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| {{#Wiki_filter:Page 1 REGULATORY ANALYSIS Regulatory Guide 1.216, "Containment Structural Integrity Evaluation for Internal Pressure Loadings Above Design-Basis Pressure" (Draft was issued as DG-1203, dated December 2008) | | {{#Wiki_filter:REGULATORY ANALYSIS Regulatory Guide 1.216, Containment Structural Integrity Evaluation for Internal Pressure Loadings Above Design-Basis Pressure (Draft was issued as DG-1203, dated December 2008) |
| : 1. Statement of the Problem Revision 1 to Regulatory Guide 1.57 1 endorsed American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), Section III, Division 1, with some exceptions, for design and loading combinations for metal primary reactor containment system components for nuclear power plants. Regulatory Guide 1.57 gives brief guidance for ultimate capacity of steel containments. | | : 1. Statement of the Problem Revision 1 to Regulatory Guide 1.571 endorsed American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), Section III, Division 1, with some exceptions, for design and loading combinations for metal primary reactor containment system components for nuclear power plants. Regulatory Guide 1.57 gives brief guidance for ultimate capacity of steel containments. |
| Revision 3 to Regulatory Guide 1.136 2 endorsed ASME Code, Section III, Division 2, with some exceptions for design, loading combinations, materials, construction, and testing of concrete containments for nuclear power plants. Regulatory Guide 1.136 also gives brief guidance for ultimate capacity of concrete containments. | | Revision 3 to Regulatory Guide 1.136 2 endorsed ASME Code, Section III, Division 2, with some exceptions for design, loading combinations, materials, construction, and testing of concrete containments for nuclear power plants. Regulatory Guide 1.136 also gives brief guidance for ultimate capacity of concrete containments. |
| The staff proposes to include the use of deterministic performance goals for pressure loads in the containments. Therefore, the publication of this regulatory guidance is necessary to provide detailed and up-to-date guidance on deterministic performance goals for pressure loads in steel and concrete containments in evolutionary and Advanced Light-Water Reactor (ALWR) designs. | | The staff proposes to include the use of deterministic performance goals for pressure loads in the containments. Therefore, the publication of this regulatory guidance is necessary to provide detailed and up-to-date guidance on deterministic performance goals for pressure loads in steel and concrete containments in evolutionary and Advanced Light-Water Reactor (ALWR) designs. |
| : 2. Objective The objective of this regulatory action is to provide acceptable methods for demonstrating containment performance in accordance with regulatory requirements and Commission performance goals for pressure loadings of steel and concrete containments, especially for evolutionary and ALWR designs. | | : 2. Objective The objective of this regulatory action is to provide acceptable methods for demonstrating containment performance in accordance with regulatory requirements and Commission performance goals for pressure loadings of steel and concrete containments, especially for evolutionary and ALWR designs. |
| : 3. Alternative Approaches The U.S. Nuclear Regulatory Commission (NRC) staff considered the following alternative approaches: | | : 3. Alternative Approaches The U.S. Nuclear Regulatory Commission (NRC) staff considered the following alternative approaches: |
| * Take no action. | | * Take no action. |
| * Publish a new regulatory guide. | | * Publish a new regulatory guide. |
| | 1 Regulatory Guide 1.57, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components, U.S. Nuclear Regulatory Commission, Washington, DC. |
| | 2 Regulatory Guide 1.136, Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments, U.S. Nuclear Regulatory Commission, Washington, DC. |
| | Page 1 |
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| 1 Regulatory Guide 1.57, "Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components," U.S. Nuclear Regulatory Commission, Washington, DC.
| | 3.1 Alternative 1: Take No Action Under this alternative, the NRC would not publish guidance on meeting the deterministic containment performance goals for pressure loads. This alternative is considered the baseline or no action alternative. However, if the NRC does not publish guidance on accepted approaches to meet deterministic containment performance goals for pressure loads, the staff position may not be clear. |
| 2 Regulatory Guide 1.136, "Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments," U.S. Nuclear Regulatory Commission, Washington, DC.
