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| {{#Wiki_filter:REGULATORY ANALYSIS REGULATORY GUIDE RG 3.75 CORRECTIVE ACTION PROGRAMS FOR FUEL CYCLE FACILITIES (Proposed New Regulatory Guidance) | | {{#Wiki_filter:REGULATORY ANALYSIS REGULATORY GUIDE RG 3.75 CORRECTIVE ACTION PROGRAMS FOR FUEL CYCLE FACILITIES (Proposed New Regulatory Guidance) |
| : 1. Statement of the Problem This regulatory guide describes methods and procedures that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable when developing corrective action programs (CAPs) for fuel cycle facilities that are licensed under Title 10 of the Code of Federal Regulations (10 CFR) Part 40, "Domestic Licensing of Source Material" or 10 CFR Part 70, "Domestic Licensing of Special Nuclear Material"; or holders of certificates of compliance for gaseous diffusion plants under 10 CFR Part 76, "Certification of Gaseous Diffusion Plants." NRC is issuing a new guide in conjunction with the withdrawal of Draft NUREG-2154, "Acceptability of Corrective Action Programs for Fuel Cycle Facilities." | | : 1. Statement of the Problem This regulatory guide describes methods and procedures that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable when developing corrective action programs (CAPs) for fuel cycle facilities that are licensed under Title 10 of the Code of Federal Regulations (10 CFR) Part 40, Domestic Licensing of Source Material or 10 CFR Part 70, Domestic Licensing of Special Nuclear Material; or holders of certificates of compliance for gaseous diffusion plants under 10 CFR Part 76, Certification of Gaseous Diffusion Plants. NRC is issuing a new guide in conjunction with the withdrawal of Draft NUREG-2154, Acceptability of Corrective Action Programs for Fuel Cycle Facilities. |
| | | In the staff requirements memorandum (SRM) for SECY-10-0031, Revising the Fuel Cycle Oversight Process (Agencywide Documents Access and Management System [ADAMS] Accession No. ML102170054), the Commission directed the NRC staff to make modest adjustments to the existing oversight program to enhance its effectiveness and efficiency. The Commission further directed the staff to reflect in the NRCs Enforcement Policy that most fuel cycle licensees have voluntarily developed CAPs and that the approach provides incentives for licensees to maintain adequate CAPs. This direction was reiterated in the SRMs for SECY-09-0180 Major Revision to NRC Enforcement Policy, and SECY-11-0140, Enhancements to the Fuel Cycle Oversight Process (ADAMS Accession Nos. |
| In the staff requirements memorandum (SRM) for SECY-10-0031, "Revising the Fuel Cycle Oversight Process" (Agencywide Documents Access and Management System [ADAMS] Accession No. | | ML102390327 and ML120050322, respectively). Section 2.3.2.a of the NRCs Enforcement Policy (ADAMS Accession No. ML13228A199) provides the criteria for NRC-identified Severity Level (SL) IV violations to be dispositioned as non-cited violations (NCVs), and is applicable to licensees and non-licensees with a CAP. Further, Section 2.3.2.a states the NRC will credit a formal CAP that has been inspected and found to meet regulatory guidance, industry standards, or both. In order to provide regulatory stability for fuel cycle licensees who wish to take credit for their CAPs in the Enforcement Policy, guidance should be developed describing acceptable programmatic elements when developing CAPs. |
| ML102170054), the Commission directed the NRC staff to make modest adjustments to the existing oversight program to enhance its effectiveness and efficiency. The Commission further directed the staff to reflect in the NRC's Enforcement Policy that most fuel cycle licensees have voluntarily developed CAPs and that the approach provides incentives for licensees to maintain adequate CAPs. This direction was reiterated in the SRMs for SECY-09-0180 "Major Revision to NRC Enforcement Policy," and SECY-11-0140, "Enhancements to the Fuel Cycle Oversight Process" (ADAMS Accession Nos. | | : 2. Objective The objective of this regulatory action is to provide guidance to fuel cycle licensees and NRC staff on acceptable methods and procedures when developing CAPs for fuel cycle facilities. |
| ML102390327 and ML120050322, respectively). Section 2.3.2.a of the NRC's Enforcement Policy (ADAMS Accession No. ML13228A199) provides the criteria for NRC-identified Severity Level (SL) IV violations to be dispositioned as non-cited violations (NCVs), and is applicable to licensees and non-licensees with a CAP. Further, Section 2.3.2.a states the NRC will credit a formal CAP that has been inspected and found to meet regulatory guidance, industry standards, or both. In order to provide regulatory stability for fuel cycle licensees who wish to take credit for their CAPs in the Enforcement Policy, guidance should be developed describing acceptable programmatic elements when developing CAPs. | | : 3. Alternative Approaches The NRC staff considered the following alternative approaches: |
| : 2. Objective The objective of this regulatory action is to provide guidance to fuel cycle licensees and NRC staff on acceptable methods and procedures when developing CAPs for fuel cycle facilities. | | Alternative 1: Issue New Regulatory Guidance Under this alternative, the NRC would issue guidance to describe the elements and commitments that are necessary for the NRC to determine that a fuel cycle facility licensed or certified in accordance with 10 CFR Part 40, Domestic Licensing of Source Material, Part 70, Domestic Licensing of Special |
| : 3. Alternative Approaches The NRC staff considered the following alternative approaches: | |
| | |
| Alternative 1: Issue New Regulatory Guidance Under this alternative, the NRC would issue guidance to describe the elements and commitments that are necessary for the NRC to determine that a fuel cycle facility licensed or certified in accordance with 10 CFR Part 40, "Domestic Licensing of Source Material," Part 70, "Domestic Licensing of Special Page 2 Nuclear Material," or Part 76, "Certification of Gaseous Diffusion Plants" has an acceptable CAP. The guidance will provide a description of provisions for use by applicants and licensees and will make clear that implementation of the RG is voluntary and is not necessary in order for applicants and licensees to continue to be in compliance with NRC regulations. | |
