ML20138H509
| ML20138H509 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 08/08/1985 |
| From: | AMERICAN SOCIETY OF MECHANICAL ENGINEERS |
| To: | |
| References | |
| OL-S-138, NUDOCS 8510290058 | |
| Download: ML20138H509 (23) | |
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Qua ity Assurance Requirements for he Design of Nuclear Power Plants-ANSI N45.2.ll - 1974
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PUBLISHED BY THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS United Engineering Center 345 East 47th Street New York, N. Y.10017 s+d+ l 38
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i AMERICAN N ATION AL STANDARD An American National Standard implies a consensus of those substantially concemed with its scope and provisions. An American National Standard is intended as a guide to aid the manufacturer, the consumer, and the general public. The existence of an American Na-tional Standard does not in any respect preclude anyone, whether he has approved the standard or not, from manufacturing, marketing, purchasing, or using products, processer, or procedures not conforming to the standard. American National Standards are subject to periodic review and users are cautioned to obtain the latest editions.
CAUTION NOTICE: This American National Standard may be revised or withdrawm at any time.The procedures of the American National Standards Institute require that action be taken to reaffirm, revise, or withdraw this standard no later than five years from the l
date of publication. Purchasers of American National Standards may receive current infor-((^
mation on all standards by calling or writing the American National Standards Institute.
i This standard was approved by the American NationalStandards Committee N45 and its Secretariat, and it was subsequently approved and designated N45.2.11-1974 by the American NationalStandards Institute on June 6,1974.
No part of this document may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written permission of the publisher.
Copyright C 1974 by THE AMERICAN SOCIETY OF MECilAN!OAL ENGINEERS Printed in U.S.A.
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l FOREWORD (This Foreword is not a part of The A merican National Standards institute Standard for the Quality A ssurance Requirements for the Design ofNuclear Power Plants.)
This standard delineates the minimum quality assurance requirements to be implemented during the de-sign of nuclear power plants. The standard was developed by the American National Standards Committee N45 on Reactor Plants and their Maintenance.This committee has been chartered to promote the develop-ment of standards for the location, design, construction, and maintenance of nuclear reactors and plants embodying nuclear reactors, including equipment, material, methods and components specifically for this purpose.
In April of 1970, the N45 Committee established a subcommittee, N45 3, to guide the preparation of nuclear quality assurance standards. This subcommittee is responsible for establishing guidelines and policy to govem the scope and content of the various standards; monitoring the status of standards in process; recommending preparation of additional standards; and final approval of standards prior to their submittal to the N45 Committee for balloting.
In October 1971,the N45-3 Subcommittee established a working group, N45-3.11,on Quably Assurance Requirements for the Design of Nuclear Power Plants. The purpose of this working group was to prepare a standard for general industry use that would define the quality assurance requirements to be implemented during the design of nuclear power plants. The work group was composed of representatives of key segments of the nuclear industry including electne utilities, nuclear energy system supplica, engineers, constructors and the Atomic Energy Commission.The standard contained herein was prepared by this work group.
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Working with the N45-3 Subcommittee and concurrently with the development of this standard by the N45.3.1I working group, other working groups of N45 are developing a series of standards that set forth both general and detailed technical provisions for certain activities to assure quality of nuclear power plants.
These requirements will be coordinated with the requirements of this standard as they are developed.
l In October 1972, the N45-3 Subcomnittee was renamed N45-2, and the work groups were renamed ac-cordingly. As of September 1973, the following associated standards were in preparation or issued:
Work Group Standard in Preparation N45.2 Quality Assurance Program Requirements for Nuclear Power Plants i
N45-2.1 N45.2.1 Cleaning of Fluid Systems and Associated Components During the Construction Phase of Nuclear Power Plants.
N45-2.2 N45.2.2 Packaging, Shipping, Receiving. Storage, and Handling of items for Nuclear Power Plants (During the Construction Phase).
N45-2.3 N45.2.3 liousekeeping During the Construction Phase of Nuclear Power Plants.
N45-2.4 N45.2.4 Supplementary Quality Assurance Requirements for Installation, inspection and Testing of Instrumentation and Electric Equipment During the Construction of Nuclear Power Generating Stations.
N45 2.4 N45.2.5 Supplementary Quality Assurance Requirements for Installation, inspection and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants.
N45 2.6 N45.2.6 Qualificatioas of Inspection, Examination and Testing Personnel for the Con-struction Phase of Nuclear Power Plants.
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Work Group
_ Standard in Preparation N45-2.8 N45.2.8 Supplementary Quality Assurance Requirements for Installation.Inspeetttm an Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants.
N45-2.9 N45.2.9 Requirements for Collection, Storage and Maintenance of Quahty Assurance Records for Nuclear Power Plants.
N45-2.10 N45.2.10 Quality Assurance Terms and DeGriitions.
N45 2.12 N45.2.12 Requirements fur Auditing Quality Assurance Programs for Nuclear Power Plants.
N45-2.13 N45.2.13 Quality Assurance Requirements for Control of Procurement of Equipment, Matenals and Services for Nuclear Power Plants.
N45 2.14 N45.2.14 Design and Quality Assurance Requirements During the Manufs:ture of Class IE Instrumentation and Electric Equipment for Nuclear Power Generating Stations.
N45 2.2 N45.2.15 Requirements for the Control of Hoisting, Rigging and Transporting ofitems at Nuclear Power Plant Sites.
N452.4 N45.2.16 Supplementary Requirements for the Calibration and Control of Measuring and Test Equipment used in the Construction and Maintenance of Nuclear Facilities.
N45 2.17 N45.2.17 Quality Assurance Requirements for Control of the Welding Process for Nuclear Power Plant Construction.
Suggestions for improvement gained in the use of this standard will be welcomed. They sho The American Society of Mechanical Engineers,345 East 47th Street, New York, N.Y.10017
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AMERICAN NATIONAL STANDARDS COMMITTEE N45' Reactor Plants and Their Maintenance OFFICERS ss euremin,o eirman we.m es u. urine, viceaeirmen J. C. Rom, Secretary COMMITTEE PERSONNEL AMERICAN FEDERATION OF LABOR AND CONGRESS OF INDUSTRIAL ORGANIZATIONS P. A. Snoop, international Brotherhood of Dectrical Workers, Washington, D.C.
