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:
areas in accordance with the requirements of 10 CFR 20.1601, 10 CFR 20.1602, 10 CFR 20.1901, 10 CFR 20.1902, and 10 CFR 20.1903 and access control alternatives in the Standard Technical Specifications (NUREG-1430, NUREG-1431, NUREG- 1432, NUREG-1433, and NUREG-1434) and are acceptable. 12.3-12.4-28 Draft Revision 5 – October 2012 All plant radiation sources capable of producing radiation levels in excess of 1 Gy per hour (100 rads per hour) will be shielded and clearly marked, indicating that potentially lethal radiation fields are possible. If other than permanent shielding is used, administrative controls will be initiated and local audible and visible alarming monitors must be installed to alert personnel if temporary shielding is removed. The radiation shielding will be designed to provide protection against radiation for operating personnel, both inside and outside the plant, and for the general public. The following are several of the shielding design features incorporated into [plant name]. [List several examples of shielding design features used at plant.] Some of the criteria used by [utility] in locating penetrations in shield walls at [plant name] are [list several shield penetration location criteria used]. These shielding techniques are designed to maintain personnel radiation exposures ALARA, in accordance with the provisions of RGs 8.8 and 8.10, and are acceptable. The general shield design methodology and source term inventories used for [plant name] are similar to those from operating reactors. The basic radiation transport analysis used for the applicants’ shield design is based on [list appropriate shielding computer codes used]. The applicant also used shielding information from operating nuclear plants as input data for the shield design calculations. All concrete shielding in the plant will be constructed in general compliance with RG 1.69. The staff finds the shielding design and methodology presented in the [CP PSAR, OL FSAR, DC FSAR, or