ML20077A409
| ML20077A409 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/10/1983 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20077A397 | List: |
| References | |
| NUDOCS 8307220314 | |
| Download: ML20077A409 (148) | |
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1 "t ; IDATE 6/10/83 1 4 , p,, ,l &) o ..I APPP,0 VAL SIGNATURES I l '+ r I ' ' le^ l I I C 'l l l I N L;-__._.-,-..-.---.-- l l l 1 l TABLE OF CONTENTS l l O i l i .I Section Subject Tab h Rev. l. l 1- -l l l APPROVAL COVERSHEET l _l l TABLE OF CONTENTS TC-1 6 l TC-2 6-l l ] TC-3 6 l TC-4 6 l l l TC-5 6 l .TC-6 6 l { l l POLICY STATEMENT A-1 6 l l A-2 6 l i l INTRODUCTION B-1 6 l B-2 6 l ) l B-3 6 i l B-4 6 l~ I l B-5 6 l TERMS AND DEFINITIONS C-1 6 l I l C-2 6 I 1 l C-3 6 l I l l C-4 6 l-l C-5 6 l l l C-6 6 l C-7 6 l C-8 6 l C-9 6 l l C-10 6 l
- 1. 0 ORGANIZATION 1
1-1 6 l l l 1-2 6 l 1-3 6 l l l 1-4 6 l 1-5 6 l- 'l I l l l l l 1 A l TOPICAL REPORT lREV. 6 l P ] lDATE 6/10/83 l l 1 SECTION: TABLE OF CONTENTS lPAGE TC-1 l I L i i I I I I l l i i I i 1-6 6 l l l 1-7 6 I 1-8 6 l l l 1-9 6 1 1-10 6 l l l l-11 6 1 1-12 6 l l l 1-13 6 l 1-14 6 l l l 1-15 6 l 1-16 6 l l l 1-17 6 l 1-18 6 l l 1-19 6 l 1-20 6 l l l 1-21 6 l 1-22 6 l l l 2.0 QUALITY ASSURANCE PROGRAM 2 2-1 6 l 2-2 6 l l l 2-3 6 l 2-4 6 l l l 2-5 6 l 2-6 6 l l l 2-7 6 l 3.0 DESIGN CONTROL 3 3-1 6 l l l~ 3-2 6 l 3-3 6 l l l 3-4 6 l 3-5 6 I l f 4.0 PROCUREMENT DOCUMENT 4 4-1 6 I CONTROL 4-2 6 l l l 4-3 6 l l l I I I 'i I G 1 I I ,V l A I TOPICAL REPORT IREV. 6 l l P 1 IDATE 6/10/83 I I 1 SECTION: TABLE OF CONTENTS IPAGE TC-2 l l L I i l l l I I .I I I l l 5.0 INSTRUCTIONS, PROCEDURES 5 5-1 6 l I AND DRAWINGS 5-2 6 I 5-3 6 l l 5-4 6 l 6.0 DOCUMENT CONTROL 6 6-1 6 l I l l 6-2 6 i l 6-3 6 l l
- 7. 0 CONTROL OF PURCHASED 7
7-1 6 l l MATERIAL, EQUIPMENT AND 7-2 6 l l SERVICES 7-3 6 I 7-4 6 l l l 7-5 6 l 7-6 6 l l 8.0 IDENTIFICATION AND CONTROL 8 8-1 6 l l OF MATERIALS, PARTS AND 8-2 6 l l COMPONENTS 8-3 6 l
- 9. 0 CONTROL OF SPECIAL 9
9-1 6 l l l PROCESSES 9-2 6' l 9-3 6 l 10.0 INSPECTION 10 10-1 6 l l 10-2 6 l l l 10-3 6 l l 10-4 6 l l l 10-5 6 l 11.0 TEST CONTROL 11 11-1 6 l l l~ 11-2 6 l 11-3 6 l l 11-4 6 l 11-5 6 l l l 12.0 CONTROL 0F MEASURING AND 12 12-1 6 l TEST EQUIPMENT 12-2 6 l l l 12-3 6 l 12-4 6 l l I I I -l l l 1 Q l l I I V l A TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l l SECTION: TABLE OF CONTENTS IPAGE TC-3 l l L l l l l l I I l l I I l 13.0 HANDLING, STORAGE AND 13 13-1 6 l I I cs SHIPPING 13-2 6 13-3 6 l l l 13-4 6 l 13-5 6 l l l 14.0 INSPECTION, TEST AND 14 14-1 6 l OPERATING STATUS 14-2 6 l l l 14-3 6 l 14-4 6 l l 14-5 6 l 15.0 NONCONFORMING MATERIAL, 15 15-1 6 l l l PARTS OR COMPONENTS 15-2 6 l 15-3 6 l l l 15-4 6 l 16.0 CORRECTIVE ACTION 16 16-1 6 l l 16-2 6 l 16-3 6 l l l 16-4 6 l 17.0 QUALITY ASSURANCE RECORDS 17 17-1 6 l c(.) l 17-2 6 l 17-3 6 l l 17-4 6 l 17-5 6 l l 17-6 6 l 18.0 AUDITS 18 18-1 6 l l l 18-2 6 l 18-3 6 l l 18-4 6 l 18-5 6 l l l 18-6 6 l l l I l 1 l l l ~ l l l l 1 l l I I I I (O) l A l TOPICAL REPORT lREV. 6 l l P I lDATE 6/10/83 l l 1 SECTION: TABLE OF CONTENTS lPAGE TC-4 I I L l l 1 I I I I l I l l l FIGURES l Number Title Tab Page Rev. l l 1 AP&L Corporate 19 F-1 6 l Organization l l 2 AP&L Corporate Services 19 F-2 6 l l 3 AP&L Energy Supply 19 F-3 6 l l Organization l l 4 AP&L Quality Assurance 19 F-4 6 l l Organization l l 5 AP&L Nuclear Plant 19 F-5 6 l l Organization l l 6 AP&L Nuclear Plant 19 F-6 6 l l Organization (Plant l l Operations and Main-l l tenance) l 7 AP&L Nuclear Plant 19 F-7 6 l l l Organization (Plant f3 l Engineering and Technical l 'd l Support) l l 8 AP&L Nuclear Plant 19 F-8 6 l l Organization (Plant l l Administrative Services) l l I l l l I I I-1 I I I I I I I l I I I I I I I I I I I I I I I I I I I I I ('S I l l l 'v' l A I TOPICAL REPORT lREV. 6 l l P I lDATE 6/10/83 l l l SECTION: TABLE OF CONTENTS lPAGE TC-5 I I L l l l l 1 I l I I I I l Ti.al.ES l l l O i i -I Number Title Tab. M Rev. l l l 1 AP&L Exceptions / Inter-19 T1-1 6 l pretations of Regulatory T1-2 6 l l ] Guides and ANSI Standards T1-3 6 I T1-4 6 I l l T1-5 6 l T1-6. 6 l l l T1-7 6 l T1-8 6 I l 6 l T1-9 l T1-10 6 l l l T1-11 6 l T1-12 6 I l l T1-13 6 l T1-14 6 I l l T1-15 6 l 2 Quality Assurance 19 T2-1 6 l l l Procedures Matrix l 3 Quality Program Policies, 19 T3-1 6 l l l Procedures and Instruc-T3-2 6 l tion Manuals List I i l t l 1 1 I I I-1 I I I l I I I I l 1 I I I I I I .I I ~ l I I l I I I I l l I I I l Q l l I I I l .A I TOPICAL REPORT IREV. 6 I l i P I lDATE 6/10/83 I i I l SECTION: TABLE OF CONTENTS IPAGE TC-6 l l L I l l l 1 I I t l l I I l ARKANSAS POWER & LIGHT COMPANY POLICY STATEMENT l I QUALITY ASSURANCE PROGRAM FOR OPERATION I l 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 10 CFR 50, Appendix B, with respect to operation, maintenance, refueling, l repair and modifications, and inservice inspection of AP&L Nuclear l 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 to Code requirements. l l l 1 l l Under the Program the Energy Supply Sr. Vice President, is the final l lmanagementauthorityresponsibleforassuringthatthispolicystatement l l and the Quality Assurance Program are implemented within AP&L. The l Nuclear Operations Vice President and each Energy Supply Director is l responsible for the procedural implementation of the program within his j assigned area. The plant's General Manager is responsible for the daily O implementation of the Program's procedural requirements at the plant. l l i i l l l The Quality Assurance Manager is responsible for establishing the l Program. The Quality Assurance Manager, Energy Supply Services Director l and the Energy Supply Sr. Vice President are responsible for approval of l the Program. I I 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. l l l l l l l The Quality Assurance Manager is to provide for annual review of the l adequacy and overall effectiveness of the Program. Any defects in the l i 1 I l l l 1 l I l I Q l I I I l A l TOPICAL REPORT lREV. 6 l l P l0 ATE 6/10/83 l l l SECTION: STATEMENT OF POLICY lPAGE A-1 l l L i l l l 1 1 1 1 I I I I l implementation of either this policy or the Program that are revealed l 3 ' during the review are to be reported to appropriate levels of management l l together with appropriate recommendations. I I i 1 1 I Implementation of this policy is necessary in order to achieve the l lreliabilityandsafetyrequiredatourNuclearPlants. Each person I involved in activities concerning our Nuclear Plants is to be responsible l l for assuring quality in his own work, and for compliance with the i requirements of the Program. The Quality Assurance Program policies, I l manuals,andproceduresaremandatoryrequirementswhichmustbe l i implemented and enforced by all responsible organizations and I ' individuals. l l l 1 I I I I W. Cavanaugh, III. I Energy Supply Sr. Vice President I g l l Date: I I O i i l l I I I I I .I I I I I I I I I I l-1 I I I I l l I l l I I I I l I I I l I l I I I I I I I I l -O I I I I d i A I TOPICAL REPORT (REV. 6 l l P l lDATE 6/10/83 l l 1 SECTION: STATEMENT OF POLICY lPAGE A-2 l I L i I I l l l 1 I I I I l INTRODUCTION l (y I I s l l 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 Analysis Reports for Nuclear. Power Plants, Section 17, published by the l Nuclear Regulatory Commission. l l The objective of this program is to control those phases, as applicable, I l for the design, procurement, manufacture and fabrication, installation, l operation, testing, refueling, repair, maintenance or modification to l l existing safety related (Q-List) structures, systems and components that l prevent or mitigate the consequences of a postulated accident which may l -l 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 l individual contributor and that management is responsible for creating an l awareness of quality. l o i The AP&L quality program is designed to comply with the requirements of l 10CFR50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants l I and Fuel Reprocessing Plants, and to comply with the quality assurance l l requirements of the ASME Boiler and Pressure Vessel Code,Section XI for i repair, replacement, and inservice inspection of items covered by the l Code and Licensing commitments. l l l-I l l In general, the AP&L quality program complies with NRC positions l contained in the following regulatory guides, subject to specific l exceptions noted in the body of this manual, Table 1 of this manual or in l the final safety analysis reports: I I I l l l l l I -l-I l I l 1 l l (~' l l l I l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l l SECTION: INTRODUCTION lPAGE B-1 l l L l l l l l l 1 l l l l l 1.8, rev. 1-R Personnel Selection and Training (5/77) l q 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 and Electrical Equipment (8/72) i 1.33, rev. 2 QA Program Requirements-Operations (2/78) l 1.37 QA Requirements For Cleaning of Fluid l 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 l Receiving, Storage and Handling of Items l l For Water Cooled Nuclear Power Plants l l (5/77) l l 1.39, rev. 2 Housekeeping Requirements For Water Cooled l Nuclear Ppwer Plants (9/77) l 1.58, rev. 1 Qualification of Nuclear Power Plant l Inspection, Examination and Testing l l Personnel (9/80) l IsI V I 1.64, rev. 2 QA Requirements For the Design of Nuclear l g g l Power Plants (6/76) l 1.74 QA Terms and Definitions (2/74) l c l 1.88, rev. 2 Collection, Storage, and Maintenance of l Nuclear Power Plant Quality Assurance l Records (10/76) l 1.94, rev. 1 QA Requirements for Installation, l l Inspection and Testing of Structured l Concrete and Structural Steel During the l l Construction Phase of Nuclear Power Plants l I (4/76) I l 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 i l l l I I I ^ ( l l I l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l l SECTION: INTRODUCTION lPAGE B-2 l I L 1 l l i l l I I _._ I 1 l 1-l l 1.123, rev. 1 QA Requirements For Control.of Procurement 1 p of Items and Services For Nuclear Power i l Plants (7/77) _ l ~ 1.146 Qualification of Quality Assurance Program l 4 l Audit Personnel For Nuclear Power Plants I (8/80) l-I [ l-Baseduponcompliancetothese.regulatoryguides,theAP&Lquality l l program also complies with the following American National Standard I j l Institute (ANSI)standardssubjecttoexceptionsnotedinthebodyof l l this manual, Table 1 of this manual or in the final safety analysis l l reports: 1 l l l'N45.2-1977 Quality Assurance Program Requirements for Nuclear l j l Facilities 1 -l i I 4 l l _l N45.2.1-1973 Cleaning of Fluid Systems and Associated I ~ l Components During the Construction Phase of I l Nuclear Power Plants l
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i l l -l -N45.2.2-1972 Packaging, Shipping, Receiving, Storage and l l Handling of Items for Nuclear Power Plants (During - l the Construction Phase) l 1 1 I l l l l N45.2.3-1973 Housekeeping During the Construction Phase'of l Nuclear Power Plants ~ I l N45.2.4-1972 Supplementary Quality Assurance Requirements for i Installation, Inspection and Testing of I Instrumentation and Electric Equipment During the l l Construction of Nuclear Power Generating Stations l I l -l I =l I I I I I I I I I O l i I l V I A I TOPICAL REPORT IREV. 6 l -l P l lDATE 6/10/83 1 I 1 SECTION: INTRODUCTION IPAGE B-3 l l l L l l l i 'l i I ___l I I I I l N45.2.5-1974 Supplementary Quality Assurance Requirements for l q Installation and Testing of Structural Concrete l V l and Structural Steel During the Construction Phase l l l of Nuclear Power Plants l l N45.2.6-1978 Qualifications of Inspection, Examination and l l Testing Personnel for Nuclear Power Plants l l l l l 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 l Nuclear Power Plants l 1 N45.2.9-1974 Requirements for Collection, Storage and l Maintenance of Quality Assurance Records for l l Nuclear Power Plants l l N45.2.10-1973 Quality Assurance Terms and Definitions l 0> lN45.2.11-1974 l Quality Assurance Requirements for the Design of y l Nuclear Power Plants l 1 1 I I l N45.2.li.-1977 Requirements for Auditing of Quality Assurance l 'I Programs for Nuclear Power Plants l l N45.2.13-1976 Quality Assurance Requirements for Control of I i Procurement of Items and Services for Nuclear i l Power Plants l 1 lN45.2.23-1978 Qualification of Quality Assurance Program Audit l Personnel for Nuclear Facilities l l l l t i I l N18.1-1971 Selections and Training of Nuclear Power Plant l Personnel I g i l i l I 'N (O l l I I l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l 1 SECTION: INTRODUCTION lPAGE B-4 l l L l l l l I I l t _~ I I I I i N18.7-1976 Administrative Controls and Quality Assurance for 1 I O l the Operational Phase of Nuclear Power Plants I I i l-The above requirements are implemented by controlling activities as. l l described in'this manual and by prdcedures referenced in this manual. I I I I I I Definitions of terms applicable to the AP&L quality program are found in I the Terms and Definitions section of this manual. l l 1 l 1 I 'l 1 I I I I 1 I I I .I l l l l 1 1 I 1 I I I l-l- 1 I !o l l I I l l ^ 1 l -l 1 I i l I l-I I I i l I I 1. L I I I I I I I I I I I I I I I I I I I I I I I I l 1 I I I I C i i l 1 d I /, I TOPICAL REPORT IREV. 6 I l P l IDATE 6/10/83 l l 1 SECTION: INTRODUCTION lPAGE B-5 l I L I I I -l 1 I I I l 1 l l TERMS AND DEFINITIONS l i n I y l l l The terms used in this manual follow the definitions provided in l lANSIN45.2.10-1973..supplementedbyadditionaltermsanddefinitions l applicable to this report. I I I I I I Approval - An act of endorsing or adding positive authorization, or both. I l l l l l Appurtenance - A part that is attached to a component which h.as been I completed. t I i lAs-BuiltData-Documenteddatathatdescribestheconditionactually l l achieved in a product. l l l 1 I l Asseinbly - A combination of subassemblies or components, or both, fitted l together to form a unit. I I ,I Audit - An activity to determine through investigation, the adequacy of I and adherence to, established procedures, instructions, specifications, I g> l ( codes, and standards or other applicable contractual and licensing l requirements, and the effectiveness of implementation. j i l I l Bid Evaluation - A formal evaluation of all proposals received in i response to an inquiry to determine the vendor to whoni the purchase order l l will be awarded. l l l.- 1 I l Certificate of Conformance - A written statement, signed by a qualified l party, certifying that items or services comply with specific l requirements. l I I I l l Certificate of Compliance - A written statement, signed by a qualified l party, attesting that the items or services are in accordance with [ specified requirements and accompanied by additional information to l substantiate the statement. I g I I I I O i i i i l A I TOPICAL REPORT IREV. 6 I I P l IDATE 6/10/83 l l I SECTION: TERMS AND DEFINITIONS lPAGE C-1 l l L l l I l __ i I l I I I I l Certified Test Report - A written and signed document, approved by a l I Q l qualified party, that contains sufficient data and information to verify I m I I the actual properties of items and the actual results of all required l ,I tests. I ,I l Certification-Theactionofdetermining,verifyingandattesting,in I writing, to the qualifications of personnel or material. l 'l i I i l Characteristic - Any property or attribute of an item, proces.s, or l service that is distinct, describable, and measurable, as conforming or l nonconforming to specified quality requirements. Quality characteristics l are generally identified in specifications and drawings which describe l l the item, process, or service. l 1 l-I l l Checks - The tests, measurements, verifcations or controls placed on an l activity by means of investigations, comparisons, or examinations, to l l determine satisfactory conditions, accuracy, safety or performance. -l l l 1 I l Cleanness - A state of being clean in accordance with predetermined b standards, and usually implies free' dom from dirt, scale, heavy rust, oil l or other contaminating impurities. l l I I I l Code Inspector - A qualified nuclear inspector (ANI or ANII) employed by l l a legally constituted agency of a Municipality or State of the United l States, or Canadian Province, or regularly employed by an Authorized l lInspectionAgencyandhavingauthorizedjurisdictionatthesiteof l manufacture for installation, repair, modification, and in service l inspection of ASME Boiler and Presssure Vessel items designated l safety-related. I I I I I l Commercial Grade - Those items contained in Q systems and equipment that l lare: (1) not subject to design or specification requirements unique to l 'l nuclear facilities or activities; (2) used in application other than l l 1 I I I I I I O i i l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l 1 SECTION: TERMS AND DEFINITIONS lPAGE C-2 l l L l l l l l l 1 .I I -l I C l' nuclear facilities.or activities; (3) to be ordered on the basis of l specifications set forth in manufacturer's published product description; I and (4) not associated with a loss of safety function. I I I I I l-l Component - A piece of equipment such as a vessel, piping, pump, valve or l l core support structure, which will be combined with other components to l form an assembly. l I I i I I ). I Contaminants - Foreign materials such as mill scale, dirt, 01.1, chemicals l landanymatterthanrendersafluid,solidorsurfaceimpureandunclean l I .I according to preset standards of acceptable cleanness. l I I l I l Contractor - Any organization under contract.for furnishing items or I services. It includes 'the terms Vendor, Supplier, Subcontractor, .l l Fabricator and sub-tier levels.of these where appropriate. l 1 l I I j l Defective Material - A material or component which has one or more l l g characteristics that do not comply with specified requirements, l g L O l Deviation-Anonconformanceordeparture.ofacharacteristicfrom l I specified requirements. I l' l 1 I I I Documentation - Any written or pictorial information describing, I defining, specifying, reporting or certifying activities, requirements, I procedures, or results. 1 I l-1 I I Examination - An element of inspection consisting of investigation of I l materials,-components,suppliesorservicestodetermineconformanceto -l those specified requirements which can be determined by such I investigation. Examination is usually nondestructive and includes simple l I. physical manipulation, gaging, and measurement. I 1 1 'l I 4 l Dndling - An act of physically moving items by hand or mec'ianical means, I lbutnutincluding-transportmodes. l z. l 1 I I Q-l I l I ~ l A l TOPICAL REPORT lREV. 6 l I P I lDATE 6/10/83 l l 1 SECTION: TERMS AND DEFINITIONS (PAGE C-3 1 i L l l l 2 1 I I l .-..~ l-1 I I l Inquiry - A document that contains the necessary information for a vendor 4 l I to make a proposal. ~ An inquiry may include specifications pertaining to I O i i l the equipment, materials, or services proposed to be procured. l I l l Inspector (Owner's) - A qualified inspector employed by the Owner whose l I 1 1 duties'. include the verification of quality related activities or I I i l ' installations or.both. l l l l l l Inspection - A phase of quality control which by means of examination, l observation or measurement determines the conformance of materials, 1 -l supplies, components, parts, appurtenances, systems, processes or l . structures to predetermined quality requirements. 1 I l Item - Any level of unit assembly, including structure, system, l l subsystem, subassembly, component, part or material. l I I 1 I I l. Job Order (J.O.) The Job Order is the document used for identifying and l I I administratively controlling the work effort on station equipment and I .I l systems. It identifies applicable procedures.and drawings; documents l I l reviews, approvals and results of inspections and tests; and provides a I 1 l l mechanism for planning, scheduling and authorizing work. l 1 l' l I t l l Manufacturer - One who constructs any class of component, part, or l appurtenance to meet prescribed design requirements. I I Material - A substance or combination of substances forming-components, ~ l parts, pieces and equipment items. (Intended to include such as l machinery, castings, liquids, formed steel shapes, aggregates, and l cement.) i l i i l l 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 I safety restrictions. I I l i I l 'Q-l- 1 I l l. A l TOPICAL REPORT lREV. 6 l r l P l lDATE 6/10/83 l i l l.SECTION: TERMS AND DEFINITIONS lPAGE C-4 I I -l L I I I I i 1 I t .--.y-= .w,,, ,.v.,w,-w,-3.-c,,,,,,,r,-,,m-, -- w w e ee4-,,,,,,.,4,,-, -w-w,-=w,,-w,,w-,,,,#-=,...m,,-,~.,,..-.ww._,,.me-+,-t-ef.,-ww----wy,w-----m-,,e--* l l I I I Nonconformance - A deficiency in characteristic, document, or procedure l p which renders the quality of an item unacceptable or indeterminate. V l Examples of nonconformance include: physical defects, test failures, l incorrect or inadequate documentation, or deviation from prescribed I processing, inspection or test procedures. l l l l l 1 Ob.iective Evidence - Any statement of fact, information, or record, I either quantitative or qualitative, pertaining to the quality of an item l l or service based on observations, measurements, or tests which can be l l verified. I I l Operation - The' total of administrative, maintenance and monitor l activities necessary to sustain the power generating capabilities of the I plant after initial start-up. l l l Owner - The person, group, company or corporation who will have or has l title to the facility or installation under construction. I I I I I l Package - A wrapping or container including its contents of materials or l equipment. 1 I Packaged Unit - An assembly of items and parts which can be disassembled I without destroying the integrity of the individual parts. I I I I I I Part - An item which has work performed on it and which is attached to I and becomes part of a component before completion of the component. ~ l l Plant - The equiment, piping, structures, buildings and property that I comprise an installation or facility. I I I I I l Procedure - A document that specifies or describes how an activity is to I be performed. It may include methods to be employed, equipment or l materials to be used and sequence of operations. l l l l 1 I l l I O' i i i i l A l TOPICAL REPORT IREV. 6 l l P l lDATE 6/10/83 l l 1 SECTION: TERMS AND DEFINITIONS lPAGE C-5 l l L I l l l 1, I l I I I I l Procurement Documents - Contractually binding documents that identify and l m define the requirements that items or services must meet in order to be I I considered acceptable by f.he purchaser. I l. I I l l Project - A planned series of activities including all actions necessary l ltoprovide, utilize,andmaintainafacilityorportionthereof. l 1 I Proposal - A bid, usually written by a vendor in response to an inquiry, I which provides the issuing party with the vendor's proposed c.ompliance to l !theinquiryandthecost. I I I I Purchase Order (or Contract) - A document authorizing a vendor to provide l equipment, material or services in accordance with stated terms and l conditions. l l Purchaser - The organization or organizations responsible for issuance l l and administration of a contract, subcontract, or purchase order. l I l I l l Q-List - A list which specifically identifies those structures, systems l O i g and components whose failure could cause an uncontrolled release of i g l radioactivity, or those essential for the safe shutdown and immediate and l llong-termoperationfollowingaLossofCoolantAccident. l 1 I Qualification (Personnel) - The characteristics or abilities gained l through training or experience or both that enable an individual to i perform a required function. ~ l I Qualified Party - A person or organization competent and recognized as l knowlegeable to perform certain functions. l l l 1 I l Qualified Procedure - A procedure which incorporates all applicable codes l and standards, manufacturer's parameters, and engineering specifications l and has been proven adequate for its intended purpose. l I I I I I I I I f~N I l' I I O l A l TOPICAL REPORT-lREV. 6 l l P l lDATE 6/10/83 l l l SECTION: TERMS AND DEFINITIONS lPAGE C-6 l l L l l l 1 I I I I I I l l Qualified Vendor List - A listing of vendors having quality assurance l I h l programs consistent with the requirements of applicable portions ~of I r l .l 10CFR50, Appendix 8. l l 1 I I l Quality Assurance - All those planned and systematic actions necessary to l lprovideadequateconfidencethatanitemorafacilitywillperform l satisfactorily in service. l l 1 1 l l Quality Control - Those quality assurance actions which provide a means l to control and measure the characteristics of an item, process, or i facility to established requirements. l l l 1 l l Receiving - Taking delivery of an item at a designated location. l l l l l l Repair - The process of restoring a nonconforming characteristic to a l lconditionsuchthatthecapabilityofanitemtofunctionreliablyand l safely is unimpaired, even though that item still may not conform to the l loriginalrequirement. Report - Something (document) that gives information for record purposes. I I Review - An element of inspection to determine conformance to specified l requirements, which can be determined by examination of documents and l activities. 1 I l Rework - The process by which a nonconforming item is made to conform to ~ l l a prior specified requirement by completion, remachining, reassembling or l ,1 other corrective means. 1 I I Safety-Related - The term " safety-related", as used in this program, l refers to those materials, parts, components, systems, structures and l consumeable items classified as "Q" and so identified on the Q-list l applicable to each nuclear plant. l l 1 I I l I l l Q l i I I l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l l SECTION: TERMS AND DEFINITIONS lPAGE C-7 l l L l l l l l I I I I l l l Source Surveillance - A review, observation, or inspection for the i p_ lpurposeofverifyingthatanactionhasbeenaccomplishedasspecifiedat l the location of material procurement or manufacture. l-1 I I I l Specification - A concise staterrent of a set of requirements to be l satisfied by a product, material or process indicating, whenever l appropriate, the procedure by means of which it may be determined whether l the requirements given are satisfied. I I Standard - The result of a particular standardization effort approved by l a recognized authority. l l l l 1 l Storage - The act of holding items at the construction site or in an area l other than its permanent location in the plant. I l l Subsystem - A group of assemblies or components or both combined to l l performed a single function. 1 I i l l q l Surveillance - The continuing analysis and evaluation of records, methods I U and procedures, including the act of verification, to assure conformance l l with technical requirements. 1 I l l I l System - A group of subsystems united by some interaction or I interdependence, performing many duties but functioning as a single unit. I g l I 1 System Performance Test - A test performed on a completed system I including electric, instrumentation, controls, fluid and mechanical I subsystems under normal or simulated normal process conditions such as l temperature, flow, level, and pressure. I I I I I l Testing - The determination or verification of the capability of an item l to meet specified requirements by subjecting the item to a set of I physical, chemical, environmental or operating conditions. l l l l l l l l l 1 I I O I 1 l l I l A l TOPICAL REPORT IREV. 6 l l P l lDATE 6/10/83 l l l 1 SECTION: TERMS AND DEFINITIONS IPAGE C-8 l l L I I I l l l 1._ I I I I I I Titles - Titles of individuals, such as Quality Assurance Manager, when I used in the~ TOPICAL report assigns the responsibility of' performing the I requirement to the noted individual or his appointed designee. I I I I I l Ransit - The state of being conveyed or transported from one place to l' I another. I I l 'Trans'it Carrier '(Open) - Trucks, trailers, railroa'd cars, barges, l
- 1. aircraft or ships which do not afford items protection from the l-environment.
