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Category:Report
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MONTHYEARML24292A1502024-10-21021 October 2024 SSHAC Level 1 Demonstration Project ML24292A1392024-10-21021 October 2024 Applying a Graded Approach and Adapting Guidance on Site Characterization of External Hazards for Advanced Reactor and Microreactor Applications ML24292A1532024-10-21021 October 2024 Simulation of Physics-Based 0-10 Hz Synthetic Ground Motion Using High - Performance Computing Supporting Refinements to Regional Ground Motion Models for CEUS ML24032A0102023-09-30030 September 2023 FY2023 University Nuclear Leadership Program (Unlp) Research and Development Award Executive Summaries ML22048B5932022-04-12012 April 2022 Attachment -1 Table - EDG Trips Bypass at Various Plants Based on TSs and FSARs ML21314A2282022-03-0808 March 2022 Impacts of Embrittlement on Reactor Pressure Vessel Integrity from a Risk-Informed Perspective Final Report ML21312A0862021-11-0808 November 2021 2021 Research Grant Executive Summaries ML21280A3632021-10-26026 October 2021 Watermarked for ACRS - Response to Public Comments on Proposed RG 1.244 -10-7 ML21155A1322021-05-24024 May 2021 Faculty Development Executive Summaries ML21145A0902021-05-24024 May 2021 Trade School and Community College Scholarship Executive Summary ML21145A0892021-05-24024 May 2021 Scholarship Executive Summaries ML21145A0882021-05-24024 May 2021 Fellowship Executive Summaries ML21145A0872021-05-24024 May 2021 Faculty Development Executive Summaries ML21155A1352021-05-24024 May 2021 Trade School and Community College Scholarship Executive Summary ML21155A1342021-05-24024 May 2021 Scholarship Executive Summaries ML21155A1332021-05-24024 May 2021 Fellowship Executive Summaries ML20287A1982021-01-0101 January 2021 Public Comment Dispositions on DG-1370 for Regulatory Guide (RG) 1.191, Rev 1, Fire Protection Program for Nuclear Power Plants During Decommissioning ML20164A2132020-07-31031 July 2020 Response to Comments on DG-3036 for RG 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 ML19353B2032020-04-0101 April 2020 Public Comments to Rev 1 of Regulatory Guide 8.39, Release of Patients Administered Radioactive Material NUREG-2233, EPRI 3002016054 Comments Resolution2020-03-31031 March 2020 NUREG-2233 EPRI 3002016054 Comments Resolution ML20100E2992020-03-31031 March 2020 Technical Letter Report - TLR-RES/DE/CIB-2020-03, Final Report on Support for Xfem Component Integrity Analysis: Task 1 Literature Survey ML19156A1282020-02-0606 February 2020 Public Comments Rg 1.151 OIG-19-A-06, Status of Recommendations: Audit of NRCs Process for Developing and Coordinating Research Activities (OIG-19-A-06) (RES Response)2020-01-16016 January 2020 Status of Recommendations: Audit of NRCs Process for Developing and Coordinating Research Activities (OIG-19-A-06) (RES Response) ML19175A0482019-12-19019 December 2019 Public Comments on Rg 1.180 ML19248C6472019-12-0404 December 2019 Enclosure 4 - Staff Report Documenting Technical Basis for the Alternative FHA Model NUREG-2178, Comment Resolution - NUREG-2178 Vol 2 Final2019-08-31031 August 2019 Comment Resolution - NUREG-2178 Vol 2 Final ML19101A3962019-06-30030 June 2019 DG-1329 (RG-1.8 R-4) Public Comment Response ML19162A4022019-06-13013 June 2019 01_04_Exercise_C Task 5 MSO Analysis ML19162A4052019-06-13013 June 2019 01_05_Exercise_B Task 7 Cutset Analysis Print Color ML18172A1902018-08-22022 August 2018 Assessment Plan - Enclosure 1 ML18172A1912018-08-22022 August 2018 Assessment Plan - Enclosure 2 ML16315A1272018-06-30030 June 2018 Public Comment Resolutions for DG-1309 ML17319A5502017-12-0707 December 2017 NRC Non-Light Water Reactor Vision and Strategy - Strategy 2 Near-Term Implementation Action Plan Progress Report for Fiscal Year 2017 ML17278A7592017-10-0505 October 2017 Soarca Sequoyah Updated Draft Executive Summary ML23123A3512017-10-0202 October 2017 Response to SRM-22-0009: Proposed Limited Revision to Policy Statement on Criteria