AMERICAN NATIONAL STANDARDREACTOR PLANTS AND THEIR MAINTENANCE

Quality Assurance Requirementsfor the Design of NuclearPower Plants

ANSI N45.2.11-1974

SECRETARIAT

THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS

PUBLISHED BY

THE A ME R ~ CAN SO C lET Y 0 F M E C HAN I CAL ENG I NEE R S

United Engineering Center 345 East 47th Street New York, N. Y. 10017

AMERICAN NATIONAL STANDARD

An American National Standard implies a consensus of those substantially concerned withits scope and provisions. An American National Standard is intended as a guide to aid themanufacturer, the consumer, and the general public. The existence of an American Na­tional Standard does not in any respect preclude anyone, whether he has approved thestandard or not, from manufacturing, marketing, purchasing, or using products,processes, or procedures not confonning to the standard. American National Standardsare subject to periodic review and users are cautioned to obtain the latest editions.

CAUTION NOTICE: This American National Standard may be revised or withdrawn atany time. The procedures of the American National Standards Institute require that actionbe taken to reaffirm, revise, or withdraw this standard no later than five years from thedate of publication. Purchasers of American National Standards may receive current infor­mation on all standards by calling or writing the American National Standards Institute.

This standard was approved by the American National Standards Committee N45 and itsSecretariat, and it was subsequently approved and designated N45.2.11-1974 by theAmerican National Standards Institute on June 6,1974.

No part of this document may be reproduced in any form, in an electronicretrieval system or otherwise, without the prior written permission of thepublisher.

Copyright © 1974 byTHE AMERICAN SOCIETY OF MECHANICAL ENGINEERS

Printed in U.S.A.

FOREWORD

(This Foreword is not a part of The American National Standards Institute Standard for the QualityAssurance Requirements for the Design of Nuclear Power Plants.)

This standard delineates the minimum quality assuraru;e requirements to be implemented during the de­sign of nuclear power plants. The standard was developed by the American National Standards CommitteeN45 on Reactor Plants and their Maintenance. This committee has been chartered to promote the develop­men t of standards for the location, design, construction, and main tenance of nuclear reactors and plan tsembodying nuclear reactors, including equipment, material, methods and components specifically for thispurpose.

In April of 1970, the N45 Committee established a subcommittee, N45·3, to guide the preparation ofnuclear quality assurance standards. This subcommittee is responsible for establishing guidelines and policyto govern 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 submittalto the N45 Committee for balloting.

In October 1971, the N45·3 Subcommit tee established a working group, N45-3 .11, on Quality AssuranceRequirements for the Design of Nuclear Power Plants. The purpose of this working group was to prepare astandard for general industry use that would define the quality assurance requirements to be implementedduring the design of nuclear power plan tS. TIle work group was composed of represen tatives of key segmen tsof the nuclear industry including electric utilities, nuclear energy system suppliers, engineers, constructorsand the Atomic Energy Commission. The standard contained herein was prepared by this work group.

Working with the N45-3 Subcommittee and concurrently with the development of this standard by theN45.3.11 working group, other working groups of N45 are developing a series of standards that set forthboth general and detailed technical provisions for certain activities to assure quality of nuclear power plan ts.These requirements will be coordinated with the requirements of this standard as they are developed.

In October 1972, the N45·3 Subcommittee was renamed N45-2, and the work groups were renamed ac­cordingly. As of September 1973, the following associated standards were in preparation or issued:

WorkGroup

N45.2

N45-2.1· N45.2.l

N45-2.2 N45.2.2

N45-2.3 N45.2.3

N45-2.4 N45.2.4

N45-2.4

N45·2.6

N45.2.5

N45.2.6

Standard in Preparation

Quality Assurance Program Requirements for Nuclear Power Plants

Cleaning of Fluid Systems and Associated Components During the ConstructionPhase of Nuclear Power Plants.

Packaging, Shipping, Receiving, Storage, and Handling of Items for NuclearPower Plants (During the Construction Phase).

Housekeeping During the Construction Phase of Nuclear Power Plants.

Supplementary Quality Assurance Requirements for Installation, Inspection andTesting of Instrumentation and Electric Equipment During the Construction ofNuclear Power Generating Stations.

Supplementary Quality Assurance Requirements for Installation, Inspection andTesting of Structural Concrete and Structural Steel During the ConstructionPhase of Nuclear Power Plants.

Qualifications of Inspection, Examination and Testing Personnel for the Con·struction Phase of Nuclear Power Plants.

iii

N45-2.9 N45.2.9

N45-2.10 N45.2.10

N45-2.12 N45.2.12

N45-2.13 N45.2.13

N45-2.14 N45.2.14

N45·2.2 N45.2.15

N45·2.4 N45.2.16

N45·2.17 N45.2.17

WorkGroup

N45-2.8 N45.2.8

Standard in Preparation

Supplementary Quality Assurance Requirements for Installation, Inspection andTesting of Mechanical Equipment and Systems for the Construction Phase ofNuclear Power Plants.

Requirements for Collection, Storage and Maintenance of Quality AssuranceRecords for Nuclea r Powe r Plan ts.

Quality Assurance Terms and Definitions.

Requirements for Auditing Quality Assurance Programs for Nuclear PowerPlan ts.

Quality Assurance Requirements for Control of Procurement of Equipment,Materials and Services for Nuclear Powe r Plan ts.

Design and Quality Assurance Requirements During the Manufacture of Class IEInstrumentation and Electric Equipment for Nuclear Power Generating Stations.

Requirements for the Control of Hoisting, Rigging and Transporting of Hems atNuclear Power Plant Sites.

Supplementary Requirements for the Calibration and Control of Measuring andTest Equipment used in the Construction and Maintenance of Nuclear Facilities.

Quality Assurance Requirements for Control of the Welding Process for NuclearPower Plant Construction.

Suggestions for improvement gained in the use of this standard will be welcomed. They should be sent toThe American Society of Mechanical Engineers, 345 East 47th Street, New York, N.Y. 10017.

iv

AMERICAN NATIONAL STANDARDS COMMITTEE N45*Reactor Plants and Their Maintenance

OFFICERS

Sol Buntain. Chairman Willi.." de MIJurillC. Vice-ChairmanJ. C. Rus. Secretllry

COMMITTEE PERSONNEL

AMERICAN FEDERATION OF LABOR AND CONGRESS OF INDUSTRIAL ORGANIZATIONSP. R.Shoop, International Brotherhood of Electrical Workers, Washington, D.C.

