Document: NUREG-0800
Document ID: 805f7e09-51a2-413b-92af-e23bb9073497
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070493.pdf
Revision Date: 2023-06
Chapter: 8
Section ID: 8
CFR Part: 
CFR Title: 

Content:
n all sources of offsite power by: a) loading the station distribution buses, including all Class 1E buses down to the 120/208 v level, to at least 30%; b) recording the existing grid and Class 1E bus voltages and bus loading down to the 120/208 volt level at steady state conditions and during the starting of both a large Class 1E and non-Class 1E motor (not concurrently); Note: To minimize the number of instrumented locations, (recorders) during the motor starting transient tests, the bus voltages and loading need only be recorded on that string of buses which previously showed the lowest analyzed voltages from item 3 above. c) using the analytical techniques and assumptions of the previous voltage analyses cited in item 3 above, and the measured existing grid voltage and bus loading conditions recorded during conduct of the test, calculate new set of voltages for all the Class 1E buses down to the 120/208 volt level; d) compare the analytically derived voltage values against the test results. With good correlation between the analytical results and the test results, the test verification requirement will be met. That is, the validity of the mathematical model used in performance of the analyses of item 3 will have been established; therefore, the validity of the results of the analyses is also established. In general the test results should not be more than 3% lower than the analytical results; however, the difference between the two when subtracted from the voltage levels determined in the original analyses should never be less than the Class 1E equipment rated voltages. 8A-17 DRAFT Rev. 3 - April 1996 C. REFERENCES 1. General Design Criterion 17, "Electric Power Systems."42 1. Regulatory Guide 1.153, "Criteria for Power, Instrumentation, and Control Portions of Safety Systems."43 32. Millstone Unit No. 2, Safety Evaluation Supporting Amendment No. 16 to License No. DPR-65. 43. NRC Summary of Meeting for Arkansas Nuclear One Incident of September 16, 1978, dated