Developing Software Life Cycle Processes Used in Safety Systems of Nuclear Power Plants, 47012-47014 [2013-18681]
Download as PDF
47012
Federal Register / Vol. 78, No. 149 / Friday, August 2, 2013 / Notices
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.
sroberts on DSK5SPTVN1PROD with NOTICES
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
VerDate Mar<15>2010
18:55 Aug 01, 2013
Jkt 229001
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
PO 00000
Frm 00108
Fmt 4703
Sfmt 4703
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
NUCLEAR REGULATORY
COMMISSION
[NRC–2012–0195]
Developing Software Life Cycle
Processes Used in Safety Systems of
Nuclear Power Plants
Nuclear Regulatory
Commission.
ACTION: Revision to regulatory guide;
issuance.
AGENCY:
E:\FR\FM\02AUN1.SGM
02AUN1
Federal Register / Vol. 78, No. 149 / Friday, August 2, 2013 / Notices
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
https://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 https://www.nrc.gov/readingrm/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,
sroberts on DSK5SPTVN1PROD with NOTICES
SUMMARY:
VerDate Mar<15>2010
18:55 Aug 01, 2013
Jkt 229001
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
PO 00000
Frm 00109
Fmt 4703
Sfmt 4703
47013
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
E:\FR\FM\02AUN1.SGM
02AUN1
47014
Federal Register / Vol. 78, No. 149 / Friday, August 2, 2013 / Notices
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
NUCLEAR REGULATORY
COMMISSION
sroberts on DSK5SPTVN1PROD with NOTICES
[NRC–2012–0195]
Configuration Management Plans for
Digital Computer Software Used in
Safety Systems of Nuclear Power
Plants
Nuclear Regulatory
Commission.
ACTION: Revision to Regulatory Guide;
Issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a revised
SUMMARY:
VerDate Mar<15>2010
18:55 Aug 01, 2013
Jkt 229001
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
https://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 https://www.nrc.gov/readingrm/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,
PO 00000
Frm 00110
Fmt 4703
Sfmt 4703
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
E:\FR\FM\02AUN1.SGM
02AUN1
Agencies
[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 https://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 https://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