Final Regulatory Guide; Issuance, Availability, 3345-3346 [E6-619]

Download as PDF wwhite on PROD1PC65 with NOTICES Federal Register / Vol. 71, No. 13 / Friday, January 20, 2006 / Notices of the reactor in the event of a significant fire, (2) NRC has not quantified the full extent of the amount of Hemyc/MT fire barrier material in terms of linear and/or square footage deployed per fire protection regulation, and NRC has not determined the safety significance of this deployment for safe shutdown systems that are not currently protected by these fire barriers, and (3) the petitioners believe that the above listed nuclear power stations are operating in violation of NRC fire protection requirements and in an unanalyzed condition resulting in a degradation of defense-in-depth fire protection and safe shut down in the event of a significant fire. The petitioners requested that the NRC take the following actions: (1) Collect information through generic communications with nuclear industry and specifically with the named reactor sites to determine the extent of condition of the inoperable fire barriers; including the requirement that the licensees conduct a full inventory of the type Hemyc/MT to include the amount in linear and square footage, its specific applications, and the identification of safe shutdown systems, which are currently unprotected by the noncompliance and an assessment of the safety significance of each application; (2) The communication should require, at minimum that the abovenamed sites provide justification for operation in noncompliance with all applicable fire protection regulations; and (3) With the determination that any and/or all of the above-mentioned sites are operating in unanalyzed condition and/or that assurance of public health and safety is degraded, promptly order a suspension of the license or a power reduction of the affected reactors until such time as it can be demonstrated that the licensees are operating in conformance with all other applicable fire protection regulations. In a letter dated June 27, 2005, the NRC informed the petitioners that the issues in the petition were accepted for review under Section 2.206 of the Code of Federal Regulations (10 CFR) and had been referred to the Office of Nuclear Reactor Regulation for appropriate action. A copy of the acknowledgment letter is publicly available in the NRC’s Agencywide Documents Access and Management System (ADAMS) under Accession No. ML051740562. A copy of the petition is publicly available in ADAMS under Accession No. ML051440209. The petitioners’ representatives held a teleconference with the Petition Review VerDate Aug<31>2005 16:16 Jan 19, 2006 Jkt 208001 Board to discuss the petition on June 1, 2005. The teleconference transcript was treated as a supplement to the petition and is publicly available in ADAMS under Accession No. ML051640452. The NRC sent a copy of the proposed Director’s Decision to the petitioners for comment on October 20, 2005 (Accession No. ML052630411). The NRC staff did not receive any comments on the proposed Director’s Decision. The Director of the Office of Nuclear Reactor Regulation has determined that, with regard to Request Nos. 1 and 2, the NRC staff has granted the petitioners’ request through the generic communication process. Specifically, the NRC staff is planning to issue a Generic Letter (GL) to all licensees asking them to provide detailed information about the use of Hemyc/MT in their nuclear power plants. In response to Request No. 3, the NRC staff is planning to review all affected plants in detail and will take appropriate actions to resolve the issues with the use of Hemyc/MT material commensurate with the safety significance of the protected systems. The GL will be issued after the NRC’s internal review process to consider comments received on the proposed GL is completed. The reasons for these decisions are explained in the Director’s Decision pursuant to 10 CFR 2.206 (DD–06–01), the complete text of which is available in ADAMS, and is available for inspection at the Commission’s Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland, and from the ADAMS Public Library component on the NRC Web site, https://www.nrc.gov/ reading-rm/adams.html (the Public Electronic Reading Room). Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR reference staff at 1–800–397–4209 or 301–415–4737, or by e-mail to pdr@nrc.gov. A copy of the Director’s Decision will be filed with the Secretary of the Commission for the Commission’s review in accordance with 10 CFR 2.206 of the Commission’s regulations. As provided for by this regulation, the Director’s Decision will constitute the final action of the Commission 25 days after the date of the decision, unless the Commission, on its own motion, institutes a review of the Director’s Decision in that time. Dated at Rockville, Maryland, this 9th day of January 2006. PO 00000 Frm 00090 Fmt 4703 Sfmt 4703 3345 For the Nuclear Regulatory Commission. J.E. Dyer, Director, Office of Nuclear Reactor Regulation. [FR Doc. E6–625 Filed 1–19–06; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Final Regulatory Guide; Issuance, Availability The U.S. Nuclear Regulatory Commission (NRC) has issued a revision to an existing guide in the agency’s Regulatory Guide Series. This series has been developed to describe and make available to the public such information 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. Revision 2 of Regulatory Guide 1.152, entitled ‘‘Criteria for Use of Computers in Safety Systems of Nuclear Power Plants,’’ describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) deems acceptable for complying with the Commission’s regulations for promoting high functional reliability, design quality, and cyber-security for the use of digital computers in safety systems of nuclear power plants. In this context, the term ‘‘computer’’ identifies a system that includes computer hardware, software, firmware, and interfaces. The guidance provided in Revision 2 of Regulatory Guide 1.152 is consistent with General Design Criterion (GDC) 21, ‘‘Protection System Reliability and Testability,’’ of Appendix A, ‘‘General Design Criteria for Nuclear Power Plants,’’ to title 10, part 50, ‘‘Domestic Licensing of Production and Utilization Facilities,’’ of the Code of Federal Regulations (10 CFR part 50). Among other things, GDC 21 requires that protection systems (or safety systems) must be designed for high functional reliability, commensurate with the safety functions to be performed. In addition, Criterion III, ‘‘Design Control,’’ of Appendix B, ‘‘Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,’’ to 10 CFR part 50 requires, among other things, that quality standards must be specified, and design control