Document: NUREG-0800
Document ID: 0c942a2c-afa6-4bbd-8f3f-4eede9dc146e
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350048.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
eas within the restricted area will be divided into (number of zones) radiation zones. The dose rate criterion for each of these zones is derived from expected occupancy and access restrictions. These criteria are then used as the basis for the radiation shielding design. This allows for arrangements of radioactive equipment that are in accordance with the requirements of 10 CFR Part 20, and the guidelines of Regulatory Guide 8.8. During plant operation and refueling conditions, the Health physics staff will evaluate area access classifications, and monitor entry into areas to update posting and entry requirements in accordance with 10 CFR Part 20.203 (and Standard Technical Specifications). All plant radiation sources capable of producing radiation levels in excess of 100 rads per hour will be shielded and clearly marked, indicat- ing 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 312. 3-13 Rev. 2 - July 1981 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 as low as is reasonably achievable, in accordance with the ALARA provisions of Regulatory Guides 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