Document: NUREG-0800
Document ID: 49a0a1b8-7ac0-48d6-881a-1c6e94dd2437
Document Type: srp
Title: TRAINING FOR NON-LICENSED PLANT STAFF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350062.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.2.2
CFR Part: 
CFR Title: 

Content:
hods for direct readings at terminal junctions. iii. Methods for calling up (printing) incore data from the plant computer. B. Excore Nuclear Instrumentation (NIS) Use of NIS for determination of void formation; void location basis for NIS response as a function of core temperatures and density changes. C. Vital Instrumentation i. Instrumentation response in an accident environment; failure sequence (time to failure, method of failure); indication reliability (actual vs indicated level). ii. Alternative methods for measuring flows, pressures, levels, and temperatures. a. Determination of pressurizer level if all level transmitters fail. b. Determination of letdown flow with a clogged filter (low flow). c. Determination of other reactor coolant system parameters if the primary methods of measurement has failed. D. Primary Chemistry i. Expected chemistry results with severe core damage; consequences of -transferring small quantities of liquid outside containment; importance of using leak-tight systems. 13. 2.2-310 Rev. 0 - July 1981 ii. Expected isotopic breakdown for core damage; for clad damage. iii. Corrosion effects of extended immersion in primary water; time to failure. E. Radiation Monitoring i. Response of process and area monitors to severe damages; behavior of detectors when saturated; method for detecting radiation readings by direct measurement at detector output (overranged detector); expected accuracy of detectors at different locations; use of detectors to determine extent of core damage. ii. Methods of determining dose rate inside containment from measurements taken outside containment. F. Gas Generation i. Methods of hydrogen generation during an accident; other sources of gas (xenon, krypton); techniques for venting or disposal of non-condensibles. ii. Hydrogen flammability and explosive limit, sources of oxygen in containment or reactor coolant system. III.-REVIEW PROCEDURES Preparation for the review of Section 13.2 of the SAR should include