Final Regulatory Guide: Issuance, Availability, 6010-6011 [E7-2088]

Download as PDF 6010 Federal Register / Vol. 72, No. 26 / Thursday, February 8, 2007 / Notices Copyright Office. Affidavits received in this manner will be accepted with the understanding that the owners of those stations will resubmit affidavits when the Office next formally updates the specialty station list. An interested party may file an objection to any late–filed affidavit. Such objections shall be kept on file in the Copyright Office together with the corresponding affidavit. February 2, 2007 Marybeth Peters, Register of Copyrights. [FR Doc. E7–2104 Filed 2–7–06; 8:45 am] conditions in corporate credit unions, and to allocate supervision and examination resources. Respondents: Corporate credit unions, or ‘‘banker’s banks’’ for natural person credit unions. Estimated No. of Respondents/Record keepers: 30. Estimated Burden Hours per Response: 2 hours. Frequency of Response: Monthly. Estimated Total Annual Burden Hours: 720 hours. Estimated Total Annual Cost: None. By the National Credit Union Administration Board on February 5, 2007. Mary Rupp, Secretary of the Board. [FR Doc. E7–2096 Filed 2–7–07; 8:45 am] BILLING CODE 1410–30–S NATIONAL CREDIT UNION ADMINISTRATION BILLING CODE 7535–01–P Agency Information Collection Activities: Submission to OMB for Extension of a Currently Approved Collection; Comment Request NUCLEAR REGULATORY COMMISSION National Credit Union Administration (NCUA). ACTION: Request for comment. Final Regulatory Guide: Issuance, Availability The NCUA intends to submit the following information collection to the Office of Management and Budget (OMB) for review and clearance under the Paperwork Reduction Act of 1995 (Pub. L. 104–13, 44 U.S.C. Chapter 35). This information collection is published to obtain comments from the public. DATES: Comments will be accepted until April 9, 2007. ADDRESSES: Interested parties are invited to submit written comments to the NCUA Clearance Officer listed below: Clearance Officer: Mr. Neil McNamara, National Credit Union Administration, 1775 Duke Street, Alexandria, VA 22314–3428, Fax No. 703–837–2861, E-mail: mcnamara@ncua.gov. FOR FURTHER INFORMATION CONTACT: Requests for additional information or a copy of the information collection request, should be directed to Tracy Sumpter at the National Credit Union Administration, 1775 Duke Street, Alexandria, VA 22314–3428, or at (703) 518–6444. SUPPLEMENTARY INFORMATION: Proposal for the following collection of information: Title: Corporate Credit Union Monthly Call Report. OMB Number: 3133–0067. Form Number: NCUA 5310. Type of Review: Recordkeeping, reporting and monthly. Description: NCUA utilizes the information to monitor financial 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. Like its predecessor, Revision 1 of Regulatory Guide 1.196, ‘‘Control Room Habitability at Light-Water Nuclear Power Reactors,’’ provides guidance and criteria that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for implementing the agency’s regulations in Appendix A, ‘‘General Design Criteria for Nuclear Power Plants,’’ to Title 10, Part 50, of the Code of Federal Regulations (10 CFR part 50), ‘‘Domestic Licensing of Production and Utilization Facilities,’’ as they relate to control room habitability (CRH). Specifically, this guide outlines a process that licensees may apply to control rooms that are modified, are newly designed, or must have their conformance to the regulations reconfirmed. In Appendix A to 10 CFR Part 50, General Design Criteria (GDC) 1, 3, 4, 5, and 19 apply to CRH, as follows: • GDC 1, ‘‘Quality Standards and Records,’’ requires that structures, systems, and components (SSCs) AGENCY: jlentini on PROD1PC65 with NOTICES SUMMARY: VerDate Aug<31>2005 15:58 Feb 07, 2007 Jkt 211001 PO 00000 Frm 00052 Fmt 4703 Sfmt 4703 