless otherwise noted 1
in Table 1.
Personnel whose qualifications do not meet those specified l
in ANSI _N18.1-1971, and who are performing inspection, examination and l
testing activities during the operational phase of the plant, are to meet l
the requirements of ANSI N45.2.6-1978, unless otherwise noted in Table 1.
l l
l l
l 2.6.3 l
1 l
I I
l l
Personnel performing inspection and examination activities are to be l
lindoctrinatedandtrainedtoassuretheyareawareoftherequirements l which govern their activity.
Inspection and examination personnel are to I
~be qualified according to the applicable codes, standards, l
specifications, regulatory requirements and LRGO and plant procedures.
l Personnel performing inspections on those activities occurring during the l operational phase that are comparable in nature and extent to related l
activities occurring during initial plant design and construction are to l ~ meet the provisions of Regulatory Guide 1.58, rev.1 (9/80) and ANSI
.,m l
.i s
V I
N45.2.6-1978, in lieu of ANSI N18.1-1971.
I I
I I
I 2.6.4 I
I I
Personnel involved with welding or nondestructive examination of l
i l materials, systems or components are to meet the appropriate i
qualification requirements of the ASME Boiler and Pressure Vessel Code, i
Sections III and XI, or for structural welds, the American Welding l
Society (AWS) Structural' Steel Code D1.1, and the American Society l
Nondestructive Testing Standard SNT-TC-1A-1975, and certified to perform l
these tasks in accordance with these codes and standards.
I I
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2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-7 l
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1 l
l a.
I I
I l
l 2.6.5 l
'l em I
L)
I l
l Personnel performing audits of the quality prcgram are to meet the l
experience, training and qualification / certification requirements of l ANSI N45.2.23-1978, and regulatory guide 1.146 (8/80), unless otherwise l
noted in Table 1.
I l
l 2.6.6 l
l Training records are to be maintained in accordance with approved i
procedures.
For formal training programs, documentation is to include l
the objective, content of the program, attendees, and date of attendance.
I I
2.7 PROGRAM REVIEW l
l l
l - 2. 7.1
,1 1
1 lTheQualityAssuranceManagerisresponsiblef'orareviewofthisprogram
()
l on an annual basis to determine the effectiveness and proper l
'd implementation of the quality program.
I I
2.7.2 l
1 Management reviews of the status and adequacy of the quality program are l -accomplished through regular reports and presentations by the QA0 and l
through reviews of quality assurance audit reports.
Quality Assurance l
reports supply data on the status of outstanding audit and corrective l
action items and may identify the status of other significant quality
.l program activities as requested by management.
l l
l l
1 l-l I
l
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l 1
l.
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1
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TOPICAL REPORT lREV.
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2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-8 l
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l 3.0 DESIGN CONTROL i
l 7
l 1
1 I
~
-l 3.1 SCOPE l
l-1 I
I l
Design activities are to be controlled to assure that proposed plant l
changes to the structures, systems, equipment and components conform to
,I l
applicable regulatory requirements and that design bases are correctly l
ltranslatedintoappropriatedesigndocuments.
l Design Control activities l
are to be in accordance with the requirements of Regulatory Guide 1.64 -
l l.Rev.2(6/76)unlessotherwisenotedinTable1.
_I I
I 3.2 GENERAL I
I I
I I
,I
- 3. 2.1 1
1
- Engineering Services and Plant Engineering are to be responsible for the l
continued upgrading and modification of plant design.
Design documents l
(drawings, specifications, procedures and instructions) originating or l
,e l
released through these departments are to be based upon the required l
O]-
lregulatoryrequirements,licensingbaseddocuments, functional l
l requirements, quality standards and design bases in accordance with NRC l
,I licensing requirements.
Design activities may include calculations, l
l analyses, materials selection, equipment arrangement and layouts, l
accessability for inservice inspection, and the specification of test and l
inspection criteria.
Those design activities performed by individuals l
within Engineering Services are controlled by the use of LRGO Energy l
Supply Procedures.
Those design activities performed by individuals l
within Plant Engineering are controlled by the use of Plant l
Administrative and Engineering Administrative Procedures.
These l
procedures include controls to assure that verified computer codes are
-l certified for use and that their use is specified.
l 1
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3.0 DESIGN CONTROL IPAGE 3-1 l
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l 3.2.2 l
,Q l
l V
l l
l Design standards and requirements are to be at least equivalent to those l
lemployedduringtheconstructionoftheplantandaretobeconsistent I
with the technical specifications and license requirements.
1 I
I I
I l
3.3 DESIGN INTERFACE I
l l
I I
l Design control activities include measures for the identification and l
l control of design interfaces between the various engineering disciplines l
l within the department, between LRGO and plant engineering personnel, l
lbetweenengineeringpersonnelandotherAP&Lsupportorganizations,and l
l between engineering personnel and firms / suppliers outside the AP&L l
j organization.
These measures include the development of procedures among l
g l
the participating organizations for the review, approval, release, i
distribution and revision of documents involving design interface.
I l
Coordination of the interface control is the responsibility of the l
originating organization's management unless otherwise specified in an j
l AP&L procedure applicable to the design activity.
Design information I
v g
g between interfacing organizations is to be documented and retained for g
g l
permament records.
I l
l
'l I
l 3.4 DESIGN VERIFICATION I
I I
l l
I 3.4.1 I
I I
I I
l To assure the design is adequate and the above requirements and l
I g
procedures are implemented, Engineering Services for LRGO design or Plant i
Engineering for plant design are to verify the adequacy of the design i
through the performance of design reviews, the use of alternate or l
l simplified calculation methods, or the performance of a qualification i
l 1
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D l
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3.0 DESIGN CONTROL lPAGE 3-2 l
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1
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I l
testing program.
The extent and depth of design verification performed I
h~
.lbytheresponsibleorganizationisdeterminedbyanassignedengineering I
g i
reviewer based upon the importance and complexity of the design, the l
I l
g degree of standardization and its similarity with proven designs.
In all l cases, the design verification is to be complete prior to relying upon l
the component, system or structure to perform its function.
l l
3.4.2 I
l The verification process is to be performed by competent individuals or l
groups other than those who performed or supervised the design but who I
may be from the same organization.
This verification, however, may be I
performed by the originator's supervisor in accordance with departmental I
procedures if he is the only individual in the organization competent to I
g l
perform the verification and provided the need is individually documented l
landapprovedinadvancebytheresponsibleManagerorSuperintendent.
l The frequency and effectiveness of use of Supervisors as design verifiers l
is to be verified by QA through scheduled audits to guard against abuse.
l (l
l Where changes to previously verified designs have been made, design i
V l
verifications are required for the change, including evaluation of the l
g g
l effects of the changes on the overall design.
I I
I I
I l
3.4.3 l
l l
l 1
l When a test program is used to verify the adequacy of a design, it is to I
f'includesuitablequalificationtestingofaprototypeorinitial I
g l
production unit under the most adverse conditions and carried out in I
accordance with documented procedures and/or instructions.
Testing is to l
l be performed as early as possible prior to installation of plant I
equipment, or prior to the point when the installation would become I
irreversable.
I I
I I
I I
l l
l l
l l
1
,q l
l V
l l
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I TOPICAL REPORT IREV.
6 l
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l lDATE 5/30/84 l
l I SECTION:
3.0 DESIGN CONTROL lPAGE 3-3 l
l L
I i
l
-l l
I I
i l
1 l
l l-3.4.4 l
q_
l I
- / -
l l
l Design work performed by organizations outside of AP&L is to receive a l
I documented review and approval by engineering personnel in accordance l
with LRGO and plant departmental procedures.
l l
i I
I l
3.5 DESIGN CHANGE l
l l
l l
l 3.5.1 l
l 1
l-l l
Methods for the preparation, review, approval and implementation of l
design changes, including field changes, are documented in departmental l
4 l
procedures for Engineering Services and Plant Engineering.
Design l
lchangesaresubject'toreviewandverificationbythesameorganization
-l which review and verified the original design unless otherwise specified l
in departmental procedures for design control.
If minor changes to an l
approved design are required to meet plant requirements or conditions, l
' Field Change Notices (FCN) may be issued or otherwise documented by a l. cognizant engineer and transmitted with the changes for review and l
b' a'prcval in accordance with Plant Engineering Administrative Procedurcs.
p I
I I
3.5.2 I
I I
I I
-Changes from specified design inputs, such as decign bases, regulatory l
l requirements, codes and standards (including quality standards) are to be l
ident1 Tied, approved, documented and controlled through applicable LRGO
.l-and plant departmental procedures.
l l
l I
I l
3.5.3 l
l l
l l
l During preparation of a design change, the responsible engineering l
organization is to perform a safety and environmental evaluation per l
I l
l l
1
-l l
o l
l l
A l
TOPICAL REPORT (REV.
6 l
l_
P l
lDATE 5/30/84 l
l l SECTION:
3.0 DESIGN CONTROL lPAGE 3-4 l
l.
L l
l l
~l I
l l
Iz
e I
I i
l l
10CFR50.59 to verify compliance with the Final Safety Analysis Report and l
l i >-
_l to determine if NRC approval of the design change is required.
The I
,7 l
l evaluation is to be documented and then reviewed by the PSC.
l l
1 l
l 3.5.4 l
l l
l l
l l
Design changes are also to be submitted to the Manager, Nuclear Quality l
l I
Control _ prior to plant implementation to verify the use of appropriate l
I l
quality codes, standards and inspection requirements in the design l
I documents.
1 I
l' I
I I
3.6 CORRECTIVE ACTIONS I
I I
I I
I l When design changes are made as a result of design deficiencies or I
l l
errors, corrective actions (for significant conditions) are to be taken l
l in accordance with Section~16.0, to determine the cause and to institute I
l I
l appropriate changes in the design process and/or Quality program to l
prevent recurrence. When a significant design cnange is necessary l
because of an incorrect design, the design process and verification l
_\\J l
procedures shall be reviewed and modified as necessary.
I I
I I
I I
- 3. 7 DESIGN RECORDS I
I l
l l
I The Plant Administrative Manager is responsible for maintaining permanent I
I I
l records of the design documents for the construction and testing phases.
l l
In addition, he shall be responsible for maintaining records of the I
I l upgrading or modification of these documents as described in this l
I section.
I The controls for maintaining these records are established by I
I l
specific procedures described in Section 17 of this manual.
These l
l records provide the historic reference necessary for the safe and I
I I
l reliable operation of the plant.
l l
1 1
I I
I I
I I
I I
I
T I
I I
I
\\d i
A l
TOPICAL REPORT IREV.
6 l
1 P
l 10 ATE 5/30/84 l
l I SECTION:
3.0 DESIGN CONTROL lPAGE 3-5 l
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I l
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l 1
1
f I
l
-l l
l 4.0 PROCUREMENT DOCUMENT CONTROL l
l n
s l
l 4.1 SCOPE I'
l l
c l
'(l Requirements,for the procurement of items and services are to be clearly l
I
_I stated and, documented to assure that applicable regulatory requirements, I
l 1
design bases', technical requirements and quality assurar,ce criteria are l
'l r-t b
j included or referenced in the procurement docurnents, whether procured by l
LRGO or'; slant procurement groups.
Procurement document control l
l a'ctivities are to be in accordance with LRGO and plant procurement I
g y
l procedures and are to meet the provisions set forth in NRC Regulatory l
Guide 1.'123, rev.1 (7/77) unless otherwise rioted in 7able 1.
~
s l_
N l
I' 4.2 Pit 0CUREMENT DOCUMENTS I
l s
l l
l
'4.2.1 l
+
l The_ procurement of materials, parts and components are gene' rated through NN N
l t!le prepaiation of a Purchase Requisition (PR) and subsequent issuance of l
t
'd
.g l 6,Purchast Order (PO), or when' additional services from the Vendor is a
l l
req'uired, ?.hrough the preparation and issuance of a Contract.
The l
proct.rement 'af-services is initiated through the preparation and issuance I
of a Contract.
The preparation, review, approval and issuance of these l
g procurement documents is to be in accordance with applicable procurement l
l and contract administration procedures.
Purchase Orders for items are I
issued through the AP&L Purchasing group and Contracts for items and/or l. services are issued through'the AP&L Contracts Administration group.
l l
l l
l l
4.2.2 l
l l
l l
l Procurement documents are to include or reference specific dasign l
specifications for the items or services to be procured which define l
'l specific codes, standards, tests, inspections, environmental l
qualifications, and records to be applied and/or furnished.
For standard I
I i
I
, n
(
I l
l l
l l
A l
TOPICAL REPORT lREV.
6 l
- l P
l lDATE 5/30/84 l
l 1 SECTION:
4.0 PROCUREMENT DOCUMENT CONTROL lPAGE 4-1 l
l L
l l
l l
l-1 I
1.
r; I
l 1
l l
"off-the-shelf" items, reference to the items catalog number and I
/~'
identification number may be included on the procurement document in lieu l
l of a design specification.
New or revised specifications for replacement l
items are-to be evaluated by the responsible engineering organization l ~against the original specification for the item.
The evaluation is to be l
~in accordance with applicable engineering procedures and results in the I
g
-l establishment of new baseline and technical quality requirements, which I
are to be used for subsequent procurements.
l
.I I
I I
- 4. 2. 3 i
l I
- lProcurementdocumentsarealsotoincludetheidentificationofquality l
l assurance program requirements applicable to the items or services l
procured.
Procurement documents also establish requirements for source l
audits and inspection, extension of the procurement requirements to lower i
tier suppliers or subcontractors, and preparation and delivery of I
documentation.
These requirements may either be in the form of documents I
attached to the P0 or Contract or by incorporating them in the specific 7]
l design specifications.
Quality programs are to be specified by invoking l
d the appropriate sections of 10CFR50, App. B, the appropriate ANS1 I
g l
standards and/or the appropriate AP&L generated quality requirements for l
l items or services.
The appropriate sections of the ASME Boiler and i
Pressure Vessel Code are to be invoked for items originally designed to l
l meet ASME requirements.
l l
l 4.3 REVIEW OF PROCUREMENT DOCUMENTS g
l l
The responsible Quality Assurance or Quality Control organization, as l
l identified in the LRGO and plant procedures for procurement and contract l
administration activities, is to review all procurement documents to l
assure that the required quality requirements (including source l
surveillance and/or inspection) are imposed on suppliers / contractors.
l 1
I l
l I
I I
l l
l A
TOPICAL REPORT REV.
6 I
P l
IDATE 5/30/84 l
l 1 SECTION:
4.0 PROCUREMENT DOCUMENT CONTROL lPAGE 4-2 l
1 L
l I
l l
l l
l L.
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T' i
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I 7';1 1
4.4 CHANGES T0*conctiorMENT DOCUMENTS j
l l
\\
- -m I
('3) l
.?i, i
I
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Changes to, procurement documents are/to have the same degree of control l
h'fy and review as imposeo'on the original documents. Changes such as W
l. inconsequential editorial corrections or changes 'to commercial terms and l
- ,.. J -
l condiffons mai be made by the Nuclear Buyer or Contract Administrator as I
l l
appropriate, af ter concurrence f rom the originator.of the document.
l
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I l'
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l l
1 I
i I
- 44
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- ,- N J
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l
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lDATE 5/30/84 l
{4*
l J SECTION:
4.0 PROCUREMENT DOCUMENT CONTF.0L lPAGE 4-3 l
l pgd. L l
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.--cn TNCTRUCTIONC PRnrFDURE9 ann nRAWINGS l
l l
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l I
l 5.1 SCOPE-l l
l
'l-I
~l 5.1.1 l
l l
l l
.l-Instructions, procedures and drawings are provided for the control of l
~
those activities which affect quality and safety at the nuclear plant.
l Activities covered by written procedures include, as a minimum:
l administrative, ga:eeral plant operations, start-up; shutdown; power
-l operation and load changing, process monitoring, fuel handling; l
modification; maintenance and repair; radiation control; calibration and I ~ test; chemical-radiochemical control; plant emergencies; test and l
' nspection; and quality assurance, quality control and LRGO activities in i
l support of plant activities.
The format, content and philosophy of l
- instructions and procedures are to comply with the guidelines in ANSI l
N18.7-1976 and Regulatory Guide 1.33 (2/78) unless otherwise noted in l
I I
Table 1.
- l l
7-)
l l
I l
5.1. 2 I
I I
I Instructions and procedures are also provided for the control of l
activities relating to the repair, replacement or modifications to ASME l
l Code,Section III, Class 1, 2 or 3 components required to be operable to l
mitigate the consequences of a postehted accident.
l l
1 l
l l
5.2 GENERAL l
l 1
1 I
l
- 5. 2.1 1
I I
I l
l Instructions, procedures and drawings are to include appropriate l
quantitative criteria such as dimensions, tolerances and operating limits l
and/or qualitative criteria such as comparative workmanship samples to l
I determine that important activities have been satisfactorily I
I 1
I (m-I I
I I
)
l A
l TOPICAL REPORT IREV.
