[Federal Register Volume 78, Number 149 (Friday, August 2, 2013)]
[Notices]
[Pages 47012-47014]
From the Federal Register Online via the Government Publishing 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: [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 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: 
[email protected].

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