measures must be provided, for verifying or checking the adequacy of design. Revision 2 of Regulatory Guide 1.152 also contains the staff’s regulatory E:\FR\FM\20JAN1.SGM 20JAN1 wwhite on PROD1PC65 with NOTICES 3346 Federal Register / Vol. 71, No. 13 / Friday, January 20, 2006 / Notices position on IEEE Std 7–4.3.2–2003, ‘‘Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,’’ which was prepared by Working Group SC 6.4, ‘‘Application of Programmable Digital Computers to Safety Systems,’’ of the Institute of Electrical and Electronics Engineers (IEEE) Nuclear Power Engineering Committee. This standard evolved from IEEE Std 7–4.3.2–1993 and reflects advances in digital technology. It also represents a continued effort by IEEE to support the specification, design, and implementation of computers in safety systems of nuclear power plants. In addition, IEEE Std 7–4.3.2–2003 specifies computer-specific requirements to supplement the criteria and requirements of IEEE Std 603–1998, ‘‘Standard Criteria for Safety Systems for Nuclear Power Generating Stations.’’ In Revision 2 of Regulatory Guide 1.152, the staff endorses IEEE Std 7– 4.3.2–2003, with certain exceptions, as an acceptable method for satisfying the NRC’s regulations with respect to (1) high functional reliability and design requirements for computers used in safety systems of nuclear power plants, and (2) independence between safety software and nonsafety software residing on the same computer. The NRC previously solicited public comments on this revised guide by publishing a Federal Register notice (69 FR 75359) concerning Draft Regulatory Guide DG–1130 on December 16, 2004. Following the closure of the public comment period on March 14, 2005, the staff considered all stakeholder comments in the course of preparing Revision 2 of Regulatory Guide 1.152. The NRC staff encourages and welcomes comments and suggestions in connection with improvements to published regulatory guides, as well as items for inclusion in regulatory guides that are currently being developed. You may submit comments by any of the following methods. Mail comments to: Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. Hand-deliver comments to: Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. on Federal workdays. Fax comments to: Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission at (301) 415–5144. VerDate Aug<31>2005 16:16 Jan 19, 2006 Jkt 208001 Requests for technical information about Revision 2 of Regulatory Guide 1.152 may be directed to NRC Senior Program Manager, Satish Aggarwal, at (301) 415–6005 or SKA@nrc.gov. Regulatory guides are available for inspection or downloading through the NRC’s public Web site in the Regulatory Guides document collection of the NRC’s Electronic Reading Room at https://www.nrc.gov/reading-rm/doccollections/. Electronic copies of Revision 2 of Regulatory Guide 1.152 are also available in the NRC’s Agencywide Documents Access and Management System (ADAMS) at http: //www.nrc.gov/reading-rm/adams.html, under Accession #ML053070150. In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR), which is located at 11555 Rockville Pike, Rockville, Maryland; the PDR’s mailing address is USNRC PDR, Washington, DC 20555–0001. The PDR can also be reached by telephone at (301) 415–4737 or (800) 397–4205, by fax at (301) 415– 3548, and by e-mail to PDR@nrc.gov. Requests for single copies of draft or final guides (which may be reproduced) or for placement on an automatic distribution list for single copies of future draft guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, Attention: Reproduction and Distribution Services Section; by e-mail to DISTRIBUTION@nrc.gov; or by fax to (301) 415–2289. Telephone requests cannot be accommodated. Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them. (5 U.S.C. 552(a)) Dated at Rockville, Maryland, this 30th day of December, 2005. For the U.S. Nuclear Regulatory Commission, James T. Wiggins, Deputy Director, Office of Nuclear Regulatory Research. [FR Doc. E6–619 Filed 1–19–06; 8:45 am] BILLING CODE 7590–01–P RAILROAD RETIREMENT BOARD Proposed Collection; Comment Request Summary: In accordance with the requirement of Section 3506(c)(2)(A) of the Paperwork Reduction Act of 1995 which provides opportunity for public comment on new or revised data collections, the Railroad Retirement Board (RRB) will publish periodic summaries of proposed data collections. PO 00000 Frm 00091 Fmt 4703 Sfmt 4703 Comments are invited on: (a) Whether the proposed information collection is necessary for the proper performance of the functions of the agency, including whether the information has practical utility; (b) the accuracy of the RRB’s estimate of the burden of the collection of the information; (c) ways to enhance the quality, utility, and clarity of the information to be collected; and (d) ways to minimize the burden related to the collection of information on respondents, including the use of automated collection techniques or other forms of information technology. Title and purpose of information collection: Survivor Questionnaire; OMB 3220–0032. Under Section 6 of the Railroad Retirement Act (RRA), benefits that may be due on the death of a railroad employee or a survivor annuitant include (1) a lump-sum death benefit (2) a residual lump-sum payment (3) accrued annuities due but unpaid at death, and (4) monthly survivor insurance payments. The requirements for determining the entitlement of possible beneficiaries to these benefits are prescribed in 20 CFR 234. When the RRB receives notification of the death of a railroad employee or survivor annuitant, an RRB field office utilizes Form RL–94–F, Survivor Questionnaire, to secure additional information from surviving relatives needed to determine if any further benefits are payable under the RRA. Completion is voluntary. One response is requested of each respondent. The RRB proposes no changes to Form RL–94–F. The completion time for the RL–94–F is estimated at between 5 to 11 minutes. The RRB estimates that approximately 8,000 responses are received annually. Additional Information or Comments: To request more information or to obtain a copy of the information collection justification, forms, and/or supporting material, please call the RRB Clearance Officer at (312) 751–3363 or send an e-mail request to Charles.Mierzwa@RRB.gov. Comments regarding the information collection should be addressed to Ronald J. Hodapp, Railroad Retirement Board, 844 North Rush Street, Chicago, Illinois 60611–2092 or send an e-mail to Ronald.Hodapp@RRB.gov. Written comments should be received within 60 days of this notice. Charles Mierzwa, Clearance Officer. [FR Doc. E6–629 Filed 1–19–06; 8:45 am] BILLING CODE 7905–01–P E:\FR\FM\20JAN1.SGM 20JAN1

