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Category:Regulatory Guide
MONTHYEARML24038A3102024-04-30030 April 2024
Rev 1 Dedication of Commercial-Grade Items for Use in Nuclear Power Plants
ML23263A9972024-02-0202 February 2024
Watermarked - DG-5072 - Rev 0 of RG 5.90 - Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors
ML23286A2512024-02-0202 February 2024
Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23
ML23286A2682024-02-0202 February 2024
Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23)
ML23286A2862024-02-0202 February 2024
Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23
ML23286A2822024-02-0202 February 2024
Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23
ML23286A2782024-02-0202 February 2024
Watermarked - DG-5075 - Cyber Security 10-13-23
ML23194A1942023-08-31031 August 2023
Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs
ML22165A0722023-02-28028 February 2023
DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2
ML23012A2422023-02-28028 February 2023
DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants
ML23018A2932023-02-16016 February 2023
Draft Regulatory Guide DG-1418 (RG 1.212 Rev 2), Sizing Large Lead-Acid Storage Batteries. (ACRS Copy)
Regulatory Guide 5.892022-11-0101 November 2022
Rev.0, Fitness-for-Duty Programs for Commercial Power Reactor and Category I Special Nuclear Material Licensees
ML22067A0142022-03-31031 March 2022
Rev 3 ACRS Spent Fuel Heat Generation in an ISFSI
ML22048B8222022-02-18018 February 2022
DG-1389 (ACRS Version for 3-16-22 Meeting) - Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors
ML22040A0822021-10-30030 October 2021
Document to Support ACRS Subcommittee Meeting - Redline RG 1.57, Rev 3, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components
ML21167A3512021-06-0101 June 2021
Rev 5 Final Watermarked for ACRS
ML21092A1512021-05-0505 May 2021
Rev. 4 ACRS Version
ML21092A1342021-05-0505 May 2021
Rev. 2 ACRS Version
ML21181A2492021-04-30030 April 2021
Watermark for ACRS Fc Meeting RG 1.9 Rev 5
ML21006A3372021-04-0101 April 2021
Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities
ML21006A3352021-04-0101 April 2021
DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities
ML20168A8832021-04-0101 April 2021
DG-1371, Proposed Rev 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants
ML21083A2892021-02-28028 February 2021
Draft for Acrs Review
ML21048A4482021-02-17017 February 2021
Rev. 2
ML21011A2312021-01-31031 January 2021
Rev 4 (Draft for ACRS Fc Review on 2-3-21)
ML20120A6312021-01-31031 January 2021
Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367)
ML20120A6292021-01-31031 January 2021
Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368)
ML20120A6332021-01-31031 January 2021
Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366)
ML20120A6272021-01-31031 January 2021
ASME Code Cases Not Approved for Use, Revision 7 (DG-1369)
ML21012A1972021-01-12012 January 2021
a Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0
ML20183A4232020-12-31031 December 2020
Draft Regulatory Guide DG-1361 (Proposed Rev. 2 to Reg. Guide 1.89), Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants
Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities2020-12-31031 December 2020
Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
ML20238B8732020-12-29029 December 2020
Public Comment Resolutions on DG-1362 for RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
ML20282A2992020-12-0404 December 2020
Regulatory Analysis for DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
ML20282A2982020-12-0404 December 2020
DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
ML20210M0472020-12-0101 December 2020
Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping
ML20231A8352020-11-30030 November 2020
Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants
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Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants
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Draft for ACRS Public Meeting, RG 1.200, R3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
ML20210M0442020-10-28028 October 2020
Regulatory Analysis: Draft Regulatory Guide DG-1288 - an Approach for Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping (Proposed Revision 2 of Regulatory Guide 1.178, Dated September 2003)
ML20154K5842020-09-17017 September 2020
Results of Periodic Review of Regulatory Guide (RG) 1.78
ML20182A7882020-08-31031 August 2020
DG 1373 for RG 1.240 - Fresh and Spent Fuel Pool Criticality Analyses
ML20055G8232020-08-0707 August 2020
DG 1363 for Proposed Rev 4 to Regulatory Guide (RG) 1.105 - Setpoints for Safety-Related Instrumentation
Regulatory Guide 3.152020-07-31031 July 2020
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
Regulatory Guide 1.2362020-07-30030 July 2020
Draft for ACRS Review
ML20119A6142020-04-28028 April 2020
Response to Comments for RG 1.236 for ACRS
ML20105A4672020-04-14014 April 2020
Memo to OCA - for Revision 1 of Regulatory Guide 8.39, Release of Patients Administered Radioactive Material
ML20099F0262020-04-0707 April 2020
Public Comment Resolution Table for DG 1341 (Regulatory Guide (RG) 1.188, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses, Rev. 2
ML19206A4892020-02-0606 February 2020
Draft Regulatory Guide DG-1287, an Approach for Plant-Specific, risk-Informed Decisionmaking: Technical Specifications
ML19116A0772019-08-31031 August 2019
Draft Regulatory Guide DG-5040, Urine Specimen Collection and Test Results Review Under 10 CFR Part 26, Fitness for Duty Programs.
