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Category:Regulatory Guide
MONTHYEARML22264A1092024-10-30030 October 2024
DG-5078 - Fatigue Management for Nuclear Power Plant Personnel at Commercial Nuclear Plants Licensed Under 10 CFR Part 53
ML22257A1732024-10-30030 October 2024
DG-1413 - Technology-Inclusive Identification of Licensing Events for Commercial Nuclear Plants
ML22203A1312024-10-30030 October 2024
DG-5076 - Guidance for Technology-Inclusive Requirements for Physical Protection of Licensed Activities at Commercial Nuclear Plants
ML22200A0372024-10-30030 October 2024
DG-5073 - Fitness-For-Duty Programs for Commercial Nuclear Plants and Manufacturing Facilities Licensed Under 10 CFR Part 53
ML22199A2572024-10-30030 October 2024
DG-5075 - Establishing Cybersecurity Programs for Commercial Nuclear Plants Licensed Under 10 CFR Part 53
ML22199A2462024-10-30030 October 2024
DG-5074 - Access Authorization Program for Commercial Nuclear Plants
ML23291A2982024-02-29029 February 2024
DG-1422 (RG 1.245 Rev 1) Preparing Probabilistic Fracture Mechanics (Pfm) Submittals
ML23072A0452024-01-31031 January 2024
Watermarked - RG 1.235 Revision 0 - Emergency Planning for Decommissioning Nuclear Power Reactors (02-14-24)
ML23248A3432023-08-31031 August 2023
Draft Regulatory Guide DG-1404, Rev. 1, Guidance for a Technology-Inclusive Content-Of-Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications,
ML23102A0322023-05-17017 May 2023
Rev 2 Periodic Review
ML22196A0652023-01-31031 January 2023
DG 1408 ASME Code Cases Not Approved for Use (RG 1.193 Rev 8)
ML22196A0632023-01-31031 January 2023
Draft Regulatory Guide DG 1407, Operation and Maintenance Code Case Acceptability, ASME OM Code (RG 1.192 Rev 5)
ML22195A2842023-01-31031 January 2023
Draft Regulatory Guide DG 1406, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1 (RG 1.147 Rev 21)
ML22195A2822023-01-31031 January 2023
DG 1405 - Design, Fabrication, and Materials Code Case Acceptability, ASME Section III (RG 1.84 Rev 40)
ML22101A2632023-01-30030 January 2023
Rev 2 Acceptability of ASME Code Section III Division 5 High Temperature Reactors
ML22221A2202022-10-0505 October 2022
Rev 0, Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Production and Utilization Facilities
ML22223A1592022-08-12012 August 2022
Draft Regulatory Guide 1.250, Rev. 0, Dedication of Commercial-Grade Digital Instrumentation & Control Item for Use in Nuclear Power Plants (for ACRS on 9-7-22)
ML22066B2752022-05-31031 May 2022
Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation
ML21288A1152022-01-31031 January 2022
Draft Regulatory Guide DG-1393, RG 1.248 Rev. 0, Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations
Regulatory Guide 1.1922021-12-31031 December 2021
Operation and Maintenance Code Case Acceptability, ASME OM Code
Regulatory Guide 1.1472021-12-17017 December 2021
0, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1
Regulatory Guide 1.842021-12-17017 December 2021
9, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III
Regulatory Guide 1.1932021-12-17017 December 2021
ASME Code Cases Not Approved for Use
ML21288A5652021-11-0909 November 2021
ACRS Version DG-1393 (RG 1.248 Rev. 0) (Advance Copy for ACRS Use)
ML20356A1272021-03-31031 March 2021
Regulatory Guide RG 1.240, Fresh and Spent Fuel Pool Criticality Analyses
ML21068A4042021-03-12012 March 2021
RG 1.102. Transmittal Memo Periodic Review 2021
ML20301A1702021-02-17017 February 2021
Transmittal Memo to OCA for Revision 4 of RG 1.136, Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments
ML20339A5582021-02-0303 February 2021
DG-1304 for Rev 0 of RG 1.243, Safety-Related Steel Structures and Steel-Plate Composite (Sc) Walls for Other than Reactor Vessels and Containments
