Regulatory Guide: Issuance, Availability, 6794-6795 [E6-1774]

Download as PDF 6794 Federal Register / Vol. 71, No. 27 / Thursday, February 9, 2006 / Notices NATIONAL SCIENCE FOUNDATION Notice of Intent To Extend an Information Collection National Science Foundation. Notice and request for comments. AGENCY: ACTION: In compliance with the requirement of Section 3506(c)(2)(A) of the Paperwork Reduction Act of 1995 for opportunity for public comment on proposed data collection projects, the National Science Foundation (NSF) will publish periodic summaries of proposed projects. 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 shall have practical utility; (b) the accuracy of the agency’s estimate of the burden of the proposed collection of information; (c) ways to enhance the quality, utility, and clarity of the information to be 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. SUMMARY: Written comments on this notice must be received by April 10, 2006, to be assured of consideration. Comments received after that date will be considered to the extent practicable. FOR FURTHER INFORMATION CONTACT: Suzanne H. Plimpton, Reports Clearance Officer, National Science Foundation, 4201 Wilson Boulevard, Suite 295, Arlington, Virginia 22230; telephone (703) 292–7556; or send e-mail to splimpto@nsf.gov. Individuals who use a telecommunications device for the deaf (TDD) may call the Federal Information Relay Service (FIRS) at 1– 800–877–8339 between 9 a.m. and 9 p.m., Eastern time, Monday through Friday. You also may obtain a copy of the data collection instrument and instructions from Ms. Plimpton. SUPPLEMENTARY INFORMATION: Title of Collection: Request for Proposals. OMB Approval Number: 3145–0080. Expiration Date of Approval: May 31, 2006. Type of Request: Intent to seek approval to extend an information collection for three years. Proposed Project: The Federal Acquisition Regulations (FAR) Subpart 15.2—‘‘Solicitation and Receipt of Proposals and Information’’ prescribes policies and procedures for preparing and issuing Requests for Proposals. 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[FR Doc. 06–1192 Filed 2–8–06; 8:45 am] BILLING CODE 7555–01–M 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 PO 00000 Frm 00048 Fmt 4703 Sfmt 4703 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 1.203, ‘‘Transient and Accident Analysis Methods,’’ provides guidance for NRC licensees and applicants to use in developing and assessing evaluation models that may be used to analyze transient and accident behavior that is within the design basis of a nuclear power plant. Evaluation models that the NRC has previously approved will remain acceptable and need not be revised to conform with the guidance given in this regulatory guide. Chapter 15 of the NRC’s ‘‘Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants’’ (NUREG–0800) and the ‘‘Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants’’ (Regulatory Guide 1.70) describe a subset of the transient and accident events that must be considered in the safety analyses required by Title 10, part 50, of the Code of Federal Regulations (10 CFR part 50), ‘‘Domestic Licensing of Production and Utilization Facilities,’’ section 50.34, ‘‘Contents of Applications; Technical Information’’ (10 CFR 50.34). In particular, 10 CFR 50.34 specifies the following requirements regarding applications for construction permits and/or licenses to operate a facility: (1) Safety analysis reports must analyze the design and performance of structures, systems, and components, and their adequacy for the prevention of accidents and mitigation of the consequences of accidents. (2) Analysis and evaluation of emergency core cooling system (ECCS) cooling performance following postulated loss-of-coolant accidents (LOCAs) must be performed in accordance with the requirements of 10 CFR 50.46. (3) The technical specifications for the facility must be based on the safety analysis and prepared in accordance with the requirements of 10 CFR 50.36. An additional benefit is that evaluation models that are developed using the guidelines provided in Regulatory Guide 1.203 will provide a more reliable framework for riskinformed regulation and a basis for estimating the uncertainty in understanding transient and accident behavior. In addition, the NRC is issuing section 15.0.2 of the SRP, which covers the same subject material as Regulatory Guide 1.203, and is intended to complement the guide. Specifically, section 15.0.2 provides guidance to NRC reviewers of transient and accident E:\FR\FM\09FEN1.SGM 09FEN1 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

Agencies

[Federal Register Volume 71, Number 27 (Thursday, February 9, 2006)]
[Notices]
[Pages 6794-6795]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-1774]


=======================================================================
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 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 1.203, ``Transient and Accident Analysis 
Methods,'' provides guidance for NRC licensees and applicants to use in 
developing and assessing evaluation models that may be used to analyze 
transient and accident behavior that is within the design basis of a 
nuclear power plant. Evaluation models that the NRC has previously 
approved will remain acceptable and need not be revised to conform with 
the guidance given in this regulatory guide.
    Chapter 15 of the NRC's ``Standard Review Plan (SRP) for the Review 
of Safety Analysis Reports for Nuclear Power Plants'' (NUREG-0800) and 
the ``Standard Format and Content of Safety Analysis Reports for 
Nuclear Power Plants'' (Regulatory Guide 1.70) describe a subset of the 
transient and accident events that must be considered in the safety 
analyses required by Title 10, part 50, of the Code of Federal 
Regulations (10 CFR part 50), ``Domestic Licensing of Production and 
Utilization Facilities,'' section 50.34, ``Contents of Applications; 
Technical Information'' (10 CFR 50.34). In particular, 10 CFR 50.34 
specifies the following requirements regarding applications for 
construction permits and/or licenses to operate a facility:
    (1) Safety analysis reports must analyze the design and performance 
of structures, systems, and components, and their adequacy for the 
prevention of accidents and mitigation of the consequences of 
accidents.
    (2) Analysis and evaluation of emergency core cooling system (ECCS) 
cooling performance following postulated loss-of-coolant accidents 
(LOCAs) must be performed in accordance with the requirements of 10 CFR 
50.46.
    (3) The technical specifications for the facility must be based on 
the safety analysis and prepared in accordance with the requirements of 
10 CFR 50.36.
    An additional benefit is that evaluation models that are developed 
using the guidelines provided in Regulatory Guide 1.203 will provide a 
more reliable framework for risk-informed regulation and a basis for 
estimating the uncertainty in understanding transient and accident 
behavior.
    In addition, the NRC is issuing section 15.0.2 of the SRP, which 
covers the same subject material as Regulatory Guide 1.203, and is 
intended to complement the guide. Specifically, section 15.0.2 provides 
guidance to NRC reviewers of transient and accident

[[Page 6795]]

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/doc-collections. 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.
    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
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