AMERICAN NUCLEAR SOCIETY J. 1 Moore, %estinghouse Dectric Corporation, Pittsburgh, Pennsylvania J.
A. Aohlfs, North American Rockwell,Canoga Park, California AMERICAN SOCIETY OF CIVIL ENGINEERS A A Ferrito, Ebasco Services, New York, New York c 8. Micie&, Ntemere, Stone and Webster Engineering Corporation, Boston, Massachusetts AMERICAN SOCIETY OF MECH ANICAL ENGINEERS. THE E. c Seitey, Commonwealth Edison Company,Oticago, Illinois V. S Soyer, Philadelphia Dectric Company, Philadelphia, Pennsylvania M F. Brush, Bechtel Corporation, San Francuco, California Sol surstein, Wisconsin Dectric Power Company, Milwaukee, Wisconsin AMERICAN WELDING SOCIETY J.
A. Mc Guffey, Union Carbide Corporation. Oak Ridge, Tennessee H. E. seosament, Neemese, American Welding Society, Maami, Florida i
ATOMIC INDUSTRIAL FORUM,INC.
D.
- Montpomery, Babcock & %ilcox, Lynchburg, Virginia EDISON EECTRIC INSTITUTE-ELECTRIC LIGHT AND POWER GROUP A. W Oement, Consolidated Edison Company of New York. Incorporated New York, New York H. 8. Rey, Alternere, Southern Cahfornia Edison Company, Los Angeles, California G. A Okon, Nternere, Edison Dectric Institute, New York, New York HEALTH PHYSICS SOCIETY T. J. surnett, Oak Ridge National Laboratory, Oak Ridge. Tennessee INSTITUTE OF ELECTRICAL AND ELECTRONICS ENGINEERS M. Omen, American Dectnc Power Corporation, New York, New York J.
C Auss, General Dectric Company, San Jose, Cahfornia INSTRUMENT SOCIETY OF AMERICA H. C Cope /end, Douglas United Nuclear Incorporated, Richland, Washington T. M. Dement, Nternere, Douglas United Nuclear Incorporated, Richland, Washington MANUFACTURING CHEMISTS' ASSOCIATION, INCORPORATED Joe Haspe, Jersey Nudear Company, Bellevue, Washington NUCEAR ENERGY PROPERTY INSURANCE ASSOCIATION A. P. Oey, Nudear Energy Property Insurance Assocution Hartford, Connecticut John J. Ctrney, Neernere, Nuclear Energy Property Insurance Association, Hartford, Connecticut U.S. ENVIRONMENTAL PROTEC110N AGENCY J. E. Merrin, U.S. Department of Environmental Protection Agency, Rockville, Maryland E, D. Here=ord, Neernere U.S. Department of Environmental Protection Agency, Rockville, Maryland
'As of August 14,1973.
v
f TRAVELERS INSURANCE COMPANY THE F.
- Oneds/, ne Travelers Insurance Company. Hartford, Connecticut U.S. ATOMIC ENERGY COMMISSION Robert Minogue, U.S. Atomic Energy Commission, %ashinston, D.C.
M4/ bur Morrison, A/remere, U.S. Atomic Energy Commission, Washington, D.C.
Aobert E Yo*r. Division of Operational Safety, U.S. Atomic Energy Comrmuion, Washington, D.C.
INDIVIDUAL MEMBERS 1 A Sernsen. Bechtel Corporation, San Francisco.Cahfornia w F. Ferguson, Oak Ridge National Laboratory, Oak Ridge, Tennessee D. L. Leone, Sargent & Lundy Engineers, Clucago, Illinois Heroid Lichren6erper, Combustion Engineering. Inc., %indsor, Connecticut 1.
N. Monda, Washington, D.C.
Dons /d E vendenburgh, Yankee Atomic Dectric Company, %estborough, Massachusetts SUBCOMMITTEE ON NUCLEAR QUALITY ASSURANCE N45 2 1 A sernsen, cheirmen, Bechtel Corporation, San Francisco, California J
W. Anderson, Secretary, Oak Ridge National Laboratory Oak Ridge, Tennessee
- 8. G. Avers, General Public Utilities Services Corporation, Parsippany, New Jersey A.1 mein, Pacific Gas & Dectric Company, San Francisco, Cahfornia Gene assile, United States Testing Company, Inc., Hoboken, New Jersey A. A/eineis, United Er.pneers & Constructors, Boston, Massachusetts
& A Casteke, Westinghouse Dectne Corporacon, Pittsburgh, Pennsylvania A W Devesse, Tenneuee Valley Authority, Osattanooga, Tennessee A. L. Deck, Duke Power Company, Charlotte, North Carolina H. F. Do6el, Babcock & Wilcox, Lynchburg, Virginia W. F. Ferguson Oak Ridge Nationallaboratory, Oak Ridge Tennessee g'
J w Hellowell, %estinghouse Dectric Corporation, httsburgh, Pennsylvania A K. Nasije, Meatu/Nelia Engineering Dept., New York, New York i K. He// men, ne Ralph M. Persea Co., les Angeles, California E. J Momsy, Commonwealth Edi on Company Oticago, Illinois
H. Nicks, Babcock & Wilcox, Lynchburg. Virginia J. P. Jackson, Gulf General Atomic, San Diego, California G.1 Keeley, Consumers Power Company, Jackson. Michigan J P. Knishr, Tennessee Valley Authority, Knoxville, Tennessee M. E. Langseon, U.S. Atomic Energy Commission, Washington, D.C.
