Introduction-Part 2, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: Light-Water Small Modular Reactor Edition, 6657-6658 [2014-02317]
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Federal Register / Vol. 79, No. 23 / Tuesday, February 4, 2014 / Notices
application(s) for CHRCs, including the
FBI fingerprint record.
mstockstill on DSK4VPTVN1PROD with NOTICES
F. Right to Correct and Complete
Information
1. Prior to any final adverse
determination, the licensee shall make
available to the individual the contents
of any criminal history records obtained
from the FBI for the purpose of assuring
correct and complete information.
Written confirmation by the individual
of receipt of this notification must be
maintained by the licensee for a period
of 1 year from the date of notification.
2. If, after reviewing the record, an
individual believes that it is incorrect or
incomplete in any respect and wishes to
change, correct, or update the alleged
deficiency, or to explain any matter in
the record, the individual may initiate
challenge procedures. These procedures
include either direct application by the
individual challenging the record to the
agency (i.e., law enforcement agency)
that contributed the questioned
information, or direct challenge as to the
accuracy or completeness of any entry
on the criminal history record to the
Assistant Director, Federal Bureau of
Investigation Identification Division,
Washington, DC 20537–9700 (as set
forth in 28 CFR 16.30 through 16.34). In
the latter case, the FBI forwards the
challenge to the agency that submitted
the data and requests that agency to
verify or correct the challenged entry.
Upon receipt of an official
communication directly from the agency
that contributed the original
information, the FBI Identification
Division makes any changes necessary
in accordance with the information
supplied by that agency. The licensee
must provide at least 10 days for an
individual to initiate an action
challenging the results of a FBI CHRC
after the record is made available for
his/her review. The licensee may make
a final access determination based on
the criminal history record only upon
receipt of the FBI’s ultimate
confirmation or correction of the record.
Upon a final adverse determination on
access to an ISFSI, the licensee shall
provide the individual its documented
basis for denial. Access to an ISFSI shall
not be granted to an individual during
the review process.
G. Protection of Information
1. The licensee shall develop,
implement, and maintain a system for
personnel information management
with appropriate procedures for the
protection of personal, confidential
information. This system shall be
designed to prohibit unauthorized
access to sensitive information and to
VerDate Mar<15>2010
20:14 Feb 03, 2014
Jkt 232001
prohibit modification of the information
without authorization.
2. Each licensee who obtains a
criminal history record on an individual
pursuant to this Order shall establish
and maintain a system of files and
procedures, for protecting the record
and the personal information from
unauthorized disclosure.
3. The licensee may not disclose the
record or personal information collected
and maintained to persons other than
the subject individual, his/her
representative, or to those who have a
need to access the information in
performing assigned duties in the
process of determining suitability for
unescorted access to the protected area
of an ISFSI. No individual authorized to
have access to the information may redisseminate the information to any
other individual who does not have the
appropriate need to know.
4. The personal information obtained
on an individual from a CHRC may be
transferred to another licensee if the
gaining licensee receives the
individual’s written request to redisseminate the information contained
in his/her file, and the gaining licensee
verifies information such as the
individual’s name, date of birth, social
security number, sex, and other
applicable physical characteristics for
identification purposes.
5. The licensee shall make criminal
history records, obtained under this
section, available for examination by an
authorized representative of the NRC to
determine compliance with the
regulations and laws.
[FR Doc. 2014–02324 Filed 2–3–14; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2012–0268]
Introduction—Part 2, Standard Review
Plan for the Review of Safety Analysis
Reports for Nuclear Power Plants:
Light-Water Small Modular Reactor
Edition
Nuclear Regulatory
Commission.
ACTION: Standard review plan section;
issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing a final
revision to the following section of
NUREG–0800, ‘‘Standard Review Plan
for the Review of Safety Analysis
Reports for Nuclear Power Plants: LWR
Edition.’’ The final revision is the
Standard Review Plan (SRP),
‘‘Introduction—Part 2, Standard Review
SUMMARY:
PO 00000
Frm 00127
Fmt 4703
Sfmt 4703
6657
Plan for the Review of Safety Analysis
Reports for Nuclear Power Plants: LightWater Small Modular Reactor Edition.’’
DATES: The effective date of this SRP
update is March 6, 2014.
ADDRESSES: Please refer to Docket ID
NRC–2012–0268 when contacting the
NRC about the availability of
information regarding this document.
