|
|
(One intermediate revision by the same user not shown) |
Line 9: |
Line 9: |
| | docket = | | | docket = |
| | license number = | | | license number = |
| | contact person = Rodriguez-Luccioni H L | | | contact person = Rodriguez-Luccioni H |
| | case reference number = DG-1300 | | | case reference number = DG-1300 |
| | document report number = RG-1.033, Rev 3 | | | document report number = RG-1.033, Rev 3 |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:April 2013 Response to Public Comments on Draft Regulatory Guide (DG)-1300 Quality Assurance Program Requirements (Operations) Proposed Revision 3 of Regulatory Guide (RG) 1.33 A notice that Draft Regulatory Guide, DG-1300 (Proposed Revision 3 of RG 1.33) was published for comments in the Federal Register on February 4, 2013 on page 78 FR 7816. The public comment period ended April 1, 2013. Comments were received from the organizat ions listed below. The NRC has combined the comments and NRC staff disposition in the following table. | | {{#Wiki_filter:Response to Public Comments on Draft Regulatory Guide (DG)-1300 Quality Assurance Program Requirements (Operations) |
| | | Proposed Revision 3 of Regulatory Guide (RG) 1.33 A notice that Draft Regulatory Guide, DG-1300 (Proposed Revision 3 of RG 1.33) was published for comments in the Federal Register on February 4, 2013 on page 78 FR 7816. The public comment period ended April 1, 2013. Comments were received from the organizations listed below. The NRC has combined the comments and NRC staff disposition in the following table. |
| Comments were received from the following: Donald Spellman, Chair American Nuclear Society (ANS) Standards Board 555 N. Kensignton Ave. | | Comments were received from the following: |
| La Grange Park, IL 60526 | | Donald Spellman, Chair American Nuclear Society (ANS) Standards Board 555 N. Kensignton Ave. |
| | | La Grange Park, IL 60526 ADAMS Accession No. ML13063A433 Commenter Section of Specific Comments NRC Resolution DG-1300 ANS General This draft Regulatory Guide (RG) endorses the latest, 2012, edition of ANSI/ANS-3.2-2012, This comment did not "Managerial, Administrative, and Quality Assurance Controls for Operational Phase of Nuclear require any answer or Power Plants." The nuclear industry certainly will benefit from an up-to-date endorsement of a action from the staff. |
| ADAMS Accession No. ML13063A433 Commenter Section of DG-1300 Specific Comments NRC Resolution ANS General This draft Regulatory Guide (RG) endorses the latest, 2012, edition of ANSI/ANS-3.2-2012, "Managerial, Administrative, and Quality Assurance Controls for Operational Phase of Nuclear Power Plants." The nuclear industry certainly will benefit from an up-to-date endorsement of a standard that has been revised six times in the past thirty-seven years reflecting a myriad of quality improvements for the industry. It is noted that the NRC recently endorsed American Society of Mechanical Engineers NQA-1-2008/2009 Addenda), "Quality Assurance Requirements for Nuclear Facility Applications," via RG 1.28 in 2010. Thus the industry now finds itself with two recently revised, nuclear standards for design & construction and for operations both of which will have received formal NRC endorsement. This truly is a "win-win" for the nuclear industry and the regulatory environment. A clear delineation of quality assurance requirements is now available for the new generation of plants as well as for consideration of existing licensees who may want to migrate to a consistent set of requirements for their fleet of rectors within their company. | | standard that has been revised six times in the past thirty-seven years reflecting a myriad of quality improvements for the industry. It is noted that the NRC recently endorsed American Society of Mechanical Engineers NQA-1-2008/2009 Addenda), "Quality Assurance Requirements for Nuclear Facility Applications," via RG 1.28 in 2010. Thus the industry now finds itself with two recently revised, nuclear standards for design & construction and for operations both of which will have received formal NRC endorsement. This truly is a "win-win" for the nuclear industry and the regulatory environment. A clear delineation of quality assurance requirements is now available for the new generation of plants as well as for consideration of existing licensees who may want to migrate to a consistent set of requirements for their fleet of rectors within their company. |
