Document: NUREG-0800
Document ID: 968e9bbe-e8ca-4639-a8d2-f96483377bae
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1219/ML12191A219.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
of the SAR expected to identify the types and quantities of radioactive material in the plant. II. ACCEPTANCE CRITERIA 1. Added clarification of the requirement to identify radiation monitors used to monitor high radiation levels in containment, consistent with 10 CFR 50.34(f)(2)(xvii) and NUREG-0737, Item II.F.1 2. Provided clarification to the staff regarding the need to identify the radiation environment of equipment important to safety, required by 10 CFR 50.49(e)(4) and GDC 4. This change is consistent with and supports the portion of the application review performed in SRP Subsection 3.11. 3. Provided clarification regarding the need to ensure adequate access to important areas following an accident, consistent with 10 CFR 50.34(f)(2)(vii) and Section II.B.2 of NUREG- 0737. 4. Added a statement clarifying the need to ensure radiation monitors were provided to assess RCS pressure boundary leakage, consistent with GDC 14 and GDC 30. 5. Added a statement clarifying the requirement 10 CFR Part 50, Appendix E “Emergency Planning and Preparedness for Production and Utilization Facilities”, Section VI.2(a), which requires radiation monitoring systems for reactor coolant radioactivity, containment radiation level, condenser air removal radiation level and process radiation monitor levels. 6. Added a statement describing requirements in 10 CFR 52.47(a)(22) regarding the use of operating experience. 7. Added a statement describing requirements in 10 CFR 20.1406 regarding minimization of contamination of the facility, the environment, waste generation and facilitation of decommissioning. 8. Added a statement clarifying the intended use of RG 1.70 during this review. 9. Added a statement clarifying the use of the guidance in RG 1.140 in conjunction with RG 8.8 guidance for evaluating design features to maintain ORE ALARA. 10. Added a statement regarding the use of the guidance contained in RG 1.89 as it relates to identifying the radiation dose to equipment in