ML20091G479
| ML20091G479 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/10/1983 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20091G451 | List: |
| References | |
| NUDOCS 8406040291 | |
| Download: ML20091G479 (158) | |
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QUALITY ASSURANCE
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l MANUAL O
OPERATIONS I
SRKANSAS POWER LIG H T
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HELPING BUILD ARKANSAS i
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l-ARKANSAS POWER & LIGHT COMPANY I
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l QUALITY ASSURANCE MANUAL FOR OPERATIONS I
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l TOPICAL REPORT-1 I
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ENERGY SUPPLY SERVICES l
DIRECTOR' g
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SR. VICE PRESIDENT l
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-l l-I APPROVAL SIGNATURES I
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U l REVISION l
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Initial Issue 6/11/74 l
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Response to AEC Questions Submitted 12/13/74 l
l 11/21/74.
Revisions to Section 2, l
l 4, and 7 as indicated.
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2 Response to NRC Questions Submitted 3/4/75 l
l 2/7/75.
Procedure Numbers 1005.xx l
1 changes to 1004.xx (Number Change Only).
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3 General revision to change AEC to NRC, 9/8/76 l
l update organization, reflect NSP l
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l changes.
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4 Eliminate Quality' Assurance Committee 9/8/77 l
l Changes to Procurement Control -
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Qualification of Vendors. Organizational l
l Changes.
Incorporate Technical l
l Specification Changes.
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5 Incorporate Organizational Changes 10/10/80 l
and responses to subsequent NRC I
l Questions.
Incorporate Regulatory l
l Guides and retype document in its l
l entirety in standardized format.
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6 Incorporate organizational changes, l
I delete procedural references l
l throughout manual, and accurately l
l reflect current regulatory commitments l
1 and QA practices related to the l
l safe operatior, of AP&L nuclear plants.
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Manual has been reformated and retyped l
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.in its entirety.
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RECORD OF REVISIONS
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APPROVAL COVERSHEET l
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TABLE OF CONTENTS TC-1 6
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TC-2 6
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INTRODUCTION B-1 6
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TERMS AND DEFINITIONS C-1 6
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2.0 QUALITY ASSURANCE PROGRAM 2
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3.0 DESIGN CONTROL 3
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4.0 PROCUREMENT DOCUMENT 4
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.5.0 INSTRUCTIONS, PROCEDURES 5
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AND DRAWINGS 5-2 6
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MATERIAL, EQUIPMENT AND 7-2 6
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l 8.0 IDENTIFICATION AND CONTROL 8
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OF MATERIALS, PARTS AND 8-2 6
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COMPONENTS 8-3 6
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9.0 CONTROL OF SPECIAL 9
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l 10.0 INSPECTION 10 10-1 6
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12.0 CONTROL OF MEASURING AND 12 12-1.
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l 14.0 INSPECTION,-TEST'AND 14 14-1 6
l OPERATING STATUS 14-2 6
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l 15.0 NONCONFORMING MATERIAL, 15 15-1 6
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l PARTS OR COMPONENTS-15-2 6
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16.0 CORRECTIVE ACTION 16 16-1 6
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17.0 QUALITY ASSURANCE RECORDS 17 -
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AUDITS 18 18-1 6
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AP&L Corporate 19 F-1 6
l-Organization l
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'AP&L Corporate Services 19 F-2 6
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-3 AP&L Energy Supply 19 F-3 6
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AP&L Quality Assurance 19 F-4 6
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5 AP&L Nuclear Plant i
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AP&L Nuclear: Plant 19 F-6 6
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Organization (Plant-l Operations'and Main-l I
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lAP&L Nuclear Plant
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l Organization (Plant l
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1 AP&L Exceptions / Inter-19 T1-1 6
l pretations of Regulatory T1-2 6
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Guides and ANSI Standards T1-3 6
l-T1-4 6
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2 Quality Assurance 19 T2-1.
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Procedures Matrix I
l l-3 Quality Program Policies,-
19 T3-1
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l Procedures,and Instruc-T3-2 6
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tion Manuals List
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.IL IPAGE TC-6~
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~l ARKANSAS POWER & LIGHT COMPANY POLICY STATEMENT l
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- Q QUALITY ASSURANCE PROGRAM FOR OPERATION v
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
lforOperationmeettherequirementsoftheCodeofFederalRegulations, l
l 10 CFR 50, Appendix B, with respect--to operation, maintenance, refueling, l
l repair and modifications, and inservice inspection of AP&L Nuclear l
l Plants.
The' program shall also meet the requirements of the ASME Boiler l
landPressureVesselCodeswithrespecttoitemsconstructed,repairedor l
l replaced to Code requirements.
l l
1 I
I l Under the Program the Energy Supply Sr. Vice President, is the final l
l management authority responsible for assuring that this policy statement l
and the Quality Assurance Program are implemented within AP&L.
The l
Nuclear Operations Vice President and each Energy Supply Director is l
l responsible for the procedural implementation of the program within his l
lassignedarea.
The plant's General Manager is responsible for the daily implementation of the Program's procedural requirements at the plant.
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
ltheProgram.
I l-Quality Assurance personnel reporting to the Quality Assurance Manager l
are responsible for auditing the Program as necessary and monitoring
.l activities required by the Program to assure compliance with its--
l requirements.
Disputes involving quality, arising from. difference of l
opinions between QA personnel and other personnel, which cannot be l
settled interdepartmentally, shall be presented to the Energy Supply l
l-Senior Vice President for resolution.
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l SECTION:. STATEMENT OF. POLICY lPAGE A-1 l'
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'l The Quality Assurance Manager is to provide:for annual review of the 1
- adequacy and overall_ effectiveness of the Program.
Any defects in the
- :l ' ' implementation of.either this policy or the Program that are revealed I
~
during the. review are to be_. reported to appropriate levels of management
- =
-l together with appropriate recommendations.
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I. Implementation of this policy is necessary in order to achieve. the l
l_reliabilityandsafetyrequiredatourNuclearPlants.
Each person l
l -involved in activities concerning our Nuclear Plants is to be responsible l
for assuring quality in his own work, and for compliance with the l
requirements of the Program.
The Quality Assurance Program policies,.
l l manuals,andproceduresaremandatoryrequirementswhichmustbe l
implemented and enforced by all responsible organizations and l
I individuals.
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l l
J. Griffin l
l Energy Supply Sr. Vice President-o i
I t
gate:
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TOPICAL' REPORT.
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l' l-SECTION: ? STATEMENT.0F POLICYL
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l INTRODUCTION I
I (7
I v
I l 'This TOPICAL report (manual) describes the AP&L quality program applied I
l by AP&L to its operating nuclear plants.
This manual is intended to l
serve as a standard reference for final safety analysis reports to I
f'fulfilltherequirementsoftheStandardFormatandContentsofSafety l
l Analysis Reports for Nuclear Power Plants, Section 17, published by the l
lNuclearRegulatoryCommissson.
l l
l ll The objective of this program is to control those phases, as applicable, l
g I
for the design, procurement, manufacture and fabrication, installation, l
I
.g operation, testing, refueling, repair, maintenance or modification to l
I existing safety related (Q-List) structures, systems and components that I
prevent or mitigate the consequences of a postulated accident which may I
cause undue risk to the health and safety of the public.
The program is l
I an outgrowth of the principle that quality assurance emanates from each I
individual contributor and that management is responsible for creating an l
lawarenessofquality.
l q
l I
v i
The AP&L quality program is designed to comply with the requirements of i
g i
10CFR50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants l
landFuelReprocessingPlants,andtocomplywiththequalityassurance l
l requirements of the ASME Boiler and Pressure Vessel Code,Section XI for I
l repair, replacement,andinserviceinspectionofitemscoveredbythe l
Code and Licensing commitments.
I I
I I
I I
The AP&L quality program is also designed to comply with the NRC I
l positions contained in the following regulatory guides, subject to I
specific exceptions noted in. Table 1-of this manual:
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T TOPICAL REPORT lREV..,6 l
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I.SECTION:
INTRODUCTION IPAGE B-1
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1.'8, rev. 1-R Perscnnel Selection and Training (5/77) l
. /'~~\\
I 1.28, rev. 1 QA Program Requirements-Design and I
v' 1-I l'
Construction (3/78) l 1.30 QA Requirements for Installation, l
.l' Inspection and Testing of Instrumentation I
and Electrical Equipment (8/72) l l
1.33, rev. 2 QA Program Requirements-Operations (2/78) l l.
1.37.
QA Requirements For Cleaning of Fluid l
Systems and Associated Components of Water l
Cooled Nuclear Power Plants (3/73) l l
1.38, rev. 2 QA Requirements for Packaging, Shipping, l
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. Power Plants (9/77) l
'l 1.58, rev. 1 Qualification of Nuclear Power Plant l
l Inspection, Examination and Testing l
l Personnel (9/80) l l
1.64,.rev. 2 QA Requirements For the Design of Nuclear l
l Power Plants (6/76) l.
l 1.74
.QA Terms and Definit' ions (2/74) l l
1.88, rev. 2 Collection, Storage, and Maintenance of l
l-Nuclear Power Plant Quality Assurance l
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 Construction. Phase of Nuclear Power Plants l
l' (4/76)
I l-I i
1.116,'rev. 0-R QA Requirements For Installation,
-l l
Inspection and Testing of Mechanical l
. Equipment and Services (5/77)
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1 l SECTION:
INTRODUCTION lPAGE 'B-2 l
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1
-l 1.123, rev. 1 QA Requirements For Control of Procurement l
l of Items and Services For Nuclear Power l
Plants-(7/77) l l
1.144, rev. 1 Auditing of Quality Assurance Programs for 1
the Nuclear Power Plant (9/80).
l l
1.146 Qualification of Quality Assurance Program l
l Audit Personnel For Nuclear Power Plants l
l l
(8/80) l-l lBaseduponcompliancetotheseregulatoryguides,theAP&Lquality l
l program also complies with the following American National Standard l
Institute (ANSI) standards subject to exceptions noted in Table 1 of this I
manual:
1 I
I
.I I
I N45.2-1977
. Quality Assurance Program Requirements for Nuclear l
l Facilities l
l lN45.2.1-1973 Cleaning of Fluid Systems-and Associated l
Components During the Construction Phase of I
Nuclear Power Plants l
l lN45.2.2-1972 Packaging, Shipping, Receiving, Storage and-l l
Handling of' Items for Nuclear Power Plants (During l
l the Construction Phase) l l
1 lN45.2.3-1973 Housekeeping During the Construction Phase of l
Nuclear Power Plants l
l l
l 1
I N45.2.4-1972 Supplementary Quality Assurance Requirements for l
l Installation, Inspection and Testing of l
l Instrumentation and Electric Equipment During the i
I l
Construction'of Nuclear Power Generating Stations I
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A l-TOPICAL REPORT lREV.
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l 1 SECTION:
INTRODUCTION IPAGE B-3
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.1 1(N45.~2.5-1974 I
I-i Supplementary Quality Assurance Requirements for' l
l Installation and Testing of Structural Concrete l
1
~l and Structural Steel'During the Construction Phase l
l L
'of Nuclear Power Plants
~[N45.2.6-1978 Oualifications of Inspection, Examination and l
'~
.I _
Testing Personnel _for Nuclear Power Plants l
1-1 I
I
- l N45.2.8-1975
. Supplementary Quality Assurance Requirements for
'l l-Instal'1ation,' Inspection and Testing of Mechanical l
i Equipment;and System for the Construction Phase of l
-l
~ Nuclear Power Plants-f
-l-l lN45.2.9-1974' Requirements for Collection',- Storage and l
Maintenance of Quality Assurance Records-for..
l
-l-Nuclear Power Plants' 1.
I=
N45.2.10-1973 Quality _ Assurance: Terms and Definitions-l o
jlN45.2.11-1974.
i Quality Assurance Requirements;for the Design'of 1
Nuclear Power Plants
'l l
-l
.l..
l l
N45.2.12-1977 Requirements for Auditing _o_f Quality Assurance
.l-l1 Programs for Nuclear Power. Plants
- -l; I
l-l: N45.2.13-1976 Quality. Assurance Requiremen'ts >for. ' Control 'of :
f l
Procurement of Items and. Services lfor Nuclear
- l Power Plants-1 lN45.2.23-1978 Qualification of Quality Assurance Program Auditu l7 31
-Personnel. for Nucle'ar Facilitie's
- l I
l-1 1
.N 8. -1971 Selections and Traini_ng of. Nuclear Power Plant:
Personnel' I:
I
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LA:. . TOPICAL ~REPORTJ ?lREV. -6... 11 (l_ Pc , t. i l.. ...-INTRODUCTION -lPAGEE B-4 : -ll l: SECTION: ,lDATE ;6/10/83. l l- 'l;
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p ,g m l l ,g_ l -l TERMS AND DEFINITIONS -l b., - l l -l The terms used in this manual follow the definitions provided in l LANSI N45.2.10-1973, supplemented by additional terms and definitions -l-applicable to this report. l ~l l l l l Approval.- An act of endorsing or adding' positive authorization, or both. l l l .I I l -Appurtenance - A part that is attached to a component which has been l completed. I I As-Built Data - Documented data that describes the condition actually l l achieved in a product. l l l 1 l-l-Assembly - A combination of_ subassemblies or components, or both, fitted-l ~ l . together to form a unit. l 1 l Audit'-Anactivitytodeterminethroughinvestigation,theadequacyof. l and adherence to, established procedures, instructions, specifications, l l codes,andstandardsorotherapplicablecontractualandlicensing -l requirements, and the effectiveness of implementation. l. I I 1 'l l Bid Evaluation - A formal evaluation of all proposals received in l l response _:toaninquirytodeterminethevendorto;whomthepurchaseorder l willibe awarded. l. 1-1 I 1. .l Certificate of Conformance - A written statement, signed by a ~ qualified l _ party, Ecertifying,that items or services comply _ with specific l requirements.. -l 1 I .I ~ i
- ljCertificateofCompliance-Awritten' statement,signedby.aqualified
-- l. . ; party, attesting that the' items or services-are in accordance with-l specified requirements ~and accompanied by additional information!to l-I' substantiate the statement. .I
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I .-Q l .1-l l- -l= .A. .) . TOPICAL. REPORT -lREV. .-6' I il. . P. ' ..l" ~
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'l - l- -&J 'fl SECTION:. TERMS AND DEFINITIONS. .lPAGE -C " l
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o J-l' l-I I l Certified Test Report - A written and signed document, approved by a l s f7 -qualified party, that contains sufficient data and information to verify l I the' actual' properties of items and the actual results of all required l l tests. l l l Certification - The action of determining, verifying and attesting, in .I writing, to the qualifications of personnel or material. I i l i I l Characteristic - Any property or attribute of an item, process, or I service that is distinct, describable, and measurable, as conforming or -l 1 ~ nonconforming to specified quality requirements. Quality characteristics I laregenerallyidentified'inspecificationsanddrawingswhichdescribe l the item, process, or service. l I I I I l Checks - The tests, measurements, verifcations or. controls placed on an l l activity by means of investigations, comparisons, or examinations, to l I determine satisfactory conditions, accuracy, safety or performance. 1 I I I I l Cleanness - A state of being clean in accordance with predetermined I l standards,andusuallyimpliesfreedomfromdirt, scale,heavyrust,01,1 I or other contaminv ing-impurities. l l- ~ l 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 l States, or Canadian Province, or regularly employed by an Authorized l l Inspection Agency and having authorized jurisdiction at the site of j manufacture for installation, repair, modification, and -in-service l linspectionofASMEBoilerand'PresssureVesselitemsdesignated l l safety related. l l 1 1 1 l l I l I. I I I I l-l l I l O I l l-l 1 -'A J. TOPICAL REPORT IREV. 6 l l P l lDATE 6/10/83 l 'l ' 1 SECTION: TERMSANDDEfINITIONS IPAGE C-2 l l
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I I l I l Commercial Grade - Those items contained in Q systems and equipment that l (~) are: (1) not subject to design or specification requirements unique to l. nuclear facilities or activities; (2) used in application other than l l nuclear facilities or activities; (3) to be ordered on the basis of l l specifications set forth in manufacturers published product description; l and (4) not associated with a loss of safety function. l I I Component - A piece of equipment such as a vessel, piping, pump, valve or l core support structure, which will be combined with other components to l form an assembly. l l l Computer Code - The application software utilized within a digital l computer to accomplish a specific function or task. Computer codes l requiring Quality Assurance are those whose satisfactory performance is l required to prevent accidents which may cause undue risk to the health l and safety of the public or relied upon to mitigate the consequences of l such accidents if they were to occur. This involves those computer codes l I utilized in design and analyses of Q-list components, and those utilized I I I p l as an active portion of Q-list components. l V l l l l l Contaminants - Foreign materials such as mill scale, dirt, oil, chemicals l I I and any matter than renders a fluid, solid or surface impure and unclean I i l according to preset standards of acceptable cleanness. 1 l I I i l Contractor - Any organization under contract for furnishing items or l l services. I It includes the terms Vendor, Supplier, Subcontractor, I i l Fabricator and sub-tier levels of these where appropriate. l 1 I 1 l l Defective Material - A material or component which has one or more l l characteristics that do not comply with specified requirements. I I l l l l l l l l l l l l l l g l A l TOPICAL REPORT IREV. 6 l l P l lDATE 6/10/83 l l l SECTION: TERMS AND DEFINITIONS IPAGE C-3 l l L l l l l l l l
l l I I I l Deviation - A nonconformance or departure of a characteristic from l [~') ._specified requirements. v l Documentation - Any written or pictorial information describing, l l defining, specifying, reporting or certifying activities, requirements, l l procedures,orresults. l 1 l l Examination-Anelementofinspectionconsistingofinvestigationof l l materials, components, supplies or services to determine conformance to l those specified requirements which can be determined by such l l investigation. Examination is usually nondestructive and includes simple l physical manipulation, gaging, and measurement. I I Handling - An act of physically moving items by hand or mechanical means, l but not including transport modes. I i 1 1 I [ Inquiry - A document that contains the necessary information for a vendor l to make a proposal. An inquiry may include specifications pertaining to O'v' l the equipment, materials, or services proposed to be procured. l I l I I l Inspector (Owner's) - A qualified inspector employed by the Owner whose l I duties include the verification of quality related activities or I I l installations or both. l I I l l l Inspection - A phase of quality control which by means of examination, l l observation or measurement determines the conformance of materials, l l supplies, components, parts, appurtenances, systems, processes or l I structures to predetermined quality requirements. I I I I I I Item - Any level of unit assembly, including structure, system, I I I l subsystem, subassembly, component, part or material. l l l I I I I I I I I I I g I l I I I l ~' l A l TOPICAL REPORT lREV. 6 l l P l IDATE 6/10/83 l m l l SECTION: ' TERMS'AND DEFINITIONS lPAGE C-4 I i I L l l l I I I -l.
4 l l 1 ~ Job Order (J.0.) - The Job Order is the document used for identifying and l l l .N I t f I administratively controlling the work effort on station equipment and I I l systems. It identifies applicable procedures and drawings; documents l l reviews,approvalsandresultsofinspectionsandtests;andprovidesa l. mechanism for planning, scheduling and authorizing work. l .l l o 1 l l Manufacturer - One who constructs any class of temponent, part, or l lappurtenancetomeetprescribeddesign' requirements. l l l l' Material - A substance or combination of substances forming components, l l parts, pieces and equipment items. (Intended to include such as l l machinery, castings, liquids,formedsteelshapes, aggregates,and I cement.) l l 1 1 I 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 1 4 l safety restrictions. i o i Nonconformance - A deficiency in characteristic, document, or procedure l which renders the quality of an item unacceptable or indeterminate. l Examples of nonconformance include: physical defects, test failures, l incorrect or inadequate documentation, or deviation from prescribed l processing, inspection or test procedures. l l-i Objective Evidence - Any statement of fact, information, or record, l l either quantitative or qualitative, pertaining to the quality of an item l or service based on observations, measurements, or tests which can be l Verified. l 1 l i I l Operation - The total of administrative, maintenance and monitor l activities necessary to sustain the power generating capabilities of the l
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l l l l .A- -l TOPICAL REPORT. -lREV. 6. l l .P l l0 ATE 6/10/83 l ~ l 1 SECTION: TERMS AND DEFINITIONS lPAGE C-5 l l L l l l l-1 I. __ u _ _ _. I ' i m
I I 'I I l Owner - The person, group, company or corporation who will have or has l f'; title to the facility or installation under construction. m I Package - A wrapping or container including it; anter" cf materials or I i [ equipment. 1 I I I I l Packaged Unit - An assembly of items and parts which can be disassembled l without destroying the integrity of the individual parts. I I Part - An item which has work performed on it and which is attached to l and becomes part of a component before completion of the component. l l l l l l Plant - The equiment, piping, structures, buildings and property that l comprise an installation or facility. l l l I Procedure - A document that specifies or describes how an activity is to l l be performed. It may include methods to be employed, equipment or l I materials to be used and sequence of operations. O I l \\ / l v Procurement Documents - Contractually binding documents that identify and I I i l define the requirements that items or services must meet in order to be l I considered acceptable by the purchaser. I I I I I I Project - A planned series of activities including all actions necessary l l to prcvide, utilize, and maintain a facility or portion thereof. l l l l l l Proposal - A bid, usually written by a vendor in response to an inquiry, l I which provides the issuing party with the vendor's proposed compliance to I ll the inquiry and the cost. l l l l 1 l l Purchase Order (or Contract) - A document authorizing a vendor to provide l I equipment, material or services in accordance with stated terms and l I l conditions. I l l l l l I m l I l I I I I I 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 l l 1 _ _l
I I I I l Purchaser - The organization or organizations responsible for issuance l ~') and administration of a contract, subcontract, or purchase order. Q-List - A list which specifically identifies those structures, systems. l and components whose failure could cause an uncontrolled release of l radioactivity, or those essential for the safe shutdown and immediate and l long-term operation following a Loss of Coolant Accident. l I I I I l Qualification (Personnel) - The characteristics or abilities gained l through training or experience or both that enable an individual to l l perform a required function. l l l l l l Qualified Party - A person or organization competent and recognized as l knowlegeable to perform certain functions. I l lQualifiedProcedure-Aprocedurewhichincorporatesallapplicablecodes l and standards, manufacturer's parameters, and engineering specifications l and has been proven adequate for its intended purpose. O I l L/ l Qualified Vendor List - A listing of vendors having quality assurance I l l l programs consistent with the requirements of applicable portions of l l 10CFR50, Appendix 8. I l i l l I l Quality Assurance - All those planned and systematic actions necessary to I l l provide adequate confidence that an item or a facility will perform l I satisfactorily in service. I l l I I puality Control - Those quality assurance actions which provide a means l to control and measure the characteristics of an item, process or l I facility to established requirements. I I I l l I I l l 1 l l l l l l l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l 1 SECTION: TERMS AND DEFINITIONS lPAGE C-7 l l L l l l l 1 I I
I I I I l Receiving - Taking delivery of an item at a designated location. I h l I Repair - The process of restoring a nonconforming characteristic to a j condition such that the capability of an item to function reliably and l l safely is unimpaired, even though that item still may not conform to the l original requirement. l l l Report - Something (document) that gives information for record purposes. I I l Review-Anelementofinspectiontodetermineconformancetospecified l requirements, which can be determined by examination of documents and I activities. l l Rework - The process by which a nonconforming item is made to conform to l a prior specified requirement by completion, remachining, reassembling or i I other corrective means. I i Safety-Related - The term " safety related", as used in this program, ^ l refers to those materials, parts, components, systems, structures and I consumeable items classified as "Q" and so identified on the Q-list l l applicable to each nuclear plant. [ l l I I l Source Surveillance - A review, observation, or inspection for the I purpose of verifying that an action has been accomplished as specified at l the location of material procurement or manufacture. l l l l l l Specification - A concise statement of a set of requirements to be l I satisfied by a product, material or process indicating, whenever I I I l appropriate, the procedure by means of which it may be determined whether l I the requirements given are satisfied. I I I I I 1 I I I i i I I I I l { l l 1 1 I I l A I TOPICAL REPORT lREV. 6 l I P l lDATE 6/10/83 l l I SECTION: TERMS AND DEFINITIONS IPAGE C-8 l 1 L I l l l I I I
r i l I l l Standard - The result of a particular standardization effort approved by l ~} larecognizedauthority. l g l Storage-Theactofholdingitemsattheconstructionsiteorinanarea l other than its permanent location in the plant. l l 1 1 1 l Subsystem - A group of assemblies or components or both combined to l lperformedasinglefunction. l l 1 Surveillance - The continuing analysis and evaluation of records, methods I and procedures, including the act of verification, to assure conformance l with technical requirements. l l l l System-Agroupofsubsystemsunitedbysomeinteractionor l l interdependence, performing many duties but functioning as a single unit. l I I I I l System Performance Test - A test performed on a completed system l lincludingelectric, instrumentation, controls,fluidandmechanical l n l subsystems under normal or simulated normal process conditions such as l ~' temperature, flow, level, and pressure. I I Testing - The determination or verification of the capability of an item l to meet specified requirements by subjecting the item to a set of l l physical, chemical,environmentaloroperatingconditions. l l l Titles-Titlesofindividuals,suchasQualityAssuranceManager,when l used in the TOPICAL report c2 signs the responsibility of performing the l requirement to the noted individual or his appointed designee. I I Transit - The state of being conveyed or transported from one place to l l another. l I I I I I I I I l I l I l i I I I l A l TOPICAL REPORT IREV. 6 l l P I lDATE 6/10/83 l l I SECTION: TERMS AND DEFINITIONS lPAGE C-9 l l L l 1 l l l l I f
I I l l i Transit Carrier (0 pen) - Trucks, trailers, railroad cars, barges, I (~} laircraftorshipswichdonotafforditemsprotectionfromthe l ~' l environment. l l l 1 I l Transit Carrier (Closed) - Trucks, trailers, railroad cars, barges, I aircraft or ships which provide protection of items from the environment l l by nature of their closed design. I I I I l i Use-As-Is - A disposition which may be imposed for a nonconformance when l l it c ' be established that the discrepancy will result in no adverse I conditions and that the item under consideration will continue to meet l lallengineeringfunctionalrequirementsincludingperformance, l I maintainability, fit and safety. 1 I I I I l Vendor - Any organization under contract for furnishing items or l l services. It includes the terms Contractor, Subcontractor, Supplier, l l Fabricator and sub-tier levels of these where appropriate. I i 1 1 I -p i Verification - An act of confirming, substantiating and assuring that an I kJ l activity or condition has been implemented in conformance with the l l specified requirements. I I I I I I Work Instructions - Written instructions used to transmit detailed I information on the specific measures necessary to comply with the I requirements of quality assurance procedures or any complex or difficult l l quality-relatedtask. l l l lWorkpackage-Aworkpackageisacollectionofapplicabledocuments, l l such as procedures, cleanliness control forms, inspection and test forms, I lholdcardforms,IgnitionSourcePermits, drawings,technicalmanuals, l l etc., needed to perform the job. l I I I I I I I I l l I l I I (? I I l l 'n l A l TOPICAL REPORT IREV. 6 l l P 1 10 ATE 6/10/83 I I 1 SECTION: TERMS AND DEFINITIONS IPAGE C-10 l I L i I I I I l l J
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- 1. 0 ORGANIZATION l
l ~ 0v l1.1 l-l SCOPE I I I l 1 j.This section describes the AP&L. organizational structure and l l responsibilities for establishing and executing the Quality Assurance l I I l Program for AP&L operational nuclear plants in compliance with 10CFR50, l l l Appendix B and applicable Regulatory Guides and ANSI Standards identified l g l in the Introduction. It also includes a description of the interfaces l i lwithotherorganizationswhomaybedelegate'dtheworkofestablishing l -l and executing portions of the Quality Assurance Program. The AP&L l I Corporate Organization relevant to the operation of its nuclear plants is I I l l shown in Figure 1. l l I I l l 1.2 GENERAL RESPONSIBILITIES I l l 1 l l 1.2.1 l l l l l l l The ultimate responsibilities for operational nuclear plants within AP&L, l C l including Quality Assurance, lies with the Energy Supply Senior Vice I l I l President. He provides management assessment of the Quality Assurance l 1 -Program through review of QA Audit Reports and reports of NRC activities. I I I I 1 1.2.2 I i I I I l l I The Administrative Services Vice President is responsible for the l I l purchasing functions affecting plant operation as described in Subsection l l l
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1 l l l 1 -l l l l l l I 1 I l I I 1. I l I l l l l l A I TOPICAL REPORT lREV.* 6 'l P l lDATE 6/10/83 l l -l SECTION: 1.0 ORGANIZATION lPAGE 1-1 I .I L-1 I l .I-1 I I
I I I I I l
- 1. 3 CORPORATE SERVICES l
l I m ( ) i I w/ l 1.3.1 I l l l l l Corporate Services is responsible for the procurement of materials, parts l and components requested by Little Rock General Office (LRGO) personnel l l and for supporting the procurement activities at the plant. Procurement l 'I organization is noted in Figure 2. l l l 1 1.3.2 I l l l l The Nuclear Buyer reports to the Supervisor of Purchasing who reports to l l the Manager, Purchasing and Stores and is responsible for the following i duties and activities: l l l l 1. Prepares purchase orders based upon receipt of reviewed and l approved Purchase Requisitions. l I I I I n l 2. Performs the commercial interface functions between AP&L and ) l (V contractors or vendors. l I I I 3. I Assures that quality documentation prepared by Energy Supply I I l personnel are included in purchasing documents. l l 1 1 l 1.4 ENERGY SUPPLY I l l l l l l Energy Supply, headed by the Energy Supply Senior Vice President is l 1 responsible for all activities related to the operation of AP&L Nuclear I I I l Plants. These activities include as a minimum: design, modification, l l maintenance, inservice inspection and test, operation and those l I I g additional activities discussed in Sections 2 through 18 of this manual. l I Within Energy Supply, the Nuclear Operations and Energy Supply Service Il organizations are involved in activities requiring execution of the I l l Quality Assurance Program (See Figure 3). I I I I I O l i I l 1/ l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l l SECTION: 1.0 ORGANIZATION lPAGE 1-2 l l L I l l 1 I I l t
I I I I l 1.4.1 Eneroy Supply Services l l m l I l s/ l Energy Supply Services is under the direction of the Energy Supply l I Services Director, who reports to the Energy Supply Senior Vice l l President. The Energy Supply Services Director is responsible for l l providing support to AP&L nuclear plants in the areas of quality l assurance, administrative services, engineering services and technical l services. His duties include providing technical direction, l administrative guidance and supervision to the: l 1 I I I Energy Supply Administrative Services General Manager l l a. l b. Engineering Services General Manager l Technical Services General Manager l c. l d. Quality Assurance Manager l l l l 1.4.1.1 Quality Assurance Manager I l 1 1 I I The AP&L Quality Assurance Organization (QA0) as shown in Figure 4 is I I n l under the direction of the Quality Assurance Manager,.'o reports to the l U l Energy Supply Services Director. The QA0 performs review, surveillance, I l l l inspection and audit functions during the operational phase of AP&L's l l nuclear plants an, is independent of Nuclear Operations, and from cost I r l l l and scheduling considerations when opposed to safety and quality l I considerations. l The QA Manager shall have direct access to management I l l levels, which assures his ability to: identify quality problems; l I initiate, recommend or provide solutions through designated channels; and I I l verify implementation of solutions. I l l l 1 l The qualification requirements of the QA Manager are established within l l I his AP&L job description which includes the following prerequisites: I l I l l l 1. Possess a degree from an accredited school in engineering or a l I~ i l related scientific discipline or equivalent; I I I I f /7 l I l l l A -l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 I l ' i SECTION: 1.0 ORGANIZATION IPAGE l-3 l l L I I I I I I I L
I I I l l 2. Possess a minimum of five years experience in the quality l l assurance or quality control disciplines with atleast two years ^' g l in the nuclear field; and i l l i I l 3. Exhibit the ability to plan, schedule and direct the activities l of others assigned to or functioning within the QA0. l l l l The duties and responsibilities of the Quality Assurance Manager include l l the following: l l 1 I I l 1. Develop Quality Assurance Program requirements for l l modification, operation, and maintenance activites related to l l the safety related (Q-listed) systems structures, and l components in AP&L nuclear plants. l l l 2. Audit of the quality assurance activities as described in l l Section 18 of this manual. l l l l l p l 3. Review, approval and verification of the quality assurance l CJ l requirements placed upon contractors or vendors that provide l equipment, material, or services for AP&L nuclear plants. l l l l l l 4. Authority to stop work where conditions exist that prohibit l I l effective quality control inspections, or if faulty materials, I l l incorrect workmanship or procedures are detected. l l l l l l l 5. Review, approval, distribution and control of QA Manuals and QA l l Procedures and revisions thereto. I l l I l I 6. I Review and approval of QA programs for outside organizations I l participating in the AP&L QA program. l I l 1. l l I l l I l I I I I l /D l l I I \\ l A J TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l ' l SECTION: 1.0 ORGANIZATION lPAGE 1-4 I I L I I I I I _L.....
