RG 1.105安全相关仪表的整定点 1999.pdfVIP

U.S. NUCLEAR REGULATORY COMMISSION Revision 3 December 1999 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.105 (Draft was DG-1045) SETPOINTS FOR SAFETY-RELATED INSTRUMENTATION A. INTRODUCTION 1 Criterion 13, Instrumentation and Control, of Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, requires, among other things, that instrumentation be provided to monitor variables and systems and that controls be provided to maintain these variables and systems within prescribed operating ranges. Criterion 20, Protection System Functions, of Appendix A to 10 CFR Part 50 requires, among other things, that the protection system be designed to initiate operation of appropriate systems to ensure that specified acceptable fuel design limits are not exceeded. Paragraph (c)(1)(ii)(A) of § 50.36, Technical Specifications, of 10 CFR Part 50 requires, in part, that, where a limiting safety system setting is specified for a variable on which a safety limit has been placed, the setting be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded. It also requires, among other things, that the licensee notify the NRC if the licensee determines that an automatic safety system does not 1 For the full text of the General Design Criteria and othe