Regulatory Guide: Issuance, Availability, 6795-6796 [E6-1775]

Download as PDF cprice-sewell on PROD1PC66 with NOTICES Federal Register / Vol. 71, No. 27 / Thursday, February 9, 2006 / Notices analysis methods, while Regulatory Guide 1.203 provides practices and principles for the benefit of method developers. Chapter 15 of the SRP recommends using approved evaluation models or codes for the analysis of most identified events. The SRP also suggests that evaluation model reviews should be initiated whenever an approved model does not exist for a specified plant event. If the applicant or licensee proposes to use an unapproved model, an evaluation model review should be initiated. The NRC previously solicited public comment on this guide by publishing a Federal Register notice (65 FR 77934) concerning Draft Regulatory Guide DG– 1096 on December 13, 2000, followed by a Federal Register notice (68 FR 4524) concerning Draft Regulatory Guide DG– 1120 on January 29, 2003. Following the closure of the latest public comment period on March 24, 2003, the staff considered all stakeholder comments in the course of preparing the new Regulatory Guide 1.203. 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 Regulatory Guide 1.203 may be directed to Shawn O. Marshall at (301) 415–5861 or via e-mail to SOM@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 Regulatory Guide 1.203 and SRP section 15.0.2 are also available in the NRC’s Agencywide Documents Access and Management System (ADAMS) at https:// www.nrc.gov/reading-rm/adams.html, under Accession Nos. ML053500170 and ML053550265, respectively. VerDate Aug<31>2005 17:24 Feb 08, 2006 Jkt 208001 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 email 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 29th day of December, 2005. For the U.S. Nuclear Regulatory Commission. James T. Wiggins, Deputy Director, Office of Nuclear Regulatory Research. [FR Doc. E6–1774 Filed 2–8–06; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Regulatory Guide: Issuance, Availability The U.S. Nuclear Regulatory Commission (NRC) has issued a new 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. Regulatory Guide 1.201, ‘‘Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance,’’ which is being issued for trial use, provides guidance for use in developing and assessing evaluation models for accident and transient analyses. An additional benefit is that evaluation models that are developed using these guidelines will provide a more reliable framework for risk- PO 00000 Frm 00049 Fmt 4703 Sfmt 4703 6795 informed regulation and a basis for estimating the uncertainty in understanding transient and accident behavior. The NRC has promulgated regulations to permit power reactor licensees and license applicants to implement an alternative regulatory framework with respect to ‘‘special treatment,’’ where special treatment refers to those requirements that provide increased assurance beyond normal industrial practices that structures, systems, and components (SSCs) perform their design-basis functions. Under this framework, licensees using a riskinformed process for categorizing SSCs according to their safety significance can remove SSCs of low safety significance from the scope of certain identified special treatment requirements. The genesis of this framework stems from Option 2 of SECY–98–300, ‘‘Options for Risk-Informed Revisions to 10 CFR part 50, ‘Domestic Licensing of Production and Utilization Facilities’,’’ dated December 23, 1998.1 In that Commission paper, the NRC staff recommended developing risk-informed approaches to the application of special treatment requirements to reduce unnecessary regulatory burden related to SSCs of low safety significance by removing such SSCs from the scope of special treatment requirements. The Commission subsequently approved the NRC staff’s rulemaking plan and issuance of an Advanced Notice of Proposed Rulemaking (ANPR) as outlined in SECY–99–256, ‘‘Rulemaking Plan for Risk-Informing Special Treatment Requirements,’’ dated October 29, 1999. The Commission published the ANPR in the Federal Register (65 FR 11488) on March 3, 2000, and subsequently published a proposed rule for public comment (68 FR 26511) on May 16, 2003. Then, on November 22, 2004, the Commission adopted a new section, referred to as § 50.69, within Title 10, part 50, of the Code of Federal Regulations, on risk-informed categorization and treatment of SSCs for nuclear power plants (69 FR 68008). This trial regulatory guide describes a method that the NRC staff considers acceptable for use in complying with the Commission’s requirements in § 50.69 with respect to the 1 Commission papers cited in this notice are available through the NRC’s public Web site at https://www.nrc.gov/reading-rm/doc-collections/ commission/secys/, and the related Federal Register notices are available through the Federal Register Web site sponsored by the Government Printing Office (GPO) at https://www.gpoaccess.gov/ fr/. E:\FR\FM\09FEN1.SGM 09FEN1 6796 Federal Register / Vol. 71, No. 27 / Thursday, February 9, 2006 / Notices cprice-sewell on PROD1PC66 with NOTICES categorization of SSCs that