You may access publicly-available
information related to this action by the
following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2012–0268. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publiclyavailable documents online in the NRC
Library at https://www.nrc.gov/readingrm/adams.html. To begin the search,
select ‘‘ADAMS Public Documents’’ and
then select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. The final
revision for ‘‘Introduction—Part 2,
Standard Review Plan for the Review of
Safety Analysis Reports for Nuclear
Power Plants: Light-Water Small
Modular Reactor Edition’’ is available in
ADAMS under Accession No.
ML13207A315.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
• The NRC posts its issued staff
guidance on the NRC’s external Web
page at https://www.nrc.gov/reading-rm/
doc-collections/nuregs/staff/sr0800/.
FOR FURTHER INFORMATION CONTACT:
Jonathan DeGange, Office of New
Reactors, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–6992 or
email: mailto:Jonathan.DeGange@
nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
On January 22, 2013 (78 FR 4477), the
NRC published for public comment the
initial issuance of ‘‘Introduction—Part
2, Standard Review Plan for the Review
of Safety Analysis Reports for Nuclear
Power Plants: Integral Pressurized Water
Reactor (iPWR) Edition.’’
E:\FR\FM\04FEN1.SGM
04FEN1
6658
Federal Register / Vol. 79, No. 23 / Tuesday, February 4, 2014 / Notices
mstockstill on DSK4VPTVN1PROD with NOTICES
Comment submissions were received
on the proposed revision (ADAMS
Accession No. ML12142A237).
The NRC staff made several changes
to the proposed revision after
consideration of the comments. The
scope of use of the new introduction has
been expanded to include any type of
application under Part 52 of Title 10 of
the Code of Federal Regulations (10
CFR): early site permits (ESPs), design
certifications (DCs), standard design
approvals (SDAs), combined licenses
(COLs), or manufacturing licenses
(MLs). Additionally, throughout the
document, the use of the term ‘‘iPWR’’
(integral pressurized water reactor) has
been replaced by ‘‘SMR’’ (small modular
reactor) for consistency. Finally, the
historical summary paragraph related to
SECY–11–0156 was removed as it did
not directly apply to the guidance in the
new part of the introduction.
A summary of the public comments
and the NRC staff’s disposition of the
comments are available in a separate
document, Response to Public
Comments on Draft SRP,
‘‘Introduction—Part 2’’ (ADAMS
Accession No. ML13207A309). The
ADAMS Accession Number for the
Nuclear Energy Institute letter and
comments is ML13091A017.
II. Backfitting and Issue Finality
Issuance of this final SRP section does
not constitute backfitting as defined in
10 CFR 50.109 (the Backfit Rule) and is
not otherwise inconsistent with the
issue finality provisions in 10 CFR part
52. The NRC staff’s position is based
upon the following considerations:
1. The SRP positions do not constitute
backfitting, inasmuch as the SRP is
internal guidance directed at the NRC
staff with respect to their regulatory
responsibilities.
The SRP provides guidance to the
staff on how to review an application for
NRC regulatory approval in the form of
licensing. Changes in internal staff
guidance are not matters for which
either nuclear power plant applicants or
licensees are protected under either the
Backfit Rule or the issue finality
provisions of 10 CFR part 52.
2. Backfitting and issue finality—with
certain exceptions discussed below—do
not protect current or future applicants.
Applicants and potential applicants
are not, with certain exceptions,
protected by either the Backfit Rule or
any issue finality provisions under 10
CFR part 52. This is because neither the
Backfit Rule nor the issue finality
provisions were intended to apply to
every NRC action which substantially
changes the expectations of current and
future applicants.
VerDate Mar<15>2010
20:14 Feb 03, 2014
Jkt 232001
The exceptions to the general
principle are applicable whenever an
applicant references a 10 CFR part 52
license (e.g., an early site permit) and/
or NRC regulatory approval (e.g., a
design certification rule) with specified
issue finality provisions. The staff does
not currently intend to impose the
positions represented in this SRP
section in a manner that is inconsistent
with any issue finality provisions of 10
CFR part 52. If in the future the NRC
staff does indeed intend to impose
positions inconsistent with these issue
finality provisions, the NRC staff must
address the regulatory criteria for
avoiding issue finality.
3. The NRC staff has no intention to
impose the SRP positions on existing
nuclear power plant licenses or
regulatory approvals either now or in
the future (absent a voluntary request
for change from the licensee, holder of
a regulatory approval, or a design
certification applicant).