AMERICAN NUCLEAR SOCIETYJ. S. Moore, Westinghouse Electric Corporation, Pittsburgh, PennsylvaniaJ. R. Rohln, North American Rockwell, Canoga Park, California

AMERICAN SOCIETY OF CIVIL ENGINEERSA A. Ferliro, Ebasco Services, New York, New YorkC B. Miczek, Altemste, Stone and ,Webster Engineering Corporation, Boston, Massachusetts

AMERICAN SOCIETY OF MECHANICAL ENGINEERS, THEE. C &liley, Commonwealth Edison Company, OUcago, IllinoisV. S. 8oyer, Philadelphia Electric CompanYJ Philadelphia, PennsylvaniaH. F. Brush, Bechtel Corporation, San Francisco, CaliforniaSol Burstein, Wisconsin Electric Power Company, Milwaukee, Wisconsin

AMERICAN WELDING SOCIETYJ. R. Me Guffey, Union Carbide Corporation, Oak Ridge, TennesseeH. E. Brpadbent, Alternate, American Welding Society, Miami, Florida

ATOMIC INDUSTRIAL FORUM, INC.D. W. Montgomery, Babcock & WI.1cox, Lynchburg, Virginia

EDISON ELECTRIC INSTITUTE-ELECTRIC LIGHT AND POWER GROUP. R. W. Clement, Consolidated Edison Company of New York, Incorporated, New York, New York

H. 8. Ray, Alternate, Southern California Edison Company, Los Angeles, CaliforniaG. A. Olson, Alternate, Edison Electric Institute, New York, New York

HEALTH PHYSICS SOCIETYT. J. Burnett, Oak Ridge National Laboratory, Oak Ridge, Tennessee

INSTITUTE OF ELECTRICAL AND ELECTRONICS ENGINEERSM. OIken, American Electric Power Corporation, New York, New YorkJ. C Ru", General Electric Company, San Jose, California

INSTRUMENT SOCIETY OF AMERICAH. C. Copeland, Douglas United Nuclear, Incorporated, Richland, WashingtonT. M. Clement, Alternate, Douglas United Nuclear, Incorporated, Richland, Washington

MANUFACTURING CHEMISTS' ASSOCIATION, INCORPORATEDJoe Haags, Jersey Nuclear Company, Bellevue, Washington

NUCLEAR ENERGY PROPERTY INSURANCE ASSOCIATIONR. P. Day. Nuclear Energy Property Insurance Association, Hartford, ConnecticutJohn J. Carney, Alternate, Nuclear Energy Property Insurance Association, Hartford, Connecticut

U.S. ENVIRONMENTAL PROTECTION AGENCYJ. E. Martin, U.S. Department of Environmental Protection Agency, Rockville, MarylandE. D. Hllrward, Alternate, U.S. Department of Environmental Protection Agency, Rockville, Maryland

*As of August 14, 1973.

v

TRAVELERS INSURANCE COMPANY. THEF. W. Catudal, The Travelers Insurance Company, Hartford, Connecticut

U.S. ATOMIC ENERGY COMMISSIONRobert Minogutl, U.S. Atomic Energy Commission, Washington, D.C.

.Wilbur Morrison, Alternate, U.S. Atomic Energy Commission, Washington, D.C.Robert E. Yoder, Division of Operational Safety, U.S. Atomic Energy Commission. Washington, D.C.

INDIVIDUAL MEMBERSS. A. Bernsen, Bechtel Corporation, San Francisco. CaliforniaW. F. F.rguson, Oak Ridge National laboratory, Oak Ridge, TennesseeD. L. Leone, Sargent & Lundy Engineers. Chicago, IllinoisHarold Lichtenberger, Combustion Engineering, Inc., Windsor, ConnecticutI. H. Mandi!, Washington, D.C.Donald E. Vandenburgh, Yankee Atomic Electric Company, Westborough, Massachusetts

SUBCOMMITTEE ON NUCLEAR QUALITY ASSURANCE N45-2

S. A. Bernsen, Chairman, Bechtel Corporation, San Francisco, CaliforniaJ. W. Anderson. Secretary. Oak Ridge National Laboratory. Oak Ridge, TennesseeB. G. Avers. General Public Utilities Services Corporation, Parsippany, New JerseyR. S. 8IIin, Pacific Gas & Electric Company, San Francisco, CaliforniaGene Basile. United States Testing Company, Inc., Hoboken, New JerseyA. BI8i_is. United Engineers & Constructors, Boston, MassachusettsS. A. Caslake. Westinghouse Electric Corporation, Pittsburgh, PennsylvaniaA. W. Crevasse. 'Tennessee Valley Authority. Chattanooga, TennesseeR. L. Dick. Duke Power Company, Charlotte, North CarolinaH. F. Dobel. Babcock & Wilcox, Lynchburg, VirginiaW. F. Ferguson. Oak Ridge National Laboratory, Oak Ridge, TennesseeJ. W. Hal/owel/. Westinghouse Electric Corporation, Pittsburgh, PennsylvaniaA. K. Hasija. MealujNelia Engineering Dept., New York, New YorkS. K. Hel/man, The Ralph M. Parson Co., Los Angeles. CaliforniaE. J. Hemzy. Commonwealth Edison Company, Chicago, IllinoisW. C Herman. Ebasco Services. Inc.• New York. New YorkJ. H. Hicks. Babcock & Wilcox, Lynchburg, VirginiaJ. P. Jackson. Gulf General Atomic, San Diego. CaliforniaG. S. Keeley. Consumers Power Company, Jackson. MichiganJ. P. Knight. Tennessee Valley Authority, Knoxville, TennesseeM. E. Langston. U.S. Atomic Energy Commission, Washington, D.C.D. G. Long. General Electric Company, San Jose, CaliforniaW. M. Morrison, U.S. Atomic Energy Commission, Washington, D.C.Gerald Schierberg, Stone & Webster Engineering Corporation, Lycoming, New YorkJ. E. Wahler. Combustion Engineering. Windsor, ConnecticutF. W. Knight. Westinghouse Electric Company, Pittsburgh, Pennsylvania

vi

The Work Group N4S.2.11, included the following personnel during the development of this standard:

A. Bleiweis, Chairman, United Engineers & Constructors, Inc.M. M. Glatzer, Secretary, Combustion Engineering. Inc.

G. Nugent, Burns & Roe, Inc.S. Barnes, Consolidated Edison Co. of New York, Inc.R. H. Beers, General Electric CompanyC. W Dick, Bechtel Power CorporationD. R. Grain, Westinghouse Electric CorporationG. P. Field, American Electric Power Service CorporationJ. P. Moore, Jr., General Public Utilities ::-ervice CorporationW M. Morrison, Atomic Energy CommissionD. H. Rhoads, Jr., United Engineers & Constructors Inc.G. L. Stiehl, Gulf General AtomicC. R. Healy, EBASCO ServicesA. Cygleman, resigned, Burns & Roe, Inc.

