|
|
| (9 intermediate revisions by the same user not shown) |
| Line 1: |
Line 1: |
| {{Adams | | {{Adams |
| | number = ML13051A421 | | | number = ML003740073 |
| | issue date = 06/27/2013 | | | issue date = 06/30/1975 |
| | title = Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants | | | title = Nuclear Material Control Systems for Nuclear Power Plants. Label as Withdrawn 01/15/98 |
| | author name = | | | author name = |
| | author affiliation = NRC/RES | | | author affiliation = NRC/RES |
| Line 9: |
Line 9: |
| | docket = | | | docket = |
| | license number = | | | license number = |
| | contact person = Jervey R A | | | contact person = |
| | case reference number = DG-5028
| | | document report number = RG-5.29 Rev 1 |
| | document report number = RG-5-029, Rev. 2 | |
| | package number = ML13032A392
| |
| | document type = Regulatory Guide | | | document type = Regulatory Guide |
| | page count = 5 | | | page count = 1 |
| }} | | }} |
| {{#Wiki_filter: U.S. NUCLEAR REGULATORY COMMISSION June 2013 Revision 2 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH Written suggestions regarding this guide or development of new guides may be submitted through the NRC's public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html. Electronic copies of this regulatory guide, previous versions of this guide, and other recently issued guides are available through the NRC's public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/. The regulatory guide is also available through the NRC's Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession No. ML13051A421. The regulatory analysis may be found in ADAMS under Accession No. ML13051A418 and the staff responses to the public comments on DG-5028 may be found under ADAMS Accession No. ML13051A417. REGULATORY GUIDE 5.29 (Draft was issued as DG 5028, dated May 2012) SPECIAL NUCLEAR MATERIAL CONTROL AND ACCOUNTING SYSTEMS FOR NUCLEAR POWER PLANTS | | {{#Wiki_filter:Revision I |
| | U.S. NUCLEAR REGULATORY COMMISSION June 1975 REGULATORY GUIDE |
| | OFFICE OF STANDARDS DEVELOPMENT |
| | REGULATORY GUIDE 5.29 NUCLEAR MATERIAL CONTROL SYSTEMS |
| | FOR NUCLEAR POWER PLANTS |
|
| |
|
| ==A. INTRODUCTION== | | ==A. INTRODUCTION== |
| Purpose This guide describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable to implement special nuclear material control and accounting system requirements for nuclear power plants. This guide applies to all nuclear power plants.
| | NI5 on Methods of Nuclear Material Control has developed a standard. ANSI N15.8, which provides Paragraph 70.51(c) of 10 CFR Part 70 requires each guidelines on nuclear material control systems for licensee who is authorized to possess at any one time nuclear power plants. |
|
| |
|
| Applicable Rules and Regulations Title 10, of the Code of Federal Regulations, Part 74, "Material Control and Accounting of Special Nuclear Material" (10 CFR Part 74) (Ref. 1), Subpart B, "General Reporting and Recordkeeping Requirements," establishes the material control and accounting performance requirements for special nuclear material at nuclear power plants. The regulations at 10 CFR 74.11, "Reports of loss or theft or attempted theft or unauthorized production of special nuclear material," require, in part, that nuclear power reactor licensees notify the NRC of any such events within one hour of discovery. The regulations at 10 CFR 74.13, "Material status reports," require nuclear power reactor licensees to submit material status reports for certain quantities of special nuclear material. The regulations at 10 CFR 74.15, "Nuclear material transaction reports," require nuclear power reactor licensees to complete transaction reports when transferring, receiving, or making adjustments to specified quantities of special nuclear material. The regulations at 10 CFR 74.19, "Recordkeeping," require, in part, that nuclear power reactor licensees keep records that show the receipt, inventory (including location and unique identity), acquisition, transfer, and disposal of all special nuclear material in their possession. Additionally, 10 CFR 74.19 requires, in part, that licensees establish, maintain, and follow written material control and accounting procedures, and that they conduct physical inventories of special nuclear material at intervals not to exceed once every 12 months.
