Document: NUREG-0800
Document ID: 0f097ac2-b7b1-437d-a055-1546a9094ef6
Document Type: srp
Title: CONCRETE CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100620888.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.1
CFR Part: 
CFR Title: 

Content:
30. SRM SECY 93-087, Staff Requirements Memorandum, “SECY-93-087—Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs.” 31. RG 1.84, “Design, Fabrication, and Material Code Case Acceptability, ASME Section III.” 32. RG 1.147, “Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1.” 3.8.1-29 Revision 3 - May 2010 APPENDIX A TO SRP SECTION 3.8.1 STAFF POSITION ON BOILING-WATER REACTOR CONTAINMENT POOL DYNAMICS 1. LOSS-OF-COOLANT ACCIDENTS A. Loads associated with loss-of-coolant accidents (LOCAs) (such as drywell pressure; annulus pressurization; suppression pool pressures including chugging, condensation oscillation, vent clearing, and pool swell; and jet loads and drag loads acting on submerged structures/components and those above the water surface) should be treated as abnormal pressure loads, Pa. Appropriate load combinations and load factors should be applied accordingly. B. All of the various LOCA-induced loads may be combined in accordance with their actual time-dependent mutual occurrence. 2. SAFETY/RELIEF VALVE DISCHARGE A. Safety/relief valve (SRV) loads (such as single valve, single valve plus adjacent valve, automatic depressurization system valves, and all valves) should be included in all load combinations as defined in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section III, Division 2, Subsection CC. However for the load combination that contains 1.5 Pa, a load factor of 1.25 should be applied to the appropriate SRV loads. Also, for the severe environmental load combination, the load factor should be 1.3, which is consistent with the practice of treating SRV as a live load. B. A single active failure causing one SRV discharge must be considered in combination with the design-basis accident. C. Appropriate multiple SRV discharges should be considered in combination with the small-break accident and intermediate-break