Document: NUREG-0800
Document ID: 65bf963b-2ae7-4caf-aee2-1ceabe52e775
Document Type: srp
Title: INITIAL PLANT TEST PROGRAM - FINAL SAFETY ANALYSIS REPORT1
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070650.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.2
CFR Part: 
CFR Title: 

Content:
SRP Section, requires that each licensee (licensee in this context is licensed to receive and possess byproduct material) perform, or permit the Commission to perform tests of radiation detection and monitoring instruments. In nuclear power plants, radiation detection and monitoring instruments are used for ambient monitoring related to worker radiation protection, effluent monitoring, automatic initiation of features to mitigate accidental releases of radioactive materials, and automatic initiation of engineered safety features to mitigate the consequences of design basis accidents. Application of 10 CFR 30.53 to the initial test program ensures that capabilities to perform these functions are adequately verified initially and that deficiencies are identified and corrected. This provides increased assurance of reliable DRAFT Rev. 3 - April 1996 14.2-10 radiation detection/monitoring and instrument response to any detected adverse radiological conditions. 2. 10 CFR 50.34(b)(6)(iii) requires that each application for a license to operate a facility include a final safety analysis report. The final safety analysis report is required to include information concerning facility operation including plans for preoperational testing and initial operations. A major purpose of the initial test program (including preoperational testing and testing during initial operation) is to verify that SSCs are capable of performing their safety functions as specified in the design and assumed/credited in safety analyses. Application of 10 CFR 50.34(b)(6)(iii) to the initial test program ensures that the applicant submits adequate information, commitments, and plans demonstrating that capability will exist for initial operation within the bounds of the design and safety analyses and that initial testing activities will be conducted in a sequence and manner which minimizes operational reliance on untested SSCs/safety functions. 3. Appendix B to 10 CFR 50 requires, in Section XI, that a