| | 3.2 Alternative 2: Publish a New Regulatory Guide Under this alternative, the NRC would publish a new regulatory guide, taking into consideration current regulations, standards, and related staff regulatory positions. |
| Page 2 3.1 Alternative 1: Take No Action Under this alternative, the NRC would not publish guidance on meeting the deterministic containment performance goals for pressure loads. This alternative is considered the baseline or "no action" alternative. However, if the NRC does not publish guidance on accepted approaches to meet deterministic containment performance goals for pressure loads, the staff position may not be clear.
| |
| | |
| 3.2 Alternative 2: Publish a New Regulatory Guide Under this alternative, the NRC would publish a new regulatory guide, taking into consideration current regulations, standards, and related staff regulatory positions. | |
| One benefit of this action is that it would enhance reactor safety by incorporating the latest technical information for guidance on the containment performance for pressure loads and would address the potential ambiguity associated with other regulatory guidance documents. | | One benefit of this action is that it would enhance reactor safety by incorporating the latest technical information for guidance on the containment performance for pressure loads and would address the potential ambiguity associated with other regulatory guidance documents. |
| The costs to the NRC would be the one-time cost of issuing a new regulatory guide (which is expected to be relatively small), and applicants would incur little or no cost. | | The costs to the NRC would be the one-time cost of issuing a new regulatory guide (which is expected to be relatively small), and applicants would incur little or no cost. |
| : 4. Conclusion Based on this regulatory analysis, the staff recommends that the NRC publish this new regulatory guide. The staff concludes that the proposed action will enhance reactor safety by providing updated guidance on the containment performance assessment for pressure loads.}} | | : 4. Conclusion Based on this regulatory analysis, the staff recommends that the NRC publish this new regulatory guide. The staff concludes that the proposed action will enhance reactor safety by providing updated guidance on the containment performance assessment for pressure loads. |
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Category:Regulatory Analysis
MONTHYEARML22250A4722023-04-17017 April 2023 DG 5079 (RG 5.83 Rev 1) Regulatory Analysis ML21155A0042021-07-22022 July 2021 Regulatory Analysis for Regulatory Guide 1.29, Seismic Design Classification for Nuclear Power Plants ML20168A8932021-04-0101 April 2021 Regulatory Analysis for DG-1371, Proposed Revision 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants ML20192A2302020-12-10010 December 2020 Regulatory Analysis for DG 1361 RG 1.89 Revision 2 RA - Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants 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 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) ML20195A1742020-09-17017 September 2020 Regulatory Analysis ML20055G8242020-08-0707 August 2020 Regulatory Analysis for DG 1363 for Rev 4 to Regulatory Guide (RG) 1.105 - Setpoints for Safety-Related Instrumentation ML20078K9252020-08-0505 August 2020 Regulatory Analysis for DG-1370 Proposed Revision 1 of Regulatory Guide (RG) 1.191, Titled, Fire Protection Program for Nuclear Power Plants During Decommissioning ML20105A2162020-07-0101 July 2020 Regulatory Analysis for DG-1372, Rev 4 of RG 1.136 Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments ML14161A6242020-02-12012 February 2020 Regulatory Analysis for Draft Regulatory Guide 3036 ML19213A3432019-09-30030 September 2019 Draft Regulatory Analysis (DG)-1341 - Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses ML19108A4622019-07-31031 July 2019 Regulatory Analysis ML19045A4322019-05-31031 May 2019 Draft Regulatory Guide DG-1356 (Rg 1.187 Rev 2), Guidance for Implementation of 10CFR50.59 Changes, Tests and Experiments - Regulatory Analysis ML19042A1832019-03-31031 March 2019 Regulatory Analysis ML18093A6762019-02-28028 February 2019 DG-1328 Regulatory Analysis ML18158A3012019-01-31031 January 2019 Regulatory Analysis DG-1352 ML18087A1672018-10-31031 October 2018 DG-4019 Reg Analysis ML18016A1302018-08-31031 August 2018 Regulatory Anlaysis DG-5061 ML18086A6852018-06-30030 June 2018 DG-1351 RA