| | special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow |
|
| |
|
| Purpose of Regulatory Guides The NRC issues regulatory guides to describe methods that the staff considers acceptable for use in implementing specific parts of the agency's regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to applicants. Regulatory Rev. 2 of RG 5.29, Page 2 guides are not substitutes for regulations and compliance with them is not required. Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission. This regulatory guide provides ANSI N15.8-2009 as an acceptable approach to the NRC staff for complying with the NRC's regulations regarding material control and accounting requirements in Subpart B of 10 CFR Part 74 at nuclear power plants.
| | ==C. REGULATORY POSITION== |
| | written material control and accounting procedures that are sufficient to enable.the licensee to account for The guidelines set forth in ANSI N]5.8-1974,l the special nuclear material in his possession under "Nuclear Material Control Systems for Nuclear Power license. While other paragraphs and sections of Part 70 Plants,"' are generally acceptable to the NRC staff andi provide specific requirements for nuclear material con provide an adequate basis for systems for the control trol systems for fuel cycle plants, such detailed require and accounting for special nuclear material at a nuclear ments are not included for nuclear power reactors. This power plant. |
|
| |
|
| Paperwork Reduction Act This regulatory guide contains information collection requirements covered by 10 CFR Part 74 that the Office of Management and Budget (OMB) approved under OMB control number 3150-0123. The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.
| | guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power |
| | |
| ==B. DISCUSSION==
| |
| Reason for Revision Revision 1 to Regulatory Guide 5.29, "Nuclear Material Control Systems for Nuclear Power Plants," issued June 1975, (Ref. 2) found American National Standards Institute (ANSI) N15.8-1974, "Methods of Nuclear Material Control-Material Control Systems-Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants" as an acceptable method for implementing NRC's requirements for material control and accounting of special nuclear material at nuclear power plants. However, this standard primarily addressed control and accounting of fuel assemblies and did not address fuel rods that are separated from the parent assembly. Additionally, ANSI N15.8-1974 did not provide specific guidance on control and accounting of pieces resulting from fuel damage. The NRC, therefore, withdrew Regulatory Guide 5.29 in January 1998 (63 FR 2426). In the absence of endorsed guidance, licensees relied on site-specific procedures and processes to implement material control and accounting requirements, and licensee programs and procedures were reviewed by the NRC on a case-by-case basis.
| |
| | |
| Subsequently, ANSI revised its standards for special nuclear material control and accounting and published ANSI N15.8-2009, "Methods of Nuclear Material Control-Material Control Systems-Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants" (Ref. 3). ANSI N15.8-2009 provides guidance on the control and accounting of 1) fuel rods that are separated from their parent assemblies; and 2) pieces of irradiated material that are separated as a result of fuel damage.
| |
| | |
| Revision 2 is also consistent with the recommendations in U.S. Government Accountability Office 05-339, "NRC Needs To Do More To Ensure That Power Plants Are Effectively Controlling Spent Nuclear Fuel" (Ref 4). Background Control and accounting for special nuclear material at a nuclear power plant are considerably less complex than at other facilities, such as fuel cycle facilities, because the material is usually maintained in the form of readily identifiable fuel assemblies that can be managed on a per-item basis. However, problems in control and accounting can arise when fuel rods become separated from the parent assembly. Maintaining proper control is necessary to ensure that licensed material is properly accounted for in a manner that provides continuity of control throughout the total fuel cycle.