vii

CONTENTS

Page

1. INTRODUCTION .

1.1 Scope .1.2 Applicability .1.3 Responsibility .1.4 Definitions .1.5 Referenced Documents .' .

2. PROGRAM REQUIREMENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

2.1 Establishment and Documentation. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22.2 Program Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22.3 Factors Considered .- . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

3. DESIGN INPUT REQUIREMENTS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

3.1 General 23.2 Requirements...................................................... 2

4. DESIGN PROCESS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3

4.1 General.......................................................... 34.2 Design Analyses. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34.3 Drawings ·......................... 44.4 Specifications..................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . 44.5 Other Design Documents. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

5. INTERFACE CONTROL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

5.1 External......................................................... 45.2 Internal.......................................................... 4

6. DESIGN VERIFICATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

6.1 General.......................................................... 56.2 Extent.......................................................... 56.3 Methods......................................................... 5

7. DOCJJMENT CONTROL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

7.1 Document Preparation, Approval and Issue. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77.2 Document Revision. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

8. DESIGN CHANGE CONTROL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

8.1 Reasons for Changes. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 78.2 Review of Changes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

ix

Page

9. CORRECTIVE ACTION : . . . . . . . . . . . . . . . . . . . . . . . . . 8

9.1 Detection of Errors. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89.2 Review of Procedure. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

10. RECORDS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

11. AUDITS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

11.1 Personnel........................................................ 811.2 Internal Audits. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 811.3 External Audits. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8IIA Audit Control. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 811.5 Schedule : . 911.6 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 911.7 Follow.Up Action. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9

12. AMERICAN NATIONAL STANDARDS REFERRED TO IN THIS DOCUMENT. . . . . . . . . . . . 9

APPENDIX

A. Seismic Design-All Systems. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 10B. Seismic Interface Chart IIC. Drawing Issue Check List . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 12

x

ANSI N45.2.11-1974

AMERICAN NATIONAL STANDARD

QUALITY ASSURANCE REQUIREMENTS FOR THEDESIGN OF NUCLEAR POWER PLANTS

1. INTRODUCTION

1.1 Scope

This standard provides requirements and guidancefor a quality assurance program for the design ofnuclear power plant structures, systems and com­ponents whose satisfactory and reliable performanceis required:

1. To prevent acciden ts that could cause unduerisk to the health and safety of the public; or

2. To mitigate the consequences of such accidentsif they were to occur.

The requirements of this standard may also be ex­tended to other structures, s~tems and componentsin whole or in part as specified by the purchaser.

This standard covers activities which affect thefinal design.

This standard is intended to be used in conjunctionwith ANSI N45.2.

1.2 Applicability

This standard applies to the plan towner, nuclearsteam supply system (NSSS) designer, archi teet en­gineer or plant designer, and other organizations par­ticipating in design activities affecting quality of itemscovered by this standard. The exten t to which the in­dividual sections and elements of this standard areapplied will depend upon factors such as the natureand scope of the work to be performed and the im­portance of the structures, systems and componen tsto safe plant operation.

The ASME Boiler and Pressure Vessel Code (Here­after referred to as the Code) as well as other ANSIStandards, has been considered in the development ofthis standard, and this standard is intended to be com­patible with their requirements.

However, this standard does not apply to ac­tivities covered by Section III Division I and 2 andSection Xl of the Code for those activities covered bythe Code.

1.3 Responsibility

It is the responsibility of the plant owner to pro­vide for the establishment and execution of a qualityassurance program for the plant design consistent with

the provisions of this standard. The plant owner maydelegate to other organizations the work of establish­ing and executing the quality assurance program, orany part thereof, but shall retain responsibility foroverall program effectiveness. It is the responsibilityof the plant owner and other organizations invokingthis standard to iden tify the structures, systems andcomponents, and to specify the extent to which theprovisions of this standard apply to such structures,systems and components. In no way shall the programoperate to diminish the responsibility of any contrac­tor for the quality of services furnished.

1.4 Definitions

The following definitions are provided to assure auniform understanding of select terms as they areused in this standard.

Design- Technical and management processeswhich commence with identification of design inputand which lead to and include the issuance of designoutput documents.

Design Input- Those criteria, parameters, bases orother design requirements upon which detailed finaldesign is based.

Design Output-Documents such as drawings, spe­cifications and other documents defining technical re­quirements of structures, systems and components asdelineated in Section 4.

External Design Interface-Relationship betweendesign groups from different companies. Examples arethe interfaces between the plant owner and thearchitect e:1gineer or the plant owner and the NSSSsupplier, or the architect.engineer and the NSSS sup­plier.

Final DeSign - Approved design ou tpu t documen tsand approved changes thereto.

Internal Design Interface-Relationship betweendesign groups or organizations within a company.

Procedures-A document that specifies or describeshow an activity is to be performed. It may includemethods to be employed, equipment or materials tobe used and sequence of operations.

1.5 Referenced Documents

Other documents that are required to be includedas part of this standard will be identified at the pointof reference and described in Section 12 of this

QUALITY ASSURANCE REQUIREMENTS FORTHE DESIGN OF NUCLEAR POWER PLANTS

standard. The issue or edition of the referenced docu­ment that is required will be specified either at thepoint of reference or in Section 12 of this standard.

2. PROGRAM REQUIREMENTS

2.1 Establishment and Documentation

A quality assurance program for design shall beestablished and documented to comply with the reoquirements of this Standard.

The program documents shall define the organiza·tional structure within which the program is to be im­plemented, and shall delineate the authority and reosponsibility of the persons and organizations involvedperforming design activities affecting the quality ofdesign.

The program documents shall identify the itemsand services and the specific activities to which thisstandard is applied. The design responsibilities andinterfaces among the contributing organizations, bothinternal and external, shall be identified.

Provisions shall be made in the program forperiodic audits, review and evaluation of the effective­ness of the program in achieving quality objectives.Correction of deficiencies shall be an in tegral part ofthe program.