ML16358A1562017-03-31031 March 2017 DG-1285 Regulatory Analysis ML15237A3852015-12-0707 December 2015 Regulatory Analysis for DG-4025 ML14310A3382015-09-0303 September 2015 Regulatory Analysis for DG-5049 ML14119A2822015-06-24024 June 2015 Regulatory Analysis DG-1305 ML14356A2472015-04-10010 April 2015 Regulatory Analysis for DG-1314 ML14218A8612014-11-18018 November 2014 Regulatory Analysis, Draft Regulatory Guide DG-5036, Fitness for Duty Programs at New Reactor Construction Sites ML14139A3202014-06-27027 June 2014 Regulatory Analysis for Rg 3.75, Corrective Action Programs for Fuel Cycle Facilities (Proposed New Regulatory Guidance) ML13144A8422013-10-0404 October 2013 Regulatory Analysis for Draft Regulatory Guide 1271 ML12300A3282013-10-0404 October 2013 Regulatory Analysis for Rg 1.79.1, Initial Test Program of Emergency Core Cooling Systems for Boiling-Water Reactors, (Draft Was Issued as DG-1277, Dated June 2012) ML13140A0392013-06-27027 June 2013 Regulatory Analysis for DG-1272, Standard Format and Content for Post-Shutdown Decommissioning Activities Report ML12228A5912012-11-15015 November 2012 Reg Analysis to DG-1294, Pre-Operational Testing of Onsite Electric Power Systems to Verify Proper Load Group Assignments, Electrical Separation, and Redundancy ML12220A0442012-09-21021 September 2012 Regulatory Analysis to Rg 1.92, Rev. 3 Combining Modal Responses and Spatial Components in Seismic Response Analysis. ML12013A0892012-05-31031 May 2012 Regulatory Analysis for DG-1285 ML1035104582012-04-30030 April 2012 Regulatory Analysis to Regulatory Guide 1.218 ML1023803112011-12-31031 December 2011 Regulatory Analysis for DG-4021, General Site Suitability Criteria for Nuclear Power Stations ML1121600132011-10-31031 October 2011 Regulatory Analysis to Rg 1.159, Rev. 2 ML1101300462011-08-0505 August 2011 Regulatory Analysis for DG-4016, Terrestrial Environmental Studies for Nuclear Power Stations (Proposed Revision 2 of Regulatory Guide 4.11, Dated August 1977) ML1121016102011-08-0505 August 2011 Guidance for the Assessment of Beyond-Design-Basis Aircraft Impacts (Draft Was Issued as DG-1176 Dated July 2009) (New Regulatory Guide) ML1033706592011-04-30030 April 2011 Regulatory Analysis, Regulatory Guide 3.67, Standard Format and Content for Emergency Plans for Fuel Cycle and Materials Facilities ML1018005172010-12-31031 December 2010 Regulatory Analysis for Rg 5.80, Pressure-Sensitive and Temper-Indicating Device Seals for Material Control and Accounting of Special Nuclear Material. ML1017203112010-12-15015 December 2010 Regulatory Analysis to Regulatory Guide 4.16, Revision 2 ML1027203352010-10-0404 October 2010 Regulatory Analysis to DG-1196, Qualification for Cement Grouting for Prestressing Tendons in Containment Structures ML1017403272010-08-31031 August 2010 Draft Regulatory Guide 1228, (Revision 1 of Regulatory Guide 1.179), Standard Format and Content of License Termination Plans for Nuclear Power Reactors (Regulatory Analysis) ML1018900472010-07-31031 July 2010 Regulatory Analysis to Regulatory Guide 1.216 Containment Structural Integrity Evaluation for Internal Pressure Loadings Above Design-Basis Pressure. ML1015403482010-06-17017 June 2010 Regulatory Analysis on Rg 1.62, Manual Initiation of Protective Actions, Revision 1 ML1013203172010-06-14014 June 2010 Regulatory Analysis for Revision 3 of Regulatory Guide 1.152 2023-04-17
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MONTHYEARML24038A3102024-04-30030 April 2024 Rev 1 Dedication of Commercial-Grade Items for Use in Nuclear Power Plants ML23286A2862024-02-0202 February 2024 Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23 ML23286A2682024-02-0202 February 2024 Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23) ML23286A2512024-02-0202 February 2024 Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 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 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 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 ML21092A1342021-05-0505 May 2021 Rev. 2 ACRS Version ML21092A1512021-05-0505 May 2021 Rev. 4 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 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 ML21006A3352021-04-0101 April 2021 DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities ML21083A2892021-02-28028 February 2021 Draft for Acrs Review ML21048A4482021-02-17017 February 2021 Rev. 2 ML20120A6332021-01-31031 January 2021 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366) 