| |
| | |
| Rev. 2 of RG 5.29, Page 3 The material control and accounting process is designed to use control and monitoring measures to prevent or detect loss when it occurs or soon thereafter. Additionally, statistical and accounting measures are used to maintain knowledge of the quantities of special nuclear material present in each area of a facility. Physical inventories and material balances are used to verify the presence of licensed material or to detect the loss of such material after it occurs, in particular, through theft by an insider. Harmonization with International Standards The International Atomic Energy Agency (IAEA) has established a series of safety guides and standards constituting a high level of safety for protecting people and the environment. IAEA safety guides present international good practices and increasingly reflects best practices to help users striving to achieve high levels of safety. Pertinent to this regulatory guide, "IAEA Nuclear Security Series No. 13, Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities," issued January 2011, (Ref. 5) et. al. , address considerations necessary for a nuclear material security program. While the NRC has an interest in facilitating the harmonization of standards used domestically and internationally and because security requirements typically follow requirements identified in the CFR, the NRC does not specifically accept the IAEA document for use, and is only acknowledging that it may be valuable as a reference for general programmatic information. The NRC could consider the use of the international standard in a licensing action following adequate justification and technical revie
| |
| | |
| ====w. ====
| |
| Documents Discussed in the Staff Regulatory Guidance This regulatory guide endorses the use of a voluntary consensus standard developed by an external organization. This standard may contain references to other codes or standards ("secondary references"). If a secondary reference has itself been incorporated by reference into NRC regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation. If the secondary reference has been accepted for use in a regulatory guide as an acceptable approach for meeting an NRC requirement, then the standard constitutes a method acceptable to the NRC staff for meeting that regulatory requirement as described in the specific regulatory guide. If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in a regulatory guide, then the secondary reference is neither a legally-binding requirement nor a "generic" NRC approval as an acceptable approach for meeting an NRC requirement. However, licensees and applicants may consider and use the information in the secondary reference, if appropriately justified and consistent with current regulatory practice, consistent with applicable NRC requirements such as 10 CFR 50.59. C. STAFF REGULATORY GUIDANCE The staff considers conformance with the provisions of ANSI N15.8-2009 an acceptable approach to meet the material control and accounting requirements in Subpart B of 10 CFR Part 74 at nuclear power plant
| |
| | |
| ====s. ====
| |
| Rev. 2 of RG 5.29, Page 4
| |
|
| |
|
| ==D. IMPLEMENTATION== | | ==D. IMPLEMENTATION== |
| This section discusses how applicants, licensees,1 and the NRC staff may use this regulatory guide. The materials control and accounting activities addressed in this regulatory guide are not within the scope of matters subject to the requirements of the Backfit Rule (10 CFR 50.109) or any issue finality provisions in 10 CFR Part 52. Use by Applicants and Licensees Applicants and licensees may voluntarily2 use the guidance in this document to demonstrate compliance with the underlying NRC regulations. Methods or solutions that differ from those described or referenced in this regulatory guide may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative demonstrates compliance with the appropriate NRC regulations. Licensees may use the information in this regulatory guide for actions which do not require NRC review and approval. Licensees may use the information in this regulatory guide or applicable parts to resolve regulatory or inspection issues. Use by NRC Staff The staff may discuss with licensees various actions consistent with staff positions in this regulatory guide, as one acceptable means of meeting the underlying NRC regulatory requirement. Such discussions would not ordinarily be considered backfitting even if prior versions of this regulatory guide are part of the licensing basis of the facility. However, unless this regulatory guide is part of the licensing basis for a facility, the staff may not represent to the licensee that the licensee's failure to comply with the positions in this regulatory guide constitutes a violation. If an existing licensee voluntarily seeks a license amendment or change and (1) the NRC staff's consideration of the request involves a regulatory issue directly relevant to this new or revised regulatory guide, and (2) the specific subject matter of this regulatory guide is an essential consideration in the staff's determination of the acceptability of the licensee's request, then the staff may request that the licensee either follow the guidance in this regulatory guide or provide an equivalent alternative process that demonstrates compliance with the underlying NRC regulatory requirements.
| | reactors. |
|
| |
|
| This regulatory guide addresses compliance with the NRC's current material control and accounting regulations in 10 CFR Part 74. The NRC considers these requirements to be information collection and reporting, and therefore are not within the scope of matters covered by the Backfit Rule or the issue finality provisions of 10 CFR Part 52.
