Document: NUREG-0800
Document ID: 2c839e4a-a342-4e25-9a7c-82d678a0f754
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340657.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
nd/or Appendix B of this SRP section; and for all Mark III containment designs in accordance with Section 4 of NUREG-0978. 3. Reactor coolant system safety/relief valve(s) - related pool dynamic loads criteria are implemented on all plants with Mark I containments in accordance with section 5 of NUREG-0661 and supplement 1 to it, and for all Mark II and III containments in accordance with section 4.1 of NUREG-0802. VI. REFERENCES The references for this SRP section are those listed in SRP Section 6.2.1, together with the following: la. SRP Section 3.6.2, "Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping." lb. NUREG-0808, "Mark II Containment Program Load Evaluation and Acceptance Criteria." 1c. NUREG-0661, Supplement 1, "Mark I Containment Long Term Program." 6.2. 1. 1.C-8 Rev. 6 - August 1984 Id. NUREG-0763, "Guidelines for Confirmatory In-plant Tests of Safety/Relief Discharge for BWR Plants." le. NUREG-0802, "Safety/Relief Valve Quencher Loads: Evaluation for BWR Mark II and III Containments." If. NUREG-0783, "Suppression Pool Temperature Limits for BWR Containments." 1g. NUREG-0978, "Mark III LOCA-Related Hydrodynamic Load Definition." 6. 2.1. 1.C- 9 Rev. 6 - August 1984