Standards & Guidelines

American Nuclear Society - ANS
        (All are © by ANS.  They maintain copies of all historical ANS standards for purchase.)

ANS 3.2 ANSI N18.7-1976	February 19, 1976 (Superseded)	Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants, Revision of N18.7-1972 (Contact ANS for pricing on historical standards) * Endorsed by Regulatory Guide 1.33 * Addresses all aspects of operational QA controls including maintenance, modifications, temporary modifications, nonconforming items, Design Outputs.
ANSI/ANS 3.2-1982	August 9, 1982 (Superseded)	Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants Contains a comparison of 10CFR50 Appendix B and NQA-1-1979 versus ANSI/ANS 3.2-1982 (Contact ANS for pricing on historical standards)
ANSI/ANS 3.2-1994	1994	Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants ($82.00)

American Society of Mechanical Engineers - ASME
       (All are © by ASME.  Contact ASME for purchase of these standards.)

ANSI/N45.2.9-1974	1974	Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants * Endorsed by Regulatory Guide 1.88
ANSI/N45.2.10-1973	1973	Quality Assurance Terms and Definitions
ANSI/N45.2.11-1974	1974	Quality Assurance Requirements for the Design of Nuclear Power Plants * Endorsed by Regulatory Guide 1.64 * Outlines the design process * Defines Design, Design Inputs, Design Outputs * Lists examples of Design Inputs
ANSI/N45.2.13-1976	1976	Quality Assurance Requirements for Control of Procurement of Items and Services for a Nuclear Power Plant
ANSI/ASME NQA-1c-1982		Addenda to ANSI/ASME NQA-1-1979, Quality Assurance Program Requirements for Nuclear Power Plants
ANSI/ASME NQA-1-1986	1986	Quality Assurance Program Requirements for Nuclear Facilities
ASME NQA-1-1989	August 30, 1989	Quality Assurance Program Requirements for Nuclear Facilities (NQA-1) Terms used in this Standard that require unique definition are included in Supplement S-1, Terms and Definitions ($83.00, ISBN 0791820386,  ASME Order # A10589)
ASME NQA-1a-1989	March 31, 1990	Addenda to ASME NQA-1-1989 Edition, Quality Assurance Program Requirements for Nuclear Facilities
ASME NQA-1b-1989	April 15, 1991	Addenda to ASME NQA-1-1989 Edition, Quality Assurance Program Requirements for Nuclear Facilities
ASME NQA-1c-1992	September 30, 1992	Addenda to ASME NQA-1-1989 Edition, Quality Assurance Program Requirements for Nuclear Facilities
ANSI/NQA-1	July 25, 1994	Quality Assurance Program Requirements for Nuclear Facilities (NQA-1) ($125.00, ISBN 079182229X,  ASME Order # A10594)
ASME NQA Technical Report 1993	September 15, 1993	Comparison of ASME NQA-1 and ISO 9001 There are many areas where NQA-1 contains additional requirements. Hence, a quality program that meets the requirements of ISO 9001 may not meet the requirements of NQA-1. ($30.00, ISBN 079182232X, ASME Order # A13793)

Code of Federal Regulations
       10CFR50 - (Title 10 to Code of Federal Regulations, Part 50 - Domestic Licensing of Production and Utilization Facilities)

10 CFR 50.2		Definitions (Includes the following term: "Design bases") NEI 97-04 notes that this is a subset of the engineering design bases.
10 CFR 50.34		Contents of applications; technical information (requires a PSAR to specify the principal design criteria (PDC) and to specify the relation of the design bases to the PDC (10 CFR 50.34(a)(3)).)
10 CFR 50.54(f)		A provision that requires licensees to submit responses under oath if requested by the NRC.   In CMBG, refers to NRC request in 1996 for most utilities to describe their CM programs under oath.
10 CFR 50.59		Changes, tests and experiments * describes evaluation process for making changes to nuclear plants
10 CFR 50.65		Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants
10 CFR 50.71		Maintenance of Records making reports
10 CFR 50, Appendix A		General Design Criteria for Nuclear Power Plants (Some plants pre-date the GDCs) * 64 criteria in six categories - cover everything from QA records to Containment design basis
10 CFR 50, Appendix B		Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants. (Criteria VI - Document Control, Criteria XVII - Quality Assurance Records)

Title 10 Code of Federal Regulations - continued

10 CFR 54	May, 1995	Requirements for Renewal of Operating Licenses for Nuclear Power Plants (Section 54.3   includes a regulatory definition of "Current Licensing Basis" which includes the plant-specific design-basis information defined in 10 CFR 50.2...)
10 CFR 61	December, 1982	Licensing Requirements for Land Disposal of Radioactive Waste (10 CFR 61.12, Specific technical information, includes discussion of 'design features', 'principal design criteria', and 'design basis natural events')
10 CFR 71	September, 1995	Packaging and Transportation of Radioactive Material
10 CFR 72	August, 1988	Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste ('Design Bases' is defined in subpart A)
10 CFR 100		Reactor Site Criteria