D. G. Long. General Dectric Company, San Jose California w M. Morrison, U.S. Atomic Energy Commission, Washington, D.C.
Gers/dSchier6ery, Stone & Webster Engineering Corporation, Lycoming, New York
-J E. M4Ner, Combustion Engineering. Windsor, Connecticut F. W Knishr, Westinghouse Dectric Company, httsburgh, Pennsylvania
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The Work Group N45.2.11, included the following personnel during the development of this standard; A. Bleeweis. Osirmarr, Umted Engineers & Constructors. Inc.
M. M. Glotrer Secretary, Combustion Engineering. Inc.
G. AWeent, Burns & Roe. Inc.
& sarnes, Consolidated Edison Co. of New York,Inc.
M. H. Seers, General Dectric Company
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C W. Dek, Bechtel Power Corporation 1
D. A. Grain, %estinghouse Dectric Corporation G. P. Field, American Electric Power Service Corporation J. P. Moore,.k., General Public Utilities Service Corporation W. M. Morrison, Atomic Energy Commission j
D. H. Ahoods, Jr., United Engineers & Constructers Inc.
l G. L. Sticht, Gulf General Atomic C R. Nes/y, EBASCO Services A. Cyg/eman, resigned Burns & Roe,Inc.
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CONTENTS Page
- 1. INTRODUCTION.
I 1.1 Scope..
I 1.2 Applicability.
I 1.3 Responsibility...
I 1.4 Definitions.
I 1.5 Referenced Documents I
- 2. PROGRAM REQUIREMENTS.
2 2.1 Establishment and Documentation..
2 2.2 P'ogram Procedures.
2 r
2.3 Factors Considered.....
2
- 3. DESIGN INPUT REQUIREMENTS 2
3.1 General.
2 3.2 Requirements.
2 S
- 4. DESIGN PROCESS..
3 4.1 General......
3 4.2 Design Analyses...
3 4.3 Drawings........................................
4 4.4 Specifications.
4 4.5 Other Design Documents.
4
- 5. INTERFACE CONTROL...
4 5.1 External.
4 5.2 Internal..
4
- 6. DESIGN VERIFICATION.
5 6.1 General.
5 6.2 Extent 5
6.3 Metheds.
5
- 7. DOCUMENT CONTROL 7
7.1 Document Preparation, Approval and issue...
7 7.2 Document Revision.
7 7
1
- 8. DESIGN CHANGE CONTROL,
1 7
8.1 Reasons for Changes...
8.2 Review of Changes 7
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- 9. CORRECTIVE ACTION....
8 9.1 Detection of Errors.
8 9.2 Review of Procedure.....
8
- 10. RECORDS..
8
- 11. AUDITS.
8 I
11.1 Personnel....
8 11.2 Interna! Audits.
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3 11.3 External Audits...
8 I
11.4 Audit Control.
8 11.5 Schedule..
9 i
i 11.6 Results...
9
]
11.7 Follow.Up Action......
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- 12. AMERICAN NATIONAL STANDARDS REFERRED TO IN THIS DOCUMENT.
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APPENDIX A. Seismic Design-All Systems..
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B. Seismie lnterface Chart..
11 C. Drawing issue Check Ust...
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AN54 N45 2.11-1974 AMERICAN NATION AL STANDARD QUALITY ASSURANCE REQUIREMENTS FOR THE DESIGN OF NUCLEAR POWER PLANTS
- 1. INTRODUCTION the provisions of this standard. The plant owner may delegate to other organizations the work of establish-l
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1.1 Scope ing and executing the quality assurance program, or any part thereof, but shall retain responsibility for This standard provides requirements and guidance overall program effectiveness. It is the responsibility for a quality assurance program for the design of of the plant owner and other organizations invoking nuclear power plant structures, systems and com-this standard to identify the structures, systems and ponents whose satisfactory and reliable performance components, and to specify the extent to which the is required:
provisions of this standard apply to such structures,
- 1. To prevent accidents that could cause undue systems and components.In no way shall the program risk to the health and safety of the public;or operate to diminish the responsibihty of any contrac-
- 2. To mitigate the consequences of such accidents tor for the quality of services furnished.
if they were to occur.
1.4 Definitions The requirements of this standard may also be ex-tended to other structures systems and components The following definitions are provided to assure a in whole or in part as specified by the purchaser, uniform understanding of select terms as they are This standard covers activities which affect the used in this standard.
i final design.
Design-Technical and management processes Tlus standard is tr. tended to be used in conjunction which commence with identification of design input with ANSI N45.2.
and which lead to and include the issuance of design output documents.
I Design Input-Those criteria, parameters, bases or 1.2 Applicability other design requirements upon which detailed final This standard applies to the plant owner, nuclear design is based.
steam supply system (NSSS) designer, architect en-Design Output-Documents such as drawings, spe-gineer or plant designer, and other organizations par-cifications and other documents defining technical re-ticipating in design activities affecting quality of items quirements of structures, systems and components as covered by this standard. The extent to which the in-delineated in Section 4.
dividual sections and elements of this standard are External Design Interface-Relationship between applied will depend upon factors such as the nature design groups from different companies. Examples are and scope of the work to be performed and the im-the interfaces between the plant owner and the portance of the structures, systems and components architect engineer or the plant owner and the NSSS to safe plant operation.
supplier, or the architect engineer and the NSSS sup-The ASME Boiler and Pressure Vessel Code (llere.
plier.
after referred to as the Code) as well as other ANSI Final Design-Approved design output documents Standards, has been considered in the deselopment of and approsed changes thereto.
this standard,and this standard is intended to be com.
Internal Design Interface-Relationship between patible with their requirements.
design groups or organizations within a company.
i llowever, this standard does not apply to ac.
Procedures-A document that specifies or describes tivities covered by Section Ill Division I and 2 and how an activity is to be performed. It may include Section XI of the Code for those activities covered by methods to be employed, equipment or materials to the Code, be used and sequence of operations.
