【正文】 21 / 21。 1981.147.NEMA MG198, “Motors and Generators,” Revision 1, January 1998, National Electric Manufacturers Association.148.NFPA 30, “Flammable and Combustible Liquids Code.”149.NFPA 37, “Standard for the Installation and Use of Stationary Combustion Engines and Gas Turbines.”150.NFPA 70, “National Electrical Code (NEC),” 1999.151.NFPA 90 A, “Installation of AirConditioning and Ventilation Systems.”152.NFPA 92A2000, “Remended Practice for Smoke Control Systems.”153.NFPA 101, “Life Safety Code” 154.NFPA 324M, “Fire Hazard Properties of Flammable Liquids, Gases, and Volatile Solids.”155.NFPA 780, “Standard for the Installation of Lighting Protection Systems,” 1997.156.SMACNA, HVAC Duct Construction Standards, Metal and Flexible, Second Edition 1995.157.SMACNA, “HVAC Systems – Testing, Adjusting, and Balancing,” 1993.158.SMACNA, “Rectangular Industrial Duct Construction Standards,” 1980.159.SMACNA 1995, HVAC Duct Construction Standards Metal and Flexible, 1985 Edition.160.UL 181, “Factory Made Air Duct Materials and Air Duct Connectors.”161.UL 555, “Safety Fire Dampers.”162.UL 555S, “Leakage Rated Dampers for Use in Smoke Control Systems.”163.UL 586, “HighEfficiency, Particulate, AirFilter Units.”164.UL 900, “Test Performance of AirFilter Unit.”165.UL 1025, “Electric Air Heaters.”166.UL 1096, “Electric Central Air Heating Equipment.”167.MILHDBK217F, Notice 2 (1995), “Reliability Prediction of Electronic Equipment.”168.MILHDBK338B (1998), “Electronic Reliability Design Handbook.”169.MILHDBK472, Notice 1 (1984), “Maintainability Prediction.”170.MILHDBK781A (1996), “Handbook for Reliability Test methods, Plans and Environments for Engineering Development, Qualification and Production.”171.MILSTD1629A, Notice (1984), “Procedure for Performing a Failure Mode Effects and Criticality Analysis.”172.NUREG 0800, “Standard Review Plan.”173.NUREG 0908, “Acceptance Criteria for Evaluation of Nuclear Power Reactor Security Plants.”174.NUREG/CR 2156, “Radiation Thermal Degradation of PE and PVC: Mechanism of Synergism and Dose Rate Effects,” Clough and Gillen, June 1981.175.NUREG/CR 2157, “Occurrence and Implication of Radiation Dose Rate Effects for Material Aging Studies,” Clough and Gillen, June 1981.176.NUREG/CR 5118, “Leak and Structural Test of Personnel Airlock for LWR Containments Subjected to Pressures and Temperatures beyond Design Limits,” SAND887155, May 1989.177.NUREG/CR6519, “Screening Reactor Steam/Water Systems for Water Hammer,” November 1996.178.NUREG/CR6634, “ComputerBased Procedure Systems: Technical Basis and Human Factors Review Guidance,” . Nuclear Regulatory Commission, Washington, ., March 2000.179.NUREG0612, “Control of Heavy Loads at Nuclear Power Plants,” . Nuclear Regulatory Commission, Washington, ., July 1980.180.NUREG0654, “Criteria for Preparation and Evaluation of Radiological Emergency Response Plan,” . Nuclear Regulatory Commission, Washington, .181.NUREG0696, “Functional Criteria For Emergency Response Facilities,” . Nuclear Regulatory Commission, Washington, .182.NUREG0700, “HumanSystem Interface Design Review Guideline,” Revision 1, . Nuclear Regulatory Commission, Washington, ., February 1995 (Draft Report).183.NUREG0711, “Human Factors Engineering Program Review Model,” . Nuclear Regulatory Commission, Washington, ., July 1994.184.NUREG0711, Revision 1, “Human Factors Engineering Program Review Model,” . Nuclear Regulatory Commission, Washington, ., May 2002.185.NUREG0899, “Guidelines for the Preparation of Emergency Operating Procedures,” . Nuclear Regulatory Commission, Washington, ., August 1982.186.NUREG1061, “Evaluation of Potential for Pipe Breaks, Report of the . Nuclear Regulatory Commission Piping Review Committee,” Volume 3 (prepared by the Pipe Break Task Group), November 1984.187.NUREG1358, “Lessons Learned from the Special Inspection Program for Emergency,” . Nuclear Regulatory Commission, Washington, ., April 1989.188.NUREG1431, “Standard Technical Specifications – Westinghouse Plants,” . Nuclear Regulatory Commission, Washington, ., April 1995.189.NUREG1465, “Accident Source Terms for LightWater Nuclear Power Plants,” . Nuclear Regulatory Commission, Washington, ., February 1995.190.Contents and Format of Environmental Impact Reports for Nuclear Power Plants NEPARG1 (Aug. 1988)191.Contents and Format of Environmental Impact Report for GNPS (Trial Operation Phase ) NEPARG3 (Feb. 1994)常規(guī)島采用的有關(guān)法規(guī)、規(guī)范和標(biāo)準(zhǔn)常規(guī)島采用的有關(guān)法規(guī)、規(guī)范和標(biāo)準(zhǔn)主要是國際標(biāo)準(zhǔn)，美國國家標(biāo)準(zhǔn)。1991.105.EPRI Report TR102323, Revision 1, “Guidelines for Electromagnetic Interference Testing in Power Plants.”106.EPRI Utility Requirement Document, “Advanced Light Water Reactor Utility Requirements Document,” Revision 8.107.FEMA 356, “Prestandard and Commentary for the Seismic Rehabilitation of Buildings,” Federal Emergency Management Agency, November 2000.108.ICEA Standard Publication P54440, “Ampacities of Cables in OpenTop Cable Trays,” 1986.109.IEEE Standard , “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” 1993.110.IEEE Standard 141, “IEEE Remended Practice for Electric Power Distribution for Industrial Plants,” (IEEE Red Book), 1993.111.IEEE Standard 242, “IEEE Remended Practice for Protection and Coordination of Industrial and Commercial Power Systems” (IEEE Buff Book), 1986.112.IEEE Standard 279, “IEEE Standard Criteria for Protection Systems for Nuclear Power Generating Stations,” 1971.113.IEEE Standard 308, “IEEE Standar