l lTransitCarrier(Closed)-Trucks, trailers,railroadcars, barges,. I aircraft or. ships which provide protection of items from the environment I by nature of their closed design. I I lUse-As-Is-Adispositionwhichmaybeimposedforanonconformancewhen I it can be established that the discrepancy will result in no adverse I conditions and that the item under consideration will continue to meet-l l all engineering functional requirements including performance, I maintainability, fit and safety. l l l 'I Vendor'- Any organization under contract for furnishing items or l l services. It includes the terms Contractor, Subcontractor, Supplier, I fFabricatorand.sub-tierlevelsofthesewhereappropriate. l l l Verification - An act of confirming, substantiating and assuring that 'an ~ I activity or condition has been implemented in conformance with the i t specifled requirements. I I ( Work Instructions - Written instructions used to transmit detailed I I infomation on the specific measures necessary to comply with the 1 [ requirements,of quality assurance procedures or any complex or difficult l quality-related task. I I I j< l' I l l l 1 O l A I TOPICAL REPORT lREV. 6 l i-i i l P l lDATE 6/10/83 1 i. 1 1 SECTION: TERMS AND DEFINITIONS lPAGE C-9 l I L l l l t l l-I i _ _ _,.. -. _... ~. _ _ - - - - I I l 1 l Work Package - A work package is a collection of applicable documents, I such as procedures, cleanliness control forms, inspection and test forms, ,I hold card forms, Ignition Source Permits, drawings, technical manuals, I letc.,neededtoperformthejob. I I I I I I I I I I I I I I I l I l I l I l 1 I I I I I I I I I I I I I I I I I I I O I l l l l 1 1 I i 1 I I I I I I I I I I-1 I I I I I I I I I I I l l l l 1 I I I I I I I I I I I I I O I i i i l A I TOPICAL REPORT IREV. 6 l 1 P l lDATE 6/10/83 I I 1 SECTION: TERMS AND DEFINITIONS IPAGE C-10 l i L 1 I I I I I l I I I l l 1.0 ORGANIZATION I l I 1.1 SCOPE I I l-l This section describes the AP&L organizational structure and l lresponsibilitiesforestablishingandexecutingtheQualityAssurance l Program for AP&L operational nuclear plants in compliance with 10CFR50, l Appendix B and applicable Regulatory Guides and ANSI Standards identified l l in the Introduction. It also includes a description of the interfaces l l with other organizations who may be delegated the work of establishing l-and executing portions of the Quality Assurance Program. The AP&L l lCorporateOrganizationrelevanttotheoperationofitsnuclearplantsis l l shown in Figure 1. l l l l l 1
- 1. 2 GENERAL RESPONSIBILITIES l
l 1 1 I l The ultimate responsibilities for operational nuclear plants within AP&L, l l including Quality Assurance, lies with the Energy Supply Sen'ior Vice l President. He provides management assessment of the Quality Assurance l Program through review of QA Audit Reports and reports of NRC activities. I I ,I .l 1.2.2 l l lTheAdministrativeServicesVicePresidentisresponsibleforthe l l purchasing functions affecting plant operation as described in Subsection l l1.3. ~ I l I I I I I I l l I_ l l l i l l l r i I [ l I I i l l I 1 l l O l l l l N/ l A l TOPICAL REPORT IREV. 6 l I P l lDATE 6/10/83 I I I SECTION: 1.0 ORGANIZATION IPAGE 1-1 l l L l l l l l l I i i l I 1 l I ~1.3i CORPORATE SERVICES I I . O i I i i-I
- 1. 3.1 i
i l' I l-j i Corporate Services is responsible for the procurement of materials, parts l l and components requested by Little-Rock General Office.(LRGO) personnelj-I and.for supporting the procurement activities at the plant. Procurement l organization is noted in Figure 2. l I 4 -l 1.3.2 l l l ' i The Nuclear Buyer reports to the Supervisor of Purchasing who reports to i l the Manager, Purchasing and Stores and is responsible.for the following l ~ ldutiesandactivities: l 4 - l I ] l 1. Prepares purchase orders based upon receipt o'f reviewed and I approved Purchase Requisitions. l 1-l L i 1 l l 2. Performs the commercial interface functions between AP&L and l l contractors or vendors. l l 3. Assures that quality documentation prepared by Energy supply l I personnel are included in purchasing documents. l i I i I I 1
- 1. 4 ENERGY SUPPLY l
} l 1-I I I l Energy Supply, headed by the Energy Supply Senior Vice President is l I l l responsible for all activities related to the operation of AP&L Nuclear . l l l Plants. These activities include as a minimum: design, modification, I [ l maintenance,inserviceinspectionandtest,operationandthose i additional activities discussed in Sections 2 through 18 of this manual. l l Within Energy Supply, the Nuclear Operations and Energy Supply Service l I organizations are involved in activities requiring execution of the i Quality Assurance Program (See Figure 3). l l l l l I O l A I TOPICAL REPORT lREV. 6 l i i i l l l P l lDATE 6/10/83 I l l SECTION: 1.0 ORGANIZATION (PAGE 1-2 l i l L i i l I I I l -,g ve-*'-WV t "*se War g-yne t w w-y-+w-w" --va'w-~+v-we m y-vw 6 re ' =,- w wr wrmw mw w w "* w*wwm = vr-vNm wrv "w-* w=-mt w w - -- ww w& We-'P -e-wm'e'tSt'm*'**-'w=&w ,- c I 1 l l i 1.4.1 Energy Supply Services l l 4. x,. O-I _l Energy Supply Services is under the direction of the_Fnergy Supply 'l ' l l Services Director, who reports to the Energy Supply Senior Vice l President. The Energy Supply Services Director is responsible for l lprovidingsupporttoAP&Lnuclearplantsintheareasofquality l l assurance, administrative services, engineering service.s and technical le I r services. g His duties include providing technical direction, l I administrative guidance and supervision to the: I l l I Energy Supply Administrative Services General Manager l l a. F EngineeringServicesGen[eialManager - -, Technical Services General. Manager ' l . b. l c. I l l d. Quality Assurance Managei-l l l1.4.1.1 Quality Assurance Manager l I ' ' ' ~
- The AP&L Quality Assurance Organization (QAO) as shown in Figure 4 is l
y I under the direction of the Quality-Assurance Manager, who reports to the 1 ON I g Energy Supply Services Director. The QA0 performs review, surveillance, I g l inspection and audit functions during the operational phase of AP&L8 s l l nuclear plants and is independent of Nuclear Operations, and from cost I g I and scheduling considerations when opposed to safety and quality l l considerations. e l I ~ l ~
- ThedutiesandresponsibilitiesoftheluslityAssuranceManagerinclude l-g I
the following: l 1 I ~ g. i 1. Develop Quality Assurance Program requirements for l-l modification, operation, and maintenance activites related to l the safety-related (Q-listed) systems, structures, and I components in AP&L nuclear plants. l l l I l I l ~ i 1 l l l i s I I -C1 1 I i 1 t l A .I TOPICAL REPORT lREV. 6 l l p-l lDATE 6/10/83 l l l SECTION: 1.0 ORGANIZATION lPAGE 1-3 l l L l l l l 1 l I I. _ _ _. = _ _ _ _ _.,,.. _ s d g g V l ~ l l 2. Audit of the quality assurance activities as described in l V Section 18 of this manual. I O. l l g ~ l g Review,. approval and verification of the quality assurance l 3. h I requirements placed upon contractors or vendors that provide 1 4 l g equipment, material, or services for AP&L nuclear plants. l g I l
- 4.
Authority to stop work where conditions exist that prohibit l l effectiv,e quality control. inspections, or if faulty materials, l in. correct workmanship or procedures are detected. g g e _ ls; g g l v. - ~5.
I - I .rev,isions thereto.' l 1 I i l l '6: - Review and approval of QA programs for outside organizations l ^ participating in the AP&L QA program. - g u I g l I ~ Serve as a member of the Safety Review Committee. g ~ g. '7. g I i 8. Provide,and maintain a qualified and suitable trained staff to i ~' I carry out required staff' functions. l 'l 1 y l 3 1 s ~, 'I 9. Formulate prograr.s for maintaining.the professional competence l of pdrsonnel within the QA0 and provide assistance in QA I I l I, training and indoctrination programs for division management,- .I f engineering and plant personnel whose activities affect ~ 1. quality. I { l l .I l m I l l 10. Provide technical direction and guidance to the Quality l. ? Engineering Supervisors. l I l' l ~ l l l-i l I l l l I 1 l N I g g i f] I I I I / i I A l TOPICAL REPORT lREV. 6 l 1 P l,. .lDATE 6/10/83 l I -. L,1 l-1 SECTION: 1.0 ORGANIZATION lPAGE 1-4 l ~ I L %l _, I l l r.- ,I l-N 9....g
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1 1.4.1.1.1 Quality Engineering Supervisor I
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i TheQualityEnkineeringSupervisorreportstotheQualityAssurance l
g 3
- lHanager, supervises QA Engineers and Auditors / Inspectors as assigned, l
l and assists the Quality Assurance Manager in the coordination of I
I l
- activities within the QA Section.
The Quality Engineering Supervisor may I
also perform duties normally assigned to Quality Assurance Engineers.
1 I
l l
l l
1.4.1.1.2 Quality Assurance Engineers I
i y
I l
l l The Quality Assurance Ensineers (QAE's) report to a Quality Engineering i
g Su' pervisor, as assigned.
The Quality Assurance Engineers are to be l
^
l familiar with the Quality Assurance Program and associated procedures, I
j I
l 10CFR50 Appendix B, regulatory guides, codes, and standards that address l
I l u q>uality assurance. They also possess the necessary functional l
l' independence and authority to:
identify quality problems, initia'te, I
l g
l recommeyd,orprovidesolutionsthrough;designatedchannels,and, verify i
j l implementation,of solutions.
Specifically:
I A'
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<The QAE's[are to have the authority to inspect, audit or review l
g g
l practices, records, files, instructions, directions or l
g documents concerned with all areas affecting quality.
I I
2.
The QAE's are to schedule and coordinate audits or surveillance i
efforts in the areas assigned, document findings, and report I
l#')
results to the Quality Assurance Manager and the Manager of the
~
j l
f audited area.
I
~
I I
I l
l 1.4.1.1.3 Quality Assurance Auditors / Inspectors l
l l
t l
l 1
i l
The Quality Assurance Auditors / Inspectors report to the Quality I
l-EngineeringSupervisorandassisthimintheimplementationofthe I
g l
l program by performing audits and inspections as required to assure proper l
lapplicationoftheQualityAssuranceProgram.
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- 1. 4.1. 2 Technical Services General Manager l
I I
O l
l I
The Technical Services General Manager reports to the Energy Supply l
lServicesDirectorandisresponsibleforprovidingsupporttoAP&L l
1 nuclear plants in the areas of plant performance, maintenance and l
l availability, chemistry, environmental monitori.ig, metallurgy and l
His duties include the following:
l l
l 1
l l
1.
Provides technical direction and administrative guidance to:
l I
I I
i l
a.
Plant Performance Evaluation Manager l
l b.
Plant Maintenance Manager l
l c.
Availability Engineerir.g Manager l
l d.
Technical Analysis Manager l
1 1
2.
Assure conformance to the Quality Assurance Program by l
l instituting the necessary quality-related procedures and I
instructions within the Technical Services Department.
l n
l l
V -
g Provide for coordination of environmental surveillance programs 3.
g i
I l
4.
Direct development of programs aimed at maximizing efficiency l
l and availability.
I I
I I
I l
5.
Provide for review and analysis of outage data and make l
I g
recommendations for correct'ng deficiencies which affect I-g I
availability or performance.
1 I
I I
I l
6.
Direct the plant maintenance tupport activities that are l
'l assigned to the LRGO.
l l
l 7.
Serve as a member of the Safety Review Committee.
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l 8.
Provide and maintain a qualified and suitably trained staff to l
I carry out required departmental functions.
I O
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,l 1.4.1.3 Engineering Services General Manager
,I 4
i I
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 l
following:
l l
l l
l l
1.
Provide technical direction and administrative guidance to:
l l
l l
l l
a.
Mechanical Engineering Manager i
b.
Electrical Engineering Manager l
l c.
Civil Engineering Manager l
l d.
Iitstrumentation and Controls Engineering Manager l
l l
2.
Assure conformance to the Quality Assurance Program by l
g l
instituting the necessary quality-related procedures and l
V instructions within Engineering Services.
I I
3.
Provide for review and approval of LRGO design and engineering l
I activities performed by contractors, vendors, and AP&L l
personnel.
I 1
I l
,I 4.
Provide for review and approval of procurement documents for
~
l equipment, a;aterial and services for LRGO engineering projects, l
as appropriate.
I I
l S.
Provide and maintain a qualified and suitable trained staff to l
carry out required departmental functions.
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l 1.4.1.4 Energy Supply Adr.inistrative Services General Manager i
l-l l
I l The Energy Supply Administrative Services General Manager reports to the l
l Energy Supply Services Director and is responsible for the development of l l administrative progt-ams, systems and services supportive to management.
l l.His'dutiesincludethefollowing:
l 1
l l
1.
Provide technical direction and guidance to:
I l
l a.
Energy Supply Training Manager l
l b.
General Services Manager l
l Planning, Scheduling & Cost Control Manager c.
l d.
Contract Administration Manager i
I I
I I
l 2.
Maintain overall department fiscal direction and control, and l
l provides supportive accounting functions.
I I
3.
Provide contract administration and administration of l
p procedures for Energy Supply Little Rock General Office (LRGO)
I d
l activities.
I l
4.
Administration of the training and development effort for l
l Energy Supply.LRGO personnel.
l I
I I
I l
5.
Ancillary support services to Energy Supply operation sections.
I I
l'~
l l
I 6.
Provida and maintain a qualified and suitable staff to carry I
out required departmental functions.
}
l 7.
Serve as a member of the Safety Review Committee.
I I
1 I
I i
1.4.2 Nuclear Operations l
l I
I I
l Nuclear Operations is under the direction of the Nuclear Operations Vice I
President who reports to the Energy Supply Senior Vice President and is i
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I responsible for the formulation, licensing, implementation and discharge 1
of operating policies and procedures relative to nuclear plant operations l and for nuclear fuel management.
His duties include the following:
I l'
l l
l
-l 1.
Provide technical direction and administrative guidance to the:
1 I
1.
i I
a.
Plant's General Manager I
l i
b.
Nuclear Services Manager l
I c.
ANO Project Manager
.I l
d.
Licensing Manager
.1 l
'2.
Assure conformance to the Quality Assurance Program by l
I instituting the necessary procedures and instructions within
-l the Nuclear Operations Department.
I I
3.
Provide for review and approval of design and engineering l
I performed for the operating nuclear plants.
I I
I I
I I-4.
. Provide for review and approval of procurement documents for 1
equipment, material and services.
I I
l 5.
Provide for liason between AP&L and applicable regdlatory -
l
- 1.
agencies.
I I
I I
I i
6.
Provide and maintain a qualified and suitable staff to carry l
l out required departmental functions.
I I
7.
Provide for procurement and' design review of nuclear fuel.
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1.4.2.1 Nuclear Services Manager I.
I I
eG l
V i
l The Nuclear Services Manager reports to the Nuclear Operations Vice l-President and is responsible for providing the necessary support services I
related to the effective operation and maintenance of the AP&L nuclear l
l plants.
The duties include the following:
l l
l l
1.
Review, approval and coordination of design changes through the l
Little Rock General Office.
l l
l l
l l
2.
Review, approval and coordination of purchase requisitions and I
I g
contracts generated at the Little Rock General Office.
l l
l l
3.
Interface with other departments to assure effective l
implementation of Regulatory and Company requirements.
I I
I I
I l
4.
Communication interface dealing with all activities at the l
l l
nuclear plants.
0 l
l 5.
Provide. technical direction and administrative guidance to the g
g I
Nuclear Fuel Supervisor, who is responsible for the I
procurement, design review and performance evaluation of l
l nuclear fuel and to provide support to the plant in the areas l
l of reactor core performance and assessment of core design I
analysis.
1 I
l-1 I
l 6.
Serve as a member of the Safety Review Committee.
I I
I I
I l
1.4.2.2 Licensing Manager l
I I
I I
l The Licensing-Manager reports to the Nuclear Operations Vice President l
landisresponsibleforthecoordinationofalllicensingdocuments, I
requirements and revisions thereto which are required to be reviewed l
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l and/or approved by the NRC and for interfacing with the NRC.
The l
~ Licensing manager is also responsible for the review and approval of l Q-List changes and for the tracking of possible nuclear safety concerns l
ltoassuretimelyclosecut.
I i
1.4.2.3 Project Manager l
l l
The Project Manager reports to the Nuclear Operations Vice President and I
is responsible for providing services at the nuclear plant for field l
lconstructionactivitiesandformodifications'tothecontrolroom
,I simulators used for operator's training.
