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:
e detection, consistent with GDC 14 and GDC 30, (6) incorporation of guidance regarding the review of radiation monitoring equipment specified in 10 CFR Part 50, Appendix E, Subsection VI.2(a)(i), (6) incorporation of the regulatory bases stated in 10 CFR 52.47(a)(22), for including operating experience in the design phase, consistent with the existing requirements of 10 CFR 20.1101(b) and the definition of ALARA, and the guidance contained in RG 8.8, (6) incorporated use of the types of documents discussed in the EPRI URD and the associated Safety Evaluation documented in NUREG-1242, as sources of information available to the staff for assessing the use of the current state of technology to reduce ORE, consistent with the guidance contained in RG 8.8 and the requirements of 10 CFR 20.1101(b). The changes to this SRP Subsection reflect the experience gained by the staff developed during NRC reviews of DC and COL applications completed after Revision 4 of SRP 12.3-12.4 was issued. The technical changes in each SRP section are as follows: I. AREAS OF REVIEW 1. Added a discussion clarifying the purposes of the review under this SRP section. 2. Added a statement regarding the use of RG 4.21 and Appendix 12.3-12.4-A guidance during 10 CFR 20.1406 design reviews. 3. Added clarification regarding the use of guidance contained in RG 1.206, Subsection C.I.12.3.5, to provide a description of the basis for the dose assessment process for plant construction workers. 4. In order to improve how the staff finds information related to the design features discussed in RG 8.8 Regulatory Position C.2, RG 1.206 Subsection C.I.12.3 and RG 4.21, the discussion under Review Interfaces was expanded to provide 12.3-12.4 -2 Draft Revision 5 – October 2012 guidance to the staff on the sections 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