Notice of Issuance of Regulatory Guide, 30648 [E8-11847]
Download as PDF
30648
Federal Register / Vol. 73, No. 103 / Wednesday, May 28, 2008 / Notices
available. If you are interested in
receiving this Commission meeting
schedule electronically, please send an
electronic message to dkw@nrc.gov.
Dated: May 22, 2008.
R. Michelle Schroll,
Office of the Secretary.
[FR Doc. 08–1303 Filed 5–23–08; 10:44 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Notice of Issuance of Regulatory Guide
Nuclear Regulatory
Commission.
ACTION: Issuance, Availability of
Regulatory Guide 1.45, Revision 1.
AGENCY:
John
Ridgely, Regulatory Guide Development
Branch, Division of Engineering, Office
of Nuclear Regulatory Research, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, telephone
(301) 415–6555 or e-mail to
John.Ridgely@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
SUPPLEMENTARY INFORMATION:
mstockstill on PROD1PC66 with NOTICES
I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a revision
to an existing guide in the agency’s
‘‘Regulatory Guide’’ series. This series
was developed to describe and make
available to the public information such
as methods that are acceptable to the
NRC staff for implementing specific
parts of the agency’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 1.45,
‘‘Guidance on Monitoring and
Responding to Reactor Coolant System
Leakage,’’ was issued with a temporary
identification as Draft Regulatory Guide
DG–1173. General Design Criterion
(GDC) 14, ‘‘Reactor Coolant Pressure
Boundary,’’ as set forth 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,’’
requires that the reactor coolant
pressure boundary (RCPB) shall be
designed, fabricated, erected, and tested
so as to have an extremely low
probability of abnormal leakage, of
rapidly propagating failure, and of gross
rupture. As a result, these nuclear
components are normally designed to
the criteria established in Section III of
VerDate Aug<31>2005
16:31 May 27, 2008
Jkt 214001
the Boiler and Pressure Vessel Code
promulgated by the American Society of
Mechanical Engineers.
During the design phase, degradationresistant materials are normally
specified for reactor coolant system
(RCS) components. However, materials
can degrade as a result of the complex
interaction of the materials, the stresses
they encounter, and the normal and
upset operating environments in which
they are used. Such material
degradation could lead to the leakage of
the reactor coolant. Consequently, GDC
30, ‘‘Quality of Reactor Coolant Pressure
Boundary,’’ of Appendix A to 10 CFR
Part 50 requires that means shall be
provided for detecting and, to the extent
practical, identifying the location of the
source of reactor coolant leakage.
Additionally, 10 CFR 50.55a, ‘‘Codes
and Standards,’’ requires the
performance of inservice inspection and
testing of nuclear power plant
components. Thus, the concept of
defense-in-depth is used to provide
assurance that structural integrity of the
RCPB is maintained. This guide
describes methods that the staff of the
NRC considers acceptable for
implementing these requirements, with
regard to selecting reactor coolant
leakage detection systems, monitoring
for leakage, and responding to leakage.
This guide applies to light-water cooled
reactors.
II. Further Information
In June 2007, DG–1173 was published
with a public comment period of 60
days from the issuance of the guide. The
public comment period closed on
August 28, 2007. The staff’s responses to
the public comments are located in the
NRC’s Agencywide Documents Access
and Management System (ADAMS),
Accession Number ML073200289.
Electronic copies of Regulatory Guide
1.45, Revision 1 are available through
the NRC’s public Web site under
‘‘Regulatory Guides’’ at https://
www.nrc.gov/reading-rm/doccollections/.
In addition, regulatory guides are
available for inspection at the NRC’s
Public Document Room (PDR), which is
located at Room O–1F21, One White
Flint North, 11555 Rockville Pike,
Rockville, Maryland 20852–2738. 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) 397–4209, by
fax at (301) 415–3548, and by e-mail to
pdr@nrc.gov.
Regulatory guides are not
copyrighted, and NRC approval is not
required to reproduce them.
PO 00000
Frm 00049
Fmt 4703
Sfmt 4703
Dated at Rockville, Maryland, this 21st day
of May, 2008.
For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch,
Division of Engineering, Office of Nuclear
Regulatory Research.
[FR Doc. E8–11847 Filed 5–27–08; 8:45 am]
BILLING CODE 7590–01–P
OFFICE OF PERSONNEL
MANAGEMENT
Submission for OMB Review;
Comment Request for Extension,
Without Change, of a Currently
Approved Information Collection: RI
20–64, RI 20–64A and RI 20–64B
Office of Personnel
Management.
ACTION: Notice.
AGENCY:
SUMMARY: In accordance with the
Paperwork Reduction Act of 1995 (Pub.