l -l l l l l 7. Serve as chairman of the Safety Review Committee. I n l l i l (d-I l 8. Provide and maintain a qualified and suitable trained staff to I carry out required staff functions. l l I 9. Formulate programs for maintaining the professional competence l l of personnel within the QA0 and provide assistance in QA l { l training and indoctrination programs for division management, l engineering and plant personnel whose activities affect l l quality. l l l 10. Provide technical direction and guidance to the Quality l l Engineering Supervisors. l l l I I I J 1.4.1.1.1 Quality Engineering Supervisor l I l l l l l l The Quality Engineering Supervisor reports to the Quality Assurance l Mariager, supervises QA Engineers and Auditors / Inspectors as assigned, l and assists the Quality Assurance Manager in the coordination of l V I activities within the QA Section. The Quality Engineering Supervisor may I l I l also perform duties normally assigned to Quality Assurance Engineers. l l l I l 1.4.1.1.2 Quality Assurance Engineers l l l l l 1 l The Quality Assurance Engineers (QAE's) report to a Quality Engineering l l Supervisor, as assigned. The Quality Assurance Engineers are to be l I I l familiar with the Quality Assurance Program and associated procedures, l i 10CFR50 Appendix B, regulatory guides, codes, and standards that address I i i l quality assurance. They also possess the'necessary functional I t l l independence and authority to: identify quality problems, initiate, I I I l l recommend or provide solutions through. designated channels, and verify l i l implementation of solutions. Specifically: I l. I I I I I i l I f I
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I l l I l 1. The QAE's are to have the authority to inspect, audit or review l p l practices, records, files, instructions, directions or l l documents concerned with all areas affecting quality. I I I I l l 2. The QAE's are to schedule and coordinate audits or surveillance l l efforts in the areas assigned, document findings, and report l l results to the Quality Assurance Manager and the Manager of the l l audited area. l l l 1.4.1.1.3 Quality Assurance Auditors / Inspectors l l l lTheQualityAssuranceAuditors/InspectorsreporttotheQuality l l Engineering Supervisor and assist him in the implementation of the l lprogrambyperformingauditsandinspectionsasrequiredtoassureproper l l application of the Quality Assurance Program. l I I I I l 1.4.1.2 Technical Services General Manager l l l l l p l The Technical Services General Manager reports to the Energy Supply l \\ lServicesDirectorandisresponsibleforprovidingsupporttoAP&L l l nuclear plants in the areas of plant performance, maintenance and l l availability, chemistry, environmental monitoring, metallurgy and l ^ l nondestructive examination. His duties include the following: l l l l l l 1. Provides technical direction and administrative guidance to: l l l l l Plant Performance Evaluation Manager l a. l l b. Plant Maintenance Manager l Availability Engineering Manager l c. l l d. Technical Analysis Manager l l l l' 2. Assure conformance to the Quality Assurance Program by l j instituting the necessary quality related procedures and l l instructions within the Technical Services Department. I I l I l (D l l l l K l l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l l SECTION: 1.0 ORGANIZATION lPAGE -6 l l L I l l l l l l
t._ l l' l I l 3. Provide for coordination of environmental surveillance programs l L O- I l l I t V l 4. Direct development of programs aimed at maximizing efficiency l l and availability. l l l S. Provide for review and analysis of outage data and make l l recommendations for correcting deficiencies which affect l l availability or performance. l l l .l 6. Direct the plant maintenance support activities that are l assigned to the LRGO. l l l l l l 7. Serve as a member of the Safety Review Committee. l l l l i l l l l 8. Provide and maintain a qualified and suitably trained staff to l I carry out required departmental functions. l l l
- 1. 4.1. 3 Engineering Services General Manager l
l The Engineering Services General Manager reports to the Energy Supply I I I l Services -Director and is responsible for LRGO design and engineering l I activities related to nuclear plant ope' rations. His duties include the I 1 l following: I l l l l l l 1. Provide technical direction and administrative guidance to: l l 'l 1 l a. Mechanical Engineering Manager 1 l l b. Electrical Engineering Manager I I l c. Civil Engineering Manager I l I d. l Instrumentation and Controls Engineering Manager I I i l 1 ~ Assure conformance to the Quality Assurance Program by l 2. l fnstituting the necessary quality related procedures and l I instructions within Enginearing Services. I I I l 'f) l l l l v i A l TOPICAL REPORT lREV. 6 l g l P l IDATE 6/10/83 l l .l SECTION: 1.0 ORGANIZATION lPAGE 1-7 l l L I I I I I I i
I I I I l 3. Provide for review and approval of LRG0 design and engineering I (7 I ' 'j l activities performed by contractors, vendors, and AP&L I t I l personnel. I I l l I l 4. Provide for review and approval of procurement documents for l l equipment, material and services for LRG0 engineering projects, l l as appropriate. 1 I I I l l 5. Provide and maintain a qualified and suitable trained staff to l l carry out required departmental functions. l l l l1.4.1.4 Energy Supply Administrative Services General Manager l l l lTheEnergySupplyAdministrativeServicesGeneralManagerreportstothe l Energy Supply Services Directnr and is responsible for the development of l l administrative programs, systems and services supportive to management. l l His duties include the following: l l 1 I i 1. Provide ~ technical direction and guidance to: l w-Energy supply Training Manager l a. l l b. General Services Manager l Planning, Scheduling & Cost Control Manager l l c. I d. Contract Administration Manager I I I l l l 2. Maintain overall department fiscal direction and control, and l l provides supportive accounting functions. l l l 1 l l 3. Provide contract administration and administration of l procedures for Energy Supply Little Rock General Office (LRGO) l l activities. 1 l I I l l' 4. Administration of the training and development effort for l l Energy Supply LRGO personnel, l I l l O I I I I 'J l A j TOPICAL REPORT lREV. 6 l ~ l P l 10 ATE 6/10/83 l l l SECTION: 1.0 ORGANIZATION lPAGE 1-8 l-l L l l l l 1 _. _1
.p l-1 I I l 5. Ancillary support services to Energy Supply operation sections. l l (o I l. I V l 6. Provide and maintain a qualified and suitable staff to carry l' ~ l out required departmental functions. l .l 7. Serve as a member of the Safety Review Committee. l l 1 1 I l 8. . Assure conformance to the Quality Assurance Program by l l instituting the necessary quality-related procedures and l l instructions within Administrative Services. l I I l l l 1.4.2 Nuclear Operations l l l l l 1 l Nuclear Operations is under the direction of the Nuclear Operations Vice l j l President who reports to the Energy Supply Senior Vice President and is l l responsible for the formulation, licensing, implementation and discharge l l of operating policies and procedures relative to nuclear plant operations l l l and for nuclear fuel management. His duties include the following: l I l l l l l 1. Provide' technical direction and administrative guidance to the: l l l I 1 l a. Plant's General Manager l b. Nuclear Services Manager l l c. 'ANO Project Manager l l d. Licensing Manager I I I j l 2. Assure conformance to the Quality Assurance Program by I l instituting the necessary procedures and instructions within l I the Nuclear Operations Department. l l l 1 l I l l 3. Provide for review and approval of design and engineering 'l I l l performed for the operating nuclear plants. I l l -l~ I l l 4. Provide for review and approval of procurement documents for l l equipment, material and services. I l I lI D) I I I I (. l A j TOPICAL REPORT lREV. 6 l l P .l -l0 ATE 6/10/83 l-l 'l SECTION:. 1.0 ORGANIZATION lPAGE 1-9 ~l L. I I -1. I I
I l l .l 1 -l '5. Provide for liason between AP&L and applicable regulatory l (3 I' j l agencies. v l 6. Provide and maintain a qualified and suitable staff to carry l ll out required departmental functions. l I I I l 'l' 7. Provide for procurement and design review of nuclear fuel. I I I l l l-8. Overall responsibility for the fire protection program l l implemented at the nuclear plants. l l 1 l1.4.2.1 Nuclear Services Manager l l l lTheNuclearServicesManagerreportstotheNuclearOperationsVice l l President-and is responsible for providing the necessary support services l lrelatedtotheeffectiveoperationandmaintenanceoftheAP&Lnuclear l l plants. The duties include the following: l l 1 l l l 1. Review, approval and coordination of design changes through the l Little Rock General Office. l g l l l 2. Review, approval and coordination of purchase requisitions and l l contracts generated at the Little Rock General Office. l 73 l l e l l l 3. Interface with other departments to assure effective l g l implementation of Regulatory and Company requirements. l lh 'l-l l. 4. Communication interface dealing with all activities at the l l. nuclear-plants. .I l I g LI l I 1 I. 1 I.,. .l, i 1 l l .l 1.- t (~') ~l I l I V l A cj . TOPICAL REPORT IREV.~-6~ l-i P l1
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l' ' I SECTION: 1.0 ORGANIZATION lPAGE 1-10 l'- e?fhb: I L I- -l l g i i-t t ..i.- -- -^ ^ ~ ^ ^
l l 1: I r l 5. Provide technical direction and administrative guidance to the l I C) l Nuclear Fuel Supervisor, who is responsible for the I sV l l 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 l l analysis. l l-l l 6. Serve as a member of the Safety Review Committee. l l 1 l'1.4.2.2 Licensing Manager l l 1 i lTheLicensingManagerreportstotheNuclearOperationsVicePresident l l and is responsible for the coordination of all licensing documents, l lrequirementsandrevisionstheretowhicharerequiredtobereviewed l I and/or approved by the NRC and for interfacing with the NRC. The l l Licensing manager is also responsible for the review and. approval of l l-Q-List changes and for the tracking of possible nuclear safety concerns l ltoassuretimelyclosecut. l 3 1.4.2.3 ProjectManager 1 l l -The Project Manager reports to the Nuclear Operations Vice President-and I I I l is responsible for providing services at the nuclear plant for field l-I construction activities and for modifications to the control room. I I I l simulators.used for operator's training. His duties include providing ' l I technical direction and administrative guidance to the' Field Construction I I I l Manager'and the Simulator Project Coordinator. I _l 1 I 4 I l 1.4.2.3.1 Field Construction Manager i l ~ l i I . l JThe Field Construction Manager is responsible for' directing the-l I activities of his staff relating to work associated with plant .: I I l l construction and modifications. His duties includei -l l I l-I f I -l- . I l . l. .A .l TOPICAL REPORTi 'lREV.". 6 l-l '.P. l. lDATE 6/10/83 - l l' .l SECTION:. 1.0 ORGANIZATION
- l PAGE 1-11'
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1 I l-I -l '1) Interface with other departments to assure effective l , ('~} l implementation o'f job assignments l V g g l 2) Provide cost _and schedule contiols for departmental activities l l I l -3) Provide' tech'nical and administrative guidance to the l l Construction Quality Control (CQC) Supervisor. The CQC l l Supervisor is responsible for the surveillance and inspection l of activities performed under the direction of_ the Field l ^ l Construction Manager, and shall have sufficient authority and l l organizational freedom to: identify quality problems; l l initiate, recommend or provide solutions through designated l channels; and verify implementation of solutions. The CQC l l Supervisor is also responsible for assuring adequate inspection l points have been assigned for the work activity, inspectors l have been certified to ANSI N45.2.6, directing the activities l of the inspectors, and interfacing with the Code Inspector for l activities involved Code items. ' 'p I I O I
- 1. 5 PLANT ORGANIZATION I
I I I I 1 1.5.1 General Manager I I I I I I
- 1. 5.1.1 1
I I I ~ I I The General Manager reports to the Nuclear Operations Vice President on l' I i l the corporate level (see figure 5).and has direct responsibility for-F I1 operating the plant in a safe, reliable and efficient manner. He is. I 1 l -responsible for operating _the plant in accordance with the provisions of .l l the operating' licenses, including.the on-site quality program. I I 4 _l-I l 1 I
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I I I l 1.5.1.2 I l l I ( ) l l l The General Manager has the authority to shut the plant down if required l and has final approval of plant procedures. l l l l
- 1. 5.1. 3 I
I I l l I The General Manager is to provide technical direction and administrative l guidance to the: l 1 l l l l 1) Operations Manager l I 2) Maintenance Manager I I I l 3) Administrative Manager l l 4) Engineering and Technical Support Manager I l 1 l 5) Special Projects Manager l l 6) Manager, Nuclear Quality Control I l l l l 1 1.5.2 Operations Manager I I I 7~s l l k) I The Operations Manager (Figure 6) is responsible for directing the actual l I i l day-to-day operations of the plant. He supervises the operating staff j l and interfaces with the Maintenance Manager to accomplish I I I l operation related maintenance activities. The Operations Manager is to l 1 provide technical direction and administrative guidance to the: I l I l I 1) Operations Superintendents I i l 2) Operations Technical Staff 1 l l I I l 1.5.2.1 I 1 l l I l l The Operations Superintendents report to and assist the Operations l l Manager in directing the day-to-day operation of the power plants. They I l I l are responsible for coordination of the daily review of operating l l surveillance tests and coordination of operation-related maintenance I I I ( l i i 1. C l A .I TOPICAL REPORT lREV. 6 l l
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I I .l l l activities. They are to assist the Operations Manager in the supervision l of core refueling, which includes advance planning for the outage, plant l \\d l preparation, equipment check-out and the refueling operations. l 1 I l l 1.5.2.2 l I I l l I l 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 of the operators during their assigned shift. The Shift Supervisor is to l l be cognizant of operation activities being performed while on duty. l The l Shift Supervisor on duty has the authority to shut down the unit if, in l l his judgement, conditions warrant such action. l l l l 1.5.3 Maintenance Manager l l l The Maintenance Manager (Figure 6) is responsible for the maintenance of l plant equipment, facilities and planning / scheduling of station work l activities as defined by plant maintenance program implementing l c l procedures and to assure that maintenance of equipment is conducted in l b conformance with applicable standards, codes, specifications and I l procedures The Maintenance Manager is also to coordinate l lI operation related maintenance activities with the Operations Manager and I I l is responsible to make repairs on any structure, system or component l I under his control. I The Maintenance Manager is to provide technical I l direction and administrative guidance to the: I l l I 1 l 1. Mechanical Maintenance Superintendent l l I 2. Electrical Maintenance Superintendent I l l 3. Instrument & Control Superintendent l l l 4. Planning and Scheduling Supervisor I l l 5. Senior Maintenance Coordinator l l I 6. Shift Maintenance Superintendent I i I l 1 l l I f I y l g g l A l TOPICAL-REPORT 'lREV. 6' l l P 1 lDATE 6/10/83 l l ~&' i SECTION: 1.0 ORGANIZATION lPAGE 1-14 l l L I I I I I I' I
l-I l. l .-l: '1.5.4. Engineering and Technical Support Manager l f l \\ l The Engineering and Technical Support Manager (Figure-7) is responsible l l 'for providing plant' engineering support services as well as technical and l-plant analysis and health physics support services to the plant staff. l lTheEngineeringandTechnicalSupportManageristoprovide' technical l l direction and administrative guidance to the: l I l 4 I i { l 1) Technical Analysis Superintendent l 2) Plant Analysis Superintendent l l 3) Plant Engineering Superintendent l-l 4) Operations Assessment Superintendent-l l l 5) Health Physics-Superintendent. l 1 1 I l i 1.5.4.1 Technical Analysis Superintendent l l .I 1 I l i-l The Technical Analysis Superintendent maintains overall-responsibility l I for radiochemistry, chemistry and environmental programs at the plant.
- . g-)
l The Technical Analysis Superintendent is also responsible for maintaining l i k/ l the Station Emergency Plan and ensuring the plant staff'is_ capable of l. l implementing the requirements delineated.in the Plan and~its procedures. _l' I I l l 1.5.4.1.1 l U i i ~.1 - 1 I ~ l' l The Radiochemistry Supervisor reports to the Technical Analysis. .l 1 Superintendent and is respcasible for analyzing the reactor plant' water l-1 1 j. . l conditions and providing recommendations to maintain conditions. l' j l .I I l-1.5.4.1.2 'l' l-l 1 I I l The Chemistry and: Environmental Supervisor reports to the Technical l I. Analysis Superintendent and is responsible forLestablishing water- .I ~ l .l 1 l chemistry criteria, analyzing secondaryLplant water and auxiliary water . l -- l . 1-l -- .l- \\ .G I . 1-I , L/ l.1 A_ l--
- TOPICAL REPORT-lREV.
6' 'l l P .I'. l0 ATE _~6/10/83 Ll' - lt L&
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I I .1-I l conditions and providing recommendations to maintain conditions within i /7-I acceptable limits. O. l'1.5.4.2 Plant Analysis Superintendent l l lThePlantAnalysisSuperintendentisresponsiblefortheareasofplant l l-performance, nuclear support and computer support. A supervisor is l lprovidedforeachoftheseareas. l l l l1.5.4.2.1 l l 1 lThePlantPerformanceSupervisorreportstothePlantAnalysis l l Superintendent and is-responsible for: evaluating equipment and system l lperformanceoverextendedperiods,recommendingmethodsofimprovingand I maintaining good plant efficiency, investigating and evaluating equipment l lmalfunctionsorfailuresandrecommendingcorrectiveactiontoprevent l l recurrences, and coordinating the activities of the Inservice Testing l lProgramattheplant. l O l1.5.4.2.2 l l l l The Nuclear Support Supervisor reports to the Plant Analysis 1 Superintendent and is responsii>le for monitoring reactor core and Nuclear l lSteamSupplySystem(NSSS) performance;conductingreactor' performance l l and physics testing to assure safe and reliable operation and to provide -l current' accurate information to operations; collection and transmittal of l nuclear fuel management data to the Nuclear Fuel Supervisor in.Little l l-Rockandthereactorvendorsasrequired;on-sitesafeguardsand l l -accountability of the nuclear' fuel; and as'sisting in the planning of all l lfuelmovementsincludingnewfuelreceipt.andins'pection,fuelshuffling-l at. refueling, inspection of irradiated fuel and shipment of spent fuel. .l. -I .I I I I I l I i 1 I I o l i V l '. A. l ' TOPICAL REPORT lREV. '6-- O l .P. 1. lDATE. 6/10/83. -l l -l &L llSECTION: 1.0 ORGANIZATION lPAGE 1-16 l l .L1 -l-1 -l- .I l 1 I
1. I l l 1.5.4.2.3 I 1 7, I I l The Computer Support Supervisor reports to the Plant Analysis l I Superintendent and is responsible for the maintenance, revision and I l development of computer software for the plant monitoring computers and l I for providing technical assistance to the Nuclear Support Supervisor and I I I l Nuclear Engineers in development and use of test apparatus for evaluation l l of fuel, core and NSSS performance. I I I I I i 1.5.4.3 Plant Engineering Superintendent I I I l I I The Plant Engineering Superintendent is responsible for drawing control, I I I l implementation and coordination of the Inservice Inspection Program and l I design and plant engineering activities at the plant. The Plant I l l l Engineering Superintendent is to provide technical direction and l l administrative guidance to the: I l l l l 1 1) Mechanical Engineering Supervisor I I I l 2) Electrical Engineering Supervisor q(./ l I 3) Drafting and Drawing Control Supervisor. I J I I I I I 1.5.4.4 Operations Assessment Superintendent I l l l l I Tha Operatior.s Assassment Superintencent provides the capability to I- .l 2 l perform engineering evaluations of operating experiences which occur both l l l at the AP&L nuclear plants and at other nuclear power plants and to l _I I l recommend corrective actions as a result of these evaluations to help _l I plant-operations personnel in preventing or dealing with similar I l l.ocurrences. l l -l l I I I l 1 I I l I I-- 'l l 1 I l l ) (~N l l l l w.f -l-A -l TOPICAL REPORT lREV. 6 l l P' _l-1.0 ORGANIZATION lPAGE 1-17_ l 10 ATE 6/10/83 l. i 1 .l SECTION: l-L -l 'l -l <l 1 I I
.l 1 I I -l 1.5.4.5 Health Physics Superintendent l A l U l The Health Physics Superintendent is directly responsible for and has the I hauthoritytoimplementtheHealthPhysicsprogramatthenuclearplant l l and to maintain radiation exposure as low as reasonably achievable l l'(ALARA).The Health Physics Superintendent has the authority to stop l l work in radiation areas if he evaluates that a potential for_an l lunanticipatedexcessiveexposuretoplantpersonnelortheenvironment l_ may exist. I i l I I l 1.5.5 Administrative Manager I i l l 1 l The Administrative Manager (Figure 8) reports to the General Manager and l laidshimintheadministrativeaspectsoftheplant'soperation. l The l Administrative Manager directs the activities of the administrative staff l and'provides technical direction and administrative guidance to the: l 1 l l 1) Office Services Supervisor l l 2) Material Management Supervisor l l 3) Human Resources Supervisor l l 4) Training Superintendent 1. I 5) Plant Controller I i I 1 I i 1.5.5.1 I 1 l I l lTheOfficeServicesSupervisorisresponsibleforadministrationofthe l l clerical staff activities rd the accumulation and disposition of quality l assurance records.related to all phases of the nuclear plant. l l l 1 1.5.5.2 1 l l l l l The Material Management Supervisor is responsibl'e for plant procurement,. l l storage of materials, parts and-equipment, issuance of tools and test .l. . equipment-and the. disposal of surplus materials. I I 1 -l- '.7 -l l l l / I V-I- A-l TOPICAL REPORT-lREV. 6 l HI .P. l-lDATE 6/10/83 -l l. -1 SECTION: 1.0.0RGANIZATION lPAGE 1-18 l- -l- ~ LL .l- -l. -l. I-l 'l l
l l I. l 3 ~ l-1.5.5.3~ l I-l l'TheHumanResourcesSupervisorisresponsibleforemployment, industrial .lrelationsindustrialsafetyandfirepreventionandsecurity. Reporting l il to him are the Safety and Fire Prevention Coordinators, the Security l l Coordinator,andtheEmploymentandIndustrialRelationsCoordinator. l l l [1.5.5.3.1 l l l l The Safety and Fire Prevention Coordinators are responsible for l l conducting periodic checks to examine control of combustables, l r l.housekeepingandotherfireprevention/protectioneffortsaswellasto l l provide a centralization of OSHA and plant safety programs. l l l l l 1.5.5.3.2 l I l I l l The Security Coordinator is responsible for coordination of the efforts l l ]ofthesecurityforceandtomanagetheoperationofthe'securitysystem. 1 5.5.4 I l l l 1 lTheTrainingSuperintendentisresponsibleforthetrainingand 4 l retraining of plant personnel and of Little Rock General Office personnel l ds established by Plant procedures. I I I
- 1. 5. 6 Manager, Nuclear Quality Control l
I I I 4 I l The Manager, Nuclear Quality Control (Figure 5) is responsible for .[ l verifying the implementation of the-Quality Control' Program at the plant l fandreportstoandreceives-directionfromtheGeneralManager. The l. Plant Quality Control department shalI have sufficient authority and l 'I organizational. freedom to: identify quality' problems; initiate,- l I l -l recommend or provide' solutions through designated channels;.and verify._ -l implementation of solutions. 'His duties include: the following: ~I h l 'l-l- ,'6 l' l- =- d l- .A~ l - TOPICAL REPORT lREV. .l .P'
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1 I .I I '[- 1)' Provide technical direction and administrative assistance to l pq .l I the: l. . a. l Quality Control Engineering Supervisor l l b. Quality Control Supervisw I c. Quality Control Engineers l .- l d. Quality Control Inspectors l 'l l l l 2; l . Interface with the Quality Assurance Manager or his l f representative for technical assistance in resolving .l significant conditions adverse to quality. I I I I I 'l 3) Authority to place an item in a nonconforming status when such l l 'an' item is determined to be in violation of purchase documents, I applicable codes and standards or FSAR requirements. l I I .I l 4).. l Assuring surveillances, inspections and reviews of plant -l l activities and documents are conducted in accordance with plant l l procedures. 1. l l I I l 1.5.7 Special Projects Manager t i 1_ I l 1 l The Special Frcjects Manager is responsible for the administration and -l .ll control.:of.special projects pertaining to plant operations, maintenance i~ l and administration and is to provide technical directior. and l I administrative guidance.to a staff' of Special Project Cdordinators. .I Additional dutics' incluaa: I l
- 1 1
l .I
- 1) --
Serving as chairman of'the Plant Safety Committee l l .l_ -I i' -l l 2)
- Interfacing with onsite regulatory agencies' 1.
l I l- ~ 12 l~ J3)' Providingl evaluations;and recommendations-to regulatory
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.. requirements and' meeting regulatory commitments. l I ~ l-l ~' D .I I-l. .l u 'l ' A - l . TOPICAL. REPORT- - IREV. 6.- l . P.-- _ ' i:SECTION: '1.0 ORGANIZATION.