Agencies

NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 71, Number 13 (Friday, January 20, 2006)]
[Notices]
[Pages 3345-3346]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-619]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION


Final Regulatory Guide; Issuance, Availability

    The U.S. Nuclear Regulatory Commission (NRC) has issued a revision 
to an existing guide in the agency's Regulatory Guide Series. This 
series has been developed to describe and make available to the public 
such information 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.
    Revision 2 of Regulatory Guide 1.152, entitled ``Criteria for Use 
of Computers in Safety Systems of Nuclear Power Plants,'' describes a 
method that the staff of the U.S. Nuclear Regulatory Commission (NRC) 
deems acceptable for complying with the Commission's regulations for 
promoting high functional reliability, design quality, and cyber-
security for the use of digital computers in safety systems of nuclear 
power plants. In this context, the term ``computer'' identifies a 
system that includes computer hardware, software, firmware, and 
interfaces.
    The guidance provided in Revision 2 of Regulatory Guide 1.152 is 
consistent with General Design Criterion (GDC) 21, ``Protection System 
Reliability and Testability,'' of Appendix A, ``General Design Criteria 
for Nuclear Power Plants,'' to title 10, part 50, ``Domestic Licensing 
of Production and Utilization Facilities,'' of the Code of Federal 
Regulations (10 CFR part 50). Among other things, GDC 21 requires that 
protection systems (or safety systems) must be designed for high 
functional reliability, commensurate with the safety functions to be 
performed. In addition, Criterion III, ``Design Control,'' of Appendix 
B, ``Quality Assurance Criteria for Nuclear Power Plants and Fuel 
Reprocessing Plants,'' to 10 CFR part 50 requires, among other things, 
that quality standards must be specified, and design control measures 
must be provided, for verifying or checking the adequacy of design.
    Revision 2 of Regulatory Guide 1.152 also contains the staff's 
regulatory