His duties include providing i
technical direction and administrative guidance to the Field Construction l Manager and the Simulator Project Coordinator.
I I
I I
I l
1.4.2.3.1 Field Construction Manager 1
I i
i l
l The Field Construction Manager is responsible for directing the l
lactivitiesofhisstaffrelatingtoworkassociatedwithplant l
q l
construction and modifications.
His duties include:
l V
I I
I l
l 1)-
Interface with other departments to assure effective l
l implementation of job assignments 1
I 2)
Provide cost and schedule controls for departmental activities l
l 1
3)
Provide technical and administrative guidance to the i
Con e.uction Quality Control (CQC) Supervisor.
The CQC I
Supervisor is responsible for the surveillance and inspection l
of activities performed under the direction of the Field l
l Construction Manager.
The CQC Supervisor is also responsible l
l-I for assuring adequate inspection points have been assigned for I
the work activity, inspectors have been certified to ANSI l
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l N45.2.6, directing the activities of the inspectors, and i
I interfacing with the Code Inspector for activities involved
.I Code items.
I l
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- 1. 5 PLANT ORGANIZATION I
I I
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i I
1.5.1 General Manager l
I I
l i
1.5.1.1 I
l l
l l
l l The General Manager reports to the Nuclear. Operations Vice President on I
the corporate level (see figure 5) and has direct responsibility for I operating the plant in a safe, reliable and efficient manner.
He is l
I responsible for operating the plant in accordance with the provisions of I
the operating licenses, including the on-site quality program.
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i 1.5.1.2 I
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l l The General Manager has the authority to shut the plant down if required l
landhasfinalapprovalofplantprocedures.
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l 1.5.1.3 l
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lTheGeneralManageristoprovidetechnicaldirectionandadministrative l guidance to the:
I l
1 I-I l
1)
Operations Manager l
l 2)
Maintenance Manager I
l 3)
Administrative Manager 1
4)
Engineering and Technical Support Manager 1
5)
Special Projects Manager I
6)
Manager, Nuclear Quality Control l
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l 1.5.2 Operations Nanager 1
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l The Operations Manager (Figure 6) is responsible for directing the actual l
' day-to-day operations of the plant.
He supervises the operating staff l and interfaces with the Maintenance Manager to accomplish l
operation related maintenance activities.
The Operations Manager is to l
provide technical direction and administrative guidance to the:
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1)
Operations Superintendents l
2)
Operations Technical Staff l
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l1.5.2.1 l
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lTheOperationsSuperintendentsreporttoandassisttheOperations 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
l surveillance tests and coordination of operation-related maintenance I
activities.
They are to assist the Operations Manager in the supervision l
of core refueling, which includes advance planning for the outage, plant i
q J
g preparation, equipment check-out and the refueling operations.
I I
l1.5.2.2 l
l 1
i The Shift Supervisors report to the Operations Superintendent and are l
l responsible for the actual operation of the unit and for the activities l
I i
of the operators during their assigned shift.
The Shift Supervisor is to l~
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be cognizant of operation activities being performed while on duty.
The i
Shift Supervisor on duty has the authority to shut down the unit if, in I
his judgement, conditions warrant such action.
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1.5.3 Maintenance Manager l
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The Maintenance Manager (Figure 6) is responsible for the maintenance of I
I plant equipment, facilities and planning / scheduling of station work 1
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l activities as defined by plant maintenance program implementing I
procedures and to assure that maintenance of equipment is conducted in l
V l conformance with applicable standards, codes, specifications and l-procedures The Maintenance Manager is also to coordinate ~
l operation-related maintenance activities with the Operations Manager and l
I g
is responsible to make repairs on any structure, system or component l
g l under his control.
The Maintenance Manager is to provide technical l
ldirectionandadministrativeguidancetothe:
I I
l 1.
Mechanical Maintenance Superintendent i
2.
Electrical Maintenance Superintendent l
l 3.
Instrument & Control Superintendent l
4.
Planning and Scheduling Supervisor l
5.
Senior Maintenance Coordinator l
6.
Shift Maintenance Superintendent l
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l 1.5.4 Engineering and Technical Support Manager l
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l The Engineering and Technical Support Manager (Figure-7) is responsible 1
O i
l for providing pla.it engineering support services as well as technical and i
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plant analysis and health physics support services to the plant staff.
l The Engineering and Technical Support Manager is.to provide technical I
direction and administrative guidance to the:
l l
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Technical Analysis Superintendent l
l 2)
Plant Analysis Superintendent
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l 3)
Plant Engineering Superintendent l
l 4)
Operations Assessment Superintendent 5)
Health Physics Superintendent.
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1.5.4.1 Technical Analysis Superintendent l
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l The Technical Analysis Superintendent maintains overall responsibility l
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for radiochemistry, chemistry and environmental programs at the plant.
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l l-1 1 The -Technical Analysis Superintendent is also responsible for maintaining l
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the Station Emergency. Plan and' ensuring the-plant staff.is capable of I
l implementing the. requirements delineated in the Plan and its procedures.
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1.5.4.1.1 l
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l' The Radiochemistry Supervisor reports to the Technical Analysis l'
l Superintendent and is responsible for analyzing the reactor plant water z
I conditions and providing recommendations to maintain conditions.
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'l -1.5.4.1.2 1
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I l
I
-l The Chemistry and Environmental Supervisor reports to the-Technical l
lAnalysisSuperintendentandisresponsibleforestablishingwater l_
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l ' chemistry criteria, analyzing secondary plant water and auxiliary water l
lconditionsandprovidingrecommendationstomaintainconditionswithin l.
l' acceptable limits.
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- l 1.5.4.2 Plant Analysis Superintendent l
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l.The Plant Analysis Superintendent is responsible for.the areas of plant 1
l performance, nuclear support and computer support.
A supervisor is-1 provided for each of these areas.
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1.5.4.2.1 l
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!- The Plant Performance Supervisor reports to the Plant Analysis I
- Superintendent and'is responsible for:
evaluating equipment and system l
l performance over extended periods, recommending methods of improving and I
(
maintaining good plant efficiency, investigating and evaluating equipment l
l malfunctions or failures and recommending corrective action to prevent I
recurrences, and coordinating the activities of the Inservice Testing l
l-l Program at the plant.
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1.5.4.2.2 I
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-l The Nuclear Support Supervisor reports to the Plant Analysis l-Superintendent and is responsible 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 1 -current accurate information to operations; collection and transmittal of I
g 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_
l fuel movements including new fuel receipt and inspection, fuel shuffling I
at refueling, inspection of irradiated fuel and shipment of spent fuel.
l l
l 1.5.4.2.3 l
I 1
The Computer Support Supervisor reports to the Plant Analysis l
l Superintendent and is responsible for the maintenance, revision and I
development of computer software for the plant monitoring computers and I
for providing technical assistance to the Nuclear Support Supervisor and l
lNuclearEngineersindevelopmentanduseoftestapparatusforevaluation l
4 l
of fuel, core and NSSS performance.
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1.5.4.3 Plant Engineering Superintendent i
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I The Plant Engineering Superintendent is responsible for drawing control, I
f I
I implementation and coordination of the Inservice Inspection Program and i
design and plant engineering activities at the plant.
The Plant l
lEngineeringSuperintendentistoprovidetechnicaldirectionand j
l administrative guidance to the:
l l
l l
l l
l 1)
Mechanical Engineering Supervisor l
l 2)
Electrical Engineering Supervisor l
I 3)
Drafting and Drawing Control Supervisor.
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l 1.5.4.4 Operations Assessment Superintendent I
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l The Operations Assessment Superintendent provides the capability to I
perform engineering evaluations of operating experiences which occur both I at the AP&L nuclear plants and at other nuclear power plants and to I
recommend corrective actions as a result of these evaluations to help i
plant operations personnel in preventing or dealing with similar I
ocurrences.
I I
l1.5.4.5 Health Physics Superintendent l
l 1
l The Health Physics Superintendent is directly responsible for and has the I
authority to implement the Health Physics program at the nuclear plant I
and to maintain radiation exposure as low as reasonably achievable I
(ALARA).
The Health Physics Superintendent has the authority to stop I
work in radiation areas if he evaluates that a potential for an l
I unanticipated excessive exposure to plant personnel or the environment l
may exist.
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U 1.5.5 y
Administrative Manager I
y i
I The Administrative Manager (Figure 8) reports to the General Manager and l
l aids him in the administrative aspects of the plant's operation.
The I
Administrative Manager directs the activities of the administrative staff I
and provides technical direction and administrative guidance to the:
I i
l -
1 I
i 1)
Office Services Supervisor l
l 2)
Material Management Supervisor I
y l
l 3)
Human Resources Supervisor l
I 4)
Training Superintendent I
5)
Plant Controller I
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'l The Office Services Supervisor is responsible for administration of the
- l '
l - clerical staff activities and the accumulation and disposition of quality l' assurance records related to all phases of the nuclear plant.
l l
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1 -1.5.5.2 I
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l l The Material Management Supervisor is responsible for plant procurement,
-I storage of materials, parts and equipment, issuance of tools and test I equipment ~and the disposal of surplus materials.
l l
l l
i 1.5.5.3 I
- l 1
l.
l
.I l The Human Resources Supervisor is responsible for employment, industrial l
l relations,industrialsafetyandfirepreventionandsecurity. Reporting y
I to him are the Safety and Fire Prevention Coordinators, the Security l
Coordinator, and the Employment and Industrial Relations Coordinator.
y l
O l
- 1. 5. 5. 3.1 l
I I-I revention Coordinators are responsible for l
The Safety and Fire o l conducting periodic checks to examine control of combustables, I
l housekeeping and other fire prevention / protection efforts as well as to l provide a centralization of OSHA and plant safety programs.
l l
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i 1.5.5.3.2 I
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l The Security Coordinator is responsible for coordination of the efforts I
of the security force-and to manage the operation of the security system.
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..,.. - - - -.. - - _... - _ - - - - - _ _ _. - ~ -. - _. -,... _ _. ~. _ _ _ _ _ - - - _ _ -..
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l 1.5.5.4 l
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The Training Superintendent is responsible for the training and l
retraining of plant personnel and of Little Rock General Office personnel I
l as' established by Plant procedures.
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1.5.6 Manager, Nuclear Quality Control l
1 I
l-l l The Manager, Nuclear Quality Control (Figyre 5) is responsibl.e for l
l verifying the implementation of the Quality Control Program at the plant l
and reports to and receives direction from the General Manager.
His l
duties include the following:
I i
l 1)
Provide technical direction and administrative assistance to l
the:
l l
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a.
Quality Control Supervisor l
b.
Quality Control Engineers l
g l
c.
Quality Control Inspectors i
N,.;
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l 2)
Interface with the Quality Assurance Manager or his l
representative for technical assistance in resolving j
significant conditions adverse to quality.
l l
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3)
Authority to place an item in a nonconforming status when such l
I an item is determined to be in violation of purchase documents,
~
l applicable codes and standards or FSAR requirements.
l l
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4)
Assuring surveillances, inspections and reviews of plant l
activities and documents are conducted in accordance with l
plant procedures.
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-l 1.5.7 Special Projects Manager l
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l The Special Projects Manager is responsible for the administration and l
control of special projects pertaining to plant operations, maintenance I
and administration and is to provide technical direction and administrative guidance to a staff of Special Project Coordinators.
l Additional duties include:
l 1
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l i
1)
Serving as chairman of the Plant Safety Committee l
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l 2)
Interfacing with onsite regulatory agencies l
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l 3)
Providing evaluations and recommendations to regulatory l
l requirements and meeting regulatory commitments.
l l
l l1.6 INDEPENDENT REVIEW ORGANIZATIONS
,I I
i lInadditiontotheresponsibilitiesofkeyindividualswithintheAP&L q
l organization who are involved with the overall quality. program, AP&L has l
lestablishedthefollowingcommitteesasamanagementtoolto l
V l
independently review activities occurring during the operational phase of l
a nuclear plant.
I i
1.6.1 Safety Review Committee (SRC) 1 I
The SRC reports to the Nuclear Operations Vice President and is
~
l responsible for providing off-site independent reviews, and/or audits l
relating to:
the Safety Analysis Report, Technical Spacifications, l
Procedures and changes thereto; unreviewed safety questions; violations, l
deviations and reportable events; and any other matter involving safe l
operation of the nuclear plant which the committee deems appropriate or l
I is referred to them by the on site operating group.
The SRC is also to l
l review the reports and meeting minutes generated from the Plant Safety l
Committee.
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l 1.6.2 Plant Safety Committee (PSC)
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-l The PSC reports to the plants' General Manager and is responsible for l
l-reviewingactivities_specifiedintheAdministrativeTechnical 1 - Specifications for the purpose of:
l l
1 l
l l
1)
Rendering determinations in writing with regard as to whether
,l or not an unreviewed safety question (defined by_10CFR50.59) is l
l involved; and i
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?
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i.
-I 2)
Furnishing written recommendations to the plants' General I
Manager for approval of disapproval.
i I
I l
These activities include changes-to plant procedures and Technical l
l Specifications, proposed modifications to plant systems, changes to l
[
plant security and emergency plans, and review of facility l
l operations to detect potential nuclear safety hazards.
!l I
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l l-l.1.6.3 Committee Structure O
a I
t i
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l l-The organization structure and administrative requirements specific-to l
i each committee'are' described in the plant's Technical Specifications and i
l in internal-procedures / documentation.
l i
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l l
- 1. 7 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES I
i l
l-l l
l As owner and operator, AP&L assumes full responsibility and authority for I.
,I the plant including-action to assure that the plant is operated in l
accordance with sound engineering practices, Licensing requirements and I
applicable codes, specifications and procedures.
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l l
lEachsupplierofequipment,materialorservicesandeachmaintenanceor l
l modification contractor is responsible for administering the applicable I
. quality control functions as requiret by AP&L.
The Quality Assurance and l
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- 1. Quality Control organizations are responsible.for assuring by I
surveillance, inspection, audit or review of objective evidence (e.g.,
.I audit reports conducted by others, etc.) that these. functions are l
~
accomplished for systems and structures that affect the safety and I
integrity of the plant.
l I
I I
I I Visits to manufacturer's shops.by Quality Assurance organization l
lpersonnelareconducted,whendeemednecessary,baseduponsafety l
significance,. complexity, method of acceptance'and past history of the I
vendor,.to establish product quality and to assure that quality assurance
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I and quality control programs function in accordance with AP&L l
requirements.
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l 2.0 QUALITY ASSURANCE PROGRAM l
l
()
l l
l
_l 2.1 SCOPE l
1 I
l-I l
This quality program is to assure that AP&L nuclear plants are operated l
in a safe, reliable and efficient manner and in accordance with NRC' l
regulations, applicable industrial standards and codes and applicable l
Company policies, rules, procedures and licensing documents. A matrix of l QA Procedures cross-referenced to each criterion of 10CFR50,. App. B, is l
lincludedinTable2tothismanual.
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2.2 GENERAL I
i 1
l 1
l 2.2.1 l
l l
,I This quality program is applied 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 l
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
the Q-list for each nuclear plant.
When structures, systems and l
components as a whole are on the Q-list, portions not associated with a l
loss of safety function as determined by Engineering are to be considered l
l Non-Q, unless otherwise dispositioned by Engineering.
l l
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- Expendable and/or consumable items are to include, as a minimum:
l l
nuclear fuel, weld rods, boric acid, and diesel fuel.
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2.2.2 l
l 1
I I
l The Q-list is under the control of the Licensing Manager.
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
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t l Q-list and changes thereto are performed in accordance with approved l
,f3 procedures.
Changes to the Q-list require review / approval by the J
l discipline Engineering Manager, Quality Assurance Manager and Licensing i
Manager.
1 I
l2.3 l
RESPONSIBILITIES l
l l2.3.1 l
l l
l AP&L recognizes that quality assurance is an interdisciplinary function I
involving many organizational groups, encompasses many functions and l
I activities and extends to various levels in all participating l organizations (from the Energy Supply Senior Vice President to all I
workers whose activities may influence quality).
This quality program l
l designates responsibilities and duties of specific individuals, which may l
be performed by their. appointed designees.
l l
1 l
2.3.2 n
l This quality program assigns the responsibility for quality to the l
departments performing the work and includes as a basic requirement that l
individuals responsible for verification of conformance are qualified and I 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.
l l
l-1 I
l 2.3.3 l
l 1
1 I
l This quality program also includes provisions that require suppliers, l
~
contractors, subcontractors, consultants, etc. to maintain and use l
l quality assurance programs reviewed and approved by the Quality Assurance l
Manager.
Audits or surveillances by the QA0 provide assurance of l compliance with applicable procedures.
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2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-2 l
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l 2.3.4 l
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.l The' Nuclear Fuel Supervisor within Nuclear Operations is responsible for l_
I 1
the assurance that nuclear fuel used in AP&L nuclear plants is designed, I
I 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
d ladministrativeprocedures.
These procedures include the receipt, s
l inspection, handling, storage, and accountability of Special Nuclear l
Material (SNM).
The Nuclear Support Supervisor maintains a 1isting of l
l l
those individuals qualified to perform receipt inspections.
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l 2.4 PROCEDURES l
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2.4.1 l
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l l Activities which affect quality are defined in appropriate procedures, l
which are developed to cover AP&L administration and control.
The l procedures state the policies and instructions necessary to fulfill the l
O i
intent of the program.
Procedures provide for standard forms, lists, and i
I check-offs used in documenting the inspections, certifications, reviews, l
surveillances and audits.
The program and the procedures shall be' l
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 l
l instructions are contained in the documents listed in Table 3.
l l
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-l 2.4.2 l
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l Procedures assure that activities affecting quality are performed under i
suitably controlled conditions.
Controlled conditions include the use of l appropriate equipment; suitable environmental conditions for performing l
the activity such as adequate cleanliness; and assurance that required I prerequisites for the given activity have been satisfied.
Administrative l
' procedures also assure that the need for special controls, processes, l
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l commitments in the program description previously accepted by the Nuclear I
S g
Regulatory Commission.
Changes to the program description that reduce V
l the commitments are to be submitted and approved by the Nuclear l
Regulatory Commission prior to implementation.
The Quality Assurance y
l Manager is to determine if changes do or do not reduce the commitments of
'l this quality program.
l l
,I 2.6 PERSONNEL I
I l
2.6.1 l
1 1
lEmployeeswhosedutiesandresponsibilitiesarerelatedtothe, quality I program activities at or in support of the nuclear plant are to l
participate in appropriate indoctrination and training programs to assure I
that suitable proficiency is achieved and maintained in the work they are l
performing.
Such training shall include, as a minimum:
plant security; I discussion of the overall Company policies, procedures and instructions I
Ig which establish the quality program; an explanation of the AP&L quality I organizations; and a discussion of those procedures which implement the l
O-Ig quality program related to the employee's specific job-related activity.
I I
l l2.6.2 l
1 l
l The education, experience and responsibility requirements of individuals l
l involved in this quality program are documented in job descriptions which I
l l-g are approved and periodically reviewed by management.
Requirements for I
education, experience and proficiency levels are commensurate with the l
degree of importance of the job assignment.
Experience and training I
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 I
in Table 1.
Personnel whose qualifications do not meet those specified I
in ANSI N18.1-1971, and who are performing inspection, examination and I
testing activities during the operational phase of the plant,,are to meet I
the requirements of ANSI N45.2.6-1978, unless otherwise noted in Table 1.
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2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-5 I
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l Personnel performing inspection and examination activities are to be l
indoctrinated and trained to assure they are aware of the requirements I which govern their activity.
Inspection and examination personnel are to I
be qualified according to the applicable codes, standards, I
specifications, regulatory requirements and LRGO and plant procedures.
I Personnel performing inspections on those activities occurring during the 1 operational phase that are comparable in nature and extent to related I
activities occurring during initial plant design and construction are to I
meet the provisions of Regulatory Guide 1.58, rev. 1 (9/80) and ANSI l
N45.2.6-1978, in lieu of ANSI N18.1-1971.
l l
l l2.6.4 I
l-Personnel involved with welding or nondestructive examination of I materials, systems or components are to meet the appropriate I
qualification requirements of the ASME Boiler and Pressure Vessel Code, 1
Sections III and XI, or for structural welds, the American Welding i
Society (AWS) Structural Steel Code 01.1, and the American Society l
l Nondestructive Testing Standard SNT-TC-1A-1975, and certified to perform I
lthesetasksinaccordancewiththesecodesandstandards.
I I
l 2.6.5 l
l lPersonnelperformingauditsofthequalityprogramaretomeetthe
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l experience, training and qualification / certification requirements of I
I ANSI N45.2.23-1978, and regulatory guide 1.146 (8/80), unless otherwise I
noted in Table 1.
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2.0 QUALITY ASSURANCE PROGRAM lPAGE 2-6 I
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l 1 2.7 -PROGRAM REVIEW l
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.I 2.7.1 I
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I The Quality Assurance Manager is responsible for'a review of-this program I
on an annual basis to determine the effectiveness and proper.
I implementation of the quality program.
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2.7.2 I
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i-I Management reviews of the status and adequacy of the quality program are I
accomplished through regular reports and presentations by the QA0 and i
l through' reviews of quality assurance audit reports. -Quality Assurance l
reports supply data on the status of outstanding audit and corrective I action items and may identify the status of other significant quality l'
I program activities as requested by management.
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2.0 QUALITY ASSURANCE PROGRAM IPAGE 2-7 l
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-l 3.0 DESIGN CONTROL.
l-l g
3.1 SCOPE-l l
l, l
l Design activities are to be controlled to assure that proposed plant I
1g changes to the structures, systems, equipment and components conform to I
g 1
l' applicable-regulatory requirements and that design bases are correctly l
l j
g tran' slated into appropriate design. documents.
Design-Control activities l
l!
I are to be in accordance with the requirements of Regulatory Guide 1.64 -'
I Rev. 2'(6/76) unless otherwise noted in Table 1.
l 1
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l 3.2 ~ GENERAL I
1 l
1 1-I l -3. 2.1 '
l I
3 I
l Engineering Services and Plant Engineering are to be responsible for the I
continued upgrading and modification of plant design.
Design' documents l
I (drawings, specifications, procedures and instructions) originating or n
l released through these departments are to be based upon the required l
regulatory requirements, licensing based documents, functional
- l l
requirements, quality standards and design bases in accordance with NRC l
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;
l l
inspection criteria.
Those design activities performed by individuals 1-l 1g within Engineering Services are controlled by the use of LRGO-Energy
[I-l Supply Procedures.
Those design activities performed by individuals I
within Plant Engine' ring are controlled by the use of Plant l
e 2
l Administrative and Engineering Administrative Procedures.
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TOPICAL REPORT lREV.