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| Alternative 2: Issue No Regulatory Guidance Under this alternative, the NRC would not issue new guidance. If NRC does not take action, there would not be any changes in costs or benefit to the public, licensees or NRC. However, the "no-action" alternative would not address changes made in the current revision of the NRC Enforcement Policy which allows SL IV violations for fuel cycl e facilities to be dispositioned as NCVs if the NRC determines that the applicant (non-licensee) or licensee has an adequate CAP.
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| : 4. Consequences Maintaining adequate CAPs is an important facet of sustaining high safety and security performance and is consistent with the Commission's safety culture initiatives. In other words, one of the benefits of licensees implementing adequate CAPs is that they are able to identify and correct issues outside the NRC inspection process. In addition, adequate CAPs support a safety conscious work environment because they enable employees to identify concerns that may affect facility safety and security and provide a formal mechanism for the review and resolution of such concerns.
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| | Nuclear Material, or Part 76, Certification of Gaseous Diffusion Plants has an acceptable CAP. The guidance will provide a description of provisions for use by applicants and licensees and will make clear that implementation of the RG is voluntary and is not necessary in order for applicants and licensees to continue to be in compliance with NRC regulations. |
| | Alternative 2: Issue No Regulatory Guidance Under this alternative, the NRC would not issue new guidance. If NRC does not take action, there would not be any changes in costs or benefit to the public, licensees or NRC. However, the no-action alternative would not address changes made in the current revision of the NRC Enforcement Policy which allows SL IV violations for fuel cycle facilities to be dispositioned as NCVs if the NRC determines that the applicant (non-licensee) or licensee has an adequate CAP. |
| | : 4. Consequences Maintaining adequate CAPs is an important facet of sustaining high safety and security performance and is consistent with the Commissions safety culture initiatives. In other words, one of the benefits of licensees implementing adequate CAPs is that they are able to identify and correct issues outside the NRC inspection process. In addition, adequate CAPs support a safety conscious work environment because they enable employees to identify concerns that may affect facility safety and security and provide a formal mechanism for the review and resolution of such concerns. |
| It may also lead to an improved allocation of resources by the industry and NRC. This is because, even though a licensee is responsible for correcting an NRC-identified SL IV violation that is dispositioned as an NCV, a response to the NRC describing the corrective action would not normally be required. Therefore, the licensee and NRC can focus on important safety and security issues. | | It may also lead to an improved allocation of resources by the industry and NRC. This is because, even though a licensee is responsible for correcting an NRC-identified SL IV violation that is dispositioned as an NCV, a response to the NRC describing the corrective action would not normally be required. Therefore, the licensee and NRC can focus on important safety and security issues. |
| The NRC staff expects that licensees will choose to implement the guidance described in this regulatory guide only if it is perceived to be in their benefit to do so based on consideration of the voluntary nature of the RG and individual applicant and licensee circumstances. | | The NRC staff expects that licensees will choose to implement the guidance described in this regulatory guide only if it is perceived to be in their benefit to do so based on consideration of the voluntary nature of the RG and individual applicant and licensee circumstances. |
| : 5. Conclusion Based on this regulatory analysis, the NRC staff concludes that the issuance of a new regulatory guide is warranted. If licensees implement adequate CAPs, fuel facility safety and security would improve because licensees would be able to self-identify and correct issues, and provide the mechanism for their employees to raise safety and security concerns and the program to review and correct those concerns.}} | | : 5. Conclusion Based on this regulatory analysis, the NRC staff concludes that the issuance of a new regulatory guide is warranted. If licensees implement adequate CAPs, fuel facility safety and security would improve because licensees would be able to self-identify and correct issues, and provide the mechanism for their employees to raise safety and security concerns and the program to review and correct those concerns. |
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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
[Table view]Some use of "" in your query was not closed by a matching "". 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 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 RG 3.75 CORRECTIVE ACTION PROGRAMS FOR FUEL CYCLE FACILITIES (Proposed New Regulatory Guidance)
- 1. Statement of the Problem This regulatory guide describes methods and procedures that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable when developing corrective action programs (CAPs) for fuel cycle facilities that are licensed under Title 10 of the Code of Federal Regulations (10 CFR) Part 40, Domestic Licensing of Source Material or 10 CFR Part 70, Domestic Licensing of Special Nuclear Material; or holders of certificates of compliance for gaseous diffusion plants under 10 CFR Part 76, Certification of Gaseous Diffusion Plants. NRC is issuing a new guide in conjunction with the withdrawal of Draft NUREG-2154, Acceptability of Corrective Action Programs for Fuel Cycle Facilities.
