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1、Regulatory guides are issued to describe and make available to the public such information as methods acceptable to the NRC staff for implementing specific parts of the NRC s regulations techniques used by the staff in evaluating specific problems or postulated accidents and data needed by the NRC s
2、taff in its review of applications for permits and licenses Regulatory guides are not substitutes for regulations and compliance with them is not required Methods and solutions different from those set out in the guides will be acceptable if they provide a basis for the findings requisite to the iss
3、uance or continuance of a permit or license by the Commission This guide was issued after consideration of comments received from the public Comments and suggestions for improvements in these guides are encouraged at all times and guides will be revised as appropriate to accommodate comments and to
4、reflect new information or experience Written comments may be submitted to the Rules and Directives Branch ADM U S Nuclear Regulatory Commission Washington DC 20555 0001 Regulatory guides are issued in ten broad divisions 1 Power Reactors 2 Research and Test Reactors 3 Fuels and Materials Facilities
5、 4 Environmental and Siting 5 Materials and Plant Protection 6 Products 7 Transportation 8 Occupational Health 9 Antitrust and Financial Review and 10 General Single copies of regulatory guides which may be reproduced may be obtained free of charge by writing the Distribution Services Section U S Nu
6、clear Regulatory Commission Washington DC 20555 0001 or by fax to 301 415 2289 or by email to DISTRIBUTION NRC GOV Electronic copies of this guide and other recently issued guides are available at NRC s home page at through the Electronic Reading Room Accession Number ML032740277 U S NUCLEAR REGULAT
7、ORY COMMISSION Revision 1 October 2003 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1 180 Draft was issued as DG 1119 GUIDELINES FOR EVALUATING ELECTROMAGNETIC AND RADIO FREQUENCY INTERFERENCE IN SAFETY RELATED INSTRUMENTATION AND CONTROL SYSTEMS A INTRODUCTION This regula
8、tory guide has been revised to provide guidance to licensees and applicants on additional methods acceptable to the NRC staff for complying with the NRC s regulations on design installation and testing practices for addressing the effects of electromagnetic and radio frequency interference EMI RFI a
9、nd power surges on safety related instrumentation and control I or from the National Technical Information Service by writing NTIS at 5285 Port Royal Road Springfield VA 22161 telephone 703 487 4650 Copies are available for inspection or copying for a fee from the NRC Public Document Room at 11555 R
10、ockville Pike Rockville MD the PDR s mailing address is USNRC PDR Washington DC 20555 telephone 301 415 4737 or 800 397 4209 fax 301 415 3548 email is PDR NRC GOV 1 180 2 CFR Part 50 states that protection systems must meet the requirements of the Institute of Electrical and Electronics Engineers IE
11、EE standard Std 603 1991 Criteria for Safety Systems for Nuclear Power Generating Stations 1 or IEEE Std 279 1971 Criteria for Protection Systems for Nuclear Power Generating Stations 1 contingent on the date of construction permit issuance The design basis criteria identified in those standards or
12、by similar provisions in the licensing basis for such facilities include the range of transient and steady state environmental conditions during normal abnormal and accident circumstances throughout which the equipment must perform Criterion III Design Control Criterion XI Test Control and Criterion
13、 XVII Quality Assurance Records of Appendix B Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants to 10 CFR Part 50 establish practices to confirm that a design fulfills its technical requirements Furthermore 10 CFR 50 49 and 50 55a address validation measures such as te
14、sting that can be used to check the adequacy of design Related requirements are contained in General Design Criteria 1 2 4 13 21 22 and 23 of Appendix A General Design Criteria for Nuclear Power Plants to 10 CFR Part 50 Additionally Subpart B Standard Design Certifications of 10 CFR Part 52 Early Si
15、te Permits Standard Design Certifications and Combined Licenses for Nuclear Power Plants addresses verification requirements for advanced reactor designs Specifically 10 CFR 52 47 a vi requires that an application for design certification must state the tests inspections analyses and acceptance crit
16、eria that are necessary and sufficient to provide reasonable assurance that a plant will operate within the design certification Methods for addressing electromagnetic compatibility EMC constitute Tier 2 information under the 10 CFR Part 52 requirements 2 Electromagnetic interference EMI radio frequency interference RFI and power surges have been identified as environmental conditions that can affect the performance of safety related electrical equipment Confirmatory research findings to support