important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions performed. • GDC 3, ‘‘Fire Protection,’’ requires that SSCs important to safety be designed and located to minimize the effects of fires and explosions. • GDC 4, ‘‘Environmental and Dynamic Effects Design Bases,’’ requires SSCs important to safety to be designed to accommodate the effects of, and to be compatible with, the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-ofcoolant accidents (LOCAs). • GDC 5, ‘‘Sharing of Structures, Systems, and Components,’’ requires that SSCs important to safety not be shared among nuclear power units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions, including, in the event of an accident in one unit, the orderly shutdown and cooldown of the remaining units. • GDC 19, ‘‘Control Room,’’ requires that a control room be provided from which actions can be taken to operate the nuclear reactor safely under normal conditions and to maintain the reactor in a safe condition under accident conditions, including a LOCA. Adequate radiation protection is to be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of specified values. Since the NRC initially issued Regulatory Guide 1.196 in May 2003, the staff determined that the information presented in Appendix B to that guide did not accurately represent a viable technical specification for CRH at light-water nuclear power reactors. In particular, it referred to failure of a particular surveillance as a plant state, rather than having the results of the surveillance factor into the operability determination. In addition, it did not provide for a definite time to restore functionality to the control room envelope, whereas all improved standard technical specifications (iSTS) contain such provisions. Moreover, Appendix B was included as a ‘‘strawman,’’ to be deleted when details had been more carefully worked out with industry participation, and those technical specifications placed in the iSTS with all other acceptable technical specifications. As of the publication date of this Revision 1 of Regulatory Guide 1.196, no utility has been granted the technical specification changes represented by E:\FR\FM\08FEN1.SGM 08FEN1 jlentini on PROD1PC65 with NOTICES Federal Register / Vol. 72, No. 26 / Thursday, February 8, 2007 / Notices Appendix B to the original version of this guide. Consequently, the NRC staff elected to remove Appendix B (and all related references) from this revision. Removal of Appendix B from this revised guide does not require any stakeholder to take any action and does not reduce safety in any way. Moreover, public meetings with the owners’ group Technical Specification Task Force have provided ample opportunity for public comment regarding this revision. Therefore, the staff views the removal of Appendix B as a neutral action, for which further public comments are unnecessary. For that reason, the staff chose not to issue this revision as a draft guide for public comment before publishing this Revision 1 of Regulatory Guide 1.196. Nonetheless, 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: Rulemaking, Directives and Editing Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. Hand-deliver comments to: Rulemaking, Directives and Editing 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: Rulemaking, Directives and Editing Branch, Office of Administration, U.S. Nuclear Regulatory Commission at (301) 415–5144. Requests for technical information about Revision 1 of Regulatory Guide 1.196 may be directed to Harold Walker, at (301) 415–2827 or HXW@nrc.gov. Regulatory guides are available for inspection or downloading through the NRC’s public Web site at http:// www.nrc.gov/reading-rm/doccollections/reg-guides/. In addition, Revision 1 of Regulatory Guide 1.196 is available for inspection or downloading through ADAMS at