6 l
l P-l lDATE 5/30/84 l
l l SECTION:
5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-1 l
l L
l AND DRAWINGS l
l l
l l
1
o I
i l
I l
accoinpl i sneu. tach procedure is to be sufficiently detailed so that a l
(~')
I l
qualified individual may perform the required function (s) without direct I
x /
l
~
l supervision and is to include measures to document the activity being l
performed.
l 1
I l '
- 5. 2. 2 I
l l
l
. To assure the accomplishment of activities in accordance with approved l
instructions, procedures and drawings, each supervisor is responsible for l
lqualitycomplianceofhispersonnel.
Verification that activities are l. accomplished in accordance with approved instructions, procedures and l
drawings is obtained through various levels of surveillance and l
inspection by Quality Control personnel and through periodic surveillance l
and audits by the QA0.
1 I
l 5.3 REVIEW 0F INSTRUCTIONS, PROCEDURES AND ORAWINGS I
l i
I I
5.3.1 l
(')
l l
Instructions, procedures and drawings are prepared, reviewed and approved l
in accordance with applicable plant administrative procedures, when l
originated at the plant, or in accordance with applicable Energy Supply l
l procedures, when originated from LRGO.
l l
l l.
l l-5.3.2 l
l 1
1 I
l Plant procedures identifiad in the Technical Specifications for each unit I
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
procedures to the Plants' General Manager for approval and subsequent h
l issuance.
Plant Administrative procedures (1000.XX Series) are also I
reviewed by the Quality Control staff to verify compliance to AP&L's l
l l
l l
1 1
1 i
I
-n
(
)
l I
i 1
l
'A l
TOPICAL REPORT lREV.
6 l
l P
l l0 ATE 5/30/84 l
l l SECTION:
5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-2 l
l L
l AND DRAWINGS 1
1 1
I l
I
7_
i i
i I
quality program requirements.
LNbU Energy supply procedures describing l
i activities. required to implement this quality program are to be reviewed
~'
l and approved by a procedures task force committee and Quality Assurance l
to assure compliance to AP&L's quality program requirements prior to l
submittal of the procedures to the Department Head responsible for l
implementation, for approval and subsequent issuance.
I I
I
- 5. 3. 3 I
I l
i I
Plant and LRGO procedures and instructions are to be reviewed no less I
l-than every two years to determine if changes are necessary to meet NRC l
. commitments and current AP&L practices.
Applicable procedures (i.e.
l those that relate to the incident cause) are to be reviewed following an l
lunusualincidentsuchasanaccidentunexpectedtransient,significant l_
operator error or equipment malfunction.
Applicable procedures are also I
to be reviewed following any modification to a plant system.
I I
I 5.3.4 I
I I
f3
-l l
Y-Drawings related to plant changes and modifications are controlled as l
l. described in Section 3 and 6 to this manual.
l 1
1 I
I l
5.4 CHANGES TO PROCEDURES l
l 1
l l
5.4.1 I
l l
1 I
i l
Changes or revisions to approved instructions, procedures and drawings l
are to be reviewed and approved by the same organizations or groups that l
performed the original review unless otherwise noted in specific AP&L l
I procedures and controlled in the same manner as the original.
I l
I I
l l
I I
I i
1 1
I I
I I
O l
. (d l
l l
l l
A I
10PICAL REPORT lREV.
6 l
1 P
l 10 ATE 5/30/84 l
l l SECTION:
5.0 INSTRUCTIONS, PROCEDURES IPAGE 5-3 l
l L
l AND ORAWINGS I
I I
I I
__I
l l
l l
5.4.2 l
p I
I As I
l Temporary changes to approved plant procedures which do not change the l
intent of the procedure may be made provided such changes are approved by l
two members of the plant staff, at least one of whom holds a senior l
reactors operators license on the unit affected and the change is l
docurnented, reviewed by the PSC, and approved by the plant's General l
Manager within 14 days of implementation.
Temporary changes to approved l
plant procedures which change the intent of the procedure may be made l
provided such changes are reviewed by the PSC and approved by the Plants' l
l General' Manager prior.to implementation.
Temporary changes to approved l
l plant procedures are to specify the period of time during which they may l
be used and made readily available to affected members of the plant I
fstaff.
In the event of an emergency not covered by an approved I
procedure, operations personnel may take action, without obtaining l
approvals, so as to minimize personnel injury and damage to the facility l
and to protect health and safety.
l l
l 1,
I q
(_)
l l
l 1
- l l
l l
l 1
l-1 I
I l
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1 I
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l 1
I l
[
l l
I I
I I
I I
I l
l I
I
)
.l.
l l
.I-A l
TOPICAL REPORT lREV.
6 l
l P.
j IDATE 5/30/84 l
l 1 SECTION:
5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-4 I
l L
l AND DRAWINGS l
I I
I l
i.
k l
I
-g-l 6.0 DOCUMENT CONTROL l
I I
l i
I 6.1 SCOPE l
l-l 1
l l
The various quality program documents identified in Table 3 provide means I
to control the review, approval, issuance, use and retrievability of I
l documents, such as calculations, computer codes, analyses, Topical l
l Report, FSAR, instructions, procedures, specifications, manuals and I
drawings, including changes thereto, which prescribe activities affecting l
l.
quality.
I I
l
.6.2 l
RESPONSIBILITIES l
l l6.2.1 l
l l
lEachorganizationoriginatingdocumentswhichprescribeactivities I
af fecting quality is responsible for the establishment of document l
l g
control procedures which identify individuals or groups responsible for
)
I preparation, review, approval and maintenance of the document and for the l
g issuance of these procedures to the affected individuals or groups.
I I
- 6. '2. 2 l
l Review of these documents for concurrence with quality related I
requirements is to be pe-formed by the appropriate Quality Assurance or l
Quality Control organization or by the appropriate reviewer as described I
in LRGO and plant procedures.
l I
l l
l l
6.2.3 l
l l
l l
l The plant Administrative Manager is responsible for the control and l
issuance of plant procedures, and revisions thereto, to assure I
distribution in accordance with plant procedures.
The plant I
Administrative Manager is also responsible for the storage and control of l
-l I
~
l l
l l
l A
I TOPICAL REPORT IREV.
6 l
l
-P l
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l 1 SECTION:
6.0 DOCUMENT CONTROL IPAGE 6-1 1
'l L
l l
1 I
l I
l
I l
l I
nistorical plant documents, and the storage of historical
-appeuveu l
I drawing records.
The Engineering and Technical Support Manager is 7(o, I
l
'~
l responsible for the control and issuance of drawings and revisions l
thereto to. assure that they reflect the as-built conditions of the plant.
l l
l 6.3 IDENTIFICATION I
I I
I l
Documents are to be identified by a title descriptive of their purpose or
-l applicability and marked or stampad as to their current status (Draft, l
For Information Only, Void, etc.) per departmental procedures.
Revision l
status of documents are to be identified in document registers, l
' distribution lists and/or within the revision record page/ block of the
.l document.
[
.I I
I l
6.4 DISTRIBUTION I
l l
I I
I l
Distribution lists and/or document registers are to be maintained by the l
organization responsible for issuance of the document.
These lists are l
fy l
to identify the revision status of the document and are to be reviewed l
V I-and update'd periodically by the responsible organization to maintain them l
in a current status.
These lists are available to individuals using the l
document to assure they are in receipt of the current document.
These l
measures are to preclude the possibility of using outdated or l
inappropriate documents.
I, l
l l
-6.5 CHANGES I
l-1 I
I I
6.5.1 I
I I
I I
Changes to controlled documents are to be reviewed and approved by the l
same organizations which performed the original review and approval l
unless otherwise specified in departmental procedures applicable to the
_l affected activity.
1 I
I I
I I
I I
l C
l l
l l
V l.
A l
TOPICAL REPORT IREV.
6 l
l
-P l
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l 1 SECTION:
6.0 DOCUMENT CONTROL IPAGE 6-2 l
l-L l
l l
l l
I l
x
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'I ~ 6.5.2 l l' l
C
)
I l
i Obsolete or superceded documents are to be destroyed or marked to prevent I
inadvertent use in'accordance with applicable document control g
I procedures.
l I
I I
I I
6.6 STORAGE I
I I
I I
I Documents which affect quality are to be stored and maintained at the I
'l plant in permanent storage facilities and controlled as described in l
l Section 17 of this manual.
l l
l 1
l l 6.7 VERIFICATION I
I I
I I
l Quality Control personnel, through their various levels of quality I
surveillance and inspection activities, and Quality Assurance personnel, l
l through their audit activities, assure proper documents are being used I
. and made available to those individuals performing the work.
y r^N l
I V
I I
I I
l l
l 1
1 I
I l
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I l
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1 I
I I
I I
I l
I l
+
A I
TOPICAL REPORT lREV.
6 I
I P
l lDATE 5/30/84 l
l 1 SECTION:
6.0 DOCUMENT CONTROL IPAGE 6-3 l
i l
L l
I I
I I
I I
I
-..__ _ _._ _,. ~._ _
F I
I I
i 1
/. u CONTNUL UF PURCHASED MATERIAL, EQUIPMENT AND SERVICES l
I g
l i
l I
l 7.1 SCOPE l
l l
l l
1 The purchase of material, equipment and services is controlled to assure l
that, whether purchased directly or through vendors, the material, l
l equipment and services which affect quality conform to the procurement l
documents.
Procurement control includes provisions for source evaluation I
l ~ and selection, objective evidence of quality furnished by the contractor, l
-lsurveillanceandauditatthesource,examinationofproductsupon l
delivery and testing of received material for conformance to procurement l
criteria.
The depth and necessity of procurement controls depend upon I
the uniqueness and complexity of the item / service, procurement frequency I
with the same supplier and past supplier performance for the specific l
items or services covered by the procurement document.
The control of l
. purchased material, equipment and services is to be in accordance with l
the requirements of Regulatory Guide 1.38 Rev. 2 (5/77) and 1.123 Rev.1 l
(7/77) unless otherwise noted in Table 1.
l n
i I
LJ l7.2.SOURCEEVALUATIONANDSELECTION l
1 l
l 7.2.1 l
l l
s lAQualifiedVendorsList(QVL)istobemaintainedandcontrolledunder l
the direction of the Quality Assurance Manc er.
The QVL identifies l
lthosevendors/contractorsthathavebeenevaluatedandapprovedbythe l
QA0 to furnish material,,eguipment or services, and identifies any l
' restrictions imposed by the QA0 on the vendor / contractor as a result of l
l their evaluation.
I I
l l
l 1
l l
I l-I
-l 1
I I
I I
I I
l l
(~3 l
l l
l Is' l
A l
TOPICAL REPORT IREV.
6 l
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'l l SECTION:
- 7. 0 CONTROL OF PURCHASED lPAGE 7-1 1.
I L
l MATERIAL, EQUIPMENT AND SERVICES I
l l
l l
l
4
- 3ph y & -
3 I:
1
(.f
~l l
I Vendors / Contractors are_ evaluated and placed on the QVL by any of the l
~
following methods, as approved by the Quality Assurance Manager:
ll~
l (1) Source' survey by AP&L to verify compliance to applicable 10CFR50,
,I gr
-l!
_ Appendix B requirements or to applicable ASME Section III Quality l
Assurance program requirements (for ASME Class 1,2,3,MC,NF and NG I
I components).
l
'l l
I l
l (2). Evaluation and acceptance of source surveys performed by others l
(ex. CASE, other utilities, NSSS suppliers, and prime contractors) l indicating a program meeting the appropriate requirements of l
(This method is not applicable for ASME l
l-procurements.)
l l
l 1
I I
(3)- A review of the vendors / contractors current quality records l
supported by evidence of documented qualitative and quantitative h
I information which can be objectively evaluated.
This includes l
l review and approval of the veridor's/ contractor's quality assurance l
l program, manual and procedures, when available.
(This method is not l
applicable for ASME procurements).
l
~
l l
l-(4)' Evaluation of the vendor's/ contractor's history of providing a l
l
. product / service which performs satisfactorily in actual use.
l l
l Evaluation information includes:
experience of users of identical l
or similar products / services of the prospective vendor / contractor; l
I and/or procurement records that have been accumulated in connection y
l with previous procurement activities and operating experiences.
l (This method is not applicable to ASME procurements).
l l
l l(5) l Verification that a vendor is a holder of an ASME Certificate of
.l Authorization issued as a result of an ASME survey may be used in l
l-lieu of methods 1 and 2 for ASME procurements.
I l
.O i
i i
i l
A l
TOPICAL REPORT IREV.
6 l
l P
l lDATE 5/30/84 l
l l SECTION:
7.0 CONTROL OF PURCHASED lPAGE 7-2 l
l L
l MATERIAL, EQUIPMENT AND SERVICES l
l l
l l
l
.I l
l 1
l (6)- Verification'that a contractor is a holder of a NRC letter i
confirming QA program implementation may be used in lieu of
,I I
method 1.
I I
l I.
I I
- 7. 2. 3 -
l I
l l
l l
Only vendors / contractors listed on the QVL are to be selected for I
procurement of material, equipment or services except for items I
designated " commercial grade" per plant and LRGO procedures.
Standard I
catalog items may be procured from a vendor / contractor not listed on the I
g l
QVL provided the manufacturer of the item is on the QVL and all AP&L l
l requested' documentation originates from the manufacturer.
The QVL is to
-l be periodically reviewed and updated per quality assurance procedures to I
ensure the current status of all selected vendors / contractors is l
l Lavailable to personnel involved in the procurement process.
I I
l l
l l-7.2.4-1 I
l l
l p
I When contractors are selected to perform work activities at the plant, l
V their personnel and work activities are to be controlled in accordance l
l with plant procedures to assure that the contractor conforms to the l
l
l 1
l-7.3.SOURCESURVEILLANCE-ANDAUDIT g
I I
l'7.3.1 l
1 1
-The effectiveness of a vendor's/ contractor's quality assurance program is l
l assessed by QA personnel at intervals consistent with the importance, 1
l complexity, method of receipt and quantity of the products or services.
l l
This assessment may be through source surveillance, source audit, receipt 1
I l
- . inspection, independent testing or review of source documentation files.
g i
1 1.
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D 1
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TOPICAL REPORT lREV.
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l l SECTION:
7.0 CONTROL OF PURCHASED lPAGE 7-3 l
l L
l MATERIAL, EQUIPMENT AND SERVICES I
l l
l 1
I
m
.I l
LJ
.I-I
~
w, l7 7.3.2 l
l l
l l
l ' Requests for source surveillance are mada by the originator of the PR/
l Contract,_and/or tne responsible Quality Control or Quality Assur ece l
organization during. their review of the procurement document (reference l
I section 4.3) Source surveillance is to be performed by QA personnel or I
l-l l..their appointed representative in accordance with <.urveillance plans l
approved by the _ Quality Assurance Manager and the results documented per l
quality assurance procedures.
Reports documenting inspections performed l
and discrepancies observed are prepared by the person performing the I
-l
- surveillance to _ document compliance to the procurement documents and for i
future use as historical quality perf ormance data.
I I
I 7.3.3 I
l-1 I
I I
l Audits of the_ vendor's/ contractor's quality assurance programs are I
1 l
periodically performed under the direction of the Quality Assurance l
Manager to' verify implementation of a satisf actory quality program on the
- )
l items or services being procured by AP&L.
Audits performed by others l
I (e.g., CASE, other utilities, or prime contractors), as evaluated and I
l l
l approved by the Quality Assurance Manager, may be used as an alternative l
l to audits by AP&L to verify the vendor / contractor is implementing a I
I l
satisfactory quality program.
Audits are to be conducted in accordance I
with Section 18 of this manual.
(This alternative method does not apply I
l-I
-l to ASME procurements.)
i I
I I
I l
7.4 RECEIPT INSPECTION I
I I
l l
l 7.4.1 l
1 l
i 1
l Materials and equipment, including ASME Code materials and equipment, are l
subject to inspection upon receipt at the plant.
The degree of l
inspection is specified in the procurement documents and is to be i
I performed in accordance with plant procedures for receipt inspection.
I l
I I
I I
I
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7.0 CONTROL Of FURCHASED IPAGL
/-4 l
l L
l MATERIAL, EQUIPMENT AND SERVICLS I
i l
i l
l
1 1
1.
l 1
7.4.2 1
l
'~
l L
l l
-I 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 1
- documentation, to verify compliance with the procurement document.
In l
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-. performed by a Quality Control Inspector at the point of receiving to I
.l verify that the material or equipment confor:n to the inspection I
requirements identified in the procurement documents.
I I
I l
l I
7.4.3 I
l-l l
l l-Vendors are to furnish documentation as requ' ired by the procurement I
documents for objective evidence that the material or equipment conforms I
to the procurement requirements.
