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Category:Regulatory Guide
MONTHYEARML24176A2292024-09-11011 September 2024
DG-4032 (RG 4.2 Rev 4) Redline Strikeout to Support Proposed Rule
Regulatory Guide 4.22024-08-0101 August 2024
Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2
ML23333A4462024-01-24024 January 2024
Basis for Withdrawal of Regulatory Guides
ML23226A0362023-11-0909 November 2023
Rulemaking - Final Rule - Regulatory Guide - 1.242, Revision 0 - Emergency Preparedness for Small Modular Reactors and Other New Technologies
ML22272A0452022-09-29029 September 2022
10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DG-1414 Alternative Evaluation for Risk Insights (Aeri) Methodology
ML22272A0422022-09-29029 September 2022
10/18-19/2022 ACRS Public Meeting - Predecisional - Documents to Support Part 53 - DG-1413 Technology-Inclusive Identification of Licensing Events for Commercial Nuclear Plants
ML22041A2832022-02-0909 February 2022
Document to Support the ACRS Subcommittee Meeting Redline RG 4.7, Rev 4, General Site Suitability Criteria for Nuclear Power Stations
ML22042A1042022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Redline RG 1.149, Rev 5, Nuclear Power Plant Simulation Facilities for Use in Operator Training, License Examinations, and Applicant Experience Requirements
ML22041A3352022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Redline RG 5.84, Rev 1, Fitness-For -Duty Programs at New Reactor Construction Sites
ML22041A3102022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Redline RG 5.66, Rev 3, Access Authorization Program for Nuclear Power Plants
ML22041A2712022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Redline RG 1.206, Rev 2, Applications for Nuclear Power Plants
ML22041A2342022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Redline RG 1.200, Rev 4, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
ML22041A2292022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Redline RG 1.187, Rev 4, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments
ML22041A2252022-02-0909 February 2022
Document to Support ACRS Subcommittee Meeting Redline RG 1.174, Rev 4, an Approach for Using Probablistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis
ML21208A1202021-12-14014 December 2021
Draft Regulatory Guide DG-4032,(RG 4.2 Rev 4), Preparation of Environmental Reports for Nuclear Power Stations
ML21274A1522021-12-14014 December 2021
Rulemaking: Proposed Rule: Redline Strikeout Regulatory Guide 4.2 (DG-4032) Preparation of Environmental Reports for Nuclear Power Stations (Publishing to Support Proposed Rule: Advanced Nuclear Reactor Generic Environmental Impact Statemen
ML20205L5632020-08-31031 August 2020
DG 1373 RG 1.240 Regulatory Analysis - Fresh and Spent Fuel Pool Criticality Analyses
ML20034F2542020-07-0101 July 2020
Reg Guide 7.4 New Reg Analysis-Leakage Tests on Package for Shipment of Radioactive Material
ML19059A4032019-06-27027 June 2019
Draft Regulatory Basis GTCC Rulemaking
ML19157A1112019-06-0606 June 2019
Preliminary Draft Proposed Regulatory Guide 8.39, Release of Patients Administered Radioactive Materials, Revision 1 (Phase 1) for ACMUI Review with Note
ML19141A0902019-05-30030 May 2019
Regulatory Guide Number 4.14, Revision 1
ML19141A0892019-05-30030 May 2019
Regulatory Guide Number 3.61
ML19141A0922019-05-30030 May 2019
Regulatory Guide Number 3.48
ML19141A0932019-05-30030 May 2019
Regulatory Guide Number 3.56, Revision 0
ML19141A0912019-05-30030 May 2019
Regulatory Guide Number 8.30
ML19008A0952019-01-11011 January 2019
01/23/2019 - Predecisional - Advisory Committee on Reactor Safeguards Sub-Committee Public Meeting Regulatory Guide 2.7 for Non-Power Production or Utilization Facility License Renewal (Rin 3150-AI96, NRC-2011-0087)
