2 August 2013
Nuclear Power Plant Safety Software
Four regulatory guides.
[Federal Register Volume 78, Number 149 (Friday, August 2, 2013)]
[Notices]
[Pages 47015-47016]
From the Federal Register Online via the Government Printing Office
[www.gpo.gov]
[FR Doc No: 2013-18678]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2012-0195]
Software Requirement Specifications for Digital Computer Software
Used in Safety Systems of Nuclear Power Plants
AGENCY: Nuclear Regulatory Commission.
ACTION: Revision to regulatory guide; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a
revised regulatory guide (RG), revision 1 of RG 1.172, ``Software
Requirement Specifications for Digital Computer Software used in Safety
Systems of Nuclear Power Plants.'' This RG endorses the Institute of
Electrical and Electronic Engineers (IEEE) Standard (Std.) 830-1998,
``IEEE Recommended Practice for Software Requirements Specifications,''
issued in 1998 and reaffirmed in 2009 with the exceptions and
clarifications stated in Section C, ``Staff Regulatory Guidance'' of RG
1.172. IEEE Std. 830-1998 describes methods that the NRC staff
considers acceptable to demonstrate compliance with NRC regulations for
achieving high functional reliability and design quality in software
used in safety systems in nuclear power plants.
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: Carol.Gallagher@nrc.gov.
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 pdr.resource@nrc.gov. 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 1 of RG 1.172 is available in ADAMS under
Accession No. ML13007A173. The regulatory analysis may be found in
ADAMS under Accession No. ML13075A007.
NRC's PDR: You may examine for free or 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: 301-251-74955; email:
Mark.Orr@NRC.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing a revision to an existing RG 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,
[[Page 47016]]
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 1 of RG 1.172 was issued with a temporary identification
as Draft Regulatory Guide, DG-1209 on August 22, 2012 (77 FR 50726) for
a 60-day public comment period. The public comment period closed on
November 22, 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 ML13007A160.
Revision 1 of RG 1.172 endorses IEEE Std. 830-1998, ``IEEE
Recommended Practice for Software Requirements Specifications,'' issued
in 1998 and reaffirmed in 2009 with the clarifications and exceptions
as stated in Section C, ``Staff Regulatory Position'' of the RG. IEEE
Std. 830-1998 describes methods that the NRC staff considers acceptable
for use in complying with the NRC regulations for achieving high
functional reliability and design quality in software used in safety
systems. In particular, the methods are consistent with the previously
cited GDC and the criteria for quality assurance programs in Appendix B
to Title 10, of the Code of Federal Regulations, Part 50, ``Domestic
Licensing of Production and Utilization Facilities'' (10 CFR Part 50)
as they apply to the development of software requirement
specifications. The criteria of Appendix A and Appendix B to 10 CFR
part 50 applies to systems and related quality standards and quality
assurance processes as well as the software elements of those systems.
This RG is one of six RG revisions 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 final 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
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
CRF 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.
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. 2013-18678 Filed 8-1-13; 8:45 am]
BILLING CODE 7590-01-P
________________________________________________________________________
[Federal Register Volume 78, Number 149 (Friday, August 2, 2013)]
[Notices]
[Pages 47011-47012]
From the Federal Register Online via the Government Printing Office
[www.gpo.gov]
[FR Doc No: 2013-18682]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2012-0195]
Software Unit Testing for Digital Computer Software Used in
Safety Systems of Nuclear Power Plants
AGENCY: Nuclear Regulatory Commission.
ACTION: Revision to Regulatory Guide; Issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a
revised regulatory guide (RG), revision 1 of RG 1.171, ``Software Unit
Testing for Digital Computer Software Used in Safety Systems of Nuclear
Power Plants.'' This RG endorses American National Standards Institute/
Institute of Electrical and Electronics Engineers (ANSI/IEEE) Standard
(Std.) 1008-1987, ``IEEE Standard for Software Unit Testing'' with the
clarifications and exceptions stated in Section C, ``Staff Regulatory
Position'' in the RG. ANSI/IEEE Std. 1008-1987, which was reaffirmed in
2002, describes a method acceptable to the NRC staff for complying with
NRC regulations for promoting high functional reliability and design
quality in the software used in safety systems of nuclear power plants.
