Document: NUREG-0800
Document ID: 8da52d2b-9980-4076-8056-2cafebb25ed6
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550060.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
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Content:
les for conformance to parts of the method discussed herein are contained in the referenced regulatory guides, NUREGs, and generic letters. VI. REFERENCES 1. 10 CFR 50.34(f), “Additional TMI-Related Requirements,” paragraph 10 CFR 50.34(f)(2)(xviii). 2. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 3. 10 CFR Part 50, Appendix A, General Design Criterion 10, “Reactor Design.” 4. 10 CFR Part 50, Appendix A, General Design Criterion 12, “Suppression of Reactor Power Oscillations.” 5. Regulatory Guide 1.68, “Initial Test Programs for Water-Cooled Nuclear Power Plants,” March 2007. 6. Regulatory Guide 1.133, Rev. 1, “Loose Parts Detection Program for the Primary System of Light-Water-Cooled Reactors,” May 1981, ADAMS Accession No. ML003740137. 7. NUREG-0737, “Clarification of TMI Action Plan Requirements,” November 1980. 8. NUREG-1449, “Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States,” Final Report, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, September 1993. 9. NRC Letter to All Licensees of Operating Westinghouse and CE PWRs (Except Arkansas Nuclear One-Unit 2 and San Onofre Units 2 and 3), “Inadequate Core Cooling Instrumentation System (Generic Letter No. 82–28),” December 10, 1982. 10. NRC Letter to All Boiling Water Reactors (BWR) Licensees of Operating Reactors Except Lacrosse, Big Rock Point, Humboldt Bay and Dresden-1), “Reactor Vessel Water Level Instrumentation in BWRs (Generic Letter No. 84–23),” October 26, 1984. 11. NRC Letter to All Licensees of Operating BWRs and PWRs and License Applicants, “Technical Resolution of Generic Issue No. B-59-(N-1) Loop Operation in BWRs and PWRs (Generic Letter No. 86–09),” March 31, 1986. 12. NRC Letter to All Holders of Operating Licenses and Construction Permits for Pressurized Water Reactors (PWRs), “Loss of Decay Heat Removal