[Federal Register Volume 78, Number 151 (Tuesday, August 6, 2013)]
[Notices]
[Pages 47804-47805]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2013-18728]
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NUCLEAR REGULATORY COMMISSION
[NRC-2012-0195]
Verification, Validation, Reviews, and Audits for Digital
Computer Software Used in Safety Systems of Nuclear Power Plants
AGENCY: Nuclear Regulatory Commission.
ACTION: Revision to regulatory guide; issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a
revised regulatory guide (RG), revision 2 of RG 1.168, ``Verification,
Validation, Reviews, and Audits for Digital Computer Software Used in
Safety Systems of Nuclear Power Plants.'' This guide endorses, with
clarifications and exceptions, the Institute of Electrical and
Electronic Engineers (IEEE) Standard 1012-2004, ``IEEE Standard for
Software Verification and Validation,'' and IEEE Std. 1028-2008, ``IEEE
Standard for Software Reviews and Audits.'' These two IEEE standards
describe methods acceptable to the NRC staff for demonstrating
compliance with the NRC's regulations for design verification and
control of software used in the safety systems of a nuclear power
plant.
ADDRESSES: Please refer to Docket ID NRC-2012-0195 when contacting the
NRC about the availability of information regarding this document. You
may access information related to this document, which the NRC
possesses and is publicly available, using the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2012-0195. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: [email protected].
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at http://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to [email protected]. The ADAMS accession number
for each document referenced in this notice (if that document is
available in ADAMS) is provided the first time that a document is
referenced. Revision 2 of RG 1.168 is available in ADAMS under
Accession No. ML13073A210. The regulatory analysis may be found in
ADAMS under Accession No. ML103160461.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
FOR FURTHER INFORMATION CONTACT: Mark Orr, Division of Engineering,
Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, telephone: 301-251-7495; email:
[email protected].
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing a revision to an existing guide in the NRC's
``Regulatory Guide'' series. This series was developed to describe and
make available to the public information such as methods that are
acceptable to the NRC staff for implementing specific parts of the
NRC's regulations, techniques that the staff uses in evaluating
specific problems or postulated accidents, and data that the staff
needs in its review of applications for permits and licenses.
II. Further Information
Revision 2 of RG 1.168 was issued with a temporary identification
as Draft Regulatory Guide, DG-1267 on August 22, 2012 (77 FR 50723) for
a 60-day public comment period. The public comment period closed on
November 23, 2012. Multiple public comments were received and addressed
by the NRC staff. These comments and the NRC staff responses are
available in ADAMS under Accession number ML13073A208.
Revision 2 of RG 1.168 endorses, with clarifications and
exceptions, the consensus practices for complying with NRC regulations
promoting the development of, and compliance with, a software lifecycle
program for software used in safety systems in nuclear power plants
described in the Institute of Electrical and Electronic Engineers
(IEEE) Standard 1012-2004, ``IEEE
[[Page 47805]]
Standard for Software Verification and Validation,'' and IEEE Std.
1028-2008, ``IEEE Standard for Software Reviews and Audits.'' These two
IEEE standards describe methods acceptable to the NRC staff for
demonstrating compliance with the NRC's regulations for verification,
validation, and design control of software used in safety systems of a
nuclear power plant. In particular, the methods are consistent with
part 50 of Title 10 of the Code of Federal Regulations (10 CFR),
``Domestic Licensing of Production and Utilization Facilities,''
Appendix A, ``General Design Criteria for Nuclear Power Plants,''
General Design Criterion (GDC) 1, ``Quality Standards and Records,''
which requires, in part, that a quality assurance program be
established and implemented to provide adequate assurance that systems
and components important to safety will satisfactorily perform their
safety functions.
Revision 2 of RG 1.168 supersedes Revision 1 of RG 1.168 and
represents the NRC staff's guidance for future users and guidance.
