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| {{#Wiki_filter:Regulatory Guide Periodic Review Regulatory Guide Number: | | {{#Wiki_filter:Regulatory Guide Periodic Review Regulatory Guide Number: 1.69 |
| 1.69 Title: Concrete Radiation Shields for Nuclear Power Plants Office: RES/DRA/ETB Technical Lead: | |
| Jacob Philip
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| Recommended Staff Action: Reviewed with no issues identified | | ==Title:== |
| : 1. What are the known technical or regulatory issues with the current version of the Regulatory Guide (RG)? | | Concrete Radiation Shields for Nuclear Power Plants Office: RES/DRA/ETB Technical Lead: Jacob Philip Recommended Staff Action: Reviewed with no issues identified |
| 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. | | : 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| Also, it encompasses applicable material previously endorsed in Regulatory Guide 2.1 (withdrawn June 2009), "Shield Test Program for the Evaluation of Installed Biological Shielding in Research and Training Reactors." | | Also, it encompasses applicable material previously endorsed in Regulatory Guide 2.1 (withdrawn June 2009), Shield Test Program for the Evaluation of Installed Biological Shielding in Research and Training Reactors.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 re gulatory 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. | | The NRC staff did not identify any technical or regulatory issues with the current version. |
| : 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 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. | | 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? | | : 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. | | 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)? | | : 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. | | 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. | | : 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. | | 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.}} |
| NOTE: This review was conducted in July 2014 and reflects the staff's plans as of that date. These plans are tentative and subject to change.}} | |
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Category:Regulatory Guide
MONTHYEARML23248A3432023-08-31031 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 ML22195A2822023-01-31031 January 2023 DG 1405 - Design, Fabrication, and Materials Code Case Acceptability, ASME Section III (RG 1.84 Rev 40) 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) ML22196A0632023-01-31031 January 2023 Draft Regulatory Guide DG 1407, Operation and Maintenance Code Case Acceptability, ASME OM Code (RG 1.192 Rev 5) ML22196A0652023-01-31031 January 2023 DG 1408 ASME Code Cases Not Approved for Use (RG 1.193 Rev 8) 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 ML20142A4892020-08-31031 August 2020 DG-1351 Rev 1 - Licensee Actions to Address Nonconservative Technical Specifications_FY20 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 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 ML20055F4902020-06-30030 June 2020 Reg Guide 1.236 - Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod Drop Accidents Regulatory Guide 1.1872020-06-30030 June 2020 Rev. 2, Guidance for Implementation of 10 CFR 50.59, Changes, Tests and Experiments 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) 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 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 ML18312A2422019-04-30030 April 2019 Draft Regulatory Guide DG-1353, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water ML18114A2262018-08-31031 August 2018 Draft Regulatory Guide DG-1343, (Rg 1.192 Rev 3), Operation and Maintenance Code Case Acceptability, ASME OM Code ML16315A1302018-06-30030 June 2018 Rev. 1, Guidelines for Evaluating the Effects of Light-Water Reactor Water Environments in Fatigue Analyses of Metal Components. ML17083A1332017-12-31031 December 2017 DG-1335 - Regulatory Analysis ML17083A1342017-12-31031 December 2017 Draft Regulatory Guide DG-1335,(Revision 5 to Reg Guide 1.97), Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants ML16182A3212016-10-28028 October 2016 Draft Regulatory Guide (DG)-1337, Restart of a Nuclear Power Plant Shut Down by a Seismic Event ML16104A2202016-09-30030 September 2016 Draft Regulatory Guide DG-1332 (Proposed Revision 3 of Regulatory Guide 1.12), Nuclear Power Plant Instrumentation for Earthquakes ML15313A4252016-06-30030 June 2016 DG-1292, Dedication of Commercial-Grade Items for Use in Nuclear Power Plants ML15203B4102015-12-18018 December 2015 Draft Regulatory Guide DG-8033, Operating Philosophy for Maintaining Occupational Radiation Exposure as Low as Is Reasonably Achievable ML14107A4102015-11-17017 November 2015 Public Comment Resolution Table October 2014 2023-08-31
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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.