2.2 Program Procedu res

Procedures shall be employed to assure that designactivities are carried out in a planned, controlled,orderly and correct manner. Program procedures shallcover the following as applicable:

I. Responsibilities of organizations involved inthe program, such as owner, A-E, NSSS supplier andother con tractors.

2. Responsibilities within design organizations.3. Technical information exchanges across ex­

ternal and internal interfaces.4. Document control including review, approval,

release, distribution, and revision.5. Maintenance and retention of design docu-

ments. •6. Management review of status and adequacy of

program.7. Necessary training of personnel performing

activi ties covered by this standard.8. Identifying appropriate design input.9. Preparation of design documents.

10. Specifying quality levels, acceptance standards,and record requirements.

II. Performance of design verifications.12. Conducting audits of design activities, their

reporting and foUowup.

2

ANSI N45.2.11-1974

13. Taking corrective action (see Section 9).14. Making experience reports available to cog­

nizant design personnel.15. Controlling design changes.16. Other procedures as required by this standard.

2.3 Factors Considered

Some of the factors to be considered in establish­ing the program include:

I. Nature of the organization such as the plantowner, manufacturer, or architect-engineer'; and thenature of the design interfaces among them.

2. Importance of the design activity to plantsafety.

3. State of the art such as experimental, develop­mental, or standard design.

4. Nature of design activity such as conceptual,preliminary, detailed design, or field engineering.

3. DESIGN INPUT REQUIREMENTS

3.1 General

Applicable design inpu ts, such as design bases,regulatory requiremen"ts, codes and standards, shall beidentified, documented and their selection reviewedand approved. Changes from specified design inputsincluding the reasons for the changes shall beidentified, approved, documented and controlled.

The design input shall be specified on a timelybasis and to the level of detail necessary to pe rmi t thedesign activity to be carried out in a correct mannerand to provide a consistent basis for making designdecisions, accomplishing design verification measures,and evaluating design changes.

3.2 Requirements

The design inpu t shall include bu t is not Iimi ted tothe following, where applicable:

I. Basic functions of each structure, system andcomponent.

2. Performance requiremen ts such as capacity,rating, system output.

3. Codes, standards, and regulatory requirementsincluding the applicable issue and/or addenda.

4. Design conditions such as pressure, tempera­ture, fluid chemistry and voltage.

5. Loads such as seismic, wind, thermal anddynamic.

6. Environmental conditions anticipated duringstorage, construction and operation such as pressure,temperature, humidity, corrosiveness, site elevation,

QUALITY ASSURANCE REQUIREMENTS FORTHE DESIGN OF NUCLEAR POWER PLANTS

wind direction, nuclear radiation, electromagneticradiation and duration of exposure.

7. In terface requirements including definition ofthe functional and physical interfaces involving struc­tures, systems and components.

8. Material requirements including such items ascompatibility, electrical insulation properties, protec­tive coating and corrosion resistance.

9. Mechanical requirements such as vibration,stress, shock and reaction forces.

10. Structural requiremen ts covering such items asequipment foundations and pipe supports.

II. Hydraulic requirement~ such as pump netpositive suction heads (NPSH), allowable pressuredrops, and allowable fluid velocities.

12. Chemistry requirements such as provisions forsampling and limi tations on water chemistry.

13. Electrical requirements such as source ofpower, voltage, raceway requirem~nts, electrical in­sulation and motor requirements.

14. Layout and arrangement requirements.15. Operational requirements under various condi·

tions, such as plant startup, normal plant operation,plant shutdown, plan t emergency operation, special orinfrequent operation, and system abnormal or emer·gency operation.

16. Instrumentation and control requirements in·cluding indicating instruments, controls and alarms re­quired for operation, testing, and maintenance. Otherrequirements such as the type of instrument, installedspares, range of measurement, and location of indica­tion should also be included.

17. Access and administrative control requirementsfor plant security.

'18. Redundancy, diversity and separation require­ments of structures, systems and components.

19. Failure effects requirements of structures, sys·tems and components, including a definition of thoseevents and accidents which they must be designed towithstand.

20. Test requirements including in-plant tests andthe conditions under which they will be performed..

21. Accessibili ty, main tenance, repair and inserviceinspection requirements for the plant including theconditions under wltich these will be performed.

22. Personnel requirements and limitations in­cluding the qualification and number of personnelavailable for plant operation, maintenance, testing andinspection and permissible personnel radiation ex­posures for specified areas and conditions.

23. Transportability requirements such as size andshipping weight, limitations, Le.e. regulations.

24. Fire protection or resistance requirements.25. Handling, storage and shipping requiremen ts.26. Other requirements to prevent undue risk to

the health and safety of the public.

3

ANSI N45.2.11-1974

27. Materials, processes, parts and equipmentsuitable for application.

28. Safety requirements for preventing personnelinjury including such items as radiation hazards, re­stricting the use of dangerous materials, escape pro­visions from enclosures, and grounding of electricalsystems.

4. DESIGN PROCESS

4.1 General

Design activities shall be prescribed and accom·plished in accordance with procedures of a type suf­ficient to assure that applicable design inputs are cor­rectly translated in to specifications, drawings, proce­dures or instructions. Appropriate quality standardsshall be identified, documented and their selection re­viewed and approved. Changes from specified qualitystandards including reasons for the changes shall beidentified, approved, documen ted and controlled.

The design activities may be prescribed in job spe­cifications, work instructions, planning sheets, proce·dure manuals, test procedures, or any other type ofwritten form, which provides adequate control andpermits reviewing, checking or verifying the results ofthe activity by personnel who are experienced in thesubject activity.

Methods shall provide for relating the final designback to the source of design input. This traceabilityshall be documented in accordance with the require­ments of Section 10.

The design activities shall be documented in suf­ficient detail to permit verification and auditing as reoquired by this standard.

4.2 Design Analyses

Design analyses such as physics, stress, thermal,hydraulic and accident, shall be performed in a plan­ned, controlled and correct manner.

Design analyses shall be legible and be in a formsuitable for reproduction, filing and retrieving. Anal­yses shall be sufficiently detailed as to purpose,method, assumptions, design input, references anduni ts such tha tape rson technically quali fied in thesubject can review and understand the analyses andverify the adequacy of the results without recourse tothe originator. Calculations shall be identifiable bysubject (including structure, system, or component towltich the calcula tion applies), origina tor, reviewer anddate; or by other data such that the calculations areretrievable. Procedures shall include requirements for:

I. Identifying documents to pemlit ready refer­ence and re trieval.

2. Defining the objective of the analyses.3. Definition of design inputs and their sources.

QUALITY ASSURANCE REQUIREMENTS FORTHE DESIGN OF NUCLEAR POWER PLANTS

4. Documenting the results of literature searchesor other applicable background data.

5. Documenting assumptions, and identifyingthose assumptions that must be verified as the designproceeds.

6. Identification of computer calculations, in·cluding computer type, code or programming, inputsand ou tpu ts.

7. Review and approval.

4.3 Drawings

Procedures shall be established for the preparationand control of drawings. Typical subjects to be coveredby such procedu res are:

I. Drafting room standards.2. Standardized symbols.3. Identification system.4. Indication of status.S. Checking me thods.6. Review and approval requirements.7. Issuance and distribution.8. Storage and control of originals or master

copies.9. Revisions.