In the staff requirements memorandum (SRM) for SECY-10-0031, Revising the Fuel Cycle Oversight Process (Agencywide Documents Access and Management System [ADAMS] Accession No. ML102170054), the Commission directed the NRC staff to make modest adjustments to the existing oversight program to enhance its effectiveness and efficiency. The Commission further directed the staff to reflect in the NRCs Enforcement Policy that most fuel cycle licensees have voluntarily developed CAPs and that the approach provides incentives for licensees to maintain adequate CAPs. This direction was reiterated in the SRMs for SECY-09-0180 Major Revision to NRC Enforcement Policy, and SECY-11-0140, Enhancements to the Fuel Cycle Oversight Process (ADAMS Accession Nos.
ML102390327 and ML120050322, respectively). Section 2.3.2.a of the NRCs Enforcement Policy (ADAMS Accession No. ML13228A199) provides the criteria for NRC-identified Severity Level (SL) IV violations to be dispositioned as non-cited violations (NCVs), and is applicable to licensees and non-licensees with a CAP. Further, Section 2.3.2.a states the NRC will credit a formal CAP that has been inspected and found to meet regulatory guidance, industry standards, or both. In order to provide regulatory stability for fuel cycle licensees who wish to take credit for their CAPs in the Enforcement Policy, guidance should be developed describing acceptable programmatic elements when developing CAPs.
- 2. Objective The objective of this regulatory action is to provide guidance to fuel cycle licensees and NRC staff on acceptable methods and procedures when developing CAPs for fuel cycle facilities.
- 3. Alternative Approaches The NRC staff considered the following alternative approaches:
Alternative 1: Issue New Regulatory Guidance Under this alternative, the NRC would issue guidance to describe the elements and commitments that are necessary for the NRC to determine that a fuel cycle facility licensed or certified in accordance with 10 CFR Part 40, Domestic Licensing of Source Material, Part 70, Domestic Licensing of Special
Nuclear Material, or Part 76, Certification of Gaseous Diffusion Plants has an acceptable CAP. The guidance will provide a description of provisions for use by applicants and licensees and will make clear that implementation of the RG is voluntary and is not necessary in order for applicants and licensees to continue to be in compliance with NRC regulations.
Alternative 2: Issue No Regulatory Guidance Under this alternative, the NRC would not issue new guidance. If NRC does not take action, there would not be any changes in costs or benefit to the public, licensees or NRC. However, the no-action alternative would not address changes made in the current revision of the NRC Enforcement Policy which allows SL IV violations for fuel cycle facilities to be dispositioned as NCVs if the NRC determines that the applicant (non-licensee) or licensee has an adequate CAP.
- 4. Consequences Maintaining adequate CAPs is an important facet of sustaining high safety and security performance and is consistent with the Commissions safety culture initiatives. In other words, one of the benefits of licensees implementing adequate CAPs is that they are able to identify and correct issues outside the NRC inspection process. In addition, adequate CAPs support a safety conscious work environment because they enable employees to identify concerns that may affect facility safety and security and provide a formal mechanism for the review and resolution of such concerns.
It may also lead to an improved allocation of resources by the industry and NRC. This is because, even though a licensee is responsible for correcting an NRC-identified SL IV violation that is dispositioned as an NCV, a response to the NRC describing the corrective action would not normally be required. Therefore, the licensee and NRC can focus on important safety and security issues.
The NRC staff expects that licensees will choose to implement the guidance described in this regulatory guide only if it is perceived to be in their benefit to do so based on consideration of the voluntary nature of the RG and individual applicant and licensee circumstances.
- 5. Conclusion Based on this regulatory analysis, the NRC staff concludes that the issuance of a new regulatory guide is warranted. If licensees implement adequate CAPs, fuel facility safety and security would improve because licensees would be able to self-identify and correct issues, and provide the mechanism for their employees to raise safety and security concerns and the program to review and correct those concerns.
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