are considered in risk-informing special treatment requirements. This categorization method uses the process that the Nuclear Energy Institute (NEI) described in Revision 0 of its guidance document NEI 00–04, ‘‘10 CFR 50.69 SSC Categorization Guideline,’’ dated July 2005.2 Specifically, this process determines the safety significance of SSCs and categorizes them into one of four risk-informed safety class (RISC) categories. The NRC issued a draft of this guide, Draft Regulatory Guide DG–1121, as part of the § 50.69 rulemaking package in May 2003, and solicited public comments specifically concerning the draft guide by publishing related Federal Register notices (68 FR 34012 and 68 FR 41408) on June 6 and July 11, 2003. Following the closure of the public comment period on August 1, 2003, the staff considered all stakeholder comments in the course of preparing the new Regulatory Guide 1.201. However, a few issues of technical interpretation and implementation still remain, with respect to specific aspects of the guidance. Because the staff believes these issues will be best resolved by testing the guide against actual applications, the NRC decided to issue this guide for trial use. This trial regulatory guide does not establish any final staff positions, and may be revised in response to experience with its use. As such, this trial guide does not establish a staff position for purposes of the Backfit Rule, 10 CFR 50.109, and any changes to this trial guide prior to staff adoption in final form will not be considered to be backfits as defined in 10 CFR 50.109(a)(1). This will ensure that the lessons learned from regulatory review of pilot and follow-on applications are adequately addressed in the final regulatory guide, and that the guidance is sufficient to enhance regulatory stability in the review, approval, and implementation of probabilistic risk assessments (PRAs) and their results in the risk-informed categorization process required by § 50.69. The NRC staff encourages and welcomes comments and suggestions in connection with improvements to published regulatory guides, as well as 2 NEI 00–04, ‘‘10 CFR 50.69 SSC Categorization Guideline,’’ is available through the NRC’s public Web site at https://adamswebsearch2.nrc.gov/ idmws/doccontent.dll?ID=052910091:&LogonId= 2b2cbc48fd7897510347535dd7c30495, and through the NRC’s Agencywide Documents Access and Management System (ADAMS), https://www.nrc.gov /reading-rm/adams/web-based.html, under Accession #ML052910035. VerDate Aug<31>2005 13:56 Feb 08, 2006 Jkt 208001 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 Regulatory Guide 1.201 may be directed to Donald G. Harrison at (301) 415–3587 or via e-mail to DGH@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 Regulatory Guide 1.201 are also available in the NRC’s Agencywide Documents Access and Management System (ADAMS) at https:// www.nrc.gov/reading-rm/adams.html, under Accession No. ML060260164. 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 27th day of January, 2006. PO 00000 Frm 00050 Fmt 4703 Sfmt 4703 For the U.S. Nuclear Regulatory Commission. Carl J. Paperiello, Director, Office of Nuclear Regulatory Research. [FR Doc. E6–1775 Filed 2–8–06; 8:45 am] BILLING CODE 7590–01–P SECURITIES AND EXCHANGE COMMISSION Proposed Collection; Comment Request Upon Written Request, Copies Available From: Securities and Exchange Commission, Office of Filings and Information Services, Washington, DC 20549. Extension: Form ADV–E; Sec File No. 270–318; OMB Control No. 3235–0361. Notice is hereby given that pursuant to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.) the Securities and Exchange Commission (the ‘‘Commission’’) is soliciting comments on the collection of information summarized below. The Commission plans to submit this existing collection of information to the Office of Management and Budget (‘‘OMB’’) for extension and approval. Form ADV–E is the cover sheet for accountant examination certificates filed pursuant to rule 206(4)–2 under the Investment Advisers Act of 1940 by certain investment advisers retaining custody of client securities or funds. Respondents each spend approximately three minutes, annually, complying with the requirements of the form. The estimate of burden hours set forth above is made solely for the purposes of the Paperwork Reduction Act and is not derived from a comprehensive or representative survey or study of the cost of Commission rules and forms. Written comments are invited on: (a) Whether the proposed collection of information is necessary for the proper performance of the functions of the agency, including whether the information will have practical utility; (b) the accuracy of the agency’s estimate of the burden of the collection of information; (c) ways to enhance the quality, utility, and clarity of the information collected; and (d) ways to minimize the burden of the collection of information on respondents, including through the use of automated collection techniques or other forms of information technology. Consideration will be given to comments and suggestions submitted in writing within 60 days of this publication. E:\FR\FM\09FEN1.SGM 09FEN1