10. As-built drawings.II. Nonconformance with drawing requirements.

4.4 Spe~Jications

Procedures shall be established for the preparationand control of specifications. Typical subjects to becovered by such procedures are:

I. Format requirements.2. Identification system.3. Review and approval requirements.4. Issuance and distribution.5. Revisions.6. Indication of status.7. Nonconformance wi th specifica tion require·

ments.8. Storage and control of originals or master

copies.

4.5 Other Design Documents

Procedures shall be established for the preparationand control of other design documents such as instal·lation instructions and test procedures. Typical sub·jects to be covered are:

I. Format requirements.2. Identification system.3. Review and approval requirements.4, Issuance and distribution.5. Revisions.6. Indication of status.

4

ANSI N45.2.11-1974

7. Nonconformance wi th design documen t reoquiremen ts.

8. Storage and control of originals or mastercopies.

5. INTERFACE CONTROL

5.1 External

5.1.1 Identification of Interface. The externalinterfaces between organizations performi;g work af·fecting quality of design shall be identified in writingand shall include those organizations providing criteria,designs, specifications and technical direction.

5.1.2 Responsibilities. Responsibilities for organi­zations shall be defined and documented in sufficientdetail to cover the preparation, review and approvalof documents involVing design interfaces. Respon­sibilities may be set forth in tabular form or flowcharts accompanied by appropriate text to clarify theintent. Appendices A and B prOVide examples.

5.1.3 Lines of Communication. Systematic meth­ods shall be establish~d for communicating neededdesign information across external design interfaces,including changes to the design information as workprogresses. Documents shall identify the positions andtitles of key personnel in the communication channelsand their responsibilities for decision-making, forresolution of problems, for prOViding and reviewinginformation, and for taking other action within thescope of this standard.

5.1.4 Documentation. Procedures shall be estab­lished to control the flow of design information be·tween organizations. Design information transmittedfrom one organization to another shall be documentedin specifications, drawings or other controlled docu­ments which are uniquely identified and issued byauthorized persons. The procedures shall provide thatdesign interface information be transmitted to affectedorganizations and that any information requested inthe design interface transmittal be transmitted back tothe originator. Documentation requesting informationor action shall be controlled by a system which as­sures that the response and the request can be related.Where it is necessary to initially transmit design in·formation orally or by other informal means, thetransmittal shall be confirmed promptly by a con­trolled documen t.

5.2 Internal

5.2.1 Identification of Interface. Each organiza­tion performing work affecting quality of design shall

QUALITY ASSURANCE REQUIREMENTS FORTHE DESIGN OF NUCLEAR POWER PLANTS

identify in writing its internal design interfaces formanaging the flow of design information between or­ganizational units.

5.2.2 Responsibilities, Responsibilities for eachorganizational unit shall be defined and documentedin sufficient detail to cover the preparation, review,approval, distribution and revision of documents in­volVing design interfaces.

5.2.3 Lines of Communication. Systematic meth­ods shall be established for communicating needed de­sign information across the internal design interfaces,including changes to the design information as workprogresses.

5.2.4 Documentation. Procedures shall be estab­lished to control the flow of design information be­tween organizational units. Design Information trans­mitted from one organizational unit to another shallbe documented and controlled. Transmittals shallidentify the status of the design information or docu­ment provided and, where necessary, iden tify in­complete items which require further evaluation, re­view or approval. Where it is necessary to initiallytransmit design information orally or by other in­formal means, the transmittal shall be confirmedpromptly by a controlled document.

6. DESIGN VERIFICATION

6.1 General

Measures shall be applied to verify the adequacy ofdesign. Design verification is the process of reviewing,confirming, or substantiating the design by one ormore methods to provide assurance that the designmeets the specified design inputs.

Design verification shall be performed by any com­petent individuals o'r groups other than those whoperformed the original design but who may be fromthe same organization. This verification may be per­formed by the originator's supervisor provided thesupervisor did not specify a singular design approach,or rule out certain design considerations and did notestablish the design inputs used in the design, or ifthe supervisor is the only individual in the organiza­tion competent to perform the verification. Cursorysupervisory reviews do not satisfy the intent of thisstandard. Design verification may vary from spotchecking of calculations to actual tests in the field.

The results of design verification efforts shall beclearly documented, with the identification of theverifier clearly indicated thereon, and filed. Docu­mentation of results shall be auditable against the

5

ANSI N45.2,ll-1974

verification methods identified by the responsibledesign organization.

6.2 Extent

The extent of the design verification reqUired is afunction of the importance to safety of the itemunder consideration, the complexity of the design,the degree of standardization, the state-of-the-art, andthe similarity with previously proven designs. How­ever, the applicability of standardized or previouslyproven designs, with respect to meeting pertinent de­sign inputs, including environmental conditions, shallbe verified for each application. Where the design of aparticular structure, system, or componen t for aparticular nuclear power plant has been subjected to averification process in accordance with this standard,the verification process need not be duplicated foridentical designs. However, known problems affectingthe standardized design and their effects on otherfeatures shall be considered. The original design andassociated verification measures shall, however, beadequa tely documented and referenced in the files ofsubsequent application of the design.

Where changes to previously verified designs havebeen made, design verification shall be required forthe changes, including evaluation of the effects ofthose changes on the overall design.

6.3 Methods

The responsible design organization shall identifyand document the particular design verification meth­ods to be used. Acceptable verification methods in­clude but are not limited to:

I. Design reviews-2. Alternate calculations-3. Qualification testing-

6.3.1 Design Reviews. Design reviews are criticalreviews to prOVide assurance that design documen tssuch as drawings, calculations, analyses or specifica­tions are correct and satisfactory. Design reviews canrange from multi-organization reviews to single-per­son reviews. The depth of review can range from adetailed check of the complete design to a limitedcheck of such things as the design approach and theresults obtained. The results of the review shall bedocumented and measures taken to ensure that thefindings are implemented. Whether the review is con­ducted by one individual or a multi-organization thereare a number of basic questions that shall be ad­dressed such as:

I. Were the inputs correctly selected and in­corporated into design? (See paragraph 3.2).

2. Are assumptions necessary to perform the de·

QUALITY ASSURANCE REQUIREMENTS FORTHE DESIGN OF NUCLEAR POWER PLANTS

sign activity adequately described and reasonable?Where necessary, are the assumptions identified forsubsequent re-verifications when the detailed designactivities are completed?

