Document: NUREG-0800
Document ID: bfe08773-10ce-45c6-9767-3cbe51c1726f
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070720019.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
, used, or stored. In addition, GDC 63 provides for adequate monitoring spaces containing radioactive waste systems. Prompt detection of excessive radiation levels in these areas resulting from normal operations or abnormal operational occurrences is necessary to identify potentially hazardous conditions for the plant workers and possible releases of radioactivity. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 1. The staff will review the information on radiation protection design features furnished in the SAR, including referenced parts of Chapters 9 and 11, for completeness in accordance with Regulatory Guide 1.70 (or RG 1.206 for DC or COL applicants under 10 CFR Part 52). The reviewer will evaluate the SAR text and the scaled layout drawings of the facility, concentrating on the sources, shielding, and layouts for the auxiliary building, including the radwaste systems, decontamination facilities, office and access control areas, laundry, lockers and shower rooms (including the personnel 12.3-12.4-15 Revision 3 - March 2007 decontamination area), and laboratory facilities; the fuel handling facilities, including the spent fuel pool fuel transfer and related equipment; and the BWR turbine building, including location of steam lines, reheaters, and moisture separators. For the CP PSAR, this review is particularly concerned with preliminary design features that may not appear to be consistent with ensuring that ORE will be ALARA. This review will evaluate the radiation protection design features using the guidelines of Regulatory Guide 8.8. The reviewer will