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- l 1 SECTION:
3.0 DESIGN CONTROL IPAGE 3-1 l
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l l
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i I
l N w gr--tr t w a+1---*vr=-g-7yyySt e ur-e-e9ew a9-m e-me--
gp ww ey a-r w-p g-e g gg
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= y gr e wy e y--=re---'Wiw,W41--y'+-Fr-1e p g
- 14 Mag p-5
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I I
I I
i 3.2.2 i
O D
l I Design standards and requirements are to be at least equivalent to those I
employed during the construction of the plant and are to be consistent I with the technical specifications and license requirements.
I I
l l
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3.3 DESIGN INTERFACE I
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l l
l Design control activities include measures for the identification and I
control of design interfaces between the various engineering disciplines I within the department, between LRGO and plant engineering personnel, I
g between engineering personnel and other AP&L support organizations, and l
l between engineering personnel and firms / suppliers outside the AP&L I
l organization.
These measures include the development of procedures among I
the participating organizations for the review, approval, release, I
distribution and revision of documents involving design interface.
I Coordination of the interface control is the responsibility of the I
originating organization's management unless otherwise specified in an l
l g
AP&L procedure applicable to the design activity.
Design information l
V between interfacing organizations is to be documented and retained for i
permament records.
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3.4 DESIGN VERIFICATION l
l I
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l 3.4.1 l
l l
l 1
J To assure the design is adequate and the above requirements and I
procedures are implemented, Engineering Services for LRGO design or Plant l
Engineering for plant design are to verify the adequacy of the design l
I g
through the performance of design reviews, the use of alternate or -
I g
I simplified calculation methods, or the performance of a qualification I
testing program.
The extent and depth of design verification performed 1
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I by the responsible organization,is determined by.an assigned engineering l
reviewer based upon the importance and complexity of the design, the d
I degree of standardization and"its similarity with proven designs.
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3.4.2 I
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I l The verification process is to be performed by competent individuals or i
groups other than those who performed or supervised the design but who I
g I may be from the same organization.
This' verification, however, may be I
performed by the originator's supervisor "in~ accordance with departmentall l Procedures if he is the only individual in the organization competent to i
perform the verification.
Where changes to previously verified designs l have been made, design verifications are required for the change, I
including evaluation of the effects of the changes on the overall design.
I I
3.4.3 l-1 I
l When a test program is used to verify the adequacy of a design, it is to I
include suitable qualification testing of a prdtotype or initial I
I production unit under the most adverse conditions and' carried out in l
l accordance with documented procedures and/or instructions.
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5 I
3.4.4 l
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l Design work performed by organizations outside.of[ AP&L is to receive a i
documented review and approval by engineering personnel in accordance
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I with LRGO and plant departmental procedures; l
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3.5 DESIGN CHANGE I
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l 3.5.1 l
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I Methods for the preparation, review, approval and impl.ementation of I
design changes, including field changes, are documented in departmental l
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3.0 DESIGN CONTROL IPAGE 3-3
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l - procedures for Engineering Services and Plant Engineering.
Design l
I 1
o
_g changes are subject to review and verification by the same organization j
I which review and verified the original design unless otherwise specified I
in departmental procedures for design control.
If minor changes to an l
l approved design are required to meet plant requirements or conditions, 1
Field Change Notices (FCN).may be issued or otherwise documented by a l
l' cognizant' engineer and transmitted with the changes for review and I
approval in accordance with Plant Engineering Administrative Procedures.
I I
l 3.5.2 l
I Changes from specified design inputs, such as design bases, regulatory l
l requirements, codes and standards (including quality standards) are to be l
identified, approved, documented and controlled through applicable LRGO l and plant departmental procedures.
I I
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3.5.3 I
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l During preparation of a design change, the responsible engineering l
e lorganizationistoperformasafetyandenvironmentalevaluationper l
l 10CFR50.59 to verify compliance with the Final' Safety Analysis Report and l
ltodetermineifNRCapprovalofthedesignchangeisrequired.
The 1 evaluation is to be documented and then reviewed by the PSC.
I I
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3.5.4 I
I l-1 I
l Design changes are also to be submitted to the Manager, Nuclear Quality l
l Control prior to plant implementation to verify the use of appropriate l
l quality codes, standards and inspection requirements in the design l
I documents.
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3.0 DESIGN CONTROL lPAGE 3-4 l
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I el 3.6 - i'ESIGN RECORDS I
j'/ '
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(V; l The Pidnt Administrative Manager is responsible for mainta1Mng permanent I
s i
x lrecorosofthedesigndocumentsfortheconstructionandtestingphases.
1 In addition, he shall be responsible for maintaining records of the i
upgrading or modification of these documents as described in this l
l section.
The controls for maintaining these records are established by I
lspecificproceduresdescribedinSection17ofthismanual.
l These l
records provide the historic reference necessary for the safe and I
lreliableoperationoftheplant.
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3.0 DESIGN CONTROL IPAGE 3-5 I
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l 4.0 PROCUREMENT DOCUMENT CONTROL i
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l Requirements for the procurement of items and services are to be clearly l
lstatedanddocumentedtoassurethatapplicableregulatoryrequirements, l
l design bases, technical requirements and quality assurance criteria are l
lincludedorreferencedintheprocurementdocuments,whetherprocuredby l
l LRGO or plant procurement groups.
Procurement document control l
lactivitiesaretobeinaccordancewithLRG0andplantprocurement l
l procedures and are to meet the provisions set forth in NRC Regulatory l
Guide 1.123, rev. 1 (7/77) unless otherwise noted in Table 1.
l l
l l4.2 l
l l
4.2.1 l
1 l
lTheprocurementofmaterials,partsandcomponentsaregeneratedthrough l
I the preparation of a Purchase Requisition (PR) and subsequent issuance of l
,,U laPurchaseOrder(P0),orwhenadditionalservicesfromtheVendoris l
l required, through the preparation and issuance of a Contract.
The l
lprocurementofservicesisinitiatedthroughthepreparationandissuance l
l of a Contract.
The preparation, review, approval and issuance of these l
lprocurementdocumentsistobeinaccordancewithapplicableprocurement l
l and contract administration procedures.
Purchase Orders for items are l
lissuedthroughtheAP&LPurchasinggroupandContractsforitemsand/or l~
l services are issued through the AP&L Contracts Administration group.
l l
l l
1 l
l 4.2.2 l
l l
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1 l
l Procurement documents are to include or reference specific design I
lspecificationsfortheitemsorservicestobeprocuredwhichdefine I
specific codes, standards, tests, inspections, 2nvironmental,
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l qualifications, and records to be applied and/or furnished.
For standard l
,3 "of f-the-shelf" items, reference to the items catalog number and l
O l
identification number may be included on the procurement document in lieu l
lofadesignspecification.
New or revised specifications for replacement l
l items are to be evaluated by the responsible engineering organization l
lagainsttheoriginalspecificationfortheitem.
l The evaluation is to be l
in accordance with applicable engineering procedures and results in the l
lestablishmentofnewbaselineandtechnicalqualityrequirements,which l
l are to be used for subsequent procurements.
1 l
1 l
l 4.2.3 l
l 1
l l
1 1
Procurement documents are also to include the identification of quality I
assurance program requirements applicable to the items or services l procured.
Procurement documents also establish requirements for source l
lauditsandinspection,extensionoftheprocurementrequirementstolower l
l tier suppliers or subcontractors, and preparation and delivery of I
documentation.
These requirements may either be in the form of documents l
attached to the P0 or Contract or by incorporating them in the specific l
design specifications.
Quality programs are to be specified by invoking i
the appropriate sections of 10CFR50, App. B, the appropriate ANS1 l
lstandardsand/ortheappropriateAP&Lgeneratedqualityrequirementsfor l
l items or services.
The appropriate sections of the ASME Boiler and l
l Pressure Vessel Code are to be invoked for items originally designed to l
l meet ASME requirements.
I I
I I
I l
4.3 REVIEW 0F PROCUREMENT DOCUMENTS I
1 I
I i
l The responsible Quality Assurance or Quality Control organization, as identified in the LRGO and plant procedures for procurement and contract l
l administration activities, is to review all procurement documents to l
lassurethattherequiredqualityrequirements(includingsource l
l surveilla'ce and/or inspection) are imposed on suppliers / contractors.
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4.0 PROCUREMENT DOCUMENT CONTROL lPAGE 4-2 l
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l 4.4' CHANGES TO PROCUREMENT DOCUMENTS I
(]
l l
l Changes to procurement documents are to have the same degree of control l
landreviewasimposedontheoriginaldocuments.
Changes such as l
l inconsequential editorial corrections or changes to commercial terms and l
l conditions may be made by the Nuclear Buyer or Contract Administrator as l
l appropriate, after concurrence from the originator of the document.
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4.0 PROCUREMENT DOCUMENT CONTROL IPAGE 4-3 l
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l 5.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS l
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V l
5.1 SCOPE l
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5.1.1 j
l I
I I
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 minimu.m:
l administrative, general plant operations, start-up; shutdown; power l
operation and load changing, process monitoring, fuel handling; l
l modification;maintenanceandrepair;radiationcontrol;calibrationand l
test; chemical radiochemical control; plant emergencies; test and l
inspection; and quality assurance, quality control and LRGO activities in 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
l Table 1.
I l
l I
I
-,U 5.1. 2 I
I Instructions and procedures are also provided for the control of l
l activities relating to the repair, replacement or modifications to ASME l
Code,Section III, Class 1, 2 or 3 components required to be operable to l mitigate the consequences of a postulated accident.
l l
l l
l l
5.2 GENERAL l
l 1
l l
l 5.2.1 1
I I
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l Instructions, procedures and drawings are to include appropriate l
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
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5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-1 l
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l accomplished. Each procedure is to be sufficiently detailed so that a l
lqualifiedindividualmayperformtherequiredfuaction(s)withoutdirect q
I supervision and is to include measures to document the activity being l
l performed.
I l
l l5.2.2 I
l l
To assure the accomplishment of activities in accordance with approved I
instructions, procedures and drawings, each supervisor is responsible for l
lqualitycomplianceofhispersonnel.
Verification that activities are l
accomplished in accordance with approved instructions, procedures and I
drawings is obtained through ve.rious levels of surveillance and l
inspection by Quality Control personnel and through periodic surveillance l
landauditsbytheQAO.
l l
I g
REVIEW OF INSTRUCTIONS, PROCEDURES AND DRAWINGS l
5.3 I
1 l
5.3.1 l
l Instructions, procedures and drawings are prepared, reviewed and approved l
in accordance with applicable plant administrative procedures, when I
originated at the plant, or in accordance with applicable Ener5y Supply l
l procedures, when originated from LRGO.
l l
l l
1 l
5.3.2 l
l l.
I I
l Plant procedures identified in the Technical Specifications for each unit l
,I and changes thereto which describe activities required to implement this l
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 l
issuance.
Plant Administrative procedures (1000.XX Series) are also l
reviewed by the Quality Control staff to verify compliance to AP&L's l
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5.0 INSTRUCTIONS, PROCEDURES lPAGE 5-2 l
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l AND DRAWINGS l
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l quality program requirements.
LRGO Energy Supply procedures describing l
activities required to implement this quality program are to be reviewed
.I and approved by a procedures task force committee and Quality Assurance I
to assure compliance to AP&L's quality program requirements prior to I
submittal of the procedures to the Department Head responsible for l
l implementation,forapprovalandsubsequentissuance.
I I
l5.3.3 l
1 I
lPlantandLRGOproceduresandinstructionsaretobereviewednoless I
than every two years to determine if changes are necessary to meet NRC l
commitments and current AP&L practices.
Applicable procedures,(i.e.
I those that relate to the incident cause) are to be reviewed following an l
lunusualincidentsuchasanaccident,unexpectedtransient,significant l
l operator error or equipment malfunction.
Applicable procedures are also l
to be reviewed following any modification to a plant system.
I i
l5.3.4 l
o lDrawingsrelatedtoplantchangesandmodificationsarecontrolle l
g g
i described in Section 3 and 6 to this manual.
l l
l l
1 I
5.4 CHANGES' TO PROCEDURES I
l i
I I
l 5.4.1 1
I I~
l l
l Changes or revisions to approved instructions, procedures and drawings 1
are to be reviewed and approved by the same organizations or groups that I
performed the original review unless otherwise noted in specific AP&L i
lproceduresandcontrolledinthesamemannerastheoriginal.
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5.0 INSTRUCTIONS, PROCEDURES IPAGE 5-3 l
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i AND DRAWINGS I
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5.4.2 l
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l (V
l 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 documented, 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 General Manager prior to implementation.
Temporary changes to approved l
l plant procedures are to specify the period of time during which they may
,1 be used and made readily available to affected members of the plant l
l staff.
In the event of an emergency not covered by an approved l 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 1
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5.0 INSTRUCTIONS, PROCEDURES IPAGE 5-4 l
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l AND ORAWINGS I
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l 6.0 DOCUMENT CONTROL l
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/ '.
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l 6.1 SCOPE l
1 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 l
documents, such as instructions, procedures, specifications, manuals and l
l drawings,includingchangesthereto,whichprescribeactivitiesaffecting l
quality.
l l
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6.2 RESPONSIBILITIES l
l l
l l
6.2.1 l
I 1
I I
I l
Each organization originating documents which prescribe activities l
I affecting quality is responsible for the establishment of document I
control procedures which identify individuals or groups responsible for l
preparation, review, approval and maintenance of the document and for the l
issuance of these procedures to the affected individuals or groups.
l O
i i
i I
l 6.2.2 l
l l
1 I
I The plant Administrative Manager is responsible for the control and l
y issuance of plant procedures, and revisions thereto, to assure l
distribution in accordance with plant procedures.
The plant l
t Administrative Manager is also responsible for the storage arid control of
~
l l
approved historical plant documents, and the storage of historical I
drawing records.
The Engineering and Technical Support Manager is I
responsible for the control and issuance of drawings and revisions l
thereto to assure that they reflect the as-built conditions of the plant.
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6.0 DOCUMENT CONTROL IPAGE 6-1 l
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6.3 IDENTIFICATION l
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l l
l I Documents are to be identified by a title descriptive of their purpose or l
l applicability and marked or stamped as to their current status (Draft, l
For Information Only, Void, etc.) per departmental procedures.
Revisfors 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.
l l
l6.4 DISTRIBUTION l
l l
lDistributionlistsand/ordocumentregistersaretobemaintainedbythe l
organization responsible for issuance of the document.
These lists are l
l to identify the revision status of the document and are to be reviewed l
and updated periodically by the responsible organization to maintain them l
linacurrentstatus.
These lists are available to individuals using the l
l document to assure they are in receipt of the current document.
These j
measures are to preclude the possibility of using outdated or l
inappropriate documents.
O i
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l 6.5 CHANGES I
I I
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l 6.5.1 l
l I
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l 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
I I
affected activity.
g 1
I l
6.5.2 l
1 lObsoleteorsupercededdocumentsaretobedestroyedormarkedtoprevent l
inadvertent use in accordance with applicable document control I
t procedures.
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6.0 DOCUMENT CONTROL lPAGE 6-2 l
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l 6.6 STORAGE l
1
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_l Documents which affect quality are to be stored and maintained at the 1.
l.plantinpermanentstoragefacilitiesandcontrolledasdescribedin.
l l Section 17 of this manual.
I I
i i
I 6.7 VERlFICATION-l I
I I
I l Quality Control personnel, through their various levels of quality i
I surveillance and inspection activities, and Quality Assurance personnel, l
l through their audit activities, assure proper documents are being used
-l and made available to those individuals performing the work.
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6.0 DOCUMENT CONTROL IPAGE 6-3 I
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l 7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES l
l Q
l l
.l 7.1 SCOPE l
l l
1 l
I l The purchase of material, equipment and services is controlled to assure l
l that, whether purchased directly or through vendors, the material, l
equipment and services which affect quality conform to the procurement l
documents.
Procurement control includes provisions for source evaluation l and selection, objective evidence of quality furnished by the contractor, l
l surveillance and audit at the source, and examination of products upon I delivery.
The depth and necessity of procurement controls depend upon l
the uniqueness and complexity of the item / service, procurement frequency l with the same supplier and past supplier performance for the specific l
items or services covered by the procurement document.
The control of l
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 ii. Table 1.
l l
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l l
7.2 SOURCE EVALUATION AND SELECTION l
O i
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l l
7.2.1 l
l l
1 l
l A Qualified Vendors List (QVL) is to be maintained and controlled under l
the direction of the Quality Assurance Manager.
The QVL identifies l
those vendors / contractors that have been evaluated and approved by the l
QA0 to furnish material, equipment or services.
l~
l I
l 7.2.2 i
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l l
Vendors /ContractorsareevaluatedandplacedontheQVLbyanyofthe l
following methods, as approved by the Quality Assurance Manager:
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- 7. 0 CONTROL OF PURCHASED (PAGE 7-1 l
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l MATERIAL, EQUIPMENT AND SERVICES l
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I j
l
I l
l l
l (1). Source survey by AP&L to verify compliance to applicable 10CFR50, l
I Appendix B requirements or to applicable ASME Section III Quality I
i l
Assurance program requirements (for ASME Class 1,2,3,MC,NF and NG l
components).
I I
l(2) Evaluation and acceptance of source surveys performed by others l
(ex. NRC, ASME, other utilities, NSSS suppliers, and prime l
contractors) indicating a program meeting the appropriate l
requirements of 10CFR50, Appendix B or ASME Section III.
I I
l I
l l
(3) A review of the vendors / contractors current quality records l
supported by evidence of documented qualitative and quantitative l
information which can be objectively evaluated.
This includes l
l review and approval of the vendor's/ contractor's quality assurance i
program, manual and procedures, when available.
(This method is not l
y applicable for ASME procurements).
l l
1 (4) Evaluation of the vendor's/ contractor's history of providing a l
l product / service which performs satisfactorily in actual use.
l Evaluation information includes:
experience of users of identical l
l or similar products / services of the prospective vendor / contractor; l
and/or procurement records that have been accumulated in connection l
with previous procurement activities and operating experiences.
l (This method is not applicable to ASME procurements).
l l-(5) Verification that a vendor is a holder of an ASME Certificate of
~
l Authorization may be used in lieu of methods 1 and 2 for ASME l
procurements.
I I
l 7.2.3 I
I l
l l
Only vendors / contractors listed on the QVL are to be selected for l procurement of material, equipment or services except for items l
designated " commercial grade" per plant and LRGO procedures.
Standard l
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l TOPICAL REPORT lREV.
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7.0 CONTROL OF PURCHASED lPAGE 7-2 l
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l MATERIAL, EQUIPMENT AND SERVICES l
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l l
1 l
l l catalog items may be procured from a vendor / contractor not listed on the
.l QVL provided the manufacturer of the. item is on the QVL and all AP&L l
I requested documentation originates-from the manufacturer.
The QVL is to l.
lbeperiodicallyreviewedandupdated'perqualityassuranceproceduresto l ensure the current status of all selected vendors / contractors is l
lavailabletopersonnelinvolvedintheprocurementprocess.
t I
-l 7.2.4 I
I l
lWhencontractorsareselectedtoperformworkactivitiesattheplant, I
their personnel and work activities are to be controlled in accordance l-with plant procedures to assure that the contractor conforms to the l
l
-l I
I I
l
- 7. 3 SOURCE ~ SURVEILLANCE AND AUDIT l
1 I
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l 7.3.1 l
1 1
I I
l The effectiveness of a vendor's/ contractor's quality assurance program is l
assessed by QA personnel at intervals consistent with the importance, l
l complexity, method of receipt and quantity of the products or services.-
I This assessment may be through source surveillance, source audit, receipt l
inspection or review of source documentation files.
l l
I I
I l
7.3.2 l
1 1-l l
l Requests for source surveillance are made by the originator of the PR/.
l Contract,'and/or the responsible Quality Control or Quality Assurance l
organization during their review of the procurement document (reference l
section 4.3) Source surveillance is to be performed by QA personnel or l
l their appointed representative in accordance with surveillance plans l
lapprovedbytheQualityAssuranceManagerandtheresultsdocumentedper l
quality assurance procedures.
Reports documenting inspections performed l
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- l MATERIAL, EQUIPMENT AND SERVICES I
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.l l
l l
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l and discrepancies observed are prepared by the person performing the l
surveillance to document compliance to the procurement documents and for J
l future use as historical quality performance data.
1 l
l l
l 7.3.3 l
l l
l l
'l l Audits of the vendor's/ contractor's quality assurance programs are l
periodically performed under the direction of the Quality Assurance l
l Manager to verify implementation of a satisfactory quality pr.ogram on the l
items or services being procured by AP&L.
Audits performed by others l
(e.g., NRC, ASME, or prime contractors), as evaluated and approved by the l
lQualityAssuranceManager,maybeusedasanalternativetoauditsby l AP&L to verify the vendor / contractor is implementing a satisfactory l
lqualityprogram.
Audits are to be conducted in accordance with l
l Section 18 of this manual.
l l
l l
l l
- 7. 4 RECEIPT INSPECTION l
l l
l q
l 7.4.1 l
l V
I I
I I
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 l
performed in accordance with plant procedures for receipt inspection.
I l
7.4.2 I
I I
Receipt inspection activities are to be documented and irwlude, as a j minimum:
examination of material or equipment for shipping damage, l
proper identification, and quantity; and the review of vendor l
documentation, to verify compliance with the procurement document.
In l
addition, if material and equipment received at the plant were not l
l inspected at the vendor's facility by AP&L, an inspection is t.o be l
l 1
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- 7. 0 CONTROL OF PURCHASED lPAGE 7-4 l
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l MATERIAL, EQUIPMENT AND SERVICES l
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I I
l performed by a Quality Control Inspector at the point of receiving to l
g-verify that the material or equipment conform to the inspection I
requirements identified in the procurement documents.
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7.4.3 I
I I
I I
I Vendors are to furnish documentation as required by the procurement I
documents for objective evidence that the material or equipment conforms l
l to the procurement requirements.
Review and acceptance of th.is I
documentation is to be performed by a Quality Control Engineer prior to l
l installation or use of such material.or equipment and documented unless l
l otherwise specified in plant procedures.
Certificates of Conformance may I be required by procurement documents which identify the requirements met i
by the vendor.
The validity of the vendor's certification program is to I
be periodically verified through scheduled source surveillance and audit l
lactivitiesorthroughindependenttestingoftheitembyAP&L.
I I
l7.4.4 l
1 O
l' il Accepted material and equipment is released, identified as to its i
l inspection status and forwarded to a controlled storage area or released l
I l
for installation per applicable plant procedures.
I g
i I
l7.4.5 l
l I
l Acceptence of services furnished by a contractor is to be identified in I-g I
Depending upon the service performed, I
acceptance may be by technical verification of the data produced, I
surveillance and/or audit of the activity, or review of objective i
evidence for conformance to the procurement document requirements.