3. Are the appropriate quality and quality as­surance requirements specified?

4. Are the applicable codes, standards and regu­latory requirements including issue and addendaproperly identified and are their requirements fordesign met?

5. Have applicable construction and operating ex­perience been considered?

6. Have the design interface requirements beensatisfied?

7. Was an appropriate design method used?8. Is the output reasonable compared to inputs?9. Are the specified parts, equipmen t, and

processes suitable for the required application?10. Are the specified materials compatible with

each other and the design environmental conditions towhich the material will be exposed?

II. Have adequate maintenance features and re­quirements been specified?

12. Are accessibility and other design provisionsadequate for performance of needed maintenance andrepair?

13. Has adequate accessibility been provided toperform the in-service inspection expected to be re­quired during the plan t life?

14. Has the design properly considered radiationexposure to the public and plant personnel?

15. Are the acceptance criteria incorporated in thedesign documents sufficient to allow verification thatdesign requirements have been satisfactorily accom­plished?

16. Have adequate pre-operational and subsequentperiodic test requirements been appropriately spe­cified?

17. Are adequate handling, storage, cleaning andshipping requirements specified?

18. Are adequate identification requirements spe­cified?

19. Are require men ts for record preparation re­view, approval, retention, etc., adequately specified?

6.3.2 Alternate Calculations. Verification of sometypes of calculations or analyses may be achieved bycomparison with alternate methods of calculation oranalyses. ntis shall be performed by a person or per­sons other than those who performed the originalcalculation. Where alternate calculations are per­formed t.o verify the correctness of the original cal­culation a review shall also be performed to addressthe appropriateness of assumptions, input data, andthe code or other calculation method used.

6

ANSI N45.2.11-1974

The alternate method used for comparison may bea more simplified approach or less rigorous, such aswhen a hand calculation is used to check the computercode output. Although the simplified or less rigorousmethod may not exactly check the original calcula­tion or analysis, it must provide results consistentwith the original calculation or analyses.

6.3.3 Qualification Testing. Design verification forsome dt'signs or specific design featur.es can beachieved by suitable qualification testing of a proto­type or initial production unit.

In those cases where the adequacy of a design is tobe verified by a qualification test, the testing shall beidentified and documented. Testing shall demonstrateadequacy of performance under the most adverse de­sign conditions. All pertinent operating modes shall beconsidered in determining these design conditionswhere it is intended that the test program confirm theadequacy of the overall design. Where the test is onlyintended to verify a specific design feature, the otherfeatures of the design shall be verified by othermeans. For example, it may be most effective toverify that an instrumentation cabinet is designed towithstand the maximum earthquake-caused vibratorymotions by actually subjecting the cabinet and its as­sociated componen ts to shaker tests which correspondto these vibratory motions. The shaker tests will not,however, verify that the circuitry is designed correct­ly, or that the component in the cabinet will performits intended function. Other tests or verificationmeans are required to confirm that remaining designfunctions are adequately performed by the instru­mentation and that those components perform the in­tended functions for the varying design conditions towhich they are subjected.

Qualification testing shall be performed in accord­ance with written test procedures which incorporateor reference the requirements and acceptance limitscontained in applicable design documents. The testprocedures shall include provisions for assuring thatprerequisites for the given test have been met, thatadequate instrumentation of the required range andaccuracy is available and used, and that necessarymonitoring is performed. PrereqUisites include suchitems as calibrated instrumentation, appropriateequipment, trained personnel, condition of test equip­ment and the item to be tested, suitable environ­mental conditions and provisions for data acquisition.Test results shall be documen ted and evaluated by theresponsible designer to assure that test requiremen tshave been satisfied.

If testing indicates that modifications to the itemare necessary to obtain acceptable performance, themodification shall be documented and the item

QUALITY ASSURANCE REQUIREMENTS FORTHE DESIGN OF NUCLEAR POWER PLANTS

modified and retested or otherwise verified to assuresatisfactory performance. When tests are being per­formed on models or mock-ups, scaling laws shall beestablished and verified. The test configuration shallbe clearly defined and documented. The results ofmodel test work shall be subject to error analysis,where applicable, prior to use in final design work.

7. DOCUMENTCONTROL

Documented procedures shall be used to controlissuance of design documen ts and changes the reto.These procedures shall assure that documents in­cluding changes, are reviewed for adequacy' andapproved for release by authorized personnel and areproperly distributed.

7.1 Document Preparation, Approval and Issue

Personnel shall be made aware of and use properand current instructions, procedures, drawings anddesign inputs. Participating organizations shall havedocumented procedures for control of design docu­ments and changes thereto to assure that current andappropriate documents are available for use. Thedocumen t con trol procedu res shall provide for:

I. Iden tification of personnel positions or organi­zations responsible for preparing, reviewing, approvingand issuing documents and revisions thereto. Thisidentification may take the form of Project GeneralInstructions, design organization Policy Statements, amatrix showing document type against function, orother wri tten forms appropriate to the organizationalmethod of performing the design process.

2. Identification of the proper documents to beused in performing the design. The identificationshould include title applicable revisions, date of issueor any other relevant information that would precise·Iy identify the document to be used.

3. Coordination and control of design (internaland external) interface documents. These interfacedocuments should be mutually agreed to and preparedin sufficient detail to assure that the required reviewsand approvals are accomplished.

4. Ascertaining that proper documents are ac·cessible and are in fact being used. This might be ac·complished by several schemes including the follow­ing examples: periodic issuance of master drawing orspecification lists showing the latest applicable revi­sion (such lists could provide a reference for auditingthe accessibility and use of the latest documents); orsome type of receipting system can proVide 3SSU rancethat the latest documents have been received and ob·solete revisions recalled. An example of such a

7

ANSI N45.2.11-,1974

receipting system is Appendix C, Drawing Issue CheckList.

5. Establishing distribution lists which are up­dated and maintained current 10 assure that the properpersonnel a're sent all the required documents to per­form the work.

