1、- ASME N626.3-1993 (REVISION OF ANSI/ASME N626.3-1988) Qualifications and Duties of Specialized Professional tngmeers 1 AN AMERICAN NATIONAL STANDARD The American Society of Mechanical Engineers r AN AMERICAN NATIONAL STANDARD Qualifications and Duties of Specialized Professional Engineers ASME N626
2、.3-I993 (REVISION OF ANSI/ASME N626.3-1988) The American Society of Mechanical Engineers 345 East 47th Street, New York, N.Y. 1 O01 7 ASME Nb2b.3 93 m 0759b70 05398L3 347 m Date of Issuance: March 15, 1994 The 1993 edition of this Standard is being issued with an automatic addenda subscription servi
3、ce. The use of an addenda allows revisions made in re- sponse to public review comments or committee actions to be published on a regular yearly basis; revisions published in addenda will become effective 1 year after the Date of Issuance of the addenda. The next edition of this Standard is schedule
4、d for publication in 1998. ASME issues written replies to inquiries concerning interpretations of technical aspects of this Standard. The interpretations will be included with the above addenda service. Interpretations are not part of the addenda to the Standard. ASME is the registered trademark of
5、The American Society of Mechanical Engineers. This code or standard was developed under procedures accredited as meeting the criteria for American National Standards. The Consensus Committee that approved the code or standard was balanced to assure that individuals from competent and concerned inter
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7、ny item, construction, proprietary device, or activity. ASME does not take any position with respect to the validity of any patent rights asserted in connection with any items mentioned in this document, and does not undertake to insure anyone utilizing a standard against liability for infringement
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10、interpretations by individual vol- unteers. 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. THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS Copyright Q 1994 by All Rights Reserved Printed in U
11、.S.A. ASME N626.3 93 m 0759670 0539834 283 m FOREWORD (This Foreword is not part of ASME N626.3-1993.) At the March 29, 1973, meeting of the Policy Board, Codes and Standards, a Special Committee of the Policy Board, Codes and Standards, was established to develop a stan- dard whose scope would incl
12、ude the duties and qualifications of the Authorized Inspection Agency, the supervisory personnel of the Authorized Inspection Agency, and the Author- ized Nuclear Inspectors, as covered in the ASME Boiler and Pressure Vessel Code, Section III, Division I. The Policy Board, Codes and Standards, at it
13、s meeting of September 27, 1973, desig- nated the Special Committee as a Safety Code Committee and approved procedures for the Committee activities. The scope of the Safety Code Committee was expanded by the Policy Board, Codes and Standards, to include the development of standards whose scope would
14、 include the duties and qualifications of the Authorized Inspection Agency, the supervisory personnel of the Authorized Inspection Agency, and the Authorized Nuclear Inspectors, as covered in the ASME Boiler and Pressure Vessel Code, Section XI, and Section III, Division 2, and the de- velopment of
15、a standard for qualifications and duties of Specialized Professional Engi- neers. To facilitate the development of such standards, Task Groups were appointed by the Safety Code Committee. The Safety Code Committee was made up of individuals associ- ated with: Nuclear Component Manufacturers Engineer
16、ing Organizations Utilities State Regulatory Agencies Nuclear Regulatory Commission (NRC) Authorized Inspection Agencies National Board of Boiler and Pressure Vessel Inspectors ASME Boiler and Pressure Vessel Code Joint ACVASME Committee on Concrete Nuclear Components The Safety Code Committee, now
17、designated Committee on Authorized Nuclear Inspec- tion and Specialized Professional Engineers, reports to the ASME Board on Nuclear Codes and Standards. The Committee operates under procedures accepted by the American National Standards Institute as meeting the criteria of consensus procedures for
18、American National Standards. The first edition of this Standard was approved by the American National Standards In- stitute on May 2, 1978. Subsequent editions of the Standard were issued in 1979 and 1984. Requests for interpretations, or suggestions for improvement of this American National Standar
19、d, should be addressed to the Secretary, ASME Committee on Authorized Nuclear Inspection and Specialized Professional Engineers, American Society of Mechanical Engi- neers, 345 East 47th Street, New York, NY 10017. This edition incorporates all previous editions and addenda issued prior to December