Department of Energy - DOE (refer to the osti web site)

DOE-STD-1073-93 (Parts 1 and 2)	November 1993	Standard Guide for Operational Configuration Management Program, Including the Adjunct Programs of Design Reconstitution and Aging Management (found on the web as two PDF files) (Also Ref DOE Order 5700.6C)

Electric Power Research Institute - EPRI

(the "TERI" document)		Guidelines for Commercial Grade Dedication
TR-106828	July 1996	Use of Electronic Media Authorization and Electronic Document Storage in the Nuclear Power Industry
TR-103586-R1	October 1998	Guidelines for Optimizing the Engineering Change Process for Nuclear Power Plants * Provides decision criteria to select level of administrative and technical effort for engineering changes (update to R-0 issued March 1994)
NP-6295	May 1989	Guidelines for Quality Records in Electronic Media for Nuclear Facilities (NCIG-10)
NCIG-05	May 1988	Guidelines for Piping System Reconciliation, Rev 1

Institute of Nuclear Power Operations - INPO

INPO 84-010	March 1984	Nuclear Utility Action Committee (NUTAC) Report Discusses the Vendor Equipment Technical Information Program (VETIP)
INPO 85-013 (Good Practice TS-402)	May 1985	Plant Modification Control Program
INPO 85-016 (Good Practice TS-412)	February 1988	Temporary Modification Control
Good Practice TS-415	Preliminary March 1986	Technical Review of Design Changes
INPO 87-006	July 1987	Report on Configuration Management in the Nuclear Utility Industry
INPO 87-009 (DE-102)	August 1987	Control of Vendor Manuals, Good Practice
INPO 88-022 (TS-403)		Vendor Manual Specification and Procurement
INPO 90-015	August 1990	Performance Objectives and Criteria for Operating and Near-Term Operating License Plants (Section ES.3 Plant Modifications Section OA.8 Configuration Management)
INPO 97-002	September 1997	Performance Objectives and Criteria for Operating Nuclear Electric Generating Stations (A working reference for INPO evaluators.  Section PS entitled "Plant Status and Configuration Control" provides performance objectives and criteria for INPO evaluators and for member utilities to use in self-evaluations)
AP-905	November 1996	Configuration Change Process Description (See INPO AP-929)
AP-906 (Prelim)	May 1996	Design Change Process Description (See INPO AP-929)
AP-922		Design Basis Change Process Description (See INPO AP-929)
AP-929	May 1998	Configuration Control Process Description features include: * "bulls-eye" diagram showing relationship of Design Bases, Design Requirements and Operational Configuration * nested flowcharts showing work flow process for Configuration Changes, Design Changes and Design Basis Changes * relationship between design bases and licensing requirements - Fig A-1 (compare with definitions in 10 CFR 50 Appendix B and NEI 97-004) * outlines graded approach to maintain configuration information in four levels of documents

National Academy for Nuclear Training

ACAD 91-017	December 1994	Guidelines for Training and Qualification of Engineering Support Personnel (Replaced by ACAD 98-04)
ACAD 98-04

Nuclear Information and Records Management Association - NIRMA

NYA-1995	protected)	NIRMA Recommendations for Voluntary Utility EIE (Electronic Information Exchange)With NRC (Task Force White Paper, Version 3.0)
PP 02-1994	(protected)	Configuration Management * Defines CM * Outlines classical principles * Flow chart on change control * Describes three methods for Design Basis Documents
PP 03-1992	(protected)	Implementing CM Enhancement in a Nuclear Facility * How to establish and implement a CM program * Lists functional areas of a nuclear plant * Good definitions appendix with references to regulatory standards * Figures show simplified process flows
PP 04-1994	(protected)	Configuration Management Information Systems
TG 06-1984		Preparation of Technical Manuals
TG 11-2001	(protected)	Authentication of Records and Media
TG 13-1986	(protected)	Records Turnover
TG 14-1992	(protected)	Support of Design Basis Information Needs
TG 15-2001	(protected)	Management of Electronic Records
TG 16-1998	(protected)	Software Configuration Management and Quality Assurance
TG 17-1993	(protected)	Management of Nuclear Training Records
TG 18-1994	(protected)	Guideline for Implementing Vendor Information Programs
TG 18-1999	(protected)	Guideline for Implementing Vendor Information Programs (Exhibit 1 contains a cross reference of Industry Guidance)
TG 19-1996	(protected)	Configuration Management of Nuclear Facilities * proposed ANSI standard on configuration management * provides definitions and functional criteria for configuration management * Includes graphic showing CM objective that design requirements, physical configuration and facility configuration information must conform
TG 20-1996	(protected)	Drawing Management Program Principals and Processes
TG 21-1998	(protected)	Electronic Records Protection and Restoration
TG 22-draft	(protected)	Identifying Quality Assurance Records