1.3 Responsibili'ty 1.5 Referenced Documents It is the responsibility of the plant owner to pro-Other documents that are required to be included vide for the establishment and execution of a quality as part of this standard will be identified at the point assurance program for the plant design consistent with of reference and described in Section 12 of this 4
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C;v A UT ) AEM A%ci REC AEYINTt FOR TME DEDGN OF NUCLE AR FOV.L6 F L ANTS ANSI N45.2.11-19 74 standard. The issue or edition of the referenced docu-
- 13. Tabng corrective action (see Section 9).
ment that is required will be specified either at the
- 14. Mabng experience reports available to cog-point of reference or in Section 12 of this standard.
nizant design personnel.
- 15. Controlling design changes.
- 2. PROGRAM REQUIREMENTS
- 16. Other procedures as required by this standard.
2.1 Establishment and Documentation 2.3 Factors Considered A quality assurance prcgram for design shall be f the factors to be considered in establish.
S me established and documented to comply with the re.
mg the program include:
quirements of this Standard.
- 1. Nature of the organization such as the plant The program documents shall define the organiza.
wner, manufacturer, or architect.enpneer, and the tional structure within which the program is to be im-nature of the design interfaces among them.
plemented, and shall delineate the authority and re.
- 2. Importance of the design actaity to plant spcmsibility of the persons and organizations involved safety.
performing design activities affecting the qua'ity of
- 3. State of the art such as experimental, develop-
- design, mental, or standard design.
j The program documents shall identify the items
- 4. Nature of design activity such as conceptual, i
and semees and the specific activities to which this preliminary, detailed design or field engmeermg.
standard is applied. The design responsibilities and interfaces among the contributing organizations, both intemal and external, shall be identified.
- 3. DESIGN INPUT REQUIREMENTS Provisions shall be made in the program for i
periodic audits. review and evaluation of the effective.
3.1 General ness of the program in achieving quality objectives.
Applicable design inputs, such as design bases, j
Correction of deficiencies shall be an integral part of regulatory requirements, codes and standards, shall be the program.
identified, documented and their selection reviewed and approved. Changes from specified design inputs 2.2 Program Procedures includmg the reasons for the changes shall be Procedures shall be employed to assure that design identified, approved, documented and controlled.
activities are carried out in a planned, controlled The design input shall be specified on a timely orderly and correct manner. Program procedures shalj basis and to the level of detail necessary to permit the cover the following as applicable:
design activity to be carried out m a correct manner
- 1. Responsibilities of organizations involved in and to provide a consistent basis for making design the program, such as owner, A.E, NSSS supplier and decisi ns, accomplishing design verification measures, other contractors.
and evaluatmg design changes.
- 2. Responsibilities within design organizations.
- 3. Technical information exchanges across ex.
3.2 Requirements temal and intemalinterfaces.
- 4. Document control includmg review, approval, The design input shallinclude but is not limited to release, distribution, and revision.
the following, where apphcable:
- 5. Maintenance and retention of design docu.
- 1. Basic functions of each structure, system and ments.
component.
- 6. Management review of status and adequacy of
- 2. Performance requirements such as capacity, program.
rating, system output.
- 7. Necessary training of personnel performing
- 3. Codes. standards, and regulatory requirements
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activities covered by this standard.
including the applicable issue and/or addenda.
- 8. Identifying appropriate design input.
- 4. Design conditions such as pressure, tempera.
- 9. Preparation of design documents.
ture, fluid chemistry and voltage.
4
- 10. SpecifyiEg qualitylevels, acceptance standards,
- 5. Loads such as seismic, wind, thermal and and record requirements.
dynamic.
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- 11. Performance of design verifications.
- 6. Environmental conditions anticipated during
- 12. Conducting audits of design activities, their storage, construction and operation such as pressure, reporting and followup.
temperature, humidity, corrosiveness, site elevation, 2
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ANSI N45 211-1974 wind direction, nuclear radiation, electiomagnetic
- 27. Matenals, processes, parts and equipment radiation and duration of exposure.
suitable for application.
- 7. Interface requirements including dennition of
- 28. Safety requirements for preventing personnel 3
the functional and physicalinterfaces insolving struc-injury including such items as radiation hazards, re-tures, systems and components.
stricting the use of dangerous materials, escape pro-
- 8. Material requirements including such items as visions from enclosures, and grounding of electrical compatibihty, electrical insulation properties, protec-systems.
tise coating and corrosion resistance.
- 9. Mechanical requirements such as vibration,
- 4. DESIGN PROCESS stress, shock and reaction forces.
- 10. Structural requirements covering such items as 4.1 General equipment foundations and pipe supports.
Design activities shall be prescribed and accom-
- 11. Hydraulie requirements such as pump net positive suction heads (NPSil), allowable pressure plished in accordance with procedures of a type suf.
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& d@ ip m e drops, and allowable fluid selocities.
- 12. Chemistry requirements such as provisions for rectly translated into specifications, drawings, proce-dure's or instructions. Appropriate quality standards sampling and hmitations on water chemistry.
shall be identined, documented and their selection re-
- 13. Electrical requirements such as source of power, voltage, raceway requirements, electrical in.
viewed and approved. Changes from specified quality standards including reasons for the changes shall be I
ou dr ement equirements.
identified, approved, documented and controlled.
- 15. O[erational requirements under various condi-
. The design activities may be prescribed m, Job spe-tions, such as plant startup, normal plant operation, cifications, work instructions, planning sheets, proce-plant shutdown. plant emergency operation,special or dure manuals, test procedures, or any other type of infrequent operation, and system abnormal or emer-written form, which provides adequate control and gency operation.
pennits reviewing, checkmg or venfying the results of
- 16. Instrumentation and control requirements in-the activity by personnel who are experienced in the ciudmg indicating mstruments. controls and alarms re-subject activity.
quired for operation, testing, and maintenance. Other Methods shall provide for relating the final design
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requirements such as the type ofinstrumer.t. installed back to the source of design input. This traceability spares, range of measurement, and location ofindica-shall be documented m accordance with the require-tion should also be included.
ments of Section 10.
- 17. Access and administrative control requirements lhe design activities shall be documented in suf-for plant security.
ficient detail to permit verification and auditing as re-
- 18. Redundancy, diversity and separation require-quired by this standard.
ments of structures, systems and components.