| | The purpose of this section is to provide information |
|
| |
|
| If a licensee believes that the NRC is either using this regulatory guide or requesting or requiring the licensee to implement the methods or processes in this regulatory guide in a manner inconsistent with the discussion in this Implementation section, then the licensee may file a backfit appeal with the NRC in accordance with the guidance in NUREG-1409, "Backfitting Guidelines," and NRC Management Directive 8.4, "Management of Facility-specific Backfitting and Information Collection." 1 In this section, "licensees" refers to licensees of nuclear power plants under 10 CFR Parts 50 and 52; and the term "applicants," refers to applicants for licenses and permits for (or relating to) nuclear power plants under 10 CFR Parts 50 and 52, and applicants for standard design approvals and standard design certifications under 10 CFR Part 52. 2 In this section, "voluntary" and "voluntarily" mean that the licensee is seeking the action of its own accord, without the force of a legally binding requirement or an NRC representation of further licensing or enforcement action.
| | ==B. DISCUSSION== |
| | to licensees regarding the NRC staffs plans for utilizing this regulatory guide. |
|
| |
|
| Rev. 2 of RG 5.29, Page 5 REFERENCES 1. 10 CFR Part 74, "Material Control and Accounting of Special Nuclear Material," U.S. Nuclear Regulatory Commission, Washington, DC. 3
| | Control and accounting for special nuclear material at This guide reflects current regulatory practice. |
| 2. Regulatory Guide 5.29, "Nuclear Material Control Systems for Nuclear Power Plants," Revision 1, issued June 1975. U.S. Nuclear Regulatory Commission, Washington, DC.
| |
|
| |
|
| 3. ANSI N15.8-2009, "Methods of Nuclear Material Control-Material Control Systems-Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants," American National Standards Institute, New York, NY, February 18, 2009.4
| | a nuclear power reactor is considerably less complex Therefore, except in those cases in which the licensee than at other fuel cycle facilities because the material is proposes an altefnative method for complying with in the form of identifiable fuel assemblies that can be specified portions of the Commission's regulations, the controlled on an item basis. Nevertheless, control is method described herein will be used in the evaluation necessary to ensure that 'the material is properly of a licensee's performance in connection with nuclear accounted for and to provide continuity of control for material control systems for nuclear power plants after the total fuel cycle. Subcommittee INMM-l on Material this guide is issued. |
| 4. U.S. Government Accountability Office 05-339, "NRC Needs To Do More To Ensure That Power Plants Are Effectively Controlling Spent Nuclear Fuel."5 5. NUREG 1409, "Backfitting Guidelines," U.S. Nuclear Regulatory Commission, Washington, DC. 6. Management Directive 8.4, "Management of Facility-specific Backfitting and Information Collection," U.S. Nuclear Regulatory Commission, Washington, DC.
| |
|
| |
|
| l3 Publicly available NRC published documents are available electronically through the NRC Library on the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/. The documents can also be viewed online or printed for a fee in the NRC's Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the mailing address is USNRC PDR, Washington, DC 20555; telephone 301-415-4737 or (800) 397-4209; fax (301) 415-3548; and e-mail pdr.resource@nrc.gov. 4 Copies of American National Standards Institute (ANSI) standards may be purchased from ANSI, 25 West 43rd St, 4th floor, New York, NY 10036; telephone (212) 642-4900 and fax (212) 398-0023. Purchase information is available at the ANSI web-based store at http://webstore.ansi.org/. 5 Copies of this report are available electronically through the U.S. Government Printing Office web site at http://www.gpo.gov/fdsys.
| | Control Systems of the Nuclear Standards Committee Copies may be obtained from the American National Standards |
| | "*Linesindicate substanlivc changes from previous issue. Institute. Inc., 1430 Broadway. New York, New York. 10018. |
|
| |
|
| }} | | 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 Gu-deý are issued to describe and make available to the public Service Section methods acceptable to the NRC stalf of implementing specific parns of the Commission s regulations, to delineate techniques used by the staff in evalu The guides are issued in the following ten broad divisions atinq specilic problems or postulated accidents. or to provide guidance to appli cants Regulatory Guides are not substitutes for regulations. and compliance 1. PowerReactors 6 Products with them is not required Methods and solutions different from those set out in 2 Research and Test Reactors 7 Transportation the guides will be acceptable it they provide a basis for the findings requisite to 3 Fuels and Materials Facilities & Occupational Health the issuance or continuance of a permit or license by the Commission 4. Environmental and Siting 9 Antitrust Review Comments and suggestions for improvements in these guides are encouraged 5 Materials and Plant Protection 10 General at all timet, and guides will be revised, as appropriate, to accommodate com ments and to reflect new information or experience However. comments on Copies of published guides may be obtained by written request indicating the this guide, if received within about two months after its issuance, will be par divisions desired to the U.S Nuclear Regulatory Commission. Washington. O.C |
| | hicularly useful in evaluating the need for an early revision 2055. Attention Director. Office of Standards Development}} |
|
| |
|
| {{RG-Nav}} | | {{RG-Nav}} |
|
|---|
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
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.