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- 1. 6 INDEPENDENT REVIEW ORGANIZATIONS l
l 1 ( ) 1 I l In adoition to the responsibilities of key individuals within the AP&L l lorganizationwhoareinvolvedwiththeoverallqualityprogram,AP&Lhas l l established the following committees as a management tool to l independently review activities occurring during the operational phase of l a nuclear plant. I I I I I l 1.6.1 Safety Review Committee (SRC_) l l 1 I l l 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 Specifications, l Procedures and changes thereto; unreviewed safety questions; violations, l l deviations and reportable events; and any other matter involving safe l operation of the nuclear plant which the committee deems appropriate or l is referred to them by the on site operating group. The SRC is also to l review the reports and meeting minutes generated from the Plant Safety l q l Committee. l V l l 1 l l 1.6.2 Plant Safety Committee (PSC) [I I l l lhe PSC reports to the plants' General Manager and is responsible for l l reviewing activities specified in the Administrative Technical I l l l Specifications for the purpose of: l l l l l l 1) Rendering determinations in writing with regard as to whether l I or not an unreviewed safety question (defined by 10CFR50.59) is I I I l involved; and l l l l l l 2) Furnishing written recommendatior.: to the plants' General l l Manager for approval of disapproval. I 1. I l i I I I I l I (7 l g ' a' l A -} TOPICAL REPORT lREV. 6 l-I P l lDATE 6/10/83 l l l SECTION: 1.0 ORGANIZATION lPAGE 1-21 I I L I l l l I I I
r l-1 l I -l These activities include changes to plant procedures and Technical I p Specifications, proposed modifications to plant systems, changes to l V l plant security and emergency plans, and review of facility 1 -l operations _to detect potential nuclear safety hazards. l 1 l l1.6.3 Committee Structure l l 1 lTheorganizationstructureandadministrativerequirementsspecificto l l each committee are described in the plant's Technical Specifications and l in internal procedures / documentation. l l l l
- 1. 7 ORGANIZATIONAL INTERFACES AND RESPONSIBILITIES I
I I I I I As owner and operator, AP&L assumes full responsibility and authority for I I l l the plan #. including action to assure that the plant is operated in I accordance with sound engineering practices, Licensing requirements and l [ applicable codes, specifications and procedures. I I I l-l l Each supplier of equipment, material or services and each maintenance or l I modification contractor is responsible for aaministering the applicable l l _I l quality control functions as required by AP&L. The Quality Assurance and l l Quality Control organizations are responsible for assuring by I l l 1 J l-sur/eillance, inspection, audit or review of cbjective evidence (e.g., l I audit reports conducted by o'ners, etc.) that these functions are l I I l acco:rplished for systems and structures that affect the safety.and l I integrity of the plant. I 1 l I l I Visits to manufacturer's shops by Quality Assurance organization I l l l l personnel are conducted,.when deemed necessary, based upon safety l-I significance, complexity, method of acceptance and past history of the I I l-l -l vendor, to establish product quality'and to assure that quality assurance l I and quality control programs. function in accordance with AP&L l l l -[l r6quirements. l lL o i I I l .I f i l ' n: l-l l 1
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l. TOPICAL REPORT _ .lREV. 6 l-l P i lDATE 6/10/83. l .) l. l SECTION: 1.0 ORGANIZATION lPAGE 1-22 l l L. l l -l l-1 1 t a
1. I I I l The AP&L Energy Supply Organizational Chart (Figure F-3) shows the l reporting relationships and the lines of communication established I l between the Quality Assurance and Quality Control organizations. These l- 'I lines of communication are established between the various quality I l organizations in order to provide assistance and/or information, when l requested, -in verifying satisfactory implementation of the quality l program and in resolving significant conditions adverse to quality. l l 1 I I I I I I l-l l l' I I I I I .l I l l 1-4 l l l l i l l 4 I I i 1 l l l I I I ~O l l l l l l l ~ ,= I I l 1 1 I I i 1 l j .i I I I I l l l 1 l l l. I l I i-1 l I 1 1 1 l.- l~ 1 I -j. I I I-I- j-l A( f l l .l l ^ ,l - A ' _.I -TOPICAL REPORT -lREV. 6 l. I P. .l lDATE.6/10/83 ll l-L& l SECTION: 1.0 ORGANIZATION lPAGE 1-23 l 1-L I ~[ j l i I-1:
y,. l l 'I 1: ' I -~l 2.0- QUALITY ASSURANCE PROGRAM 4 l Ll. .h7 ~ l I 1 L, l .2.1 SCOPE I I -l l 1 -l 1 This quality program is to assure that AP&L nuclear plants are operated l hinasafe,reliableandefficientmannerandinaccordancewithNRC l -l regulations, applicable industrial standards cnd codes and applicable l lCompanypolicies, rules,proceduresandlicensingdocuments. l i' A matrix of I QA Procedures cross referenced to each criterion of 10CFR50, App.- B, is l. lincludedinTable2tothismanual. l I I l
- 2. 2 GENERAL I
I l 2.2.1 l l 1 l-Thisqualityprogramisappliedtothosesafety-relatedstructures, l l systems and components and to those expendable and/or consumable items
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[ l whose satisfactory performance is required to prevent accidents which may l l cause undue risk to the health and safety of. the public or to mitigate ~ l~ g the consequences of such accidents if they were to occur. These y I structures, systems, components and consumable' items are identified in l 4 I g the Q-list within the FSAR for each nuclear unit. When structures, I g I systems and components as a whole are on'the Q-list, portions not.- l 4 associated with a loss of safety function as determined by Engineering-l I are to be considered Non-Q, unless otherwise dispositioned by l-l Engineering. - l-1 I I i .
- Expendable and/or consumable items are to include, as'a. minimum:
I 1 nuclear fuel, weld rods, boric acid, and. diesel fuel. F ~l. I . l s ~l-l l. l- . l. l..
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- l. _The quality program. for fire protection is addressed in the applicable l
section^of the FSAR for'each operating nuclear unit, and implemented
- l. through appropriate LRGO and plant procedures.
The effectiveness of the l 7 -fire protection program'is verified through scheduled audits conducted by I l Lthe QA organization, under the cognizance of the SRC. l l-1 -l' l- _l 2.2.3 l l I l l l l The Q-list is under the control of the Licensing Manager. The Licensing l I Section maintains a'n up-to-date list of personnel issued a copy of the l Q-list and assures that reviews, approvals and distributions of the [ l Q-list and changes thereto'are performed in accordance with approved I l l l-procedures. Changes to the Q-list require review / approval by the l d'iscipline Engineering Manager,' Quality Assurance Manager and Licensing l -Manager. l I l m i I 2.2.4' i l l .l The following expendable and/or consui6able items are to'be controlled in l l l -the fo' lowing nanner to assure service quality: I 1 l I l l I-L Diesel Feel - Service quality is assured by applicable l I-l provisions / tests required by the. Technical Specification for, -l J. I cach operating nuclear unit. l l - 1. L l. - l' I 2. Welding Rod ' Service quality is. assured by prccurementifrom an' I I 4 I -l. Levaluated source, requiring material test results, and i l-I controlling the rod on-site prior to use, to prevent: I I l idegradation. - lL., ; l .1 l l. I . l. I 1: I l -l i l !. h' 'l-1 l' A. -) .. TOPICAL REPORT- - l I: lREV. '6 l l P-l.. ..2.0 QUALITY. ASSURANCE: PROGRAM'IPAGE. 2-2 l~SECTION: lDATE 6/10/83- ~ l: 3-
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Boric Acid - Service quality is assured by procurement from an l lL evaluated source, requiring a batch analysis to assure l ~ 'l-conformance with our specification requirements, and on-site l control prior-to use, to prevent degradation. l l l l 2.3 RESPONSIBILITIES l 1 l2.3.1 f I I AP&L recognizes that quality assurance is an interdisciplinary function l l involving many organizational groups, encompasses many functions and l l activities and extends to various levels in all participating l l organizations (froc the Energy Supply Senior Vice President to all l lworkerswhoseactivitiesmayinfluencequality). This quality program l designates responsibilities and duties of specific individuals, which may - l be performed by their appointed designees. l 1 l-l 2.3.2 I I I -O l This quality program assigns the responsibility for quality to the l departraents-performing the work and includes as a basic requiierrent that l individuals responsible for verification of conformanch are quclified ano l do not perform or directly supeivise the work. Additicnally, independent l reviews, auoits and surveillances are provided by individuals _not. l reporting to the groups responsible for performir.g the work. l l l 1 l 2.3.3 1: 1 1 1: 'l l _l This quality program also includes provisions.that require sup' pliers, l:- -l. contractors,isubcontractors, consultants,etc.tomaintainanduse-
- l' quality-assurance'programsreviewedandapprovedbytheQuality; Assurance;
-l ~I'Nanager. Audits'.or surveillances by the: QA0 provide _ assurance of I la.. l l. compliance with applicable procedures. 1 .l l l 1 l 11 1 .s l- 'A .l TOPICAL REPORT IREV. 6' 1 P; .l LIDATEL 6/10/83 l~ l .l SECTIONi ~2.0 QUALITY ASSURANCE-PROGRAM
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i l-I -l l l 2.3.4-l o' j l 1l The Nuclear Fuel Supervisor within Nuclear Operations is responsible for l theLassurance.that nuclear fuel used in AP&L nuclear plants is designed, l 'l procured, manufactured, and utilized in accordance with regulatory l - requirements, and related industrial codes and standards. On-site l l quality control'~of nuclear fuel is implemented through the use of plant l ladministrativeprocedures. These procedures include the receipt, l inspection, handling, storage,- and accountability of Special Nuclear l -l Material:(SNM).-TheNuclearSupportSupervisormaintainsalistingof l 'those_ individuals qualified to perform receipt inspections. l l 1 I I l 2.4 PROCEDURES l I I i l l l 2.4.1 l l l l - l l Activities which affect quality are defined in appropriate procedures, l I which are developed'to cover AP&L administration and' control. The l s l l -( l procedures state the policies and instructions necessary_to fulfill the l l intent of the program.- Precedures provide for standard forms, lists, and i l check-offs used in documenting the inspections, certifications, reviews, l surveillances and audits..The progras and the procedures shall be l modified or' supplemented from tinie to time as the need for change arises l during the life et tSe plant. < Quality program policies, procedures and y l instructions are contained in the documents listed in Table 2. .l I I l l 2.4.2 .l l l l l l' l j Procedure's assure that activities.affecting quality are performed under l. 'I suitably controlled conditions. Controlled conditions include the'use~of. l l- -1 l appropriate equipment; suitable environmental conditions for. performing- .I ~ l ~l. the activity such as.. adequate cleanliness;.and assurance that required 'l-3 l l-l- -l l l l' O~
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i i l A.. } . TOPICAL REPORT. lREV. -6 -l 1l .P ' :l -lDATE 6/10/83: 'l l -- ~.& l,SECTION: 2.0 QUALITY ASSURANCE ~ PROGRAM-. lPAGE 2-4 l l 'L-i .l l l l ~ .I 'l
0 l I .I 1. .l. prerequisites for the given activity have been satisfied. Administrative I (7 I i procedures also assure that the need for special controls, processes, I As ~ l test, and equipment to ' attain the required quality and the need for l I . verification of quality by inspections, evaluation or test is taken into l l account. I I I I I l 2.4.3 l l l 1 l 1 Other AP&L organizations outside of Energy Supply may establish written l lprocedurestocontrolsupportactivitiesaffectedbytherequirementsof l I this quality program. Procedures developed by such organizations are l prepared and reviewed for technical adequacy within the cognizant l l organization, reviewed by the Quality Assurance Manager and approved by l lthecognizantorganization'sdepartmenthead. l l l l2.5 PROGRAM REVISION AND CONTROL l l l l
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l A l U l l Program revision and control shall be the responsibility of the Quality I y I Assurance Manager. I i l l 1 1 I 2.5.2 i I .1 l l l Proposed changes to the Quality Assurance Program for Operations are to' I l be submitted by the Quality Assurance Manager to-affected LRGO and plant l l management personnel for review and comment prior to approval and - I transmittal to the Nuclear Regulatory Commission. After resolution of l l comments, changes are to be approved by the Quality Assurance Manager, l Energy Supply Se'rvices Director, and the Energy Supply. Senior Vice .l l President.
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I I zl I l 2.5.3 1 I. /~) I l l l The Nuclear Regulatory Commission is to be notified of changes to this l lqualityprogramannuallyforthosechangesthatdonotreducethe I commitments in the program description previously accepted by the Nuclear I l-RegulatoryCommission. Changes to the program description that reduce l l the commitments are to be submitted and approved by the Nuclear l Regulatory Commission prior to implementation. The Quality Assurance l l Manager is to determine if changes do or do not reduce the commitments of l this~ quality program. l l l l2.6 PERSONNEL' l l l l
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l l l Employees-whosedutiesandresponsibilitiesarerelatedtothequality l program activities at or in support of the nuclear plant are to I y participate in appropriate indoctrination and training programs to assure l that suitable proficiency is achieved and maintained in the work they are l performing. - Such training shall include, as a minimum: plant security; l l discussion of the overall Company policies, procedures and instructions l which establish the quality program; an explanation of the AP&L quality l l organizations; and a discussion of those procedures whicn inplement the l quality program related to the employee's specific job-related activity. l -l l 2.6.2 I I I I I 'The education, experience and responsibility requirements of individuals l l involved in this quality program are documented in job descriptions which l are approved and periodically reviewed by management. Requirements for-I education, experience and proficiency levels are commensurate with the l I 1. i l I 1 I l il I I I I i f) I . A j . TOPICAL ~ REPORT IREV. 6 l i l l l l l-P l .[DATE 6/10/83 I i . ' l SECTION: '2.0 QUALITY ASSURANCE PROGRAM [PAGE 2-6 I i 1 .L 1. .I l l-- l l .l- = - - - = - - - - - - - - - - -
1 -l l I l' degree of importance of the job assignment. Experience and training l } requirements for plant staff personnel are to meet the requirements of l l ANSI N18.1-1971 and Regulatory Guide 1.8 (9/75), unless otherwise noted l l'inTable1. Personnel whose qualifications do not meet those specified l -l in ANSI N18.1-1971, and who are performing inspection, examination and l ltes'tingactivitiesduringtheoperationalphaseoftheplant,aretomeet l l the requirements of ANSI N45.2.6-1978, unless otherwise noted in Table 1. l 1 1 I I l 2.6.3 l l-1 I I l Personnel performing inspection and examination activities are to be l lindoctrinatedandtrainedtoassuretheyareawareoftherequirements I which govern the#r activity. Inspection and examination personnel are to l lbequalifiedaccordingtotheapplicablecodes, standards, I specifications, regulatory requirements and LRGO and plant procedures. l lPersonnelperforminginspectionsonthoseactivitiesoccurringduringthe l l operational phase that are comparable in nature and extent to related l activities occurring during initial plant design and construction are to l meet.the provisions of Regulatory Guide 1.58, rev. 1 (9/80) and ANSI I N45.2.6-1978, in lieu of ANSI N18.1-1971. l 1 1 I 2.6.4 I l I l I lFersonnel-involvedwithweldingornondestructiveexaminationof-l materials, systems or components are to meet the appropriate l lqualificationrequirementsoftheASMEBoilerandPressure_VesselCode, 1 Sections III and XI, or for structural welds, the American Welding l l Society (AWS) Structural _SteelCodeD1.1,'andtheAmericanSociety-l l Nondestructive Testing Standard SNT-TC-1A-1975, and certified to perform l lthese_tasksinaccordancewiththesecodes'andstandards. f I l 1 1 1. _l l l. -l l l l l I l-p l A ' TOPICAL REPORT. IREV. 6 i P _. , l-10 ATE 6/10/83 -l I-lcSECTION: .2.0 QUALITY ASSURANCE PROGRAM 'IPAGE 2 I-l
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sin 2. 6.' 5 l f( - l 1 ' Jij' l l l Personnel performing audits of the quality program are to. meet the .l experience,' training and qualification / certification. requirements of l~ ANSI N45.2.23-1978, and regulatory guide 1.146 (8/80), unless otherwise l l noted in Table-1. I l '2.6.6 I I .j.Trainingrecordsaretobemaintainedinaccordancewithapproved l procedures. For formal' training programs, documentation is to include l l the objective ~, content 'of the program, attendees, and date of attendance. l I l 2.7 PROGRAM REVIEW I I I l I l: 2.7.1 l l l The Quality Assurance Manager is responsible for a' review of this program 7' 1 on an annual basis to determine the effectiv'eness and proper l implementation of the quality program. l 2 l [ l
- 2. 7. 2
] I -l l Management. reviews.ofthestatusandadequacyofthequality.programare l accomplished through regular reports and presentations by the QA0.and l l'throughreviewsof'qualityassuranceaudit. reports. -Quality Assurance l reports supply data on the status of outstanding audit and corrective -l. action. items and may. identify the status of other significant quality. I 1.' program activities as: requested by management.
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1 I l~ l l-3.0- DESIGN CONTROL [ l 3.1-SCOPE l l l l l l Design activities are to be controlled to assure that proposed plant l lchangestothestructures, systems,equipmentandcomponentsconformto l applicable regulatory requirements and that design bases are correctly l l'translatedinto'appropriatedesigndocuments. Design Control activities l are to be in accordance with the requirements of Regulatory Guide 1.64 - l lRev.2(6/76)unlessotherwisenotedinTable1. l 1 I I 3.2 GENERAL I I I I I l 3.2.1 I I I I I lEngineeringServicesandPlantEngineeringaretoberesponsibleforthe l continued upgrading and modification of plant design. Design documents j (drawings, specifications, procedures and instructions) originating or l released through these departments are to be based upon the required l lregulatoryrequirements,licensingbaseddocuments, functional l l requirements, quality standards and design bases in accordance with NRC l licensing requirements. Design activities may include calculations. l analyses, materials selection, equipment arrangeme'it and laycuts, l accessability for inservice inspection, and the specification of test and l inspection criteria. Those design activities performed by individuals l within Engineering Services are controlled by the use of LRGO Er.ergy l l Supply Procedures. Those design activities performed by-individuals-l I within Plant Engineering are controlled by the use of Plant l' I I. l Administrative and Engineering Administrative Procedures. These j l procedures include controls to assure that verified computer codes are 'l i 1 l certified for use and that their use is specified. l I .I I I I I i l i I 'O l i I I 'O l A' l TOPICAL REPORT lREV. 6 l. I P-l lDATE 6/10/83-l l I SECTION:. 3.0 DESIGN CONTROL lPAGE 3-1_ l l_ ,L -1 l l 'l I l- -l
m I I I. I l 3.2.2 I g. -l l ('~'i - '1 I l Design standards and requirements are to be at least equivalent to those l employed 'during.the construction of the plant and are to be consistent l l with the technical specifications and license requirements. I l-l l 1 -l 3.3 DESIGN INTERFACE I I I l l l Design control activities include measures for the' identification and l control of design interfaces between the various engineering disciplines l l within the department, between LRGO and plant engineering personnel, I l between engineering personnel and other AP&L support organizations, and l l between engineering personnel and firms / suppliers outside the AP&L l l organization. These measures include the development of procedures among l the participating organizations for the review, approval, release, l distribution and revision-of documents. involving design interface. l l Coordination of the interface control is the responsibility of the l originating organization's management unless otherwise specified in an l AP&L procedure applicable to:the design activity. Design information I between interfacing organizations is.to be documented.and retained for i permament records. I I l 1 l l 3.4 DESIGN VERIFICATION l l l I l l 3.4.1 l 1 l 1 l l To assure the design is adequate and the above requirements and l procedures are implemented, Engineering Services for LRGO design or Plant l l Engineering for plant design are to verify the adequacy of the design l through the performance of design reviews, the use of alternate or l 'l simplified calculation methods, or_the performance of a qualification l I l l l l l 1 l 1 I l l (") l I. 1-l. l A. l TOPICAL REPORT lREV. 6 -l l Pf. I 10 ATE 6/10/83 l l l SECTION: 3.0 DESIGN CONTROL- .lPAGE 3-2 l l. L 'l l l 1-I l-l
-l-l l I l-testing program.- The extent and depth of design verification performed l I -by the. responsible organization is determined by an assigned engineering U^~- I 1 I l-reviewer based upon the importance and complexity of the design, the l degree of standardization and its similarity with proven designs. In all l-cases, the. design verification is to be complete prior to relying upon [ the component, system or structure to perform its function. I I i 3.4.2 I I l i I lTheverificationprocessistobeperformedbycompetentindividualsor~ l l groups other than those who performed or supervised the design but who l may be from the same organization. This verification, however, may be l performed by the originator's supervisor in accordance with departmental I l I procedures if he is the only. individual in the organization competent to I I l perform the verification and provided the need is individually documented l and approved in advance by the responsible Manager or Superintendent. l The frequency and effectiveness of use of Supervisors as design verifiers l is to be verified by QA through scheduled audits to guard against abuse. ) l Where changes to previously verified designs have been made, design l l I verifications are required for the change, including evaluation of the l l effects of the changes on the overall design. I l l l l l 3.4.3 l l l l l l l When a test program is used to verify the adequacy of a design, it is to l I I include suitsble qualification testing of a prototype or initial I l production unit ur. der the most adverse conditions and carried out in I I -l I accordance with documented procedures and/or instructions. Testing is to 'l I l be parformed as early as possible prior to installation of plant l l l equipment, or prior to the point when the installation would become I l irreversable. l l j I i I I l l 1 l I o) I l t i I l -A .I TOPICAL REPORT IREV. 6 l~ l-P l 10 ATE 6/10/83 l- .- l l SECTION: 3.0 DESIGN CONTROL IPAGE 3-3 l 1 L I I .I I l-l l
t ~l 'l l l '3.4.4; I 1-I ~/ ) l l _l l Design work performed by organizations outside of AP&L is to receive a l ldocumentedreviewandapprovalbyengineeringpersonnelinaccordance l l-with LRGO and plant departmental procedures. 1 I I l l l 3.5 DESIGN CHANGE I 1 l l l l 3.5.1-1 I l I l l Methods for the preparation, review, approval and implementation of l design cht.nges, including field changes, are documented in departmental l l procedures for Engineering Services and Plant Engineering. Design-l lchangesaresubjecttoreviewandverificationby-thesameorganization I which review and verified the original design unless otherwise specified l in departmental p'rocedur'es 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 cognizant engineer and transmitted with the changes for revie'w and l approval in accordance with Plant-Engineering _ Administrative Procedu es. l l 3.5.2 I i lChangesfromspecifieddesigninputs,suchasdesignbases, regulatory l 'l requirements, codes and standards (including quality standards) are to be l identified, approved, documented and controlled throunh applicaole LRGO l l and plant departmental procedures. l' l 1 l l 3.5.'3 1 -l l l l l l During preparation of a design change, the responsible engineering l .lorganizationistoperformasafetyfandenvironmentalevaluationper l l'l 1 l 1 l l l () l l l v l A. l TOPICAL REPORT lREV. 6 l.. =.l P- .I lDATE 6/10/83 l 1, ~l SECTION: '3.0. DESIGN CONTROL) lPAGE 3-4 l lI L 1 1: ,1 I I I I
k 11: I 'l-1 l: -10CFR50.59 to. verify' compliance with the Final Safety Analysis Report and l l,todetermineifN'RCapproval,ofthedesignchangeisrequired. ~ The .l evaluation is to.be documented and then reviewed by the PSC. l -l I
- l l
l.:3.5.4 l l. l l ~l- .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 quality codes, standards and inspection requirements in the design .l l documents.
