Document: NUREG-0800
Document ID: 968e9bbe-e8ca-4639-a8d2-f96483377bae
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1219/ML12191A219.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
UREG-0737, item II.F.1; and RG 1.97 and the Memorandum from D.G. Eisenhut, NRR, to Regional 12.3-12.4-21 Draft Revision 5 – October 2012 Administrators dated August 16, 1982 regarding calibration of radiation monitoring equipment. ii. 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. iii. Emergency power should be provided for installed accident monitoring systems. iv. The accident monitoring systems should have usable ranges that include the maximum calculated accident levels and should be designed to operate properly in the environment caused by the accident. v. Two high-range radiation monitors are provided in containment in accordance with the requirements of 10 CFR 50.34(f)(2)(xvii) and item II.F.1 of NUREG-0737. D. Appendix A to RG 1.21 provides useful guidance about effluent monitoring that applies to the acceptability of in-plant airborne radioactivity monitoring. RG 8.2 includes guidance on surveys to evaluate radiation hazards. The detailed guidance in ANSI N13.1-1999 covers the sampling of airborne radioactive materials in ventilation ducts and stacks of nuclear facilities and may be used for acceptance criteria on the actual sampling process and certain techniques involved. RG 8.8 provides further guidance on monitoring systems. E. Instrumentation for monitoring areas where reactor fuel is stored or handled will be acceptable if it meets the criteria of 10 CFR 50.68 or 10 CFR 70.24. F. To the extent that it is not covered in section application Section 5.2.5 or Section 11, the specified sensitivity of radiation monitoring equipment provided for Reactor Coolant Pressure Boundary Leakage detection (i.e. RG 1.45) is acceptable if it is capable of meeting the required fluid leakage detection criteria. G. To the extent that it is not covered in BTP 5-1 or application Section 11.5, the specified sensitivity of radiation monitoring equipment provided for Primary