The staff does not intend to impose or
apply the positions described in the SRP
section to existing (already issued)
licenses (e.g., operating licenses and
combined licenses) and regulatory
approvals—in this case, design
certifications. Hence, the issuance of
this SRP guidance even if considered
guidance which is within the purview
of the issue finality provisions in 10
CFR part 52—need not be evaluated as
if it were a backfit or as being
inconsistent with issue finality
provisions. If, in the future, the staff
seeks to impose a position in the SRP on
holders of already issued licenses in a
manner which does not provide issue
finality as described in the applicable
issue finality provision, then the staff
must make the showing as set forth in
the Backfit Rule, or address the criteria
for avoiding issue finality as described
applicable issue finality provision, as
applicable.
III. Congressional Review Act
In accordance with the Congressional
Review Act, the NRC has determined
that this action is not a major rule and
has verified this determination with the
Office of Information and Regulatory
Affairs of the Office of Management and
Budget.
Dated at Rockville, Maryland, this 28th day
of January 2014.
For the Nuclear Regulatory Commission.
Joseph Colaccino,
Chief, Policy Branch, Division of Advanced
Reactors and Rulemaking, Office of New
Reactors.
[FR Doc. 2014–02317 Filed 2–3–14; 8:45 am]
BILLING CODE 7590–01–P
PO 00000
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Sfmt 4703
SECURITIES AND EXCHANGE
COMMISSION
Proposed Collection; Comment
Request
Upon Written Request, Copies Available
From: Securities and Exchange
Commission, Office of Investor
Education and Advocacy,
Washington, DC 20549–0213.
Extension:
Rule 203A–2(e), OMB Control No. 3235–
0559, SEC File No. 270–501.
Notice is hereby given that, pursuant
to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et seq.) (‘‘PRA’’), the
Securities and Exchange Commission
(‘‘Commission’’) is soliciting comments
on the collections of information
summarized below. The Commission
plans to submit this existing collection
of information to the Office of
Management and Budget for extension
and approval.
Rule 203A–2(e),1 which is entitled
‘‘Internet Investment Advisers,’’
exempts from the prohibition on
Commission registration an Internet
investment adviser who provides
investment advice to all of its clients
exclusively through computer softwarebased models or applications, termed
under the rule as ‘‘interactive Web
sites.’’ 2 These advisers generally would
not meet the statutory thresholds
currently set out in section 203A of the
Advisers Act 3—they do not manage $25
million or more in assets and do not
advise registered investment companies,
or they manage between $25 million
and $100 million in assets, do not
advise registered investment companies
or business development companies,
and are required to be registered as
investment advisers with the states in
which they maintain their principal
offices and places of business and are
subject to examination as an adviser by
such states.4 Eligibility under rule
203A–2(e) is conditioned on an adviser
maintaining in an easily accessible
place, for a period of not less than five
years from the filing of Form ADV,5 a
1 17
CFR 275.203A–2(e).
in rule 203A–2(e) is a limited
exception to the interactive Web site requirement
which allows these advisers to provide investment
advice to fewer than 15 clients through other means
on an annual basis. 17 CFR 275.203A–2(e)(1)(i). The
rule also precludes advisers in a control
relationship with an SEC-registered Internet adviser
from registering with the Commission under the
common control exemption provided by rule 203A–
2(b) (17 CFR 275.203A–2(b)). 17 CFR 275.203A–
2(e)(1)(iii).
3 15 U.S.C. 80b–3a(a).
4 Id.
5 The five-year record retention period is a similar
recordkeeping retention period as imposed on all
2 Included
E:\FR\FM\04FEN1.SGM
04FEN1
Agencies
[Federal Register Volume 79, Number 23 (Tuesday, February 4, 2014)]
[Notices]
[Pages 6657-6658]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-02317]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2012-0268]
Introduction--Part 2, Standard Review Plan for the Review of
Safety Analysis Reports for Nuclear Power Plants: Light-Water Small
Modular Reactor Edition
AGENCY: Nuclear Regulatory Commission.
ACTION: Standard review plan section; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing a
final revision to the following section of NUREG-0800, ``Standard
Review Plan for the Review of Safety Analysis Reports for Nuclear Power
Plants: LWR Edition.'' The final revision is the Standard Review Plan
(SRP), ``Introduction--Part 2, Standard Review Plan for the Review of
Safety Analysis Reports for Nuclear Power Plants: Light-Water Small
Modular Reactor Edition.''
