Document: NRC Regulatory Guide
Document ID: d091c815-99a5-4fc4-8fe1-bedd55306708
Document Type: regulatory_guide
Title: Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants + HISTORY - HISTORY 07/2014 – Periodic Review of Revision 1 – No issues identified 11/2008 – DG-1187 , Proposed Revision 1 Prior to the issuance of Revision 1, RG 1.69 was entitled, "Concrete Radiation Shields for Nuclear Power Plants" (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1421/ML14211A389.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.69
CFR Part: 
CFR Title: 

Content:
Regulatory Guide Periodic Review Regulatory Guide Number: 1.69 Title: Concrete Radiation Shields for Nuclear Power Plants Office: RES/DRA/ETB Technical Lead: Jacob Philip Recommended Staff Action: Reviewed with no issues identified 1. What are the known technical or regulatory issues with the current version of the Regulatory Guide (RG)? Regulatory Guide 1.69, Revision 1, “Radiation Shields for Nuclear Power Plants,” was issued in May 2009, and establishes the NRC’s position for an acceptable approach for the design and construction of concrete radiation shields in nuclear power plants. Also, it encompasses applicable material previously endorsed in Regulatory Guide 2.1 (withdrawn June 2009), “Shield Test Program for the Evaluation of Installed Biological Shielding in Research and Training Reactors.” The NRC staff did not identify any technical or regulatory issues with the current version. The staff has reviewed the guide and has not identified any safety concerns or a need to revise it at this time. The standard ANSI/ANS-6.3.1, “Program for Testing Radiation Shields in Light Water Reactors” that is endorsed in this guide for testing radiation shields was developed in 1987 (reaffirmed in 1998 and 2007), and is still acceptable to the staff. 2. What is the impact on internal and external stakeholders of not updating the RG for the known issues, in terms of anticipated numbers of licensing and inspection activities over the next several years? The staff is not anticipating any issues with operating reactors or new reactors over the next several years. 3. What is an estimate of the level of effort needed to address identified issues in terms of full-time equivalent (FTE) and contractor resources? Currently this guide will not be revised and therefore there is not any required effort and coordination with NRC program offices needed. Also, no contractor support is anticipated. 4. Based on the answers to the questions above, what is the staff action for