Review and acceptance of this I
documentation is to be performed by a Quality Control Engineer prior to l
ey 1
installation or use of such material or equipment and documented unless I
I otherwise specified in plant procedures.
Certificates of Conformance may l
n-l be required by procurement documents which identify the requirements met I
by the vendor.
The validity of the vendor's certification program is to l
be periodically verified through scheduled source surveillance and audit l
lactivitiesorthroughindependenttestingoftheitembyAP&L.
I I
7.4.4 I
I Accepted material and equipment is released, identified as to its l
inspection status and forwarded to a controlled storage area or released 1
- for installation per applicable plant procedures.
l l
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1 SECTION:
7.0 CONfROL OF PURCHASED lPAGE 7-5 I
I L
I MATERIAL, EQUIPMENT AND SERVICES I
l
.I I
I I
w
I I
I l
j 7.4.5-
~
l l
l
)
l l
l. Acceptance of services furnished by a contractor is to be identified in l
l the procurement documents.
Depending upon the service performed, l
acceptance may be by technical verification of the data produced, l
I surveillance and/or audit of the activity, or review of objective I
1.
l l
evidence for conformance to the procurement document requirements.
The l
I acceptance method is to be performed by qualified individuals I
l l
l knowledgeable in the service provided.
l l
l 1
I l
7.4.6 l
l 1
I l
l Independent testing of selected material is to be performed in accordance l
with plant procedures / instructions to verify conformance to procurement l
criteria and the validity of the vendor's certification documents.
l l
l 1
l l
- 7. 5 NONCONFORMING ITEMS l
l 1
1 I
o l
7.5.1 l
J l
l I
I l Nonconformances identified by the vendor / contractor which adversely l
affect reliability, performance or interchangeability of the item and l
dispositioned repair or use-as-is are to be submitted to and accepted by l
I AP&L prior to closure of the nonconformance by the vendor / contractor.
l These nonconformances are to be documented and become part of the l
I procurement documentation furnished by the vendor / contractor for the l material, equipment or services procored.
l l
1 1
I l
7.5.2 l
l 1
1 I
l Material and equipment found to be deficient or missing procurement l
I documentation during receiving inspection or found to be deficient as a e
l result of independent testing is to be clearly identified, segregated l
l l
l l
l 1
1 I
(')
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TOPICAL REPORT IREV.
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l l SECTION:
7.0 CONTROL OF PURCHASED lPAGE 7-6 l
l L
l MATERIAL, EQUIPMENT AND SERVICES I
l l
l l
1
d i
I l
l T
2 i: from acceptable items and dispositioned per plant procedures and as I
.. (] '
g. described in Section 15 of this manual.
l
~l i
17.6-SPARE PARIS I
f I
f l
Spare parts are to be purchased to the original design requirements or to
~
l those.specified by a properly reviewed and approved revision to the l
,_n
-gl design requirements.
The applicable quality assurance requirements and
-l-documentation requirements for spare parts are to be included in the l
1 I
l
- 7. 7 STORAGE I
I I
Material and equipment are-to be handled and stored as described in plant l
- l. proceoures and Section 13 of this manual.
I I
I l-I
.1 -
1 I
I l~
l Jet i
I U-
>l I
l I
I I
i l
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1 l
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1 l
I l
.I l
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I
. I I
a~
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l A
I TOPICAL REPORT IREv.
6 l
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P I
lDATE 5/30/84 l
l 1 SECTION:
/. 0 CONTROL Of PURCilASLD lPAGE 7-7 I
I L
I MATERIAL, [QtilPMENI AND SERVICE 5 l
1 1
I I
I
h l
I I
l
-l' 8.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS I
l q
I I
l
~'
I 8.1 SCOPE l
l l
l l
l 8.1.1 1
l i
I I
l. Measures.for the identification and control of materials. (including l
lconsumables),partsandcomponents,includingpartiallyfabricated l
l subassemblies,.are_to be established within LRGO and plant procedures.
l lTheseproceduresaretorelateanitemofproduction(batch, component, I
part, etc.) at any stage, from initial receipt through fabrication, I
l installation,repairormodificationtoanapplicabledrawing, l
l specification, or other pertinent technical documents.
These measures I
are to assure that only correct and accepted items are used and I
installed.
I l
l I
I l
8.1.2 I
l I
I I
p, 1
Methods for the traceability of materials, parts and components to l
U specific inspection and test records, when required by codes, standards, l
l specifications or procurement documents, are to be established within I
I g
LRGO and plant procedures and maintained throughout the life or l
l consumption of the item.
l I
I I
I l
8.2 IDENTIFICATION I
I I
I I
l 8.2.1 l
l I
l l
l Materials, parts and components are to be identified by the vendor in I
accordance with the applicable design standards, codes and/or 1
instructions specified in the procurement documents.
l I
1 l
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1 I
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1 l
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8.0 IDENTIFICATION AND CONTROL IPAGE 8-1 l
l L
l OF MATERIALS, PARTS AND COMPONENTS I l
I i
l 1
i l
I i
l 8.2.2 I
l l
^'C'
.I l
l l
Materials, parts and components are to be identified and/or tagged at the l
I plant in accordance with applicable plant procedures.
These tags I
l I
l identify the status of and provide traceability to the item throughout l
I storage and release to installation.
I I
i I
I I
8.2.3 I
I I
I I
I l
Identification of materials, parts and components is accomplished by I
l l
either marking or tagging on the item or through records traceable to the l
I item.
I 1
I I
I I
8.2.3.1 1
l l
I l
l Physical identification is to be used to the maximum extent possible.
I I
I l
Where physical identification is either impractical or insufficient, l
physical separation, procedural controls or other appropriate means are f7 l
to be employed in accordance with plant procedures.
l Cl
-l l
l 1
l 8.2.3.2 l
1 1
I I
l When identification markings are employed, the markings are to be clear, l
I unambiguous and indelible, and applied in such a manner as not to affect I
I I
l the integrity or function of the item.
Markings are also to be l
transferred to each piece of material (plate, barstock, tubing, etc.)
l when subdivided.
Large quantities of small items, may be identified by l
I applying markings or tags to their shipping packages, boxes or other l
suitable containers.
l l
1 1
I I
I I
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TOPICAL REPORT lREV.
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l 1 SECTION:
8.0 IDENTIFICATION AND CONTROL lPAGE 8-2 l
l' L
l OF MATERIALS, PARTS AND COMPONENTS l l
l l
l l
i l
I l
l-8.2.3.3 l
i l
g i
f I
s l
l Identification markings are to be recorded on records or as-built l
documents if current markings are to be hidden or subject to obliteration l
by surface treatment or coatings during fabrication, installation, repair l
or modifications.
I I
I 8.3 CONTROL I
I i
I l
lPlantorganizationsreceivingmaterials,partsandcomponentsareto l
l verify that they are properly identified while under their control.
l lQualityControlpersonnelthroughtheirsurveillanceandinspection l
activities assure that compliance to these requirements are being met.
l
'lQualityAssurancepersonnelthroughtheirauditactivities,alsoassure I
that materials, parts and components are being identified in accordance l
with this manual.
I I
l8.4 l
DEFECTIVE OR INCORRECT ITEMS n
i I
V I
8.4.1 I
I I
I I
Defective or incorrect materials, parts and components identified by l
l plant personnel or support groups are to be handled in accordance with i
Section 15 of this manual and plant procedures for nonconformances and
'l corrective action.
Defective or incorrect iteins are to be tagged with a l
l
" hold tag" affixed to the item or otherwise identified per plant l
procedures.
I l
l 1
I i
8.4.2.
I I
I l
I l
Defective or incorrect items are to be stored in segregated areas except l
for those items installed or which, due to their size, weight l
configuration, etc., are impractical or impossible to store in the I
designated controlled storage area.
I I
l l
f) l I
I I
l A
l TOPICAL REPORT lREV.
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l lDATE 5/30/84 l
l 1 SECTION:
8.0 IDENTIFICATION AND CONTROL IPAGE 8-3 l
l L
l OF MATERIALS, PARTS AND COMPONENTS l l
l l
l I
I.
I I
I l
tl 9.0. CONTROL"Or-SPECIAL PROCESSES l
. [D.
V l
l 9.1 SCOPE l
l-l I;
1
.l-;Special. processes are to be controlled through the use of qualified I
?
personnel and plant procedures which meet the requirements of applicable l
l ' codes, specifications, standards and other criteria stipulated in AP&L l
ll'icensingdocuments.
l l
l l ' 9. 2 GENERAL I
I-1 I
I l:9.2.1' l
I Special processes are those activities which require interim inprocess l controls in addition to final inspection to assure quality and include l
such activities as welding, nondestructive examination, heat treating, I coating, plating and chemical cleaning.
l 1
l l
I W
J 9.2.2 l
V; l
l l
1 l Technically qualified LRGO or plant personnel are to establish the l
procedural and qualification requirements for those special processes not l
l covered by existing codes or standards or where AP&L quality requirements l
s exceed the requirements of established codes or standards.
l l
9.2.3 l
.I l
The requirements for welding and nondestructive examination are to comply l
-l' with the: applicable portions of the ASME Boiler and Pressure Vessel Code l
or for structural welds, the AWS Structural Steel Code D1.1, and the l American Society of Nondestructive Testing (ASNT-TC-1A-1975 and l
supplements).
The requirements for cleaning and flushing of fluid l
ll systems are to comply to the requirements of NRC regulatory guide 1.37, l
' dated 3/16/73 unless otherwise noted in Table 1.
l
=
l.
I I
I O
I I
I l
C l
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TOPICAL REPORT lREV.
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9.0 CONTROL OF SPECIAL PROCESSES lPAGE 9-1 l
1 L
i i
l l
I I
I
r "l
l
-l l
l' 9.3 QUALIFICATION l
l l
l l
l 9.3.1 l
'l l
1 l
l Special process procedures for welding and nondestructive examinations l
laretobequalifiedpriortousetoassurecompliancetoapplicable l.. codes, standards or specifications.
These qualifications are to be l
~ documented and also made available for review to the Code Inspector for I
activities on ASME items.
l l
l 1
l l
9.3.2 l
l l
l-l l
Personnel responsible for the performance and verification of special l
processes are to be qualified and/or certified according to applicable l
codes, standards, specifications, regulatory guides and plant procedures.
l These qualifications and certifications are to be documented and made I
available for review to the Code Inspector for activities on ASME items.
l j
Personnel qualification and/or certification records for a special l
q-l process are to be regularly reviewed by the supervisor responsible for l
'J
.that special process to assure that the appropriate documents are I
l up-to-date and personnel are periodically requalified and/or recertified l
In accordance with plant procedures.
l l
I
- 9. 4 RECORDS I
l i
l I
I The results of special processes are to be documented, reviewed, approved
.y l
and stored in accordance with appropriate plant procedures and as l
addressed in other sections of this manual.
I I
l l
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9.0 CONTROL OF SPECIAL PROCESSES lPAGE 9-2 l
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1 I
I
l I
_l l
31
.J 9.5 VERIFICATION l
I n.--
l l
Performance of special processes in accordance with applicable codes, strudards, specifications and plant procedures is verified by Quality 1
Control personnel through their surveillance and inspection activities, I
and by Quality Assurance personnel through their audit activities.
l I
- g-g 1
I l
l I
I l-1 I
I I
I
-l l
i I
I I
-I I
I I
l I
1 1
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i l
i I
_.n i
l U
l_
I I
I
-l i
I I
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I I
I I
I I
l i
I l
l I
I I
.I I
I 1
1
,1
-3:
I I
I
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I
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I TOPICAL REPORT IREV.
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1 1 SECTION:
9.0 CONTROL OF SPECIAL PROCESSES IPAGE 9-3 1
'l L
I I
l 1
1 I
I
I I
I I
i~ 10.0 INSPECTION l
- ^
l l
( ;-
1 l
l 10.1 SCOPE l
l I
l l
l Inspections relating to normal operating activities and inspections l
relating to operating activities comparable in nature and extent to those
.l occurring during initial plant design and construction are to be I
controlled to assure that inspections are performed in accordance with l applicable design documents, codes, standards, specifications and l
procedures.
Inspection activities are to be in accordance with l Regulatory Guide 1.33, Rev. 2 (2/78), unless otherwise noted in Table 1.
I l
l I
I i
10.2 GENERAL l
l l
1 I
i 10.2.1 l
1 1
I I
l Inspection activities relating to normal operating activities l
(Operational Inspections) include:
l l
l 1)
Work functions associated with normal operation of the plant; l
2)
Routine maintenance; I
,I 3)
Technical services routinely assigned to the onsite operating l
organization; and l
4)
Non-routine maintenance activities and minor modifications made l
by the onsite operating organization that are not comparable in l
nature and extent to related activities accurring during l
l initial plant design and construction.
I l
I l
l l
10.2.2 l
l l
1 l
l Inspection activities relating to operating activities comparable in l
nature and extent to related activities occurring during design and l construction (Construction Inspections) include:
l I
I l
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I o) 1 l
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10.0 INSPECTION lPAGE 10-1 l
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l l
l l
l 1
l L
I l
I 1
.l 1)
Non routine maintenance, except as noted in paragraph 10.2.1; l
l q
and i
i I
I l
2)
Modifications, except as noted in paragraph 10.2.1.
1 l
1 I
l l
The following Regulatory Guides are to be applied, as applicable, in l
determining the basis for required construction inspections:
R.G. 1.30, l
Rev. 0 (4/76); R.G. 1.38, Rev. 2 (5/77); R.G. 1.39, Rev. 2 (9/77);
l lR.G.1.37,Rev.0(3/73);R.G.1.94,Rev. 1 (4/76); and R.G. 1.116, l
l Rev. 0-R (7/76).
l l
l
-l 10.2.3 l
1 l
I 1
l l
Personnel performing inspection activities to verify quality are to be l
lqualifiedasstatedinSection2ofthismanual.
When inspection I
techniques require specialized qualifications or skills, personnel l
performing the inspection are to meet applicable licensing requirements, l
l codes'and standards appropriate to the discipline involved.
i i
l i
I n
l 10.3 CONTROL OF INSPECTIONS I
L) l I
I I
l 10.3.1 I
I I
I I
l Inspections are to be performed in accordance with approved written l
procedures, which set forth the requirements and acceptance limits and l
specify the inspection responsibilities.
If inspections require detailed l
written procedures to perform the task, the procedures are to contain, as l
a minimum, the following:
I 1
l l
l l
1)
Qualitative and/or quantitative acceptance criteria; i
2)
Prerequisites for performing the inspection and any limiting l
l conditions; l
l I
i 1
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I I
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1 I
I I
O l
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l C'
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10.0 INSPECTION lPAGE 10-2 l
l t
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1 I
l
=
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1 l-
- ~
l' 3)
-Identification of any special equipment and tools required to l
- f]
perform the inspection (when accuracy = requirements for 1
inspections exceed the accuracy of normally available process l
.l-or_ measuring and test equipment, such additional accuracy l
l requirements are to be specified within those inspection I
procedures);
i 14)
A step-by-step description of the method of inspection, l
examination,. measurement or test to be performed; and
.I 5)
Identification of those inspection results to be documented.
l Inspection forms or checklists are to be used as an aid in l
l-documenting ~the inspection activity to assure quality l
l requirements have been met.
l l
10.3,2 l
~l I
lOperationalinspectionsaretobeperformedbyqualifiedi.ndividuals l
l other than those who performed or directly supervised the activity being l
l inspected.
Construction inspections are to'be performed by qualified l
A l
individuals other than those who performed or directly supervised the l
Y
.lactivitybeinginspectedanddonotreportdirectlytotheimmediate l
l supervisors who are responsible for the activity being inspected.
l
-l l
i I
l 10.3.2.1 l
I I
.I I
l Operational inspections may be performed by second-line supervisory l
lpersonnelorbyotherqualifiedpersonnelnotassignedfirst-line l
-l. supervisory responsibility for conduct of the work.
l l
l l
l l
10.3.2.2 l
l l
l I
l Construction inspections are to be conducted in a manner similar to that l
lassociatedwithconstructionphaseactivitiesinaccordancewith l applicable plant procedures.
1 I
I I
I I
l 1
I
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TOPICAL REPORT lREV.
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10.0 INSPECTION IPAGE 10-3 l
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1 l
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l l
1
I i
l10.3.2.3 l
l 73
\\
)
l l
l l
If individuals performing inspections are not part of the Quality l
Assurance or Quality Control organizations, the inspection procedures.
l personnel qualification criteria, and independence from undue pressure l
such as cost and schedule are to be reviewed and found acceptable by the I
l responsible Quality Assurance or Quality Control organization prior to l
I initiation of the activity.
I I
I l
I l
10.3.3 I
I l
I I
If an inspection determined to be required is impossible or l
disadvantageous, indirect control by monitoring processing methods, l
equipment and personnel is to be provided to verify conformance with l
applicable documented instructions, procedures and drawings.