http://www.nrc.gov/ reading-rm/adams.html, under Accession #ML063560144. Revision 1 of Regulatory Guide 1.196 and other related publicly available documents can also be viewed electronically on computers in the NRC’s Public Document Room (PDR), which is located at 11555 Rockville Pike, Rockville, Maryland. The PDR’s reproduction contractor will make copies of documents for a fee. The PDR’s mailing address is USNRC PDR, Washington, DC 20555–0001. The PDR VerDate Aug<31>2005 15:58 Feb 07, 2007 Jkt 211001 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. Please note that the NRC does not intend to distribute printed copies of Revision 1 of Regulatory Guide 1.196, unless specifically requested on an individual basis with adequate justification. Such requests for single copies of draft or final guides (which may be reproduced) 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 23rd day of January, 2007. For the U.S. Nuclear Regulatory Commission. Brian W. Sheron, Director, Office of Nuclear Regulatory Research. [FR Doc. E7–2088 Filed 2–7–07; 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 1 of Regulatory Guide 1.200, ‘‘An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for RiskInformed Activities,’’ describes one acceptable approach for determining whether the quality of a probabilistic risk assessment (PRA), in total or the parts that are used to support an application, is sufficient to provide confidence in the results, such that the PRA can be used in regulatory decisionmaking for light-water reactors. Specifically, Revision 1 of Regulatory PO 00000 Frm 00053 Fmt 4703 Sfmt 4703 6011 Guide 1.200 provides guidance in four areas: (1) A minimal set of requirements of a technically acceptable PRA. (2) The NRC’s position on PRA consensus standards and industry PRA program documents. (3) Demonstration that the PRA (in total or specific parts) used in regulatory applications is of sufficient technical adequacy. (4) Documentation to support a regulatory submittal. This guidance is intended to be consistent with the NRC’s PRA Policy Statement, entitled ‘‘Use of Probabilistic Risk Assessment Methods in Nuclear Activities: Final Policy Statement,’’ which the NRC published in the Federal Register on August 16, 1995 (60 FR 42622) to encourage use of PRA in all regulatory matters. That Policy Statement states that ‘‘* * * the use of PRA technology should be increased to the extent supported by the state-of-theart in PRA methods and data and in a manner that complements the NRC’s deterministic approach.’’ Since that time, many uses have been implemented or undertaken, including modification of the NRC’s reactor safety inspection program and initiation of work to modify reactor safety regulations. Consequently, confidence in the information derived from a PRA is an important issue, in that the accuracy of the technical content must be sufficient to justify the specific results and insights that are used to support the decision under consideration. Revision 1 of Regulatory Guide 1.200 is also intended to be consistent with the more detailed guidance in Regulatory Guide 1.174, ‘‘An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on PlantSpecific Changes to the Licensing Basis,’’ which the NRC issued in November 2002. In addition, Revision 1 of Regulatory Guide 1.200 is intended to reflect and endorse (with certain objections) the following guidance provided by the American Society of Mechanical Engineers (ASME) and the Nuclear Energy Institute (NEI): • ASME RA–S–2002, ‘‘Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications,’’ dated April 5, 2002. • ASME RA–Sa7–2003, ‘‘Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications,’’ Addendum A to ASME RA–S–2002, dated December 5, 2003. • ASME RA–Sb–2005, ‘‘Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications,’’ E:\FR\FM\08FEN1.SGM 08FEN1

