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:
e capability to assess the radiation hazard in areas which may be accessed during the course of an accident, in accordance with the criteria of Item II.F.1 of NUREG-0718 and 0737, and Regulatory Guide 1.97. 2. Portable instruments to be used in the event of an accident should be placed so as to be readily available to personnel responding to an emergency. 3. Emergency power should be provided for installed accident monitoring systems. 4. The accident monitoring systems should have usable ranges which include the maximum calculated accident levels; and should be designed to operate properly in the environment caused by the accident. 5. Applicants for CPs and OLs should provide two high-range radia- tion monitor systems in containment which are documented to meet the requirements of Table II.F.1 of NUREG-0718 and 0737. d. Regulatory Guide 1.21, Appendix A, provides useful guidance about effluent monitoring, that is applicable to the acceptability of airborne radioactivity monitoring in-plant. Regulatory Guide 8.2 includes guidance on surveys to evaluate radiation hazards. American National Standard ANSI N13.1-1969 provides detailed guid- ance on sampling airborne radioactive materials in nuclear facilities and may be used for acceptance criteria on the actual sampling process and certain techniques involved. Regulatory Guide 8.8 provides further guidance on monitoring systems. e. Instrumentation to monitor for accidental criticality will be accept- able if it meets the criteria of 10 CFR Part 70.24 (a)(l), Regulatory Guide 8.12, and ANSI Standard N16.2. 5. DOSE ASSESSMENT The dose assessment will be acceptable if it documents in appropriate detail the assumptions made, calculations used, the results for each radiation zone, including numbers and types of workers involved in each, expected and design dose rates, and projected person-rem doses, in accordance with Regulatory Criteria 8.19. III. REVIEW PROCEDURES The information on radiation protection design features