[[Page 3346]]

position on IEEE Std 7-4.3.2-2003, ``Standard Criteria for Digital 
Computers in Safety Systems of Nuclear Power Generating Stations,'' 
which was prepared by Working Group SC 6.4, ``Application of 
Programmable Digital Computers to Safety Systems,'' of the Institute of 
Electrical and Electronics Engineers (IEEE) Nuclear Power Engineering 
Committee. This standard evolved from IEEE Std 7-4.3.2-1993 and 
reflects advances in digital technology. It also represents a continued 
effort by IEEE to support the specification, design, and implementation 
of computers in safety systems of nuclear power plants. In addition, 
IEEE Std 7-4.3.2-2003 specifies computer-specific requirements to 
supplement the criteria and requirements of IEEE Std 603-1998, 
``Standard Criteria for Safety Systems for Nuclear Power Generating 
Stations.''
    In Revision 2 of Regulatory Guide 1.152, the staff endorses IEEE 
Std 7-4.3.2-2003, with certain exceptions, as an acceptable method for 
satisfying the NRC's regulations with respect to (1) high functional 
reliability and design requirements for computers used in safety 
systems of nuclear power plants, and (2) independence between safety 
software and nonsafety software residing on the same computer.
    The NRC previously solicited public comments on this revised guide 
by publishing a Federal Register notice (69 FR 75359) concerning Draft 
Regulatory Guide DG-1130 on December 16, 2004. Following the closure of 
the public comment period on March 14, 2005, the staff considered all 
stakeholder comments in the course of preparing Revision 2 of 
Regulatory Guide 1.152.
    The NRC staff encourages and welcomes comments and suggestions in 
connection with improvements to published regulatory guides, as well as 
items for inclusion in regulatory guides that are currently being 
developed. You may submit comments by any of the following methods.
    Mail comments to: Rules and Directives Branch, Office of 
Administration, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.
    Hand-deliver comments to: Rules and Directives Branch, Office of 
Administration, U.S. Nuclear Regulatory Commission, 11555 Rockville 
Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. on 
Federal workdays.
    Fax comments to: Rules and Directives Branch, Office of 
Administration, U.S. Nuclear Regulatory Commission at (301) 415-5144.
    Requests for technical information about Revision 2 of Regulatory 
Guide 1.152 may be directed to NRC Senior Program Manager, Satish 
Aggarwal, at (301) 415-6005 or SKA@nrc.gov.
    Regulatory guides are available for inspection or downloading 
through the NRC's public Web site in the Regulatory Guides document 
collection of the NRC's Electronic Reading Room at https://www.nrc.gov/
reading-rm/doc-collections/. Electronic copies of Revision 2 of 
Regulatory Guide 1.152 are also available in the NRC's Agencywide 
Documents Access and Management System (ADAMS) at http: //www.nrc.gov/
reading-rm/adams.html, under Accession ML053070150.
    In addition, regulatory guides are available for inspection at the 
NRC's Public Document Room (PDR), which is located at 11555 Rockville 
Pike, Rockville, Maryland; the PDR's mailing address is USNRC PDR, 
Washington, DC 20555-0001. The PDR can also be reached by telephone at 
(301) 415-4737 or (800) 397-4205, by fax at (301) 415-3548, and by e-
mail to PDR@nrc.gov. Requests for single copies of draft or final 
guides (which may be reproduced) or for placement on an automatic 
distribution list for single copies of future draft guides in specific 
divisions should be made in writing to the U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, Attention: Reproduction and 
Distribution Services Section; by e-mail to DISTRIBUTION@nrc.gov; or by 
fax to (301) 415-2289. Telephone requests cannot be accommodated.
    Regulatory guides are not copyrighted, and Commission approval is 
not required to reproduce them.

(5 U.S.C. 552(a))

    Dated at Rockville, Maryland, this 30th day of December, 2005.

    For the U.S. Nuclear Regulatory Commission,
James T. Wiggins,
Deputy Director, Office of Nuclear Regulatory Research.
[FR Doc. E6-619 Filed 1-19-06; 8:45 am]
BILLING CODE 7590-01-P

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