L. 104–13, May 22, 1995), this notice
announces that the Office of Personnel
Management (OPM) has submitted to
the Office of Management and Budget
(OMB) a request for extension, without
change, of a currently approved
information collection. RI 20–64, Letter
Reply to Request for Information, is
used by the Civil Service Retirement
System to provide information about the
amount of annuity payable after a
survivor reduction, to explain the
annuity reductions required to pay for
the survivor benefit, and to give the
beginning rate of survivor annuity. RI
20–64A, Former Spouse Survivor
Annuity Election, is used by the Civil
Service Retirement System to obtain a
survivor benefits election from
annuitants who are eligible to elect to
provide survivor benefits for a former
spouse. RI 20–64B, Information on
Electing a Survivor Annuity for Your
Former Spouse, is a pamphlet that
provides important information to
retirees under the Civil Service
Retirement System who want to provide
a survivor annuity for a former spouse.
We estimate that 30 survivor elections
on RI 20–64A will be processed per year
and that of these eight will use RI 20–
64 to ask for information about electing
a smaller survivor benefit. Form RI 20–
64A requires 45 minutes to complete for
a burden of 23 hours. Form RI 20–64
requires 8 minutes to complete for a
burden of 1 hour. The total burden is 24
hours.
For copies of this proposal, contact
Mary Beth Smith-Toomey on (202) 606–
8358, FAX (202) 418–3251 or via E-mail
to MaryBeth.Smith-Toomey@opm.gov.
E:\FR\FM\28MYN1.SGM
28MYN1
Agencies
[Federal Register Volume 73, Number 103 (Wednesday, May 28, 2008)]
[Notices]
[Page 30648]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-11847]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Notice of Issuance of Regulatory Guide
AGENCY: Nuclear Regulatory Commission.
ACTION: Issuance, Availability of Regulatory Guide 1.45, Revision 1.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: John Ridgely, Regulatory Guide
Development Branch, Division of Engineering, Office of Nuclear
Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone (301) 415-6555 or e-mail to John.Ridgely@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision
to an existing guide in the agency's ``Regulatory Guide'' series. This
series was developed to describe and make available to the public
information such as methods that are acceptable to the NRC staff for
implementing specific parts of the agency'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 1.45, ``Guidance on Monitoring and
Responding to Reactor Coolant System Leakage,'' was issued with a
temporary identification as Draft Regulatory Guide DG-1173. General
Design Criterion (GDC) 14, ``Reactor Coolant Pressure Boundary,'' as
set forth 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,'' requires that the reactor coolant pressure boundary
(RCPB) shall be designed, fabricated, erected, and tested so as to have
an extremely low probability of abnormal leakage, of rapidly
propagating failure, and of gross rupture. As a result, these nuclear
components are normally designed to the criteria established in Section
III of the Boiler and Pressure Vessel Code promulgated by the American
Society of Mechanical Engineers.
During the design phase, degradation-resistant materials are
normally specified for reactor coolant system (RCS) components.
However, materials can degrade as a result of the complex interaction
of the materials, the stresses they encounter, and the normal and upset
operating environments in which they are used. Such material
degradation could lead to the leakage of the reactor coolant.
Consequently, GDC 30, ``Quality of Reactor Coolant Pressure Boundary,''
of Appendix A to 10 CFR Part 50 requires that means shall be provided
for detecting and, to the extent practical, identifying the location of
the source of reactor coolant leakage. Additionally, 10 CFR 50.55a,
``Codes and Standards,'' requires the performance of inservice
inspection and testing of nuclear power plant components. Thus, the
concept of defense-in-depth is used to provide assurance that
structural integrity of the RCPB is maintained. This guide describes
methods that the staff of the NRC considers acceptable for implementing
these requirements, with regard to selecting reactor coolant leakage
detection systems, monitoring for leakage, and responding to leakage.
This guide applies to light-water cooled reactors.
II. Further Information
In June 2007, DG-1173 was published with a public comment period of
60 days from the issuance of the guide. The public comment period
closed on August 28, 2007. The staff's responses to the public comments
are located in the NRC's Agencywide Documents Access and Management
System (ADAMS), Accession Number ML073200289.
Electronic copies of Regulatory Guide 1.45, Revision 1 are
available through the NRC's public Web site under ``Regulatory Guides''
at https://www.nrc.gov/reading-rm/doc-collections/.
In addition, regulatory guides are available for inspection at the
NRC's Public Document Room (PDR), which is located at Room O-1F21, One
White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852-
2738. 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) 397-4209, by fax at (301) 415-3548, and by e-mail to pdr@nrc.gov.
Regulatory guides are not copyrighted, and NRC approval is not
required to reproduce them.
Dated at Rockville, Maryland, this 21st day of May, 2008.
For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch, Division of Engineering,
Office of Nuclear Regulatory Research.
[FR Doc. E8-11847 Filed 5-27-08; 8:45 am]
BILLING CODE 7590-01-P