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[3.6CORRECTIVEACTIONS I -l l When design changes are made as a result of design deficiencies or' l l errors, corrective actions (for significant conditions) are.to be taken l in accordance with Section 16.0, to determine.the cause and to institute-l l appropriate: changes in the design process and/or Quality program to. l. ' prevent recurrence. When a significant design change'is necessary l because of an incorrect ~ design, the design process and verification 'l . proce'dures shall be reviewed and modified as necessary. 1 -l I 3.7 DESIGN RECORDS I l -l l l The Plant Administrative Manager is responsible.for maintaining permanent l .scords'of the design documents for the construction'and testing phases. l In f addition l he shall be responsible for. maintaining records *of.the. ~ 'l upgrading or modification of these documents as. described in this l-I I: section. The controls for maintaining these records are established by- ~I l-l. specific procedures described in Section-17,of this manual. These l; . records provide the' historic reference necessary for.the safe and -l reliable operation of the plant. l I l
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I I 'I l l 4.0. PROCUREMENT DOCUMENT CONTROL l g3 l l 4.1 -SCOPE I I I .I I 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 l included or referenced in the procurement documents, whether procured by l l LRGO or plant procurement groups. Procurement document control l activities are to be in accordance with LRG0 and plant procurement l l ' procedures and are to meet the provisions set forth in NRC Regulatory l l Guide 1.123,rev.1(7/77)unlessotherwisenotedinTable1. l l l l4.2 l PROCUREMENT DOCUMENTS f I l l 4.2.1 l l I lTheprocurementofmaterials,partsandcomponentsaregeneratedthrough l the preparation of a Purchase Requisition (PR).and subsequent issuance of l laPu'chaseOrder(P0),orwhenadditionalservicesfromtheVendoris 7, l required, through the preparation and issu'nce of a Contract. The j a prccurement of services is initiated through tbe preparation and issuance- ? l of a Contract. The preparation, review, approval and issuance of these l procurement dccuments is to be in accordance with applicable procurement' l l and contract administration procedures. Purchase Orders for items are l 1 issued through the AP&L Purchasing group and Contracts for items and/or l services are issued through the AP&L Contracts Administration group. l l yp l l l 4.2.2 l l l. l 1-. ? I l Procurement documents are to include or reference specific design .l specifications for' the items or services to be$ 5. ' procured which define -l specific codes, standards, tests, inspections, environmental l_ l. qualifications, and records to be applied and/or furnished. For standard I I 'I* I t 5 (] Il-l j l l l A l TOPICAL REPOR7 lREV. 6 _l I P i-lDATE 6/10/83 l l 1 SECTION: 4.0 PROCUREMENT DOCUMENT CONTROL IPAGE 4-1 l ly L~ fl' Ll -l y_ I l-6 l 1 3 4 L-
i ~ ' h_ l .f ;g l "off-the-shelf" items, reference to the items ~ catalog number and l
- [9 j% T,
/ il identification number may be included on the procurement document in lieu l Y of a design specification. New or revised specifications for replacement l -items are to be evaluated by the~ responsible engineering organization l !I y -l against the original spe'ification for the item. The evaluation is to be l c k# I in accordance with applicable engineering procedures and results in the I l 1 .l establishment of new baseline and technical quality requirements, which I are to be used for subsequent procurements. ze l l ? $f l l NJ -l 4.2.3 l N 1 $..3-l 1 gy i I [~ lProcurementdocumentsarealsotoincludetheidentificationofquality y l assurance program requirements applicable to the items or services l I -f e procured. Procurement documents.also establish requirements for source I ib h audits and inspection, extension of the procurement requiremen'.s to lower l T' 4 >' ~ y /' tier suppliers or subcontractors, and preparation and delivery of 7 g ?$._. l documentation. These requirements may either be in the form of documents l 3 attached to the P0 or Contract or by incorporating them in the specific j. /yl l design specifications. Quality programs are to be specified by ir.voking l Q }N x the appropriate sections of 10CFR50, App. 8, the appropriate ANSI b, [ l standards and/or the appropriate AP&L generated quality requirements for -l 3/ k - g items or services. The appropriate sections of the ASME Boiler and I' I .o y l l . ?%* l Pressure vessel Code are to be invoked for items originally designed to l Nh [ I meet ASME requirements. I-
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1 N' l l 3 l 4.3 REVIEW 0F PROCUREMENT DOCUMENTS l p 9 ~ l Nt) R ' 4,I 'l~ d-4 ' h 'l The responsible Quality Assurance or Quality Control organization, as-I .( ' A .l e A. q' identified in the LRGO and plant procedures for procurement and contract l
- i. I' administration activities, is to review all procurement' documents to I
S l o $(4ggi '. l ~ assure that the required quality requirements (including source l-l ..z ^ >S lI' surveillance and/or inspection) are imposed on-suppliers / contractors. .I h-I A hy -l j tN
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x. 1-l l' I .l 4.4' CHANGES.T0 PROCUREMENT DOCUMENTS l 1 Changes to procurement documents are to have-the same degree of control l and review as imposed on the original documents. Changes such as l. inconsequential editorial corrections or changes to commercial terms and l conditions may be made by the Nuclear Buyer or Contract Administrator as ~1 appropriate, after concurrence from the originator 'of the document. l l I l' l .' l i I I l-l .I l I 1 ~l l 1 l l' -l. l l l. l l l 1 l l I -l l l 0 l l 1 I i l l I i l I I I l. l .l l -l l -l-l i. I l- -I 1: .l l l' l- -l- .l l l- 'l. l l l. l-l- .I 'l-I- l .l, l --
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a l I l I ~ l ~ 5.0 INSTRUCTIONS, PROCEDURcc AND' DRAWINGS l LOL l. l l. 5.1 SCOPE I -l-1 l I 'l 5.1.1 l l l l' l l Instructions, procedures and drawings are provided for the control of l ' those activities which affect quality and safety at the nuclear plant. l Activities covered by written procedures include, as a minimum: l administrative, general plant operations, start-up; shutdown; power l operation and load changing, process monitoring, fuel handling; l modification; maintenance and repair; radiation control; calibration and l test; chemical-radiochemical control; plant emergencies; test and l inspection; and quality assurance, quality control and LRGO activities in l support of p.lant activities. The format, content and philosophy of l instructions and procedures are to comply with the guidelines in ANSI l N18.7-1976'and Regulatory Guide 1.33 (2/78)-unless-otherwise noted in ~ l .I Table 1. I I l O l5.1.2 I I I l I l Instructions and procedures are also provided for the control of - l activities relating to the repair, rep.lacement or modifications to ASME -l Code,-Section III, Class 1, 2 or 3 components required to be operable to-l l mitigate-the consequences of a postulated. accident. 4 l l 1: I l
- 5. 2 GENERAL l
l l -1 .I .l 5.2.1 l 'l l I i l .l Instructions _, procedures and drawings are to include appropriate, _l. quantitative criteria such as-dimensions, tolerances and operating limits-I ~ _l and/or qualitative criteria such as: comparative workmanshipisamples ~to l l l-determine that important activities have been satisfactorily- '. I. I 1 l -O 'l. I: l-l l .A. l-TOPICAL REPORT lREV. 6' -l l P .I -lDATE - 6/10/83- -l- 'l- 'l SECTION: 5.0-INSTRUCTIONS,_ PROCEDURES' lPAGE 5-1 l l L i AND DRAWINGS. .l' l ll I 'l -
DI l l I l': accomplished. Each procedure is to be'sufficiently detailed so that a l . qualified individual may perform the required function (s) without direct .l~ supervision and is toLinclude measures to document the activity being l performed. l l l l5.2.2 l 1-l To assure the accomplishment of activities in accordance with approved l 1 instructions, procedures and drawings, each supervisor is responsible for l quality compliance of his personnel.. Verification that activities are l l accomplished in accordance with approved instructions, procedures and l ) l.drawingsisobtainedthroughvariouslevelsofsurveillanceand l l~ inspection by Quality Control personnel and through periodic surveillance l landauditsbytheQA0. l l l5.3 REVIEW 0F. INSTRUCTIONS, PROCEDURES AND' DRAWINGS l l l l5.3.1 f I e) I Instructions, procedures and drawings are prepared, reviewed and approved. l in accordance with applicable plant administrative procedures, when j originated at the plant, or in accordance with applicable Energy Supply-l l procedures, when originated from LRGO. l l l l I 5.3.2 1 l l I I I l Plant procedures identified in.the Technical Specifications for each unit l landchangestheretowhichdescribeactivities'requiredtoimplementthis 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-l reviewed by the Quality Control staff-to verify compliance to AP&L's I I l 1 l-I I .I l' i l l l .I l 'd i A l TOPICAL REPORT .lREV. 6- 'l I -P l' ..5.0 INSTRUCTIONS, PROCEDURES'. IPAGE '5 l ~lDATE~ 6/10/83 l [ l SECTION: .I L l. AND DRAWINGS-l. _l 'l I l I~
.; [ l .I I l;; quality program requirements. LRGO Energy Supply prrcedures describing l cf W -I activities required to' implement this quality progran are to be reviewed I -() l- .I l and ' approved by a procedures, task force committee ard Quality Assurance l l to assure compliance to AP&L's. quality program requirements prior to l l submittal of the procedures to the Department Head responsible for l implementation, for approval and subsequent issuance. l ~ l l l 5.3.3 I l I l' l lPlantandLRGOproceduresandinstructionsaretobereviewednoless l l than every two years to determine if changes are necessary to meet NRC l I commitments and current AP&L practices. Applicable procedures (i.e. I i I l those that relate to the incident cause) are to be reviewed following an l lunusualincidentsuchasanaccidentunexpectedtransient,significant l operator error or equipment' malfunction.' Applicable procedures are also l l to be' reviewed following any modification to a plant system. I l l I l-l 5.3.4 I I I "O' I I Drawings related to plant changes and modifications are ' controlled as I l l l described in Section 3 and 6 to this manual. l l l l l 5.4 CHANGES TO PROCEDURES l l- -l l I l 5.4.1 I l l l
- l l
- l. Changes.or-' revisions to approved' instructions, procedures and drawings
-l .Il are to be reviewed and approved by.the same organizations or groups that l .I l performed the. original' review unlessiotherwise noted.in specific AP&L_ -l-I procedures'~and controlled.in the same manner as the' original. I'- 1 I I l l l-1. I. l l l- 'l;- l-
- l-l l
l-h'-
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l l -l A ,l. TOPICAL ~ REPORT lREV. 6- - -l l P' l.. ~ lDATE'?6/10/83 ll -l E&'. . -l SECTION: 5.0: INSTRUCTIONS,' PROCEDURES .lPAGE: 5 3 -l. l' -L:- 'l 'AND ORAWINGS. <l l. .l
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I I I I =l 5.4.2 l X li I , i._) l I I Temporary changes to approved plant procedures which do not change the i intent of the procedure-may be ma'de 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 I plant procedures which change the intent of the procedure may be made i lprovidedsuchchangesarereviewedbythePSCandapprovedbythePlants' l I General Manager prior to implementation. Temporary changes to approved .I plant procedures are-to specify the period of time during which they may l l 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 l procedure, operations personnel may take action, without obtaining I approvals, so as to minimize personnel injury and damage to the facility l l ' and to protect health and safety. I I I l-l O l l. 1 I l i I I I I i l-I- 1 I I I I I I I I I I I I I I I I I -l i l-1 -1 l-1 I l.. l l il I l .I I l~ I -l C~~. I I I I I i .I A-1] . TOPICAL' REPORT - IREV. 6. -l l P .'l-IDATE~ 6/10/83 l I T& ' I SECTION: 5.0 IllSTRUCTIONS, PROCEDURES (PAGE 41 l .1 L i-(AND DRAWINGS 'l I -1 i -1 i
'l l I I l 6.0 -DOCUMENT CONTROL l n 'l l T J1 I I ~~ l 6.1 SCOPE-l I I ~l l l The various quality program documents identified in Table 3 provide means l to control the review, approval, issuance, use and retrievability of l documents, such as calculations, computer codes, analyses, Topical l l Report,FSAR, instructions, procedures, specifications, manuals'and I drawings, including changes thereto, which prescribe activities affecting l l quality. l 1 I 6.2 iRESPONSIBILITIES l -l I l6.2.1 l l I l Each organization originating documents which prescribe activities l affecting quality is responsible for the establishment of document l control procedures which identify individuals or groups responsible for l 1 l preparation, review, approval and maintenance of the document and for the l lissuanceoftheseprocedurestotheaffectedindividualsorgroups. l l .1 - l6.2.2 l l 'l l lReviewofthesedocumentsforconcurrencewithqualityrelated l l l requirements is to be performed by the appropriate Quality Assurance or l . Quality Control organization or by the appropriate reviewer as described l in LRGO and plant procedures. I l I I l 6.2.3' l l-l 1 l -1 l The plant Administrative Manager is responsible for the. control and- .l I
- 1. issuance of plant procedures, and revisions thereto, to assure I-l.
l d'istribution in accordance with plant procedures. The plant l ' Administrative Manager.is also responsible for the storage and control of I
- I 1
r-() I l-l l ~ l A 1 TOPICAL REPORT .lREV. 6 l l PL ' ll SECTION: lDATE 6/10/83 l l 6.0 DOCUMENT CONTROL -lPAGE 6-1 l l-L- l l 'l. I -l I 'l
'b:v, 'g. ~ - ~ \\ Ll. l .l^ I l-approved-historical plant documents, and 'h'e storage of historical-l t i drawing,. records..The-Engineering and Technical Support Manager is l 'l: responsible' for the. control and issuance of _ drawings and revisions l ~ th_ereto to assure that theyereflect the as-built conditions of the plant. l .I I .l::6.3. IDENTIFICATION 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. Revision l status of. documents are to be identified in document registers, -l distribution lists and/or within the revision record page/ block'of the -l l document. 1-1 I I l 6.4 _ DISTRIBUTION l l-l l-1 I-l Distribution lists and/or document registers are to be maintained by the' l organization responsible'for issuance of the document. These lists are l l to identify the revision status.of the document and are,to be reviewed - l and updated periodicallylby. the responsible organization to maintain them ' l in a cur' rent status. These lists are available to indiv.iduals using the l document to assure they are in_ receipt of the current document. These ^ ~ l _ measures are to preclude the possibility.of using outdated or -l . inappropriate -documents. l: l l
- l-
_l'
6.5 CHANGES
I l- .I I
- I ~6.5.1 l-l l
.1-l- ].(Changestocontrolled'documentsareto'bereviewedandapprovedbythe3 l same organizations which' performed the original reviewfand approval- ~ -l. Lunless otherwise specified.in departmental procedures 1 applicable to the'- (l'. saffected activity. - l l 1. l l-I .I .I I -1 l A. j . TOPICAL REPORT . l REV.' - 6 l -l. P..
- 1.. -
~ l 1 ";l.LSECTION: - - lDATEL 6/10/83: .l ~ ~ 6.0 DOCUMENT CONTROL lPAGE 6 :1.
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l- 'h
- l,
-l: >,. l LI ~ l' -l I'l [ 4
I l: l I). I -l .6.5.2 1 !:(). I 17 Obsolete or. superceded documents are to be destroyed or marked to prevent l - inadvertent-use in accordance with applicable document control
- l' procedures.
l 11 I l. l l
- 6. 6 STORAGE l
l I .I I -l Documents which affect quality are to be stored and maintained at the l I plant in permanent storage facilities and controlled as described in l l Section 17 of-this manual.- .l l l l l l 6.7. VERIFICATION l l 1 I l l Quality Control personnel, through their.various levels of quality l surveillance and inspection activities, and Quality Assurance personnel, l through their' audit activities, assure proper documents are being used l I and made available to those individuals performing.the work. O l
- l l
l' I I I; I l l l 1 l l I .I I I l~ l l l -1 1 l -l: l-l .I l l 1 .1, .I .I .I I; l L.. 1 l: I 'l I l- .l-1 l fp
- l 1
. 1: N cn I-A~ 'l - . TOPICAL REPORT. IREV. l l-P., 'l IDATE 6/10/83' .l. -I;
- &7,.
llSECTION: ~6.0 DOCUMENT CONTROL .IPAGEE6-3 1. J l.',- .L-le I I l. s
~l l l I l 7.0 CONTROL'0F PURCHASED MATERIAL, EQUIPMENT AND SERVICES l l l .-. (7 l l l 7.1 SCOPE I 1 l -l I l The purchase of material, equipment and services is controlled to assure l l that, whether purchased directly or through vendors, th' e material, l equipment and services which affect quality conform to the procurement l l documents. Procurement control includes provisions for source evaluation l l and selection, objective evidence of quality furnished by the contractor, l lg, surveillance and audit at the source,' examination of products upon I g I delivery and testing of received material for conformance to procurement l I I l criteria. The depth and necessity of_ procurement controls depend upon y I the uniqueness and complexity of the item / service, procurement frequency i I l with the same supplier and past supplier performance for the specific l I items or services covered by the procurement document. The control of I purchased material, equipment and services is to be in accordance with-I the requirements of Regulatory Guide 1.38 Rev. 2 (5/77) and 1.123 Rev. 1 l l(7/77)unlessotherwisenotedinTable1. l n I I 7.2 _ SOURCE EVALUATION AND SELECTION I I l 7.2.1 l l lAQualifiedVendorsList(QVL)istobemaintainedandcontrolledunder l the direction of the Quality Assurance Manager. The QVL identifies I those vendors / contractors that have been evaluated and approved by the QA0 to furnish material, equipment or services, and identifies any I restrictions imposed by the QA0 on the vendor / contractor as a result of ~ l l their evaluation. I l I l-l l l I I l I I I l l I I 1 I Im. l l _ TOPICAL REPORT IREV._ 6 l 'j - l l l A ~l l P. l - lDATE. 6/10/83 l l_ I=SECTION: 7.0 CONTROL OF PURCHASED lPAGE 1 l l L. I MATERIAL, EQUIPMENT AND SERVICES I I
- l l
I I
I I l.. 1 l 7.2.2 l w l I l ' Vendors / Contractors are evaluated and placed on the QVL by any of the l following methods, as approved by the Quality Assurance Manager: l 1 I (1).-Source survey by AP&L to verify compliance to applicable 10CFR50, l l-Appendix B requirements or to applicable ASME Section III Quality l Assurance program requirements (for ASME Class 1,2,3,MC,NF and NG l components). I 1. I I I l (2) Evaluation and acceptance of source surveys' performed by others l ] (ex. CASE, other utilities, NSSS suppliers, and prime contractors) l l indicating a program meeting the appropriate requirements of l l 10CFR50, Appendix B. (This method is not applicable for ASME l l procurements.) l l l 'l 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 l l program, manual and procedures, when available. (This method is not l applicable for ASME procurements). l l l(4) Evaluation of the vendor's/ contractor's history of providing a l . product / service which performs satisfactorily in actual use. l 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 l 1 (5) i' Verification that a vendor is a holder of an ASME Certificate of I 1 l Authorization issued as a result of an ASME survey may be used in l lieu of methods 1 and 2 for ASME procurements. I l (D l l l l l A 'J . TOPICAL REPORT -lREV. 6 l l P l lDATE 6/10/83 l l &.. ' l-SECTION:. 7. 0 CONTROL OF PURCHASED lPAGE 7-2 l l L' .1 MATERIAL, EQUIPMENT.AND SERVICES l l 'l 'l l _l
W 'l l I I l -(6) Verification that-a contractor is -a holder of a NRC letter I (3 l confirming-QA program implementation may be used in lieu of l l method 1. l l 1 I I l 7.2.3 i l l = l-I l Only vendors / contractors listed on the QVL.are to be selected for i procurement of material, equipment or services except for items l l designated " commercial grade" per plant and LRGO procedures. Standard I l'catalogitemsmaybeprocuredfromavendor/contractornotlistedonthe l l QVL provided the manufacturer of the item is on the QVL and all AP&L l lrequesteddocumentationoriginatesfromthemanufacturer. The QVL is to l l be periodically reviewed and updated per quality assurance procedures to l ensure the current status of all selected vendors / contractors is I available to personnel involved in the procurement process. l l l l l I 7.2.4 I I l -l I p l When contractors are selected to perform work activities at the plant, l their personnel and work activities ~are to be controlled in accordance l with plant procedures to assure that the contractor conforms to the l procurement documents. I I i I. 7. 3 SOURCE SURVEILLANCE AND AUDIT I I l l 7.3.1 l l l l-Theeffectivenessofaven' dor's/ contractor'squalityassuranceprogramis l 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, independent testing or revi.ew of. source documentation files.' l 1 l I I I l I I I f') I l i I l l A 1 TOPICAL REPORT' lREV. 6 l l P ~l lDATE 6/10/83-l l ' l SECTION:
- 7. 0 CONTROL ~0F PURCHASED (PAGE 7-3 l
l' .L. I MATERIAL, EQUIPMENT AND SERVICES I l-I l i 1.
l 1: I I .l 7.3.2 I l l 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 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 their appointed representative in accordance with surveillance plans l approved by the Quality Assurance Manager and the results documented per l quality assurance procedures. Reports documenting inspections performed l I and discrepancies observed are prepared by the person performing the l surveillance to document compliance to the procurement documents and for l future use as historical quality performance data. l 1 I l7.3.3 l l l l Audits of the vendor's/ con. tractor's quality assurance programs are l l periodically performed under the direction of the Quality Assurance l Manager to verify implementation of a satisfactory quality program on the l items or services being procured by AP&L. Audits performed by others l l(e.g., CASE,otherutilities,.orprimecontractors),asevaluatedand l approved by the Quality Assurance Manager, may be used.as an alternative l ltoauditsbyAP&Ltoverifythevendor/contractorisimplementinga l l satisfactory quality program.. Audits are to be conducted in.accordance l with Section 18 of this manual. -(This alternative method does not apply l l to-ASME procurements.) 1 j. l l l 7.4 RECEIPT INSPECTION l l' l l .) l 7.4.1 l l l I 1 l Materials and equipment, including ASME Code materials and equipment, are-l l-I subject to inspection upon receipt at the plant. The degree of I I l inspection is specified in the procurement documents and is to be I l performed in'accordance with plant procedures for receipt inspection.. O-
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.A I TOPICAL REPORT lREV. 6 I i i i l
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lDATE '6/10/83 I l l SECTION: _ 7. 0 CONTROL'0F PURCHASED lPAGE '7 'l 'l L I MATERIAL, EQUIPMENT AND SERVICES I l l l l l.
l i I I l 7.4.2 1 s l l ) l I ~ .l Receipt inspection activities are to be documented and include, as a l minimum; examination of material or equipment for shipping damage, l l proper identification, and quantity; and the review of vendor l l documentation, to verify compliance with the procurement document. In l addition, if material and equipment received at the plant were not l inspected at the vendor's facility by AP&L, an inspection is to be l l performed by a Quality Control Inspector at the point of receiving to l l verify that the material or equipment conform to the inspection i requirements identified in the procurement documents. l l l l l 1 7.4.3 I I I I I l Vendors are to furnish documentation as required by the procurement l l documents for objective evidence that the material or equipment conforms l to the procurement requirements. Review and acceptance of this l ldocumentationistobeperformedbyaQualityControlEngineerpriorto l r] l installation or use of such material or equipment and documented unless I otherwise specified in plant procedures. Certificates of Conformance may l be required by procurement documents which identify the requirements met l by the vendor. The validity of the vendor's certification program is to l be periodically verified through scheduled source surveillance and audit l activities or through independent testing of the item by AP&L. l l l l 7.4.4 I I I I I Accepted material and equipment is released, identified as to its l inspection status and forwarded to a controlled storage area or released l l for installation per applicable plant procedures. I I l I I I I I I l I l i I ,o i l I I I l A l TOPICAL REPORT lREV. 6 l l P l 10 ATE 6/10/83 l -l l SECTION:
- 7. 0 CONTROL OF PURCHASED IPAGE 7-5 l
l L l MATERIAL, EQUIPMENT AND SERVICES I l l - 1 I I
I I I I I 7.4.5~ l l. p$. l I (# I l Acceptance of services furnished by a' contractor is to be identified in l the procurement documents. Depending upon the service performed, .I acceptance may be by technical verification of the data produced, l l surveillance and/or audit of the activity, or review of objective i l evidence for conformance to the procurement document requirements. The l lacceptancemethodistobeperformedbyqualifiedindividuals l l knowledgeable in the service provided. l l l l l l 7.4.6 i l I I l l Independent testing of selected material is to be performed in accordance l lwithplantprocedures/instructionstoverifyconformancetoprocurement I l criteria and the validity of the vendor's certification documents. l l l l l l 7.5' NONCONFOR
- G ITEMS l
l l-l l 7.5.1 l l l l Nonconformances identified by the vendor / contractor which adversely l laffectreliability,performanceorinterchangeabilityoftheitemand l dispositioned repair or use-as-is are to be submitted to and accepted by l AP&L. prior to closure of the nonconformance by the vendor / contractor, i These nonconformances are to be documented and become part of the l lprocurementdocumentationfurnishedbythevendor/contractorforthe l material, equipment or services procured. l l l l l 7.5.2-l l l l-l l l Material and equipment found to be deficient or missing procurement l documentation during receiving inspection or found to be deficient as a I l result of independent testing is to be clearly identified,= segregated l l 1 l I 1 I ) I l-1 I - v ~ -l A l TOPICAL REPORT -lREV. 6 I l. P l l0 ATE 6/10/83 l l l SECTION: - 7. 0 CONTROL OF PURCHASED lPAGE 7-6 l l . L' l MATERIAL, EQUIPMENT AND SERVICES l l l l I 1
l l 1 l l from acceptable items and dispositioned per plant procedures and as I -( described in Section 15 of this manual. l l l l 7.6 l SPARE PARTS l 1 lSparepartsaretobepurchasedtotheoriginaldesignrequirementsorto l those specified by a properly reviewed and approved revision to the l ldesignrequirements. The applicable quality assurance requirements and I documentation requirements for spare parts are to be included in the 1 lprocurementdocuments. l l l l
- 7. 7 l
STORAGE l l lMaterialandequipmentaretobehandledandstoredasdescribedinplant i procedures and Section 13 of this manual. l l l l l I I I I I I O I I 'd l l l l l l l 1 l I I I I l i l l l l l l l l l 1 l l l l l l l l l l l I l I I i l l l 1 l O I I I l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 I I 1 SECTION: 7.0 CONTROL OF PURCHASED (PAGE 7-7 l l L l MATERIAL, EQUIPMENT AND SERVICES l l l-l l l
7 l ~. I l l l 8.0. IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMP 0NF*is l . m i I -8.1 SCOPE: l I I I I I 8.1.1 I I I I I I Measures for the identification and control of. materials, (including l lconsumables),partsandcomponents,includingpartiallyfabricated l l subassemblies, are to be established within LRGO and plant procedures. I I These procedures.are to relate an item of production (batch, component, l part, etc.) at any stage,.from initial receipt through fabrication, I l installation,repairormodificationtoanapplicabledrawing, l l specification, or other pertinent technical documents. These measures I are to assure that only correct and accepted items are used and l l installed. I l l I I I 8.1. 2 1 I I I I Methods for the traceability of materials, parts and components to I specific inspection and test records, when required by codes, standards, I specifications or procurement documents, are to be established within l l LRGO and plant procedures and maintained throughout the life or l l consumption of the item. I l-1 I i 1 8.2 ' IDENTIFICATION I l l l I l 8.2.1 1 l l 1 l l Mater.ials, parts and components are to be identified by.the vendor in l laccordancewiththeapplicabledesignstandards,codesand/or I instructions specified in the procurement documents. l I I I l I 1 1 l-l l [ I O l i I .I i A I TOPICAL' REPORT lREV. 6 I I .P. l. IDATE 6/10/83' l l & -~ l SECTION: 8.0 IDENTIFICATION AND CONTROL IPAGE 8-1 1 l L l 0F MATERIALS, PARTS AND COMPONENTS 1 I ? I l l 1.'