Both l
inspection and process monitoring are to be provided when control is I
l inadequate without both.
l l
l 1
I n
l 10.4 INSPECTION POINTS l
.)
l
~
l l
l l
10.4.1 l
1 I
l-l l
Inspection hold points are established for non-routine maintenance l
procedures and design change packages (DCPs) by Plant Engineering and l
l reviewed by the Plant Quality Control group for concurrence and possible l
assignment of additional inspection hold points to further assure I
l conformance with applicable instructions, procedures, drawings and l
related documents or to meet appropriate cude and regulatory
,I l
requirements.
Inspection hold points for work functions associated with I
activities other than non-routine maintenance and DCPs, are established l
by the originating department, by Quality Control or other responsible l
individuals.
I I
l l
I I
l l
I I
I C]/
(
l l
l l
l A
I TOPICAL REPORT lREV.
6 l
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l lDATE 5/30/84 l
l l SECTION:
10.0 INSPECTION lPAGE 10-4 l
l L
l-I l
l l
l I
s I
I
'l I
'l :10,4,f l
J, -;)
~
l l
l l
l Inspection hold points are inserted in procedures based upon safety l
' significance, complexity of the item or activity, degree of
'l standardization of the item or activity, past performance of the item or l
lactivitu, procurement frequency, anc' the ability to verify quality by l jobsite testing.
l 1
I i 10.4.3 l
l l
l l
l Inspection responsibilities, requirements, information and acceptance l
lcriteriafortheworkactivityaretobeidentifiedinappropriate, l
l approved plant documents (e.g. procedures, checklists, ett..)
l I
I I
I i 10.4.4 l
l l
1 l
I For work involving the modification, repair, replacement or in-service l
linspectionofASMECodematerials,partsandcomponents,thework l
.n l packages are to be made available to the Code Inspector prior to l
b commencing work for his review and assignment of inspection hold points.
l
-i.The department responsible for the work activity is responsible for l
notifying the Code Inspector when the hold point is reached.
Work is not I to proceed past a Code Inspector's inspection hold point until signed or l
lwaivedbytheCodeInspector.
l l -
l l10.5 DOCUMENTATION l
l l
c l10.5.1 l
l 1
' Inspections and process monitoring activities are to be performed and the l
l results documented in accordance with approved procedures or l
l instructions. Records are to:
provide objective evidence that the
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10.0 INSPECTION lPAGE 10-5 l
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inspections and monitoring activities were performed in compliance with l
s p}
procedures, 4nstructions or drawings to verify design requirements; show
\\
l compliance with acceptance criteria or identify the cause of rejected l
k items;andidentifhtheappropriateinspectionpersonnelapprovingthe N
-1 results.
l s
t
.1 10.5.2 l
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l Records are to be maintained in accordance with plant procedures and l
l'Section17ofthismanual. Inspection results on ASME code items are l available to the Code Inspector for his review.
l 1
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10.5.3 l
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l The results of all inspection and monitoring activities are periodically l
levaluatedperplantproceduresandtheresultsdocumentedtodetermine l
l whether the individual inspection programs demon:,trate that the plant can l
lbeoperatedsafelyandasdesigned.
l p
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l10.6NONCONFORMANCES l
L' l
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I g
Noncomforming items,'found as a result of inspection and monitoring t
g ei activities are identified, segregated and dispositioned in accordance l
l with plant procedur'Ys, and Section 15 of this manual.
l Rework, repair or l
replacement performed after completion of inspections are to require l
l I
g reinspection to the extent necessary to determine acceptability to l
established criteria. w I
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10.0 INSPECTION lPAGE 10-6 l
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11.0 TEST CONTROL l
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l 11.1 SCOPE l
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l l A test program is to be established to assure that testing required to I
demonstrate that an item will perform satisfactorily in service is l
l identified, documented, and performed in accordance with written test I
procedures.
These procedures are to incorporate or reference the I
requirements and acceptance criteria contained in applicable codes, I
standards and specifications and in the licensing documents.
These l
activities include testing during the operational phases of the plant and I
those tests required as a result of modifications, repairs or l
l maintenance.
These activities are also to comply with the applicable I
lprovisionsofRegulatoryGuides1.33,Rev.2,unlessotherwisenotedin i
Table 1, and with the applicable sections of the ASME Boiler and Pressure l
lVesselCodeforASMEdesignateditems.
l 1
l l11.2 PROCEDURES l
l l
l11.2.1 l
l l
Written procedures / instructions are to be prepared to describe the l
l requirements for conduct of the testing activities.
These procedures /
I instructions are to contain or reference the information required in l
Section 5 of this manual and in the applicable Regulatory Guides l
lpertainingtoQualityAssurancerequirementsfortestingactivities.
l l
l l11.2.2 l
L.
I l
Test procedures / instructions and revisions thereto are to be subject to l
the same review and approval process as outlined in Section 5 of this l
l manual.
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11.0 TEST CONTROL lPAGE 11-1 l
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11.3 TEST CONTROLS I
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'>jl 11.3.1 1
' 1 l
I l
l Tests relating to plant start up following a unit shut down or fuel l
lloadingareiobeconductedperwrittenprocedures/instructionsinorder l
1 to evaluate plant performance as the start-up progresses.
Initial l
I I
s'.' art-up' test programs are to be planned to permit safe fuel loading and I
l y
s l
start-up, to increase power in safe increments and to perform major l
testing at specified power plateaus.
l 3
I l
11.3.2.
l 1
I l.Surveillancetestsduringtheoperationalphaseoftheplantaretobe l
l^
conducted per written procedures / instructions to assure that failures or l
lsubstandardperformancesdonotremainundetectedandthattherequired l
l operability is maintained to ensure they will continue to operate, I
lkeepinsparameterswithinnormalbounds,orwillacttoputtheplantin l
.,,m l
a safe condition if they exceed normal bounds.
I
()
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i 11.3.2.1 l
l l
l l
l Mandatory inplant surveillance tests and inspections required to assure l
loperationwithinthelimitingconditionsofoperationareidentifiedin I
the-Technical Specifications applicable to each unit at the plant.
To l
ensure that the required tests are performed as scheduld within the I
specified time interval, surveillance procedures are established and l
. maie'ained for mandatory surveillances identified in the Technical l
Specifications.
These procedures are to specify the component or system, l
.l type of surveillance activity, frequency of activity and the cognizant 1 -individual responsible for completion of the surveillance activity.
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11.0 TEST CONTROL lPAGE 11-2 l
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11.3.2.2 I
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Inservice inspections reouired to meet the requirements of ASME Boiler i
landPressureVesselCode,SectionXI,aretobeidentifiedinthe i
In-Service Inspection (ISI) Programs applicable to each unit at the l
l plant.
Plant Engineering 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.
Plant l
l Engineering is to coordinate the implementation of the ISI plans at l
appropriate scheduled outages.
The plans are also to be made available l
l for review by the Code Inspector.
I l
I I
I l
11.3.3 I
I I
I I
l Tests following plant modifications, repairs, maintenance, or significant i
lchangesinoperatingprocedures,aretobeconductedtoconfirmthatthey l
l are not detrimental to the safe and efficient operation of the plant and l
that the components or systems demonstrate satisfactory performance.
l
.q l
l
'v'
- l11.3.4 l
l 1
Requirements for the given test to be performed are to be identified in I
the test procedures / instructions.
Evidence is to be available to assure I
the following minimum requirements are met:
l l
l l
a) test equipment and measuring devices are calibrated in l
l accordance with the requirements of Section 12 of this manual l
l and are functioning properly; I
b) test personnel have been qualified to perform the test in 1
accordance with the requirements of Section 2 of this manual; l
l c) appropria'e witness and hold point notifications have been I
provided; I
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11.0 TEST CONTROL lPAGE 11-3 l
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d) test perequisites completed; and I
[]
e) when accuracy requirements for tests exceed the accuracy of l
l normally available process or measuring and test equipment, I
l such additional accuracy requirements are to be specified I
within those test procedures.
I I
I I
I i
11.3.5 l
l I
i I
I Testing activities are to be subject to surveillance / inspections in l
laccordancewithSection10ofthismanual.
Testing as a result of l
l repair, modifications, replacement or scheduled inservice tests on ASME l
lCodeitemsisalsosubjecttoinspectionbytheCodeInspector.
The i assignment of inspection hold points is described in Section 10 of this l
l manual.
l l
1 11.3.6 l
l l
Test results are to be documented in accordance with the applicable l
(']
l procedures / instructions.
Test documents are to contain at least the l
lfollowing:
l 1
I l
(1) Identity of item tested.
l (2) Date of test.
l l
(3) As-found condition.
1 (4)
Identification of individuals performing test.
l l
(5) Test results.
l (6) Corrective actions performed if any.
l l
l (7) As-left condition.
l 1
I 11.3.7 I
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lTestresultsaretobeevaluatedbyresponsibleplantpersonnelperplant I procedures to assure that test objectives and inspection requirements l
1 1
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11.0 TEST CONTROL lPAGE 11-4 I
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l have been satisified.
Non-conforming conditions, are to be identified l
I I
u landcontrolledinaccordancewithSection15ofthismanual.
l 7
l-11.4 RECORDS l
-l i
Test results are to provide objective evidence that the testing was I performed in compliance with approved procedures.
Test records are to be I
maintained and transmitted to the plant Document Control Center for l
l retention in accordance with Section 17 of this manual.
I I
I l
l l 11.5 TEST STATUS I
l l
l 1
I Inspection and test status is to be controlled in accordance with the l
lprovisionsofSection14ofthismanual.
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11.0 TEST CONTROL IPAGE 11-5 I
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i 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT l
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I 12.1 SCOPE I
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12.1.1 1
1 1
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1 A program is to be established to assure that devices used for I
' measurements, tests and calibrations are identified, controlled and
,I l
1 calibrated against reference standards to assure that accuracy is I
maintained within the limits specified by the inspection or test I
requirements.
Control of measuring and test equipment is to comply with I
the applicable provisions of Regulatory Guide 1.33, rev. 2, pertaining to I
measuring and test equipment, unless otherwise noted in Table 1.
1 I
I i
l l
12.1.2 I
I I
I I
I This section does not apply to rulers, tape measures, levels or other l
lsuchdeviceswherenormalcommercialpracticesprovideadequateaccuracy.
n l
l l12.2 RESPONSIBILITIES l
l 1
12.2.1 I
g I
l I
The cognizant Superintendents / group Supervisors it the plant are y
I responsible for establishing and maintaining lists of measuring and test i
equipment under their control that require periodic calibration and for j
the calibration of this equipment, as assigned within plant procedures.
I l
l I
I i
12.2.2 l
l l
L l
I I
The cognizant Supervisor is responsible for identifying measuring and l
ltestequipmentrequiredfortheactivityandassuresthatthedevicesare l
.I used only by qualified personnel.
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12.0 CONTROL OF MEASURING IPAGE 12-1 I
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I AND TEST EQUIPMENT I
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o
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-l 12.2.3 l
.I D-,'
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1
'l Plant personnel are to be responsible for utilizing only properly 1
fidentifiedandcalibratedmeasuringandtestequipmentwhenperforming l
+
l ~ inspections and tests for record.
I
'l I
l l
l 12.2.4' l
l l
l l
l.The Manager, Nuclear Quality Control and his staff are responsible for I
monitoring test equipment control and use in order to verify compliance I
with the program.
1 I
I I
l l' 12.3 GENERAL I
I l
l l
I 12.3.1 l
l l
l l
' I -Calibration procedures are to be established for each type of measuring l
and test equipment.
These prv.edures are to conform to recognized codes l
[
l and standards and to local, state and federal regulations, and are to be I
lreferencedonthecalibrationreports.
l
.I i
.l12.3.2 l
.I l
Measuring and test equipment'is to be properly controlled, calibrated and
.I adjusted at specific intervals or prior to use to assure the necessary 1
accuracy of calibrated. equipment.
Calibration intervals are to be based I
upon the type of equipment, manufacturer's recommendations, stability and 1
- reliability characteristics, required accuracies, use and other
- 1.
conditions affecting calibration.
l I
I I
I l
12.3.3 I
I l- ' Reference standards used in the calibration of measuring and test i
^
equipment are to be traceable to the National Bureau of Standards, or if g
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12.0 CONTROL OF MEASURING lPAGE 12-2 l
ll L
1 AND TEST EQUIPMENT l
l 1
I I
l
e.
I I
I l
l nonexistent, to accepted industry or AP&L standards.
Reference standards l
(~}
are to have an accuracy at least four times that of the measuring and I
test equipment.
In any instance where the four times criteria is unable l
to be met, standards are to have an accuracy level, acceptable I
calibration range, and precision equal to or better than those required l
l for the ranges affected by the calibration.
Accuracies less than four l
times will be acceptable when warranted by statistical analysis or l
llimitedbythestate-of-the-artasauthorizedbyresponsiblemanagement.
l l
Reference standards are to be maintained in an environment with l
temperature, humidity and cleanliness controls compatible with l
l maintaining accuracy and operating characteristics of the standards.
l l
l l
l l
12,3.4 I
l i
1 l
l When measuring and test equipment are found to be out of calibration, an l
levaluationofthevalidityofpreviousinspectionortestresultsandthe l
l acceptability of items previously inspected or tested is to be made and l
ldocumentedbywrittenreportinaccordancewithplantprocedures.
If any o
i piece of measuring and test equipment is consistently found to be out of I
i I
I
's g
calibration, it is to be repaired or replaced.
,I I
I l12.3.5 l
l 1
- R3 calibration per plant procedures is to be performed when the accuracy l
l of either installed or calibrated equipment is questionable.
1 I
I l
I i
12.4 EQUIPMENT IDENTIFICATION I
I I
I I
i 12.4.1 I
I I
I I
l The measuring and test equipment list is to contain sufficient l
information to uniquely identify each iten listed and is to include as a l
minimum, calibration intervals, tolerances and storage locations.
The l
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12.0 CONTROL OF MEASURING IPAGE 12-3 l
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l AND TEST EQUIPMENT l
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- ~ - --.
1 I
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_l list is also to it'entify the group responsible for the control of each l
I N
item.
I
-$(.].
l 12.4.2 l
l lEachitemlistedonthemeasuringandtestequipmentlististobe l
l tagged, labeled or otherwise identified per plant procedures in such a l
lmannerthatclearlyidentifiestheequipmentanditscalibrationstatus I
and provides traceability to the calibration records.
I 1.
I I
I i
12.4.3 I
I I
I l
l Measuring and test equipment found to oe out of calibration is to be 1
l tagged'andsegregatedfromacceptableequipmentinaccordancewithplant l
l procedures until repaired and recalibrated.
I I
I I
l l
12.5 RECORDS l
I l
1 I
o l
Calibration documentation is to be maintained to verify calibration I
status, condition, accuracy and out of tolerance trends of the equipment.
l l
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12.0 CONTROL OF MEASURING IPAGE 12-4 1
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I 13.0 HANDLING STORAGE AND SHIPPING l
i I
m
)
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U l
13.1 SCOPE I
I I
I I
l Activities for the handling, storage and shipping, including cleaning, l
packaging and preservation of materials and equipment are to be performed I
in accordance with established instructions, procedures or drawings, to i
prevent damage, deterioration or loss of the item.
Activities are to 1-comply with the provisions of Regulatory Guide 1.38 rev. 2 unless l
l otherwise noted in Table 1.
1 l
l13.2 GENERAL l
l l
l13.2.1
,I I
I Instructions for preservation are to be provided for items subject to I
deterioration or damage through exposure to air, moisture, or other l
environments during fabrication, processing, assembly, and interim l
I storage periods.
Items are to be cleaned, preserved and packaged as I
~l required to preclude deterioration and prevent damage. When maintenance I
of specific internal or external environments are necessary, they are to l
be included in special packaging instructions and maintenance procedures.
I I
.13.2.2 I
g i
I lProcurementdocumentsassurethatanyspecialcleaning, preserving, l; handling, packaging or shipping requirements for purchased material or i
equipment are taken into account.
I y
.I i
I l
13.2.3 l
1 fForcritical, sensitive,perishableorhighvaluearticles, I
recommendations for their handling, storage, packaging, shipping and I
. reservation are to be requested from the supplier per the procurement p
i I
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13.0 HANbLING, STORAGE AND lPAGE 13-1 l
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-L-I SHIPP!NG l
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I
d i
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l l. documents and furnished to the plant prior to or upon receipt of the item l
l at the plant.
I I
13.3 S' HIPPING CONTROLS I
- l l
113.3.1-l
'l I
. Shipping requirements are to be specified in the procurement documents.