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: Carol.Gallagher@nrc.gov.
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 pdr.resource@nrc.gov. 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 1 of RG 1.171 is available in ADAMS under
[[Page 47012]]
Accession No. ML13004A375. The regulatory analysis may be found in
ADAMS under Accession No. ML103120752.
NRC's PDR: You may examine for free or 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:
Mark.Orr@NRC.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing a revision to an existing RG 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 1 of RG 1.171 was issued with a temporary identification
as Draft Regulatory Guide, DG-1208 on August 22, 2012 (77 FR 50722) 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 ML13004A370.
Revision 1 of RG 1.171 endorses ANSI/IEEE Std. 1008-1987, ``IEEE
Standard for Software Unit Testing'' with the exceptions stated in
Section C, ``Staff Regulatory Position'' in the RG. ANSI/IEEE Std.
1008-1987, which was reaffirmed in 2002, describes a method acceptable
to the NRC staff for complying with NRC regulations for promoting high
functional reliability and design quality in the software used in
safety systems. In particular, the method is consistent with the
previously cited GDC in Appendix A to part 50 of Title 10, of the Code
of Federal Regulations (10 CFR), ``Domestic Licensing of Production and
Utilization Facilities'' and the criteria for quality assurance
programs in Appendix B to 10 CFR part 50 as they apply to software unit
testing. The criteria in Appendices A and B of 10 CFR part 50 apply to
systems and related quality assurance processes, and the requirements
extend to the software elements if those systems include software.
This RG is one of six RG revisions 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 guides
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 final 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
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.
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. 2013-18682 Filed 8-1-13; 8:45 am]
BILLING CODE 7590-01-P
________________________________________________________________________
[Federal Register Volume 78, Number 149 (Friday, August 2, 2013)]
[Notices]
[Pages 47012-47014]
From the Federal Register Online via the Government Printing Office
[www.gpo.gov]
[FR Doc No: 2013-18681]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2012-0195]
Developing Software Life Cycle Processes Used in Safety Systems
of Nuclear Power Plants
AGENCY: Nuclear Regulatory Commission.
ACTION: Revision to regulatory guide; issuance.
-----------------------------------------------------------------------
[[Page 47013]]
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a
revised regulatory guide (RG), revision 1 of RG 1.173, ``Developing
Software Life Cycle Processes for Digital Computer Software used in
Safety Systems of Nuclear Power Plants.'' This RG endorses the
Institute of Electrical and Electronic Engineers (IEEE) Standard (Std.)
1074-2006, ``IEEE Standard for Developing a Software Project Life Cycle
Process,'' issued 2006, with the clarifications and exceptions as
stated in Section C, ``Staff Regulatory Position'' of the RG, as a
method acceptable to the NRC staff for complying with NRC regulations
to promote high functional reliability and design quality in software
used in safety systems in nuclear power plants.
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: Carol.Gallagher@nrc.gov.
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 pdr.resource@nrc.gov. 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 1 of RG 1.173, is available in ADAMS under
Accession No. ML13009A190. The regulatory analysis may be found in
ADAMS under Accession No. ML103120737.
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:
Mark.Orr@NRC.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing a revision to an existing RG 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 1 of RG 1.173 was issued with a temporary identification
as Draft Regulatory Guide DG-1210 on August 22, 2012 (77 FR 50724) for
a 60-day public comment period. The public comment period closed on
November 22, 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 ML13009A055.