20、1993, with no other changes. . 111 ASME N62603 93 m 0759670 0539835 LIT m COMMITTEE ON AUTHORIZED NUCLEAR INSPECTION AND SPECIALIZED PROFESSIONAL ENGINEERS (The following is the roster of the Committee at the time of approval of this Standard.) OFFICERS W. C. LaRochelle, Chairman G. L. Hollinger, Vi
21、ce Chairman M. E. Sheehan. Secretary COMMIITEE PERSONNEL J. P. Allen, Kennebunk Beach, Maine V. Bogosian, The National Board of Boiler and Pressure Vessel Inspectors, Columbus, Ohio R. W. Boyce, Factory Mutual System, Norwood, Massachusetts E. W. Brach, U. S. Nuclear Regulatory Commission, Washingto
22、n, D. C. E. B. Branch, Sargent of the N Certificate Holder; Owner; Report on behalf of the Owner; on behalf of the N Certificate Holder. (I) certification of the Design Specification on (2) certification of the Design Report on behalf (3) review of the Design Report on behalf of the (4) certificatio
23、n of the Overpressure Protection (5) certification of the Load Capacity Data Sheet (b) for Division 2: (I) certification of the Design Specification on behalf of the Owner; (2) certification of the Construction Specifica- tion, Design Drawings, and Design Report on behalf of the Designer; (3) review
24、 of the Design Report on behalf of the Owner. Also provided are the duties of these personnel in the performance of the activities described above. 2 QUALIFICATIONS 2.1 One or more registered Professional Engineers (PE) shall be selected by the Owner, Designer, or N Certificate Holder, as applicable
25、, to perform Code ac- tivities in the appropriate specialized field(s), pro- vided the qualifications of the PE in meeting the requirements of this Standard have been evaluated and verified by the Owner, Designer, or N Certificate Holder, as applicable, responsible for the activity be- ing certified
26、 or reviewed. Guidelines for demonstrat- ing PE qualifications are contained in Appendix C. A ASME Code refers to the ASME Boiler and Pressure Vessel Code, Section III, Divisions 1 and 2, with Addenda and Code Cases. record of the qualifications of the PE shall be main- tained by the responsible org
27、anization or the PE. 2.2 He shall be a registered Professional Engineer in at least one state of the United States or Province of Canada and have the following qualifications. He shall have 4 years of varied application experi- ence, at least 2 of which have been in each specialty field for which he
28、 performs certifying or review ac- tivities as delineated in para. 2.3 through para. 2.6. In addition, he shall keep current his knowledge of Code requirements and continue his professional develop- ment in his specialty field through personal study and experience, or by attendance at appropriate co
29、urses, seminars, Society meetings, and technical committee meetings. The Owner, Designer, or N Certificate Holder, as applicable, shall review the qualifications of the PE at least once every 3 years to assure that his qualifications have been maintained. A continuing re- cord of all such activity s
30、hall be included in the qualifi- cation records of the PE. 2.3 To qualify as certifier of the Design Specifica- tion on behalf of the Owner, the PE shall be experi- enced in the applicable field of design and related nuclear power plant requirements, and in the applica- tion of the requirements of t
31、he Code relating to the construction of nuclear power plant items.3 This expe- rience shall indicate that the PE has sufficient knowl- edge of anticipated plant and system operating and test conditions and their relationship to Code design criteria pertinent to the applicable Code item. In addi- tio
32、n, he shall be knowledgeable of the specific Code requirements pertaining to his specialty field. Guide- lines reflecting the degree of knowledge appropriate for preparation of the Design Specification are con- tained in Appendix B, Table B1. *This requirement for para. 2.3 and para. 2.5 may be fulf
33、illed concurrently. 31tems as used in this Standard are defined in Subsection NCA of the Code and include components, component and piping supports, appurtenances, core support structures, parts, piping subassem- blies, and materials. 1 ASME Nb2b-3 73 m 0757670 0537838 927 m ASME N626.3-1993 2.4 To
34、qualify as certifier of the Load Capacity Data Sheet, the Construction Specification, Design Drawings, or Design Report, the PE shall be experi- enced in the applicable field of design and analysis and in the application of the requirements of the Code. In addition, he shall be knowledgeable of the