'l I l 1 -l 8.2.2 l ln i I ~' Materials, parts and components are to be identified and/or tagged at the l plant in accordance with applicable plant procedures. These tags l l: Identify the status of and provide traceability to the item throughout l l storage and release to installation. l 1 l-8.2.3 l l 1 (; l Identification of materials, parts and components is accomplished by l either marking or tagging on the item or through records traceable to the l item. I I l8.2.3.1 l l 'l Physical identification is to be used to the maximum extent possible. l Where physical identification is either impractical or insufficient, l physical separation, procedural controls or other appropriate means are l_ l to be employed in accordance with plant procedures. l L l i I -l l 8.'2.3.2 I l l l I l l l When identification markings are employed, the markings are to be clear, l unambiguous and indelible, and applied in such a manner as not to affect -l the integrity or function of the item. Markings are also to be j transferred to each piece of material (plate, barstock, tubing, etc.) l when subdivided. Large quantities of small items, er ay be identified by l . applying markings.or tags to their shipping packages, boxes or other-l suitable containers. l l l l -l I l l l. I l 1 l I l l l l /D' l l \\ l l l A l TOPICAL REPORT lREV. 6 l l P l l0 ATE 6/10/83-l l l SECTION: 8.0 IDENTIFICATION AND CONTROL lPAGE 8-2 -l -l L l-0F MATERIALS, PARTS AND COMPONENTS l l l I l _l
E. I I I I I 8.2.3.3 I ~ I I l Identification markings are to be recorded on records or as-built l ldocumentsifcurrentmarkingsaretobehiddenorsubjecttoobliteration l by surface treatment or coatings during fabrication, installation, repair I lormodifications. l l 1 l8.3 l CONTROL l 1 lPlantorganizations.receivingmaterials,partsandcomponentsareto l l verify that they are properly identified while under their control. l lQualityControlpersonnelthroughtheirsurveillanceandinspection l activities assure that compliance to these requirements are being met. l lQualityAssurancepersonnelthroughtheirauditactivities,alsoassure l i l that materials, parts and components are being identified in accordance l l with this manual. I I l8.4-DEFECTIVEORINCORRECTITEMS l O l8.4.1 l g I l f lDefectiveorincorrectmaterials,partsandcomponentsidentifiedby l l plant personnel or support groups are to be handled in accordance with l l Section 15 of this manual and plant procedures for.nonconformances and l corrective action. Defective or incorrect items are to be tagged with a l " hold tag" affixed to the item or otherwise identified per plant l i l procedures. l l l l l l 8.4.2.. l l l l l I Defective or incorrect items are to be stored in segregated areas except l for those. items installed or which,'due to their size, weight l l configuration, etc., are impractical or. impossible to store in the l ldesignatedcontrolledstoragearea. l l I .l n l .l l A I' TOPICAL REPORT -lREV. 6 l 1 P -l l0 ATE.6/10/83. l l 1 SECTION: 8.0 -IDENTIFICATION AND CONTROL -lPAGE 8-3 l 1 L-l OF MATERIALS, PARTS AND COMPONENTS ~l l l 1 I I
I I I I l
- 9. 0 CONTROL OF SPECIAL PROCESSES I
(D l I ll 9.1 SCOPE l ~l-l l l l Special processes are to be controlled through the use of qualified l l personnel and plant procedures which meet the requirements of applicable l l codes, specifications, standards and other criteria stipulated in AP&L l llicensingdocuments. l l l l9.2 l GENERAL l 1 9.2.1 l l l lSpecialprocessesarethoseactivitieswhichrequireinteriminprocess I controls in addition to final inspection to assure quality and include-l lsuchactivitiesaswelding,nondestructiveexamination,heattreating, l coating, plating and chemical cleaning. l l l l 1 O l 9.2.2 i V l l l l-l Technically qualified LRGO or plant personnel are to establish the l lproceduralandqualificationrequirementsforthosespecialprocessesnot l covered by existing codes or standards or where AP&L quality requirements -i exceed the requirements of established codes or standards. I I l9.2.3 l l l ~lTherequirementsforweldingandnondestructiveexaminationaretocomply l l with the applicable portions of the ASME Boiler and Pressure Vessel Code l l or for structural welds, the AWS Structural Steel. Code D1.1, and the. I American Society.of Nondestructive _ Testing (ASNT-TC-1A-1975 and l 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 dated 3/16/73 unless otherwise noted in Table 1. I fl l l l l l A -l P.. -l TOPICAL REPORT: IREV. 6 -l' l l l0 ATE 6/10/83 l l SECTION: -9.0 CONTROL OF SPECIAL PROCESSES IPAGE 9-1 I i ,L I-l 1. l I I l-
l I l-l l 9.3 QUALIFICATION I p-l 9.3.1 I l i I I -l 'Special process procedures for welding and nondestructive examinations l l are to be qualified prior to use to assure compliance to applicable l l codes, standards or specifications. These qualifications are to be l documented and also made available for review to the Code Inspector for l activities on ASME items. l I I I I l 9.3.2 l l l l l l Personnel responsible for the performance and verification of special l l_processesare'tobequalifiedand/orcertifiedaccordingtoapplicable l l l codes, standards,' specifications, regulatory guides and plant procedures. l These qualifications and certifications are to be documented and made l available for review to the Code Inspector for activities on ASME items. l j lPersonnelqualificationand/or.certificationrecordsfor,aspecial l p] l process are to be regularly reviewed by the supervisor responsible for l ,I that special process to assure.that the appropriate documents are l g l l up-to-date and personnel are periodically requalified and/or. recertified l linaccordancewithplantprocedures. l l 1 I l 9.4 RECORDS I l l i l I I The results of special processes are to be documented, reviewed, approved l and stored in accordance with appropriate plant procedures and as I addressed in other sections of this manual. l 1 l I 1 l l I I l 1 l l l 'l l I l I I 'l -ll' (O I I I l A l TOPICAL REPORT [REV. 6 l i l P.. l lDATE 6/10/83 l ~ l l SECTION: 9.0 CONTROL 0F SPECIAL PROCESSES lPAGE.9-2 l l L -l l l ,I I I I i
w l 'l l. l ~ 'l-1 i l -9.5 iVERIFICATION I i-l; l 1 f-a .l Performance of.special processes in accordance with applicable codes, l Lstandardsi specifications and plant procedures is verified by Quality l .1. Control personnel through their surveillance'and inspection activities, I . and by. Quality ~ Assurance personnel through their audit activities. I l I I .I I ( I I
- l 1
.I .I 'I I 1 I -I l I I 1 -l L I I l l 1 I l-L I -l-i i I i ~ l I l l I i O -l l 1 l.- I ~l I l: I I I I L I I I l I l t i l I 1-I -l -l I
- I
- I.
I I l I I I' I I I I. .I l I l -l L .I l Li-l l I-l l 1 I !lC'- I A I- , TOPICAL REPORT IREV. _6-l l 1-1 I I l -P... I~ 'IDATE: 6/10/83 I I 'l.SECTION: 9.0 CONTROL'0F SPECIAL. PROCESSES' IPAGE 9-3 l- .I L I i I p q .- l i 1 l m
I I L I I i 10.0 INSPECTION l .,m l'- 1 O I i l 10.1 SCOPE I I l 1 I I Inspections relating to normal operating activities and inspections l l relating.tooperatingactivitiescomparableinnatureandextenttothose 1 occurring during initial plant design and construction are to be l L controlled to assure that inspections are performed in accordance with I applicable design documents, codes, standards, specifications and l procedures. Inspection activities are to be in accordance with l l l Regulatory Guide 1.33, Rev. 2 (2/78), unless otherwise noted in Table 1. l I I I I i 10.2 GENERAL l l 1 1 I i l 10.2.1 l I I + l l l l Inspection activities relating to normal operating activities l l(OperationalInspections) include: l 0 l l l g 1) Work functions associated with normal operation of the plant; I 2) Routine mai'ntenance; I l 3) Technical services routinely assigned to the onsite operating L l organization; and I 4) Non routine maintenance activities and minor modifications made l l by the onsite operating organization that are not comparable in i nature and extent to related activities occurring during l initial plant design and construction. 1 l I I l 10.2.2 I l -l l l l l Inspection activities relating to operating activities comparable in l lnatureandextenttorelatedactivitiesoccurringduringdesignand l l l' construction (Construction Inspections) include: l l l l l l l l l l n l l l i l I A l TOPICAL REPORT IREV. 6 l l P l l0 ATE 6/10/83-l l l l SECTION: 10.0 INSPECTION lPAGE 10-1 l l L I l l l I I l
l 1 I I l 1) Non routine maintenance, except as noted in paragraph 10.2.1; l and l 2) Modifications, except as noted in paragraph 10.2.1. l 1 l l I l The following Regulatory Guides are to be applied, as applicable, in l-determining the basis for required construction inspections: R.G. 1.30, l-Rev. 0 (4/76); R.G. 1.38, Rev. 2 (5/77); R.G. 1.39, Rev. 2 (9/77); l I R.G. 1.37, Rev. 0 (3/73); R.G. 1.94, Rev. 1 (4/76); and R.G. 1.116, l Rev. 0-R (7/76). l l l l l l 10.2.3 l l l l l l Personnel performing inspection activities to verify quality are to be l lqualifiedasstatedinSection2ofthismanual. When inspection l techniques require specialized qualifications or skills, personnel l performing the inspection are to meet applicable licensing requirements, l codes and standards appropriate to the discipline involved. l l l l l rm l 10.3 CONTROL OF INSPECTIONS l (,) l l l l 10.3.1 l l l l l l l Inspections are to be performed in accordance with approved written l l procedures, which set forth the requirements and acceptance limits and l specify the inspection responsibilities. If inspections require detailed l lwrittenprocedurestoperformthetask,theproceduresaretocontain,as l a minimum, the following: l l l l l l 1) Qualitative and/or quantitative acceptance criteria; l l 2) Prerequisites for performing the inspection and any limiting I i l conditions; 1 l I 1. ~l i l I l l l l l l l A J TOPICAL REPORT lREV. G l l P l 10 ATE 6/10/83 l l l SECTION: 10.0 INSPECTION lPAGE 10-2 l l L l l l l l l l
I I I I l 3) Identification of any special equipment and tools required to l (~) l perform the inspection (when accuracy requirements for l '~ l inspections exceed the accuracy of normally available process l l or measuring and test equipment, such additional accuracy l l requirements are to be specified within those inspection l l procedures); I 4) A step-by-step description of the method of inspection, l l examination, measurement or test to be performed; and l l 5) Identification of those inspection results to be documented. I l Inspection forms or checklists are to be used as an aid in l l documenting the inspection activity to assure quality l l l requirements have been met. l l l10.3.2 l l l l Operational inspections are to be performed by qualified individuals l l other than those who performed or directly supervised the activity being l inspected. Construction inspections are to be performed by qualified l l individuals other than those who performed or directly. supervised the l g activity being inspected and do not report directly to the immediate l l supervisors who are responsible for the activity being inspected. l 1 1 1 l l 10.3.2.1 l l l 1 l l Operational inspections may be performed by second-line supervisory l l personnel or by other qualified personnel not assigned first-line l l supervisory responsibility for conduct of the work. l 1 l l l l 10.3.2.2 l l l l l l Construction inspections are to be conducted in a manner similar to that l l,associatedwithconstructionphaseactivitiesinaccordancewith l applicable plant procedures. l l 1 l l 1 I p I l v i .I I I l A l . TOPICAL REPORT lREV. 6' l l P ,l lDATE 6/10/83 l l 1 SECTION: 10.0 INSPECTION .lPAGE 10-3 l l L l l l l 1 1 I w
c I I l. l l 10.3.2.3 I i i l l p) I I s l If individuals performing inspections are not part of the Quality l l lAssuranceorQualityControlorganizations,theinspectionprocedures, l personnel qualification criteria, and independence from undue pressure l such_as cost and schedule are to be reviewed and found acceptable by the i responsible Quality Assurance or Quality Control organization prior to l linitiationoftheactivity. l l l l10.3.3 l I I [ l If an inspection determined to be required is impossible or l l disadvantageous, indirect control by monitoring processing methods, l f l 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 inadequate without both. l l I l l l q l 10.4 INSPECTION POINTS l V I l l l l 10.4.1 l l I I l l Inspection hold points are established for non routine maintenance l lproceduresanddesignchangepackages(OCPs)by-PlantEngineeringand l 1 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 requirements.. Inspection hold points for work functions associated with l. lactivitiesotherthannon-routinemaintenanceandDCPs,areestabli_shed l l by the originating department, by Quality Control or other responsible l I
- l. individuals.
I I I l l -l l l l 1 O"' I l -l I l A .l TOPICAL REPORT lREV. 6 =l l-P. l. lDATE 6/10/83: l l ..l SECTION: 10.0 INSPECTION-lPAGE 10-4 'l-l L_ -l [ I. .l l I l-
h p. 1 I l- .I I I 10.4.2 1 6 l' l q l ' Inspection hold points are inserted in procedures based upon safety I significance, complexity'of the item or activity, degree of l l l standardization of.the item or activity, past performance of the item or l -l activity,procurementfrequency,andtheabilitytoverifyqualityby l ) l jobsite testing. I l l l l l I 10.4.3 l 1 I I I l Inspection responsibilities, requirements, information and acceptance l l criteria for the work activity are to be identified in appropriate, i l approved plant documen+s (e.g. procedures, checklists, etc.) l l l l l l I i l 10.4.4 I I l I I i l For work involving the modification, repair, replacement or in-service l inspection of ASME Code materials, parts and components, the work l l packages are to be made available to the Code Inspector prior to l-lcommencingworkforhisreviewandassignmentofinspectionholdpoints. i l The department responsible for the work activity is responsible for I notifying the Code Int, pee. tor when the hold point is reached. Work is not l l to proceed past a Code Inspector's inspection hold point until signed or l lwaivedbytheCodeInspector. I I l10.5 DOCUMENTATION I 1 l 10.5.1 l I 1 Inspections and process monitoring activities are to be performed and the ~ results documented in accordance with approved procedures or-I l j Instructions. Records are to: provide objective evidence'that the .l l l 1 1 0 l l l l l c I O I 1 I l I _l A l TOPICAL REPORT lREV. 6 l l P. I 10 ATE 6/10/83-l i ~&
- l.SECTION: _10.0 INSPECTION lPAGE 5 l
l L I ll 1 I I I l ( = -
') M jl-Q.n j;t h ~ rc .g QQ* 3; t. A ,e l l I ( a 1 P,
- 1. inspections and monit,oping activities,were performed in compliance with l
4 q ({' [ l procedurespstruc'tjhns or dr'awingsIo, verify'd2 sign requirements; show l(complidacewithacceptaxecriteriaoMdentify,thecauseofrejected l \\,; items; and identify the ap ofr}Tateins ctlempersonnel approving the l k l results /, I
- ).
g i l Na e, e i l 1f10.5.2 p I c f ( Q'l A(, t 1 D ) l', I Records 'are' td be maintained (in accordance with plant procedures and l bec' tion 1720f this' manual, i Ins ect3on results on' ASME code items are 'h t ' [/, - r.(( $ ,l '['af jable to_ the bcEe Inspectoh for his review. l j l lj l-i ( l I 5' </jt i 10.N3 C ', 's /' l ,1. fi,,\\ 1 I ',L .s l ',y t i i qt iril i (> t ',st I s \\ '- 1j Thy results\\gf,h11 inspect on art [ monitoring activhies are periodically l a gh f MtAted per plant procedures and th,e results doc'umented to determine ) [I k' ' - l,I khetNw sth?,ir,Ch'idual inspection pi'fgrams demo't. strate that the plant can / l !',h: Ip )i be operated safely and as) do[igned.f ' I ' h lI I \\. s I t h/ l g.}f N0$f.y'FJ4hAmp 4 I, 1 i s i,_ lI i i j l a,< l s lt: l ja,' / If,' / }j, Ntiscomfor,mi tj'ams thund u a ' result of i, spection and monitoring g 5 \\ 1 k g .(g .l*activithbart, lentifi l segrega,th.i and cispositioned in accordance l s I .l\\$,thpl'antpr'c?duresandSection15d' smanual. Rework, repair or I 1 o l d ((1, f9placemenh,erf 0f med qf ter complehh f t jg, s i l e / l f,f reinspectioki to i:'ne ext'er)t necess'sry dj determine acceptability to !', '( i d@.Ablish6h dryeria. f. I / t / l 'l .'. i A, l l-j i l 3 y -( 0I,' 'l l si l i n) ' l lM a y,/ , ' 1 A/' I N N ct 4 1 fl[i.,I 3 m I // y) a.i ,3,' c
- 4. c r
'h i t 1 g o ,a < N h .,,, r,M / I ,h I .'\\ s, j '9 lI .A 1 d. t e l l h A'sc -( TOPICAL REPORT IREV. .6 l vj_ >1 'k\\~ l .P :,T .l lDATE 6/10/83 1 d I, - () 1 [GTION: 10.0 INSPECTION .I/[ IPAGE 10-6 l
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- 5
. f; {, $,r M yf* -l-l 39 g l ])[ i 11.0 TEST CONTROL l g [7 /v j l l 11.1 SCOPE i
- ~
l-l pj l I l{l 9./: l A test program is to be established to assure that testing required to l demonstrate that an item will perform satisfactorily in service is g g identified, documented, and performed in accordance with writ, ten test l l {Mif l, g procedures. These procedures are to incorporate or reference the l 11 requirements and acceptance criteria contained in applicable codes, l I y,3 I 1 standards and specifications and in the licensing documents. These 4 I 3, I activities include testing during the operational phases of.the plant and l f those tests required as a result of modifications, repairs or I maintenance. These activities are also to comply with the spplicable l ,y lprovisionsofRegulatoryGuides1.33,Rev.2,unlessotherwisenotedin 7, / l Table 1,' and with the applicable sections of the ASME Boiler and Pressure l 4 (( Vessel Code for ASME designated items. f y f' I l } l11.2' PROCEDURES l 3C t/) l11.2.1 l 1 -. l l I I 3 I Written procedures / instructions are to be prepared to describe the - ;$j f l requirements for conduct of the testing activities. These procedures / ~l J instructions are'to contain or reference the information required in .l Section 5 of this manual and in the applicable Regulatory Guides l mg .l i g pertaining to Quality Assurance requirements for testing activities. l L). l I. I 11.2.2 l I l-l 'l Test procedures / instructions and revisions _thereto are to be subject to l l the same review and approval process as outlined in Section 5 of this I
- 1. manual.
-l z,. I l. -1 l 1 ' -/ -1. 'l a l 1 I-
- i. m) -
.l l 'l l- !ll - -l1 A ~.l. TOPICAL REPORT -lREV. 6 1 P-
- l lDATE 6/10/83?
-l W 'l. ~ j. l l: l SECTION: 11.0.--TEST CONTROL
- lPAGE'-11-1 l
~
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L f l -' I l 'l q
I I I I i 11.3 TEST CONTROLS l _g3 ~l l t l l l 11.3.1 l I l 1 I 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 l to evaluate plant performance as the start-up progresses. Initial l l start-uptestprogramsaretobeplannedtopermitsafefuelloadingand I start-up, to increase power in safe increments and to perform major I testing at specified power plateaus. l l l l11.3.2. l L l 1 lSurveillancetestsduringtheoperationalphaseoftheplantaretobe l conducted per written procedures / instructions to_ assure that failures or I substandard performances do not remain undetected and that the required 1 operability is maintained to ensure they will continue to operate, I keeping parameters within normal bounds, or will act to put the plant in l p -l a safe condition if they exceed normal bounds. I d l I I I l 11.3.2.1-l I l l l l Mandatory inplant surveillance tests and inspections required to assure l loperationwithinthelimitingconditionsofoperationareidentifiedin 1 the Technical Specifications applicable to each unit at the plant. To l lensurethattherequiredtestsareperformedasscheduledwithinthe l l specified time interval, surveillance procedures are established and l maintained for mandatory surveillances_ identified in the Technical l l Specifications. These procedures are to specify the component or system, l type of surveillance activity, frequency of activity and the cognizant' l individual responsible for completion of the surveillance activity. l l l-1. I l- .I-l l 'I I i i I I I 7,, i 1 l l-l l l A 11 .TOPIdM, REPORT- -lREV. 6 -l l P, l' -l l.SECTION:. lDATE 6/10/83 'l. J 11.0 ' TEST CONTROL -IPAGE 11-2 1 I L I -l I-1 I l-I
1 1 I I I -l 11.3.2.2 l l I (s) l I l' Inservice inspections required to meet the requirements of ASME Boiler I and Pressure Vessel Code, Su tion XI, are to be identified in the l 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 i each unit. The plan specifies the inspection items, inspection i ~ l procedures, inspection intervals and type of inspections. Plant l Engineering is to coordinate the-implementation of the ISI plans at l appropriate scheduled outages. The plans are also to be made available l l for review by the Code Inspector. l I I I i 11.3.3 l l I l l l Tests following plant modifications, repairs, maintenance, or significant l lchangesinoperatingprocedures,aretobeconductedtoconfirmthatthey I are not detrimental to the safe and efficient operation of the plant and I that the components or systems demonstrate satisfactory performance. I O l11.3.4 g l l 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 I a) test equipment and measuring devices are calibrated in I accordance with the requirements of Section 12 of this manual l and are functioning properly; I b) . test personnel have been-qualified to perform the test in l accordance with the requirements of Section 2 of this manual; I c) appropriate witness and hold point notifications have been l provided; I I I i l l -l, 1 (#) l I I l -A_ l TOPICAL REPORT IREV. 6 l l' -P l _IDATE 6/10/83- [ .l I SECTION: :11'.0 TEST.CONTROLL IPAGE 11-3 l-l L; 1 .I l-1 I -I I_ La,
5 T '1 -l_ l
- l -
l li d) test perequisites completed; and l .e)' when accuracy requirements for tests exceed the accuracy of
- l normally.available process or measuring and test equipment, l
I I l such additional accuracy requirements are to be specified I 1 -l. within those test procedures. l j', 'l ; l. J (1 I l 11 3.51 l c ~l l 'l ~ I ~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 -l -repair, modifications, replacement or scheduled inservice tests on ASME: I [ lCodeitemsisalsosubjecttoinspectionbytheCodeInspector. l The l-assignment-of inspection hold points is described in Section 10 of t,his [ ~ l manual. l g I I l11.3.6 'I I - l g' ~ l l ~ l Test results are to b'e documented in accordance with the applicable l r ? l procedures / instructions. Test documents are to contain at least the l ,~ following: g I 1. ^ (1). Identity of-item tested. l '(2) Date of test. l. (3) As-foun'd condition. -l- -(4) Identification of individuals performin~g test. l l. .(5) Test results.. 1 I l { .li -(6) ' Corrective; actions performed if=any. .l-cl i (7) ~' As-l e,f t. condi ti on. 'I L .I l' 1 i -: l - [
- 1. -
I-il 11.3.7.- e l-l _l-_- .e l ~ !bTe'st}resultsaretobeevaluatedby:respon'sibleplantpersonnelperplant f l-fprocedures,to assure that test: objectives ~and inspection = requirements. 'l ~ l -l1 Lli I it m -l- 'h 1: Ll. ~ ..J -l
- ll
.: 11.- A;. , il' TOPICAL REPORT 2 -lREV.. ! 6 --. LI 11 P. ~ll lDATE :6/10/83-~
- l<
cp u ~ 1l - j4
- liSECTION:
11.'0 XTEST CONTROL ^ l PAGE J.11-4.: l: .l. _ ; L:
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- l
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+
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l-I It. I l -have been satisified. Non-conforming conditions, are to be identified [ -and controlled in accordance with Section 15 of this manual. l-1 I 11.4 RECORDS' I I I I-l Test results are to provide objective evidence that the testing was I performed in compliance with approved procedures. Test records are to be l I maintained and transmitted to the plant Document Control Center for l. retention in accordance with Section 17 of this manual. l I I I l l 11.5 TEST STATUS [ l l l ~ I 1 Inspection and test status is to be controlled in accordance with the I provisions ~of Section 14 of this manual. l l I 1 1 I I I I l 1 I o l l l l 1 1 I I I 1. l l I I l 1 4 I I I I 1 l l l
- I i
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I [ TOPICAL' REPORT IREV. 6 -- l 1 'P 1. IDATE-6/10/83 ll- .I &~. l SECTION: ..11.0 ETEST CONTROL" IPAGE 11-5 I
- l L
1 l-i l ll-1 I l-- a + y .t v+
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l I. l l l 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT l o l l l 12.1 SCOPE l l 1 l l l 12.1.1 l l l l l l. A program is to be established to assure that devices used for j measurements, tests and calibrations are identified, controlled and l calibrated against reference standards to assure that accuracy is l maintained within the limits specified by the inspection or test l requirements. Control of measuring and test equipment is to comply with l the applicable provisions of Regulatory Guide 1.33, rev. 2, pertaining to l l measuring and test equipment, unless otherwise noted in Table 1. I L. l l l l l 12.1.2 l I I I l l This section does not apply to rulers, tape measures, levels or other l lsuchdeviceswherenormalcommercialpracticesprovideadequateaccuracy. o I 12.2 RESPONSIBILITIES I I l I 1 12.2.1 ~ l I The cognizant Superintendents / group Supervisors at the plant are l responsible for establishing and maintaining lists of measuring and test l equipment under their. control that require periodic calibration and for i l.the.calibraf, ion of this equipment, as assigned within plant procedures. l-1 l i I. 1 0 l 12.2.2 l- -l l l-The cognizant Supervisor is responsible for identifying measuring and l ' test equipment required for the activity and assures that the devices are~. -l used only by. qualified personnel. .l l l I ~ l e l l l. {'}! l l i l .A l. . TOPICAL REPORT lREV. 6 l L i. P; l. - lDATE-:. 6/10/83 ~ l l. &~.
- l SECTION
- -12.0 CONTROL'0F'MLASURING.
~lPAGE 12-l' l-l
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.AND TEST EQUIPMENT. l: I-
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r. 4 ' I 1 l 1 l 12.2.3-l h ~ ~l Plant personnel are to;be responsible for utilizing only properly' l identified-and' calibrated measuring and test eq'uipment when performing l I l -inspe'ctions and tests for record. 1 -l l-l .l. l E! 12.2.4 l 1 l -. l I The Manager, Nu' lear Quality Control and his staff are responsible for l c lmonitoringtestequipmentcontrolanduseinordertoverifycompliance l l with'the program. l l I 1 I ~l 12.3 GENERAL l l' l I I I 12.3.1 l l l l -l l Calibration procedures are to-be established for each type of-measuring l .lan'dtestequipment. Th'ese procedures'are to conform tofrecognized codes - l and standards and to local, state and federal. regulations, and are to be 1 referenced on the calibration reports. I I ..l12.3.2 l l. j Measuring and test equipment is to'be' properly controlled,- calibrated and. -l-1 adjusted at specific intervals or prior to use to assure the necessary - l ~ accuracy of-calibrated. equipment. Calibration intervals-are to.be based l. upon the type of equipment, manufacturer's.. recommendations, stability and
- l freliability
- characteristics,r'equiredaccuracies,useand.other
~ l conditions affecting calibration. l l' . l-
- l II
-l 12l3.3~ l. Ll- .1 l ^ 1: 1-l Reference standards used 'in the calibration of measuring and Ltest' ll equipment are 'to.be traceable to the National Bureau of Standards,' or if ~ l 1 Lx. Il l 'p l-I, .I 6 'l ~ : l. .l lA-
- . l.
TOPICAL. REPORT
- lREV.
1 -P.'. il-
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- - ( -
L LE l
- AND TEST EQUIPMENTo.
l-. pa ~l.
