Document: NUREG-0800
Document ID: 3c241845-034f-4f89-b12a-f51967895c13
Document Type: srp
Title: PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1307/ML13071A494.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
CFR Part: 
CFR Title: 

Content:
iques for Decommissioning of Light Water Reactors.” 75. NUREG/CR-4013, “LADTAP II – Technical Reference and User Guide,” April 1986. 76. NUREG/CR-4653, “GASPAR II – Technical Reference and User Guide,” March 1987. 77. NRC Inspection Manual Chapter IMC-2504, “Construction Inspection Program - Inspection of Construction and Operational Programs,” issued October 3, 2007. 78. Notice entitled, “Notice of Availability for Referencing in License Amendment Applications Model Safety Evaluation on Technical Specification Improvement to Eliminate Requirements on Post Accident Sampling Systems Using the Consolidated Line Item Improvement Process” (ADAMS Accession No. ML003750475. See Federal Register, Volume 66, page 66949, December 27, 2001 for supplemental information). 11.5-47 Draft Revision 6 – August 2014 79. RG 1.11, “Instrument Lines Penetrating Primary Reactor Containment.” 80. RG 1.21, “Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water- Cooled Nuclear Power Plants.” 81. RG 1.33, “Quality Assurance Program Requirements (Operation).” 82. RG 1.45, “Guidance on Monitoring and Responding to Reactor Coolant System Leakage.” 83. RG 1.68, “Initial Test Programs for Water-Cooled Nuclear Power Plants.” 84. RG 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition).” 85. RG 1.97, “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants.” For plant systems that are important to safety and also used to comply with 10 CFR Part 20 requirements, see guidance of BTP 7-10 as it relates to guidance on instrumentation and control design features for process and effluent radiological monitoring. 86. RG 1.101, “Emergency Planning and Preparedness for Nuclear Power Reactors.” 87. RG 1.109, “Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for