Document: NUREG-0800
Document ID: 0c942a2c-afa6-4bbd-8f3f-4eede9dc146e
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350048.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
nd NUREG-0737 as they relate to implementing task Action Plan Items II.B.2 and II.F.1(3) for construction permit and operating license applications. 17. ANSI/AHS-HPSSC-6.8.1-1981, "Location and Design Criteria for Area Radiation Monitoring Systems for Light Water Nuclear Reactors," as it relates to criteria for establishment of locations for fixed continuous area gamma radiation monitors, and for design features and ranges of measurement. 18. ANSI N13.1-1969, "Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities," as it relates to the principles which apply in obtaining valid samples of airborne radioactive materials, and acceptable methods and materials for gas and particle sampling. 19. ANSI N16.2-1969, "Criticality Accident Alarm Systems," as it relates to guidance for the prevention of criticality accidents in the handling, storing, processing, and transporting of fissionable materials. 10. ANSI N101.6-1972, "Concrete Radiation Shields," as it relates to require- ments and recommended practices for construction of concrete radiation shielding structures. 21. "Reactor Shielding for Nuclear Engineers" N. M. Schaeffer, Editor; Published by USAEC-OIS1 1973," as it relates to the shield designing process including physics, radiation transport, shielding calculations, special problems, and materials. 22. "Radiation Shielding Design and Analysis Approach for Light Water Reactor Power Plants." Stone and Webster Topical Report, RP-8, 1974," as it relates to the approach and objectives of the shield design and the methods of analysis employed in determining specific shielding requirements. 1. FACILITY DESIGN FEATURES Acceptability of the facility design features will be based or. evidence that the applicant has fulfilled the dose limiting requirements of 10 CFR Part 20.101, 20.103, and 20.104, as well as the radiation protection aspects of General 12.3-6 Rev. 2 - July 1981 Design Criteria 19 and 61, and 10 CFR 50.34. This includes evidence that major