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i ~ l _. I l l l nonexistent, to accepted industry or AP&L standards. Reference standards l .( are to have an accuracy at least four times that of the measuring and l test equipment. In any instance where the four times criteria is unable l ltobemet,standardsaretohaveanaccuracylevel, acceptable I l calibration range, and precision equal to or better than those required l l.fortherangesaffectedbythecalibration. Accuracies less than four l times will be acceptable when warranted by statistical analysis or l l limited by the state-of-the-art as authorized by responsible management. l Reference standards are to be maintained in an environment with l temperature, humidity and cleanliness controls compatible with l maintaining accuracy and operating characteristics of the standards. l .I I l l l 12.3.4 l l l l I l When measuring and test equipment are found to be out of calibration, an l evaluation of the validity of previous inspection or test results and the l acceptability of items previously inspected or tested is to be made and l documented by written report in accordance with plant procedures. If any ( l piece of measuring and test equipment is consistently found to be out of l calibration, it is to be repaired or replac'ed. I i i I 12.3.5 I I I l Recalibration per plant procedures is to be performed when the accuracy. l l of either installed or calibrated equipment is questionabic. [ l I l. .I l 12.4 EQUIPMENT IDENTIFICATION l l l 1 -l l 12.4.1 l .I I l l .l The measuring and test equipment. list is-to contain sufficient l information to uniquely _ identify each item 1isted and is to include as a l minimum,; calibration intervals, tolerances and storage locations. The-l l l l 1 l. I ll l (m i I l l ~) l: A 1. TOPICAL REPORT lREV. 6 l 1 P. l 10 ATE 6/10/83 l: l l-SECTION: 12.0 CONTROL OF MEASURING" 'lPAGE '12-3 I I L l AND TEST EQUIPMENT-l l l ' 1-- I l-
- 1 c
'l' l 1.- l- ?- l l ?listlis:also to identify the group responsible for the control of each l t. _ g h I tem.- l '.14 I i-I I 1 12.4.2 w l I l b
- Each item' listed on the measuring and test equipment list'is to b'e l _ tagged, labeled or. otherwise identified per plant procedures 'in such a l
manne'r that clearly identifies-the eq~uipment and its calibration status l l and provides traceability to the calibration records. l I I I I l. 12.4.3 l l-l- I I i; I Measuring a'nd test. equipment found to be out of calibration is to be. l - tagged'and segregated from;acc'eptable equipment in'accordance'with~ plant l' .l procedures until' repaired and recalibrathd. l 1 1 l l I j il ~ 12.5 RECORDS. l j. g .t l Calibration documentation is to be maintained to verify. calibration ~ I ' status,- condition, accuracy and' out Lof tole ~rance trends'of the equipment. I l l 1 l l f l' l-I ' I I l l. l-l l -l' i -l-l .l .I ^ l 1 ll- ~l l' -l. l
- l l _
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[ .l~ -j .l ~l l Il j m. .[ -- g l, l A; _l. ~~ TOPICAL REPORT SlREV. 6 .ll
- 1
- P :'. c M 11 ~ &. li .:-12.0 aCONTROL OFJMEASURING" -lPAGE f:12-4 I-
- l-SECTION
~ .lDATEE6/10/83: 1l ; 1,:;p ~ _.i. L1 -l =AN0; TEST EQUIPMENT: '[: .I cy 4 y
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l-1 I I .l 13.0 HANDLING STORAGE AND SHIPPING l ,, 3 l 1 t i l l l 13.1 SCOPE I I I ll 1 l Activities for the handiing, storage and shipping, including cleaning, l packaging and preservation uf materials and equipment are to be performed l in accordance with established instructions, procedures or drawings, to l lpreventdamage,deteriorationorlossoftheitem. Activities are to 'l comply with the provisions of Regulatory Guide 1.38 rev. 2 unless l otherwise noted in Table 1. I l 13.2 GENERAL I i l 13.2.1 l 1 Instructions for preservation are to be provided for items subject to l deterioration or damage through exposure to air, moisture, or other l environments during fabrication, processing, assembly, and interim l storage periods. Items are to be cleaned, preserved and packaged as-l (] required to preclude deterioration and prevent damage. When maintenance l of specific internal or external environments are necessary, they are to l-be included in special packaging instructions and maintenance procedures. I I I 13.2.2 I I l l I' Procurement documents assure that any special cleaning, preserving, l l handling, packaging or shipping requirements for purchased material or-l equipment are-taken into account. I I I 13.2.3 I I I I l For critical, sensitive, perishable or high value-articles, 'l recommendations for their handling, storage, packaging,: shipping and l . preservation are to'be requested from the supplier per the procurement I -l q j '[' 'l l A l-TOPICAL REPORT lREV. 6-ll l 13.0 nHANDLING, STORAGE AND. IPAGE_ 13-1 I -l _ .P-. ~l 10 ATE 6/10/83 l- -l-SECTION: l L. l SHIPPING
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.I i I I
.I I l l l documents and furnished to the plant prior to or upon receipt of the item l ^ I I at the plant. .V l I I I l 13.3 SHIPPING CONTROLS l l l13.3.1 l l l Shipping requirements are to be specified in the procurement documents. l Suppliers compliance to these requirements are to include controls to l l assure that items are complete and assembled as required; items have been l preserved and packaged in accordance with the' procurement documents; I items have been marked and identified in accordance with specifications l and procurement documents; items have been loaded for shipment in such a I manner as to prevent damage; and required documentation is complete and l furnished in accordar.ce with the procurement documents. l I I I I I 13.3.2 I I I Special nuclear material and sources are to be shipped and stored as g specified in the AP&L operating license and other appropriate regulatory g -l documents. The Health Physics Supervisor is responsible for assuring l 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. l that special nuclear. material (SNM), as defined in plant procedures, are l shipped, stored and handled per these requirements and plant procedures. I I I 13.4 RECEIVING I I I I I i 13.4.1 l l I l_ l Materials and equipment are to be received at the plant per-plant l l procedures and subjected to a receipt inspection in accordance with l Section 7 of this manual. As part of the inspection activity, received. .l I I I l _ n)' 1 -A~ l TOPICAL REPORT lREV. 6 l ( 1 l l l I P l IDATE 6/10/83 1. I -l SECTION: 13.0 HANDLING,. STORAGE AND lPAGE 13-2 l l_ L l-SHIPPING I l 1-1 I I
W 4 '. l - l n l l ~ l.-materials'and' equipment'are to be inspected for damage, deterioration, l ~ ~ ' cleanliness and proper identification and markings per plant procedures p l-for' receipt. inspection. l -. l I ,s i. l c 1 13.4.2 l I I l~ l I Results of the receiving inspection and disposition of the material or l equipment are to be documented on receiving inspection records. l l Nonconforming items are to be handled in accordance with plant procedures l l -and Section 15 of this manual. l l 13.5~ STORAGE CONTROLS i l l l13.5.1 l l l lMaterialsandequipmentwhichhavecompletedthereceivingprocessareto I be stored based on the classification level of storage specified on the l procurement documents or related design documents.
- 'o l13.5.2 l
g 1 l-l l Storage,controlproceduresaretobeestablishedwhichinclude,asa i~ l minimum, provisions -for-the following: controlled access and usage of l the storage area; cleanliness and good housekeeping controls; fire I protection; protection.from environmental hazards; segregation of l lI : hazardous materials; and control of those items which have a specified I I 1 I shelf life. I f I l l ,l 13.5.3 -l 11 l. l Ll l ' l = Only items which have compl.eted. the receiving -process.are to be placed 'in' l- ~ ' a controlled storage area. Records of the items' location laresto be -l. -- l. provided by the. Materials Management Supervisor (see paragraph 113.3.2 for - ,I ~
- f. control ~of radioactive: sources and SNM) to identify those items currently-L 7;
l_ (, .l - A; -l TOPICAL REPORT. l .i l lREV. L6' /l b i l P .1- . l 1&. I'SECTION: -13.0 HANDLING,: STORAGE AND . lDATE. 6/10/83. l' lPAGE. 13-3
- li
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.. l-L; SHIPPING l ' l' l-l -- l J T / o n h g y-- 9 gr .i,, c--- 7 p .m ,a. 4 e,,-,. g
l I 'I I ~l ;in storage andito facilitate _ inspection and maintenance planning. l Is'suance' of items from storage for installation or use are to be j' 1l documented and controlled in accordance with plant procedures. l - l -' I I I i l 13.5.4 l -1 I I l l Items. identified as requiring maintenance during storage are to be l main'tained in accordance with a documented maintenance program. 1 l l13.5.5 l l l Storage areas are to be monitored by individuals responsible for the l storage areas so that the integrity and security of-stored items is l . effectively maintained. Inspections and examinations under the_ control ll of the Manager, Nuclear Quality Control are to be performed and l ~ . documented on a periodic basis to assure that the integrity of the-items l and their containers are being maintained. Periodic audits under the I control of the-Quality Assurance Manager are also performed to assure-l compliance to-storage requirements. l -l l_ 13.6 HANDLING CONTROLS '1 l I l-1 I p l '13.6.1 l -l 1 I I l Special handling requirements are to be specified in the procurement l-document's and plant procedures to protect the quality of items: .l 'susceptable to handling damage. Special tools and' equipment:are to be l provided to_handl'e these items and are to be controlled and maintained'- I I .l: per written procedure ~ to as'sure safe and adequate handling. l ~ I 1 .g l l 13.6.2
- l
- l I
I 4
- l Special
- handling tools.and equipment are to be. inspected-and tested at~
1, .l specific times iin.accordance with written-procedures. to_ verifylth'at the. l 'I O-I~ P -.
- 1.;SECTION: :13.0-HANDLING,:STORAGEfAND lPAGE. 13-4_
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-i i- ^A i ^ TOPICAL' REPORT lREV.. 6, lL l 1-(DATE' 6/10/83 -l 'l_ l ,LL Jl~ SHIPPING I l
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+.o +-- e,, 4 a.-- + r p n m 1 I I l l ha'ndling' tools and equipment are adequately maintained. Inspection and l' -(] test status of these handling tools and equipment are to be controlled in 1 -accordance with the applicable sections of'this manual. l 'l l I I I l l l l l l l 1 l l l l 1. I I i I l-1 l i I I I l l l I I 1 I i-l- l I I ^ l l I I I l l 1 O l l l l l l l - l l ' l I I l l i I l_ I l I -l l 1 l l - l I l 1. I I l-l l I l. - l 1 I l-I I l - l - l .I l: I-l -l . l '. A. . l: TOPICAL REPORT .lREV. _ 6: I- ~ l -- .P' i l-lDATE' 6/10/83~ l l I-SECTION: 13.0 HANDLING, STORAGE AND --IPAGE-13-5 ' I: ' l L' I . SHIPPING l I l-l l-g. s y r-, m.-. W T-e 9 n- - -,, 1 y 9 p-gy.q. p
1 I i 1 l ~14.0 INSPECTION, TEST AND OPERATING STATUS l fm l' I i~) I . SCOPE I l 14.1 l l l l l 1 14.1.1 l l l l' l l The removal from service, inprocess status and return to service of l equipment, components and ' systems for maintenance, modifications, repair, l l test or inspection is to be controlled per established plant procedures. l lThesecontrolsaretoassurethatplantpersonnelareawareofequipment, l l structure or system conditions and to prevent their inadvertent use l lunlessclearedbyoperationpersonnel. l ^ l l l14.1.2 l I l Maintenance activities are to be performed in accordance with an I j l established maintenance program to assure that equipment, systems and l structures are maintained in a condition which allows them to perform their intended function. l l l l 14.2 EQUIPMENT CONTROL l l l I l l 14.2.1 l l 1 l l l Prior to removal of equipment, components or systems from service for l l maintenance, modification, repair, test-orinspectionactivities, -l 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 - l l affecting plant safety. l l l l l-1 l I I I l 1 -l-1 1 -l l l i O I l i i l A l -f0PICAL' REPORT IREV. 6 l-I P. I 'l 10 ATE ;6/10/83 I l SECTION: 14.0 INSPECTION, TEST AND lPAGE 14-1 'l I. L~ l OPERATING STATUS l _l' I I I l
7 +' -l l l l 1-14.2.2 I i I l-The _ status of equipment,_ components and systems during these activities l 1 is.to'be identified in accordance with plant procedures / instructions, l l 'which 'contain, as.a minimum, the following: l I l I l l -1) methods for control of equipment to maintain personnel and l reactor safety and to avoid unauthorized operation of equipment l. or--systems. 1 I I i I I 4' l 2) the use of markings or other suitable means to indicate the-l {_ status of activities being performed upon individual items. l' i' I Suitable means are to include identification numbers which are 1 1 traceable to records or the status of these activities. I g 1 I l 3) provisions for the identification of items-which'have I satisfactorily passed-the required activities. In cases where l required documentary evidence is not available, the associated { l ~ equipment or system is'to be considered nonconforming and handled in accordance with Section 15 of this manual. I l~ l 4) provisions for. independent, verifications to ensure that I l necessary measures (locking or tagging) to secure and identify. l 4 l g equipment or systems in a controlled status,- have been l{ + I implemented correctly. l l-I l-14.2.3 .ll l 1 l 1 .l. I When entry'into a. closed. system is required, control measures are W ba l f established to prevent entry of extraneous' material and to assure that Ll' foreign material isl removed before.the system is reclosed. l l l- .'l l I !l l' Ll1 'l ) . l-O 1 l 1 1 i ~ l- 'A- ,i TOPICAL REPORT .. l REV. _ 6- 'l ll P-il SECTION: 14.0 INSPECTION, TEST'ANO. .lPAGE.14-2 l_ .l TIDATES6/10/83-il. l. cle _ L( l ~ 0PERATING STATUS' '1: -l ~ .. l .I l l. -- n
l-I l-I i 14.2.4 I l l (w) I l l During maintenance or modification activities, certain portions of I systems, as'identifie'd in plant procedures, may be subject to potential I contamination with foreign materials. To prevent such contamination, I control measures, including measures for access control, are to be l l established. Immediately prior to closure, an inspection is to be l conducted to assure cleanness and the result of such inspection is to be l l documented. I l-1 I I l 14.2.5 I I I I I l If temporary modifications (such as temporary bypass lines, electrical I jumpers, lifted electrical leads and temporary trip point settings) are l l 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 the Shift Supervisor, identifying the current status of such temporary I modifications. Temporary modifications are to be verified by individuals l l independent of the group performing the activity and documented to assure l l the required actions are taken to return -the equipment or system to its l l original operating configuration and status. l 1 l l l l 14.2.6 I I I i 'l l l When equipment or a system is properly identified as being ready to be i returned to service, the appropriate Shift-Supervisor is notified and I initiates the proper operation procedures. Testing of the equipment or l - system for functional acceptability is to be in accordance with l l Section 11 of this manual and documented to verify current status of the .I item. l l ._ i .I 1-l I l 1 l l I I I I I 1 -l-I - ( ') l I I i ~l .A l . TOPICAL REPORT IREV. 6 l l-P- 'l IDATE 6/10/83 l l I SECTION: 14.0 INSPECTION, TEST AND lPAGE 14-3 l- 'l .L-l OPERATING STATUS I I I 'l I .I
-l i I I l 14.2.7 l l l (-) l I l Equipment, structures and systems found to be nonconforming as a result i of an activity are to be handled in accordance with plant procedures and l l Section 15 of this manual. 1 I I I I l 14.3 MAINTENANCE CONTROL l l l l I i 14.3.1-I l 1 l l l In addition to the requirements and controls identified in paragraph 14.2 l of this'section, a maintenance program is to be planned and scheduled I through the Maintenance Manager to assure that the safety of the plant is l l not compromised nor the Technical Specifications violated. l Maintenance l activities are to be performed per plant procedures and instructions and l lconductedinamannertoassurequalityatleastequivalenttothat l specified in the design documents, material specifications and inspection I requirements. As experience is gained in operation of the plant, routine l 1 maintenance may be altered to improve equipment performance and l l procedures for repair of equipment are to be improved as directed by the g. I Maintenance Manager. l l l l l l 14.3.2 l 1 I l l l A preventive maintenance program, including procedures and instructions l lforsystems,structuresandcomponents,istobeestablishedand I maintained under the Maintenance Manager which prescribes the frequency-l and type of maintenance to be performad in order-to preclude equipment 'l malfunctions. The program is to be implemented by qualified maintenance -l 'lpersonnelinaccordancewithwrittenproceduresandinstructionswhich -l specify the work activities, acceptance requirements and the control .l l22asurestoassure'adequatequality. When equipment malfunctions occur, l l~ the cause is.to be promptly determined, evaluated and recorded per plant I procedures and Section 16 of this manual. l .I -l I l l A. -I ' TOPICAL REPORT lREV. 6 l l P l 10 ATE. 6/10/83 -l-l l SECTION: ~14.0 INSPECTION, TEST AND lPAGE 14-4 l l .L- -l OPERATING STATUS-l l I I I ._. I
~ l 1 l l I 14.4 '0VERALL PLANT STATUS l -l I gq 4s i I I 14.4.1 l l-1 I I -l _The Shift Supervisor is provided' sufficient knowledge of the overall l l plant status of equipment, structures and systems to control operation of l l the plant in a safe manner. The Shift Operators are to maintain a ready I ~ reference of plant systems, equipment'and components alignments, as well l l as a status board summary of their conditions. I I I I I l 14.4.2 4 l I l l 1 l-The turnover of duties to personnel on succeeding shifts 'is conducted in l accorda: ice with approved plant procedures. These procedures include I documented turnover action appropriate to the duty station acknowledging I the status of the nuclear power plant, its structures, systems and f I components (including design changes / modifications which may affect the I performance of-their duties) and transfer of authority. O l l I I I I I I l l l l l l 1 l l l- .1 I l l I I I l l l 1 I .I l 1 I l l I i 1 l l i l l -1 l I l l l - o
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4 i i I A I TOPICAL REPORT _ lREV. '6' I-l P .l lDATE 6/10/83 1 I 1 SECTION: 14.0 INSPECTION,_ TEST AND .lPAGE 14-5 'l l I L-l .1 I. OPERATING STATUS .l l-l l, ~
y I' I ~ -l. 15.'0 NONCONFORMING MATERIAL, PARTS AND COMPONENTS l .l l -l I l_ 15.1-SCOPE I 1 I I I l -Nonconforming items are to include materials, parts, components, I processes, documents and as applicable, services (including computer I codes) that do not conform to applicable regulations, codes, stan'dards, I ~ specificatio'ns, drawings or licensing documents. Nonconforming items are l 1' to be' controlled in accordance with approved procedures to prevent their l l inadvertant use or installation. These procedures are to contain l measures to assure the-prompt identification and notification, l ' documentation, segregation, technical review, disposition and I verification of a noncoilforming item. 1 I l l 1 l 15.2 GENERAL I I I l 1 -l-15.2.1-1 I I l. l g l It is the responsibility.of each individual.to identify a nonconforming l g cond'ition, whether related-to a product, process or documentation, a'nd to ~ l-report?it to their co~gnizant supervisor for review and concurrence.- The. .1 initiator'is to document the nonco'nformance on.a Nonconformance Report l-(NCR) unless the nonconformance is determined to be a' technical l specification. violation and/or: reportable to the NRC. See paragraph'15.3 l l :for reportable nonconformances. l l l l 'l : l 15.2.2 1 'l l-I 11 l Nonconforming items are to be.. tagged with a hold tag,-or otherwise -l identified per plant procedures, to prevent inadvertant use or l installation of'the item. Nonconforming items-are to' be segregated from l. ' acceptable' items.unless they are currently' installed or their size,- l ~ 1-weight, configuration, etc.', makes.it impractical to move to'a segregated l: I l,- 'l-
- l c
I-1
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D~ - -1 I i 1: l: :A. I TOPICAL REPORT 1 lREV..6 ll l _' .- P. l .- l DATE 6/10/83. l I 'l SECTION: ;15'.0 NONCONFORMING MATERIAL,- .lPAGE 115 1 l-L 1 -PARTS AND COMPONENTS l 1 -l l.' .l-l,
l_ s 4
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l .I' I l. area. Hold tags are to remain on the. item until the disposition is l l complete per plant procedures.' l I
- l 15.2.3 i.
I {.. Nonconformance Reports are 'to identify: the group responsible for .1 ~dispositioning the nonco'nformance. The assigned individual within the 1 4 l g responsible group is to evaluate the nonconformance and confer, as l l appropriate,'with interfacing groups to determine its cause and l p recommended disposition. The disposition, which may be reject, rework, l .1 ' repair or use-as-is, and the corrective action taken to'~ prevent l recurrence is to be documented on the NCR. l != 1 l 1-15.2.4 l-I f I The initiator of the NCR and his department head.are to review the I g I _ disposition for acceptance. prior to implementing corrective action. If I _they cannot agree with the assigned individual on the disposition, the. [ l plant General Manager is to decide. For a repair or use-as-is I
- disposition, a cognizant engineer knowledgeable in the design-I requirements-for the affected item is also to review the NCR for l
~ j concurrence of the dispo'sition. Written justification for th'e design I change, repair or deviation that has been accepted is to be documented to .I denote the'as-built condition and is to be made a part of the NCR. l 1 I l15.2.5 f I ' ' -l - l- {
- The acceptability of rework or' repair of; materials, parts, components, I
- g l
1 systems and ' structures are to be verified by reinspecting -the item 'asi originally inspected or:by a method which is at least equal to the. l-3 l original inspection. method. lThe'~ rework and repair inspection-records _are.: l - to be documented and become part of the permanent records.for the item.- l'LUpon_ completion'of,the.correctiveaction,theManager,1 Nuclear. Quality j 'l ' I l >l-I l.
- j
-l-l. l . l l' A: .I 1 TOPICAL REPORT
- lREV.
6: .[; . l' P-1. .IDATE 6/10/83. . 1: l.- i&'. l.SECTION: 15.O NONCONFORMING MATERIAL,- lPAGE 2 - l. - 'L 4l ~ PARTS AND COMPONENTS. l l l-l.. sl l +<-,L,-. -,,-,,N,-n-...L,n
- aJn, s
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I l I l .'l Control is to verify completion of corrective actions in accordance with 1 - fj l-plantproceduresandifacceptable,closetheNCR. ~ l I l15.2.6 l I 1 -l. For ASME Code, Section III, Division 1 materials, parts and components l l dispositioned repair or use-as-is, the NCR is to be subject to review and I concurrence by the Code Inspector. l l 1 l15.3_REPORTABLENONCONFORMANCES l l l l15.3.1 l l l Nonconforming items or conditions which are reportable per the Technical l Specifications to the NRC are to be documented by the initiator and l forwarded to the Special Projects Manager so the appropriate report, per I plant procedures, can be prepared. l I l l 1 ( 15.3.2 I I l Upon disposition of the report by the responsible group the PSC reviews I the report for concurrence and possible assignment of additional I corrective actions and forwards the report to the plant General Manager 1 lforfinalapproval. l 4 l l 15.3.3 f I i lTheLRGOLicensingsectionistoberesponsiblefortransmittingapproved l l reports to the NRC within the time period specified in the Technical I l.SpecificationsandLicensingprocedures; I l I -l_ l 1 I I I l l 1 I I n I l -1 j l-l l _ l i A I TOPICAL REPORT IREV. 6 l l 'P l lDATE 6/10/83 ll I I SECTION: 15.0 NONCONFORMING MATERIAL, IPAGE 15-3 I I L. i ' PARTS AND COMPONENTS IL l 1 I I l
m, l I I 15.4' SUPPLIER NONCONFORMANCES l (3 l l 'l 15.4.1 I l-1 I I I Procurement documents are to contain requirements for the I vendor / contractor to identify nonconforming conditions to AP&L which I violate a technical or material requirement of the procurement document i and which results in a disposition of repair or use-as-is. All such I nonconformances are to be reported to AP&L for evaluations and I acceptance. The vendor / contractor is to document such nonconformances on I their applicable nonconformance report which is to be included in the l lfina1'documentationpackagesubmittedtoAP&L,inaccordancewiththe l l procurement documents. 1 I I I I i 15.4.2 l l l l I 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 l the nonconforming conditions have been properly dispositioned and l accepted by AP&L. I l l15.5 RECORDS I I l15.5.1 I I Upon completion of disposition and verification activities, the completed l NCR's, reports, and related documents generated to ensure proper i disposition and resolution of the nonconformance are to be forwaraed to I and maintained by the Document Control Center. I I I I i -l I I I I I I I l 'l I I I I A I 1: ' d l I l l l A I TOPICAL REPORT .lREV. 6 I .I P l-10 ATE 6/10/83 -l 1 1 SECTION: 15.0 NONCONFORMING. MATERIAL, IPAGE 15-4 1 1-L I ' PARTS AND COMPONENTS 'I I l-1 I I
s'
- 1-1
. l-I ,l:;15.5.2 I o l l I The Manager, Nuclear Quality Control is to maintain and issue a monthly I . report to the plant General Manager, identifying the current status of l l ' all.open NCRs for management review. I -l i I I
- l 1
-l i I l-1 I I I I I I I I I I I I I I -l I I I I I I I 1 I I I I i -l O l l-1 I I l-1 I I i 1 l I 1 I i l l .I l-l- I l- .I I I I I _I 1 I I l l-I. l_ l l-l' l -. I. -l l 1 _ l-I l' l l . A _- l TOPICAL, REPORT-lREV. 6 l' .I 1 i .I 'P' l IDATE:'6/10/83-I L i. I: SECTION: ~15.0 NONCONFORMING MATERIAL, lPAGE-'15-5 21 l L 1 PARTS'AND COMPONENTS I -l l l l-l 7, - 1
l I I I ~l 116.'0 CORRECTIVE ACTION l { j5 l I b I I i 16.1 SCOPE l I I I I l A corrective actions system is to be established to assure that I conditions adverse to plant safety, such' as failure, malfunctions, l I deficiencies, deviations, defective material and equipment, abnormal l l loccurrencesandnonconformancesarepromptlyidentifiedandcorrected. l In the case of significant conditions adverse to safety, this system is l ltoassurethatthecauseofthecondition'isdeterminedandcorrective -l l action taken documented and reported to appropriate. levels of management l I I l for independent review. g I I l16.2 GENERAL l l l16.2.1 l l l l When deviations, deficiencies, malfunctions or other abnormal occurrences l [] or conditions are' encountered, they are to be reported to responsible I g authorities for review and disposition in accordance with Section 15 of I this manual. l I I -l 1 I 16.2.2 l l I ~l l l Cognizant supervisors are to review discrepancies discovered during the l lcourseofstationoperations,andinthecaseofsignificantconditions 1 adverse to safety, initiate action to identify their cause and take i l necessary corrective action to prevent their recurrence.. Corrective I dction measures to resolve the discrepancies and to prevent their I recurrence are to be documented'in accordance with Section 15 of'this 1 manual. l l l 1 I I l 'l l I I l' I c I I L) I 1 I l l A 'I TOPICAL REPORT. [REV. 6 l .I P. l 10 ATE 6/10/83-l 1 1 SECTION: 16.0 CORRECTIVE ACTION IPAGE 16-1 I .I L i I I l-1 ~ I-l- g 3 M Y
- T
l.- l 1 I 'l L16.2.3 I l l Ce I I l The appropriate plant department-head is to review recorded I 'l g nonconformances and may.specify the need for additional corrective I g I action. The plant's General Manager is to review the monthly status l I I ,g reports concerning "open" nonconformance reports and takes appropriate g -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 I technical support groups at the plant and/or LRGO to evaluate the l l nonconformance for final disposition. I l l I I l 16.2.4 I I I I I l Adverse quality or safety conditions discovered by QA or QC personnel 1 during their document review, inspection, audit or surveillance l l activities, which appear to be of a repetitive nature, are to be i i 1 .g documented on an appropriate report form in accordance with applicable QA l and_QC procedures. l I I l 16.2.4.1 I I I I I l The responsible organization to which the corrective action document is 1 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 at Lion' initiated to I determine cause and to prevent recurrence. 1 I l l l l 16.2.4.2 1 I l l l l The response is to be evaluated by the initiating organization (QA or QC) l-ltodeterminetheadequacyandcompletenessofthecorrectiveaction-l l l 1 l l I I I y i I A l TOPICAL' REPORT REV. 6. l. I P l -IDATE 6/10/83 l l I SECTION: 16.0 CORRECTIVE ACTION IPAGE 16-2: I I L I I I .I I I i
] n j I I l-1 I commitments. -If the response is acceptable, the initiating organization l is to perform-follow-up action to verify implementation of the corrective l l action commitments, document their findings and when acceptable, close I -loutthecorrectiveactiondocument. I I l16.2.4'.3 l I I .lIf.theinitiatingandrespondingorganizationscannotagreeupona l l resolution, it is to be referred to the next level of management for l l resolution. 'The General Manager at the plant'and the Senior Vice l l President, Energy. Supply at LRGO are to have the final decision regarding l l resolution of QC and QA initiated corrective action documents, l. l respectively. l-I l I I i 16.2.5 I I I I I l When vendors furnish products or services that do not conform to the I requirements of the applicable purchase contract and, in'the opinion of I the Manager,. Nuclear Quality Control, the vendor warrants consideration g for reappraisal, the Manager, Nuclear Quality Control is to submit a I vendor reappraisal request to the Manager, Quality Assurance for -l determination of~ action to be taken. Results of.the reappraisal, 'l l together with-a request for specific corrective actions, are to be I transmitted to the vendor. If the ve'ndor does not improve his quality. l i l assurance system and products as requested, the-Manager, Quality l ' Assurance is.to remove the vendor from the Qualified Vendor List (QVL) in l _accordance with departmental procedures. .I I ~ l, l -l-l 1 I 'l 1-I- l-l' I' 1 I .I 1 .I I l l~ l .l I 'l ~h l 1-1 I l A. El I .6 1 ~ TOPICAL. REPORT _ 'IREV. PL .I IDATE~ 6/10/83 ~,l J ~l_ &~ l SECTION: 16.0.: CORRECTIVE ACTION lPAGE.-16-3 l-
- l-L, i
Ic I
- ,.l-l-
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y c ? i f ' 'l .z. .1 A I + 1 1 y 'e : l - 16.3 SIGNIFICANT:CONDITICNS 4 I e. l-l [ L, d.. l ~ Q [qc yl .16. 3.1 ' l ' I ' jl ;; l
- j'
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l { 'l Significant conditions are to, include, as' a minimum, the following: I il I i 'l I i, I ~(1) Conditions that have a direct advers.e affect on the safety of I ~ ^ 1 >t I l the plant or personnel. 4 l 1 l (2) Conditions that have caused the uncontrolled release of I f -l~ radioactive materials (liquid, solid,, gaseous or air ~ l l l l I particulate):to the environs. l- { (3)j Tren'ds. indicated by nonconformances Wh'ich could lead to unsafe I plant operations. I l-(4) Any condition the plant's Genera'l Manager considers'to be'of l g l l
- major consequence.