4.2 Des.en Anew
- 19. Failure effects requirements of structures,sys-tems and components, including a definition of those Design analyses such as physics, stress, thermal, l
events and accidents which they must be designed to hydraulic and accident, shall be performed in a plan-withstand.
ned, controlled and correct manner.
- 20. Test requirements including in. plant tests and Design analyses shall be legible and be in a form l
the conditions under which they will be performed.
suitable for reproduction, filing and retrieving. Anal-l
- 21. Accessibility, maintenance, repair andinservice yses shall be sufficiently detailed as to purpose, inspection requirements for the plant includmg the method, assumptions, design input, references and conditions under which these will be performed.
units such that a person technically qualified in the
- 22. Personnel requirements and limitations in-subject can review and understand the analyses and cluding the qualification ar.d number of personnel verify the adequacy of the results without recourse to available for plant operation, maintenance. testing and the originator. Calculations shall be identifiable by inspection and permissible personnel radiation ex-subject (including structure, system, or component to posures for specified areas and conditions.
which the calculation applies), originator, reviewer and
- 23. Transp,ortability requirements such as size and date; or by other data such that the calculations are shipping weight, limitations, I.C.C. regulations.
retrievable. Procedures shallinclude requirements for:
- 24. Fire protection or resistance requirements.
- 1. Identifying documents to permit ready refer-i j
- 25. Handling. storage and shipping requirements.
ence and retrieval.
- 26. Other requirements to prevent undue risk to
- 2. Defining the objective of the analyses.
the health and safety of the public.
- 3. Definition of design input > and their sources.
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- 4. Documenting the results ofliterature scarches
- 7. Nonconformance with design document re-t or other apphcable background data.
quirements.
- 5. Documenting assumptions, and identifying
- 8. Storage and control of originals or master those assumptions that must be verified as the design copies.
proceeds.
- 6. Identification of computer calculations, in-cluding computer type, code or programming inputs
- 5. INTERFACE CONTROL and outputs.
- 7. Review and approval.
5.1 External 5.1.1 Identification of Interface. The external 4.3 Drawings interfaces between organizations performing work af-Procedures shall be established for the preparation fecting quality of design shall be identified in writing ard control of drawings. Typical subjects to be covered and shallinclude those organizations providing criteria, by such procedures are:
designs, specifications and technical direction.
j-
- 1. Drafting room standards.
- 2. Standardized symbols.
5.1.2 Responsibilities. Responsibilities for organi-
- 3. Identification system.
zations shall be defined and documented in sufficient
- 4. Indication of status.
detail to cover the preparation, review and approval
- 5. Checking methods.
of documents involving design interfaces. Respon-
- 6. Review and approval requirements.
sibilities may be set forth in tabular form or flow I
- 7. Issuance and distribution.
charts accompanied by appropriate text to clarify the intent A pendices A and B provide examples.
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- 8. Storage and control of originals or master P
copies.
5.1.3 Lines of Communication. Systematic meth-
- 9. Revisions.
ods shall be established for communicating needed
- 10. As-built drawings.
design information across external design interfaces,
- 11. Nonconformance with drawing requirements.
including changes to the design information as work progresses. Documents shall identify the positions and 4
4.4 Specifications titles of keypersonnelin thecommunication channels Procedures shall be established for the preparation and their responsibilities for decision-making, for I
f roblems, for providing and reviewing re5 luti n P
and control of specifications. Typical subjects to be covered by such procedures are:
inf rmation, and for taking other action within the
- 1. Format requirements.
SC Pe of this standard.
- 2. Identification system.
5.1.4 Documentation. Procedures shall be estab.
- 3. Review and approval requirements.
lished to control the flow of design information be-
- 4. Issuance and distnbution.
tween organizations. Design information transmitted
- 5. Revisions.
from one organization to another shallbe documented
- 6. Indication of status.
In specifications, drawings or other controlled docu-
- 7. Nonconformance with specification require-ments which are uniquely identified and issued by ments.
authorized persons. The p:ocedures shall provide that
- 8. Storage and control of origmals or master design interface information be transmitted to affected copies.
organizations and that any information requested in the design interface transmittal be transmitted back to 4.5 Other Design Documents tk or@natothmentauon requesMg ermadon or action shall be controlled by a system which as-Procedures shall be established for the preparation sures that the response and the request can be related.
and control of other design documents such as instal-Where it is necessary to initially transmit design in.
lation instructions and test procedures. Typical sub-formation orally or by other informal means, the jects to be covered are:
transmittal shall be confirmed promptly by a con-
- 1. Format requirements.
trolled document.
- 2. Identification system.
- 3. Review and approval requirements.
5.2 Internal
- 4. Issuance and distribution.
S. Revisions.
5.2.1 Identification of Interface. Each organiza.
- 6. Indication of status.
tion performing work affecting quality of design shall 4
_ ~ _ _
2 i ai w e te !, +, s y J
.W. t i KAibi JJ,i' ANSI N4fs.711-1974 6
identify m writing its internal design interfaces for venfication methods identified by the responsible managing the Dow of design information between or.
design organization.
ganizational units.
6.2 Mnt 5.2.2 Responsibilities. Responsibilities for each organizational unit shall be defined and documented The extent of the design verification required is a in sufficient detail to cover the preparation, review, function of the importance to safety of the item approval, distnbution and revision of documents in-under consideration, the complexity of the design, volving design interfaces.
the degree of standardization, the state-of.the art, and the similarity with previously proven designs. How.
5.2.3 Lines of Communication. Systematic meth.
ods shallbe estabhshed for communicating needed de-ever, the applicability of standardized or previously pr ven designs, with respect to meeting pertinent de-sign informatmn across the internal design interfaces, sign inputs,includmg ermronmental conditions,shall
.includmg changes to the design information as work be verified for each apphcation.Where the design of a F *E'#55'5-particular structure, system, or component for a j
5 2.4 Documentation. Procedures shall be estab.
particular nuclear power plant has been subjected to a i
hshed to control the Dow of design information be-verification process in accordance with this standard, tween orgamzational units. Design information trans-the verification process need not be duplicated for mitted from one organizational unit to another shall identical designs. However, known problems affecting 1'
be documented and controlled. Transmittals shall the standardized design and their effects on other identify the status of the design information or docu-features shall be considered. The original design and ment provided and, where necessary, identify in.
associated verification measures shall, however, be complete items which require further evaluation, re-adequately documented and referenced in the files of view or approval. Where it is necessary to initially subsequent application of the design.
transmit design mformation orally or by other in.