7.2 Document Revision

Significant changes to documents shall be reoviewed and approved by the same organizations thatperformed the original review and approval unlessother organizations are specifically designated. The re­viewing organizations shall have access to pertinentbackground data information upon which to basetheir approval. However, minor changes to designdocuments, such as inconsequential editorial correc­tions or changes to commercial terms and conditions,may not require that the revised document receivethe same review and approval as the original docu­ments. To avoid a possible omission of a reqUired re­view, the type of minor changes which do not requiresuch a review and approval and the persons who canauthorize such a decision shall be clearly delineated inthe document control procedures.

8. DESIGN CHANGE CONTROL

Documented procedures shall be prOVided for de­sign changes to approved design documents, includingfield changes, which assure that the impact of thechange is carefully considered, required actions docu­mented and information concerning the change istransmitted to all affected persons and organizations.These changes shall be justified and subjected to designcontrol measures commensurate with those applied tothe original design.

8.1 Reasons for ChangesDesign changes frequently result from such things

as the following:I. Qualification, preoperational, or operational test

results are not satisfactory.2. Interference problems discovered during con­

st ruction.3. Failures of structures, systems. or components

to meet functional requirements.4. Dispositioli of nonconforming items.5. Changes in regulatory or other requirements.6. Operational experience.7. Design improvcments.

8.2 Review of Changes

Normally. the prcx:edures for effecting design

QUALITY ASSURANCE REQUIREMENTS FORTHE DESIGN OF NUCLEAR POWER PLANTS

changes shall require that the documents which reflectthe design change be reviewed and approved by thesame groups or organizations which reviewed andapproved the original design documents. Where anorganization which originally was responsible forapproving a particular design document is no longerresponsible, the plant owner shall designate the newresponsible organi:ution which may be the owner'sown engineering organization. The designated organi­zation shall have access to pertinent background infor­mation, have demonstrated competence in the specificdesign area of interest and have an adequate under­standing of the requirements and intent of theoriginal design.

9. CORRECTIVE ACTION

In addition to correcting a deficiency (or error),corrective action also includes, for significant or recur­ring deficiencies (or errors), dete rmining the cause andinsti tu ting appropriate changes in the design processand the quality assurance program to prevent similartypes of deficiencies (or errors) from recurring. Aprocedure shall be employed for providing such cor­rective action. This procedure shall also contain provi­sions for reporting the deficiency and corrective ac­tion to appropriate levels of supervision and manage­ment. The procedure shall also include follow-upactions that cannot be immediately completed to as­sure timely resolution and/or completion of the cor­rective action.

9.1 Detection of Errors

Deficiencies or error in the design or the designquality assurance program may be detected by:

I. Design verification measures.2. Personnel using the design documents.3. Audits.4. Tests conducted.5. Actual failure during operation.6. Other means.

9.2 Review of Procedure

Where a significan t design change is necessary be­cause of an incorrect design, the design process andverification procedure shall be reviewed and modifiedas necessary.

10. RECORDS

Design documentation and records which provideevidence that the design and review process was per·

8

ANSI N45.2.11-1974

formed in accordance with the requirements of thisstandard shall be collected, stored and main tained inaccordance with the requirements of ANSI N45.2.9.

The documen tation shall include not only the finaldesign documents such as drawings and specifications,and revisions thereto but also records of the importantsteps including sources of design inputs, which sup·port the final design. The records shall be legible,identifiable and retrievable.

Documentation and records will be either of thelifetime or nonpennanent category as defined inANSI N45.2.9.

11. AUDITS

A comprehensive system of planned and docu­mented audits shall be carried out to verify com­pliance with all aspects of the Quality Assuranceprogram for design including those procedures deline­ating quality assurance actions required during the de­sign process.

11.1 Personnel

These audits shall be perfonned in accordance withwri tten procedures or check list by personnel nothaving direct responsibilities in the areas beingaudited. For example, the person who performs anaudit on design verification should not have been reosponsible for perfonning the design verification. Thepersonnel performing audits shall be of a level of com­petency and have sufficient authority and organiza­tional freedom to make the audit process meaningfuland effective.

11.2 Internal Audits

Design organizations performing work in accord­ance with the requirements of this standard shall beaudited to assure 'that their design quality assuranceprograms are being implemented. Audits may be con­ducted in ternally by the design organization or by aunit independent of the design organization.

11.3 External Audits

Organizations shall conduct or delegate the conductof external audits of design organizations performingwork for them to assure that specified design qualityassurance program requirements are being imple­

.men ted and are effective.

11.4 Audit Control

Audits shall include an evaluation of design qualityassurance policies, practices, procedures and ins true-

QUALITY ASSURANCE REQUIREMENTS FORTHE DESIGN OF NUCLEAR POWER PLANTS

tions; the effectiveness of implementation; and ac­tions taken to correct deficiencies in the program.The audits should include the examination of designactivities, processes and documents and records. Anaudit plan shall be developed and should identify thefunctional areas to be audited, the extent of auditwithin these areas to determine effectiveness, thenames and assignments of those who will perform theaudit, the scheduling arrangements and the methodsof reporting findings and recommendations.

11.5 Audit Schedule

Audits should be conducted on a routine basis toestablish the adequacy of and conformance to thedesign quality assurance requirements. Audits shouldalso be conducted when one or more of the followingconditions exists:

I. When it is necessary to determine the capabilityof a subcontractor's quality assurance program priorto awarding of con tract or purchase order for designservices.

2. When, after award of contract, sufficient timehas elapsed for the implementation of the quality as­surance program for design and it is appropriate to de­termine that the organization is performing the func­tions as defined in the quality assurance program de­scription, codes, standards and other contract docu­ments.

3. When significant changes are made in functionalareas of the quality assurance program for design in­cluding significant reorganizations and procedurerevisions.

4. When it is suspected that safety related per­formance of the item is in jeopardy due to deficiencies

9

ANSI N45.2." -1974

and nonconformances in the quality assuranceprogram.

5. When a systematic, independent assessment ofprogram effectiveness or item quality or both is con­sidered necessary.

6. When it is considered necessary to verify im­plementation of reqUired corrective actions.

11.6 Results

Audit results shall be documented and reviewed bymanagement having responsibility in the areas audited.Audit reports shall be in sufficient detail to perrnitmanagement evaluation of the breadth of the audit aswell as the validity of the findings.

11.7 Follow-up

Appropriate corrective action and timely follow­up action, including re-audit of deficient areas, shallbe taken where indicated by the audit findings.

12. AMERICAN NATIONAL STANDARDSREFERRED TO IN THIS DOCUMENT

When the following standards referred to in thisdocument are superseded by a revision approved bythe American National Standards Institute, the revi­sion shall apply.

N4S.2 Quality Assurance Requirements forNuclear Power Plants.

