Document: NUREG-0800
Document ID: 1a1e8dec-a4fe-47ea-b26f-caf30796f404
Document Type: srp
Title: - 2.2.2  IDENTIFICATION OF POTENTIAL HAZARDS IN SITE VICINITY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070220.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.2.1
CFR Part: 
CFR Title: 

Content:
ty of the plant or special plant design measures to prevent radiological releases in excess of the 10 CFR Part 100 guidelines. For design certification reviews the findings will also summarize, to the extent that the review is not discussed in other SER sections, the staff's ITAAC evaluation, including design acceptance criteria (DAC), site interface requirements, and COL action items that are relevant to this SRP section.28 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. DRAFT Rev. 3 - April 1996 2.2.1-6 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGs. VI. REFERENCES 1. Department of the Army Technical Manual TM5-1300, "Structures to Resist the Effects of Accidental Explosions," June 1969. 2. Regulatory Guide 1.91, "Evaluation of Explosions Postulated to Occur on Transportation Routes Near Nuclear Power Plant Sites." 3. Regulatory Guide 1.78, "Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release." 4. Regulatory Guide 1.95, "Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release." 5. National Transportation Safety Board Railroad Accident Report, "Southern Railway Company, Train 154, Derailment with Fire and Explosion, Laurel, Mississippi, January 25, 1969," October 6, 1969. 6. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 7. NUREG-0014 Safety Evaluation Report, Hartsville Nuclear Plants A1, A2, B1, and B2, April 1976, Docket STN