ANS-51.1-1983-R1988.pdf
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1、- 7- . ANS 53-3 83 E 0724838 0098067 4 , = - - x. ANSIIANS-51.1-1983 nuclear safety criteria for the design of stationary pressurized water reactor plants -,-,- ANSIIANS-51 .I-1 983 O i I American National Standard Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants
2、 O Secretariat American Nuclear Society Prepared by the American Nuclear Society Standards Committee Working Group ANS-51.1 Published by the American Nuclear Society 555 North Kensington Avenue La Grange Park, Illinois 60525 USA Approved April 29, 1983 by the American National Standards Institute, I
3、nc. “ “ -,-,- American National Standard An American National Standard implies a consensus of those substantially con- cerned 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 America
4、n National Standard does not in any respect preclude anyone, whether he has approved the standard or not, from manufacturing, marketing, purchasing, or using products, processes, or procedures not conforming to the standard. American National Standards are subject to periodic review and users are ca
5、utioned to obtain the latest editions. CAUTION NOTICE This American National Standard may be reviewed or with- drawn 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
6、date of publication. Purchasers of this standard may receive current information, including interpretation, on all standards published by the American Nuclear Society by calling or writing to the Society. Published by American Nuclear Society 555 North Kensington Avenue, La Grange Park, Illinois 605
7、25 USA Price: $45.00 Copyright O 1983 by American Nuclear Society. 0 - Any part of this standard may be quoted. Credit lines should read “Extracted from American National Standard ANSIIANS-51.1-1983 with permission of the publisher, the American Nuclear Society.” Reproduction prohibited under copyri
8、ght convention unless written per- a- mission is granted by the American Nuclear Society. Printed in the United States of America - -,-,- ANS 51.1 83 W 0721.1818 0098070 4 W Foreword (This Foreword is not a part of American National Standard Nuclear Safety Criteria for the Design of Stationary Press
9、urized Water Reactor Plants, ANSIIANS-51.1-1983.) This standard is a complete revision and combination of N18.2-1973/ANS-51.1 and N18.2a-19751ANS-51.8. It has been prepared by Subcommittee ANS-51, Pressurized Water Reactor Criteria, to incorporate additional requirements for the design of pressurize
10、d water reactor (PWR) nuclear power plants and to address three major areas: 1. 2. 3. Safety Classes The results of the ANS Nuclear Power Plant Standards Committee (NUPPSCO) Ad Hoc Committee and NUPPSCO Coordinating Working Group 3 on Equip- ment Classification are incorporated. These results define
11、 Safety Classes and specify requirements for all equipment and structures in a stationary nuclear power plant having a nuclear safety function. A methodology is given to classify all equipment into one of three Safety Classes according to its importance to nuclear safety and its capability for maint
12、enance, surveillance testing, and inspection, or into a Non-Nuclear Safety Class. In addition, classification inter- face criteria are defined. Plant Conditions The results of the NUPPSCO Coordinating Working Group 2 have been incor- porated. The concept of Plant Conditions is developed that include
13、s individual process conditions, combinations of process conditions, and the combinations of process conditions and external hazards that could result in simultaneous effects on plant equipment. Probability of occurrence is the unifying basis for the categorization of Plant Conditions. Design Requir
14、ements This standard provides a set of design requirements for all Safety Classes and Non-Nuclear Safety Class in terms of industry codes and standards for each category of Plant Conditions. The design requirements reference specific stan- dards and ensure substantial interrelationship with other co
15、des and standards. The content of this standard reflects an attempt to achieve the following objectives: a. To establish a consistent set of requirements for light water reactor nuclear power plants; b. To establish a disciplined, systematic method for defining nuclear safety requirements for nuclea
16、r power plants; c. To establish and delineate the functional nuclear safety requirements for the design of nuclear power plants: d. To be responsive to both the regulatory requirements of the Nuclear Regulatory Commission and the design and technical requirements of industry codes and stan- dards; e
17、. To provide a framework for augmenting these criteria as additional standards are developed within the nuclear industry; and f. To provide a uniform basis for design safety requirements which may be reflected in regulatory documents. The existence of unique plant or site characteristics might requi
18、re the consideration of alternate design concepts. This standard has been developed along functional lines to permit this flexibility. The standard has, however, cited many standards, some of which were still in draft form at the time this document was published. Provisions -,-,- ANS 53.3 83 m 07248
19、38 0098073 b m contained in any draft standard should be considered and used with great discretion. It is strongly suggested that the prospective user fully understand the present status of the referenced standard and major factors on why it might be still in draft form; for example, controversial i
20、ssues should be recognized. A number of considerations under development concurrent with the preparation of this standard are not addressed in this standard. Examples of these considerations include: human factors engineering (HFE), probabilistic risk assessment (PRA), systems interaction, diversity
21、, plant security, emergency response facilities, degraded core, minimizing challenges to engineered safety features, safety goals and considera- tion of costhenefit analysis, and anticipated transients without scram. Subsequent revisions of this standard will address these considerations as appropri
22、ate when they become adequately defined. A designer is not restricted by this standard from proposing or using alternate criteria to ensure adequate nuclear safety. Frequently, a desirable overall result can be obtained by any of several design concepts. The designer may choose from several alternat
23、ives in satisfying the specifics of this standard by the proper consideration of the interrelationship of components and systems within the plant. For example, the PRA approach may be used as an alternative method to evaluate plant design; however, its usefulness is somewhat limited without safety g
24、oals that are currently under development. Portions of this standard were prepared separately under ANS-50 Nuclear Power Plant Systems Engineering and were reviewed individually by ANS-51, ANS-50, and NUPPSCO which replaced ANS-50 during this time. The separate documents that have been incorporated
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