I (I I e I l' c
- l ~16.3.2 l
1: i-1 l 1 \\ I When'significant conditions adverse:to safety are discovered,1the' q responsible supervisor and management personnel are to evaluate the l-
- 1. condition and determine if' it'is; a. reportable /ccdurrence. -Reportable-
'l '. occurrences'are to be handled as described in Section 15 of this; manual ~ ~ ll 'and are'to be, submitted to the PSC and SRC for review. l l 1 .I 16.4 VERIFICATION. ~l 1 l. ~ I I 'l i -l Verification by surveillance or audit of-the effective implementation of l' t g ~ 3r v ic i'
- Lcorrective actions is to be periodically psrformed ~and documented.by-g-
1:L ,1 4 l'-Quality Assurance personnel. Audits are to be performed-infaccordance; l' g y l g with Section^18 of;this' manual. .. g. 'g t' l: .l 1 l- _ -- l l ~ l .l / j' I
- l l-1 t.
l-l_ g. ?' .l-i i Y al JA=. .l -LTOPICAL1REPOR7 + ' .i g-lREV. 16 [. .l- .P. .li .l lDATE 6/10/83 ll. .h. L l' l.SECTIONi 116.0 CORRECTIVE? ACTION
- lPAGE 16-4
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y l i l l 1 - 17. '0 QUALITY-ASSURANCE RECORDS I i I n .l l J - l 17.1 SCOPE I l' I 1 I i 17.-l.1 l l ' I 1 I h l Documentation covering design, construction, procurement, fabrication, l I i l inspection, maintenance, nonconformance and corrective action, test and g l' audit activities is to be filed and stored to provide objective evidence l I l 4 l of. quality-related activities and to assure the ability to reconstruct l l significant events. Control of records is to be in accordance with l I Regulatory Guide 1.88, Rev. 2 (10/76) unless otherwise noted in Table 1. 1 .l_ g I I l [ 17.1.2 1 l I -l 1 ' Quality assurance records are to include operating logs,.results of I l g I reviews, inspections, tests, audits, material analyses; monitoring of I l l [ work performance; qualification of personnel, procedures, and equipment; g j l historical drawings, specifications, engineering reports, calculations, I l procurement documents, calibration procedures and reports, nonconformance I reports; corrective action reports, correspondence and related records r,. r j g l pertinent to quality as defined in plant procedures for records g I management. 1 [a I l -' s l l l 17.2' RESPONSIBILITY 4 .l ' /. l j i l -l I 17.2.1 ,e 1 l I -1 [. I: The Plant Administrative Manager issresponsible for the establishment, a 'l ' implementation'and maintenance of.the recorf. m wagement program to be g-Q. l~ used throughout the operational' life of t s pF end for ensuring that q [f documentation retention requirements.cotyly vnui applicable technical ID-l specifications, codes.~and regulations. .I .I; .l 1 'l 1 l -h l 1 A'j ' -l l-I' -l
- l A
l: m. TOPICAL REPORT lREV. 6 1-o
- l_
'P l lDATE -6/10/83 .I g M,. _.l. L< 1 -I -l-ll v
- I;SECTION: 617.0. QUALITY ASSURANCE. RECORDS l PAGE - 17.-1 l
n . l -l - r p g m di L~~ ~
c. 1 1 'l-l !! 17.2.2L I 'l ~AP&L personnel, other than plant staff, and.outside -firms that perform I =l. l 'l -work ~on the plant in the areas of design, procurement, maintenance, g l l ~l;; modification, testing, quality-assurance and special nuclear materials _ll are to provide documentation / certification records to the plant for I g l-subseque'nt storage and retention by the Plant Administrative Manager. l .I I 'l 1 -I -17.2.3 I
- I~
l I' l. l'_ Quality Assurance personnel 'are to periodically audit quality-related I l l records and. records filing and storage procedures to assure that the l g I ; records management program is being properly implemented. Audits are.to l I 'be performed as outlined in Section 18 of this manual. -I g g 1 I ~17.3 DOCUMENTATION RETENTION: I' l g 17.3.1 Lifetime Ouality Assurance Records ' l l .g. TO l17.3.1.11 l l l g I' lLifetimerecordsaredefinedasthose'whichmeetoneor~moreofthe I g i following criteria: .1 I I I ~ 1-1 (1) Those which would be of significant~value:in-demonstrating -l. l l capability for safe. operation. gi g 1 (2). Those which.would be of significant-value.in maintaining, 1: l - reworking,: repairing, replacing or modifying.the-. item. l. .~(3) Those which would be of'significant value'in' determining the. 'l ~ .cause 'of an > accident ~ or. malfunction ~'of 'an item. ~ I; (4)E.Those which' provide required baseline' data for..inservicel $1 _ ~ finspection. 1
- l-
~l 1:. s 'l ~l il: 1: l. [h-: . h. l' (l- .g. .l (A; cl TOPICAL REPORTL ?lREV.;:6
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u E ? l:' P-. l i lDATE 6/10/83: ~l. l !!1SECTION: ;17.0-QUALITYLASSURANCE!RECORDSL
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llT L L: lt IPAGEL17-2<. l: .l l Q - ( l l' - j.1 m, ,g-g -. s .p' 4 t ". j _,3 4 .i
I I I I 'I 17,3.1.2 l b; l-Lifetime quality-related records are to be maintained for the life of the l 'l l l particular item while it.is installed in the plant or stored for future l' use as prescribed in applicable-plant procedures for document retention I I i l and disposition. l -I l l l l 17.3.2 _Non-Permanent Quality Assurance Records l l l l l l 17.3.2.1 l 1 I I l l Non permanent records are defined as those which meet all of the l I following criteria: I l l l l l (1) Those of no significant value in demonstrating capability for I I I l safe operation. l I (2) Those of no significant value in maintaining, reworking, I I I l repairing, replacing or modifying the item. l ' f). I (3) Those of no significant value in de+.ermining the cause of an I v l l accident or malfunction of an item. l l I (4) Those which do not provide baseline data for inservice l I l inspection. I g l l l l 17.3.2.2 l I l l '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 l 1 l.specified periods.as directed by the applicable. plant procedures.for. l l document retention and disposition. l .I l -l I l 17.3.3' l l l l-l- l Categories of permanent.and non permanent records to be maintained and I l~ l .l their. appropriate retention periods are. described in plant procedures. l l i h' _I 'l C/ l 1 l-l i 'A 1, --TOPICAL REPORT .lREV; 6
- 1.
.I - P. - I 17.0 QUALITY ASSURANCE RECORDS-lPAGE.17-3 1- ~l ~l:SECTION: IDATE 6/10/83. I -l L. -l i 1: l 'l I _dl
I-l 1 I-1 17.3.4- -X l I I () -l l 1 The Manager,. Nuclear Quality Control is responsible for receiving, I ~ 'l l l inspecting and authenticating such documents as directed by plant l 'l procedures for turnover of quality assurance documents from suppliers to l 1 -AP&L. When' approved for' receipt by Quality Control, such records are to l l g
- 1. be transmitted to the Plant Administrative Manager for filing and 1
I -1 l storage. l l l 1 l l 17.4 STORAGE l l l 1 I l 17.4.1 l .I I I l Permanent records are to be microfilmed and stored within a controlled I g I area at the nuclear power plant per plant procedures. A duplicate set of l I l microfilm is also made and stored at a remote location. I l l l l l 17.4.1.1 l l l For storage of film and other special processed records, humidity and ~ l I temperature controls are to be provided to maintain-'an environment as 1 ll - recommended by the manufacturer and plant procedures. l g I - l -. 'l l-17.4.1.2 -l g i l l l A list.is to be prepared by the Plant' Administrative Manager designating l l those personnel who have access to the storage files. l l l-l 1 1 17.4.2 1- .,I l l I l' Plant storage systems _ are to provide for.the ' accurate retrieval of l l' l information.without undue delay and be sufficient to' control and account. yl l'.for records removed from'the' storage' facility. l l .l-I l 'l
- l h
l l l' A .I
- c. TOPICAL 1 REPORT.
lREV. 6: 1- .I' .P 1 .17.0. QUALITY ASSURANCE. RECORDS ~ IDATE; 6/10/83 l-1. L&: 1: SECTION: lPAGE- '17-4 .I 'j.
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re - l-l l l- 'I 17.5 RECORDS INDEXING AND RECEIPT CONTROL. I J l l; l. zlTI17.5.1' l I I I I l.' Indexing' methods and systems for quality-related records are delineated-I ~ el - .I i l in' plant' procedures for plant records management l -l
- l-ll '17:5.2-l l
l l l ~ Records-submitted for. storage in either lifetime or temporary files: are. l -- -l l 'l td beLsubject to the following requirements for receipt control: l l l I I I (1) Establishment of a records check: list d'esignating the required l I l l quality-related records. ~ g ~I (2) - stablishment of a system designating criteria for' document l I I l-inspection to assure that records are accurately completed, g I legible and received in good condition. -l - 1 I l ..(3)_ A file system to indicate which quality-related documents have g I been received. I l' L -l 17.5.2.1 -I i I -l' l.- l' Implementation.of receipt control requirements for storage.-is the ~l: I ~ l l responsibility of the' Plant Administrative Manager. g. ~ l .I f:17.6FINALDISPOSITION j I I r l l The plant'Administrativs Manager?is responsible forl disposal of l g I ll quality-related recordsLin accordance with plant procedures for document .1 lretentionlandLdisposition~,whichpermits? periodical-purgi_ngofrecor'ds p Ll iretained past their: required' retention date. -l~
- t. -.'
l- -l-g l l s m _l; .I -l. g. o i l: -l-La - 1. l + +
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. TOPICAL REPORTc ilREV. f6
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'? 14 P lL l0 ATE.'6/10/837 ,li 'aJ-ll: ~ ll SECTION: gl7.0. QUALITY: ASSURANCE RECORDSt 'IPAGE::17-5: . l. m v nq g : L:
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l. i -l. I l 18.0 AUDITS l n .I _ l l: 18.1 SCOPE. l I I -l I .I 18.1.1 I I I i 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 performed in accordance with written procedures, plans and checklists and l are to conform to the applicable portions of Regulatory Guides 1.144,- l l. rev.1 (9/80) and 1.146,- rev. 0 (8/80), unless 'otherwise noted in Table l - l 1. l I I I I l-18.1.2-l l l l l l The audit program is to include provisions to determine the compliance l: 'lwithandeffectivenessofthequalityassuranceprogram.incontrolling l structures, systems, components and activities in accordance with the l= 'I rules set forth in the codes, standards and' regulations identified in the l l Introduction of this manual. _l l I I l 18.2 AUDIT PERSONNEL i -l-I -l I l 18.2.1 I l-I l' l l .l The Quality Assurance Manager is assigned' auditing responsibility within [ I l this quality program and is responsible fo.r the-selection'and assignment l l. l: of auditors. Auditors are to be independent of any directLresponsibility -l I for performance of the activity 'which is to be-audite'd and are not to I _I l .l -report to a management. representative who has direct responsibility for -l. I~ the activity being audited. I -l- -l-1 1 l -l ~ l' l- - l 'l l I /7 'l: l l .6~ l -l 'd: -l -. ; A-. 1 . TOPICAL REPORT lREV. l-
- P. :
.l. l' l SECTION: 18.0 AUDITS.
- lDATE_ 6/10/83'
-l: lPAGELJ18-l' 'l 11 .L- -ll
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x: ^ g l l '18.2:2. I l l: g l 1 Auditors assigned; auditing responsibilities are'to have experience and I. training commensuate'with the scope, complexity and/or special nature of l l ;the activities-to be audited. When audit assignments.are made, l -considerations-'are given to special abili_ ties, specialized technical l l. training,3 prior. pertinent expertise, personal characteristics, education 1 and capability. 'If no one'within the'QA0 meets these prerequisites I completely,1 technical specialists are to be used to assist in the 1
- auditing of the activity.
Technical specialists are to meet the l l requirements of paragraph 18.2.1 of this secti.on. l. l l I I i 18.2.3-I 1 p-I l-1 I Audit personnel are provided appropriate training to assure their l lcompetenceforperformingtherequiredaudits. Proficiency'of audit l l personnel is maintained by one or more of.the following' methods: I l .I I ~ I (1)- Regular, active participation in the audit process. I g (2) ' Review and study of codes,. standards, procedures and l~ instructions. j-l '(3) Participation in training or orientation programs. l. l l l18.3AUDITSCHEDULE I I I 18.3;1' I Il' I l-l Audits'are to b_e performed on_a planned and periodic basis in accordance h
- l !with an-audit schedule. ' Audit schedules are to be prepared at the l
beginning of.each year by'the QA0 and approved by!the Quality Assurance. l: Manager and SRC. L.l l il-l l l-li I; .I I _l. . l.- - ?l. l .l.< l p- -l
- Ai.
li ' TOPICAL: REPORT <lREV. .6 ' l! -J .I'
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?I> IDATE.6/10/83 1 ~, }l1 1 .18.0' AUDITS IPAGE L18-2: .l: + l)SECTION: 4 .I s - " L -l 'l
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,_ n . ~ - -.. ~ 'lc l 'l; l ?l' 18.3.2 c._ l - idL
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~' l ~. Au'dit schedules assure that as a minimum, the following areas are l -lLaudited,under.thecognizanceeltheSRC,attheindicatedfrequencies ?, I within AP&L: l 1-I .1-l p I =(1) The conformance of. facility operation to provisions contained l l-within'the lechnical Specifications and applicable license l F l conditions at least once per 12 months. l l (2) The performance training,' qualifications, and retraining of all l j l members'of thel facility management and operations staff, and-l 7 the performance, -training, and qualifications of new members of. I the entire facility staff at least once per 12 months.- l l (3) -The results of all actions taken to correct deficiencies i l occurring in facility equipment, structure, systems or methods 1 [ of operation that affect nuclear safety at least once per six I months. (A portion of this activity is performed as a part of l I 7 each internal quality audit.). l j (4) The Facility Emergency Plan and implementing procedures at-I; [ g least once per 12 months. g l (5) The' Facility Security Plan and implementing-procedures atLleast l l once per 12 months. .g i~ l (6) Any other_' area of facility operation considered appropriate'by-- l ] the SRC or'the Nuclear Operations Vice' President. l i (7) The Facility Fire Protection Program and_ implementing 'l l procedures at-least once per 24 months. I -l-
- l: 18.3.3-l' 1
-l F ht . I 1 - Audits.of vendor / contractor activities.are to be. scheduled as identified I g 'l.~in Section 7, paragraph 7.3.3 of~this' manual. These au'dits:are to- 'l r 3
- - evaluate and~ verify their' quality assurance program, procedures and r
l !l 4
- l l
I .l~ l .I b: l .I l- ~' .l A- .l 1 TOPICAL REPORT - tIREV. 6:.. ll' P _ l .lDATE: 6/10/83. l i~ l 'l l SECTION: -18.0_ AUDITS ~ lPAGE,18-3 (l .l -L -l. Is+-. J ll -+%~ +- .- l ~' 1 ,.....,,.-.~,,.--.n~~.. ~ ~ - -. - -
irm ,g-.
- l I
=l factivities, to assure compliance with the procurement documents, and to l 77 verify they periodically.. review and-audit their suppliers quality l !l-.-assurance program. l -l 1. l l-l l 18.3.4 I I I 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 0 ~l assure that audits are.being accomplished in accordance with the 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 I I I I i 18.3.5 l l 1 I-I l Regularly scheduled audits may be supplemented, as required, to cover l lunforeseeneventsorchangedrequirements. l l 1 l18,4-AUDITIMPLEMENTATION-l O I 18.4.1 I I I l l l Audit plans and checklists are' to be prepared by the auditor and approved -l by the Quality-Assurance Manager prior to performing the audit. l ]Checklistsaretobeusedduringtheaudittoassurethat'all l requirements of the activities audited are addressed during the' audit and -l that'those procedures and instructions issued to control the' audited- .l activity are adequate. 1 .l -1 l. -l 18.4.2. l li l .I 'l ~
- l
.-l~ Upon completion of an audit, a written report is to-be prepared which l. I includes'at least the following; items: I I 1
- l -
I il l l- ' l-1- l l h l -l l l l' If . TOPICAL' REPORT: 'IREV. ~6 .l-l
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'l: P-&s. l_SECTION: 18.0' AUDITS. .lPAGE :18-4, 'l. 11. ~lDATE' 6/10/83-l I 1 L. .l; ~ l ,l l. -l-a -l. .- l a = - - 2 ~'
" - =
I l 1 I l; (1) Description of audit scope and date. l (2) ' Identification of the auditor (s). .l. (3) A summary of audit results. l (4) Details of nonconformances or programmatic deficiencies. l (5) Recommendations for correcting nonconformances or improving the l -l' . Quality Assurance Program, as appropriate. I I i 18.4.3 I I I l l lDeficienciesidentifiedasaresultofaninternalauditaretobe l l recorded on an Audit Finding Report (AFR) by the auditor and issued to l the department head responsible for the area audited for corrective 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. l I Appropriate follow up including re-audits by the assigned audit group is I l l l conducted in the deficient areas to verify proper anditimely l ~ implementation of corrective action commitments. Follow-up actions are l q(s l to be documented on the AFR. l l l l l 18.4.4 l l 1 I l l l Audit reports pertaining to plant activities are to be independently l l reviewed by the PSC and.the SRC to determine if additional corrective I I I l actions need to be initiated to assure continued. safe operation of the l-I plant. Audit reports pertaining to LRGO activities are to'be l I l l independently reviewed by the SRC. In addition to these reviews, the -l l audit reports are.to be distributed, as a minimum, to the Nuclear 1-1 ~0perations Vice President,-Quality Assurance Manager and appropriate I l l I levels of management having responsibility in the area audited to assure I .l l their awareness of the findings. l-l I l l. l- .l. l I I I l 1 h I l. l l l-A- l TOPICAL. REPORT lREV. 6 l ~ -l- -P-1 lDATE 6/10/83, l l' Ll SECTION:.18.0 AUDITS -lPAGE'.18 l l 'L' l l l =l' l l l ~
i I l l 1 l 18.4.5 l em l l l l '~' t -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. 1 Deficiencies are to be recorded on an AFR, and the audited organization l l is to describe actions taken to correct deficiencies and prevent I recurrence on the AFR. Corrective actions are to be verified by QA l l personnel and documented on the AFR. l l l l 1 l 18.5 RECORDS l 1 I l l l Written internal audit reports, including checklists, AFR's and related i I documentation supporting the follow up activities are to be forwarded to l l the Administrative Manager for-storage in accordance with Section 17 of l this manual. External audit reports are to be maintained / stored in the l l applicable vendor / contractor file maintained by the Quality Assurance l I Manager. l /7 l 1 l 18.6 NUCLEAR FUEL AUDITS I I I I I I Arkansas Power & Light Company delegates to Middle South Services, Inc., l a wholly owned subsidiary of Middle South Utilities, Inc., the l responsibility for performing those quality assurance functions necessary l to assure that its nuclear fuel is designed and fabricated in accordance l with regulatory requirements and accepted codes, standards and-l specifications. The MSS Quality Assurance section monitors the design l and fabrication of the fuel through a program of audits of the fuel l l fabricator, including both design review audits and fuel fabrication l l audits. MSS also conducts audits of component suppliers as deemed I I I l necessary by the Manager, Qualtiy Assurance (MSS), to ensure the quality l l of the fuel. I Formal audit reports are issued by MSS to document their I I I I l l l l l l (; l l l l A I TOPICAL REPORT lREV. 6 1 l P l l0 ATE 6/10/83 l -l l SECTION: 18.0 AUDITS lPAGE 18-6 .l l. L I-1 I l-1 I I
~ l. I i - l -- l
- l audit activities and to identify nonconformances. or other items requiring l
'N I action by the fuel' fabricator. Resolution of nonconformances or other I h l 1 'l --items requiring action is verified by MSS-and documented in follow-up l _l. reports. The AP&L Quality Assurance Manager is on distribution for all l '. l. audit and follow-up reports. l El l l-l i- .) l I-- 1 I I -l 1 -l l I: l I l i I I I I I .I i 1 I I i i 1 4 I 1. 'l l l l l l
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I l .i .l 1 I ll - 201 i i-i i ~ 'l 'A-l' -TOPICAL REPORT-lREV. 1; l. .P- -. I lDATE.6/10/83
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l l SECTION: 18.0 AUDITS-
- IPAGE '18-7 l.
1 nL l -l l -l l,- l-i. .l. a -O-.
