Final Regulatory Guide: Issuance, Availability, 6010-6011 [E7-2088]
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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
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below:
Clearance Officer: Mr. Neil
McNamara, National Credit Union
Administration, 1775 Duke Street,
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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:
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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
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08FEN1
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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 https://
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 https://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
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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
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Fmt 4703
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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
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]]>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 https://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
https://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