.l Suppliers compliance to these requirements are to include controls to I
assure.that items are complete and assembled as required; items have been l preserved and packaged in accordance with the procurement documents; I
items h' ave been marked and identified in accordans with specifications
- l. and procurement documents; items have been loadec for shipment in sucn a l
~
- manner as to prevent damage; and required documentation is complete and l
fu'rnished in accordance with the procurement documents.
l l
l
'l l
l 13.3.2-l
.I' I
l' I
l Special nuclear material and sources are to be shipped and stored as l
'specified in the AP&L operating license and other_ appropriate regulatory l
i documents.'
The Health Physics Supervisor is responsible for assuring l
lthatradioactivesourcesand'instrumentscontainingradioactivesources l
l are' shipped, stored and handled per these requirements and plant l
_ procedures.
The Nuclear Support Supervisor is responsible for assuring l-that special nuclear material (SNM), as defined.in plant procedures, are l
. shipped, stored and handled per these requirements and plant procedures.
l
.l l
l:
l 13.4 RECEIVING v
l l
l 13.'4.1 l
l Materials and equipment are to be received at the plant per plant l
1 pracedures and subjacted to a receipt inspection in accordance with i
Section 7 of this manual. As part of the inspection activity, received l
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13.0 HANDLING, STORAGE AND IPAGE 13-2 l
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l SHIPPING l
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materials and equipment are to be inspected for damage, deterioration, I
(].
lcleanlinessandproperidentificationandmarkingsperplantprocedures i
for receipt inspection.
I I
I I
I l
13.4.2 l
l l
l l
l Results of the receiving inspection and disposition of the material or l
lequipmentaretobedocumentedonreceivinginspectionrecords.
I Nonconforming items are to be handled in accordance with plant procedures I
and Section 15 of this manual.
I I
l13.5STORAGECONTROLS l
1 l
l13.5.1 l
l l
lMaterialsandequipmentwhichhavecompletedthereceivingprocessareto l
l be stored. based on the classification level of storage specified on the I
procurement documents or related design documents.
O l
l l
13.5.2 I
V I
l l
I lStoragecontrolproceduresaretobeestablishedwhichinclude,asa l ' minimum, provisions for the following: controlled access and usage of I
lthestoragearea;cleanlinessandgoodhousekeepingcontrols; fire I
protection; protection from environmental hazards; segregation of I
hazardous materials; and control of those items which have a specified 1. shelf life.
l l
l I
I I
i 13.5.3 I
I I
l I
l l
Only items which have completed the receiving process are to be placed in I
il a controlled storage area.
Records of the items' location are to be l
provided-by the Materials Management Supervisor (see paragraph 13.3.2 for l
l control of radioactive sources and SNM) to identify those items currently l
l l
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13.0 HANDLING, STORAGE AND IPAGE 13-3 l
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I SHIPPING I
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I
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1 I
l.in storage and to facilitate inspection and maintenance planning.
l
' ')
Issuance of iteras from storage for installation or use are to be
~^
l documented and controlled in accordance with plant procedures.
l
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l l
l 13.5.4 I
I l
.I I
I Items identified as. requiring maintenance during storage are to be l
maintained in accordance with a documented maintenance program.
I I
13.5.5 l
l Storage areas are to be monitored by individuals responsible for the l
storage areas so that the integrity and security of stored items is l
effectively maintained.
Inspections and examinations under the control
-l of the Manager, Nuclear Quality Control are to be performed and I
documented on a periodic basis to assure that the integrity of the items l
l and their containers are being maintained.
Periodic audits under the l
control of the Quality Assurance Manager are also performed to assure I
compliance to storage requirements.
l
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I l
l 13.6 HANDLING CONTROLS l
l l
l l
l 13.6.1 l
1 I
I I
l Special handling requirem'nts are to be specified in the procurement l
ldocumentsandplantprocedurestoprotectthequalityofitems I
susceptable 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
l l
l l
13.6.2 l
l l
l.
I I
Sp cial handling tools and equipment are to be inspected and tested at I
specific times in accordance with written procedures to verify that the i
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13.0 HANDLING, STORAGE AND lPAGE 13-4 l
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i SHIPPING l
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I handling tools and equipment are adequately maintained.
Inspection and I
(~Y
-test status of these handling tools and equipment are to be controlled in M
l accordance with the applicable sections of this manual.
I I
I I
I I
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13.0 HANDLING, STORAGE AND IPAGE 13-5 I
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14.0 INSPECTION, TEST AND OPERATING STATUS I
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14.1 SCOPE I
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l 14.1.1 l
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l The removal from service, inprocess status and return to service of I
l equipment,componentsandsystemsformaintenance, modifications, repair, 1
test or inspection is to be controlled per established plant procedures.
l These controls are to assure that plant personnel are aware of equipment, l
l structure or system conditions and to prevert their inadvertent use l
lunlessclearedbyoperationpersonnel.
l 1
l l14.1.2 l
l 1
' Maintenance activities are to be performed in accordance with an l
l established maintenance program to assure that equipment, systems and l
lstructuresaremaintainedinaconditionwhichallowsthemtoperform rN l
their intended function.
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i 14.2 EQUIPMENT CONTROL l
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l 14.2.1 I
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l Prior to removal of equipment, components or systems from service for I
maintenance, modification, repair, test or inspection activities, l
j i
permission is to be received and documented from the Shift Supervisor.
l The Shift. Supervisor is to assure that the item can be released without i
l affecting plant safety.
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14.0 INSPECTION, TEST AND lPAGE 14-1 l
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I OPERATING STATUS l
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l 14.2.2 l
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l The status of equipment, components and systems during these activities I
g is to be identified in accordance with plant procedures / instructions, I
which contain, as a minimum, the following:
I l
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1) methods for control of equipment to maintain personnel and I
reactor safety and to avoid unauthorized operation of equipment 1
or systems.
I I
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i 1
2) the use of markings or other suitable means to indicate the I
status of activities being performed upon individual items.
l l
Suitable means are to include identification numbers which are I
traceable to records or the status of these activities.
l l
I l
g 3) provisions for the identification of items which have I
satisfactorily passed the required activities.
In cases where l
l required documentary evidence is not available, the associated l
eq I
equipment or system is to be considered nonconforming and I
l
' handled in accordance with Section 15 of this manual.
l
/
1 I
4)
, provisions for independent verifications to casure that I
necessary measures (locking or tagging) to secure and identify I
equipment or systems in a controlled status, have been I
implemented correctly.
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-l_
14.2.3 I
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l When entry into a closed system is required, control measures are to be I
established to prevent entry of extraneous material and to assure that I
foreign material is removed before the system is reclosed.
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14.0 INSPECTION, TEST AND lPAGE 14-2 l
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OPERATING STATUS I
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i 14.2.4 i
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During maintenance or modification activities, certain portions of I
}I systems, as identified in plant procedures, may be subject to potential l
1 contamination with foreign materials.
To prevent such contamination, I
control measures, including measures for access control, are to be l
l established.
Immediately prior to closure, an inspection is to be I
conducted to assure cleanness and the result of such inspection is to be I_ documented.
l I
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.14.2.5 l
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1 I
I If temporary modifications (such as temporary bypass lines, electrical 1
g jumpers, lifted electrical leads and temporary trip point ' settings) are i
required for a system or piece of equipment, they are to be performed in I
accordance with plant procedures.
A status log is to be maintained by l
l the Shift Supervisor, identifying the current status of such temporary 1
modifications.
Temporary modifications are to be verified by individuals
/~ 3 l
independent of the group performing the activity and documented to assure I
the required actions are taken to return the equipment or system to its l
l original operating configuration and status.
I I
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14.2.6 I
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I I
l When equipment or a system is properly identified as being ready to be 1
1 I
returned to service, the appropriate Shift Supervisor is notified and I
initiates ' the proper operation procedures.
Testing of the equipment or l
lsystemforfunctionalacceptabilityistobeinaccordancewith l
Section 11 of this manual and documented to verify current status of the I
item.
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14.0 INSPECTION, TFST AND IPAGE 14-3 l
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l OPERAllNG STA105 l
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l 14.2.7 l
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l Equipment, structures and systems found to be nonconforming as a result l
of an activity are to be handled in accordance with plant procedures and l
Section 15 of this manual.
l l
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14.3 MAINTENANCE CONTROL l
l l
l 1
l 14.3.1 l
l l
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l In addition to the requirements and controls identified in paragraph 14.2 l
of this section, a maintenance program is to be planned and scheduled l
l through the Maintenance Manager to assure that the safety of the plant is l
not compromised nor the Technical Specifications violated.
Maintenance l
activities are to be performed per plant procedures and instructions and l
I l
conducted in a manner to assure quality at least equivalent to that l
specified in the design documents, material specifications and inspection l
requirements.
As experience is gained in operation of the plant, routine l
. (] -
I maintenance may be altered to improve equipment performance and l
procedures for repair of equipment are to be improved as directed by the l
l Maintenance Manager.
I I
I I
I l
14.3.2.
l I
I I
I l
A preventive maintenance program,-including procedures and instructions l
for systems, structures and components, is to be established and l
l maintained under the Maintenance Manager which prescribes the frequency l
and type of mainteaance to be performed in order to preclude equipment l
malfunctions.
The program is to be implemented by qualified maintenance l
personnel in accordance with written procedures and instructions which l
l specify the work activities, acceptance requirements and the control l
. measures to assure adequate quality.
When equipment malfunctions occur, l
l the cause is to be promptly determined, evaluated and recorded per plant l
l procedures and Section 16 of this manual.
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14.0 INSPECTION, TEST AND lPAGE 14-4 l
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OPERATING STATUS l
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I 14.4 OVERALL PLANT STATUS l
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l 14.4.1 I
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The Shift Supervisor is provided sufficient knowledge of the overall l
l plant'statusofequipment,structuresandsystemstocontroloperationof I
the plant in a safe manner.
The Shift Operators are to maintain a ready l
lreferenceofplantsystems,equipmentandcomponentsalignments,aswell l
l as a status board summary of their conditions.
I I
I I
I i
14.4.2 I
I I
I I
l -The turnover of duties to personnel on succeeding shifts is conducted in 1
accordance with approved plant procedures.
These procedures include I
documented turnover action appropriate to the duty station acknowledging I
..the status of the nuclear power plant, its structures, systems and I
components (including design changes / modifications which may affect the I
'. performance of their duties) and transfer of authority.
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14.0 INSPECTION, TEST AND IPAGE 14-5 l
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I OPERATING STATUS l
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l 15.0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS l
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l C)
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l 15.1 SCOPE I
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l Nonconforming items are to include materials, parts, components, I
l processes,documentsandasapplicable, services (includingcomputer l
l ' codes) that do not conform to applicable regulations, codes, standards, I
specifications, drawings or licensing documents.
Nonconforming items are l
l to be controlled in accordance with approved procedures to prevent their l
inadvertant use or installation.
These procedures are to contain I
measures to assure the prompt identification and notification, I
l documentation, segregation,technicalreview,dispositionand I
l verification of a nonconforming itea.
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15.2 GENERAL i
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I I
i 15.2.1 1
I I
I I
/'~')
l It is the responsibility of each individual to identify a nonconforming I
condition, whether related to a product, process or documentation, and to l
report it to their cognizant supervisor for review and concurrence.
The I
initiator.is to document the nonconformance on a Nonconformance Report I
(NCR) unless the nonconformance is determined to be a technical I
specification violation and/or reportable to the NRC.
See paragraph 15.3 l
1 for reportable nonconformances.
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15.2.2 l
1 I
l-I l
Nonconforming items are to be tagged with a hold tag, or otherwise l
identified per plant procedures, to prevent inadvertant use or 1-installation of the item.
Nonconforming items are to be segregated from I
acceptable items unless they are currently installed or_ their size, I
weight, configuration, etc., makes it impractical to move to a segregated i
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15.0 NONCONFORMING MATERIAL, IPAGE 15-1 l
4 l
L PARTS AND COMPONENTS I
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I I
I E
T l
l I
I l. area.
Hold tags are to remain on the item until the disposition is complete per plant procedures.
I I
l15.2.3 l
l l
Nonconformance Reports are to identify the group responsible for l
l dispositioning the nonconformance.
The assigned individual within the l
responsible group.is to evaluate the nonconformance and confer, as l
appropriate, with interfacing groups to determine its cause and l
recommended disposition.
The disposition, which may be reject, rework,
\\,
l repair or use-as-is, and the corrective action taken to prevent l
I recurrence is to be documented on the NCR.
g l
I l15.2.4 l
I l
The' initiator of the NCR and his department head are to review the i
disposition for acceptance prior to implementing corrective action.
If l
they cannot agree with the assigned individual on the disposition, the l
d l
plant General Manager is to decide.
For a repair or use-as-is l
disposition, a cognizant engineer knowledgeable in the design l
requireneents for the af fected item is also to review the NCR for l
concurrence of the disposition. Written justification for the design l
l change, repair or deviation that has been accepted is to be documented to I
denote the as-built condition and is to be made a part of the NCR.
I I
l15.2.5 l
I 1
I I
The acceptability of rework or repair of materials, parts, components, g
g l
systems and structures are to be verified by reinspecting the item as l
loriginallyinspectedorbyamethodwhichisatleastequaltothe I
original inspection method.
The rework and repair inspection records are l
to be documented and become part of the permanent records for the item.
l Upon completion of the corrective action, tte Manager, Nuclear Quality l
1 l
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15.0 NONCONFORMING MATERIAL, lPAGE 15-2 l
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l PARTS AND COMPONENTS l
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i l
l Control is to verify completion of corrective actions in accordance with I
(
lplantproceduresandifacceptable,closetheNCR.
l l
l l
15.2.6 l
l lForASMECode,SectionIII, Division 1 materials,partsandcomponents I
dispositioned repair or use-as-is, the NCR is to be subject to review and l
lconcurrencebytheCodeInspector.
I I
l l15.3REPORTABLENONCONFORMANCES l
l l
l15.3.1 l
l 1
l_NonconformingitemsorconditionswhicharereportablepertheTechnical l
l Specifications to the NRC are to be documented by the initiator and l
' forwarded to the Special Projects Manager so the appropriate report, per g
I plant procedures, can be prepared.
l I
I
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7" l
15.3.2 I
k.1' 1
I I
I l
Upon disposition of the report by the responsible group the PSC reviews 1
the report for concurrence and possible assignment of additional I
corrective actions and forwards the report to the plant General Manager l
lforfinalapproval.
l l
l l
15.3.3 l
1 The LRGO Licensing section is to be responsible for transmitting approved l
l reports to the NRC within the time period specified in the Technical 1
-Specifications and Licensing procedures.
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15.0 NONCONFORMING MATERIAL, IPAGE 15-3 l
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l PARTS AND COMPONENTS l
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l 15.4 SUPPLIER NONCONFORMANCES l
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l l-15.4.1 I
.I I
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l-Procurement documents are to contain requirements for the i
.l -vendor / contractor to identify nonconforming conditions to AP&L which 1 -violate a technical or material requirement of the procurement document i
.and which results in a disposition of repair or use-as-is.
All such I
nonconformances are to be reported to AP&L for evaluations and l
acceptance.
The vendor / contractor is to document such nonconformances on I
their applicable nonconformance report which is to be included in the 1
ljfinaldocumentationpackagesubmittedtoAPAL,inaccordancewiththe l
I i
l 1-I l :15.4.2 I
I I
I I
I.Upon receipt of items at the plant, a Quality Control Engineer is to I
review any nonconformance reports'in the documentation package to assure
/
l 'the nonconforming conditions have been properly dispositioned and i
I's '
accepted by AP&L.
l' l
l15.5 RECORDS l
l' I
-l-15.5.1-l l
l I
l Upon completion of. disposition and verification activities, the completed 1
NCR's, reports, and related documents generated to ensure proper l
g
- disposition and resolution of the nonconformance are to be forwarded to l
I and maintained by the Document Control Center.
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I 1
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15.0 NONCONFORMING MATERIAL, IPAGE 15-4 l
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I PARTS AND COMPONENTS l
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-l 15.5.2 I
.fi
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I I
The Manager, Nuclear Quality Control is to maintain and issue a monthly I
report to the plant General Manager, identifying the current status of l
l all open NCR's for management review.
I i
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15.0 NONCONFORMING MATERIAL, lPAGE 15-5 l
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16.0 CORRECTIVE ACTION l
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-16.1 SCOPE I
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l-A corrective actions system is to be established to assure that I
- conditions adverse to plant safety, such as failure, malfunctions, l
l deficiencies, deviations, defective material and equipment, abnormal l
l.occurrencesandnonconformancesarepromptlyidentifiedandcorrected.
l l
In the case of significant conditions adverse to safety, this system is l
ltoassurethatthecauseoftheconditionisdeterminedandcorrective 1
l action taken documented and reported to appropriate levels of management I
~ for independent review.
l l
l l
'16.2 GENERAL l
l l
16.2.1 l
l When deviations, deficiencies, malfunctions or other abnormal occurrences l
p l
or conditions are encountered, they are to be reported to responsible l
L '\\ /l l
l authorities for review and disposition in accordance with Section 15 of g
I this manual.