The I
acceptance method is to be performed by qualified individuals I
knowledgeable in the service provided.
l
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- 7. 0 CONTROL OF PURCHASED
[PAGE 7-5 l
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I MATERIAL, EQUIPMENT AND SERVICES I
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1 II -
1 7.5 PONCONFORMING ITEMS I
I D
I l
1
_l 7.5.1 l
l l
1 I
I l Nonconformances identified by the vendor / contractor which adversely l
l _ affect reliability, performance or interchangeability of the item and i dispositioned repair or use-as-is are to be-submitted to and accepted by I
AP&L prior to closure of the nonconformance by the vendor / contractor.
l l 'These nonconformances are to be documented and become part of.the l
procurement documentation furnished by the vendor / contractor for the l
material, equipment or services procured.
-1 I
I I
l 7.5.2 l
l I
I I
l-1 Material and equipment found to be deficient or missing. procurement l
documentation during receiving inspection is to be clearly. identified, I
segregated from acceptable items and dispositioned per plant procedur'es l
and as described in Section 15 of this manual.
- 7. 6 SPARE PARTS I
I lSparepartsaretobepurchasedtotheoriginaldesignrequirementsorto l
l those specified by a properly reviewed and approved revision to the.
I design requirements.
The applicable quality assurance requirements and l documentation requirements for spare parts are to be included in the l
lprocurementdocuments.
l l
l
- 7. 7 STORAGE 1
l Material and equipment are to be handled and stored as described in plant l
l procedures and Section 13 of this manual.
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- 7. 0 CONTROL OF PURCHASED lPAGE 7-6 l
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l MATERIAL, EQUIPMENT AND SERVICES l
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l
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l 8.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS l
l'3 l
8.1 SCOPE l
1 I
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i 8.1.1 l
l l
1 1
I Measures for the identification and control of materials, parts and l
components, including partially fabricated subassemblies, are to be i established within LRGO and plant procedures.
These procedures are to l
lrelateanitemofproduction(batch, component,part,etc.)atanystage, I
from initial receipt through fabrication, installation, repair or l
l modification to an applicable drawing, specification, or other, pertinent I
technical documents.
These measures are to assure that only correct and l
laccepteditemsareusedandinstalled.
l l
l l
8.1.2 l
l l
lMethodsfcrthetraceabilityofmaterials,partsandcomponentsto l
l specific inspection and test records, when required by codes, standards, l
specifications or procurement documents, are to be established within l
l LRGO and plant procedures and maintained throughout the life or l
consumption of the item.
l 1
l8.2 l
IDENTIFICATION l
l l8.2.1 l~
l l
l Materials,partsandcomponentsaretobeidentifiedbythevendorin l
accordance with the applicable design standards, codes and/or l
instructions specified in the procurement documents.
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l l SECTION:
8.0 IDENTIFICATION AND CONTROL lPAGE 8-1 l
l L
l OF MATERIALS, PAP,TS AND COMPONENTS l l
l l
l l
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' ' ^ ~ ~
' ' ~ '
- I I
I I
l 8.2;2 I
I I
r ^'i i
i V
l Materials, parts and components are to be identified and/or tagged at the l
lplantinaccordancewithapplicableplantprocedures.
These tags l
l identify the status of and provide traceability to tne item throughout l
lstorageandreleasetoinstallation.
l l
l l8.2.3 l
l l
l Identification of materials, parts and components is accomplished by l
l either marking or tagging on the item or through records traceable to the I
item.
I I
l8.2.3.1 l
l l
lPhysicalidentificationistobeusedtothemaximumextentpossible.
l l Where physical identification is either impractical or insufficient, I
lphysicalseparation,proceduralcontrolsorotherappropriatemeansare l
I to be employed in accordance with plant procedures.
I c) i I
im I
I l
8.2.3.2 I
I I
I I
l When identification markings are employed, the markings are to be clear, I
lunambiguousandindelible,andappliedinsuchamannerasnottoaffect l
l the integrity or function of the item.
Markings are also to be I
transferred to each piece of material (plate, barstock, tubing, etc.)
~
l when subdivided.
Large quantities of small items, may be identified by l
l applying markings or tags to their shipping packages, boxes or other l
l suitable containers.
I i
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^',
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(V l
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TOPICAL REPORT
[REV.
6 l
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l lDATE 6/10/83 l
I l SECTION:
8.0 IDENTIFICATION AND CONTROL IPAGE 8-2 l
l L
I 0F MATERIALS, PARTS AND COMPONENTS l l
l I
I I
t
I I
I I
I 8.2.3.3 l
l l
/l l
l D'
l Identification markings are to be recorded on records or as-built I
documents if current markings are to be hidden or subject to obliteration l
l by surface treatment or coatings during fabrication, installation, repair l
lormodifications.
l l
l l8.3 l
CONTROL l
l lPlantorganizationsreceivingmaterials,partsandcomponentsareto l
l Verify that they are properly identified while under their control.
l lQualityControlpersonnelthroughtheirsurveillanceandinspection l
l activities assure that compliance to these requirements are being met.
I lQualityAssurancepersonnelthroughtheirauditactivities,alsoassure l
l that materials, parts and components are being identified in accordance i
fwiththismanual.
l l
l l8.4 l
DEFECTIVE OR INCORRECT ITEMS I
n O
l 8.4/1 l
1 I
l Defective or incorrect materials, parts and components identified by l
l plant personnel or support groups are to be handled in accordance with l
lSection15ofthismanualandplantproceduresfornonconformancesand l
l corrective action.
Defective or incorrect items are to be tagged with a i
" hold tag" affixed to the item or otherwise identified per plant l~
l procedures.
I I
l l
I l
8.4.2.
I I
I l
l l Defective or incorrect items are to be stored in segregated areas except I
for those items installed or which, due to their size, weight I
configuration, etc., are impractical or impossible to store in the I
designated controlled storage acea.
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I TOPICAL REPORT lREV.
6 l
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1 lDATE 6/10/83 l
l 1 SECTION:
8.0 IDENTIFICATION AND CONTROL lPAGE 8-3 l
l L
I 0F MATERIALS, PARTS AND COMPONENTS l l
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.I I
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l
- 9. 0 CONTROL OF SPECIAL PROCESSES l
l l
O i
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9.1 SCOPE l
l l
l l
S ecial processes are to be controlled through the use of qualified l
l P
personnel and plant procedures which meet the requirements of applicable l codes, specifications, standards and other criteria stipulated in AP&L l
llicensingdocuments.
I I
l9.2 GENERAL l
l l9.2.1 I
I lSpecialprocessesarethoseactivitieswhichrequireinteriminprocess l controls in addition to final inspection to assure quality and include l
lsuchactivitiesaswelding,nondestructiveexamination,heattreating, l
coating, plating and chemical cleaning.
1 l
I 1
l 9.2.2 I
O l
i l
i l
l Technically qualified LRGO or plant personnel are to establish the l
procedural and qualification requirements for those special processes not l covered by existing codes' or standards or where AP&L quality requirements l
exceed the requirements of established codes or standards.
I I
l9.2.3 l
I 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
systems. are to comply to the requirements of NRC regulatory guide 1.37, l
I dated 3/16/73 unless otherwise noted in Table 1.
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9.0 CONTROL OF SPECIAL PROCESSES lPAGE 9-1 l
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. ~ - -
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l 9.3 -QUALIFICATION l
l i
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..I 9.3.1 1
I I
I I
i
- 1. Special process procedures for welding and nondestructive examinations l
l are to be qualified prior to use to assure compliance to applicable I codes, standards or specifications.
These qualifications are to be I
j ldocumentedandalsomadeavailableforreviewtotheCodeInspectorfor l
activities on ASME items.
l 4
l l
l l
l 9.3.2-l I
I I
I i Personnel responsible for the performance and verification of special I
~
lprocessesaretobequalifiedand/orcertifiedaccordingtoapplicable I codes, standards, specifications, regulatory guides and plant procedures.
l
~
lThesequalificationsandcertificationsaretobedocumentedandmade l
I available for review to the Code Inspector for activities on ASME items.
I 1
Personnel qualification and/or certification records for a special' l
l process are to be regularly reviewed by the supervisor responsible for l
O lthatspecialprocesstoassurethattheappropriatedocumentsare i
i up-to-date and pe'rsonnel are periodically requalified and/or recertified l
in accordance with plant procedures.
l l
I 9.4 RECORDS I
I lTheresultsofspecialprocessesaretobedocumented, reviewed, approved
~~
l and stored in accordance with appropriate plant procedures and as l
l'addressedinothersectionsofthismanual.
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9.0 CONTROL OF SPECIAL PROCESSES IPAGE 9-2 l
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I 10.0 INSPECTION-I 1
Q l
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v 1
10.1 SCOPE l
I
'l
'l I
I Inspections relating to normal operating activities and inspections l
lrelatingtooperatingactivitiescomparableinnatureandextenttothose l
l occurring during initial plant _ design and construction are to be l
l controlled to assure that inspections ;are performed. in accordance with l
l applicable design documents, codes, standards, specifications and l
l procedures.'
Inspection activities are to be in accordance with l
l Regulatory Guide 1.33, Rev. 2 (2/78), unless otherwise noted in Table 1.
1
~
I l
I l
10.2 GENERAL I
I 1
l i
l l
10.2.1 I
I I
I
~
l l
Inspection activities relating to normal operating activities 1
I l
(Operational Inspections) include:
I I
I l
1)
Work functions associated with normal operation of the plant; l
l 2)
Routine maintenance; l-3)
. Technical services routinely assigned to the onsite operating ~
l organization; and
-l 4)
.Non-routine maintenance activities and minor modifications made I
by the onsite operating organization that are not comparable in 1
nature and extent to related activities occurring during
~
I
!r initial plant design and construction.
I I
I I
i
{
l 10.2.2 l
1 I
I I
1 Inspection activities relating to operating activities comparable in l.
nature and extent to rslated activities occurring during design and I
l construction (Construction Inspections) include:
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10.0 INSPECTION IPAGE 10-1 l
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.1)
Non-routine maintenance, except as noted in paragraph 10.2.1; I
and 1
2)
Modifications, except as noted in paragraph 10.2.1.
I I
I l
~
l l
The following Regulatory Guides are to be applied, as applicable, in l
l determining the basis for required construction inspections:
R.G. 1.30, l
l Rev. 0 (4/76); R.G. 1.38, Rev. 2 (5/77); R.G. 1.39, Rev. 2 (9/77);
I lR.G.1.37,Rev.0(3/73);R.G.1.94,Rev.1(4/76);andR.G.1.116, l'
l Rev. 0-R (7/76).
I I
I I
I l
10.2.3 I
I I
I 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
lperformingtheinspectionaretomeetapplicablelicensingrequirements, l
l codes and standards appropriate to the discipline involved.
I I
I I
l i
10.3 CONTROL OF INSPECTIONS l
0 l
l 1
10.3.1 1
I I
I I
I Inspections are to be performed in accordance with approved written i
procedures, which set forth the requirements and acceptance limits and I
specify the inspection responsibilities.
If inspecitions require detailed l
l written procedures to perform the task, the procedures are to contain, as
~
l a minimum, the following:
I I
I I
I
-l 1)
' Qualitative and/or quantitative acceptance criteria; I
2)
Prerequisites for performing the inspection and any limiting l
l conditions; I
3)
Identification of any special equipment and tools required to I
perform the inspection; I
I
~
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10.0 INSPECTION lPAGE 10-2 I
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i l
l
I I
I l
l 4)
A step-by-step description of the method of inspection, I
l examination, measurement or test to be performed; and I
n.
l l
5)
Identification of those inspection results to be documented.
l.
l Inspection forms or checklists are to be used as an aid in l
l documenting the inspection activity to assure quality I
requirements have been met.
g I
I l10.3.2 l
l l
lOperationalandconstructioninspectionsaretobeperformedbyqualified
.I individuals other than those who performed or directly supervised the I
activity being inspected.
I y
I I
l10.3.2.1 l
l l
'g Operational inspections may be performed by second-line supervisory l
I personnel or by other qualified personnel not assigned.first-line l
supervisory responsibility for conduct of the work.
l l
I w
10.3.2.2 g
I l
lConstructioninspectionsaretobeconductedinamannersimilartothat I
associated with construction phase activities in accordance with I
applicable plant procedures.
I il' 10.3.3 l
l g
inspection determined to be required is impossible or l
If al l
disadvantageous, indirect control by monitoring processing methods, i
equipment and personnel is to be provided to verify conformance with l
l applicable documented instructions, procedures and drawings.
Both l
inspection and process monitoring are to be provided when control is l
l l
inadequate without both.
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1 SECTION:
10.0 INSPECTION lPAGE 10-3 l
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l 10.4 INSPECTION POINTS l
l-I l
10.4.1 l
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l Inspection hold points are established for non routine maintenance l
lproceduresa/iddesignchangepackages'(DCPs)byPlantEngineeringand l
l reviewed by the Plant Quality Control group for concurrence and possible l
assignment of additional inspection hold points to further assure l
conformance with applicable instructions, procedures, drawings and l
lrelateddocumentsortomeetappropriatecodeandregulatory l
l requirements.
Inspection hold points for work functions associated with l
activities other than non-routine maintenance and DCPs, may be l established by the originating department or by Quality Control.
l 1
1 I
I l
10.4.2 l
I I
I I
l Inspection responsibilities, requirements, information and acceptance l
,I criteria for the work activity are to be identified in appropriate, l
approved plant documents (e.g. procedures, checklists, etc.)
l O
i i
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l 10.4.3 l
l 1
I I
l For work involving the modification, repair, replacement or in-service l
inspectu ' _' ASME Code materials, parts and components, the work l packages are to be made available to the Code Inspector prior to l
commencing work for his review and assignment of inspection hold p'oints.
l The department responsible for the work activity is responsible for l
notifying the Code Inspector when the hold point is reached.
Work is not l
to proceed past a Code Inspector's inspection hold point until signed or l
waived by the Code Inspector.
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10.0 INSPECTION JPAGE 10-4 l
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10.5 DOCUMENTATION l
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,I g-g U
l 10.5.1 l
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1 Inspections and process monitoring activities are to ce performed and the l
results documented in accordance with approved proceddres or l
instructions.
Records are to:
provide objective evidence that the l
inspections'and monitoring activities were performed in compliance with I
procedures, instructions or ' drawings to verify design requirements; show l
compliance with acceptance criteria or identify the cause of rejected I
items; and identify the eppropriate inspection personnel approving the l
lresults.
l l
1 l10.5.2 l
l l
Records are to be maintained in accordance with plant procedures and l
Section 17 of this manual.
Inspection results on ASME code' items are l
I; available to the Code Inspector for his review.
1 1
,,b 10.5.3 l
l l
l The results of the inspection and monitoring activities are periodically l
l evaluated per plant procedures and the results documented to determine l
whether the individual inspection programs demonstrate that the plant can l
l be operated safely and as designed.
l I
I l
1 l
10.6 NONCONFORMANCES l
l l
l l
l Noncomforming items found as a result of inspection and monitoring l
activities are identified, segregated and dispositioned in accordance l with plant procedures and.Section 15 of this manual.
Rework, repair or l
replacement performed after completion of inspections are to require l
l l
reinspection to the extent necessary to determine acceptiabili,ty to l
lestablishedcriteria.
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1 SECTION:
10.0 INSPECTION lPAGE 10-5 l
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I
.l 11.0 TEST CONTROL l
l l
(J3 l'
l
- l. 11.1 SCOPE I
I l
l 1
l l A test program is to be established to assure that testing required to l
I
~-.
l demonstrate that an item will perform satisfactorily in service is I
l
[
identified, documented, and performed in accordance with written test l
l procedures.
l
'These procedures are to incorporate or reference the I
l
,l requirements and acceptance criteria contained in applicable codes, l
standards and specifications and in the licensing documents.
These l activities include testing during the operational phases of the plant and l
those tests required as a result of modifications, repairs or I maintenance.
These activities are also to comply with the applicable l
f provisions of Regulatory Guides 1.33, Rev. 2, unless otherwise noted in l
Table 1, and with the applicable sections of the ASME Boiler and Pressure l
I Vessel Code for ASME designated items.
I I
I I
I I
11.2 PROCEDURES I
I w
I I
I 11.2.1 1
I Written procedures / instructions are to be prepared to describe the l
requirements for conduct of the testing activities.
These procedures /
l instructions are to contain or reference the information required in
~
l Section 5 of this manual and in the applicable Regulatory Guides l
I pertaining to Quality Assurance requirements for testing activities.
I I
i 11.2.2 I
I I
I I
I I
Test procedures / instructions and revisions thereto are to be subject to I
I
.l the same review and approval process as outlined in Section 5 of this l
'I manual.
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TOPICAL REPORT IREV.
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1 SECTION:
- 11. G TEST CONTROL IPAGE 11-1 l
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I; 11.3 TEST CONTROLS l
l l
O I
V I
11.3.1 I
l l
e l~
I l
l Tests relating to plant start-up following a unit shut down or fuel l
loading are to be conducted per written procedures / instructions in order l
to evaluate plant performance as.the start-up progresses.
Initial j
start-up test programs are to be planned to permit safe fuel loading and l
start-up, to increase power in safe increments and to perform major l
II testing at specified power plateaus.
l 1
l l
I 11.3.2.
I I
I I
I f
Surveillance tests during the operational phase of the plant are to be I
l conducted per written procedures / instructions td assure,that failures or l
substandard performances do not remain undetected and that the required l
operability is maintained to ensure they will continue to operate, l
keeping parameters within normal bounds, or will' act to put the plant in I
l a safe condition if they exceed normal bounds.
O i
l i
i l
i 11.3.2.1 l
1 1
1 1
I Mandatory inplant surveillance tests and inspections required to assure l.
I operation within the limiting conditions of operation are identified in I
I I
l the Technical Specifications applicable to each unit at the plant.
To l
ens /rethattherequiredtestsareperformedasscheduledwithinthe
~
l' l
j l
l specified time interval, surveillance procedures are established and l
I maintained for.manc'r.!,/ turveillances identified in the Technical I
s l
I l
Specifications T w 7.rocedures are to specify the component or system, l
type of surve t!au wivity, frequency of activity and the cognizant I
l individual responsible for completion of the surveillance activity.
l l
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TOPICAL REPORT lREV.
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l' I SECTION:
11.0 TEST CONTROL lPAGE 11-2 l
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I l -11.3.2.2
.I l
l
~ Di l
l-4 l
v' l
Inservice inspections required to meet the requirements of ASME Boil'er i
landPressureVesselCode,SectionXI',aretobeidentifiedinthe
- 1. 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
f procedures, inspection intervals and type of inspections.
Plant l
l Engineering is to coordinate the implementation of the ISI pl.ans at l
lappropriatescheduledoutages.
The plans are also to be made available l
l for review by the Code Inspector.
l l
I l
I l
11.3.3 I
1 I
I I
l Tests following plant modifications, repairs,-maintenance, or significant l
lchangesinoperatingprocedures,aretobeconductedtoconfirmthatthey l
l are not detrimental to the safe and efficient operation of the plant and l
f that the componer.ts or systems demonstrate satisfactory performance.
I I
I 11.3.4 I
I I
I I
Requirements for the given test to be performed are to be identified in
' l the test-procedures / instructions.
Evidence is to be available to assure l
the following minimum requirements are met:
I 1
I I
' a) '
test equipment and measuring devices are calibrated in.
~
j l
accordance with the requirements of Section 12 of this manual l
and are functioning properly; l
b) test personnel have been qualified to perform the test in l
accordance with the requirements of Section 2 of this manual; I
and l
I c) appropriate witness and hold point notifications have been g
[
l provided.
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1 SECTION:
11.0 TEST CONTROL lPAGE 11-3 l
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l 11.3.5 l
?
1 l
i O
.l l
- l. Testing activities.are to be subject to surveillance / inspections in l-accordance with Section 10 of this manual.
Testing as a result of l
I repair, modifications, replacement or scheduled inservice tests on ASME I
f l Code'itemsisalsosubjecttoinspectionbytheCodeInspector.
-l The l
~
. assignment of inspection hold points is described in Section 10.of this l
manual.
i 1.
11.3.6 l
l lTestresultsaretobedocumentedinaccordancewiththeappligable l
l procedures / instructions.
Test documents are to contain at least the l
lfollowing:
l
~l I
f (1) Identity of item tested.
l (2) Date of test.
l (3) As-found condition.
l 0
(4). Identification.of individuals performing test.
l i
(5) Test results.
i g-l (6) Corrective actions performed if any.
1 j
(7) As-left condition.
l
.I l
11.3.7 l
1 l
lTestresultsaretobeevaluatedbyresponsibleplantpersonnelperplant l
l l procedures to assure that test objectives and inspection requirements l
-have been satisified.
Non-conforming conditions, are to be identified l and controlled in accordance with Section 15 of this manual.
l l
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11.0 TEST CONTROL IPAGE 11-4 i
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I-1 I 11.4 RECORDS I
I l
Q
I
-l l Test results are to provide objective evidence.that'the testing was l
lperformedincompliancewithapprovedprocedures.
Test records are to be
'I maintained and transmitted to the plant Document Control Center for i
. retention in accordance with Section 17 of this manual.
l l
l-l11.5TESTSTATUS l
l I
l'Inspectionandteststatusistobe'controllhdinaccordancewiththe l
.1 provisions of Section 14 of this manual.
l' I
I I
I 1
I I
I I
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1.
I l
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l -
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l 1 SECTION:
11.0 TEST CONTROL IPAGE 11-5 I
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l 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT l
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_l 12.1 SCOPE l
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i 12.1.1 I
I I
I i
l A program is to be established to assure that devices used for I
measurements, tests and calibrations are identified, controlled and i
l calibrated against reference standards to assure that accuracy is l
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 l
l measuring and test equipment, unless otherwise noted in Table 1.
l.
I I
I I
i 12.1.2 1
I l
l l
l This section does not apply to rulers, tape measures, levels or other l
lsuchdeviceswherenormalcommercialpracticesprovideadequateaccuracy.
l l
l I
12.2 RESPONSIBILITIES l
g l
I 12.2.1 l
l The cognizant Superintendents / group Supervisors at the plant are l
I responsible for establishing and maintaining lists of measuring and test I
equipment under their control that require periodic calibration and for l
the calibration of this equipment, as assigned within plant procedures.
I I
l i
l l
12.2.2 I
I I
I I
I The cognizant Supervisor is responsible for identifying measuring and I
test equipment required for the activity and assures that the devices are l
used only by qualified personnel.
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12.0 CONTROL OF MEASURING IPAGE 12-1 1
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i AND TEST EQUIPMENT l
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-1 i
12.2.3 I
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l
(}
I 1
l Plant personnel are to be responsible for utilizing only properly l
l identified and calibrated-measuring and test equipment when performing I
l inspections and tests for record.
