Document: NUREG-0800
Document ID: 15a004f9-6c99-4bc0-a858-efeaea553e8e
Document Type: srp
Title: REACTOR COOLANT SYSTEM HIGH POINT VENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070440.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.12
CFR Part: 
CFR Title: 

Content:
added to the control room as a result of this requirement do not increase the 54 potential for operator error. A human-factor analysis will be evaluated taking into consideration: (a) the use of this information by an operator during both normal and abnormal plant conditions, (b) integration into emergency procedures, (c) integration into operator training, and (d) other alarms during emergency and need for prioritization of alarms.55 9. PRTBEMEB examines provisions to test for operability of the reactor coolant vent 56 system. Testing should be performed in accordance with subsection IWV of Section XI of the ASME Code for Category B valves. 10. EQBEMEB reviews the reactor coolant vent system (i.e., vent valves, block valves, 57 position indication devices, cable terminations, and piping) to assure that it is seismically and environmentally qualified in accordance with IEEE 344-1975 as supplemented by 58 59 Regulatory Guide 1.100, and Regulatory Guide 1.92 and SEP 3.92, 3.43, and 3.10. 60 61 5.4.12-9 DRAFT Rev. 1 - April 1996 11. SPLB reviews the reactor coolant vent system (i.e., vent valves, block valves, position indication devices, and cable terminations) to assure that it is environmentally qualified62 in accordance with 10 CFR 50.49.63 12. RSBSRXB evaluates the procedures necessary to operate the vent system. The 64 65 operating procedures shall consider the following: a. When venting is needed and when it is not needed. b. The method for determining the size of a noncondensible bubble. c. A variety of initial conditions from which venting may take place. d. Operator actions and necessary instrumentation. For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site interface requirements and combined