ML17145A3402017-05-0101 May 2017
Draft Regulatory Guide DG-5062 for Fuel Cycle Cyber Security Documents for June 8, 2017, ACRS Full Committee Meeting
ML16225A4442017-03-31031 March 2017
Rev. 0, Basis for Withdrawal Questions
ML16293A1122016-10-19019 October 2016
Redline Strikeout Version Comparing September 15, 2016 Draft Final Part 61 to Current Part 61 Rule Language
ML16273A1592016-10-0606 October 2016
Draft Regulatory Guide DG-5062: Cyber Security Programs for Nuclear Fuel Cycle Facilities (Proposed New Reg Guide)
ML16221A0842016-08-10010 August 2016
Draft Regulatory Guide DG-5062 - Cyber Security Programs for Nuclear Fuel Cycle Facilities
ML14310A3392015-09-0303 September 2015
Draft Regulatory Guide DG-5049, Independent Assessment of Nuclear Material Control and Accounting Systems
ML15198A0212015-08-27027 August 2015
Draft Regulatory Basis - Cyber Security at Fuel Cycle Facilities
ML13219B2042014-02-0606 February 2014
Draft Regulatory Guide (DG) - 3044, Corrective Action Programs for Fuel Cycle Facilities
ML12087A0352013-11-18018 November 2013
Draft Regulatory Guide DG-3042, (Proposed Revision 2 of Regulatory Guide 3.50, Dated September 1989), Standard Format and Content for a License Application for an Independent Spent Fuel Storage Installation or a Monitored Retrievable Storag
ML23292A0812013-09-30030 September 2013
Rev 0 Periodic Review
ML1033705652011-04-30030 April 2011
Staff'S Responses to Public Comment on DG-3039, Standard Format and Content for Emergency Plans for Fuel Cycle and Material Facilities.
ML0506102582005-03-25025 March 2005
Sher Bahadur Memo Request to Waive CRGR Review of Proposed Revision to Regulatory Guide 3.71 Nuclear Criticality Safety Standards for Fuels and Materials Facilities
ML0506103222005-03-25025 March 2005
John T. Larkin Memo Request to Waive Acrs/Acnw Review of Proposed Revision to Regulatory Guide 3.71, Nuclear Criticality Safety Standards for Fuels and Materials Facilities
ML0313506112003-06-11011 June 2003
SECY-03-0118Attachment 3-SITE Evaluations and Design Earthquake Ground Motion for Dry Cask Independent Spent Fuel Storage and Monitored Retrievable Storage Installations
ML0321801641990-11-13013 November 1990
Draft Regulatory Guide, Format and Content for the License Application for the High-level Waste Repository.
ML0319200771990-07-13013 July 1990
Topical Guidelines for the Licensing Support System
2024-09-11
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Text
Regulatory Guide Number: 5.36, Revision 0
Title:
Recommended Practice for Dealing with Outlying Observations Office/Division/Branch: NMSS/FCSE/MCAB Technical Lead: Glenn Tuttle
SUBJECT:
Basis for Withdrawal (1) What regulation(s) did the Regulatory Guide support?
RG 5.36 was published in June 1974 to provide guidance to fuel cycle facilities on meeting the requirements for statistical control procedures in Title 10 of the Code of Federal Regulations (10 CFR) 70.22(b), Contents of applications. This requirement, regarding submittal of the licensees description of its material control and accounting (MC&A) procedures, did not specifically require the methodology that the guidance in RG 5.36 addressed and no longer exists in 10 CFR 70.22(b).
The MC&A requirements have all been moved to 10 CFR Part 74 and no specific requirements exist for performing outlier testing.
(2) What was the purpose of the Regulatory Guide?
The staff developed RG 5.36 to provide guidance for statistical procedures related to statistical analyses of outlying observations in samples, and for testing their statistical significance to ensure appropriate accounting of nuclear material.
(3) How was the Regulatory Guide used?