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) ML20120A6272021-01-31031 January 2021 ASME Code Cases Not Approved for Use, Revision 7 (DG-1369) ML20120A6292021-01-31031 January 2021 Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368) ML21012A1972021-01-12012 January 2021 a Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0 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 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 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 ML20282A2982020-12-0404 December 2020 DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals 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 ML20210M0472020-12-0101 December 2020 Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping ML20231A8562020-11-30030 November 2020 Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants ML20231A8352020-11-30030 November 2020 Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants ML20307A0462020-11-0202 November 2020 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 ANALYSIS Regulatory Guide 1.216, Containment Structural Integrity Evaluation for Internal Pressure Loadings Above Design-Basis Pressure (Draft was issued as DG-1203, dated December 2008)
- 1. Statement of the Problem Revision 1 to Regulatory Guide 1.571 endorsed American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code),Section III, Division 1, with some exceptions, for design and loading combinations for metal primary reactor containment system components for nuclear power plants. Regulatory Guide 1.57 gives brief guidance for ultimate capacity of steel containments.
Revision 3 to Regulatory Guide 1.136 2 endorsed ASME Code,Section III, Division 2, with some exceptions for design, loading combinations, materials, construction, and testing of concrete containments for nuclear power plants. Regulatory Guide 1.136 also gives brief guidance for ultimate capacity of concrete containments.
The staff proposes to include the use of deterministic performance goals for pressure loads in the containments. Therefore, the publication of this regulatory guidance is necessary to provide detailed and up-to-date guidance on deterministic performance goals for pressure loads in steel and concrete containments in evolutionary and Advanced Light-Water Reactor (ALWR) designs.
- 2. Objective The objective of this regulatory action is to provide acceptable methods for demonstrating containment performance in accordance with regulatory requirements and Commission performance goals for pressure loadings of steel and concrete containments, especially for evolutionary and ALWR designs.
- 3. Alternative Approaches The U.S. Nuclear Regulatory Commission (NRC) staff considered the following alternative approaches:
- Publish a new regulatory guide.
1 Regulatory Guide 1.57, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components, U.S. Nuclear Regulatory Commission, Washington, DC.
2 Regulatory Guide 1.136, Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments, U.S. Nuclear Regulatory Commission, Washington, DC.
Page 1
3.1 Alternative 1: Take No Action Under this alternative, the NRC would not publish guidance on meeting the deterministic containment performance goals for pressure loads. This alternative is considered the baseline or no action alternative. However, if the NRC does not publish guidance on accepted approaches to meet deterministic containment performance goals for pressure loads, the staff position may not be clear.
3.2 Alternative 2: Publish a New Regulatory Guide Under this alternative, the NRC would publish a new regulatory guide, taking into consideration current regulations, standards, and related staff regulatory positions.
One benefit of this action is that it would enhance reactor safety by incorporating the latest technical information for guidance on the containment performance for pressure loads and would address the potential ambiguity associated with other regulatory guidance documents.
The costs to the NRC would be the one-time cost of issuing a new regulatory guide (which is expected to be relatively small), and applicants would incur little or no cost.
- 4. Conclusion Based on this regulatory analysis, the staff recommends that the NRC publish this new regulatory guide. The staff concludes that the proposed action will enhance reactor safety by providing updated guidance on the containment performance assessment for pressure loads.
Page 2