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I&C > Regulations and Guidance
Regulations and Guidance
This page lists regulations and guidance for digital instrumentation and
controls (I&C) systems.
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Interim Staff Guidance (ISG)
In January 2007, the NRC formed a digital instrumentation and controls (I&C) steering committee to provide management focus on the NRC regulatory activities in progress across several offices, to interface with the industry on key issues, and to facilitate consistent approaches to resolving technical and regulatory challenges. The steering committee has formed the following six task working groups (TWGs) that focus on key areas of concern:
- Cyber Security
- Diversity and Defense-in-Depth
- Risk-Informed Digital I&C
- Highly-Integrated Control Room - Communications
- Highly-Integrated Control Room - Human Factors
- Licensing Process Issues
The TWGs consist of various staff members of NRR, NRO, RES, NSIR, and NMSS. Each TWG is responsible for developing a specific project plan to address the key area of concern. Essentially the plans are to identify and resolve technical issues that will result in more efficient licensing of digital I&C systems for new reactor applications and for retrofits at operating reactors/facilities. The Digital I&C Project Plan defines the problem statements, identifies deliverables, and establishes milestones to resolve the issues. The specific short-term objective of this project plan is to identify digital I&C technical and regulatory issues for which Interim Staff Guidance (ISG) can be developed in time to support the review of the anticipated licensing actions. On August 6, 2007, the NRC issued the Process for Development of Interim Staff Guidance (ISG) in Support of Reviews of Digital I&C Applications. For issue specific ISGs, please see our Interim Staff Guidance Associated with Digital Instrumentation & Controls for more information.
10 CFR Part 50
SECY Papers
Document Number |
Description |
SECY-91-292 |
Digital Computer Systems for Advanced Light Water Reactors, September 26, 1991 |
SECY-93-087 |
Policy, Technical, and Licensing Issues Pertaining to Evolutionary
and Advanced Light-Water Reactor (ALWR) Designs, (Item II Q),
April 2, 1993 |
SRM to
SECY-93-087 |
Policy, Technical, and Licensing Issues Pertaining to Evolutionary
and Advanced Light-Water Reactor (ALWR) Designs, (Item II Q) |
SECY-01-0155 |
NRC Research Plan for Digital Instrumentation and Control |
SECY-08-0033 |
Approaches for an Integrated Digital Instrumentation and Control and Human-Machine Interface Test Facility in the United States |
SECY-08-0033 Enclosure 1 |
Answers to Nine Questions from the Staff Requirements Memorandum for COMPBL-07-0001 |
SECY-08-0033 Enclosure 2 |
The Hub and Spoke Model |
SRM-COMPBL-07-0001 |
Development of a U.S. Digital Instrumentation and Control and Human-Machine Interface Test Facility |
Regulatory Guides
Document Number |
Description |
RG 1.97,
Rev. 4 |
Criteria For Accident Monitoring Instrumentation For Nuclear
Power Plants, June 2006 |
RG 1.152,
Rev. 2 |
Criteria for Digital Computers in Safety Systems of Nuclear Power Plants,
January
2006 |
RG 1.153,
Rev. 1 |
Criteria for Safety Systems, June 1996 |
RG 1.168,
Rev. 1 |
Verification, Validation, Reviews, and Audits for Digital Computer
Software
Used in Safety Systems of Nuclear Power Plants,” February 2004 |
RG 1.169 |
Configuration Management Plans for Digital Computer Software Used in
Safety Systems of Nuclear Power Plants, September 1997 |
RG 1.170 |
Software Test Documentation for Digital Computer Software Used
in Safety Systems of Nuclear Power Plants, September 1997 |
RG 1.171 |
Software Unit Testing for Digital Computer Software Used in
Safety Systems of Nuclear Power Plants, September 1997 |
RG 1.172 |
Software Requirements Specifications for Digital Computer Software
Used in Safety Systems of Nuclear Power Plants, September 1997 |
RG 1.173 |
Developing Software Life Cycle Processes for Digital Computer Software
Used in Safety Systems of Nuclear Power Plants, September 1997 |
RG 1.180,
Rev. 1 |
Guidelines for Evaluating Electromagnetic and Radio-Frequency
Interference in Safety-Related Instrumentation and Control Systems, October
2003 |
RG 1.206 |
Combined License Applications for Nuclear Power Plants (Draft Issued as DG-1145) |
RG 1.209 |
Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants, March 2007 |
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear
Power Plants (NUREG-0800)
Document Number |
Description |
NUREG-0800, Chapter 7 |
Instrumentation and controls
The Standard Review Plan (SRP) Chapter 7 guidance that addresses digital
I&C topics is as follows:
- Section 7.0 and Appendix 7.0-A describe the overall review
process for digital systems.
- Appendix 7.1-A addresses rule changes
(10 CFR Part 52, “Early Site
Permits; Standard Design Certifications; and Combined Licenses for Nuclear
Power Plants,” and revisions to 10 CFR Part 50, “Domestic Licensing
of Production and Utilization Facilities”) and new regulatory guides.
- Appendix
7.1-C provides guidance with respect to review according to Institute of
Electrical and Electronics Engineers (IEEE) Std. 603-1991
(referenced in 10 CFR 50.55a(h)).
- Appendix 7.1-D provides guidance for evaluation
of conformance to IEEE Std. 7-4.3.2 as endorsed by Revision 2 of
Regulatory Guide 1.152, “Criteria
for Digital Computers in Safety Systems of Nuclear Power Plants.”
- Sections
7.2 through 7.9 focus on systems that include references to digital
system guidance in Section 7.1.
- Appendix 7-A includes the following
Branch Technical Positions (BTP) that address digital system issues:
- BTP-14, “Guidance
on Software Reviews for Digital I&C”
- BTP-16, “Guidance
on the Level of Detail Required for Design Certification
Applications under 10 CFR Part 52”
- BTP-17, “Guidance
on Self-Test and Surveillance Testing”
- BTP-18, “Guidance
on Use of Programmable Logic Controllers”
- BTP-19, “Guidance
on Evaluation of Defense-in-Depth and Diversity (D3) of Digital
I&C”
- BTP-21, “Guidance on Digital Computer
Real-Time Performance”
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Safety
Evaluation
Date |
Description |
09/28/2004 |
Final Safety Evaluation for Topical Report WCAP-16096-NP-A, Revision
1, “Software Program Manual for Common Q Systems” |
02/24/2003 |
Acceptance of the Changes to Topical Report CENPD-396-P, Revision
01, “Common Qualified Platform,” and Closeout of Category
2 Open Items |
12/11/2001 |
Review of Triconex Corporation Topical Reports 7286-545, “Qualification
Summary Report,” and 7286-546, Revision 1, “Amendment 1
to Qualification Summary Report” |
06/22/2001 |
Safety Evaluation for the Closeout of Several of the Common
Qualified Platform Category 1 Open Items Related to Reports CENPD-396-P,
Revision 1, and CE-CES-195, Revision 1 |
08/11/2000 |
Acceptance for Referencing of Topical Report CENPD-396-P,
Revision 01, “Common Qualified Platform,” and Revision
01, Appendices 1, 2, 3, and 4 |
05/05/2000 |
Siemens letter, Topical Report EMF-2110 [NP] Revision 1,
Teleperm XS: A Digital Protection System |
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