for Reporting Abnormal Occurrences ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review ML15097A0762015-04-0606 April 2015 Soarca Peach Bottom 2005 Site File ML12024A0782011-12-28028 December 2011 State-of-the-Art Reactor Consequence Analysis (Soarca); Exclusive Summary for the Full NUREG for Peach Bottom and Surry ML1120701442011-07-26026 July 2011 Draft Letter Report, Entitled Risk-Informing EP Oversight: Evaluation of EALs Using Saphia Pilot Study of Peach Bottom and Surry ML0209305252002-03-31031 March 2002 SMSAB-02-01: Analysis Report: Comparison Between TRAC-M Version 3782 and RELAP5 MOD 3.2.2 Gamma Calculations of Selected Pressurized Thermal Shock Scenarios of the Oconee Unit 1 Plant 2024-10-21
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Response to Public Comments on Draft Regulatory Guide (DG)-1352 Instrument Sensing Lines Proposed Revision 2 of Regulatory Guide (RG) 1.151 On 02/08/2019, the NRC published a notice in the Federal Register (84 FR 2934) that Draft Regulatory Guide, DG-1352 (Proposed Revision 2 of RG 1.151), was available for public comment. The public comment period ended on 04/09/2019. The NRC received comments from the organizations listed below. The NRC has combined the comments and NRC staff responses in the following table.
Comments were received from the following:
Ronald LaVera Southern Nuclear Anonymous NRO/DLSE/RPAC 3535 Colonnade Parkway ADAMS Accession No. ML19099A192 US NRC Birmingham, AL 35243 11555 Rockville Pike ADAMS Accession No. ML19102A240 Rockville, MD 20852 ADAMS Accession No. ML19072A243 Commenter Section of Specific Comments NRC Resolution DG-1352 Ronald Section The proposed revision to RG 1.151 omitted 2 key criteria The staff agreed that IEEE Std 622-1987 should be in LaVera B/Section C from the Regulatory Positions of the 2010 version of the Section C instead of Section B. The staff does not agree RG 1.151. that ANSI/ISA-67.02.01-1999 should be in Section C.
IEEE Std 622-1987 regarding heat tracing.
ANSI/ISA-67.02.01-1999 regarding non-condensable The staff met with Mr. LaVera and discussed his gases. comments and reached agreement. IEEE Std 622-1987 is important enough to add an item in Section C to clarify While these documents are discussed to some limited NRCs position. The added statement in Section C is as degree in section B of the proposed revision, unless there follows: Instrument sensing lines should be designed is some other RG that you can point to within this RG and maintained to ensure that the fluids or gases in the that endorses those 2 Regulatory Positions, the references lines remain within the temperature ranges necessary to to those documents should not be deleted. perform their intended functions. Should heat tracing be used, the staff considers IEEE Std. 622-1987 to be acceptable for the design and installation of these systems. The staff explained that the non-condensable gases are addressed in ANSI/ISA-67.02.01-2014, Month Year
Commenter Section of Specific Comments NRC Resolution DG-1352 therefore, there is no need to endorse the older ANSI/ISA-67.02.01-1999 and Mr. LaVera agreed.
For these reasons, the staff decided to add a position to clarify IEEE Std. 622-1987 in Section C and modified Section B which states This revision (Revision 2) of RG 1.151 clarifies the previous Regulatory Position C.3 that was in Revision 1 regarding the acceptability and use of ANSI/IEEE Std. 622-1987.
Ronald Section B In addition, the discussion about Heat Tracing in Section The staff agreed with the comment and made two LaVera B does not sufficiently address the need for heat trace to changes to the DG.
prevent the deposition of radionuclides of interest on the sampling line surfaces. The first change is to add a position to clarify IEEE Std.
622-1987 in Section C. The second change is to modify Section B which states This revision (Revision 2) of RG 1.151 clarifies the previous Regulatory Position C.3 that was in Revision 1 regarding the acceptability and use of ANSI/IEEE Std. 622-1987.