I I
I I
I i
16.2.2 I
I I
I i
l Cognizant supervisors are to review discrepancies discovered during the l
lcourseofstationoperations,andinthecaseofsignificantconditions l
l adverse to safety, initiate action to identify their cause and take I
l necessary corrective action to prevent their recurrence.
Corrective l
action measures to resolve the discrepancies and to prevent their I
I recurrence are to be documented in accordance with Section 15 of this g
I manual.
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16.0 CORRECTIVE ACTION IPAGE 16-1 l
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16.2.3 l
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l The appropriate plant department head is to review recorded l
l nor.conformances and may specify the need for additional corrective l
l action.
The plant's General Manager is to review the monthly status l
lreportsconcerning"open"nonconformancereportsandtakesappropriate I
g I
action to ensure corrective action is both prompt and prevents I
recurrence.
If the nonconformance is of a significant condition adverse l
l to safety, the plant's General Manager may request assistance from l
technical support groups at the plant and/or LRGO to evaluate the l
l nonconformance for final disposition.
l
~
l l
l' I
i 16.2.4 1
l 1
-l l
l Adverse quality or safety conditions discovered by QA or QC personnel I
during their document review, inspection, audit or surveillance l
l activities, which appear to be of a repetitive nature, are to be I
- documented on an appropriate report form in accordance with applicable QA l
O
'I and QC procedures.
l V
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l l
l 16.2.4.1 l
l I
I l
l The responsible organization to which the corrective action document is l
l addressed is to evaluate the adverse condition and document the action l
taken to resolve the condition. 'In the case of significant conditions I
adverse to safety, documentation is to include action initiated to l
determine cause and to prevent recurrence.
l I
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1
-l 16.2.4.2 l
1 I
I
-The response is to be evaluated by the initiating organization (QA or QC) l l
l to determine the adequacy and completeness of the corrective action I
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16.0 CORRECTIVE ACTION lPAGE 16-2 l
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1
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l commitments.
If the response is acceptable, the initiating organization I
/ 1 is to perform follow-up action to verify implementation of the corrective
~'
I action commitments, document their findings and when acceptable, close I
out the corrective action document.
I I
l16.2.4.3 l
l 1
If the initiating and responding organizations cannot agree upon a l
l resolution, it is to be referred to the next level of management for l
l resolution.
The General Manager at the plant and the Senior Vice l
President, Energy Supply at LRGO are to have the final decision regarding I
resolution of QC and QA initiated corrective action documents, I
respectively.
l l
1 1
I l
16.2.5 l
l l
l l
l When vendors furnish products or services that do not conform to the 1
lrequirementsoftheapplicablepurchasecontractand,intheopinionof J]
I the Manager, Nuclear Quality Control, the vendor warrants consideration I
l for reappraisal, the Manager, Nuclear Quality Control is to submit a l
vendor reappraisal request to the Manager, Quality Assurance for I
determination of action to be taken.
Results of the reappraisal, I
together with a request for specific corrective actions, are to be I
' transmitted to the vendor.
If the vendor does not improve his quality I
assurance system and products as requested, the Manager, Quality I
Assurance is to remove the vendor from the Qualified Vendor List (QVL) in I
accordance with departmental procedures.
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16.0 CORRECTIVE ACTION lPAGE 16-3 I
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16.3 SIGNIFICANT CONDITIONS l
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16.3.1 l
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l Significant conditions are to include, as a minimum, the following:
l l
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(1) Conditions that have a direct adverse affect on the safety of I
l the plant or personnel.
l (2) Conditions that have caused the uncontrolled release of I
l radioactive materials (liquid, solid, gaseous or air l
particulate) to the environs.
l l
(3) Trends indicated by nonconformances which could lead to unsafe l
l plant operations.
1 (4) Any condition the plant's General Manager considers to be of l
l major consequent.9 1
I l
l l
l 16.3.2 l
l l
l l
l When significant conditions adverse to safety are discovered, the responsible supervisor and management personnel are to evaluate the g
g I
condition and determine if it is a repc^ table occurrence.
Reportable l
loccurrencesaretobehandledasdescribedinSection15ofthismanual l l
and are to be submitted to the PSC and SRC for review.
l l
l l
l 1
16.4 VERIFICATION l
l 1
-l l
l Verification by surveillance or audit of the effective implementation of l
I corrective actions is to be periodically performed and documented by I
Quality Assurance personnel.
Audits are to be performed in accordance l
l with Section 18 of this manual.
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16.0 CORRECTIVE ACTION lPAGE 16-4 l
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17.0 QUALITY ASSURANCE RECORDS l
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l 17.1 SCOPE l
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l 17.1.1 l
1 I
1 I
I Documentation covering design, construction, procurement, fabrication, l
inspection, maintenance, nonconformance and corrective action, test and l
audit activities is to be filed and stored to provide objective evidence l
3 I
I
^
of quality-related activities and to assure the ability to reconstruct y
l significant events.
Control of records is to be in accordance with l
Regulatory Guide 1.88, Rev. 2 (10/76) unless otherwise noted in Table 1.
l l
1 j
17.1.2 I
I i-lQualityassurancerecordsaretoincludeoperatinglogs,resultsof l
Z 2
l reviews, inspections, tests, audits, material analyses; monitoring of l
=
l l
=
work performance; qualification of personnel, procedures, and equipment; p:
I historical drawings, specifications, engineering reports, calculations, l
procurement documents, calibration procedures and reports, nonconformance I
reports, corrective action reports, correspondence and related records l
9 pertinent to quality as defined in plant procedures for records l
management.
I I
I 1
I l
17.2 RESPONSIBILITY l
=
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1 I
l 17.2.1 1
1 I
I I
E l
l The Plant Administrative Manager is respor.sible for the establishment, 1
=
implementation and maintenance of the records management program to be i
l used throughout the operational life of the plant and for ensuring that l
documentation retention requirements comply with applicable technical l
specifications, codes and regulations.
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17.0 QUALITY ASSURANCE RECORDS lPAGE 17-1 1
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4
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1
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I 17.2.2 I
m f s,
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~ ! J' I
I I
AP&L personnel, other than plant staff, and outside firms that perform I
work on the plant in the areas of design, procurement, maintenance, I
modification, testing, quality assurance and special nuclear materials I
I are to provide documentation / certification records to the plant for I
subsequent storage and retention by the Plant Administrative Manager.
I I
I I
I l
17.2.3 l
l l
l l
l Quality Assurance personnel are to periodically audit quality-relat d 1
-lrecordsandrecordsfilingandstorageprocedurestoassurethatthe l
l records management program is being properly implemented.
Audits are to I
l be performed as outlined in Section 18 of this manual.
l I
l17.3DOCUMENTATIONRETENTION I
I l17.3.1 l
Lifetime Quality Assurance Records m
l17.3.1.1 l
l l
lLifetimerecordsaredefinedasthosewhichmeetoneormoreofthe i
following criteria:
I l
I I
I l
(1) Those which would be of significant value in demonstrating l
l capability for safe operation.
l l
(2) Those which would be of significant value in maintaining, I
l reworking. repairing, replacing or modifying the item.
l (3) Those which would be of significant value in determining the l
l l
cause of an accident or malfunction of an item.
l (4) Those which provide required baseline data for i. service l
l inspection.
I I
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17.0 QUALITY ASS'JRANCE RECORDS IPAGE 17-2 I
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l
l-l 1
I i
17.3.1.2 1
'~],.
l:
I
)^
'l I
l Lifetime quality-related records are to be maintained for the life of t.he l
particular item while it is installed in the plant or stored for fotore l
use as prescribed in applicable plant piecedures for document retention 1
-l an l
idisposition.
l l
.17.3.2 Non-Permanent Quality Assurance Records l
l l~17.3.2.I I
-l' l
l'Nonpermanentrecords'aredefinedasthosewhichmeetallofthe l
following criteria:
I l-1 I
I I
.(1) Those of no significant value in demonstrating capability for l
safe operation.
-l
.(2) Those of no significant value in maintaining, reworking, l
l-repairing, replacing or modifying the item.
' (~)
l (3) Those of no significant value in determining the cause of an l
l accident or malfunction of an item.
l (4) Those which do not provide baseline data for inservice l
l Inspection.
-l l
[17.3.2.2 l
l l
!g 'Non permanent records are to provide evidence that an activity was l
l-performed in accordance with applicable requirements and be ret.ained for i
specified periods as.11rected by the applicable plant procedures for i
document retention and disposition.
I i
l l
l l
17.3.3 I
I I
I I
l Categories of permanent and non permanent records to be maintained ano i
their appropriate retention periods are described in plan + procedures.
l t
,-3 I
i t)
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I I
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'A l
TOPICAL 3EPORT IFEV.
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'l 1 SECTION:
11.0 QUALITY ASSURANCE RECORDS lPAGE 17-3 I
l' L-1 I
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l-I i
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I I
l 17.3.4 l
n l
I V-1 l
l.Tne Manager, Nuclear Quality Control is responsible for receiving, I
inspecting.and authenticating such documents as directed by plant l
procedures for turnover of quality assurance documents from suppliers to I
AP&L. When approved for receipt by Quality Control, such records are to l
l be transmitted to the Plant Administrative Manager for filing and I
! storage.
I I
-l.17.4STOP. AGE l
1 l
l'17.4.1 l
l.
l lPermanentrecordsaretobemicrofilmedandstoredwithinacontrolled l l
area at the nuclear power plant per plant procedures.
A duplicate sct of
,I l
microfilm is also made and stored at a remote location.
l l
l 17.4.1.1 7
l l
i.)/ -
l l
For storage of film and other special processed records, humidity and 1. temperature controls are to be provided to maintain an environment as I
l
~
recommended by the manufacturer and plant procedures.
l l
l-17.4.1.2 l
~~
'l I
.A-list is to be prepared by the Plant Administrative Manager designating l. those personnel who have access to the storage files.
I l-1 I
I i
17.4.2 i
1
-l l
l Plant storage systems are to provide for the accurate retrieval of l
-l l
information without undue delay and be suf ficient to control and accotml.
l g
I for records removed from the storage facility.
I l-1 1
I l
l l-I M)
I
.l.
I I
-1.
A:
1-TOPICAL REPORT IREV.
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17.0-QUALITY ASSURANCE RECORDS IPAGE 17-4 l
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l l
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I I
l l
l l
l 17.5 RECORDS INDEXING AND RECEIPT CONTROL l
..n i
1 Li I
I l
17.5.1~
l l
I I
I
-- l Indexing methods and systems for quality-related records are delineated l
linplantproceduresforplantrecordsmanagement.
l l
1 l
- 17.5.2 l
l Records submitted for storage in either 1.*etime or temporary files are l
l to be subject to the following requirements for receipt control:
l l
l l
l l
(1) Establishment of a records check list designating the required l
l quality-related records.
l (2) Establishment of a system designating criteria for document I
inspection to assure that records are accurately completed, l
l legible and received in good condition.
l (3)- A file system to indicate which quality related documents have l
(]
l been received.
I K./
1 I
l I
i 17.5.2.1 1
I I
l-1 I
Implementation of receipt control requirements for storage is the l
. responsibility of the Plant Administrative Manager.
l l
1 17.6 FINAL DISPOSITION I-l lTheplantAdministrativeManagerisresponsiulefordisposalof l
1 quality-related records in accordance with. plant procedures for document I
retention and disposition, which permits periodical purging of records I
retained past their required retention date.
I l
1 l
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l-I l'
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l
,3 I
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1 l
A l
TOPICAL REPORT lREV.
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17.0 QUALITY ASSURANCE RECORDS IPAGE 17-5 I
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I
l l
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I
~l 18.0 AUDITS I
/7 l
l l
18.1 SCOPE l
1 I
i
.l l
l 18.1.1 l
l l
1 1
I
'l -A comprehensive system of planned and periodic audits are to be provided l
i
.to assure and verify compliance with all aspects of the administrative l controls and quality assurance program.
Audits are to be planned and l
. performed in accordance with' written procedures, plans and checklists and l
- l are to conform to the applicable portions of Regulatory Guides 1.144, l
- rev. 1 (9/80) and 1.146, rev. 0 (8/80), unless otherwise noted in Table l
l 1.
l l
l 1.
l 4
l-18.1.2 l
l 1
- l
=l The audit program is to include provisions to determine the compliance l
with and effectiveness of the quality assurance program in controlling l
- ll structuras, systems, components and activities in accordance with the j
-V rules set forth in the codes, standards and regulations identified in the l
l. Introduction of this manual.
l
- l l
3;-
l 1 -18.2 AUDIT PERSONNEL l
I l
-l-l l
18.2.1 1
I I
-l l
l The Quality Assurance Manager is assigned auditing responsibility within l
-this quality' program and is responsible-for the selection and assignment l of auditors.
Auditors are to be independent of any direct responsibility l
/
. for performance of the. activity which is to be audited and are not to g
l = report to a management representative who has direct responsibility for l
the activity being audited.
l l
1 l'
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l l.
I o
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i
-U-il
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-l TOPICAL REPORT lREV.
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l lDATE 5/30/84 l
l l SECTION:
18.0 AUDITS lPAGE-18-1 l
. l L
l l
l 1-1 I
I
l-1 I
I I
18.2.2 I
g-l l
(s I
i
~ ~ ~)
l Auditors assigned auditing responsibilities are to have experience and I
. training commensuate with the scope, complexity and/or special nature of l
l the activities to be audited. When audit assignments are made, I
considerations are given to special abilities, specialized technical j
l training, prior pertinent expertise, personal characteristics, education I
and capability.
If no one within the QA0 meets these prerequisites I
completely, technical specialists are to be used to assist in the 1
lauditingoftheactivity.
Technical specialists are to meet the I
requirements of paragraph 18.2.1 of this section.
I I
I I
I i
18.2.3 I
.I l
l I
I Audit personnel are provided appropriate training to assure their I
competence for performing the required audits.
Proficiency of audit l
l personnel is maintained by one or more of the following methods:
1 I
I I
I
(~N.
l (1) Regular, active participation in the audit process.
I
'l (2) Review and study of codes, standards, procedures and l
l instructions.
I I
(3) Participation in training or orientation programs.
l l
l l18.3AUDITSCHEDULE l
l l
l 1
18.3.1 I
I lAuditsaretobeperformedonaplannedandperiodicbasisinaccordance l
.I with an audit schedule.
Audit schedules are to be pr: pared at the I
beginning of each year by the QA0 and approved by the Quality Assurance l
l Manager and SRC.
l I
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I I
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I 1 SECTION:
18.0 AUDITS lPAGE 18-2 I
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I I
I
I.
l l
l l-18.3.2 l
ym, I
l q.)
l l
l Audit scheoules assure that as a minimum, the following areas are l
l audited,underthecognizanceoftheSRC,attheindicatedfrequencies l
within AP&L:
l I
I l
l l
(1) The conformance of facility operation to provisions contain,ed l
within the Technical Specifications and applicable license l
l conditions at least once per 12 months.
I (2) The performance training, qualifications, and retraining of all l
l members of the facility management and operations staff, and l
l the performance, training, and qualifications of new members of I
the entire facility staff at least once per 12 months.
l l
(3),The results of all actions taken to correct deficiencies l
l occurring in facility equipment, structure, systems or methods I
of operation that affect nuclear safety at least once per six 1
months.
(A portion of this activity is performed as a part of I
l each internal quality audit.)
l (N
l (4) The Facility Emergency Plan and implementing procedures at I
' ~'
least once per 12 months.
1 (5) The Facility Security Plan and implementing procedures at least l
l l
once per 12 months.
l
'(6) Any other area of facility operation considered appropriate by l
l' the SRC or the Nuclear Operations Vice President.
l (7) The Facility Fire Protection Program and implementing l
l procedures at least once per 24 months.
1 l
l18.3.3 l
l l
l Audits of vendor / contractor activities are to be scheduled as identified l
in Section 7, paragraph 7.3.3 of this manual.
These audits are to l
I, evaluate and verify their quality assurance program, procedures and l
l l
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i I
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l 1 SECTION:
18.0 AUDITS lPAGE 18-3 l
l L
l l
l l
l 1
i e
s l
l l
l l. activities, to assure compliance with the procurement documents, and to I
f' verify they periodically review and audit their suppliers quality l
l assurance program.
I I
I I
l 1
18.3.4 I
I l
l I
l Periodic reviews of the audit programs are to be performed by the SRC or l
their appointed management representative at least semi-annually to l
l assure that audits are being accomplished in accordance with the I
requirements of the technical specifications, this manual and Regulatory l
l Guide 1.33, rev. 2 (2/78), unless otherwise noted in Table 1.