.)
l I
I l
12.2.4 I
l l
1 I
i l
The Manager, Nuclear Quality Control and his staff are responsible for l
monitoring test equipment control and use in order to verify compliance l with the program.
l 1
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l 12.3 GENERAL 1
l l
l 1
l 12.3.1 I
l 1
I I
I l
Calibration procedures are to be established for each type of measuring l
and test equipment.
These procedures are to conform to recognized codes l
and standards and to local, state and federal regulations, and are to be l
I referenced on the calibration reports.
I I
I 12.3.2 I
l i
1.
I Measuring and test equipment is to be properly controlled, calibrated and l
adjusted at specific intervals or prior to use to assure the necessary l
]accuracyofcalibratedequipment.
Calibration intervals are to be based l~
l upon the type of equipment, manufacturer's recommendations, stability and l
reliability characi. eristics, required accuracies, use and other l
conditions affecting calibration.
l l
l l
l
.I I
l l
12.3.3 l
l l
1 l
-I l
l l
Reference standards used in the calibration of measuring and test l
equipment are to be traceable to the National Bureau of Standards, or if l
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1 SECTION:
12.0 CONTROL OF MEASURING IPAGE 12 2 l
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I
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nonexistent, to accepted industry or AP&L standards.
Reference standards I
are to have an accuracy at least four times that of the measuring and V-l test equipment.
In any instance where the four times criteria is unable I
to be met, standards.are to have an accuracy level, acceptable l
l calibration range, and precision equal to or better than those required i
g for the ranges.affected by the calibration.
Reference standards are to I be maintained in an environment with temperature, humidity and I
lcleanlinesscontrolscompatiblewithmaintainingaccuracyandoperating I characteristics of the standards.
I I
I I
l
-12.3.4 I
l
)
I I
I l When measuring and test equipment are found to be out of calibration, an I
evaluation of the validity of previous inspection or test results and the I acceptability of items previously inspected or tested is to be made and I
documented by written report in accordance with plant procedures.
If any I
piece of measuring and test equipment is consistently found to be out of I
calibration, it is to be repaired or replaced.
I O-1 I
U 12.3.5 I
I I
Recalibration per plant procedures is to be performed when the accuracy l
1 of either installed or calibrated equipment is questionable.
l I
I I
I i
12.4 EQUIPMENT IDENTIFICATION l
1 l-1 I
i 12.4.1 l
l l
l l
l I The measuring and test equipment list is to contain sufficient I
information to uniquely identify each item listed and is to include as a l minimum, calibration intervals, tolerances and storage locations.
The 1
l list is also to identify the group responsible for the control of each I
item.
I i
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12.0 CONTROL OF MEASURING lPAGE 12-3 l
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I AND TEST EQUIPMENT l
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12.4.2
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~l I
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- l V
l Each item: listed on the~ measuring'and test equipment list is to be l-
. tagged,. labeled or otherwise identified per plant procedures in such a
.l l manner that clearly identifies the equipme.nt and its calibration status I
- and provides traceability to the calibration-records.
I i
12.4.3 I
I Measuring and test equipment found to be ~out of calibration is to be l. tagged and segregated from acceptable equipment in accordance with plant.
I' procedures until repaired and recalibrated.
l l
l I
12.5 RECORDS
- g i-I Calibration documentation is to be maintained to verify calibration
-l
- l.. status, condition, accuracy and out of tolerance trends of the equipment.
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12.0 CONTROL OF MEASURING IPAGE 12-4 I
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i AND TEST EQUIPMENT l
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i 13.0 HANDLING STORAGE AND SHIPPING I
I I
("~)
l I
l 12.1 SCOPE I
I I
I I
I Activities for the handling, storage and shipping, including cleaning, I
packaginr d preservation of materials and equipment are to be performed I
in accore with established instructions, procedures or drawings, to i
prevent ' damage, deterioration or loss of the item.
Activities are to I comply with the provisions of Regulatory Guide 1.38 rev. 2 unless l
lotherwisenoted.inTable1.
l l
1 13.2 GENERAL I
i 13.2.1 1
I lInstructionsforpreservationaretobeprovidedforitemssubjectto I
deterioration or damage through exposure to air, moisture,' or other l
environments during fabrication, processing, assembly, and interim s
I storage periods.. Items are to be cleaned, preserved and packaged as I
required to preclude deterioration and prevent damage. When maintenance I
of specific internal or external environments are necessary, they are to I
be included in special packaging instructions and maintenance procedures.
I i
13.2.2 l
l l
g Procurement documents assure that any special cleaning, preserving, l-y I
handling, packaging or shipping requirements for purchased material or i
equipment are taken into account.
I i
l 13.2.3 l
l For critical, sensitive, perishable or high value articles, l
l recommendations for their handling, storage, packaging, shipping and I
I i
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1 SECTION:
13.0 HANDLING, STORAGE AND IPAGE 13-1 l
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i SHIPPING l
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I
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l i nreservation are to be requested from the supplier per the procurement I
' documents and furnished to the plant prior to or upon receipt of the ' item l'
r l-at the plant.
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I
'l
~l
~
-l 13.3 SHIPPING CONTROLS I
l-1
-l l
.. I 13.3.1 1
I I
I I
l Shipping requirements are to be specified in the procurement documents.
l.
lSupplierscompliancetotheserequirementsaretoincludecontrolsto l_
1 l assure that items are complete and assembled as required; items have been l
preserved and packaged in accordance with the procurement c'ocuments;
~
l items have been marked and identified in accordance with specifications l
~,
and procurement documents; items have been loaded for shipment in such a' l,
I manner as to prevent damage; and required documentation is complete and l
furnished in accordance with the procurement documents.
I i
13.3.2 I
I 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
documents. The Health Physics Supervisor is responsible for assuring I
that radioactive sources and instruments containing radioactive-sources l
are shipped, stored and handled per these requirements and plant l procedures.
The Nuclear Support Supervisor is responsible for assuring I
that special nuclear material (SNM), as defined in plant procedures, are I
shipped, stored and handled per these requirements-and plant procedures.
l I
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I l
13.4 RECEIVING l
l l
I I
l 13.4.1 1
I I
I i
l Materials and equipment are to be received at the plant per plant
. l 1
procedures and subjected to a receipt inspection in accordance with I
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13.0 HANDLING, STORAGE AND lPAGE 13-2 l
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SHIPPING l
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.I l
1 Section 7. of-this manual.
As part of the inspection activity, received l
materials and' equipment are to be' inspected for damage, deterioration,--
4
.I cleanliness and proper identification and markings per plant procedures I
g for-receipt inspection.
i l
l_13.4.2 i
I I
l-j g Results of the receiving inspection and disposition.of the material or l
g i equipment are to be documented on receiving inspection records.-
)
Nonconforming items are to be handled in accordance with plant procedures I and Section 15 of this ma sal.
[
l
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- '~
l 13.5 STORAGE CONTROLS I
l I
I i
I i 13.5.1 I
i I
i i
I
.1, Materials-and equipment which have completed the receiving process _are to' l
i.
be stored based on the classification level of storage specified on the i
l procurement documents or related design documents.
l l
l l
l
{
.I 13.5.2 l-1 i
I I
l Storage control procedures are to be established which include, as a i
I g minimum, provisions for~the following:
controlled access and usage of
,i
[
l the storage area; cleanliness and good housekeeping controls; fire I
I g
protection; protection from environmental hazards; and segregation of I'-
g l
l hazardous materials.
I I
I I
1 1
13.5.3 l
1 1
I I
l Only items which have completed the receiving process are to be placed in I
l a controlled storage area.
Records of the items' location are to be 8
provided by the Materials Management Supervisor (see paragraph 13.3.2 for i
l l
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I SHIPPING i
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l control of radioactive sources and SNM) to identify those items currently l
I 'in' storage and to facilitate inspection and maintenance planning.
'I O
l Issuance of items from storage for installation or use are to be 1
ldocumentedandcontrolledinaccordancewithplantprocedures.
l-l l-13.5.4 l
1 I
Items identified as requiring maintenance during storage are 'to be i maintained in accordance with a documented maintenance program.
I I
I I
I i
13.5.5 l
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I I
l Storage areas are to be monitored by individuals responsible for the I
storage areas so that the integrity and security of stored items is i effectively maintained.
Inspections and examinations under the control I
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 I
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 1
l 13.6 HANDLING CONTROLS I
i l
13.6.1 1
l lSpecialhandlingrequirementsaretobespecifiedintheprocurement t
I documents and plant procedures to protect the quality of items I
susceptable to handling damage.
Special tools and equipment are to be I
provided to handle these items and are to be controlled and maintained l
[
per written procedure to assure safe and adequate handling.
I I
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13.0 HANDLING, STORAGE AND IPAGE 13-4 1
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I SHIPPING I
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= _ _
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. ~
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1
-~ l 13.6.2.
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I i
i
-l Special handling tools and equipment are to be inspected and tested at~
I-specific times in accordance'with written procedures to verify that the I handling tools and equipment are adequately maintained.
Inspection and I
-test status of these handling tools and equipment are to be controlled in I
g l
l accordance with the applicable sections of this manual.
I I
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4 l'
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2 l-I l-1 1
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.P I
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l 1 SECTION:
13.0 HANDLING, STORAGE AND IPAGE 13-5 I
1 L
l SHIPPING l
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l 14.0 INSPECTION, TEST AND OPERATING STATUS I
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l I
l L'
l 14.1 SCOPE I
I I
I I
I 14.1.1 l
l 1
l 1
I The removal from service, inprocess status and return to service of l
1 g equipment, components and systems for maintenance, modifications, repair, I
g I
test or inspection is to be controlled per established plant. procedures.
l I
g These controls are to assure that plant personnel are aware of equipment, I
g I
structure or system conditions and to prevent their inadvertent use l
lunlessclearedbyoperationpersonnel.
l l
l l
14.1.2 l
l I
I I
l Maintenance activities are to be performed in accordance with an I
g i established maintenance program to assure that equipment, systems and I
structures are maintained in a condition which allows them to perform l
their intended function.
'3 l
v!
I I
g I
14.2 EQUIPMENT CONTROL I
I I
I I
I 14.2.1 I
I I
I I
l Prior to removal of equipment, components or systems from service for I
I g
maintenance, modification, repair, test or inspection activities, l-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
affecting plant safety.
1 I
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14.0 INSPECTION, TEST AND lPAGE 14-1 l
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I OPERATING STATUS I
l l
I I
I
I l
-l l
14.2.2 l
-l l
l The status of equipment, components and systems during these activities-I l
is to be identified-in accordance with plant procedures / instructions, l
l which contain, as a minimum, the' following:
I l
1 l
l l
1) methods for control of equipment to maintain personnel and I
reactor safety and to avoid unauthorized operation of equipment l
or: systems.
I l
-I I
-l l
2) the use of. markings a.other suitable means to indicate the l
status of-activities being performed upon individual items.
l l
Suitable means are to include identification numbers which are l
-l traceable to records of the status of these activities.
l i
'l 3) provisions for the identification of items which have l
l'
~ satisfactorily passed the required activities.
In cases where.
l required' documentary evidence is not available, the associated I
equipment or system is to be considered nonconforming and l
handled in accordance with Section 15 of this manual.
l 1
l
~
4)-
provisions'for independent verifications, where appropriate,'to l
l ensure that necessary measures such as locking or tagging to l
secure and' identify equipment or systems in a controlled l
status, have been_ implemented correctly.
l l
l' l
l l
14.2.3 I
I I
I I
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
g l
foreign material is removed before the system is reclosed.
I I
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I I
I I
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14.0 INSPECTION, TEST AND IPAGE 14 2 l
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l OPERATING STATUS l
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I I
I l
l 14.2.4 I
I I
C) l I
L l During maintenance or modification activities, certain portions of I
l systems,asidentifiedinplantprocedures,maybe~subjecttopotential I contamination with foreign materials.
To prevent such contamination, I
control measures, including measures for access control, are to be i established.
Immediately prior to closure, an inspection is to be l
lconductedtoassurecleannessandtheresultofsuchinspectionistobe I
documented.
I I
I I
I i
14.2.5 l
I I
I I
l If temporary modifications (such as temporary bypass lines, electrical I
l l
jumpers, lifted electrical leads and temporary trip point settings) are l
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 I
g l
the Shift Supervisor, identifying the current status of such temporary I
modifications.
Temporary modifications are to be verified by individuals l
l l
independent of the group performing the activity and documented to assure l
V the required actions are taken to return the equipment or system to its I
original operating configuration and status.
I I
I I
I i
14.2.6 l
l l
1 l
I l
When equipment or a system is properly identified as being ready to be l
l returned to service, the appropriate Shift Supervisor is notified and
~
l initiates the proper operation procedures.
Testing of the equipment or i
I system for functional acceptability is to be in accordance with l
Section 11 of this manual and documented to verify current status of the 1
item.
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14.0 INSPECTION, TEST AND IPAGE 14-3 l
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l OPERATING STATUS I
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i r
-l I
l i
14.2.7 I
1.
l
/"3 I
I V
l Equipment, structures and systems found to be nonconforming as a result I
l of an activity are to be handled in accordance with plant procedures and l
Section 15 of this manual.
l l
1 l
l 14.3 MAINTENANCE CONTROL l
I I
1 l
i 14.3.1 I
l l
1 l
I I
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 I
activities are to be performed per plant procedures and instructions and l
conducted in a manner to assure quality at least equivalent to that l
specified in the design documents, material specifications and inspection I
requirements. As experience is gained in operation of the plant, routine I maintenance may be altered to improve equipment performance and b
l I
V procedures for repair of equipment are to be improved as directed by the l
y 1 Maintenance Manager.
I I
I l
i I
14.3.2 l
l l
l l
l A preventive maintenance program, including procedures and instructions l
for systems, structures and components, is to be established and
~
l maintained under the Maintenance Manager which prescribes the frequency I
and type of maintenance to be performea in order to preclude equipment I
malfunctions.
The program is to be implemented by qualified maintenance I
personnel in accordance with written procedures and instructions which l
specify the work activities, acceptance requi,rements and the control l
measures to assure adequate quality.
When equipment malfunctions occur, I
the cause is to be promptly determined, evaluated and recorde,d per plant I
procedures and Section 16 of this manual.
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14.0 INSPECTION, TEST AND lPAGE 14-4 l
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I OPERATING STATUS l
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l -14.4 '0VERALL PLANT' STATUS l
1-I A
i 1
V l 'The Shift Supervisor'is to maintain sufficient knowledge of the overall
-l lg plant status'of equipment, structures and systems to control operation of I
g l
the plant in a safe manner..The Shift Operators are to maintain a ready l
I J
g reference of plant systems, equipment and components alignments, as well-I g
I as a status' board summary of their conditions.
I l
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1 SECTION:
14.0 INSPECTION, TEST AND IPAGE 14-5 I
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l OPERATING STATUS l
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/
I I-l' l
l: 15.0 NONCONFORMING MATERIAL', PARTS AND COMPONENTS l
l N'd 1.15.1 SCOPE I
I l
l l
l 1
l l - Nonconforming items are to -include materials, parts,. components, -
l processes and documents that do not conform to app 1'icable regulations,-
l codes, standards, specifications, drawings or licensing documents.
I Nonconforming items are to be controlled in accordance with approved-I l. procedures to prevent their inadvertant use or installation.
These l
procedures are to contain measures to assure the prompt identification l
l and notification, documentation, segregation, technical review, l
ldispositionandverificationofanonconformingitem.'
I I-I 15.2 GENERAL I
I I
I I
I 15.2.1 l
I l
I l
.It_is the responsibility of ecch individual-to identify a nonconforming l
condition, whether related to a product, process or documentation, and to l
4 I
l report it to their cognizant supervisor for review and concurrence.
The I
l l
initiator is to document the nonconformance on a Nonconformance Report
-l
)
I (NCR) unless the nonconformance is determined to be a technical I
4 I
I l
specification violation and/or reportable to the NRC.
See paragraph 15.3 l
I for reportable nonconformances.
I i
.I 1
[
l l
15.2.2 I~~
I l
l l
[
' Nonconforming items are to be tagged with a hold tag, or otherwise l
identified per plant procedures, to prevent inadvertant use or l
I installation of the item.
Nonconforming items are to be segregated from I
I I
l acceptable items unless they are currently installed or their size, l
weight, configuration, etc., makes it impractical to move to a segregated l area.
Hold tags.are to remain on the item until the disposition is l
I complete per plant procedures.
I g
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I I
]
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15.0 NONCONFORMING MATERIAL, lPAGE 15-1 l
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l PARTS AND COMPONENTS l
l l
_l l
I
l I
l l
15.2.3 l
I l
(m l
I V
l l Nonconformance Reports are to identify the group responsible for l
ldispositioningthenonconformance.
The assigned individual within the I
responsible group is to evaluate the nonconformance and confer, as l
l appropriate, with interfacing groups to determine its cause and I
recommended disposition.
The disposition, which may be reject, rework, I
l repair or use as-is, and the corrective action taken to prevent I
recurrence is to be documented on the NCR.
I I
I I
i 15.2.4 I
l l
l l
l l The initiator of the NCR and his department head are to review the l
ldispositionforacceptancepriortoimplementingcorrectiveaction.
If I
they cannot agree with the assigned individual on the disposition, the l
lplantGeneralManageristodecide.
l For a repair or use-as-is l disposition, a cognizant engineer knowledgeable in the design l
requirements for the affected item is also to review the NCR for l
l concurrence of the disposition. Written justification for the_ design D
g change, repair or deviation that has been accepted is to be documented to g
i denote the as-built condition and is to be made a part of the NCR.
I I
I I
I i
15.2.5 l
1 1
I I
l The acceptability of rework or repair of materials, parts, components, I
lsystemsandstructuresaretobeverifiedbyreinspectingtheitemas l'
I originally inspected or by a method which is at least equal to the l
loriginalinspectionmethod.
The rework and repair inspection records are l
l to be documented and become part of the permanent records for the item.
I Upon completion of the corrective action, the Manager, Nuclear Quality l
l Control is to verify completion of corrective actions in accordance with I
plant procedures and if acceptable, close the NCR.
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15.0 NONCONFORMING MATERIAL, IPAGE 15-2 l
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l PARTS AND COMPONENTS l
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l l
I
l I
l-l '15.2.6 1
1 l
1
-Q
~l I
l For ASME Code,Section III, Division 1 materials, parts and components
-[
l 'dispositioned repair or use-as-is, the NCR is to be subject to review and-l concurrence by the Code Inspector.-
l l
l l
l 15.3 REPORTABLE'NONCONFORMANCES
.1-l I
1
~l-i 15.3.1 I
l l
l I
-l Honconforming items or. conditions which are reportable per the Technical l
Specifications to the NRC are to be docunanted by the initiator and l
forwarded to the Special. Projects Manager.so thel appropriate report, per I
plant procedures, can be prepared.
1
-l 15.3.2 l
l l
Upon disposition'of the report by the responsible group the PSC reviews l
the report for concurrence and possible assignment of additional I
corrective actions and forwards the report to.the plant General Manager l
l for final approval.
l I
I i
l 15.3.3 I
l l
I l-l l The LRGO Licensing section is to be responsible for transmitting approved l
I y
reports to the NRC within the time period specified in the Technical
~
-l Specifications and Licensing procedures.
l l
l l
1
-l 15.4 SUPPLIER NONCONFORMANCES l
l 1
1 l ~ 15.4.1 I
l 1
I l -
l
-- l Procurement documents are to contain requirements for the l
. vendor / contractor to identify nonconforming conditions to AP&L which l
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15.0 NONCONFORMING MATERIAL, IPAGE 15-3 l
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l PARTS AND COMPONENTS l
l
~l i
I I
f I
(
l I
l I violate a technical or material requirement of the procurement document l
p and which results in a disposition of repair or use-as-is.
All such
~
l I
nonconformances are to be reported to AP&L for evaluations and I
I acceptance.
The vendor / contractor is to document such nonconformances on g
l their applicable nonconformance report which is to be included in the l
final documentation package submitted to AP&L, in accordance with the l
l l
l l
l 15.4.2 l
l l
1 l
l l
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 l
accepted by AP&L.
I I
i 15.5 RECORDS I
I I
15.5.1 l
l l
Upon completion of disposition and verification activities, the completed l
NCR's, reports, and related documents generated to ensure proper l
disposition and resolution of the nonconformance are to be forwarded to I
g l
and maiatained by the Document Control Jenter.
l I
I I
l '15.5.2 I
1 1
I-1 I
l The Manager, Nuclear Quality Control is to maintain and issue a monthly l
report to the plant General Manager, identifying the current status of I
l all open NCR's for management review.
I l
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15.0 NONCONFORMING MATERIAL, IPAGE 15-4 l
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l PARTS AND COMPONENTS l
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I I
I
l l
16.0 CORRECTIVE ACTION I
l 1
I pd i
.l 16.1 SCOPE i
j.
I I
I I
l A corrective actions system is to be established to assure that l
conditions adverse to plant safety, such as failure, malfunctions, 1
deficiencies, deviations, defective material and equipment, abnormal l
,I occurrences and nonconformances are promptly identified and corrected.
l l
In the case of significant conditions adverse to safety, this. system is l
to' assure that the cause of the condition is determined and corrective I
l action taken documented and reported to appropriate levels of management i
for independent review.
I I
I 16.2 GENERAL I
I I
I I
I 16.2.1 I
I I
l l
I When deviations, deficiencies, malfunctions-or other abnormal occurrences l
l or conditions are encountered, they are to be reported to responsible l
I authorities for review and disposition in accordance with Section 15 of l
l this manual.
l l
l l
1 l
16.2.2 l
1 I
l-l l
Cognizant supervisors are to review discrepancies discovered during the l
course of station operations, and in the case of significant conditions
~
l adverse to safety, initiate action to identify their cause and take l
necessary corrective action to prevent their recurrence.
Corrective l
action measures to resolve the discrepancies and to prevent their l
I recurrence are to be documented in accordance with Section 15 of this I
I I
l manual.
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TOPICAL REPORT IREV.
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10 ATE 6/10/83 l
1 I SECTION:
16.0 CORRECTIVE ACTION lPAGE 16-1 l
l L
l l
l 1.,
I I
I
l l
I l
l.16.2.3 l
1 I
(v~)
l l
l The appropriate plant department head is to review recorded I
nonconformances and.nay specify the need for additional corrective l
l action.
The plant's General Manager is to review the monthly status reports concerning "open" nonconformance reports and takes appropriate l
l 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
ltechnicalsupportgroupsattheplantand/orLRGOtoevaluatethe I nonconformance for final disposition.
I l
l I
I I
16.2.4 l
l l
l l
l Adverse quality or safety conditions discovered by QA or QC personnel l
lduringtheirdocumentreview, inspection,auditorsurveillance 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
I and QC procedures.