Agencies

[Federal Register Volume 71, Number 27 (Thursday, February 9, 2006)]
[Notices]
[Pages 6795-6796]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-1775]


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

NUCLEAR REGULATORY COMMISSION


Regulatory Guide: Issuance, Availability

    The U.S. Nuclear Regulatory Commission (NRC) has issued a new 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.
    Regulatory Guide 1.201, ``Guidelines for Categorizing Structures, 
Systems, and Components in Nuclear Power Plants According to Their 
Safety Significance,'' which is being issued for trial use, provides 
guidance for use in developing and assessing evaluation models for 
accident and transient analyses. An additional benefit is that 
evaluation models that are developed using these guidelines will 
provide a more reliable framework for risk-informed regulation and a 
basis for estimating the uncertainty in understanding transient and 
accident behavior.
    The NRC has promulgated regulations to permit power reactor 
licensees and license applicants to implement an alternative regulatory 
framework with respect to ``special treatment,'' where special 
treatment refers to those requirements that provide increased assurance 
beyond normal industrial practices that structures, systems, and 
components (SSCs) perform their design-basis functions. Under this 
framework, licensees using a risk-informed process for categorizing 
SSCs according to their safety significance can remove SSCs of low 
safety significance from the scope of certain identified special 
treatment requirements.
    The genesis of this framework stems from Option 2 of SECY-98-300, 
``Options for Risk-Informed Revisions to 10 CFR part 50, `Domestic 
Licensing of Production and Utilization Facilities','' dated December 
23, 1998.\1\ In that Commission paper, the NRC staff recommended 
developing risk-informed approaches to the application of special 
treatment requirements to reduce unnecessary regulatory burden related 
to SSCs of low safety significance by removing such SSCs from the scope 
of special treatment requirements. The Commission subsequently approved 
the NRC staff's rulemaking plan and issuance of an Advanced Notice of 
Proposed Rulemaking (ANPR) as outlined in SECY-99-256, ``Rulemaking 
Plan for Risk-Informing Special Treatment Requirements,'' dated October 
29, 1999.
---------------------------------------------------------------------------

    \1\ Commission papers cited in this notice are available through 
the NRC's public Web site at https://www.nrc.gov/reading-rm/doc- collections/commission/secys/, and the related Federal Register 
notices are available through the Federal Register Web site 
sponsored by the Government Printing Office (GPO) at https://
www.gpoaccess.gov/fr/.
---------------------------------------------------------------------------

    The Commission published the ANPR in the Federal Register (65 FR 
11488) on March 3, 2000, and subsequently published a proposed rule for 
public comment (68 FR 26511) on May 16, 2003. Then, on November 22, 
2004, the Commission adopted a new section, referred to as Sec.  50.69, 
within Title 10, part 50, of the Code of Federal Regulations, on risk-
informed categorization and treatment of SSCs for nuclear power plants 
(69 FR 68008).
    This trial regulatory guide describes a method that the NRC staff 
considers acceptable for use in complying with the Commission's 
requirements in Sec.  50.69 with respect to the

[[Page 6796]]

categorization of SSCs that are considered in risk-informing special 
treatment requirements. This categorization method uses the process 
that the Nuclear Energy Institute (NEI) described in Revision 0 of its 
guidance document NEI 00-04, ``10 CFR 50.69 SSC Categorization 
Guideline,'' dated July 2005.\2\ Specifically, this process determines 
the safety significance of SSCs and categorizes them into one of four 
risk-informed safety class (RISC) categories.
---------------------------------------------------------------------------

    \2\ NEI 00-04, ``10 CFR 50.69 SSC Categorization Guideline,'' is 
available through the NRC's public Web site at https://
adamswebsearch2.nrc.gov/idmws/doccontent.dll?ID=052910091:&LogonId= 
2b2cbc48fd7897510347535dd7c30495, and through the NRC's Agencywide 
Documents Access and Management System (ADAMS), https://www.nrc.gov/
reading-rm/adams/web-based.html, under Accession 
ML052910035.
---------------------------------------------------------------------------

    The NRC issued a draft of this guide, Draft Regulatory Guide DG-
1121, as part of the Sec.  50.69 rulemaking package in May 2003, and 
solicited public comments specifically concerning the draft guide by 
publishing related Federal Register notices (68 FR 34012 and 68 FR 
41408) on June 6 and July 11, 2003. Following the closure of the public 
comment period on August 1, 2003, the staff considered all stakeholder 
comments in the course of preparing the new Regulatory Guide 1.201. 
However, a few issues of technical interpretation and implementation 
still remain, with respect to specific aspects of the guidance. Because 
the staff believes these issues will be best resolved by testing the 
guide against actual applications, the NRC decided to issue this guide 
for trial use. This trial regulatory guide does not establish any final 
staff positions, and may be revised in response to experience with its 
use. As such, this trial guide does not establish a staff position for 
purposes of the Backfit Rule, 10 CFR 50.109, and any changes to this 
trial guide prior to staff adoption in final form will not be 
considered to be backfits as defined in 10 CFR 50.109(a)(1). This will 
ensure that the lessons learned from regulatory review of pilot and 
follow-on applications are adequately addressed in the final regulatory 
guide, and that the guidance is sufficient to enhance regulatory 
stability in the review, approval, and implementation of probabilistic 
risk assessments (PRAs) and their results in the risk-informed 
categorization process required by Sec.  50.69.
    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 Regulatory Guide 1.201 may 
be directed to Donald G. Harrison at (301) 415-3587 or via e-mail to 
DGH@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 Regulatory Guide 1.201 
are also available in the NRC's Agencywide Documents Access and 
Management System (ADAMS) at https://www.nrc.gov/reading-rm/adams.html, 
under Accession No. ML060260164.
    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 27th day of January, 2006.

    For the U.S. Nuclear Regulatory Commission.
Carl J. Paperiello,
Director, Office of Nuclear Regulatory Research.
[FR Doc. E6-1775 Filed 2-8-06; 8:45 am]
BILLING CODE 7590-01-P
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