N4S.2.9 Requirements for Collection, Storageand Maintenance of Quality AssuranceRecords for Nuclear Power Plants.'

N4S.2.10 Quality Assurance Terms and Defini­tions.

o

APPENDIX A

DIVISION OF RESPONSIBILITIES

SYSTEM/COMPONENT/STRUCTURE: Seismic Design-All Systems

PROJECT:

CONTRACT/PURCHASE ORDER:

LEGENDOWNERARCHITECT/ENGINEER (AIElREACTOR MANUFACTURER (NSSS)SUBCONTRACTOR (SUB)

~Seismic/ Seismic B_ Equip. Level SeinicCritllrie

Dynamic PrelimineryAnelysis & RelpOnN ResponN Conflrmetion

Review 8t

SpecificationsModel Design

Confirmetion Curves Curves Report Approw"Activity

1. Reactor Pressure Vessel and Internals Owner-NSSS NSSS NSSS A/E·NS?S - NSSS NSSS Owner. a2. Reactor Building Owner A/E AlE ~E.N~ A/E A/E AlE Owner

~

3. NSSS Piping Owner NSSS <£"\l) ~ - - NSSS Owner

4. NSSS Piping Restraints and Supports Owner N~ ~~ A/E·NSSS - - A/E·NSSS Owner

5. Non-NSSS Piping.

Owner ~/E~ '" AlE A/E A/E Owner- -

6. Non-NSSS Piping Restraints & Supports Owner \VE A/E A/E - - A/E Owner

7. NSSS Subcontracted Equipment NSSS SUB SUB SUB - A/E SUB NSSS.Qwner

8. Non-NSSS Subcontracted Equipment A/E SUB SUB SUB - A/E SUB A/E.Qwner

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QUALITY ASSURANCE REQUIREMENTS FORTHE DESIGN OF NUCLEAR POWER PLANTS

APPENDIX C

PROJECT _

ANSI N45.2.11-1974

DRAWING ISSUE CHECK LIST I JOB ORDER NUMBER9999-1

TO DATE

JOHN DOE - CONST. SUPT. 12·31·12FROM

JOHN SMITH - PROJECT ENGINEER

THE FOLLOWING DRAWINGS HAVE BEEN SENT TO YOU SINCE T1-3Q.12 PLEASEREVIEW YOUR RECENT RECEIPTS OF DRAWINGS AND CHECK THE APPROPRIATE COLUMN AS TO WHETHERYOU HAVE RECEIVED THEM OR NOT. INITIAL AND DATE THIS FORM WHERE INDICATED. RETURN THEMARKED ORIGINAL TO ME IMMEDIATELY; KEEP THE COpy FOR YOUR RECORDS.

DRAWING NO. Issue ORAWINGDRAWING NO. Issue ORAWING

DRAWING NO. Issue DRAWINGRECEIVED RECEIVED RECEIVED

(EXCLUDING J.O.I NO. YES NO (EXCLUDING J.O.l NO. YES N_O (EXCLUDING J.O.l NO. YES NO12732 827426 044014 C32507 E

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I certify that the previous revisions ofthe documents. and drawings have beenrecalled or accounted for:

Signature - Date

IMPORTANTFIELD CHECK BY DATE•

J 2

APPENDIX B

DIVISION OF RESPONSIBILITIESSEISMIC INTERFACE CHART

l;'~ ~ ~ -P"'-"SEISIIlIC CRITERIA SEISMIC BASE LEVEl SEISMIC REVIEW

AND OYllAMIC 'RElIMIIlARY AIIIAL YSlS AIIIO RES'OIlS( RESPOIIISf COlllflRMATlOIil AIIOSPECI~C~TlOId . _MO~m OESIGIII COlllflRMUIOII CURVES CURVES RE'ORTS A"ROVAL-- -- -- -- - - - -

I ESTABLISH I REVIEW AND

OWIIEIl I CONTRACT1 I I I ,.. APPROVE

SEISMIC r- I II I I SEISMIC

CRITERIA I I REPORTSI I

-- - - - -- -- --DESIGN Of PREPARE

BRANCH IANALYZE REPORT FORLINES ,NON-NSSS REACTOR ~

CONNECTEO PIPING BUILOING ANOsPECIFY TO NSSS LOCATION NSSS PIPING

ARCMITECTI SEISMIC PIPING - OF SEISMIC AND SUPPORTS£1161111((R CAPACITY ATTACHMENT

REQUIREMENTS ESTABLISH FROM NSSS DEVElOP OEVElOP REVIEW AND

I OF NON-NSSS REACTOR I MODIFY PIPING TO I ANALYZE REACTOR I REACTOR IIf.

APPROVE

I SUBCONTRACTEO BUILDINGI u:il~°L~~II~~NG

BUILOINGI

ATTACHMENT I,. BUILDING -r- BUILDING . NON·NSSSEOUII'toIENT SOIL FROM NSSS I BASE EOUIPMENT I SUBCONTRACTED

STRUCTURE VALUES ARE PIPING TO RESPONSE LEVEl EOUII'toIENTMODEL NOT EXCEEDED BUILDING SPECTRA SPECTRA REPORTS

-- '- t ~ - I-- -- -- -- --

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DEVElOPESTABLISH ANALYZE RESPONSE

SEISMIC ESTABLISH MODifY RN & AT RNLIMITS AND

~RN & ... MQDEL INTERNALS NOZZlE

CHARACTERISTICSf-

INTERNALS IF~~~~

CAPABILITY LOCATIONSOF NSSS MaDEl REQUIRED IN REACTOR AND RESTRAIN

IlEACTOR EOUII'toIENT I , BUILDINGI

LOCATIONS I..IIIUfACTUIlEll I I I

~I ON PEDESTAL I

1 I 1 II

I1 SPECIFYDEVElO' PRE'ARE

REVIEW ANDSEISMIC ESTABLISH APPROVE

CAPACITY NSSS NSSS I ANALYZE REACTOR FORNSSS

REQUIREMENTS PIPING PIPING NSSS RN INTE RNALS -SUBCONTRACTEDSUBCONTRACTED MODH ARRANGE- PIPING NSSS PIPING EOUIPMENT

EOUII'toIENT MENTS AN 0 SUPPO RTSREPORTS

- - - -- - - - - - - - -- - -ANALYZE 'REPARE

l1l1I AND CONFIRMATIONIUICOIilTIUCTOR CONFIRM REPORT FOR

EOUII'toIENT EQUII'toIENT

I -- I -- I - - -- - - - -- ----I I I I I

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