I (n) l I
l I
l 16.2.4.1 l
l l
l l
l The responsible organization to which the corrective action document is I
'g addressed is to evaluate the adverse condition and document the action I 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.
I I
I I
I i
16.2.4.2 I
l I
I I
l The response is to be evaluated by the initiating organization (QA or QC)
I to determine the adequacy and completeness of the corrective action l
l I
I I
I i
I I
I I
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TOPICAL REPORT IREV.
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16.0 CORRECTIVE ACTION lPAGE 16-2 l
l L
l l
l l
l l
1
I I
I l
l commitments.
If the response-is acceptable, the initiating organization
.I is 'to perform follow-up action to verify implementation of. the corrective I
O i
}
1 action commitments, document their findings and when acceptable, close
, l.
out the corrective action document.
I
'l l16.2.4.3 l
l l-l j
If the initiating and responding organizatio'ns cannot agree upon a I ' resolution, it is to be referred to :the next level of management for 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_
l lresolutionofQCandQAinitiatedcorrectiveaction' documents.,
1 respectively.
l l-l l-l l
l 16.2.5 l
I l~
I l
l When vendors furnish products or services that do not conform to the l
_ requirements of the applicable purchase contract and,-in the opinion of-I the Manager,- Nuclear Quality Control, the vendor warrants consideration l
'I ~O i
for reappraisal, the Manager, Nuclear Quality Control is to submit a i
. I vendor reappraisal request to the Manager, Quality Assurance for I
determination of action to be taken.
Results of the reappraisal, l
l together with a request for specific corrective actions, are to be.
I' 7
j
. ltransmittedto-thevendor.If the vendor does not improve his quality l
l. assurance system and products as requested,'the Manager, Quality l
lAssuranceistoremovethevendorfromtheQualifiedVendorList(QVL)in g'*
I accordance with departmental procedures.
I I
l-I l-I I
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1.
l SECTION:
16.0 CORRECTIVE ACTION lPAGE 16-3 l
L l
L I
I l
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l l' 16.3 SIGNIFICANT CONDITIONS I
I l
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.I 16.3.1 1
I I
I I
I Significant conditions are to include, as a minimum, the following:
1 l
I I
4 I
i 1
(1) Conditions that have a direct adverse affect on the safety of I
the plant or personnel.
l 1
(2) Conditions that have caused the uncontrolled release of 1
radioactive materials (liquid, solid, gaseous ~or air I
g.
I particulate) to the environs.
l-(3) Trends indicated by nonconformances which could lead to unsafe I
plant operations.
'I h
(4) :Any condition the plant's General Manager considers to be of~
l major consequence.
~
I 1
l
-l l
-1 16,3.2 l
t i
l' I
I I When significant condt ions adverse to safety are discovered, the 1
O Ig responsible supervisor ahd management personnel are to evaluate the I
g l ~ condition and determine if it is a reportable occurrence.
Reportable
{
occurrences are to be handled as described in Section 15 of this manual-I and are to be submitted to the PSC and SRC for review.
I i
I l
I
'l 1 16.4 VERIFICATION 1
l l-1 I
I Verification by surveillance or audit of the effective implementation of I
f corrective actions is to be periodically performed and documented by 1 Quality-Assurance personnel. Audits are to be performed in accordance l
L
-with Section 18 of this manual.
l l
l l
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I I
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I
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1 I
' O-F i
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P l.
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16.0 CORRECTIVE ACTION IPAGE 16-4 i
1-L I
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I I
__ _ l I
~
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l-l l
l 17.0 QUALITY ASSURANCE RECORDS 1
l
[9 I
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v' l 17.1 SCOPE I
I I
I I
l 17.1.1 l
1 g
I l Documentation covering design, construction, procurement, fabrication, I
inspection, mainienance, nonconformance and' corrective action, test and I
audit activities is to be filed and stored 'to provide objective evidence I
of quality-related activities and to assure the ability to reconstruct l'
I significant events, Control'of records is to be in accordance with
}
lRegulatoryGuide1.88,Rev.2(10/76)unlessotherwisenotedinTable1.
g
-l g
17.1.2
-l l
l Quality assurance records'are to include operating l'ogs, results of l
reviews, inspections, tests, audits, matbrial-analyses' qualifications of l
I g
personnel, procedures, historical drawings, specifications, engineering-l g
I reports, calculations, correspondence and related records, pertinent to l
O
'I L
quality as defined in plant procedures for records management.
I g
i I
l17.2 RESPONSIBILITY
,I I
i I,
17.2.1 l
l l
,I ~ The Plant Administrative Manager is responsible for the establishment, I
implementation and maintenance of the records, management program to be i
I used throughout.the operational life of the plant and for ensuring that l
l documentation retention requirements comply with applicable technical l
l specifications, codes and regulations.
1 I
s 1
I I
l-I I'
I I
I I
l l
.I l
l_
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I T
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I TOPICAL REPORT lREV.
6 l
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1 SECTION:
17.0 QUALITY ASSURANCE RECORDS lPAGE 17-1 l
l l
L l
l 1-I I
l i
1 l
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l.
I l
.17.2.2-l I
l 4
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--l AP&L personnel,. other than plant staff, and outside firms that perform l
.I I
{
work on.the plant'in.the areas of design, procurement, maintenance, I modification, testing, quality assurance and special nuclear materials i
laretoprovidedocumentation/certificationrecordstotheplantfor l
U l 1 subsequent storage and retention by the Plant Administrative Manager.
l
~
l l
l s
i:
^
l -17.2.3..
I l
I I
i I
l-I Quality Assur?nce personnel are to periodically audit quality-related l
l records and' records filing and storage procedures to assure that the
- I l
N-I records management program is being properly implemented.
Audits are to l
lbeperformedasoutlinedinSection18ofthis' manual.
l j
l l
17.3 DOCUMENTATION RETENTION-l I
l l17.3.1' Lifetime Quality Assu.ance Records 1
-l l17.3.1.1 I
_ l I
fl<
l Lifetime-recordsaredefinedasthosewhichmeetoneormoreofthe t
I following criteria:
I l
l I
I l
(1) Those which would be of significant value in demonstrating l
l l
capability for safe operation.
1-
{
l 1
~ (2) Those which would be of significant value in maintaining, I
1 q.
reworking,. repairing, replacing or modifying the item.
I (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 inservice 1
g g
inspection.
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6 l
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P l
lDATE 6/10/83 l
I 1 SECTION:
17.0 QUALITY ASSURANCE RECORDS lPAGE 17-2 l
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l 17.3.1.2 I
,l 1
U l Lifetime quality-related records are,to be maintained for the life of the l
l particular item while it is installed in the plant or stored for future l
l use as prescribed in applicable plant procedures for document retention I
and disposition.
I I
l17.3.2 Non-Permanent Quality Assurance Records l
l l17.3.2.1 l
f l
l l Hon permanent records are defined as those which meet all of the l
l following criteria:
I l
l I
l I
(1) Those of no signiff,7 ant value in demonstrating capability for l
l safe operation.
i l
l (2) Those of no significant value in maintaining, reworking, l
l repairing, replacing or modifying the item.
i I
(3) Those of no signifiednt value in determining the cause of an I
7,b l
accfdent or malfbnction of an item.
I (4) Those which do not provide baseline data for inservice I
inspection.
I I
,I l
17.3.2.2 l
l Non permanent records are to provide evidence that an activity was l~
l performed in accordance with applicable requirements and be retained for i
specified periods as directed by the applicable plant procedures for i document retention and disposition.
I I
I I
I l_ 17.3.3 i
!f I
I I
l Categories of permanent and non permanent records to be maintained and I
their. appropriate retention periods are described in plant procedures.
I I
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TOPICAL REPORT IREV.
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17.0 QUALITY ASSURANCE RECORDS lPAGE 17-3 l
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I l
l 17.3.4 I
I l
b' 1 l
i l
l The Manager, Nuclear Quality Control is responsible for receiving, l
linspectingandauthenticatingsuchdocumentsasdirectedbyplant l
l procedures for turnover of quality assurance documents from suppliers to l
AP&L.
When approved for receipt by Quality Control, such records are to I be transmitted to the Plant Administrative Manager for filing and l
storage.
g l
l l
17.4 STORAGE I
I I
I I
l17.4.1 l
l l
Permancnt records are to be stored in a fire rated vault and be:
l l
(1) Adequately protected from earthquake, flood and similar l
hazardous natural phenomena.
l (2) Made safe and secure from theft, vandalism and unauthorized i
use.
m l
(3) Adequately protected against environmental deterioration.
l (4) Adequately protected against fire.
I l
I l
l l
17.4.1.1 1
1 I
I I
l The following features or suitable alternatives are to be incorporated in l
l the design of the storage facility:
g I
I (1) Reinforced concrete, concrete block, or masonry construction.
l l
(2) Coiicrete floor and roof with sufficient slope for drainage; if l
a floor drain is provided, a non-return eneck valve shall be l
included.
I (3) Firo retardant door (two-hour Underwriter's rating minimum).
l (4) Sealant applied over walls as a moisture or condensation l
I, barrier.
I I
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l
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l TOPICAL REPORT lREV.
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17.0 QUALITY ASSURANCE FECORDS lPAGE 17-4 l
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l l
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I
m i
I I
I I
(5) Surface sealant on floor providing a hard-wear surface to l
l minimize concrete dusting.
gV l
(6) Foundation sealant and provision for drainage.
l l
(7) Forced-air circulation with filter system.
l l
(8) Ory chemical or gas fire protection system.
l (9) No pipe other than those providing fire protection to the l
storage facility is to be located within the facility.
l 1
l l
l 17.4.1.2 l
l l
l l
l l
For storage of film and other special processed records, humidity and l
ltemperaturecontrolsaretobeprovidedtomaintainanenvironmentas l
l recommended by the manufacturer and plant procedures.
l l
l l
l 17.4.1.3 l
I I
I I
i l A list is to be prepared by the Plant Administrative Manager designating l
lthosepersonnelwhohaveaccesstothestoragefiles.
l I
o.
I U
17.4.2 I
i l
Plant storage systems are to provide for the accurate retrieval of I
information without undue delay and be sufficient to control and account I
for records removed from the storage facility.
l 1
I l17.5RECORDSINDEXINGANDRECEIPTCONTROL l
I l17.5.1 l
l l
Indexing methods and systems for quality-related records are delineated I
in plant procedures for plant records management.
I I
l l
1 I
I I
I I
I I
I I
I
(~1 1
I I
I V
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17.0 QUALITY ASSURANCE RECORDS lPAGE 17-5 l
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L.
1 I
I I
I I
i 17.5.2 I
I I
Q l
l i
Records submitted for storage in either lifetime or temporary files are l
ltobesubjecttothefollowingrequirementsforreceiptcontrol:
l l
1 (1) Establishment of a records check list designating the required l
l quality-related records.
l l
(2) Establishment of a system designating criteria for document I
inspection to assure that records are accurately completed, I
l legible and received in good condition.
I (3) A file system to indicate which quality-related documents have l
been received.
I l
l17.5.2.1 l
l l
lImplementationofreceiptcontrolrequirementsforstorageisthe l
l responsibility of the Plant Administrative Manager.
I I
I I
I i
17.6 FINAL DISPOSITION l
O i
i l
l l The plant Administrative Manager is responsible for disposal of l
quality related records in accordance with plant procedures for document I
retention ar;d disposition, which permits periodical purging of records I
retained past their required retention date.
I I
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17.0 QUALITY ASSURANCE RECORDS IPAGE 17-6 l
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i
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- - - - - - - - - - - - - ' ~ - - ~ ' " - - ' ' ' ' ' -
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l 18.0 AUDITS l
l l
(]
l l
I 18.1 SCOPE l
l l
1 1
l 18.1.1 I
l l
l l
l l A comprehensive system of planned and periodic audits are to be provided l
to assure and verify compliance with all aspects of the administrative l
controls and quality assurance program.
Audits are to be planned and l
l performed in acccrdance with written procedures, plans and checklists and i
are to conform to the applicable portions of Regulatory Guides 1.144, l
lrev.1(9/80)and1.146,rev.0(8/80),unlessotherwisenoted,inTable i
1.
l l
l l
l l
18.1.2 l
1 1
I I
I The audit program is to include provisions to determine the compliance l
lwithandeffectivenessofthequalityassuranceprogramincontrolling l
l Structures, systems, components and activities in accordance with the l
lrulessetforthinthecodes,standardsandregulationsidentifiedinthe l
l Introduction of this manual.
l l
l l
l l
18.2 AUDIT PERSONNEL l
l l
1 I
l 18.2.1 l
I l~
l I
l The Quality Assurance Manager is assigned auditing responsibility within l
this quality program and is responsible for the selection and assignment I of auditors.
Auditors are to be independent of any direct responsibility i
,I for performance of the activity which is to be audited and are not to l
report to a management representative who has direct responsibility for l
the activity being audited.
I I
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TOPICAL REPORT IREV.
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18.0 AUDITS lPAGE 18-1 l
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I
I 1
I I
I i
18.2.2 l
l l
(l I
l U
l Auditors assigned auditing responsibilities are to have experience and l-l training commensuate with the scope, complexity and/or special nature of l
l the activities to be audited. When audit assignments are made, I
lconsiderationsaregiventospecialabilities,specializedtechnical l
l training, prior pertinent expertise, personal characteristics, education I
and capability.
If no one within the QA0 meets these prerequisites
- l. completely, technical specialists are to be used to assist in the l
lauditingoftheactivity.
Technical specialists are to meet the I
requirements of paragraph 18.2.1 of this section.
I I
I I
l l
18.2.3 1
I I
I l
l 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:
l I
l l
l I
(1) Regular, active participation in the audit process.
I l
l (2) Review and study of codes, standards, procedures and I
instructions.
l l
(3) Participation in training or orientation programs.
I l
l18.3AUDITSCHEDULE l
l l
18.3.1 1
I I
Audits are to be performed on a planned and periodic basis in accordance I with an audit schedule. Audit schedules are to be prepared at the I
beginning of each year by the QA0 and approved by the Quality Assurance I
g l
Manager and SRC.
I I
I I
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I I
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18.0 AUDITS lPAGE 18-2 l
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l l _ __
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--- I
I I
i l
.l 18.
I l
I (V'1 l
l l Au Jit schedules assure that as a minimum, the following areas are audited l
' the indicated frequencies within AP&L:
l l
1 l
(1) The conformance of facility operation to provisions contained I
within the Technical Specifications and applicable license l
l conditions at least once per year.
l l
(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
l the entire facility staff at least once per year.
l (3) The results of all actions taken to correct deficiencies l
occurring in facility equipment, structure, systems or methods I
of operation that affect nuclear safety at least once per six l
months.
l (4) The Facility Emergency Plan and implementing procedures at l
l least once per year.
l l
(5) The Facility Security Plan and implementing procedures at least l
nU l
l once per two years.
l (6) Any other area of facility operation considered appropriate by l
the SRC or the Energy Supply Senior Vice President.
l l
(7) The Facility Fire Protection Program and implementing l
I procedures at least once per two years.
l l
l l18.3.3
[
l I
Audits of vendor / contractor activities are to be scheduled as identified I
in Section 7, paragraph 7.3.3 of this manual.
These audits are to i
levaluateandverifytheirqualityassuranceprogram,proceduresand I
activities, to assure compliance with the procurement documents, and to l
verify they periodically review and audit their suppliers quality l
l assurance program.
I l
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18.0 AUDITS IPAGE 18-3 l
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18.3.4 g
l l
Q\\ '
l l
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 l
requirements of the technical specifications, this manual and Regulatory l
l Guide 1.33, rev. 2 (2/78), unless otherwise noted in Table 1.
l 1
1 I
I I i 18.3.5 1
I I
I i
l Regularly scheduled audits may be supplemented, as required, to cover
.l lunforeseeneventsorchangedrequirements.
I l
l18.4AUDITIMPLEMENTATION l
1 l
18.4.1 I
l 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 lChecklistsaretobeusedduringtheaudittoassurethatall l
l requirements of the activities audited are addressed during the audit and l
that those procedures and instructions issued to control the audited I
activity are adequate.
l l
l l
l l
18.4.2 l
1 l-I l
l l
Upon completion of an audit, a written report is to be prepared whict l
l includes at least the following items:
l i
l I
l (1) Description of audit scope and date.
l (2)
Identification of the auditor (s).
l (3) A summary of audit results.
I l
(4) Details of nonconformances or programmatic deficiencies.
l l
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TOPICAL REPORT lREV.
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18.0 AUDITS lPAGE 18-4 l
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I I
l (5) Recommendations for correcting nonconformances or improving the I
Os l
Quality Assurance Program, as appropriate.
I l
i l18.4.3 I
I Deficiencies identified as a result of an internal audit are to be l
recorded on an Audit Finding Report (AFR) by the auditor and issued to l
lthedepartmentheadresponsiblefortheareaauditedforcorrective l action.
The department head or their assigned designee is to provide l
prompt corrective action to the deficiencies identified and document on l
the AFR the action taken or to be taken to prevent recurrence.
I lAppropriatefollow-upincludingre-auditsbytheassignedauditgroupis l
l conducted in the deficient areas to verify proper and timely I
implementation of corrective action commitments.
Follow-up actions are l
l to be documented on the AFR.
l 1
1 I
I I
18.4.4 l
l 1
I l Audit reports pertaining to plant activities are to be independently l
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 Quality l
l Assurance Manager and appropriate levels of management having l
lresponsibilityintheareaauditedtoassuretheirawarenessofthe l-L l
findings.
l l
l l
1 l
18.4.5 l
l l
l l
l l Audit results and findings related to external audits conducted by QA l
personnel are to be recorded and distributed to the Quality Assurance l
l Manager and a designated representative of the audited organization.
l l
l
~
I l
l 1
I I
Q' l
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TOPICAL REPORT lREV.
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18.0 AUDITS IPAGE 18-5 I
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I 1
O O
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9' PRESIDENT AND CHIEF r
EXECUTIVE OFFICER
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C=m W
CORPORATE COMMUNICATIONS SR.VICE PRESIDENT S VICE PRESIDENT ASSIST. TO THE PRESIDENT o.
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ENERGY SUPPLY ENERGY DELIVERY 8 FINAME REGULATION ADMINISTRATIVE CONSERVATION 8
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FIGURE 2.
AP&L CORPORATE SERVICES IPAGE F-2 I
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ENERGY SUPPLY SR. VICE PRESIDENT
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MANAGER GENERAL MANAGER MANAGER r-l MANAGER o
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SUPERIN T EN DENT SUPERIN TE N DENT I
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SHIFT SHIFT SUPERV SORS SUPE RVIS O RS SUPE RVISOR S l
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6 i
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l lDATE 6/10/83 I
l I
FIGURE 6.
AP&L NUCLEAR PLANT ORGANIZATION IPAGE F-6 l
l L
1 (PLANT OPERATIONS & MAINTENANCE l
I I
I l
f
~
l I
l I
I I
I I
o j
,i I
I II
! I l
l l
1 l
GENERAL I
MANAGER I
I l
I I
l I
I I
I I
l ENGINEERING S l
TECHNICAL l
I SUPPORT g
I MANAGER I
I I
l i
i i
i l
l TECHNICAL PLANT PLANT CPERATIONS I
g ANALYSIS ANALYSIS ENGINEERING ASSESSMENT l
SUPERLNTENDENT SUPERINTENDENT
. SUPERINTDEENT SUPERINTENENT i
g
.I i
EMERGENCY PLANT MECHANICAL HEALTH I
PLAN PERFORMANCE ENGINEERING PHYSICS I
I Co0Ron4 tor SUPERVISOR SU=ERvis0R SUPERINTENDENT O
i l
i I
l RAD NUCLEAR ELECTRICAL HEATH I
l CHEMISTRY SUPPORT ENGINEERNG PHYSICS l
g SUPERVISOR SUPERVISOR SUPERVISOR SUPERVISOR i
j l
l I
CHEMISTRY &
COMPUTER DRAFTING &
HEATH l
I ENVIRONMENTAL SUPPORT
-DRAWING CONTROL PHYSICS SUPERVISOR SUPERVISOR SUPERVISOR SPECIALISTS I
l 1
1 I
I I
I I
I I
I I
I I
I I
I I
I I
I l
ARKANSAS POWER S LIGHT COMPANY I
l l
NUCLEAR PLANT ORGANIZATION I
I I
I I
I I
O lA i
top 1 cat ReeoRT iaev.
s i
l P
I IDATE 6/10/83 l
l I
FIGURE 7.
AP&L NUCLEAR PLANT ORGANIZATION IPAGE F-7 l
l L
I (PLANT ENGINEERING & TECHNICAL SUPPORT)
I I
i i
I I
i
.I I
l I
I l
I O
l l
1 l
.I l
!I I
I I
I I
I l
I I
I II l
4 I I
I l
GENERAL i
g MANAGER I
l I
I I
1 I
^ NENN""
l I
I I
I I
I I
I I
I O
i TRAiNiNo
-OFFICE HUMAN MATERIALS PLANT eu Ee>N T sEaviCE.
EsOu CE.
MANAeEMENT CONT oLLe-i supEnvisOn supEnvisOs sueEnvisOn i
l l
I I
I I
I l
1 I
I I
SECURITY EMPLOYMENT &
SAFETY &
COORDINATOR INDUSTRIAL FIRE I
RELATIONS PREVENTION i
l COORDINATOR COORDINATORS I
l 1
I I
I I
I I
I I
I I
I I
I I
I ARKANSAS POWER 8 LIGHT CO.
I I
I NUCLEAR PLANT ORGANIZATION I
I I
I I
I O
lA l
l T0eICAL aseoar inev-6 l
P l
IDATE 6/10/82 I
l i
FIGURE 8.
AP&L NUCLEAR PLANT ORGANIZATION lPAGE F-8 l
l L
I (PLANT ADMINISTRATIVE' SERVICES) I l
I I
I I
t
r-I I
I l
l TABLE 1 l
l I
O l
ARKANSAS POWER & LIGHT'S EXCEPTIONS / INTERPRETATIONS
(
i 0F REGULATORY' GUIDES AND ANSI STANDARDS APPLICABLE l-
-TO THIS QUALITY ASSURANCE PROGRAM l
l l
1 I
I I
I Regulatory Guide /
Exceptions /-
ANSI Standard.