Where changes to previously verified designs have form.1 means, the transmittal shall be confirmed been made, design verification shall be required for promptly by a controlled document.
the changes, including evaluation of the effects of those changes on the overall design.
i t
- 6. DESIGN VERIFICATION The responsible design organization shallidentify j
6.1 General and document the particular design verification meth-i Measures shall be apphed to verify the adequacy of ds to be used. Acceptable verification methods in-clude but are not limited to:
design. Design verification is the process of reviewing, l
confirming, or substantiating the design by one or L Design reviews-
- 2. Altemate calculations-more methods to provide assurance that the design meets the specified design inputs.
- 3. Qualification testing-Design verification shall be performed by any com-6.3.1 Design Reviews. Design reviews are critical pctent indmduals or groups other than those who reviews to provide assurance that design documents performed the origmal design but who may be from such as drawings, calculations, analyses or specifica.
the same organization. This serification may be per-tions are correct and satisfactory. Design reviews can formed by the originator's supervisor provided the range from muhi organization reviews to single per-supervisor did not specify a singular design approach, son reviews. The depth of review can. range from a or rule out certain design considerations and did not detailed check of the complete design to a limite_d establish the design inputs used in the design, or if check of such_ things as the design approach and the the supervisor is the only individual in the organiza-results obtained. The results of the review shall be tion competent to perform the verification. Cursory documented and measur.es taken to ensure th.at the supervisory reviews do not satisfy the intent of this findings are implemented. Whether the review is con-standard. Design verification may vary from spot ducted by one individual or a multi-organization there checking of carchlations to actual tests in the tield.
are a number of basic questions that shall be ad-The results of design verification efforts shall be dressed such as:
clearly documented, with the identification of the
- 1. Were the inputs correctly selected and in-verifier clearly indicated thereon, and filed. Docu.
corporated into design? (See paragraph 3.2).
mentation of results shall be auditable against the
- 2. Are assumptions necessary to perform the de-5
t i
ON J14 AM Uh A*.c f 0.i L U4H E * *f N1 b F F THE DESIGN OF r,UCLE AR POWEH PL ANlb A*sSi NE 711 - 197.t i
sign activity adequately desenbed and reasonable?
The alternate method used for comparison may be
%here necessary, are the assumptions identified for a more simphfied approach or less rigorous, such as subsequent re verifications when the detailed design when a hand calculation is used to check the computer activities are completed?
code output. Although the simplified or less rigorous
- 3. Are the appropriate quality and quahty as-method may not exactly check the original calcula-surance requirements specified?
tion or analysis, it must provide results consistent
- 4. Are the applicable codes, standards and regu-with the original calculation or analyses.
latory requirements including issue and addenda 6.3.3 Qualification Testing. Design verification for properly identified and are their requirements for some designs or specific design features can be design met.
achieved by suitable quahfication testing of a proto-
- 5. Have appheable construction and operatmg ex-type or initial production unit.
penence been considered?
In those cases where the adequacy of a design is to
- 6. Have the design interface requirements been be verified by a quahfication test, the testing shall be satisfied?
identified and documented. Testing shall demonstrate
- 7. %.as an appropriate design method used?
adequacy of performance under the most adverse de-
- 8. Is the output reasonable compared to inputs?
sign conditions. All pertinent operating modes shall be
- 9. Are the specified parts, equipment, and considered in determining these design conditions processes suitable for the required application?
where it is intended that the test program confirm the
- 10. Are the specified materials compatible with adequacy of the overall design. %here the test is only each other and the design environmentalconditions to intended to venfy a specific design feature,the other which the r6aterial will be exposed?
features of the design shall be verified by other
- 11. Hase adequate maintenance features and re-means. For example, it may be most effective to quirements been specified?
verify that an instrumentation cabinet is designed to
- 12. Are accessibihty and other design provisions withstand the maximum earthquake-caused vibratory adequate for performance of needed maintenance and motions by actually subjectmg the cabinet and its as-repair.
sociated components to shaker tests which correspond
- 13. Has adequat: accessibility been provided to to these vibratory motions. The shaker tests will not, perform the in-service inspe: tion expected to be re-however, verify that the circuitry is designed correct-l quired during the plant life?
ly, or that the component in the cabinet will perform
- 14. Has the design properly considered radiation its intended function. Other tests or verification i
exposure to the public and plant personnel?
means are required to confirm that remaining design
- 15. Are the acceptance criteria incorporated in the functions are adequately performed by the instru-design documents sufficient to allow verification that mentation and that those components perform the in-design requirements have been satisfactorily accom-tended functions for the varying design conditions to plished?
which Bey are subjected.
- 16. Have adequate pre operational and subsequent Qualification testir g shall be performed in accord-periodic test requirements been appropriately spe-ance with written test procedures which incorporate cified?
or reference the requirements and acceptance hmits
- 17. Are adequate handling. storage, cleaning and contained in applicable design documents. The test shipping requirements specified?
procedures shall include provisions fnr assuring that
- 18. Are adequate identification requirements spe-prerequisites for the given test have been met, that cified?
adequate instrumentation of the required range and
- 19. Are. requirements for record preparation re-accuracy is available and used, and that necessary view, approval, retention, etc., adequately specified?
monitoring is performed. Prerequisites include such 6.3.2 Alternate Calculations. Verification of some items as calibrated instrumentation, appropriate types of calculations or analyses may be achieved by equipment, trained personnel, condition of test equip-comparison with attemate methods of calculation or ment and the item to be tested, suitable environ-analyses. This shall be performed by a person or per.
mental conditions and provisions for data acquisition.
sons other than those who performed the original Test results shall be documented and evaluated by the calculation. Where altemate calculations are per.
responsible designer to assure that test requirements formed to verify the correctness of the original cal.
have been satisfied.
culation a review shall also be performed to address If testing indicates that modifications to the item the appropriateness of assumptions, input data, and are necessary to obtain acceptable performance, the the code or other calculation method used, modification shall be documented and the item 6
--n
G tc im I
a it
.m r i ! L i. ON D5 f.Uc L t Ab i W,[i i A.Tb ANSI N45 711.1974 j
i 4
mod:Ged and retested or otherwise venfied to assure receipting system is Appendix C, Drawing issue Check satisfactory performance. % hen tests are being per.
