Document: NUREG-0800
Document ID: 66e7af3b-21c0-444f-8737-0830bb176eba
Document Type: srp
Title: PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A182.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
CFR Part: 
CFR Title: 

Content:
in Leakage Detection Sensitivity,” dated August 3, 2005. (Revision 1). 11.5-12 Revision 6 – January 2016 15. The review of design features of steam and power conversion systems and interfaces with radwaste management and monitoring systems is conducted under SRP Section 10.4, and SRP Section 5.4.2 using the guidance of RG 1.26, RG 1.29, and RG 1.143. The systems may include the main condenser evacuation system, turbine gland sealing system, condensate cleanup system, steam generator blowdown system, secondary-steam system chemistry, steam generator blowdown treatment system, circulating water system, turbine component cooling water system, and turbine floor drains. 16. The review of design features of plant and building ventilation systems and interfaces with radwaste management and monitoring systems is conducted under SRP Section 9.4 and SRP Chapter 6 using the guidance of RG 1.13, “Spent Fuel Storage Facility Design Basis”; RG 1.29; RG 1.52; RG 1.140; and RG 1.143. The systems include the reactor containment building ventilation and treatment systems, spent-fuel pool area ventilation system, isolation condenser exhaust, auxiliary and radwaste buildings and area ventilation systems, turbine building and area ventilation system, and ESF ventilation systems. 17. The review of the fire protection program and interfaces with building ventilation systems, and radiation monitoring equipment in detecting the presence of radioactivity, given the use or presence of flammable or combustible materials (as spent resins, charcoal media, and high efficiency particulate air filters, and dry wastes), is performed under SRP Section 9.5.1, “Fire Protection Program,” and SRP Section 11.4, using the guidance of RG 1.189, “Fire Protection for Nuclear Power Plants.” 18. The review of the ALARA provisions of RGs 8.8 and 8.10 in system design and operation to assure compliance with the occupational dose limits of 10 CFR 20.1201, “Occupational Dose Limits”; and 10 CFR