35、specific Code requirements pertaining to his specialty field. Guidelines reflecting the degree of knowledge appro- priate for preparation of the Design Report (Division l), the Load Capacity Data Sheet, and the Construc- tion Specification, Design Drawings, and Design Re- port (Division 2) are conta
36、ined in Appendix B, Tables B2, B4, and B5, respectively. 2.5 To qualify as reviewer of the Design Report on behalf of the Owner, the PE shall fulfill the experience and knowledge requirements of para. 2.3. 2.6 To qualify as certifier of the Overpressure Pro- tection Report on behalf of the Owner, th
37、e PE shall be experienced in nuclear power plant systems design, and in plant operation and safety control. In addition, he shall be knowledgeable of the specific Code re- quirements pertaining to his specialty field. Guide- lines reflecting the degree of knowledge appropriate for preparation of the
38、 Report on Overpressure Protec- tion are contained in Appendix B, Table B3. 3 DUTIES 3.1 The certification and review activities covered in this Standard may be performed only if the PE has assured himself that he is qualified to do so by virtue of a self-review establishing that his qualifications
39、meet those required by this Standard. He shall be fa- miliar with the Quality Assurance requirements of the organization responsible for providing the document as these requirements relate to his work. For certifica- tion activities, the document being certified must have been reviewed in detail by
40、the certifying PE, or pre- pared by him or prepared under his responsible direc- tion. He shall prepare a statement4 to be affixed to the document attesting to compliance with the applicable requirements of the Code. 3.2 it is the responsibility of the PE certifying the Owners Design Specification t
41、o assure that the De- sign Specification is correct, complete, and in compli- ance with the requirements of the applicable Edition and Addenda of the Code. As a minimum, the certi- fier of the Design Specification shall assure that: (a) the function of the item is properly specified; 4111ustrative s
42、amples of statements are shown in Appendix A. QUALIFICATIONS AND DUTIES OF SPECIALIZED PROFESSIONAL ENGINEERS (b) the design requirements, including identifica- tion of the item Design and Service Loadings and their combinations and associated Limits, are properly specified; (c) the proper environme
43、ntal conditions, including corrosion, erosion, and radiation, are specified; (d) the Code classification is properly specified; (e) the definition of the specific boundaries and load conditions on these boundaries for each item is specified, and that the boundaries and associated load conditions bet
44、ween adjacent components and struc- ture are compatible with the overall system design; u) the specified materials for items covered by the Code are permitted by the Code for the applicable item; (g) all requirements with regard to impact testing are specified; (h) any restrictions on or additional
45、requirements for heat treating are specified; (i) any restrictions on cladding materials are speci- fied; (j) any reduction to design stress intensity values, allowable stress, or fatigue curves necessitated by the given environmental conditions are specified; (k) the necessary information concernin
46、g the load carrying capacity of structures supporting Code items is given in the Design Specification; (i) when operability of a component is a require- ment, the Design Specification shall make reference to other appropriate documents that specify the operat- ing requirements; (m) the overpressure
47、protection requirements are specified; (n) the Code Edition, Addenda, and Code Cases to be used for construction are specified. 3.3 It is the responsibility of the PE certifying the Division 1 Design Report to assure that the design of the item complies with the requirements of the appli- cable Edit
48、ion and Addenda of the Code for the De- sign, Service, and Test Loadings that have been specified in the Design Specification. As a minimum, the certifier of the Design Report shall assure that: (u) the Design Report reflects the design as shown by the drawings used for construction and that all mod
49、ifications to the drawings and construction devia- tions have been reconciled with the Design Report; (b) the design as shown by the drawings is in ac- cordance with the requirements of the Code; (c) the Design Report is in accordance with the re- quirements of the Code; (d) materials specified for Code items are permit- ted by the Code, and that any reduction of material QUALIFICATIONS AND DUTIES OF SPECIALIZED PROFESSIONAL ENGINEERS impact properties from heat treatments, welding, and forming have been taken into account; (e) the Design Report is based on the Design, Ser- vice, and Test L
