|
---|
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 ML20231A8562020-11-30030 November 2020 Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water 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
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
Regulatory Guide Periodic Review Regulatory Guide Number: 1.63, Revision 3
Title:
Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants Office/division/branch: RES/DE/ICEEB Technical Lead: Eric M. Lysiak Staff Action Decided: Reviewed with issues identified for future consideration
- 1. What are the known technical or regulatory issues with the current version of the Regulatory Guide (RG)?
Revision 3 of RG 1.63 endorses, with some exceptions and clarifications, the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 317-1983, IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations. The IEEE issued a revision to the standard in 2013 (IEEE Std.
317-2013) that includes:
- a new service classification for optical fibers,
- double seals for enhanced electrical penetration safety,
- more effective pressure and seal leak monitoring,
- design tests for electro-magnetic compatibility tests for both electro-magnetic interference and radio frequency interference (susceptibility testing),
- a new section for severe accident conditions,
- an enhanced Annex D - (thermal life and aging), and
- a new Annex E - Bibliography.
It should also be noted that Revision 3 of RG 1.63 endorses the 1986 version of IEEE Std. 741, IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations, (IEEE Std. 741-1986). The IEEE revised this consensus standard in 1990, 1997, and 2007. These revisions include additional references, definitions, an enhanced Annex D - (thermal life and aging), and a new Annex E - Bibliography.
The cited revisions to the endorsed IEEE consensus standards contain enhancements.
However, there are no known technical or regulatory issues with this RG.
- 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?
Since there are no known technical or regulatory issues, there is no impact.
Regulatory Guide Periodic Review
- 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?
Updating RG 1.63 is estimated to require about 320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br /> of NRC staff effort because of the multiple references needing review.
- 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)?
Reviewed with issues identified for future consideration.
- 5. Provide a conceptual plan and timeframe to address the issues identified during the review.
The NRC staff plans to develop a draft regulatory guide to endorse the newer IEEE standard and deliver it to the Regulatory Guidance and Generic Issues Branch (RGGIB) within 18 to 24 months. The draft regulatory guide should be available for public comment within 6 to 9 months of its receipt by RGGIB.
References:
- IEEE Std 741-2007 - IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations NOTE: This review was conducted in April 2017 and reflects the staffs plans as of that date. These plans are tentative and are subject to change.