C O Op o 9* PRESIDENT AND CHIEF t-EXECUTIVE OFFICER -.m._ rf ma Cxm M CORPORATE COMMUNICATIONS SR.VICE PRESIDENT S VICE PRESIDENT ASSIST. TO THE PRESIDENT o o= F -4O OO s n 8 F x> m -1 m m en O o 3 x.$ ENERGY SUPPLY ENERGY DELIVERY 8 FINANCE, REGULATION ADMINISTRATIVE CONSERVATION 8 z SR.VICE PRESIDENT SERVICES 8 LEGAL SERVICES SERVICES RENEWABLE ~ SR.VICE PRESIDENT SR VICE PRESIDENT VICE PRESIDENT RESOURCES ASSIST. SEC. 8 VICE PRESIDENT d ASSIST. TREASURER o2 oox >>m ARKANSAS POWER 8 LIGHT CO. o em. < mm-CORPORATE ORGANIZATION e >=8 O -o N CD Gs 4 w eme. - eman - ammme amen emmen em _ emian emme _ _ enum _ emon _ emis - emmmes - emme ammme examm _ ene emme emme summe - ammum - - som - emme ames esen om amme ammme _ emme _ _ emme enum - amme asume emman emme ene e m _ esame smi-p -_ exame .& 46 4
= ~ Li g. l 1 l l -O I l Ss 1 I I I I-I PRESIDENT AND CHIEF l l EXECUTIVE OFFICER -1 l I I l I 5 I l I AouiNiSTRATivE I. I' SERVICES I VICE PRESIDENT i l I i i I I I t i I i I i I . I i 4 CORPORATE PERSONNEL CORPORATE I j -l SERVICES DIRECTOR SECURITY l l DIRECTOR MANAGER. l I I I I l l PURCHASWG & srORES I s 1 MANAGER I I I o l l l PuRCHASrNo SUPERVISOR l-l l 1 l l NUCLEAR I I suvER I I i i I I I I-1 I i 1-I l l I i I I L I - I I I ARKANSAS -POWER 8 LIGHT CO. I i . l CORPORATE SERVICES l l l
- 1. '
l l I I l i I I 1 I ' 'Q l i I I V I A l TOPICAL REPORT IREV.. 6/10/83. I 6 l' i P I 10 ATE I I FIGURE.2...AP&L CORPORATE SERVICES IPAGE F-2 1 'l .L .I I ' l i I I I .e_<, -7 m., ,,m. yy rm,i
p. O-O \\ T ik r-ENERGY SUPPLY SR. VICE PRESIDENT ._l l I n I i l I E I g NUCLEAR OPERATIONS FOSSIL & HYDRO l ENERGY SUPPLY m VICE PRESIDENT OPERATIONS SERVICES DIRECTOR DIRECTOR I I p y ASSURANCE O l .I MANAGER m 7 I z - m n x l a r-I 1
- D ANO NUCLEAR LICENSING ANO ENERGY SUPPLY TECHNICAL ENGINEERING SES SERVICES MANAGER PROJECT l ADMINISTRATIVE SERVICES SERVICES o
O l GENERAL MANAGER MANAGER SERVICES GENERAL GENERAL l N I MANAGER GENERAL MANAGER MANAGER r-l MANAGER o i I E$ I I, E I 3 N I
- MANAGER, NUCLEAR ANO FIELD
! ENERGY SUPPLY DISCIPLINE .R. L. NUCLEAR FUEL CONSTRUCTION TRAINING ENGINEERING QUALITY SUPERVISOR MANAGER l MANAGER MANAGF.RS CONTROL l 3 r mom >>m I e @ Q,< 'g CONSTRUCTION l CONTRACT t._._.._. CUALITY CONTROL .--a ADMINISTRATION m SUPERVISOR MANAGER .--- LINES OF COMMUNICATION 'e m 1N LINES OF REPORTABILITY wo3 ARKANSAS POWER 8 LIGHT CO. ENERGY SUPPLY ORGANIZATION _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ m____ _ _.__ _
T Re r- - ENERGY SUPPLY l._ _ sR. viCE PRESoENT a I I l o C:o ENERGY SUPPLY M l SERVICES l DIRECTOR I I N" i --e QUALITY Q L--- ASSURANCE ao
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m 4>- o .-. m o QUALITY ENGINEERING QUALITY z c. ENGINEERING g SUPERVISOR SUPERVISOR L z - (LRGO) m (PLANT) m I i I I QUALITY QUALITY ASSURANCE QUALITY ASSURANCE ASSURANCE ENGINEERS / INSPECTORS ENGINEERS / AUDITORS o o :o AUDITORS >>m o -e < I LINES OF REPORTABILITY m uN m --- LINES OF Ag ARKANSAS POWER 8 LIGHT CO. COMMUNICATION D OUALITY ASSURANCE ORGANIZATION w a ________-____________________________________________=_____=_
f') (' (V) V 'u ' ea r-NUCLEAR OPERATIONS VICE PRESIDENT '2 o C l .x m . GENERAL MANAGER >u o. SPECIAL PROJECTS MANAGER r-NUCLEAR g MANAGER ~- o OUALITY CONTROL c H n 9 I rm
- x 1
3 QUALITY CONTROL Q QUALITY CONTROL u >O ENGINEERING SUPERVISOR 4 -t SUPERVISOR o I xg QUALITY CONTROL Z QUALITY CONTROL ENGINEERS INSPECTORS i N> d' I i 1 o* ENGINEERING AND M AINTENANCE TECHNICAL SUPPORT ADMINISTRATIVE OPERATIONS MANAGER MANAGER MANAGER oox MANAGER > > m.c o_ mm* m ,s m me ARKANSAS POWER a LIGHT CO. 8 NUCLEAR PLANT ORGANIZATION
h .l I [ I l I I I l l I l 1 GENERAt MANAGER I I I l I l I I i I OPER ATIO N S M AIN TEN ANCE MANAGER MANAGER g l l l I I l ELECTRICAL !I MAINTENANCE I O PER ATIONS OP Tl NS l SUPERINTENDENT SUPERIN TE N DEN T
- I
.i i 31 I l l M AIN TEN ANCE l l ELECTRICAL l UNIT l UNIT 2 g SHIFT SHIFT SUPERVISORS SUPERVISORS SUPERVISORS l g i I I l MECHANICAL O l PLANT .A AINTEN ANCE l PLANT OPERATORS SUPERINTENDENT I OPERATORS l l I f il l MECHANICAL OPER A TIONS MAINTENANCE I l TECHN CAL SUPERVISORS l ENG INL ERS I I I I I I i&C 18C PLANNING S I l SUPERVISORS SUPERINTENDENT ~~ ~ ' "hhh l Syp I .I i I shirt S R. .I l M AINTENANCE ~ MAINTEN ANCE _l SUPERINTENDENT COORDINATOR I i l 1 4 l ARKANSAS POWER S LIGHT COMPANY I I ~ l NUCLEAR PLANT ORGANIZATION I l l I l i l l 1 I I I i- ] t l l I I \\ I A l TOPICAL REPORT lREV. 6 l i P. t lDATE 6/10/83 I l L .I ( NT AI M E C I i. l l l l
I I I I I I I I .O I I U l l 1 I I I l l 1 I l l GENERAL i uaNAGEn i i I 1 il I 'I l 'I i !l l ENGINEEnlNG S !l I TECHNICAL sureont l e MANAGER l I I i i i i i l l TECHNICAL PLANT PLANT OPERATIONS I g ANALYSIS ANALYSIS. ENGINEEnlNG ASSESSMENT l suPERINTENoENT surEntNTENDENT suPEnlNTDEENT suPERINTENIENT I g I I i EMUlGENCY PLANT uECHANICAL HEALTH i 1 I etAN PEnronuANcE ENGiNEEniNG rwsics -1 O i CoonoiNAron surtavison suetsvison surEm m e eENT ti l i I l nAD NuCLEAn ELECTalCAL HEATH I l enEMrsinY - sureon7 ENGiNEEniNG rnYsics l l sueEnvison surEnvison surEnvison surtavison l l I 1 1 1 CHEMISTRY 8 COMPUTER DnAFTING & HEATH surroRT l I ENvinoNMENTAt surEnvison surEnvison -DRAWING CoNTnoL PHYstCs - I surEnvison srECiausTs I I I I I i i I l I I I 4 I I I I I I I I I l ARKANSAS POWER 8 LIGHT COMPANY I I NUCLEAR PLANT ORGANIZATION I I 1 I I I I p i l i '~> l A I TOPICAL REPORT lREV. 6 l l P 1 10 ATE 6/10/83-i I FIGURE 7. AP&L NUCLEAR PLANT ORGANIZATION lPAGE F-7 l l L- -l (PLANT ENGINEERING & TECHNICAL SUPPORT) l I l l I I
I I I I O I I NJ l g I I I I I I I I I I I I I i I i l i l l OS"ESEI I ,l 1 I I i i 1 ^ UEES$"" l I <l I I I I I I I g TRAINING OFFICE HUMAN WATERIALS PLANT I SUPERIN'T SERVICES RESOURCES MANAGEMENT CONTROLLER I SUPERVISOR SUPERVISOR SUPERVISOR l I I I I I I I I I I I I I l SECURITY EMPLOYMENT & SMETY & l COORDINATOR INDUSTRIAL FIRE l l RELATIONS PREVENTION l COORDINATOR COORDINATORS I I I I I I I I I I l I I I I I I ARKANSAS POWER 8 LIGHT CO. I I l NUCLEAR PLANT ORGANIZATION l I l (-) l c I i i I l A l TOPICAL REPORT IREV. 6 I l p l 10 ATE 6/10/82 l l FIGURE 8. AP&L NUCLEAR PLANT ORGANIZATION IPAGE F-8 l l L 1 (PLANT ADMINISTRATIVE' SERVICES) I I I
l I 1 l l TABLE 1 l I m i I I ~ l ARKANSAS POWER & LIGHT'S EXCEPTIONS / INTERPRETATIONS l OF REGULATORY GUIDES AND ANSI STANDARDS APPLICABLE l l TO THIS QUALITY ASSURANCE PROGRAM l l l l 1 I I I Regulatory Guide / Exceptions / I ANSI Standard Requirement Interpretation l l General Certain Regulatory The AP&L commitment refers l Guides invoke or to the Regulatory Guides and l l imply Regulatory ANSI Standards, specifically l Guides and standards identified in this TOPICAL. l l in addition to the Additional Regulatory Guides, l l standard each ANSI Standards, Guides and l l primarily endorses. similiar documents implied I l Certain ANSI Stan-or referenced in those l l dards invoke or specifically identified in <-) l imply additional this TOPICAL are not part of l l v' standards. this commitment. l l l General Certain ANSI Our commitment to those l Standards and/or standards applies only to l l Regulatory Guides those systems, structures, l l extend the scope of and components whose satis-l applicability to factory performance is l include systems, required to prevent postu-l l structures, and lated accidents that could l l components whose cause undue risk to the l satisfactory perfor-health and safety of the l mance is required public; or to mitigate l I for a plant to the consequences of such l l operate reliably on accidents. Reliable operation l "high-value of the plant may depend upon I 1 l l ~' / ' l l l l l A l TOPICAL REPORT lREV. 6 l l P l lDATE 6/10/83 l l l SECTION: TABLE 1 lPAGE T1-1 l l L I l l I I I l 1
1 I l l l articles." other systems, structures and l /~') l l components which are not l covered by this commitment. l 1 I l l l ANSI N18.7 Where changes are Consistent with the require-l l(Section5.2.13.1) made to procure-ments of ANSI N45.2.11, para-l l ments, they shall graph 7.2, minor changes to l l be subject to the (procurement) documents, such l l same degree of as, inconsequential editorial l l control as was used corrections, or changes to l l in the preparation commercial terms and conditions l l of the original may not require that the re-l l documents. vised (procurement) document l l l receive the same review and l approval as the original l l l documents. l 1 lANSIN45.2.1 Fresh water criteria The turbidity requirement on l O l (Section 3.2) for chlorides, and fresh water is deleted and l l Jackson Turbidity the chloride requirement is l l Units. revised to read "less than i 250 ppm." The turbidity l l requirement for demineralized l l l water is deleted. l l lANSIN45.2.2 " Preliminary visual Inspection after unloading is l l Subsection 5.2.1 inspection or exami-sufficient to determine the l l nation shall be per-condition of many items. In l l formed prior to special instances, pre-unload-l l unloading..." ing examination is performed. l l I l l l I I I I I I I l l o l i i l A l TOPICAL REPORT lREV. 6 l l P l lDATE '6/10/83 l l l SECTION: TABLE 1 lPAGE T1-2 l l L l l l l 1 1 I
l i l l l ANSI N45.2.2 The (receiving) Receiving inspection is per-l ~) Section 5.2.2 inspections shall formed in a manner and-in an l l be performed in an environment which does not l l area equivalent to endanger the requisite quality -l the level of storage of an item. The receiving l l requirement for the inspection area environmental l item. controls may be less stringent l l than storage environmental l l requirements for that item, l l however, the short time spent l in the less stringent receiv-l l ing inspection area shall be l of such duration that will l l not adversely affect the item l l being received. l I l I I l ANSI N45.2.2 ... The 'Special The "Special Inspection" l l Paragraph 5.2.3 Inspection' pro-procedure shall be readily n l cedure, complete available to inspection l U l with documentation personnel and may be attached l l instructions shall to the item or container. l l be attached to the l item or con-l l tainer..." l l l lANSIN45.2.2' The use or storage People working in storage I l Subsection 6.2.4 of food, drinks, and areas have a right of access l l salt dispensers in to water dispensers per OSHA l l any storage area is requirements. Additionally, l prohibited. due to the location and I l layout of the building, per-l l sonnel may temporarily store l l lunches in the work place. l l 1 l I s l A l TOPICAL REPORT lREV. 6 l l-P l 10 ATE 6/10/83 l l l SECTION: l' L l _ TABLE l' -lPAGE T1-3 l l l l l l l
l-1 I; I l-This area is policed for l [) I v I sanitation. I I
- l l
lANSIN45.2.2 " Container markings Containers are adequately l l Appendix.'A-3) ~shall: appear on a marked for storage, identifi-l lA.3.9(1)Second minimum of two sides cation, and retrieval. l l -Group of the container, ' Multiple marking requirements l l preferably on one are imposed, where necessary. l I side and one end." l l I I I l ANSI N45.2.2 " Container markings Container markings are of a l ] Appendix (A-3) shall be...no less size which permits easy l l l A.3.9 (4) Second than 3/4" high recognition. l l Group. container permit-l l ting." l I I I I l ANSI N45.2.2 " Container marking The information required l l Appendix (A-3) shall include the in container marking is l l A.3.9 following informa-evaluated on a case-by-l l l tion..." base basis. ' Marking is. l l adequate in each case. l l l i i l. I l l ANSI N45.2.2 "Non-metallic plugs Non-metal plugs and caps are l Appendix (A-3) and caps shall be of a suitably visible color. l l l.Section A 3.5.1 (1) brightly colored." l l l l l l ANSI N45.2.2 Plugs or caps shall In cases where plugs-or caps l l Appendix (A-3) be secured with tape do not snugly fit', additional l -l Section A 3.5.1 (5) or other means as-securing devices or measures l l-necessary to prevent which will not be detrimental l l-accidental removal. to the-item will be used. l 'l I -l l l L i- 'l l' I E l l-l () 1 I I l .I A l TOPICAL REPORT l REV.' 6 l l. P. -1 l0 ATE 6/10/83 l- .I-l'SECTION: TABLE.la lPAGE T1-4 l .I L .I l l 1 .I I l l
l' l I I I l ANSI N45.2.2 Marking of items The last paragraph of Section l /1 I Appendix ( -3) 'not within a con - A.3.9 could be interpreted as I l: Section A 3.9 tainer. prohibiting any direct marking l l on bare austenitic stainless 'l steel and nickel alloy metal l 1-surfaces. In lieu thereof, l paragraphs A.3.9. (1) and (2) l ] will be used to control l l marking on the surface of l I austenitic stainless steels l I I l and nickel base alloys subject l l I to the following limitations: I I l " Marking materials'containing l l sulfur, lead, zinc, mercury, I l copper and low melting alloys l l as a basic chemical consti-l l tuent shall not be brought in l l contact, or shall not be used I p l on surfaces of corrosion l i I resistant alloys. Low sulfur, l -l low fluorine and/or. low l chlorine compounds may be l used on austenitic stainless l l l steels." The maximum limits l l l for the above mentioned mark-l I l ing materials will:be as l l l follows:- l l -l-(a) Total = inorganic and I 1 l organic halogen content l l shall not exceed one (1) _l percent. I (b) The sulfur content shall l I I l not exceed one (1) l percent. I O I l l l l 'A l-TOPICAL: REPORT lREV. 6 l l P l' IDATE 6/10/83 l l 1 SECTION: TABLE 1-lPAGE -T1-5 l l .L-l -l l-I l -l l
I l I l l ANSI N45.2.2 Inert Gas Blankets There may be cases involving l J ]' l large or complex shaped items l ~ ~~' l for which an inert or dry air l l purge is provided, rather l l than a static gas blanket, in l order to provide adequate l l protection due to difficulty l l of providing a leak proof l l barrier. In these cases, a l l positive pressure purge flow l l may be utilized as an alter-l l nate to a leak proof barrier. l l l lANSIN45.2.2 Limits halogen and Engineering may allow the use l l Appendix A, sulphur content of of tapes containing greater l lA.3.5.2,(1),(a)
- tape, amounts of halogens after l
appropriate evaluation. l however, the quantities shall l p l not be such that harmful l l l concentrations could be l leached or relased by break-l down of the compounds under l l expected environmental l l conditions. I I I lRegulatoryGuide General Alternative equivalent l l 1,39 ANSI N45.2.3 requirements may be utilized l l ] to cover those situations not l included in the subject l Standard; for example, situa-l l tions in which shoe covers l I I l i I I I I I l I l ( l l l l I l A l TOPICAL REPORT lREV. 6 l l P l IDATE 6/10/83 l l l SECTION: TABLE.1 IPAGE T1-6 l 1 L I l l l l l 'l l
r 1 I i 1 l and/or coveralls are required l I' f} but material accountability l is not. In addition, zones l l might be combined into the l l l. next more restrictive l category in order to reduce t l . total number of zones. l l l I l j l ANSI N45.2.3 Identifies various When this standard is applied, l l l housekeeping re-its requirements are imple-l l quirements, includ-mented in those areas affected l l ing cleanliness, by work activities associated l l fire prevention, with modifications, opera-l l l and fire protection tions, or maintenance as l l which must be determined necessary by Plant l I accomplished during Staff. I I I l l the progress of l l l construction. O lRegulatoryGuide Pre-Construction / This section required verifi-l 1.30/ ANSI N45.2.4 Installation Verifi-cation that items are in l l cation satisfactory condition for l l Regulatory Guide installation and have not l l 1.116/ ANSI N45.2.8 I suffered since initial l l l l receipt inspection. Upon l l-l receipt, items are inspected l l and stored in an environment l which will not adversely l l affect the item. Documented l l routine inspections and-I periodic audits of the storage -l. I I I I l i l l I I l l f)' .I l 1 l -- l -A l TOPICAL REPORT lREV. 6 I- -l P l lDATE 6/10/83 l l l SECTION: ' TABLE 1 lPAGE T1-7 l 'l L l l l l I l-1
,bi -~ ?-< - - ~^ ^ ^ ~ ' = ' p i[. lt) ' A ll.: \\ 1 l a i a . I' I 1 . l-areas assure that stored items l. ! Q" -I
- MN are maintained in satisfactory I
l I l conditions. Documentation l I' -l of pre-construction verifica-I l L l tion in addition to documen-l .d I jtation of initial receipt-l inspectiqn, periodic storage l [ ) inspections, and audits of l l_ storage is'not-required. l l l .I l l i l ANSI N45.2.4 Identifies various These tests will be performed l l tests-to be as determined by Engineering l l performed.e A ~or Nuclear Operations based l a l [ upon the significance of l l change or modification. I l-3 1. I I l R.G. 1.58 In addition... the AP&'t takes: exception' to this l I (SebtionC.6) candidate should be requirement. AP&L!s education I I I a high school i. and experience requirements l l y l[ graduate or $de are in accordance with ANSI l l 'searned the. General N45.2.6,1978. _l s I,i Education Development-I 's l -l l (GED) equivalent of-3 l l a high school l. l l diploma.
- 1 l
ll' l l / l . l _ R. G.' 1. 74/.
- Definitions of
/ Based:upon the guidance of l_ -lANSIN45.2.10 H-Certificate of-ANSI N45.2.13, 10.2, the l x s
- l-y' Conformance and 3. 0 definitions of these.two-l.
i i.c I Certiffbate of . terms will'be exchanged.. I l-c 4 l Comp 1Iarfce."o -l j. 3 f. l i l~ oe l-l g, c l .l-l 'vl
- l uy'
>t , )J l: -l ,g f l 4 p bt W k l Ot~ l. A l- %TCPICAL REPORT- -lREV. i6 -l + i i M - PJ, I Q. s ja. :l, l SECTION: TA8LE'1. -l0 ATE 16/10/83- 'l. m lPAGE TI-8: l-q ,-1 O LL
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l l:. l 4 10 l-R.G.E1.94/' 'Section:1.4 defines This requirement for rein-l .. I -AV" ,-l: ANSI ~N45.2.5' 'inprocess tests and forcing steel will be I- ~ l c ll1 (Section 1.4) .sthtes: interpreted to permit taking l .I. 1 the rebar test specimen at I !b "... samples of these the fabrication shop, prior l w l' h i' tests must be~taken to start of fabrication of g ( W %'? l-from the lot or the rebar from the heat or l I 'l l< -batch of-materials fraction thereof represented I I -l supplied to'the; site by the test specimen. For l gj. ] for use."~ these tests performed at the l l' yir l fabrication shop, certifica-l l [ n. g~ tion'shall be available to g I .U l ' provide objective evidence l e 1 I. I- .I that the test specimens I N. l represent the material sup-l [ .I' ,w l-plied for use at1the site. I l ^\\ }.- 'l; ANSI N45.2.5 I Requirement: l' 1 4 J l
- l. (Section'4.5)'
Section 4.5', Con- -l 'I [ l . crete Placement, y l references American .l; I 4 ConcreteEInstitute; I l .[p- ' l :: .-(ACI) standa'rds.
- l.
I 7- ,/.- .g ACI-305-72, l 1 i jl;. '" Recommended Prac- .l P 'lI tice for Hot Weather; I- . dp n' $ll.. - {I ? f(- Concreting" and ACI-- 1306-66E" Recommended I - J 1- -l- ' 1' sl1 Practice for Cold l
- I Weather Concreting.'"'
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I l l 1 l. ' Interpretation: 1 (~N I V l In order to clarify I l l use of these ACI 1 l standards, we will l apply the following l l requirements: l l l I ( PLACING TEMPERATURES OF CONCRETE: I l I I I A. During hot weather concreting: l l l Placing temperatures of concrete will be l limited to the following: l l l l l l
- 1) Concrete members less than 3 feet in least l
dimension will not exceed 90 F. l l l l
- 2) Concrete members from 3 feet to 6 feet' in l
kq l_ least dimension will not exceed 70 F. l J l 1 l l
- 3) Concrete members more than'6 feet in least.
l dimension'will have placing temperature as l . near 50 F as can be obtained by use of ice l l I as necessary up to'100 percent of adding I I -l. mixing water; and by shading aggregate and l L l sprinkling the coarse aggregate the day it I I j. is to be used. Care will be taken so that'~ l no unmelted ice remains in the concrete at-l the end of'the mixing period. l
- l l
.l. _ 1-1 l-I l l -l l l-l .I l'l' I, l ~ I-l -t3 l,. l l. 1 'd " 'l .A -[ . TOPICAL REP 0RT : ~lREV. 6'. 1. l' -P.... 1 'l0 ATE ~6/10/83 1.' .l -l.SECTION: TABLE 1. -lPAGE.T1-10
- l
.'l ; L1 1; 'l-l L l: l 1 .i Li +
_i 1 21 l .l B. During cold weather concreting: l h. ~ l l
- g.
l l l' In heating the water and aggregate, live-steam l to heat the fine ~and coarse aggregate shall not 'l ~
- l be used.
The permissible ran'ge'for concrete l
- l-
~ 'l temperature shall be as follows:
- l' I
I 1). Sections less than 3 feet-in least I I I l dimensions: 55 to 75*F. l-1 I I I l- -2) Mass concrete 3' feet or more in least l l dimension: '45 to 65 F. I l l The mixing water and aggregate will be l purchased as-required. 'The materials will be l- '[ free of ice, snow and frozen lumps b' fore they f ~ e' l . enter the mixer. l-l .I- .I l l. ANSI N45.2.5 Requirement: .l- = I (Sestion 4.8) I l l ,l. Section 4.8, "In process Test on. Concrete and: c: l' Reinforcing Steel" states, " Samples for~in process - .{ l . test 'of concrete shall.be taken at the sampliiig,
- j l
-point in accordance withlASTM C172. Thisl point may- ].. l be at the truck mixer discharge.if-the:last piece j I .l. of conveying equipment is:a~ chute,' bucket,- l l l conveying system, or similarjequipment. Pump-l l' concrete must.be' sampled from'the pumpLline- ~ ~ .l . discharge."
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.PL li 2lDATE 6/10/83-21: ~ M ^ .I' & k., l'SECTION: LTABLEs1.= ~ o. 1llPAGEJT1-11; l. -l w - ' L:-
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a: e. +3g 1, l l l l l. Interpretation: l (,I' l = l For performance of correlation tests, the. l l requirements of ANSI N45.2.5-1974 shall be -l-followed. l l -- -l -l I _l ANSI'N45.2.5 Requirement: I '(Section.4.8) l l Section 4.8, "In process Tests on Concrete and l l Reinforcing Steel" contains Table B entitled, l l " Required ~In pro' cess Tests." The following_ l. l modifications to this. table will be applied: l -l l-Interpretation: I l ~ l REINFORCING STEEL I I l~ In process testing or_ reinforcing' steel will l l include the mechanical properties.of yield l strength, tensile _ strength and percent elongatio~n -l-on full size specimens tor each b'ar size for each I. l 750 tons o'r fraction thereof from each~ mill heat. l._. Bend tests are' performed lduring material l l qualification' testing only, except;as_noted'below. l ^ ~ 1 for bar sizes #14-throug;; #18. ll I-l- l- ':1 - l, Table A, " Required-Qualification Tests" a's applie'd. l I I- 'to reinforcing _st'eelfwill include bend. tests'as= I-l1 -l.
- g. required by ASTM:A615 and summarized below:
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_, i, TABLE 17 -lPAGE T1 I l0 ATE:i6/10/831 .li i, -lT -. r& -l SECTION: s ~ sis -;LJ -l, .l~ l1 l g 4- .= k_ m.. )7
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l l l a) For bar sizes #3 through #11, one full size l I ij' l specimen from largest bar size rolled from each I ,e ' S l 'l mill heat, unless material from one heat l -l differs by three or more disignation numbers. l ~l_ When this occurs, one bend test shall be made l l .from both the highest and lowest designation l l number of the deformed bars rolled. l l 1 l l l b) For bar. sizes #14 through #18, Supplemeitary l l Requirements S1 of ASTM A615 will be applied. l ~l One full size specimen for each bar size for l each mill heat. If supplementary requirements l are not followed for mill tests, they will be l l applied as in process tests. l l -l The above interpretation-is consistent with l Regulatory Guide 1.15, " Testing-Reinforcing bars l l for Category I Concrete Structures," Revision 1, l l December 1972. 1 l l l l l In process test specimens may be selected at the l rebar fabrication shop, prior to start of I 'l fabrication of the rebar from the. heat or fraction-l thereof. represented by~the test specimen. l l 1 -Acceptance criteria for any failed test. l (qualifications as well as in process) may be the-l same as that for tensile tests specifiedlin -l Subarticle.CC-2331.'2 of ASME Section:III, Div. 2 l I-l- Code-(1975). 'This states that if a' test: specimen I l l-fails to meet'the specified strength requirements, l 11-l l l' l 1 l-1 Jl -l 1- ' (^)1 . l: A, l . TOPICAL REPORT-lREV. 6 l l- -l N' l . l' P 'l'. -IDATE 6/10/83_ 'l l l-SECTION: TABLE.1-lPAGE T1-13 .l 2 - 1, L-l- l fl l 4 l. g.
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two (2) additional specimens.from the same heat and l [I ~ of the same bar ' size would be test'ed, and if either
- l of'the two_ additional ' specimens fails to meet the l
specified' strength requirements, the material l (l-represented by the tests-would be rejected for the l I specified-use. Alternative use of-rejected I -l l l material under strict control may be subject to l evaluation by the Project Engineer. l -l 1 'l~ANSIN45.2.5 Requirement: .l l-(Section 4.9). l I l-Section 4.9, Mechanical (Cadwsid) Splice Testing I 1 l_ states in paragraph 4.9.4 " Separate test cycles l l .shall'bs established.for mechanical splices in. l <l horizontal,' vertical and' diagonal bars, for each-l bar size and for each splicing crew..." l l ~ l Interpretation: l~ O _l The terms '"horizo'ntal, vertical and ' diagonal bars"' l l will;be interpreted to apply respectively.to the 'l following types of_ splice positions: -l l I ~Hozizontal, including 10 -to horizoatal 'I a. I i l .b. . Vertical, including 10* to vertical-ll l c. -45 angle, including 10" to'80*. angle $I I l. .I -l. l' ~ '
- 1 The words " splicing crew" will.be interpretedito
/I ~ -l- -l: ' refer to.all; members on'the_' project thatlare -l-l~ ~ ' -l - - ac'tivitely engaged in preparing ~and assembling I cadweld-mechanical;sp1 ices'atthe' final [ splice
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- Separate. test-cycles will;be: established) l Ll-fo.r'e'ch bar_s'ize.and.each splice. position.-
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. -. = I l 4 1 I 'l ' ANSI N45.2.12 An' individual audit For those routine audits l -(j- ]'.(Paragraph.4.'2.1) plan describing conducted during operations, l l! the audit to be a written procedure (s) l l performed shall be covering each audit may be l developed and utilized. Procedure (s) will l l documented by.the identify the audit scope, I .l auditing organiza-a requirement that individual l l l tion. This plan checklists be utilized list-l shall identify the ing requirements which are to l l . audit scope, the be audited and notification j. requirements,_the, of the audited group. l l l activities tbe o -l audited,Lorganiza-l tions to~be notified, l the applicable l l documents, the l l schedule, and written l. ~ procedures or check-lists. l 1 l l ANSI N45.2.13-The certificate. The person attesting to a l l (Section 10.2.d) should be attested certificate shal'1 be an I I i l .to by a person who authorized and responsible -l-is~ responsible for employee of-the supplier, I l this quality assur-and.shall be-identified by l I ance function and theLSupplier. I l -l .l -whose function and l l position-are I-3 4 .l- <l-l . described in the l 'l Purchaser's/' 'l I l- .l Supplier's quality-l I. l-assurance program. I l l-I L .l. 4 -l L I 1 i 1. .,m 1. l-tj .l- .l-I- ~ l l A' -- I _ TOPICAL' REPORT. lREV. '6. - 1 - 11
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4 er 'I .I -1 I 'l'-R.G. 1.64-(Section "While design Consistent with the require-l .l'C.2)/ANSIN45.2.11verification by the ment of ANSI N45.2.11, l 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 l that such verifi-individual in the organization l l l cation constitutes competent to perform the I the required inde-verification. I pendent design l l Verification,..."- I -l l I I I I I I I I I I I I I I I 4 I I I I I O l l l 1 I l' I l-l- 1 I I t-1 I 'l .I i 1 I I l i I l-I l' I l .I l- 'l l l -l-
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- l IDATE' 6/10/83.
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-l-ib l ~ -l ' QUALITY PROGRAM POLICIES, PROCEDURES AND INSTRUCTION l l-- MANUALS LIST l l' l l-1 -l. 1. Quality Assurance Program for Operations l 1 l l l .l The Quality Assurance Program for Operations establishes the l l policies and guidelines of the AP&L quality assurance program for - l ~ -l its operating nuclear plants. This program is to be followed by all l ~ organizations _ involved in safety related work applicable to l operating nuclear plants. l l l 1 l l 2. Energy Supply Procedures Manual l l 'l l ~. l The: Energy Supply Department - Little Rock General Office (LRG0) l empl' oyes a system of procedures designate'd as Energy Supply I ~ l Department Procedures (ESP) in order to implement Program: l requirements fo'r the control of design, engineering, nuclear fuel,. l l . licensing, training and procurement activitie's in support.of the l operating plant. I l l The ESP's and revision thereto are prepared by. Energy Supply LRGO l l-personnel, reviewed and approv'ed by.the Quality Assurance Manager, l the Energy Supply (LRG0) Procedures Task Force and_-the. responsible l ~ department head.' 'l-l l l 3. Quality Assurance Procedures Manual-l 'l l .l-I- l -l The-Quality. Assurance Organization employes.a system of procedures-- _ ll l designated as Quality.. Assurance. Procedures (QAP) in' order to assure: Il ~ 1- ~ 1 -l. . proper implementation of the program..TheLQAP's-and revisions. l yl-
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P1 .l. ?lDATE: 6/10/83.. l. l J&s
- llSECTION
- LTABLE 3'
- lPAGEDT3-11
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'l l I I ~l thereto are prepared by the Quality Assurance Organization, reviewed I (] 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.~ l l 1 l4. Quality Assurance Administrative Procedures Manual l l l I The Quality Assurance Organization also employes a system of l l procedures designated as Quality Assurance Administrative Procedures l (QAA). These procedures provide technical and administrative l instructions to the Quality Assurance staff to aid in implementing l their responsibilities within the quality program. I I l5. Overall Plant Adminstrative Procedures Manual l } I I The plant operation organization employes a system of procedures l designated as Overall Plant Administrative Procedures. These l procedures implement Quality Assurance Program requirements and l C l control on site activities. Overall Plant Administrative Procedures l ~ d' g and changes thereto are prepared by the plant staff, reviewed by the l Plant Safety Committee-and approved by the plant's General Manager. l The procedures and revisions are also reviewed by the Manager, l Nuclear Quality Control to assure that Quality Assurance Program l commitments are met. I I 1 6. Departmental Plant Administrative Procedures I r I I I I l Each department (operations, maintenance, engineering and technical l~ _l support, training, quality control, etc.) at the-plant has developed l I procedures.in_ support of.the Overall. Plant Administrative Procedures-I I _I l and this Quality Assurance Program..These-procedures provide l I technical snd. administrative instructions to the various' departments I I l- .I I I i l 1 I I l l I ( )' l-l- l .l-V .l .A 1 ~ TOPICAL REPORT 'lREV. -6. .l l P. .lDATE-6/10/83 l
- I-l:SECTION: TABLE 3 IPAGE"T3-2
'l- ~l LE 'l .I , l: I l-1 I i
I I I I I to aid in implementing their responsibilities within the quality l g program. Each department head is responsible to perform a QA review I of their procedures to assure conformance with the Quality Assurance l Program. These procedures are reviewed by the Plant Safety i Committee and approved by the Plant's General Manager. I I I I I I I I I I I I I I l l l l l 1 I I I I I I I I I I I I I I I I I I I I I (') l l '/ I l l l l l l l l I I I I I I l l l l 1 1 I I I I I l l I I I I I I l l I I I I l l 'l i 1 1 I I s i I I i 1 ~ l_ -A l TOPICAL REPORT IREV. 6 l l P 1 IDATE 6/10/83 I I 1 SECTION: TABLE 3 IPAGE T3-3 I I L 1 1 I I I I I}}