2024-04-30
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Text
Regulatory Guide Periodic Review Regulatory Guide Number: 1.208, Revision 0
Title:
A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion Office/Division/Branch: RES/DE/SGSEB Technical Lead: Vladimir Graizer Recommended Staff Action: Revise.
- 1. What are the known technical or regulatory issues with the current version of the Regulatory Guide (RG)?
The RG dates to 2007 and some references have been superseded since then. For example, the RG refers to the seismic sources identified and characterized by the Lawrence Livermore National Laboratory (LLNL) and the Electric Power Research Institute (EPRI) and states that the characterization of specific seismic sources found in these databases may still represent the latest information available at the time that a PSHA is to be undertaken. NUREG-2115, Central and Eastern United States Seismic Source Characterization for Nuclear Facilities, (CEUS-SSC), has replaced the EPRI and LLNL models and needs to be incorporated in the RG update. The recently developed Ground Motion Models (GMMs) replaced the previous EPRI 2004 and 2006 GMMs and need to be part of the RG update. The RG also references the CEUS and WUS (Western United States) Time History databases provided in NUREG/CR-6728, Technical Basis for Revision of Regulatory Guidance on Design Ground Motions:
Hazard- and Risk- Consistent Ground Motion Spectra Guidelines, with respect to the selection of earthquake time histories for use in time history-based site response analyses. More recently updated databases, such as the Pacific Earthquake Engineering Center (PEER) Ground Motion Databases for the WUS and CEUS, need to be referenced in the guide.
The RG update should also incorporate staff experience from the reviews of early site permit (ESP) and combined license (COL) applications conducted since 2007 as well as the lessons learned from the seismic hazard re-assessments conducted as part of the Fukushima Near Term Task Force activities.
To date, the staff has identified several site response-related revisions needed in the RG. Appendix E Seismic Wave Transmission Analysis of the RG refers to the different approaches for developing a site-specific GMRS presented in NUREG/CR-6728. These approaches vary in complexity from simple deterministic amplification of probabilistically derived rock response spectra (Approaches 1, 2A, and 2B) to rigorous treatment of soil amplification within the probabilistic seismic hazard analysis (Approaches 3, 3A, 3B, and 4). The RG needs to be updated to provide guidance on selecting the appropriate site response approach for a particular site. In addition, guidance related to the following areas should be added to the RG: 1) Selection of kappa and representation of epistemic uncertainty; 2) Development of input motions for time domain methods or random
vibration theory (RVT) methods; 3) Development of probabilistic site-specific soil hazard curves (Approaches 3 or 4); and 5) Use of appropriate shear modulus reduction and damping curves and/or low strain damping values for materials in the site response model that are below the depth range where materials can be retrieved for testing.
In addition, Section C.3 Evaluation of New Information Obtained from Site-specific Investigations needs to be updated in the context of new SSHAC guidelines (e.g.
NUREG-2213, Updated Implementation Guidelines for SSHAC Hazard Studies) and the new ground motion models, such as the recently published NGA East ground motion models.
- 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?
While there are no large power reactor license applications anticipated in the near future (next 3 to 5 years), small modular reactor applications are anticipated in the next two years. Not updating the RG will hinder the progress of potential applicants.
- 3. What is an estimate of the level of effort needed to address identified issues in terms of full-time equivalent (FTE) and contract resources?
Complete revision of the RG updates will take approximately 2.0 FTEs of staff time.
Contract dollars needed will be on the order of $500K.
- 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)?
Based on the above the recommended action is Revise.
- 5. If a RG should be revised, provide a conceptual plan and timeframe to accomplish this.
The plan is to revise the RG reflective of short-term and long-term needs. The revision will incorporate updating references and some basic technical definitions to bring the RG to full compliance with already established staff positions. The revision will also incorporate results of the ongoing research activities in site-response calculations and methodologies.
The timeframe for the update is for staff to finish it by the end of the fourth quarter of the 2022 fiscal year, and to release for public comment in the first quarter of the 2023 fiscal year.
NOTE: This review was conducted in December 2020 and reflects the staffs plans as of that date. These plans are tentative and subject to change.