Document: NUREG-0800
Document ID: 55e187c7-8e17-41ed-a88e-0205d1317fb6
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A475.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
006. 13. Memorandum from D.G. Eisenhut, NRR, to Regional Administrators, August 16, 1982, “Proposed Guidance for Calibration and Surveillance Requirements for Equipment Provided to Meet Item II.F.1, Attachments 1, 2, and 3, NUREG-0737,” with enclosures. (ADAMS Accession No. ML103420044) 14. NUREG-0737, “Clarification of TMI Action Plan Requirements.” 15. NUREG-1430, “Standard Technical Specifications for Babcock and Wilcox Plants.” 16. NUREG-1431, “Standard Technical Specifications for Westinghouse Plants.” 17. NUREG-1432, “Standard Technical Specifications for Combustion Engineering Plants.” 18. NUREG-1433, “Standard Technical Specifications for General Electric Plants, BWR/4.” 19. NUREG-1434, “Standard Technical Specifications for General Electric Plants, BWR/6.” 20. NUREG/CR-3587, “Identification and Evaluation of Facility Techniques for Decommissioning of Light Water Reactors.” (ADAMS Accession No. ML081360413) 21. NUREG-1394, Revision 1, “Emergency Response Data System (ERDS) Implementation.” (ADAMS Accession No. ML080790038) 22. NUREG-1242 "NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document,” Evolutionary Designs (Vol. 2, Pt. 1, ADAMS Accession No: ML100430013 and, Vol. 2, Pt. 2, ADAMS Accession No: ML063620331) and Passive Plant Designs (Vol. 3, Pt. 1, ADAMS Accession No: ML070600372 and, Vol. 3, Pt. 2, ADAMS Accession No: ML070600373). 23. RG 1.21, “Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste.” 24. RG 1.3, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors.” 25. RG 1.4, “Assumptions Used for Evaluation of the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors.” 6 Available from the Electric Power Research Institute at http://www.epri.com/ 12.3-12.4-33 Revision 5 –