Document: NUREG-0800
Document ID: 02fef38f-79ed-4d55-825f-81551bcfdcdc
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550016.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 35, "Emergency Core Cooling." 2. 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors," and Appendix K to 10 CFR Part 50, "ECCS Evaluation Models." 3. Standard Review Plan Section 6.3, "Emergency Core Cooling System." 4. NUREG-0609, "Asymmetric Blowdown Loads on PWR Primary Systems Resolution of Generic Task Action Plan A-2." 5. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing Licenses." 6. NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980. 7. Regulatory Guide 1.157, "Best-Estimate Calculations of Emergency Core Cooling System Performance." 8. Generic Letter 85-012, "Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" for Westinghouse Designed Nuclear Steam Supply Systems." 9. Generic Letter 86-005, “Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps" for Babcox and Wilcox Designed Nuclear Steam Supply Systems." 10. Generic Letter 86-006, "Implementation of TMI Action Item