- List, formed on models or mock ups, scahng laws shall be
- 5. Estabhshing distribution hsts which are up-established and verified. The test configuration shall dated and maintained current to assure that the proper be clearly dermed and documented. The results of personnel are.ent all the required documents to per-model test work shall be subject to error analysis, form the work.
where appbcable, prior to use in final design work.
7.2 Document Revision Significant changes to documents shall be re-
- 7. DOCUMENT CONTROL viewed and approved by the same organizations that Documented procedures sha!! be used to control perf rmed the original review and approval unless issuance of design documents and changes thereto.
ther organizations are specifically designated.The re-These procedures shall assure that documents, in-viewing rganizati ns shall have access to pertinent cluding changes, are reviewed for adequacy and background data mformation upon which to base approved for release by authorized personnel and are their approval. However, minor changes to design properly distnbuted, documents, such as inconsequential editorial correc-tions or changes to commercial terms and conditions, 7.1 Document Preparation, Approval and issue may not reqyire that the revised document receive the same review and approval as the original docu-Personnel shall be made aware of and use proper ments. To avoid a possible omission of a required re-and current mstructions, procedures, drawings and view, the type of minor changes which do not require design in~ puts. Participating organizations shall have such a review and approval and the persons who can i
documented procedures for control of design docu.
authorize such a decision shall be clearly delineated in ments and changes thereto to assure that current and the document control procedures.
appropriate documents are available for use. The document control procedures shall provide for:
- 1. Identification of personnel positions or organi-
- 8. DESIGN CHANGE CONTROL i
zations responuble for prepanng, reviewing, approving and issuing documents and revisions thereto. This
. Documented procedures shall be provided for de-i i
identification may take the form of Project General sign changes to approved design documents, including Instructions, design organization Policy Statements, a field changes, which assure that the impact of the matnx showing document type against function, or change is carefully considered required actions docu-other written forms appropriate to the organizational mented and information conceming the change is method of performing the design process.
transmitted to all affected persons and organizations.
- 2. Identification of the proper documents to be These changes shall be justified and subjected to design used in performing the design. The identification c ntrol measures commensurate with those apphed to should include title applicable revisions, date ofissue th, original design.
i or any other relevant information that would precise.
ly identify the document to be used.
8.1 Reasons b Changes
- 3. Coordination and control of design (mternal Design changes frequently result from such things and external) interface documents. These interface as the following:
documents should be mutually agreed to and prepared
- 1. Qualification,preoperational.oroperational test in sufficient detail to assure that the required reviews results are not satisfactory.
and approvals are accomplished.
- 2. Interference problems discovered during con-
- 4. Ascertaining that proper documents are ac, structicn.
cessible and are in fact being used. This might be ae.
- 3. Failures of structures, systems, or components complished by several schemes including the follow-to meet functional requirements.
ing examples: periodic issuance of master drawing or
- 4. Dispositior. of nonconfonning items.
specification lists showing the latest applicable revi-
- 5. Changes m reFulatory or other requirements.
sion (such lists could provide a reference for auditing
- 6. Operational experience.
the accessibility and use of the latest documents),or
- 7. Design improvements.
some type of receipting system can provide assurance that the latest documents have been received and ob-8.2 Review of Changes solete revisions recalled. An example of such a Normally. the procedures for effecting design 7
i
h 1
m. n. A n m.. i s.1 e m. i v t. -
4.
T hi DE Lia Of r,K L t A4 rw,I E F t t *.-n um r,4., p 11_1974 changes shall require that the documents which reflect formed in accordance witu the requirements of tlus i
the design change be reviewed and approved by the standard shall be collected, stored and maintained in same groups or orFanizations which reviewed and accordance with the requirements of ANSI N45.2.9.
approved the original design documents. Where an The documentation shallinclude not only the fmal organization which origmally was responsible for design documents such as drawings and specifications, approving a particular design document is no longer and revisions thereto but also records of the important responsible, the plant owner shall designate the new steps including sources of design inputs, which sup.
responsible organization which may be the owner's port the fmal design. The records shall be legible, own engineering organization. The designated organi-identifiable and retrievable.
zation shallhave access to pertinent background infor.
Documentation and records will be either of the mation,have demonstrated competence in the specifie lifetime or nonpermanent category as defined in design area of interest and have m adequate under-ANSI N45.2.9.
standing of the requirements and intent of the original design.
i
- 11. AUDITS
- 9. CORRECTIVE ACTION A comprehensive system of planned and docu.
i mented audits shall be carned out to verify com.
In addition to correcting a deficiency (or error),
pliance with all aspects of the Quality Assurance corrective action also includes, for significant or recur-program for design including those procedures dehne.
nng deficiencies (or errors), determining the cause and ating quabty assurance actions required during the de.
instituting appropriate changes in the design process sign process.
and the quality assurance program to present similar types of deficiencies (or errors) from recurring. A 11.1 Personnel procedure shall be employed for providing such cor.
rective action. This procedure shall also contam provi.
These audits shall be performed in accordance with sions for reporting the deficiency and correctivt ac.
written procedures or check bst by personnel not tion to appropriate levels of supervision and manage.
having direct responsibihties in the areas being ment. The procedure shall also include follow up audited. For example, the person who performs as actions that cannot be immediately completed to as-audit on design venfication should not have been re.
sure timely resolution and/or completion of the cor.