Ronald Section C RG 4.16, ANSI N13.1 should be mentioned in the The staff disagreed with the comment.
LaVera regulatory positions section. RG 4.16, ANSI N13.1 and 10 CFR 20 Subpart F Surveys and Monitoring should be During the meeting with Mr. LaVera, he agreed with the discussed in Section B. staffs position that these two documents are unrelated to the scope of the DG, which is intended as guidance for the design and installation of instrument sensing lines (including sample lines) in nuclear power plants.
For this reason, no change to the DG is made.
Ronald Section C The regulatory positions section should include The staff disagreed with the comment.
LaVera references to GDC 60 and GDC 64.
GDC 60 discusses control of release of radioactive materials to the environment and GDC 64 discusses monitoring radioactivity release. These are topics covered in RG 4.16 but are not within the scope of RG 2
Commenter Section of Specific Comments NRC Resolution DG-1352 1.151, which is intended as guidance for the design and installation of instrument sensing lines (including sample lines) in nuclear power plants. During the meeting with Mr. LaVera, he agreed with the staffs position.
For this reason, no change to the DG was made.
Ronald General RG 4.16, Monitoring and Reporting Radioactivity in The staff disagreed with the comment.
LaVera Releases of Radioactive Materials in Liquid and Gaseous Effluents from Nuclear Fuel Processing and Fabrication The staff reviewed 10 CFR 20 Subpart F, Surveys and Plants and Uranium Hexafluoride Production Plants, Monitoring, and found no direct impact to RG 1.151.
states, The NRC recognizes the guidance developed in During the meeting with Mr. LaVera, he agreed with the American National Standards Institute (ANSI)/Health staffs position.
Physics Society (HPS) N13.1-1999, Sampling and Monitoring Releases of Airborne Radioactive Substances For this reason, no change to the DG was made.
from the Stacks and Ducts of Nuclear Facilities.
ANSI N13.1 states, If the contaminants are in the form of condensible vapors or reactive gases, long transport lines and large temperature changes in the sample or the transport line shall either be avoided or measures shall be taken to minimize potential loss of sample. Heat tracing of the transport line is readily accomplished, but conditioning of the sample may be necessary, such as a deliberate temperature change and purposeful dilution with a carrier gas.
Conformance with this guidance is necessary in order for licensees to demonstrate compliance with 10 CFR 20 Subpart F Surveys and Monitoring.
Anonymous General Good The staff made no changes to the DG in regards to this comment.
Southern General Typically, ISA standards have an "S" at the beginning of The staff disagreed with the comment.
Nuclear the number to differentiate it as a standard. Thus, it is 3
Commenter Section of Specific Comments NRC Resolution DG-1352 expected that the ANSI/ISA standard would be The staff checked the standard and the standard number S67.02.01-2014 versus 67.02.01-2014. is correct.
For this reason, no change to the DG was made.
Southern Section B GDC 2, "Design Basis for Protection Against Natural The staff agreed with the comment.
Nuclear Phenomena" was not included in Revision 1 of RG 1.151.
Because the "Reason for Revision" does not address the In Section B, a statement This revision of RG 1.151 inclusion of GDC 2, is not clear from the current context (Revision 2) also includes a reference to GDC 2 as an as to why the staff chose to add it in this revision. applicable regulation because the fluids or gases in sensing lines are required to remain within the temperature ranges necessary to perform their intended functions was added.
Southern Section B In revision 1 of RG 1.151, a later version of IEEE Std. The staff disagreed with the comment.
Nuclear 279 (1971) is referenced. It is not clear why the staff chose to refer to an earlier version of IEEE Std. 279 Section B of RG 1.151 (Revision 2) quotes information (1968) instead of the later version that was previously and standards directly from the requirements specified in referenced in revision 1 of RG 1.151 . 10 CFR 50.55 a(h) which includes references to both IEEE Std 279-1968, Proposed IEEE Criteria for Nuclear Power Plant Protection Systems and IEEE Std 279-1971, Criteria for Protection Systems for Nuclear Power Generating Stations, accordingly. For this reason, no changes to the DG were made.
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