Document: NUREG-0800
Document ID: b694ca5b-4dcc-4098-be04-431e0137a936
Document Type: srp
Title: - 15.5.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070820081.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
plications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guide, no reformed NUREG. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criteria. 2. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 3. ANS 51.1, “Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor [PWR] Plants,” 1983 (replaces ANSI N18.2-1973) (withdrawn in 1998). 4. ANSI/ANS-52.1-1983, “Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants,” (withdrawn in 1998). 5. Regulatory Issue Summary 2005-29, “Anticipated Transients that could Develop into More Serious Events,” December 14, 2005 (ADAMS Accession No. ML051890212). 6. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 7. RS-001, Revision 0, "Review Standard for Extended Power Uprates," December 2003, (Note 8 of Matrix 8 of Section 2.1). PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50 and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval number 3150-0011 and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.