The intent of RG 5.36 was to assist licensees in establishing written MC&A procedures as required by 10 CFR 70.22(b), specifically written procedures for statistical analyses of accounting data. RG 5.36 was initially published in June 1974 and endorsed American Society for Testing and Materials (ASTM) Standard E178-74, Recommended Practice for Dealing with Outlying Observations, with qualifications. E178-74 provided a common method used in testing for outlying observations. The standard has been revised several times since 1974 and is now designated E178-16. However, the NRC does not know if any licensee used this particular RG or the ASTM standard it endorses, since there was no requirement to evaluate MC&A data for outlying observations.
(4) Why is the Regulatory Guide no longer needed?
The requirements in 10 CFR Part 74 supersede the staff regulatory positions in RG 5.36, so that explicit guidance for written statistical control procedures is no longer needed. There are no requirements for testing for outlying observations in the MC&A regulations in 10 CFR Part 74.
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(5) What guidance is available once the Regulatory Guide is withdrawn?
The NRC has developed a reference manual of general statistical methodology, NUREG/CR-4604 (PNL-5849), Statistical Methods for Nuclear Material Management, which is a comprehensive guidance document on statistical methods that licensees may use in evaluating MC&A data. Section 10.4, Tests for Outliers, of NUREG/CR-4604 provides guidance on testing for, and dealing with, outlying observations in a data set.
(6) Is the Regulatory Guide referenced in other documents and what are the ripple effects on these documents if it is withdrawn?
RG 5.36 is not referenced in any MC&A inspection procedures or inspection manual chapters.
There is no current fuel cycle licensee or applicant that references RG 5.36 in its facility fundamental nuclear material control (FNMC) plan, which is the licensing basis for the licensees MC&A program. There are also no references to RG 5.36 in the NUREGs that provide licensees and applicants with a standard format and content for their FNMC plans.
RG 5.36 is referenced in two regulatory guides: RG 5.53, Qualification, Calibration, and Error Estimation Methods for Nondestructive Assay, and RG 5.38, Nondestructive Assay of High-Enrichment Uranium Fuel Plates by Gamma Ray Spectrometry. When RG 5.53 and RG 5.38 are revised, the reference to RG 5.36 will be deleted, and both will refer directly to ASTM standard E178-16.
RG 5.36 is referenced in NUREG/CR-0829, A Measurement Control Program for Nuclear Material Accounting. NUREG/CR-0829 was published in June 1980 and has not been revised since then, so many references are outdated. If NUREG/CR-0829 is revised in the future the reference to RG 5.36 will be deleted.
RG 5.36 is referenced in a document by Westinghouse, Westinghouse Generic Setpoint Methodology, Westinghouse Non-Proprietary Class 3, WCAP-17504-NP Revision 0, February 2012 (ADAMS Accession No. ML12058A450). This document also references the 1980 version of ASTM standard E178. The reference to RG 5.36 is inaccurate since RG 5.36 was written for MC&A applications at fuel cycle facilities, not reactor setpoint methodologies.
(7) What is the basis for believing that no guidance similar to that in the Regulatory Guide will ever be needed?
The regulations in 10 CFR Part 74 establish the appropriate requirements for control of, and accounting for, special nuclear material. There are no regulations in Part 74 that specifically require testing for outlying observations.
(8) Will generic guidance still be needed?
The regulations in 10 CFR Part 74 establish the appropriate requirements for control of, and accounting for, special nuclear material. A specific regulatory guide for testing for outlying observations will not be needed since outlier testing is not required by NRC regulations.
However, for guidance on statistical methods related to MC&A in general, licensees may use NUREG/CR-4604 if needed.
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(9) What is the rationale for withdrawing this Regulatory Guide instead of revising it?
The regulations in 10 CFR Part 74 establish the appropriate requirements for control of, and accounting for special nuclear material, and the regulations do not require testing for outlying observations. However, licensees choosing to test for outlying observations could refer to NUREG/CR-4604 for comprehensive information on statistical methods used to analyze MC&A data.
(10) Do other agencies rely upon the Regulatory Guide, e.g., the Agreement States, National Aeronautical and Space Administration, Department of Energy?
The staff is not aware of any other agency that uses or relies on the guidance in RG 5.36.
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