Earlier versions of this RG, however, continue to be acceptable for
those licensees whose licensing basis includes earlier versions of this
RG, absent a licensee-initiated change to its licensing basis.
Additional information on the staff's use of this revised RG with
respect to both current and future users and applications is set forth
in the ``Implementation'' section of the revised RG.
This RG is one of six revised RGs addressing computer software
development and use in safety related systems of nuclear power plants.
These RGs were developed by the Office of Nuclear Regulatory Research,
Division of Engineering (RES/DE) with the assistance of multiple
individuals in the Office of New Reactors, Division of Engineering
(NRO/DE); Office Nuclear Reactor Regulation, Division of Engineering
(NRR/DE); and the Office of Nuclear Security and Incident Response,
Division of Security Policy (NSIR/DSP). The six interrelated RGs are:
1. Revision 2 of RG 1.168, ``Verification, Validation, Reviews, and
Audits for Digital Computer Software used in Safety Systems of Nuclear
Power Plants,'' issued for public comment as DG-1267. The package for
Rev. 2 of RG 1.168 is in ADAMS at Accession No. ML12236A132.
2. Revision 1 of RG 1.169, ``Configuration Management Plans for
Digital Computer Software used in Safety Systems of Nuclear Power
Plants,'' issued for public comment as DG-1206. The package for Rev. 1
of RG 1.169 is in ADAMS at Accession No. ML12354A524.
3. Revision 1 of RG 1.170, ``Test Documentation for Digital
Computer Software used in Safety Systems of Nuclear Power Plants,''
issued for public comment as DG1207. The package for Rev. 1 of RG 1.170
is in ADAMS at Accession No. ML12354A531.
4. Revision 1 of RG 1.171, ``Software Unit Testing for Digital
Computer Software Used in Safety Systems of Nuclear Power Plants,''
issued for public comment as DG1208. The package for Rev. 1 of RG 1.171
is in ADAMS at Accession No. ML12354A534.
5. Revision 1 of RG 1.172, ``Software Requirements Specifications
for Digital Computer Software used in Safety Systems of Nuclear Power
Plants,'' issued for public comment as DG-1209. The package for Rev. 1
of RG 1.172 is in ADAMS at Accession No. ML12354A538.
6. Revision 1 of RG 1.173, ``Developing Software Life Cycle
Processes for Digital Computer Software used in Safety Systems of
Nuclear Power Plants,'' issued for public comment as DG-1210. The
package for Rev. 1 of RG 1.173 is in ADAMS at Accession No.
ML13008A338.
III. Backfitting and Issue Finality
Issuance of this revised RG does not constitute backfitting as
defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise
inconsistent with the issue finality provisions in 10 CFR part 52. As
discussed in the ``Implementation'' section of this RG, the NRC has no
current intention to impose this RG on holders of current operating
licenses, early site permits or combined licenses, unless this final RG
is part of the licensing basis for the facility. The NRC may apply this
revised RG to applications for operating licenses, early site permits
and combined licenses docketed by the NRC as of the date of issuance of
the final RG, as well as to future applications for operating licenses,
early site permits and combined licenses submitted after the issuance
of the RG. Such action does not constitute backfitting as defined in 10
CFR 50.109(a)(1) and is not otherwise inconsistent with the applicable
issue finality provision in 10 CFR part 52, inasmuch as such applicants
or potential applicants are not within the scope of entities protected
by the Backfit Rule or the relevant issue finality provisions in part
52.
IV. Congressional Review Act
This RG is a rule as designated in the Congressional Review Act (5
U.S.C. 801-808). However, the Office of Management and Budget (OMB) has
not found it to be a major rule as designated in the Congressional
Review Act.
Dated at Rockville, Maryland, this 19th day of July, 2013.
For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guide Development Branch, Division of Engineering,
Office of Nuclear Regulatory Research.
[FR Doc. 2013-18728 Filed 8-5-13; 8:45 am]
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