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Category:Regulatory Analysis
MONTHYEARML22076A0022023-05-18018 May 2023 Regulatory Analysis for Draft Regulatory Guide DG-1404 (RG 1.253 Rev 0) ML21288A1122022-01-31031 January 2022 DG-1393, RG 1.248 Rev. 0 Regulatory Analysis ML21285A2692021-10-12012 October 2021 Rev 2 Courtesy Copy for ACRS Review ML21004A1682021-03-12012 March 2021 Regulatory Analysis DG-1357 ML20231A8912020-11-0606 November 2020 DG 1360 RG 1.205 Rev 2 Regulatory Analysis (RA) ML20231A8742020-11-0606 November 2020 DG 1359 RG 1.189 Rev 4 Regulatory Analysis (RA) ML20091L6962020-04-30030 April 2020 Public Comment Resolution Table DG-1353 for RG 1.233, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approval ML19206A4932020-02-0606 February 2020 DG-1287 RA from Gw (1) ML18337A2142019-04-30030 April 2019 Regulatory Analysis for Draft Regulatory Guide DG-1353 - Guidance to Inform Content of Non-LWR Applications ML17258A5802019-04-30030 April 2019 DG-1284 (Rg 1.199) - Regulatory Analysis ML16172A2392019-04-30030 April 2019 DG-1283 Reg Analysis ML18129A0852018-06-30030 June 2018 DG-1336 Regulatory Analysis ML16091A2712018-02-28028 February 2018 DG-1329 Regulatory Analysis ML17083A1332017-12-31031 December 2017 DG-1335 - Regulatory Analysis ML14041A3452014-09-22022 September 2014 Periodic Review of Rg 1.198 ML12237A1242014-03-21021 March 2014 Regulatory Analysis for DG-5038 Special Nuclear Material Doorway Monitors. ML13051A0352013-05-31031 May 2013 Regulatory Analysis for Rg 1 68, Revision 4 ML12219A4002013-04-24024 April 2013 Regulatory Analysis to Draft Regulatory Guide (DG)-1235), Qualification Tests for Safety-Related Actuators in Nuclear Power Plants (Proposed Revision 1 of Regulatory Guide 1.73, Dated January 1974) ML12298A0732012-11-28028 November 2012 Draft Regulatory Guide DG-1259 ML12160A0492012-09-17017 September 2012 Regulatory Analysis to Rg 1.68.3, Rev. 1 ML12160A1702012-09-0606 September 2012 Regulatory Analysis to Rg 1.68.1, Revision 2, Initial Test Program of Condensate and Feedwater Systems for Light-Water Reactors. ML1031207522012-08-0909 August 2012 Regulatory Analysis for DG-1208, Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants ML11273A0602012-06-30030 June 2012 Regulatory Analysis for Rg 1.140 Revision DG-1280 ML1135501992012-06-30030 June 2012 Regulatory Analysis for DG-1277, Initial Test Program of Emergency Core Cooling Systems for Boiling-Water Reactors ML1201700632012-02-29029 February 2012 Regulatory Analysis for Rg 1.106, Rev. 2 2023-05-18
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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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REGULATORY ANALYSIS REGULATORY GUIDE 1.106, REVISION 2 THERMAL OVERLOAD PROTECTION FOR ELECTRIC MOTORS ON MOTOR
-OPERATED VALVES Statement of the Problem Electric motor
-operated valves used in nuclear power plants may be disabled by heat buildup in the motor internal parts. The root cause of the failures could be insulation breakdown or rotor metal damage or both. Thermal overload protection devices can be used to protect against such deficiencies by cutting off power to the motor when a condition exists where the motor is experiencing heat buildup. However, thermal overload protection devices can disable safety
-related motor
-operated valves and prevent the valves from actuating to fulfill a safety function. Consequently, the industry guidance must be followed to ensure that the thermal overload device does not become a source of failure. The existing guide dates to 1977 and the regulatory position is based in part on Institute of Electrical and Electronics Engineers, Inc. (IEEE) Standard 279
-1971, "Thermal Overload Protection for Electric Motors on Motor
-Operated Valves."