Revision 1 of RG 1.173 endorses the guidance in IEEE Std. 1074-
2006, ``IEEE Standard for Developing a Software Project Life Cycle
Process,'' issued 2006, with the clarification and exceptions stated in
Section C, Staff Regulatory Position'' of the RG. The NRC staff has
determined that IEEE Std. 1074-2006 provides an acceptable method for
complying with NRC regulations to promote high functional reliability
and design quality in software used in safety systems. In particular,
the method is consistent with the previously cited GDC in Appendix A to
Title 10, of the Code of Federal Regulations, Part 50, ``Domestic
Licensing of Production and Utilization Facilities'' (10 CFR Part 50)
and the criteria for quality assurance programs in Appendix B to 10 CFR
Part 50 as they apply to software development processes. The criteria
of Appendices A and B apply to systems and related quality assurance
processes, and the requirements also extend to the software elements if
those systems include software.
Revision 1 of RG 1.173 supersedes Revision 0 of RG 1.173 and
represents NRC staff 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 tits 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 RG revisions 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. and
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
[[Page 47014]]
Rev. 1 of RG 1.173 is in ADAMS at Accession No. ML13008A338.
III. Backfitting and Issue Finality
Issuance of this final 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 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 CRF 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.
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. 2013-18681 Filed 8-1-13; 8:45 am]
BILLING CODE 7590-01-P
________________________________________________________________________
[Federal Register Volume 78, Number 149 (Friday, August 2, 2013)]
[Notices]
[Pages 47014-47015]
From the Federal Register Online via the Government Printing Office
[www.gpo.gov]
[FR Doc No: 2013-18684]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2012-0195]
Configuration Management Plans for Digital Computer Software Used
in Safety Systems of Nuclear Power Plants
AGENCY: Nuclear Regulatory Commission.
ACTION: Revision to Regulatory Guide; Issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a
revised regulatory guide (RG), revision 1 of RG 1.169, ``Configuration
Management Plans for Digital Computer Software Used in Safety Systems
of Nuclear Power Plants.'' This RG endorses, with clarifications and
exceptions as stated in Section C, ``Staff Regulatory Guidance'' of the
RG, the Institute of Electrical and Electronic Engineers (IEEE)
Standard 828-2005, ``IEEE Standard for Software Configuration
Management Plans,'' issued in 2005. This IEEE standard describes
methods acceptable to the NRC staff for demonstrating compliance with
NRC regulations for configuration management 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: Carol.Gallagher@nrc.gov.
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 pdr.resource@nrc.gov. 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 1 of RG 1.169 is available in ADAMS under
Accession No. ML12355A642. The regulatory analysis may be found in
ADAMS under Accession No. ML103200047.
NRC's PDR: You may examine for free or 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:
Mark.Orr@NRC.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is issuing a revision to an existing RG 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 NRC
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 1 of RG 1.169 was issued with a temporary identification
as Draft Regulatory Guide, DG-1206 on August 22, 2012 (77 FR 50727) for
a 60-day public comment period. The public comment period closed on
November 22, 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 ML12355A529.
Revision 1 of RG 1.169 endorses IEEE Std. 828-2005, ``IEEE Standard
for Software Configuration Management Plans,'' issued in 2005 with the
exceptions and clarifications stated in Section C, ``Staff Regulatory
Guidance of the RG.'' IEEE Std. 828-2005 describes methods acceptable
to the NRC staff for use in complying with NRC regulations for quality
standards that promote high functional reliability and design quality
in software used in safety systems. In particular, the methods are
consistent with GDC 1 in Appendix A to part 50 of Title 10 of the Code
of Federal Regulations (10 CFR) and the criteria for quality assurance
programs in Appendix B to 10 CFR part 50 as they apply to the
maintenance and control of appropriate records of software development
activities. The criteria of Appendices A and B of 10 CFR part 50 apply
to systems and related quality assurance processes, and the
requirements also extend to software elements if those systems include
software.
This RG is one of six RG revisions 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
[[Page 47015]]
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
regulatory guide 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. 2013-18684 Filed 8-1-13; 8:45 am]
BILLING CODE 7590-01-P
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