Nuclear Energy Institute - NEI

NEI 97-04	September 1997	Design Bases Program Guidelines * Discusses genesis of term "design bases" as defined in the regulations (10CFR50.2) * Clarifies report ability requirements associated with design basis information * Provides additional examples to assist licensees in identifying design basis information (NEI 97-04 is an update to NUMARC 90-12 "Design Basis Program Guidelines" dated October 1990)
NEI 96-07		Guidelines for 50.59 Evaluations
NEI Report	October 1998	A Standard Nuclear Performance Model * A model for evaluating performance measures and costs against nuclear power plant processes.  Configuration Control is one of the processes addressed.
NEI 98-03 (Rev 1)	June 1999	Guidelines for Updating Final Safety Analysis Reports

Nuclear Management and Resources Council, Inc. - NUMARC

NUMARC 90-12	October 1990	Design Basis Program Guidelines (Superseded by NEI 97-04)

Nuclear Utility Software Management Group - NUSMG

NUSMG1		Guidance Document for Electronic Document Management Programs

U.S. Nuclear Regulatory Commission - US NRC

NRC Policy Statement	8/10/92	Availability and Adequacy of Design Bases Information at Nuclear Power Plants
NUREG/CR-5147	June 1988	Fundamental Attributes of a Practical Configuration Management Program for Nuclear Plant Design Control
NUREG-1397	February 1991	Assessment of Design Control Practices and Design Reconstitution Programs in the Nuclear Power Industry
NUREG-1412	July 1990	Foundation for the Adequacy of the Licensing Bases. A Supplement to the Statement of Considerations for the Rule on Nuclear Power Plant License Renewal (10 CFR Part 54).
NUREG-1536	January 1997	Standard Review Plan for Dry Cask Storage Systems * Includes a definition of "Design Basis" that refers to ANSI 57.9. * Section 2, "Principal Design Criteria" includes discussion of "Design Bases" and "Design Criteria" as they relate to 10 CFR Part 72.
GL 83-28	July 8, 1983	Required Actions Based on Generic Implications of Salem ATWS Events (Vendor Interface for Safety Related Components) Ref NUREG-0977 & NUREG-1000 * Imposed new requirements on equipment classification and vendor interface, among others Item 2 requires programs for assuring that all components required for safety related functions are properly identified. It also addresses establishment and maintenance of a program to ensure that vendor information for safety related components is complete.
GL 88-18	October 20, 1988	Plant Record Storage on Optical Disks * Outlines appropriate quality controls for storing QA records
GL 90-03, GL 90-03s1	March 20, 1990	Relaxation of staff position in generic letter 83-28, Item 2.2 Part 2 "Vendor Interface for Safety-Related Components" * Acknowledges INPO initiatives on Nuclear Plant Reliability Data System (NPRDS) and Significant Event Evaluation and Information Network (SEE-IN), both managed by INPO.
GL 99-XX	(Proposed)	Guidance on the Storage, Preservation, and Safekeeping of Quality Assurance Records in Electronic Media * Updates GL 88-18 * Endorses NIRMA Technical Guides: TG15, TG11, TG16 & TG21
Reg Guide 1.33, Rev 2	February 1978	Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants (Ref ANSI/ANS 3.2 (1988))
Reg Guide 1.64, Rev 2	June 1976	Quality Assurance Program Requirements for the Design of Nuclear Power Plants (withdrawn -- See 56 FR 36175, 7/31/1991)
Reg Guide 1.74, Rev 0	February 1974	Quality Assurance Terms and Definitions (withdrawn -- See 54 FR 38919, 9/21/1989)
Reg Guide 1.88 Rev 2	October 1976	Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants (Ref ANSI N45.2.9 (1979)) (withdrawn)
Reg Guide 1.169	September 1997	Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

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Related Documents

U.S. Nuclear Regulatory Commission - US NRC

IN 98-34	August 28, 1998	Configuration Control Errors
IN 98-22	June 17,1998	Deficiencies Identified During NRC Design Inspections

Papers & Miscellaneous Publications

• Impact of the Nuclear Industry Configuration Management Benchmarking Group, M.D. Stout, Pennsylvania Power & Light Company
• Guidelines for the Establishment of Design Bases Documentation Programs, Region V Engineering Managers Forum, May 19, 1989

Other CM Web Sites

• Configuration Management (CM) Resource Guide,  Created, published and edited by Steve Easterbrook, Institute of Configuration Management

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We would like to acknowledge the contribution of the following individuals to the preparation of this list:

• Richard A Harris, Duke Energy

• Samuel B Melton, Carolina Power & Light

• Lloyd R Hancock, LRH Consulting

This page is continually being updated.  If you would like to suggest additions you can send them to our webmaster.

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