That standard has been superseded by IEEE Standard 603
-2009, "Criteria for Safety Systems for Nuclear Power Generating Stations," pointing out the need to see if Regulatory Guide (RG) 1.106 is acceptable as is, if it needs to be withdrawn, or if it should to be updated.
Objective The objective of this regulatory action is to insure the necessary guidance and criteria is available to applicants/so they can properly protect the motor
-operated valve motor from excessive heat while ensuring that the motor
-operated valve is not disabled by either spurious or premature trips of the thermal overload protection device, which could prevent the valve from performing its intended safety function.
Alternative Approaches The U.S. Nuclear Regulatory Commission (NRC) staff considered the following alternate approaches for RG 1.106:
- a. Do not revise RG 1.106
- b. Withdraw RG 1.106
- c. Revise RG 1.106.
Under this alternative, NRC would not revise or issue additional guidance, and the current guidance would be retained. If NRC does not take action, no changes will result in costs or benefit to the public, licensees, or NRC. However, the "no action" alternative would not address identified concerns with the current version of the RG. NRC would continue to review each application on a case
-by-case basis. This alternative provides a baseline condition from which any other alternatives will be assessed. Moreover, Institute of Electrical and Electronics Engineers, Inc. (IEEE) Standard 279
-1971 referred in the regulatory position of RG 1.106, Revision 1, "Thermal Overload Protection for Electric Motors on Motor
-Operated Valves," has been superseded by IEEE Standard 603-2009, "Criteria for Safety Systems for Nuclear Power Generating Stations." This can cause confusion among the users of the RG by referencing
out-of-date standards.
Alternative 1: Do Not Revise RG 1.106
Withdrawing this regulatory guide would leave a void in NRC's regulatory guidance relative to thermal overload protection of electric motors on motor
-operated valves. By eliminating guidance for future applicants, the content of future applications could vary from applicant to applicant, thereby making the review of these applications more burdensome for the staff. The burden on applicants would be greater under this alternative than under Alternative 1 or Alternative 3 because applicants would spend more time preparing applications due to the lack of guidance.
Alternative 2. Withdraw RG 1.106 Under this alternative, NRC would revise RG 1.106 to provide additional guidance that is clear and concise to protect the motor
-operated valve motor from excessive heat while ensuring that the motor
-operated valve is not disabled by either spurious or premature trips of the thermal overload protection device, which could prevent the valve from performing its intended safety function. This RG will also eliminate any margin for confusion or misinterpretation that was associated with Revision 1. This will also update the guide to the latest industry standards.
Alternative 3: Revise RG 1.106 Comparison of Alternatives For Alternative 1, the benefit would be that no agency resources would be committed to revising the regulatory guide. Applicants would continue to use guidance with which many are already familiar with. They would not incur any costs needed to revise their method of implementing the guide. However, RG 1.106 would not contain the most current guidance in accordance with an industrial consensus standard For Alternative 2, withdrawing the guide could be done at very modest cost. The benefit would be removal of a guide that does not reflect the changes relative to an industrial consensus standard since 1971. The impact of withdrawal is significant. By eliminating guidance for future applicants, the content of future applications could vary from applicant to applicant, thereby making the review of these applications more burdensome for the staff. Likewise, due to the lack of guidance, applicants would be burdened by spending more time preparing applicants than under Alternative 1 or 3.
For Alternative 3, the value to the NRC staff and its applicants in revising the guide would be the benefits associated with providing guidance consistent with the most recent version of an industrial consensus standard. The impact on the NRC would be costs associated with updating the guide along with reviewing and providing comments to the NRC during the public comment period and possible revisions to existing licensing plans.
Conclusion NRC intends to revise and issue RG 1.106, Revision 2 to enhance the licensing process and to provide guidance for compliance with the applicable regulations in 10 CFR Part 50. The staff has concluded that the proposed regulatory action will increase safety and reduce any unnecessary burden that could arise by the misinterpretation of the current guidance in RG 1.106, Revision 1. Moreover, the staff does not foresee any adverse effects associated with issuing a revision of this RG. In doing this regulatory analysis, the staff considered the components of the guide to see what the individual costs might be.
The staff concluded that this RG does not have separate components in the regulatory position. Therefore the agency proposed action consists of a single technical requirement/recommendation.