2024-04-30
[Table view]Some use of "" in your query was not closed by a matching "". |
Revision I
U.S. NUCLEAR REGULATORY COMMISSION June 1975 REGULATORY GUIDE
OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE 5.29 NUCLEAR MATERIAL CONTROL SYSTEMS
FOR NUCLEAR POWER PLANTS
A. INTRODUCTION
NI5 on Methods of Nuclear Material Control has developed a standard. ANSI N15.8, which provides Paragraph 70.51(c) of 10 CFR Part 70 requires each guidelines on nuclear material control systems for licensee who is authorized to possess at any one time nuclear power plants.
special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow
C. REGULATORY POSITION
written material control and accounting procedures that are sufficient to enable.the licensee to account for The guidelines set forth in ANSI N]5.8-1974,l the special nuclear material in his possession under "Nuclear Material Control Systems for Nuclear Power license. While other paragraphs and sections of Part 70 Plants,"' are generally acceptable to the NRC staff andi provide specific requirements for nuclear material con provide an adequate basis for systems for the control trol systems for fuel cycle plants, such detailed require and accounting for special nuclear material at a nuclear ments are not included for nuclear power reactors. This power plant.
guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power
D. IMPLEMENTATION
reactors.
The purpose of this section is to provide information
B. DISCUSSION
to licensees regarding the NRC staffs plans for utilizing this regulatory guide.
Control and accounting for special nuclear material at This guide reflects current regulatory practice.
a nuclear power reactor is considerably less complex Therefore, except in those cases in which the licensee than at other fuel cycle facilities because the material is proposes an altefnative method for complying with in the form of identifiable fuel assemblies that can be specified portions of the Commission's regulations, the controlled on an item basis. Nevertheless, control is method described herein will be used in the evaluation necessary to ensure that 'the material is properly of a licensee's performance in connection with nuclear accounted for and to provide continuity of control for material control systems for nuclear power plants after the total fuel cycle. Subcommittee INMM-l on Material this guide is issued.
Control Systems of the Nuclear Standards Committee Copies may be obtained from the American National Standards
"*Linesindicate substanlivc changes from previous issue. Institute. Inc., 1430 Broadway. New York, New York. 10018.
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 Gu-deý are issued to describe and make available to the public Service Section methods acceptable to the NRC stalf of implementing specific parns of the Commission s regulations, to delineate techniques used by the staff in evalu The guides are issued in the following ten broad divisions atinq specilic problems or postulated accidents. or to provide guidance to appli cants Regulatory Guides are not substitutes for regulations. and compliance 1. PowerReactors 6 Products with them is not required Methods and solutions different from those set out in 2 Research and Test Reactors 7 Transportation the guides will be acceptable it they provide a basis for the findings requisite to 3 Fuels and Materials Facilities & Occupational Health the issuance or continuance of a permit or license by the Commission 4. Environmental and Siting 9 Antitrust Review Comments and suggestions for improvements in these guides are encouraged 5 Materials and Plant Protection 10 General at all timet, and guides will be revised, as appropriate, to accommodate com ments and to reflect new information or experience However. comments on Copies of published guides may be obtained by written request indicating the this guide, if received within about two months after its issuance, will be par divisions desired to the U.S Nuclear Regulatory Commission. Washington. O.C
hicularly useful in evaluating the need for an early revision 2055. Attention Director. Office of Standards Development