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Category:Regulatory Guide
MONTHYEARML23263A9972024-02-0202 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
ML23286A2682024-02-0202 February 2024
Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23)
ML23286A2822024-02-0202 February 2024
Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23
ML23286A2512024-02-0202 February 2024
Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23
ML23286A2862024-02-0202 February 2024
Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -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
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
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
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
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
ML21006A3372021-04-0101 April 2021
Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities
ML21083A2892021-02-28028 February 2021
Draft for Acrs Review
ML21048A4482021-02-17017 February 2021
Rev. 2
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)
ML20120A6312021-01-31031 January 2021
Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367)
ML21011A2312021-01-31031 January 2021
Rev 4 (Draft for ACRS Fc Review on 2-3-21)
ML21012A1972021-01-12012 January 2021
a Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0
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
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
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
ML20282A2982020-12-0404 December 2020
DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
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
ML20210M0472020-12-0101 December 2020
Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping
ML20231A8562020-11-30030 November 2020
Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants
ML20231A8352020-11-30030 November 2020
Draft Regulatory Guide DG-1359, Fire Protection for 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.
ML19203A0892019-07-31031 July 2019
Assessment of the Continued Adequacy of Revision 2 of Regulatory Guide 1.99 - Technical Letter Report
2024-02-02
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5 U.S. NUCLEAR REGULATORY COMMISSION October 1978
.5. 0
REGULATORY GUIDE
OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE 6.8 IDENTIFICATION PLAQUE FOR IRRETRIEVABLE WELL-LOGGING SOURCES*
A. INTRODUCTION
1. Plaque Information. All of the following infor mation should be engraved on the face of the identifi The Commission has published proposed amend cation plaque. The engraving procedure should re ments to 10 CFR Part 30, "Rules of General move sufficient material to ensure that the depth of Applicability to Domestic Licensing of Byproduct engraving will be sufficient to produce characters that Material," and to 10 CFR Part 70, "Domestic Li have long-lasting visual discernibility.
censing of Special Nuclear Material,'" concerning the implementation of certain requirements in cases of a. The words, "CAUTION RA]DIOACTIVE
irretrievable well-logging sources. One of these re MATERIAL."
quirements would call for the mounting of a perma b. The radiation sy rriblp n required) as nent identification plaque at the surface of a well that described in 10 C5V § T03 'Caution signs, contains an irretrievable well-logging source. This labels, signals and S. V,
regulatory guide describes methods that would be ac c. The well-logging ceptable to the NRC staff for the characteristics and source(s)," alf tilda'rf occurrence.
the mounting of this permanent identification plaque assuming the proposed regulation is promulgated as d. r d' he well-owner and the city and an effective rule by the Commission after considera stateý,dh, thig'ti in office is located.
tion of public comments. eSJhe well name and the well number (if appli
- Cabf Th)le sealed source(s) (radionuclide and quan
B. DISCUSSION
tity of activity).
Sealed source logging techniques use garnmw sources and neutron sources in quantity levels up to g. The source depth and the plug-back depth.
several curies per source for substrata anag, , in'oil, h. An appropriate warning, depending on the gas, and mineral exploration. When the¢i W'an fh" specific circumstances of each incident, such as:
trievable well-logging source, a perman t iden-fica tion plaque must be mounted at the s the well. The mounting of this plaque is one ]*ect of (1) Do not drill below plug-back depth, continuing control of the byproduct material, and the (2) Do not enlarge casing, or identification plaque is uitehoed to be a permanent (3) Notify the appropriate State agency before indication of a sealed sd0irce d6*nwwell. reentry (if required by regulation in the State where the well is located).
C. REGULATORY 'POSITION
2. Plaque Material. The plaque should be con Acceptabletplaque information, plaque material, structed of long-lasting material such as stainless and methods of plaqui*e mounting for active and inac steel, brass, bronze, or monel. The size of the plaque tive wells that contain an irretrievable well-logging should be convenient for use on active or inactive source are as follows: wells: e.g., a seven-inch (177.8 mm) square would be usable in both cases. The thickness of the metal
- An "irretrievable well-logging source" means any sealed plaque should be at least l/8 inch (3.2 mm). Letter source containing licensed material that is pulled off or not con size of the words, "CAUTION RADIOACTIVE
nected to the wireline downwell and for which all reasonable MATERIAL," should be approximately double the effort at recovery, as determined by the Commission, has been 1 expended. letter size of the rest of the information; e.g., /4 inch USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Regulatory Guides are issued to describe and make available to the public Service Branch.
methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evalu- The guides are issued in the following ten broad divisions:
ating specific problems or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and corn- 1. Power Reactors
6. Products
2. Research and Test Reactors 7. Transportation pliance with them is not required. Methods and solutions different from those
3. Fuels and Materials Facilities 8. Occupational Health set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the 4. Environmental and Siting 9. Antitrust and Financial Review Commission. 5. Materials and Plant Protection 10. General Comments and suggestions for improvements in these guides are encouraged Requests for single copies of issued guides (which may be reproducedl or for at all times, and guides will be revised, as appropriate, to accommodate corn- placement on an automatic distribution list for single copies of future guides ments and to reflect new information or experience. However, comments on in specific divisions should be made in writing to the U.S. Nuclear Regulatory this guide, if received within about two months after its issuance, will be Commission, Washington, D.C. 20555, Attention: Director, Division of particularly useful in evaluating the need for an early revision. Technical Information and Document Control.
(6.4 mm) and /s inch (3.2 mm) letter sizes would be readily observable if the well were reentered at a fu acceptable. ture date.
3. Plaque Mountin
g.
D. IMPLEMENTATION
a. For active wells, the plaque should be mounted in a readily observable location by welding The guidance contained herein may be used by or bolting it to the well-head structure. The plaque licensees or by applicants for a license as a reference information should be readable by personnel in the for information normally supplied in support of a immediate area. license application.
b. For inactive wells, the plaque should be Other equally effective methods for providing for mounted by welding or bolting it to the top of the and mounting of an identification plaque for irre casing cap so that the plaque information would be trievable well-logging sources may also be used.
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