Agencies

[Federal Register Volume 72, Number 26 (Thursday, February 8, 2007)]
[Notices]
[Pages 6010-6011]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-2088]


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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.
    Like its predecessor, Revision 1 of Regulatory Guide 1.196, 
``Control Room Habitability at Light-Water Nuclear Power Reactors,'' 
provides guidance and criteria that the staff of the U.S. Nuclear 
Regulatory Commission (NRC) considers acceptable for implementing the 
agency's regulations in Appendix A, ``General Design Criteria for 
Nuclear Power Plants,'' to Title 10, Part 50, of the Code of Federal 
Regulations (10 CFR part 50), ``Domestic Licensing of Production and 
Utilization Facilities,'' as they relate to control room habitability 
(CRH). Specifically, this guide outlines a process that licensees may 
apply to control rooms that are modified, are newly designed, or must 
have their conformance to the regulations reconfirmed.
    In Appendix A to 10 CFR Part 50, General Design Criteria (GDC) 1, 
3, 4, 5, and 19 apply to CRH, as follows:
     GDC 1, ``Quality Standards and Records,'' requires that 
structures, systems, and components (SSCs) important to safety be 
designed, fabricated, erected, and tested to quality standards 
commensurate with the importance of the safety functions performed.
     GDC 3, ``Fire Protection,'' requires that SSCs important 
to safety be designed and located to minimize the effects of fires and 
explosions.
     GDC 4, ``Environmental and Dynamic Effects Design Bases,'' 
requires SSCs important to safety to be designed to accommodate the 
effects of, and to be compatible with, the environmental conditions 
associated with normal operation, maintenance, testing, and postulated 
accidents, including loss-of-coolant accidents (LOCAs).
     GDC 5, ``Sharing of Structures, Systems, and Components,'' 
requires that SSCs important to safety not be shared among nuclear 
power units unless it can be shown that such sharing will not 
significantly impair their ability to perform their safety functions, 
including, in the event of an accident in one unit, the orderly 
shutdown and cooldown of the remaining units.
     GDC 19, ``Control Room,'' requires that a control room be 
provided from which actions can be taken to operate the nuclear reactor 
safely under normal conditions and to maintain the reactor in a safe 
condition under accident conditions, including a LOCA. Adequate 
radiation protection is to be provided to permit access and occupancy 
of the control room under accident conditions without personnel 
receiving radiation exposures in excess of specified values.
    Since the NRC initially issued Regulatory Guide 1.196 in May 2003, 
the staff determined that the information presented in Appendix B to 
that guide did not accurately represent a viable technical 
specification for CRH at light-water nuclear power reactors. In 
particular, it referred to failure of a particular surveillance as a 
plant state, rather than having the results of the surveillance factor 
into the operability determination. In addition, it did not provide for 
a definite time to restore functionality to the control room envelope, 
whereas all improved standard technical specifications (iSTS) contain 
such provisions. Moreover, Appendix B was included as a ``strawman,'' 
to be deleted when details had been more carefully worked out with 
industry participation, and those technical specifications placed in 
the iSTS with all other acceptable technical specifications.
    As of the publication date of this Revision 1 of Regulatory Guide 
1.196, no utility has been granted the technical specification changes 
represented by

[[Page 6011]]

Appendix B to the original version of this guide. Consequently, the NRC 
staff elected to remove Appendix B (and all related references) from 
this revision. Removal of Appendix B from this revised guide does not 
require any stakeholder to take any action and does not reduce safety 
in any way. Moreover, public meetings with the owners' group Technical 
Specification Task Force have provided ample opportunity for public 
comment regarding this revision. Therefore, the staff views the removal 
of Appendix B as a neutral action, for which further public comments 
are unnecessary. For that reason, the staff chose not to issue this 
revision as a draft guide for public comment before publishing this 
Revision 1 of Regulatory Guide 1.196. Nonetheless, 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: Rulemaking, Directives and Editing Branch, Office 
of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.
    Hand-deliver comments to: Rulemaking, Directives and Editing 
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: Rulemaking, Directives and Editing Branch, Office 
of Administration, U.S. Nuclear Regulatory Commission at (301) 415-
5144.
    Requests for technical information about Revision 1 of Regulatory 
Guide 1.196 may be directed to Harold Walker, at (301) 415-2827 or 
HXW@nrc.gov.
    Regulatory guides are available for inspection or downloading 
through the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-
collections/reg-guides/. In addition, Revision 1 of Regulatory Guide 
1.196 is available for inspection or downloading through ADAMS at 
http://www.nrc.gov/reading-rm/adams.html, under Accession 
ML063560144.
    Revision 1 of Regulatory Guide 1.196 and other related publicly 
available documents can also be viewed electronically on computers in 
the NRC's Public Document Room (PDR), which is located at 11555 
Rockville Pike, Rockville, Maryland. The PDR's reproduction contractor 
will make copies of documents for a fee. 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.
    Please note that the NRC does not intend to distribute printed 
copies of Revision 1 of Regulatory Guide 1.196, unless specifically 
requested on an individual basis with adequate justification. Such 
requests for single copies of draft or final guides (which may be 
reproduced) 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 23rd day of January, 2007.

    For the U.S. Nuclear Regulatory Commission.
Brian W. Sheron,
Director, Office of Nuclear Regulatory Research.
[FR Doc. E7-2088 Filed 2-7-07; 8:45 am]
BILLING CODE 7590-01-P