I I
I I
I
- 1. 18.3.5 I
l l
1 l
l-Regularly scheduled audits may be supplemented, as required, to cover I
unforeseen events or changed requ.Jements.
l l
l18.4AUDITIMPLCMENTATION r~T l
l I
l 18.4.1 1
I I
. Audit plans and checklists are to be prepared by the auditor and approved l
l by the Quality Assurance Manager prior to performing the audit.
l l
Checklists'aretobeusedduringtheaudittoassurethatall l
l requirements of the activities audited are addressed during the audit and I
that those procedures and instructions issued to control the audited I
activity are adequate.
l l
l l
l l
18.4.2 I
I I
I I
l Upon completion of an audit, a written report is to be prepared which l
lincludesatleastthefollowingitems:
l l
l l
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1 h~'
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I I
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I IDATE 5/30/84 I
I I SECTION:
18.0 AUDITS IPAGE 18-4 l
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I I
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I I
I
I I
I I
l (1) Description of audit scope and date.
l I
j (2) Identification of the auditor (s).
I
/
l l
v l
(3) A summary of audit results.
l (4)' Details of nonconformances or programmatic deficiencies.
l (5) Recommendations for correcting nonconformances or improving the l
Quality Assurance Program, as appropriate.
l 1
l l18.4.3 I
l lDeficienciesidentifiedasaresultofaninternalauditaretobe l
l recorded on an Audit Finding Report (AFR) by the auditor and issued to '
l
.the department head responsible for the area audited for corrective I
action.
The department head a their assigned designee is to provide l
r prompt corrective action to the deficiencies identified and document on l
the AFR the action taken or to be taken to prevent recurrence.
l l
Appropriate follow-up including re-audits by the assigned audit grau,n is l
conducted in the deficient creas to verify proper and timely l
l implementation of corrective action commitments.
Follow-up actions are q
l to be documented on the AFR.
l Y'
I I
I l
l 18.4.4 l
l l
l l
l Audit reports pertaining to plant acthities are to be independently 1
reviewed by the PSC and the SRC to determine if additional corrective l
l actions need to be initiated to assure continued safe operation of the l
l plant.
Audit reports pertaining to LRGO activities are to be l
independently reviewed by the SRC.
In addition to these reviews, the l
audit reports are to be distributed, as a minimum, to the Nuclear l
'l Operations Vice President,' Quality Assurance Manager and appropriate l
llevelsofmanagementhavingresponsibilityintheareaauditedtoassure
-l their awareness of the findings.
l l
l l
1 l
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I l
l l
1
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A l
TOPICAL REPORT lREV.
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l lDATE 5/30/84 l
l l SECTION:
18.0 AUDITS lPAGE 18-5 l
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l 1
l
m-l l
4 l
l l '18.4.5 1
l-l
-'4. j _:
l l
'l. Audit results and findings related to external audits conducted by QA i
' ~ '
.I jersonnel are to be recorded and distributed to the Quality Assurance l
ll Manager and a designated representative of the audited organization.
l
- Deficiencies are to be recorded on an AFR, and the audited organization l
l' is to describe actions taken to correct deficiencies and prevent I
recurrence on the AFR.
Corrective actions are to be verified by QA
~l personnel and documented on the AFR.
l l
I I
l I 18.5 RECORDS l
1 I
l l
l Written internal audit reports, including checklists, AFR's and related l
_ldocumentationsupportingthefollow-upactivitiesaretobeforwardedto I the Administrative Manager for storage in accordance with Section 17 of l
l t-this manual.
External audit reports are to be maintained / stored in the I applicable vendor / contractor. file maintained by the Quality Assurance l
l' Manager.
l f
l l
l 18.6 NUCLEAR FUEL AUDITS 1
l lArkansasPower&LightCompanydelegatestoMiddleSouthServices,Inc.,
l-a' wholly owned subsidiary of Middle South Utilities, Inc., the l
l responsibility for performing those quality assurance functions necessary l
-y l to assure that its nuclear fuel is designed and fabricated in accordance l
lwithregulatoryrequirementsandacceptedcodes,standardsand
. I specifications.
The MSS Quality Assurance section monitors the design l
and fabrication of the fuel through a program of audits of the fuel l
- l-fabricator, including both design review audits and fuel fabrication l
-audits. MSS a130 conducts audits of component suppliers as deemed 1 necessary by the Manager, Qualtiy Assurance (MSS), to ensure the quality l
l~ofthefuel.
Formal audit reports are issued by MSS to document their l
l l.
I l-1 l
l
{-.
-l l
l l
I I
I A
l TOPICAL REPORT IREV.
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l l SECTION:
18.0 AUDITS lPAGE 18-6 l
l L
l l
l l
l l
l
l-1 I
I I audit activities and to identify nonconformances or other items requiring I
(
action by the fuel-fabricator.
Resolution of nonconformances or other I
items requiring action ~is verified by MSS and documented in follow-up i
reports.
The AP&L Quality Assurance Manager is on distribution for all l
I audit and follow-up reports.
I I
I I
l l
l 1
I I
I l
l I
I I
l l
l l
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.I l
l 1
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TOPICAL REPORT IREV.
6 I
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I-I SECTION:
18.0 AUDITS IPAGE 18-7 I
'l-L
-l l
l 1
1 1
I
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~
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ADMINISTRATIVE SERVICES I
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l DIRECTOR MANAGER l
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P-1 IDATE 5/30/84 l
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FIGURE 2.
AP&L CORPORATE SERVICES IPAGE F-2 l
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' OPER ATIONS M AIN TEN ANCE MANAGER MANAGER I
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M AINTEN ANCE 1
OPERATIONS OP RATl NS l
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g ELECTRICAL g
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MECHANICAL OPERATIONS M AIN TEN ANCE I
TECHNICAL SUPE RVISORS I
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l 18C iaC PLANNING &
I I
SUPERVISORS SUPERINTENDENT 8
i
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SHIFT S R.
I MAINTENANCE M AINTEN ANCE
~
l SUPERINTENDENT COORDINATOR I
I I
I l
ARKANSAS POWER S LIGHT COMPANY l
i NUCLEAR PLANT ORGANIZATION I
l l
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l TOPICAL REPORT IREV.
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/30/84 I
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FIGURE 6.
(PLANT OPERATIONS & MAIN F-6 I
l t
I l -
1 I
I 1
m-I I
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l 1
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l l
l I
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I GENERAL l
l MANAGER I
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l ENGINEERING S l
l TECNNICAL I
SUPPORT l
MANAGER I
I I
I I
I l
TECHNICAL PLANT PLANT OPERATIONS I
g ANALYSIS ANALYSIS ENGINEER #fG acesetMENT l
SUPERINTENDENT SUPERINTENDENT SUPERINTEMENT SUPENINTENIENT g
i I
i E MAGENCY PLANT MECHANICAL HEALTH I
PLAN PERFORMANCE ENGINELRING PHYSICS cm i
CooRolNAToR SuPERvw R suPERvis0R SUPER 9ffENDENT I
U l
I I
I l
RAD NUCLEAR ELECTRICAL HEATH I
l CHEMISTRY SUPPORT ENGNIEERelG PHYSICS l
SUPERVl30R SUPERVISOR SUPCRVISOR SUPERVIStA g
g l
l l
l 1
CHEMISTRY 8 COMP 88TER DRAFTING &
HEATH ENVIRONENTAL SUPPORT
-DRAWING CONTROL PHYSICS l
I SUPERVISOR SUPERVISOR SUPERVISOR SPEC w STS I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I I
l ARKANSAS POWER S LIGHT COMPANY l
l NUCLEAR PLANT ORGANIZATION I
I I
I I
I I
O I
I I
I V
I A
I TOPICAL REPORT lREV.
6 l
l p
l lDATE 5/30/84 i
I I
FIGURE 7.
AP&L NUCLEAR PLANT ORGANIZATION IPAGE F-7 l
1 L
I (PLANT ENGINEERING & TECHNICAL SUPPORT)I I
I I
I I
I I
I I
.I I
(
)
_ %-./
I l
I I
I I
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l
=
l l
1 I
I l-I
^ 5ENE7' I
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I l
I
.(G l
1
,' )
g TRAINING OFFICE HUMAN MATERIALS PLANT l
SUPERIN'T SERVICES RESOURCES MANAGEMENT CONTROLLER SUoERVISOR SUPERVISOR SUPERVISOR l
I I
I I
I I
I I
I I
SECURITY EMPLDYMENT &
SAFETY &
COORDINATOR INDUSTRIAL FIRE l
RELATIONS PREVENTION l
l COORDINATOR COORDINATORS I
I I
I I
I I
I I
I I
I I
I I
I I
I ARKANSAS POWER S LIGHT CO.
I I
NUCLEAR PLANT ORGANIZATION I
I I
I I
'o l
l i
i l
A l
TOPICAL REPORT
[REV.
6 l
l p
l IDATE 5/30/84 l l
I FIGURE 8.
AP&L NUCLEAR PLANT ORGANIZATION IPAGE F-8 I
l L
l l
I (PLANT ADMINIS1RATIVE' SERVICES) I I
I I
e 1
I l-l l
TABLE 1 l
m; I
l j
i l
l ARKANSAS POWER & LIGHT'S EXCEPTIONS / INTERPRETATIONS l
l OF REGULATORY GUIDES AND ANSI STANDARDS APPLICABLE l
TO THIS QUALITY ASSURANCE PROGRAM l
l l
1 l
.1 l
l Regulatory Guide /
Exceptions /
g ANSI Standard Requirement Interpretation g
l General Certain Regulatory The AP&L commitment refers l
.l Guides invoke or to the Regulatory Guides and l
imply Regulatory ANSI Standards, specifically l
.I Guides and standards identified in this TOPICAL.
l in addition to the Additional Regulatory Guides, l
l standard each ANSI Standards, Guides and l
primarily endorses.
similiar documents implied l
l Certain ANSI Stan-or referenced in those l
dards invoke or specifically identified in l
- (]
l imply additional this TOPICAL are not part of l
l standards.
this commitment.
l l
General Certain ANSI Our commitment to those l
Standards and/or standards applies only to l
l Regulatory Guides those systems, structures, l
extend the scope of and components whose satis-l applicability to factory performance is l
l include systems, required to prevent postu-l structures, and lated accidents that could l
components whose cause undue risk to the l
. l satisfactory perfor-health and safety of the i
mance is required public; or to mitigate l
l for a plant to the consequences of such l
operate reliably on accidents.
Reliable operation l
l "high-value of the plant may depend upon l
l l
l l
l l
A l
TOPICAL REPORT lREV.
6 l
1 P
l lDATE 5/30/8a l
l l SECTION:
TABLE 1 lPAGE T1-1 l
l L
l l
l l
l 1
l
I I
l-l l
articles."
other systems, structures and l
'[
components which are not
- u.
I l
covered by this commitment.
I I
I
.I l
l ANSI N18.7 Where changes-are Consistent with the require-l (Section 5.2.13.1) made to procure-ments of ANSI N45.2.11, para-l
.I ments, they shall graph 7.2, minor changes to l
l be subject to the (procurement) documents, such l
.1 same degree of as, inconsequential editorial I
control as was used corrections, or changes to l
l in the preparation commercial terms and conditions I
of the original may not require that the re-y
~l~
documents.
vised (procurement) document l
receive the same review and I
approval as the original l
documents.
l l
lANSIN45.2.1 Fresh water criteria The turbidity requirement on l
q' l
(Section 3.2) for chlorides, and fresh water is deleted and l
f
'~
Jackson Turbidity the chloride requirement is
- l Units.
revised to read "less than l
250 ppm."
The turbidity l
l requirement for demineralized I
l water is deleted.
l l
I I
" Preliminary visual Inspection after unloading is g
g l
Subsection 5.2.1 inspection or exami-sufficient to determine the l
l l
nation shall be per-condition of many items.
In l
formed prior to special instances, pre-unload-l unloading..."
ing examination is performed.
l 1
I l
l I
I I
l
.I l
l l
l l
Rn.
I I
i
/
l l
l 1
l Ai l
TOPICAL REPORT lREV.
6 I
.I P
l 10 ATE 5/30/84 1
-l l SECTION:
TABLE 1 lPAGE T1-2 l
l L'
l l
l l
l I
I
- i:
l l
1 l
l ANSI N45.2.2 The (receiving)
Receiving inspection is per-l (l
I Section 5.2.2 inspections shall formed in a manner and in an I
(>
l l
.l be performed in an environment which does not l
l area equivalent to endanger the requisite quality I
l the level of storage of an item.
The receiving l
requirement for the inspection area environmental l
item.
controls may be less stringent l
l than storage environmental l
requirements for that item, l
however, the short time spent l
in the less stringent receiv-l ing inspection area shall be l
of such duration that will l
not adversely affect the item l
being received.
l l
l l
l
- l. ANSI N45.2.2
..."The 'Special The "Special Inspection" l
Paragraph 5.2.3 Inspection' pro-procedure shall be readily G
l cedure, complete available to inspection l
l with documentation personnel and may be attached l
instructions shall to the item or container.
l l
be attached to the l
item or con-l tainer..."
l I
ANSI N45.2.2~
The use or storage People working in storage l
Subsection 6.2.4 of food, dririks, and areas have a right of access l
l salt dispensers in to water dispensers per OSHA l
any storage area is requirements.
Additionally, l
prohibited.
due to the location and l
layout of the building, per-l sonnel may temporarily store l
lunches in the work place.
l l
l l
l l
l 0'
l l
i i
l A
l TOPICAL REPORT lREV.
6 l
l P
l lDATE 5/30/84 l
l l SECTION:
TABLE 1 lPAGE T1-3 l
l L
l l
l l
l l
l
V l
l I
l l
This area is policed for l
I
(~'i,
sanitation.
I U
" Container markings Containers are adequately l Appendix (A-3) shall appear on a marked for storage, identifi-l lA.3.9(1)Second l
minimum of two sides cation, and retrieval.
l Group of the container, Multiple marking requirements l
l preferably on one are imposed, where necessary.
I side and one end."
l l
l l
l l ANSI N45.2.2
" Container markings Container markings are of a l
l Appendix (A-3) shall be...no less size which permits easy l
l A.3.9 (4) Second than 3/4" high recognition.
l l Group container permit-l ting."
l I
I I
l l
" Container marking The information required l
l Appendix (A-3) shall include the in container inrking is A
l A.3.9 following informa-evaluated on a case-by-l tion..."
base basis.
Marking is l
l adequate in each case.
I l
l l
l l
ANSI N45.2.2 "Non-metallic plugs Non-metal plugs and caps are l
Appendix (A-3) and caps shall be of a suitably visible color.
l l
Section A 3.5.1 (1) brightly colored."
I l
l I
I l
ANSI N45.2.2 Plugs or caps shall In cases where plugs or caps l
l Appendix (A-3) be secured with tape do not snugly fit, additional l
Section A 3.5.1 (5) or other means as securing devices or measures I
l necessary to prevent which will not be detrimental l
accidental removal.
to the item will be used.
l l
l l
l l
l l
l l
l l
l O'~
l I
l A
l TOPICAL REPORT IREV.
G l
l P
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l 1 SECTION:
TABLE 1 lPAGE T1-4 l
l L
l l
l l
l I
I
,i '
I I
I l
- l. ANSI N45.2.2 Marking of items The last paragraph of Section l
^'
Appendix (A-3) not within a con-A.3.9 could be interpreted as
.l Section A 3.9 tainer.
prohibiting any direct marking l
on bare austenitic stainless
~l steel and nickel alloy metal l
surfaces.
In lieu thereof, l
paragraphs A.3.9. (1) and (2) l will be used to control l
marking on the surface of l
l austenitic stainless steels l
and nickel base alloys subject l
l l
to the following limitations:
l-
" Marking materials containing l
l sulfur, lead, zinc, mercury, l
l copper and low melting alloys l
l l
as a basic chemical consti-l tuent shall not be brought in l
l l
contact, or shall not bt used q
l on surfaces of corrosion l
v/
l resistant alioys.
Low sulfur, l
l low fluorine and/or low l
chlorine compounds may be l
used on austenitic stainless l
l steels." The maximum limits l
for the above mentioned mark-l ing materials will be as l
l follows:
l l
(a) Total inorganic and l
organic halogen content l
l shall not exceed one (1) l percent.
l (b) The sulfur content shall l
not exceed one (1) l l
percent.
l l
l l
g)
I I
I I
t."
l A
l TOPICAL REPORT lREV.
6 l
l P
l lDATE 5/30/84 l
l 1 SECTION:
TABLE 1 lPAGE T1-5 l
l L
l l
l l
l l
l
s l '.
I i
1.
l
'l ANSI N45.2.2 Inert Gc. tilankets There may be cases involving l
,C large or complex shaped items I
for which an inert or dry air l
.l purge is provided, rather I
than a static gas blanket, in l
order to provide adequate l
protection due to difficulty l
of providing a leak proof l
barrier.