ML20339A5592021-02-0303 February 2021
Regulatory Analysis for DG-1304 for Rev 0 of RG 1.243, Safety-Related Steel Structures and Steel-Plate Composite (Sc) Walls for Other than Reactor Vessels and Containments
ML21033B0912021-02-0202 February 2021
Draft for ACRS Meeting 3-3-21: Regulatory Guide - RG 1.240 Rev.0 for Fresh and Spent Fuel Pool Criticality Analyses
ML20301A1672021-02-0101 February 2021
Regulatory Guide (RG) 1.136, Rev 4, Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments
Regulatory Guide 1.1772021-01-0404 January 2021
(DG-1287) an Approach for Plant-Specific, Risk Informed Decisionmaking: Technical Specifications
ML21033B0832020-10-23023 October 2020
Draft for ACRS Meeting 3-3-21: Public Comment Resolution Table for DG-1373
ML20078K9202020-08-31031 August 2020
DG-1370 Proposed Revision 1 of Regulatory Guide (RG) 1.191, Fire Protection Program for Nuclear Power Plants During Decommissioning
ML20142A4892020-08-31031 August 2020
DG-1351 Rev 1 - Licensee Actions to Address Nonconservative Technical Specifications_FY20
ML20164A2142020-08-0404 August 2020
FRN for Regulatory Guide 3.15, Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant
ML20125A7322020-07-0101 July 2020
FRN for RG 1.187-Rev 2 - Guidance for Implementation of 10 CFR 50.59, Changes, Tests and Experiments
Regulatory Guide 1.1872020-06-30030 June 2020
Rev. 2, Guidance for Implementation of 10 CFR 50.59, Changes, Tests and Experiments
ML20055F4902020-06-30030 June 2020
Reg Guide 1.236 - Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod Drop Accidents
ML20055F4892020-06-10010 June 2020
Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod. Response to Public Comments - 2nd Comment Period
ML20141L6132020-05-31031 May 2020
Reg Guide 1.142 Rev 3 - Safety Related Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments)
ML19340B2902020-04-30030 April 2020
Draft Regulatory Guide DG-1321 (Proposed New Regulatory Guide RG-1.237) Guidance for Changes During Construction for New Nuclear Power Plants Licensed Under 10 CFR Part 52
ML19156A1292020-02-29029 February 2020
Regulatory Guide (Rg) 1.151, Revision 2 Instrument Sensing Lines
ML19266A6192020-02-21021 February 2020
Response to Public Comments on DG-1337
ML20048A0812020-02-21021 February 2020
Withdrawal RG 5.43 Plant Security Force Duties - Withdrawal Bases Questions 2-11-2020
ML14161A6212020-02-12012 February 2020
DG-3036 Standard Format and Content of License Applications for Storage Only of Unirradiated Power Reactor Fuel and Associated Radioactive Material
ML20022A2142020-01-22022 January 2020
Draft Regulatory Guide DG-1364, Volcanic Hazards. Draft for ACRS Public Meeting 1-22-20
ML19175A0442019-12-19019 December 2019
Regulatory Guide (Rg) 1.180, Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems
ML19213A3452019-09-30030 September 2019
Draft Regulatory Guide DG-1341, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses
ML19141A2142019-08-16016 August 2019
Regulatory Guide Periodic Review
2024-02-29
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Text
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 NRCs 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 this guide (Reviewed with no issues identified, Reviewed with issues identified for future consideration, Revise, or Withdraw)?
The staff reviewed the guide and has not identified any issues that need to consider for a new revision, or withdrawal. The guide should be maintained as written.
- 5. Provide a conceptual plan and timeframe to address the issues identified during the review.
The staff currently is not planning to take any action on this guide.
NOTE: This review was conducted in July 2014 and reflects the staffs plans as of that date. These plans are tentative and subject to change.