Requirement Interpretation l General Certain Regulatory The AP&L commitment refers l
Guides invoke or
'to the Regulatory Guides and l
imply Regulatory ANSI Standards, specifically l
Guides and standards identified in this TOPICAL.
l l
'in addition to the Additional Regulatory Guides, i
standard each ANSI Standards, Guides and I
primarily endorses, similiar documents implied or l'
l Certain ANSI Stan-or referenced in those l
dards invoke or -
specifically identified in I
imply additional this TOPICAL are not part of l
l standards.
this commitment.
l 1
General Certain ANSI Dur commitment to those l
Standards and/or standards applies only to l
Regulatory Guides those systems, structures, i
extend the scope of and components whose satis-l l
applicability to factory performance is l
include systems, required to prevent postu-l structures, and lated accidents that could l
components whose cause undue risk to undue l
satisfactory perfor-risk to the_ health and safety l
mance-is required of the public; or to mitigate l
for a plant to the consequences of such
'l operate reliably on accidents.
Reliable ~ operation l
I; I
I I
l l
I I
l A
l TOPICAL REPORT lREV.
6 l
P l
lDATE 6/10/83 l
l l SECTION:
TABLE 1 lPAGE T1-1 I
I L
I I
I
,l l
l I
L
I I
l l
l "high-value-of the plant may depend upon 1
articles."
other systems, structures and g
g D
I components which are not I
l covered by this commitment.
l l
lANSIN18.7 Where changes are Consistent with the require-l (Section 5.2.13.1) made to procure-ments of ANSI N45.2.11, para-I ments, they shall graph 7.2, minor changes to l
l be subject to the (procurement) documents, such I
same degree of as, inconsequential editorial I
control as was used corrections, or changes to I
in the preparation commercial terms and conditions I
of the original may not require that the re-I documents, vised (procurement) document l
l receive the same review and I
l approval as the original 1
documents.
I I
I I
l l ANSI N45.2.1 Fresh water criteria The turbidity requirement on I
g (Section 3.2) for chlorides, and fresh water is deleted and l
Jackson Turbidity the c.hloride requirement is i
Units.
revised to read "less than l
250 ppm."
The turbidity I
g requirement for demineralized I
water is deleted.
I I
l' I
I I
" Preliminary visual Inspection after unloading is l
Subsection 5.2.1 inspection or exami-sufficient to determine the l
nation shall be per-condition of many items.
In I
g formed prior to special instances, pre-unload-I unloading..."
ing examination is performed.
I I
I l
i I
I I
I I
I I
I I
I O
I 1
I I
O I
A l
TOPICAL REPORT lREV.
6 l
l P
l lDATE 6/10/83 l
l I SECTION:
TABLE 1 IPAGE T1-2 I
I L
I l
l l
l 1
I
l l
l-l l ANSI N45.2.2 The (receiving)
Receiving inspection ~is per-l l'Section5.2.2 inspections shall formed in a manner and in an l
be performed in an environment which does not
. l.
area equivalent to endanger the requisite quality l.
.l the level of~ storage: of an item.
The. receiving
['
l~
requirement for the inspection area environmental l
item.
controls may b'e less stringent l
I 4
1 1
than storage environmental l
. requirements for,that item, l
however, the short time spent I
in the less. stringent receiv-l l
ing inspection area shall be l
l of such duration that will l
not adversely affect ~'the item j
l being received.
l l'
~l l
l l
l-l ANSI N45.2.2
... The 'Special The "Special Inspection"
-l l
Paragraph 5.2.3 Inspection' pro-procedure shall be readily l
cedure, complete available t i inspection l
with documentation personnel and'may be attached.
L
'l-instructions shall to the item or container.
l be attached to the l
' item or con-l tainer..."
I l
l
-ANSI N45.2.2 The use or storage
' People working in storage
~
l ' Subsection 6.2.4 of food, drinks, and areas have a right of access l
salt dispensers in to water dispensers per OSHA l
l any storage area is requirements.
Additionally, l
prohibited.
due to the location and l
layout of the building, per--
l I
sonnel may temporarily store l
[
l I
l l
l l
l 1
I h
I l
I l
l l
A l
TOPICAL REPORT lREV.
6 l
l P
l lDATE 6/10/83 l
l l SECTION:
TABLE 1 lPAGE T1-3 l
l L
l l
l
-l i
I I
,-,,wwe%-+-ve w re e1 ew s*
l l
l l
l lunches in the work place.
l l
This area is policed'for
-l sanitation.
l
~
l l
l l
" Container markings Containers are adequately l
l Appendix (A-3')
shall appear on a marked for storage, identifi-l A.3.9 (1) Secc:td minimum of two sides cation, and retrieval.
l Group of the container, Multiple marking requirements I
g l
preferably on one are imposed, where necessary.
I side and one end."
l I
" Container markings Container markings are of a l Appendix (A-3) shall be...no less sizo which permits easy l
lA.3.9(4)Second than 3/4" high recognition.
y l
Group container permit-l l
ting."
l l
" Container marking The information required I
l Appendix (A-3)-
shall include the in container marking is l
A.3.9 following informa-
-evaluated on a case-by-l tion..."
base basis.
Marking is l
l adequate in each case.
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 lSectionA3.5.1(1) brightly colored."
l l
ANSI N45.2.2 Plugs or caps shall In cases where plugs or caps l Appendix (A-3) be secured with tape do not snugly fit, additional l
I Section A 3.5.1 (5) or other means as securing devices or measures l
necessary to prev'ent which will not be detrimental l
l accidental removal.
to the item will be used.
l I
l l
l 1
I I
I l
O i
i i
i l
A l
TOPICAL REPORT lREV.
6 l
l P
l lDATE 6/10/83 l
l l SECTION:
TABLE 1 IPAGE T1-4 l
1 L
l l
l l
l I
= _ - _. _
E 4
I I
l I
l' ANSI N45.2.2 Marking of' items The last paragraph of Section l
l Appendix (A-3) not withi,n a con-A.3.9 could be interpreted as
_l-Section A~3.9 tainer.
prohibiting any direct marking l.
-l on bare austenitic stainless j.
l steel and nickel alloy metal l
surfaces.
In lieu thereof, l
paragraphs A.3.9. (1) and (2) l l
will be used to control
{
l marking on the' surface.of-l l
l austenitic stainless steels l
and nickel base alloys subject l
to the following limitations:
l j
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
contact,'or shall not be'used l
on surfaces of corrosion l-O.
,i resistant alloys.
Low sulfur, i
g l
low fluorine and/or low l
l 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 I
(a) Total inorganic and l
l-l organic halogen content l
shall not exceed one (1) l l
percent.
l l
(b) The sulfur content shall l
not exceed one (1) l percent.
I l
l l
!O l
A l
TOPICAL REPORT lREV.
6 l
l P
l lDATE 6/10/83 l
l l SECTION:
TABLE 1 lPAGE T1-5 l
l L
l l
l 1
I I
I 9
~
l l
l l
-Inert Gas Blankets There may be cases involving l
l 1arge 'or complex shaped items
[
I g
. I for which an inert or dry air l.
l purge'is provided, rather l
l than a static gas blanket, in l
l order to provide adequate l
l protection due.to difficulty l
l of providing a leak proof g
' l barrier.
In these cases, a i
positive pressure purge flow l
l may be utilized as an alter-1 nate to a leak proof barrier.'
l I
ANSI N45.2.2 Limits halogen and Engineering may allow the use I
l Appendix A, sulphur content of of tapes containing greater l
l A.3.5J2, (1), (a) tape.
amounts of halogens after l
appropriate evaluation, l
however, the quantities shall l
not be such that harmful 1
.O i
g concentrations could be i
g I
leached or relased by break-I down of the compounds under l
expected environmental I
l conditions.
l l
lRegulatoryGuide I
General Alternative equivalent l
1.39 ANSI N45.2.3 requirements may be utilized I
to cover those situations not I
l included in the subject'
-l I
Standard, for example, situa-g I
tions in which shoe covers l
and/or coveralls are required l
but material accountability I
I is not.
In addition, zones I
l i
I
- Q l
l I
I l
A l
TOPICAL REPORT lREV.
6 l
l P
l lDATE 6/10/83
-l l
l SECTION:
TABLE 1 -
1PAGE T1-6 l
l L
l l
I l
l I
l-e
...._.........-.._,,....,.._,.._,-.__....~,_.-...___,_,_..,,._,c._._
I I
l l
l might be combined into the l
I
',)
l next more restrictive I
I l
category in order to reduce 1
total number of zones.
l l
lANSIN45.2.3 Identifies various When this standard is applied, l
housekeeping re-its requirements are imple-l quirements, includ-mented in those areas affected l
ing cleanliness, by work activities associated l
l fire prevention, with modifications, opera-l l
and fire protection tions, or maintenance as l
which must be determined necessary by Plant l
accomplished during Staff.
l the progress of I
construction.
l l
l l
l l
Regulatory Guide Pre-Construction /
This section required verifi-l 1.30/ ANSI N45.2.4 Installation Verifi-cation that items.are in I
cation satisfactory condition for 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
l and stored in an environment l
which will not adversely l
affect the item.
Documented l
routine inspections and l
periodic audits of the storage l
areas assure that stored items l
l are maintained in satisfactory l
conditions.
Documentation l
of pre-construction verifica-l-
tion in addition to documen-l l
l tation of initial receipt I
l l
1 1
I
(~\\-}
l l
l 1
l A
l TOPICAL REPORT lREV.
6 l
l P
l lDATE 6/10/83 l
l 1 SECTION:
TABLE 1 IPAGE T1-7 l
l L
l l
l l
1 I
I
[
l i
I l
l inspection, periodic storage l
inspections, and audits of l
storage is not required.
l-1 I
I I
l ANSI N45.2.4 Identifies various These tests will be performed l
I tests to be as determined by Engineering l
g l
performed.
or Nuclear Operations based l
l upon the significance of I
change or modification.
l l
l l
l R.G. 1.58 In addition... the AP&L takes exception to this l
(Section C.6) candidate should be requirement.
AP&L'_s education l
l a high school and experience requirements l
l l
graduate or have are in accordance with ANSI l
earned the General N45.2.6-1978.
l l
Education Development l
(GED) equivalent of I
a high school r.
l diploma.
l
\\
l l
l l
l R.G. 1.74/
Definitions of Based upon the guidance of l
ANSI N45.2.10 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 l
l~
l i
I l
R.G. 1.94/
Section 1.4 defines This requirement for rein-l ANSI N45.2.5 inprocess tests and forcing steel will be y
l (Section 1.4) states:
interpreted to permit taking l
the rebar test specimen at l
"... samples of these the fabrication shop, prior l
tests must be taken to start of fabrication of i
l from the lot or the rebar from the heat or l
I l
l l
l l
l 1
i fl l
1 I
I U
l A
l TOPICAL REPORT lREV.
6 l
l P
l lDATE 6/10/83 l
l l SECTION:
TABLE 1 lPAGE TI-8 l
l L
l l
l l
l l
l r
I I
I I
I batch of materials fraction thereof represented l
'l l
supplied to the site by the test specimen.~
For p
~
l for use."
these tests performed at the l
l fabrication shop, certifica-l tion.shall be available to l
l' provideobjectiveevideEce
-l l
that.the test specimens l
represent the material sup-l l
plied for use at.the site.
I i
1 l.
l l ANSI N45.2.5 Requirement:
1 (Section 4.5)
Section 4.5, Con-l l
crete Placement, l
references American l
Concrete Institute I
(ACI) standards l
ACI-305-72, i
l
" Recommended Prac-l tice for Hot Weather
[
I Concreting" and ACI-l 306-66, "Reccamended i
Practice for Cold' l
Weather Concreting."
l 1
i i
l j
l Interpretation:
l 1
In order to clarify l
use of these ACI 1
l standards, we will l
apply the following l
I requirements:
I I
I I
I I
l I
I I
I I
l I
I I
-(]
I I
I I
l A
l TOPICAL REPORT lREV.
6 l
l p
l lDATE 6/10/83 l
l l SECTION: TABLE 1 lPAGE T1-9 l
l-L l
l l
l J
L I
I
1 l
I
'l l
PLACING TEMPERATURES OF CONCRETE:
1 I
L l
o i
-l A.
During hot weather concreting:
1 I
~
l 1
-l l
Placing temperatu'res.of concrete will be l
limited to the following:
l I
i 1.
l
- 1) ' Concrete membirs'less than 3 feet in least f
l dimension will not exceed 90?F.
l~
l 4
l I
I l
- 2) Concrete members from'3 feet to 6 feet in l
l leastdimensionwillNotexceed70*F.
l
~
g I
i
- 3) Concrete members n: ore than 6 feet in least' l
l l
dimension will have placing temperature as.
l l
near 50*F'as can be.obtained by use of ice l
I as necessary up. to 100 percent of adding l
mixing water; and by shading aggregate and l
l sprinkling the coarse aggregate the day it-l I
g is to be used.
Care will be taken so that l
no unmelted ice remains in the concrete at l
1 th'e end of the, mixing period.
l I
i l
B.
Duringcoldw$ather1 concreting:
l l'
g I
I x
I l
In heating.the water and aggregate, live steam
~
~~
l to heat the fine and coarse aggregate shall not' I
be used. Thepermissiblerangeforconcrete l
l temperature shall; be as follows:
l l
l l
~
l l
- 1) Sections less than 3 feet in least I
~
l dimensions: 55 to 75 F.
1 I
l l
l l
l I
1 I
' Q
- 1
-1 TOPICAL. REPORT
[REV.
6 l
1 I
l A
l l
P l
IDATE 6/10/83 l
l 1 SECTION:
TABLE 1 IPAGE T1-10 1
l L
l l
l l__
~l i
I
- -..,. ~.. -.. _. -..... -... - -.. -
1 I
l l
l
- 2) Mass concrete 3 feet or more in least l
I dimension:
45 to 65*F.
I
.l.
l l-l The mixing water and aggregate will be l
purchased as required.
The materials will be
-l j
free of ice, snow and frozen lumps before they I
enter the mixer.
l l-g.
l l
l ANSI N45.2.5 Requirement:
l_
I (Section 4.8) l I
I l
Section 4.8, "In process Test on Concrete and l
Reinforcing _ Steel" states, " Samples for in process l
J l
test of concrete shall be taken at the sampling l
point in accordance with ASTM C172.
This point may I
l be at the truck mixer discharge if the last piece l
)
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."
[
O.
I I
I I
l Interpretation:
l 1
l I
l-j l
For performance of correlation tests, the l
l I
requirements of ANSI N45.2.5-1974 shall be I
1 I
l followed.
l l
l'~
)
l l
l l ANSI N45.2.5 Requirement:
l l,
(Section 4.8)
I
(-
l Section 4.8, "In process Tests on Concrete and l
[
I Reinforcing Steel" contains Table 8 entitled, I
1 I
l
" Required In process Tests." The following l
I modifications to this table will be applied:
I r
l 1
5 l
I o
1 I
l l
l l
l
.i
~ l l
I f]
l l
l 1
l A
l TOPICAL REPORT lREV.
6 l
i.
l P
l lDATE 6/10/83 l
1 I.
1 SECTION:
TABLE 1 lPAGE T1-11 l
- l L
l l
l 1
l I
l
..--......,-,r--
m---.=-.-,
+..-,...c.,
.,- -,,.,-- - -.. ~
,,m
---r-,,,...
-m,
.~,.-~.,,.-y,.,.,,.,-,..we
i 0
t\\
~
r l
'(
l
'l
_ _ ij l
b l
Interpratation:
a l
I a
(
l
]\\,3 l
l I
REINFORCING, STEEL l
l l
l l
l In process testing or reinforcing steel will l
l include the mechanical properties of yield I
strength, tensile strength and percent elongation l
l on full size specimens for each bar size for each I
g l
50 tons or fraction thereof from each m.ill heat.
l Bend tests are performed during material l
l qualification testing only, except as noted below l
for bar sizes #14 through #18.
I J
Q l
l
/.
Table A, " Required Qualification Tests" as applied l
l to reinforcing steel will include bend tests as l
required by ASTM A615' and summarized below:
l 1-I l,
a) For bar sizes #3 through #11, one full size l
specimen from largest bar size rolled from each l
mill heat, unless material from one heat I
differs by three or more disignation numbers.
l e
,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
f b) For bar sizss #14 through #18, Supplementary l
l Requirements S1 of ASTM A615 will be applied.
l 1
I l
One full size specimen for each bar size for
,,# f; l
each mill heat.
If supplementary requirements I
g are not followed for mill tests, they will be l
applied as in process tests.
l l
~l l
l l
l 8
l l
l l
l l
I l
O-I i
i i
l A
l TOPICAL REPORT lREV.
6 l
l P
l lDATE 6/10/83 l
l l SECTION:
TABLE 1 lPAGE T1-12 l
l L
l l
l' l
I I
.-l y
.. - ~,,
,,,..,,--c.e.-.e
I I
I I
l The above interpretation is' consistent with l
Regulatory Guide 1.15, " Testing Reinforcing bars
.I for Category I Concrete Structures," Revision 1, l.
l l
December 1972.
1 l
l In process test specimens may be selected at the I
rebar fabrication shop, prior to start of I
l fabrication of the rebar from the heat or fraction l
thereof represented by the test specime.n.
l l
l l
1 l
Acceptance criteria for any failed test l
l (qualifications as well as in process) may be the l
l same as that for tensile tests specified in l
Subarticle CC-2331.2 of ASME Section III, Div. 2 l
l Code (1975).
This states that' if a test specimen i
fails to meet the specified strength requirements,
_l l
two (2) additional specimens from the same heat and l
l of the same bar size would be tested, and if either l
l of the two additional specimens fails to meet the l
O i
specified strength requirements, the material i
g g
l represented by the tests would be rejected for the I
specified use.
Alternative use of rejected l
l material under strict control may be subject to l_
evaluation by the Project Engineer.
l I
1 ANSI N45.2.5 Requirement:
l (Section 4.9)
I Section 4.9, Mechanical (Cadweld) Splice Testing i
states in paragraph 4.9.4 " Separate test cycles I
shall be established for mechanical splices in l
horizontal, vertical and diagonal bars, for each I
bar size and for each splicing crew..."
l l
I I
I I
I I
l l
l O-i i
i l
A l
TOPICAL REPORT lREV.
6 l
l P
l lDATE 6/10/83 l
l 1 SECTION: TABLE 1 lPAGE T1-13 l
1 L
l l
l 1
I I
I I
l
1.
I i
=l l
l Interpretation:
l l
l O
i 1.
The terms " horizontal, vertical and diagonal bars" l
2 l
will be interpreted to apply respectively to the I
following types of splice positions:
1
^
l l
I l
I a.
Hozizontal, including 10* to horizontal l
I b.
Vertical, including 10* to vertical
]
l c.
45 angle, including 10* to 80* angle l
I l
l l
l The words " splicing crew" will be interpreted to l
l refer to all members on the project that.are-l-
l activitely engaged in preparing and assembling l
l cadweld mechanical splices at the final splice I
location.
Separate test cycles will be established I
for each bar size and each splice position.
l l
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ANSI N45.2.12 An individual audit For those routine audits I
(Paragraph 4.2.1) plan describing conducted during operations, I
the audit to be -
a written procedure (s) l l
performed shall be covering each audit may be l
l l
developed and utilized.
Procedure (s) will l
documented by the identify the audit scope,-
I auditing organiza-
-a requirement that individual I
tion.
This plan checklists be utilized list-l l
shall identify the ing requirements which are to I
audit scope, the be audited and notification I
requirements, the of the audited group.
I activities to be -
l audited, organiza-I tions to be notified, I
the applicable i
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documents, the I
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procedures or check-1 lists.
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lANSIN45.2.13 The certificate The person attesting to a 1
(Section 10.2.d) should be attested certificate shall be an I
to by a person who authorized and responsible l
is responsible for employee of the s.upplier, I
this quality assur-and shall be identified by I
ance function ard the Supplier.
I whose function and I
position are I
l described in the l
Purchaser's/
l Supplier's quality l
l assurance program.
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l l
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 l
couraged, it should the originator's supervisor, I
not be construed if the supervisor is 'the only l
-I tnat such verifi-individual in the organization I
~
cation constitutes competent to perform the l
the required inde-verification.
I pendent design i
veri fication,... "
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l 1 SECTION:
TABLE 1 (PAGE T1-15 l
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l F
l TABLE 3 1.
l I
'O~
I QUALITY PROGRAM POLICIES, PROCEDURES'AND INSTRUCTION
-l
.l MANUALS LIST l
I I
I
-1.
l - 1.
-Quality Assurance Program for Operations j-l-
I l
I l
The' Quality Assurance Program for Operations establishes the l
~
policies and guidelines of the AP&L quality assurance program for l
.I its operating nuclear plants.-
This prograra is to be followed by all I
j-
. organizations' involved in safety related work applicable to l
l operating nuclear plants.
Ll l
l l
l.
l 2.
Energy Supply Procedures Manual l
l' l
I i
1 l
'The Energy Supply Department - Little Rock General Office -(LRGO) l l
employes a system of procedures designated as Energy Supply l'
l
' Department Procedures (ESP) in order to implement Program
'l requirements for the control of design, engineering, nuclear fuel,.
I licensing, training and procurement activities in support of the l
i.
operating plant.
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,.
l l
the Energy Supply (LRG0) Procedures Task Force and the responsible l
l' department head.
1 i
l 1-l' l
3.
Quality Assurance Procedures Manual l
l
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l i
1 The Quality Assurance Organization employes a system of precedures.
l designated as Quality Assurance Procedures'(QAP) in order to assure l-proper implementation of the program.
The QAP's and revisions l-thereto are prepared by the Quality Assurance' Organization, reviewed l-l
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TABLE 3 lPAGE T3-1 l
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l and approved by the Quality Assurance Manager and approved by the l
l Energy Supply Services Director and the Sr. Vice President, Energy l
Supply.
I I
l 1
I l
4.
Quality Assurance Administrative Procedures Manual I
l i
I I
l The Quality Nsmrra Organization also employas a system of l
procederes designated as Quality Assurance Administrative Procedures 1
(QAA).
These procedures provide technical and administrative
-l l
instructions to the Quality Assurance staff to aid in implementing I
g l
their responsibilities within the quality program.
I I
l 1
I 5.
Overall Plant Adminstrative Procedures Manual I
l l
l 1
l l
The plant operation organization employes a system of procedures l
l designated as Overall Plant Administrative Procedures.
These l
procedures implement Quality Assurance Program requirements and l
l l
control on site activities.
Overall Plant Administrative Procedures l
and changes thereto are prepared by the plant staff, reviewed by the i
O l
Plant Safety Committee and approved,by the plant's General Manager.
l V
l The procedures and revisions are also reviewed by the Manager, I
Nuclear Quality Control to assure that Quality Assurance Program i
I commitments are met.
I I
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i I
6.
Departmental Plant Administrative Procedures i
I I
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l Each deprtment (operations, maintenance, engineering and technical I
suppm t, training, quality control, etc.) at the plant has developed I
procedures in support of the Overall Plant Administrative Procedures I
j and this Quality Assurance Program.
These procedures provide i
technical and administrative instructions to the various departments I
to aid in implementing their responsibilities within the quality l
program.
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TABLE 3 IPAGE T3-2 l
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