In these cases, a l
positive pressure purge flow l
l may be utilized as an alter-l nate to a leak proof barrier.
I I
ANSI N45.2.2 Limits halogen and Engineering may allow the use l Appendix A, sulphur content of of tapes containing greater l
-A.3.5.2,(1),(a) tape.
amounts of halogans after I
appropriate evaluation, l
I I
however, the quantities shall l
l
'(o l-not be such that harmful l
concentrations could be l
leached or relased by break-l I
l down of the compounds under l
expected environmental l
conditions.
I i
l
-lRegulatoryGuide General Alternative equivalent l
1.39 ANSI N45.2.3 requirements may be utilized l
to cover those situations not l
included in the subject l
Standard; for example, situa-l tions in which shoe covers l
I l.
I I
l l
l l
I l'
l I
l r
l l
l I
I l
A l
TOPICAL REPORT lREV.
6 l
l-p l
lDATE 5/30/84 l
l l SECTION:
TABLE 1 lPAGE T1-6 l
l t
i I
I
'l I
i l
q
~
.I I
I i
l and/or coveralls are required l
}
but material accountability l
l is not.
In addition, zones l
might be combined into the l
next more restrictive l
category in order to reduce l
total number of zones.
l l
l l
1
-l ANSI N45.2.3 Identifies various When this standard is applied, l
l-housekeeping re-its requirements are imple-l l
quirements, includ-mented in those areas affected l
.l l
ing cleanliness, by wor'. activities associated l
fire prevention, with modifications, opera-l l
and fire protection tions, or maintenance as l
which must be determined necessary by Plant l
l accomplished during Staff.
l the progress of l
l construction.
n; l
l lRegulatoryGuide Pre-Construction /
This section required verifi-l l 1.30/ ANSI N45.2.4 Installation Verifi-cation that items are in l
l cation satisfactory condition for l
l Regulatory Guide installation and have not l
l 1.116/ ANSI N45.2.8 suffered since initial l
receipt inspection.
Upon l
receipt, items are inspected l
and stored in an environment 1
which will not adversely l
l affect the item.
Documented l
routine inspections and l
periodic audits of the storage I
I I
l l
l 1
l-l i
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l n
l l
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l TOPICAL REPORT lREV.
6 l
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l 1 SECTION:
TABLE 1 lPAGE T1-7 l
l L
l l
l l
l 1
1
i OO
+k * +
b
////p kgf IMAGE EVALUATION 4)y g 1ss11AaGercur.3) gy
'k
- f w?g
///,4,}
gfs g/
~
+
l.0 l# M Ha
- i M BH in m
I l,l bb l.8 1.25 1.4 1.6 4
150mm 4
6" L*%
+j+ b
/f4%
A 4%
<>++#+
- v 7//
u 1
o
l i
1 I
~
I-areas assure that stored items l
are maintained in satisfactory
_l conditions.
Documentation l
-_v-of pre-const ruction veri fica-l tion in addition to documen-l tation of initial receipt
- l inspection, periodic storage l
inspections, and audits of I
storage is not required.
I I
I i
l 4
l -ANSI N45.2.4 Identifies various These tests will be performed l
tests to be as determined by " gineering
-I performed.
or Nuclear Operations based l
I upon the significance of l'
change or modif 4ation.
l I
1
~l l
l R.G. 1.58 In addition... the AP&L takes exception to this I
l
-(Section C.6) candidate should be requirement.
AP&L's education J/3'-
l
-a high school and experience requirements l
1 e
.g g
graduate or have are in accordance with ANSI l
earned the General N45.2.6-1978.
l l
Education Development l
l (GED) equivalent of I
l l
a high school
[
diploma.
1 I
I l'
l l
.R.G. 1.74/'
Definitions of Based upon the guidance of i
lANSIN45.2.10 Certificate of ANSI N45.2.13, 10.2,_the
'l-Conformance and definitions of these two l
Certificate of terms will be exchanged.
l' Compliance."
l I
l
'l-1 I
I l
I I
I I
I q
.l l
ij l
i I
I
'A
.1 TOPICAL REPORT IREV.
I l.
P l
lDATE 9/30/84 l
l 1 SECfl0N:
TABLE 1 lPAGE TI-8 l
l L
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1 1
I I
l
a A
^
l l
I I
l R.G. 1.94/
Section 1.4 defines This requirement for rein-I I
I
[v'E ANSI N45.2.5 inprocess tests and forcing steel will be l
l
.1 (Sectior,1.4) states:
interpreted to permit taking I
the rebar test specimen at i
... samples of these the fabrication shop, prior I
tests must be taken to start of fabrication of l
from the lot or the rebar from the heat or I
batch of ciaterials fraction thereof represented l
l supplied to the site by the test specimen.
For l
l for use."
these tests performed at the I
fabrication shop, certifica-l l
tion shall be available to l
l provide objective evidence l
l that the test specimens I
represent the material sup-l l
plied for use at the site.
I l
lANSIN45.2.5 Requirement:
l A
l (Section 4.5)
Section 4.5, Con-l l
crete Placement, I
references American l
l l
Concrete Institute l
(ACI) standards l
l l
ACI-305-72, l
" Recommended Prac-l l
tice for Hot Weather 1-Concreting" and ACI-l l
306-66, " Recommended l
Practice for Cold l
l Weather Concreting."
l l
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l l
4 p
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TOPICAL REPORT IREV.
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l 1 SECTION:
TABLE 1 IPAGE TI-9 l
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l t
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1 I
I I
Interpretation:
I
_(
In order to clarify I
l use of these ACI I
standards, we will I
apply the following I
requirements:
l l
l l
PLACING TEMPERATURES OF CONCRETE:
l l
A.
During hot weather concreting:
l l
l l
Placing temperatures of concrete will be l
l' limited to the following:
l I
I l
l l
- 1) Concrete members less than 3 feet in least I
l dimension will not exceed 90 F.
l l
l l
- 2) Concrete members from 3 feet to 6 feet in Q_
l least dimension will not exceed 70*F.
I v
1 l
l l
I
- 3) Concrete members more than 6 feet in least l
l dimension will have placing temperature as l
l near 50*F as can be obtained by use of ice l
l' as necessary up to 100 percent of adding l
l mixing water; and by shading aggregate and I
sprinkling the coarse aggregate the day it l
l is to be used.
Care will be taken so that l
l I
no unmelted ice remains in the concrete at I
the end of the mixing period.
I I
I i
l I
I I
I I
I I
l I
l l
I I
I m.
I I
t) :
1 I
I l
I A
I TOPICAL REPORT IREV.
6 l
l P
i lDATE 5/30/84 l
l 1 SECTION:
TABLE 1 lPAGE T1-10 l
l L
i l
I l-I l
I
I l
I l
l B.
During cold weather concreting:
l O
I I
~)
l l
l In heating the water and aggregate, live steam l
to heat the fine and coarse aggregate shall not l
l be used.
The permissible range for concrete l
temperature shall be as follows:
I I
- 1) Sections less than 3 feet in least l
dimensions:
55 to 75*F.
l I
I I
i l
- 2) Mass concrete 3 feet or more in least l
dimension: 45 to 65*F.
I I
The mixing water and aggregate will be -
l l
purchased as required.
The materials will be l
free of ice, snow and frozen lumps before they l
l enter the mixer.
l l
l 1
I O,
l ANSI N45.2.5 Requirement:
l l
(Section 4.8) l Section 4.8, "In process Test on Concrete and -
l Reinforcing Steel" states, " Samples for in process l
l test of concrete shall be taken at the sampling l
point in accordance with ASTM C172.
This point may l
l be at the truck mixer discharge if the last piece l
of conveying equipment is a chute, bucket, l
conveying system, or similar equipment.
Pump l
l concrete must be sampled from the pump line l
l discharge."
l I
I I
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I l
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l l
l l
l 1
l l
1 o
l l
i i
l A
I TOPICAL REPORT lREV.
6 l
l P
l lDATE 5/30/84 l
l 1 SECTION:
TABLE 1 lPAGE T1-11 1
I L
l l
l l_
l l
I
e i
l 1
l l
Interpretation:
l
('i l
1
- C/ -
l l
~~
l For performance of correlation tests, the l
I requirements of ANSI N45.2.5-1974 shall be I
followed.
I I
l l
I l ANSI N45.2.5 Requirement:
l l(Section4.8) l l
Section 4.8, "In process Tests on Concrete and I
Reinforcing Steel" contains Table B entitled, i
" Required In process Tests." The following l
l modifications to this tabla will be applied:
I I
l l
Interpretation:
l l
l l
REINFORCING STEEL l
I l
In process testing or reinforcing steel will l
(')
l include the mechanical properties of yield l
l strength, tensile strength and percent elongation l
I on full size specimens for each bar size for each l
l l
50 tons or fraction thereof from each mill heat.
l Bend tests are performed during material l
l qualification testing only, except as noted below l
1 for bar sizes #14 through #18.
I I
I I
I l
Table A, " Required Qualification Tests" as applied l
l to reinforcing steel will include bend tests as I
required by ASTM A615 and summarized below:
l l
l 1
1 1
l i
I I
I I
I I
l i
I I
l 6
I l
b l
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l l
A l
TOPICAL REPORT IREV.
6 l
l P
l IDATE 5/30/84 l
l 1 SECTION:
TABLE 1 lPAGE T1-12 I
I L
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I I
p
1 I
I I
I l
a) For bar sizes #3 through #11, one full size l
/~ ')
I specimen from largest bar size rolled from each v
l l
l mill heat, unless material from one heat l
differs by three or more disignation numbers.
l.
When this occurs, one bend test shall be made l-from both the highest and lowest designation l
number of the deformed bars rolled.
l l
l l
l l
b) For bar sizes #14 through #18, Supplementary l
l Requirements S1 of ASTM A615 will be applied.
I One full size specimen for each bar size for l
each mill heat.
If supplementary requirements l-are not followed for mill tests, they will be l
l applied as in process tests.
l l
1 The above interpretation is consistent with g
l Regulatory Guide 1.15, " Testing Reinforcing bars l
for Category I Concrete Structures," Revision 1, l
f'y l
December 1972.
l V
l l
l l
l In process test specimens may be selected at the l
rebar fabrication shop, prior to start of l
fabrication of the rebar from the heat or fraction l
thereof represented by the test specimen.
l 1
I Acceptance criteria for any failed test l
l (qualifications as well as in process) may be the l
same as that for tensile tests specified in l.
Subarticle CC-2331.2 of ASME Section is', Div. 2 l
l Code (1975).
This states that if a test specimen l
fails to meet the specified strength requirements, l
l-l I
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l l
I (X) l I
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l TOPICAL REPORT lREV.
6 I
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l 1 SECTION:
TABLE 1 lPAGE T1-13 l
l L
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l
n L
1 I
I l
l two (2) additional specimens from the same heat and I
~'l I'
I v
I of the same bar size would be tested, and if either I
I of the two additional specimens fails to meet the I
specified strength requirements, the material l
l represented by the tests would be rejected for the i
specified use.
Alternative use of rejected I
material under strict control may be subject to l
l evaluation by the Project Engineer.
l l
l lANSIN45.2.5 Requirement:
1 (Section 4.9) l l
Section 4.9, Mechanical (Cadweld) Splice Testing l
l states in paragraph 4.9.4 " Separate test cycles I
shall be established for mechanical splices in l
l horizontal, vertical and diagonal bars, for each l
l bar size and for each splicing crew..."
l l
l l
l Interpretation:
/7 l
l The terms " horizontal, vertical and diagonal bars" l
l will be interpreted to apply respectively to the l
l following types of splice positions:
l l
l l
l a.
Hozizontal, including 10 to horizontal l
b.
Vertical, including 10* to vertical l
l c.
45* angle, including 10 to 80* angle l
l l
The words " splicing crew" will be interpreted to I
refer to all members on the project that are I
activitely engaged in preparing and assembling l
cadweld mechanical splices at the final splice l
1 l
location.
Separate test cycles will be established l
1 I
for each bar size and each splice position.
l l
l l
l l
l i
I n)
I l
I l
(.
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l A
l TOPICAL REPORT IREV.
6 l
l P
I IDATE 5/30/84 l
l 1 SECTION:
TARLE 1 IPAGE T1-14 l
l L
l l
l l
l l
l L. _
.I l
l l
l ANSI N45.2.12 An individual audit For those routine audits l
(O I
(Para 0raph 4.2.1) plan describing conducted during operations, I
v l
l l
the audit to be a written procedure (s) l performed shall be covering each audit may be l
developed and utilized.
Procedure (s) will l
documented by the identify the audit scope, l
auditing organiza-a requirement that individual l
l tion.
This 'lan checklists be utilized list-p l
shall identify the ing requirements which are to l
l audit scope, the be audited and notification l
requirements, the of the audited group.
l l
l activities to be l
audited, organiza-l tions to be notified, l
the applicable l
l documents, the l
schedule, and written l
l procedures or check-(]J l
lists.
l C
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l ANSI N45.2.13 The certificate The person attesting to a l
l (Section 10.2.d) should be attested certificate shall be an l
to by a person who authorized and responsible l
l is responsible for employee of the supplier, l
this quality assur-and shall be identified by l
l ance function and the Supplier.
l l
whose function and l
position are l
described in the l
l f
Purchaser's/
l Supplier's quality l
l assurance program.
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I R.G. 1.64 (Section "While design Consistent with the require-l l
[]
C.2)/ ANSI N45.2.11 verification by the ment of ANSI N45.2.11, l
designer's immediate paragraph 6.1, design verifi-I supervisor is en-cation may be performed by l
-I couraged, it should the originator's supervisor, l
not be construed if the supervisor is the only l
l that such verifi-individual in the organization I
l cation constitutes competent to perform the l
the required inde-verification.
I l
pendent design l
l verification,..."
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TABLE 3 l
cs l
l sj-I QUALITY PROGRAM POLICIES, PROCEDURES AND INSTRUCTION l
l MANUALS LIST l
l l
1 l
l 1.
Quality Assurance Program for Operations l
l l
l l
l The Quality Assurance Program'for Operations establishes the l
.l policies and guidelines of the AP&L quality assurance program for l
l its operating nuclear plants.
This program is to be followed by all l
l organizations involved in safety-related work applicable to l
I operating nuclear plants.
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2.
Energy Supply Procedures Manual l
I I
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l The Energy Supply Department - Little Rock General Of fice (LRGO) l l
employes a system of procedures designated as Energy Supply l
l Department Procedures (ESP) in order to implement Program l
l requirements for the control of design, engineering, nuclear fuel, l
(]
l licensing, training and procurement activities in support of the l
l operating plant.
l
~#
l l
l The ESP's and revision thereto are prepared by Energy Supply LRGO l
l personnel, reviewed and approved by the Quality Assurance Manager, I
l the Energy Supply (LRGO) Procedures Task Force and the responsible l
I department head.
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I l
3.
Quality Assurance Procedures Manual i
1 I
l l
The Quality Assurance Organization employes a system of procedures l
l designated as Quality Assurance Procedures (QAP) in order to assure l
l proper implementation of the program.
The QAP's and revisions l
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l theritto are prepared by the Quality Assurance Organization, reviewed l
I I
and approved by the Quality Assurance Manager and approved by the l
I v.
l Energy Supply Services Director and the Sr. Vice President, Energy I
l l
Supply l
l l
~.
Quality Assurance Administrative Procedures Manual 4
l l
l The Quality Assurance Organization also employes a system of l
1 procedures designated as Quality Assurance Administrative Procedures l
l (QAA).
These procedures provide technical and administrative l
l instructions to the Quality Assurance staff to aid in implementing l
l their responsibilities within the quality program.
l l
l l5.
l Overall Plant Adminstrative Procedures Manual l
l l
The plant operation organization employes a system of procedures l
I designated as Overall Plant Administrative Procedures.
These l
l procedures implement Quality Assurance Program requirements and l
^\\
l control on site activities.
Overall Plant Administrative Procedures I
l and changes thereto are prepared by the plant staff, reviewed by the l
l Plant Safety Committee and approved by the plant's General Manager.
l l
The procedures and revisions are also raviewed by the Manager, l
l Nuclear Quality Control to assure that Quality Assurance Program l
l l
commitments are met.
l 1
l6.
Departmental Plant Administrative Procedures l
I l
Each department (operations, maintenance, engineering and technical l
l support, training, quality control, etc.) at the plant has developed I
procedures in support of the Overall Plant Aoministrative Procedures l
l and this Quality Assurance Program.
These procedures provide l
l technical and administrative instructions to the various departments l
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I to aid in implementing their responsibilities within the quality l
']
l l
program.
Each department head is responsible to perform a QA review
~
l of their procedures to assure conformance with the Quality Assurance l
l I
Program.
These procedures are reviewed by the Plant Safety g
l Committee and approved by the Plant's General Manager.
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