&b h
fi h
r
- l rective action.
personnel performing audits shall be of a level of com.
petency and have suf ficient authority and organiza.
)
9.1 Detection of Errors tional freedom to make the audit process meatungful and effective.
Deficiencies or error in the design or the design quality assurance program may be detected by:
11.2 Internal Audits
- 1. Design venfication measures.
- 2. Personnel using the design documents.
Design organizations performing work in accord.
- 3. Audits.
ance with the requirements of this standard shall be
- 4. Tests conducted.
audited to assure that their design quahty assurance
- 5. Actual failure during operation.
Programs are being implemented. Audits may be con.
- 6. Other means.
ducted internally by the design organization or by a unit independent of the design orgamration.
9.2 Review of Procedure 11.3 External Audits Where a significant design char re is necessary be.
I cause of an mcorrect design, the design process and Organizationsshallconduct or delegate the conduct verification procedure shall be reviewed and modified of extemal audits of design organizations performing
'5"'"55Y" work for them to assure that specified design quahty assurance program requirements are being imple.
mented and are effective.
- 10. RECORDS 11.4 Audit Control Design documentation and records which provide Audits shallinclude an evaluation of design quahty evidence that the design and review process we per.
assurance policies. practices, procedures and mstrue.
t b
i 4
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THE DE5sf.A 05 NUL LE Ah POV,Lh PL ANTS ANSI Neb 2.11-19 74 1
i tions; the effectiveness of implementation, and ac.
and nonconformances in the quality assurance tions taken to correct deficiencies in the program.
program.
The audits should include the examination of design
- 5. When a systematic, independent assessment of activities, processes and documents and records. An program effectiveness or item quahty or both is con.
l audit plan shall be developed and should identify the sidered necessary.
functional areas to be audited, the extent of audit
- 6. % hen it is considered necessary to verify im.
withm these areas to determine efrectiveness, the piementation of required corrective actions.
names and assignments of those who will perform the audit, the scheduhng arrangements and the method 11.6 Results q
of reporting fmdmgs and recommendations.
Audit results shall be documented and reviewed by 115 Audit Schedule "E
E ' 'I "I
Audit reports shall be in sufficient detail to permit Audits should be conducted on a routine basis to management evaluation of the breadth of the audit as estabbsh the adequacy of and conformance to the well as the validity of the findings.
design q abty assurance requirements. Audits should also be conducted when one or more of the following 11.7 Follow-up i
conditions exists:
- 1. % hen it is necessary to determine the capability Appropriate corrective action and timely follow.
of a subcontractor's quality assurance program pnor up action, including re audit of deficient areas, shall to awardmg of contract or purchase order for design be taken where indicated by the audit rmdings.
services.
- 2. % hen, after award of contract, sufficient time
- 12. AMERICAN NATIONAL STANDARDS j
i has elapsed for the implementation of the quality as.
REFERRED TO IN THl3 DOCUMENT surance program for design and it is appropriate to de.
% hen the fellowing standards referred to in this termine that the organization is performing the func.
document are superseded by a revision approved by tions as defined in the quahty assurance program de.
the American National Standards Institute, the revi.
scription, codes, standards and other contract docu.
sion shall apply.
q ments.
N45.2 Quality Assurance Requirements for j
- 3. % hen significant changes are made in functional Nuclear Power Plants.
i areas of the quahty assurance program for design in.
N45.2.9 Requirements for Collectien, Storage i
t cluding significant reorgaruzations and procedure and Maintenance of 0uahty Assarance revisions.
Records for Nuclear Power Plants.
- 4. When it is suspected that safety related per.
N45.2.10 Quahty Assurance Terms and Defini.
formance of the item is mjeopardy due to deficiencies tiont i
i l
i r
4 I
l
~* O APPENDIX A l';
DIVISION OF RESPONSIBILITIES Eh r-SYST E M/COMPONE NT/ST RUCTU R E : Seismic Demys-All Systems 9,t PROKCT:
N CONTRACT / PURCHASE ORDER:
b!
P2 pT 7b 2=
LEGEND OWNER 3k ARCHITECTENGINEER (AK)
?3 REACTOR MANUFACTURER (NSSSI yj SU8 CONTRACTOR (SUS)
" 7" W h'Y Seienes/
Seimnic Some Egeip. Leeel Seiminic
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Regenes
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ComRnesseen
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- 2. Reactor So.id.no 0-nor
. Am Am Am Am Am O mer
NSSS Oumer
- 4. NS$$ Piping Restraints and t=aarts Oumer AK NSSS A K *rSSS Oumer
- 6. NoMtSSS Piping Restreints & Supports Ouener N
AK AK AM Ommer
f.
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APPENDIX B
-o Ie DIVISION OF RESPONSIBILITIES
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APPENDIX C PROJECT DMAWING ISSUE CHECK LIST me onoe n nu.ei n s999-r To osia JONN DOE - CONS T. SUPT.
t22 p.72 saou JOHN SMITH - NWECT ENGINEEM THE FOLLOWING DRAWINGS HAVE BEEN SENT TO YOU SINCE
# 72 PLEASE REVIEW YOUR RECENT RECEIFTS OF DRAWINGS AND CHECK THE APPROPRIATE COLUMN AS TO WHETHER YOU HAVE RECEIVED THEM OR NOT. INITIAL AND DATE THIS FORM WHERE I..JICATED. RETURN THE MAR KED ORIGIN AL TO ME IMMEDIATELY. KEEP THE COPY FOR YOUR RECORDL.
DRAWING NO ISSUE E((s70%
DR A*NG NO IS$UE R [aE".t o DRamNG NO IS$ul ff[a$$$
f t a cLUO'NG J O I NO it ECLUDING J OJ NO.
(E aCLUDING J O I NO vs5 no
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V I cert @ that the prev %s revisens of the docurnents.end dremngs have been recalled or accounted for; Signature - Oete IMMRTANT 12
.