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NUREG-1537, Part 2 (PDF NUREG-1537, Part 2 Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors Standard Review Plan and Acceptance Criteria Office of Nuclear Reactor Regulation NUREG-1537, Part 2 Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors Standard Review Plan and Acceptance Criteria Manuscript Completed: February 1996 Date Published: February 1996 Office of Nuclear Reactor Regulation AVAILABILlTY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources, 1. The NRC Public Document Room, 2120 L Street, NW.. Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of docurnents cited in NRC publica- tions, i'ts not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices: licensee event reports; vendor reports and correspondence; Commission papers, and applicant and licensee docu- ments and correspondence. The following documents in the NUREG senes are available for purchase from the Govemment Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- ceedings, international agreement reports, grantee reports, and NRC booklets and bro- chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula- tions, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical Information Service include NUREG-senes reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libranes. Documents such as theses. dissertations, foreign reports and translations, and non-NRC con- ference proceedings are available for purchase from the organization sponsonng the publica- tion cited. Single copies of NRC draft reports are available free, to the extent of supply. upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington DC 20555-0001. Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC library. Two White Flint North,1 1545 Rockville Pike, Rock- ville, MD 20852-2738. for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards. from the American National Standards Institute, 1430 Broadway, New York, NY 10018-3308. Photograph on cover courtesy of General Atornics ABSTRACT NUREG-1537, Part 2 gives guidance on the conduct of licensing action reviews to NRC staff who review non-power reactor licensing applications. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination. in STANDARD REVIEW PLAN REV. 0,2/960, ri% ... STANDARD REvIEwPLAN NUREG-1537, Part 2, has been reproduced from the best available copy. CONTENTS Page ABSTRACT ............... '.iii ABBREVIATIONS ........... ... INTRODUCTION ... .. ........... -. X;iiM Background .i.. .............. Document Structure '.'.' .................. xvi General Requirements ............................................X' Contributors ...................... ;xX References .................................................. -' I THE FACILi ................................ TY ....... 1-1 1.1 Introduction .... 1-1 1.2 Summary and Conclusions on Principal Safety Considerations . 1-2 1.3 General Description .. .......................... 1-5 1.4 Shared Facilities and Equipment .......................... ;.'... 1-7 1.5 ComparisonWith Similar Facilities .. ......... 1:- 1.6 Summary of Operations . ;.. 1-10 1.7 Compliance With the Nuclear Waste Policy Act of 1982 1-12 1.8 Facy Modifcations and History.1-13 Appendic 1.1 IntroductionFromNNUREG-1312- Appendix 1.2 DOE Letter to NRC Concerning the Nuclear Waste Policy Act of 1982 2 SITE CHARACTERISTICS ................. 2-1 2.1 Geography and Demography .............. 2-1 2.2 Nearby Industrial Transportation, and Military Facilities .2-3 2.3 Meteorology .......................... 2-4; 2.4 Hydrology ................................................... 2-6 2.5 Geology, Seismology, and Geotechnical Engineering ............ 2-8 2.6 Bibliography .. 2-10 3 DESIGN OF STRUCTURES, SYSTEMS, AND COMPONENTS .. 3-1 3.1 Design Criteria .............. 3-1 3.2 Meteorological Damage . ...................... 3-3 3.3 Water Damage ........ 34 3.4 Seismic Damage . .3-5............ 3-5 3.5 Systems and Components . .............. -...... 3-7 3.6 Bibliography . ...... 3-8 REV. 0. 2/96 . V - STANDARD REVIEW PLAN Page ) 4 REACTOR DESCRIPTION ............................... 4-1 4.1 Summary Description .............................. 4-1 4.2 Reactor Core ............................... 4-1 4.2.1 Reactor Fuel .............................. 4-2 4.2.2 Control Rods ............................... 4-5 4.2.3 Neutron Moderator and Reflector ............................ 4-7 4.2.4 Neutron Startup Source .................................... 4-9 4.2.5 Core Support Structure ............................... 4-12 4.3 Reactor Tank or Pool ................................ 4-14 4.4 Biological Shield ........... ................... 4-17 4.5 Nuclear Design ........................................ 4-19 4.5.1 Normal Operating Conditions .............................. 4-19 4.5.2 Reactor Core Physics Parameters ..... .... .................. 4-22 4.5.3 Operating Limits ................. I ............ .... 4-24 4.6 Thermal-Hydraulic Design .............................. 4-26 5 REACTOR COOLANT SYSTEMS ............................. 5-1 5.1 Summary Description .............. ................. 5-2 5.2 Primary Coolant System ................ .............. 5-2 5.3 Secondary Coolant System . .............................. 5-7 5.4 Primary Coolant Cleanup System ............................. 5-10 5.5 Primary Coolant Makeup Water System ............. ........... 5-12 5.6 Nitrogen-16 Control System . ............................... 5-14 5.7 Auxdiary Systems Using Primary Coolant ....................... 5-16 5.8 Reference ............................... 5-18 6 ENGINEERED SAFETY FEATURES ........................... 6-1 6.1 Summary Description ................ .............. 6-4 6.2 Detailed Descriptions . ............................... -4 6.2.1 Confinement .............................. 6-4 6.2.2 Containment .............................. 6-7 6.2.3 Emergency Core Cooling System ............................ 6-11 6.3 References ............................... 6-13 7 INSTRUMETATION AND CONTROL SYSTEMS ...... ......... 7-1 7.1 Summary Description ..................................... 7-2 7.2 Design of Instrumentation and Control Systems ....... ............ 7-3 7.3 Reactor Control System ..................................... 7-3 7.4 Reactor Protection System ................................... 7-9 7.5 Engineered Safety Features Actuation Systems ....... ............ 7-14 7.6 Control Console and Display Instruments ........ ............... 7-16 7.7 Radiation Monitoring Systems ............... ................ 7-20 7.8 References . ....................................... 7-22 VI REV. O,2J96 NUREG-1537,PART2NUREG-1537PART2 vi REV.0,2/96 - - Coffrs Page 8 ELECTRICAL POWER SYSTEMS ............................. 8-1 8.1 Normal Electrical Power Systems .............................. 8-1 8.2 Emergency Electrical Power Systems ............................ 8-3 9 AUXILIARY SYSTEMS :.; ....9-1 9.1 Heating, Ventilation, and Air Conditioning Systems .9-1 9.2 Handling and Storage of Reactor Fuel ............. ............... 94 9.3 Fire Protection Systems and Programs ............ ................. 9-8 9.4 CommunicationSystems .................. 9-10 9.5 Possession and Use of Byproduct, Source, and Special Nuclear Material ........................................ 9-11 9.6 Cover Gas Control in Closed Primary Coolant Systems ..... ......... 9-14 9.7 Other Auxiliary Systems .................................... 9-16 10 EXPERIMENTAL FACiLITIES AND UTILIZATION .... ...... 10-1 10.1 Summary Description ..................... 102...12 10.2 Experimental Facilities .................................... 10-3 10.3 Experiment Review .................... 10-8 10.4 References .................... ;-.'.;.'.'.'.'.10-11 11 RADIATION PROTECTION PROGRAM AND WASTE MANAGEMEENT .. ......... 11-1 11.1 RadiationProtection . '... .. 11-2 11.1.1 Radiation Sources ........................ ......... 11-2 1.1.2 Radiation Protection Program .............. 1-5 11.1.3 ALARAProgram .... 11-10 11.1.4 RadiationMonitoringand Surveying .11-11 11.1.5 Radiation Exposure Control and Dosimetry ...... 11-14 11.1.6 Contamination
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