| The American Nuclear Society (ANS) is pleased to have developed the subject standard that is now up for NRC endorsement. Similarly, the ANS is particularly pleased that the NRC has taken this proactive route leading to a stability in endorsed requirements that has not existed for over thirty years. This comment did not require any answer or action from the staff.}} | | The American Nuclear Society (ANS) is pleased to have developed the subject standard that is now up for NRC endorsement. Similarly, the ANS is particularly pleased that the NRC has taken this proactive route leading to a stability in endorsed requirements that has not existed for over thirty years. |
| | April 2013}} |
|
---|
Category:Regulatory Guidance
MONTHYEARML20182A1082020-06-30030 June 2020 Periodic Review of RG 5.29 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants ML19126A3062019-05-0808 May 2019 Periodic Review ML18136A7612019-04-30030 April 2019 DG-1335 Public Comment Response ML19025A1732019-01-25025 January 2019 Periodic Review of Rg 1.105 ML19009A2662019-01-14014 January 2019 Periodic Review Rg 1.81 ML18353B0652018-12-20020 December 2018 Periodic Review Memo Rg 1.30 ML18353B0662018-12-20020 December 2018 Periodic Review of Rg 1.30 ML18354A8622018-12-20020 December 2018 Periodic Review Rg 1.89 ML18232A3962018-08-22022 August 2018 Periodic Review of NMSS Regulatory Guides ML18156A5452018-06-0707 June 2018 Results of Periodic Review of Regulatory Guide 8.28 ML18155A4942018-06-0505 June 2018 Periodic Review ML18155A4952018-06-0505 June 2018 Results of Periodic Review of Regulatory Guide (Rg) 1.61, Damping Values for Seismic Design of Nuclear Power Plants. ML18150A2332018-05-31031 May 2018 Periodic Review ML18142B2012018-05-23023 May 2018 Periodic Review of Rg 1.92, Revision 3, Combining Modal Responses and Spatial Components in Seismic Response Analysis ML18102B2352018-05-0101 May 2018 Memorandum - Generic Issue Management Control System Report for the First Half of Fiscal Year 2018 ML18067A7412018-03-0909 March 2018 Rg Memo for 1.109 and 1.112 Periodic Reviews ML14107A4102015-11-17017 November 2015 Public Comment Resolution Table October 2014 ML14056A0112015-03-0909 March 2015 Draft Regulatory Guide (DG)-1299, Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule ML14041A3452014-09-22022 September 2014 Periodic Review of Rg 1.198 ML13109A4672013-06-18018 June 2013 Staff Responses to Public Comments on Rg 1.33 Rev 3 2020-06-30
[Table view]Some use of "" in your query was not closed by a matching "". Category:Regulatory Guide
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
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
Response to Public Comments on Draft Regulatory Guide (DG)-1300 Quality Assurance Program Requirements (Operations)
Proposed Revision 3 of Regulatory Guide (RG) 1.33 A notice that Draft Regulatory Guide, DG-1300 (Proposed Revision 3 of RG 1.33) was published for comments in the Federal Register on February 4, 2013 on page 78 FR 7816. The public comment period ended April 1, 2013. Comments were received from the organizations listed below. The NRC has combined the comments and NRC staff disposition in the following table.
Comments were received from the following:
Donald Spellman, Chair American Nuclear Society (ANS) Standards Board 555 N. Kensignton Ave.
La Grange Park, IL 60526 ADAMS Accession No. ML13063A433 Commenter Section of Specific Comments NRC Resolution DG-1300 ANS General This draft Regulatory Guide (RG) endorses the latest, 2012, edition of ANSI/ANS-3.2-2012, This comment did not "Managerial, Administrative, and Quality Assurance Controls for Operational Phase of Nuclear require any answer or Power Plants." The nuclear industry certainly will benefit from an up-to-date endorsement of a action from the staff.
standard that has been revised six times in the past thirty-seven years reflecting a myriad of quality improvements for the industry. It is noted that the NRC recently endorsed American Society of Mechanical Engineers NQA-1-2008/2009 Addenda), "Quality Assurance Requirements for Nuclear Facility Applications," via RG 1.28 in 2010. Thus the industry now finds itself with two recently revised, nuclear standards for design & construction and for operations both of which will have received formal NRC endorsement. This truly is a "win-win" for the nuclear industry and the regulatory environment. A clear delineation of quality assurance requirements is now available for the new generation of plants as well as for consideration of existing licensees who may want to migrate to a consistent set of requirements for their fleet of rectors within their company.
The American Nuclear Society (ANS) is pleased to have developed the subject standard that is now up for NRC endorsement. Similarly, the ANS is particularly pleased that the NRC has taken this proactive route leading to a stability in endorsed requirements that has not existed for over thirty years.
April 2013