DATES: The effective date of this SRP update is March 6, 2014.
ADDRESSES: Please refer to Docket ID NRC-2012-0268 when contacting the
NRC about the availability of information regarding this document. You
may access publicly-available information related to this action by the
following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0268. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly-available documents online in the NRC
Library at https://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to pdr.resource@nrc.gov. The final revision for
``Introduction--Part 2, Standard Review Plan for the Review of Safety
Analysis Reports for Nuclear Power Plants: Light-Water Small Modular
Reactor Edition'' is available in ADAMS under Accession No.
ML13207A315.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
The NRC posts its issued staff guidance on the NRC's
external Web page at https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/.
FOR FURTHER INFORMATION CONTACT: Jonathan DeGange, Office of New
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-6992 or email:
mailto:Jonathan.DeGange@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
On January 22, 2013 (78 FR 4477), the NRC published for public
comment the initial issuance of ``Introduction--Part 2, Standard Review
Plan for the Review of Safety Analysis Reports for Nuclear Power
Plants: Integral Pressurized Water Reactor (iPWR) Edition.''
[[Page 6658]]
Comment submissions were received on the proposed revision (ADAMS
Accession No. ML12142A237).
The NRC staff made several changes to the proposed revision after
consideration of the comments. The scope of use of the new introduction
has been expanded to include any type of application under Part 52 of
Title 10 of the Code of Federal Regulations (10 CFR): early site
permits (ESPs), design certifications (DCs), standard design approvals
(SDAs), combined licenses (COLs), or manufacturing licenses (MLs).
Additionally, throughout the document, the use of the term ``iPWR''
(integral pressurized water reactor) has been replaced by ``SMR''
(small modular reactor) for consistency. Finally, the historical
summary paragraph related to SECY-11-0156 was removed as it did not
directly apply to the guidance in the new part of the introduction.
A summary of the public comments and the NRC staff's disposition of
the comments are available in a separate document, Response to Public
Comments on Draft SRP, ``Introduction--Part 2'' (ADAMS Accession No.
ML13207A309). The ADAMS Accession Number for the Nuclear Energy
Institute letter and comments is ML13091A017.
II. Backfitting and Issue Finality
Issuance of this final SRP section does not constitute backfitting
as defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise
inconsistent with the issue finality provisions in 10 CFR part 52. The
NRC staff's position is based upon the following considerations:
1. The SRP positions do not constitute backfitting, inasmuch as the
SRP is internal guidance directed at the NRC staff with respect to
their regulatory responsibilities.
The SRP provides guidance to the staff on how to review an
application for NRC regulatory approval in the form of licensing.
Changes in internal staff guidance are not matters for which either
nuclear power plant applicants or licensees are protected under either
the Backfit Rule or the issue finality provisions of 10 CFR part 52.
2. Backfitting and issue finality--with certain exceptions
discussed below--do not protect current or future applicants.
Applicants and potential applicants are not, with certain
exceptions, protected by either the Backfit Rule or any issue finality
provisions under 10 CFR part 52. This is because neither the Backfit
Rule nor the issue finality provisions were intended to apply to every
NRC action which substantially changes the expectations of current and
future applicants.
The exceptions to the general principle are applicable whenever an
applicant references a 10 CFR part 52 license (e.g., an early site
permit) and/or NRC regulatory approval (e.g., a design certification
rule) with specified issue finality provisions. The staff does not
currently intend to impose the positions represented in this SRP
section in a manner that is inconsistent with any issue finality
provisions of 10 CFR part 52. If in the future the NRC staff does
indeed intend to impose positions inconsistent with these issue
finality provisions, the NRC staff must address the regulatory criteria
for avoiding issue finality.
3. The NRC staff has no intention to impose the SRP positions on
existing nuclear power plant licenses or regulatory approvals either
now or in the future (absent a voluntary request for change from the
licensee, holder of a regulatory approval, or a design certification
applicant).
The staff does not intend to impose or apply the positions
described in the SRP section to existing (already issued) licenses
(e.g., operating licenses and combined licenses) and regulatory
approvals--in this case, design certifications. Hence, the issuance of
this SRP guidance even if considered guidance which is within the
purview of the issue finality provisions in 10 CFR part 52--need not be
evaluated as if it were a backfit or as being inconsistent with issue
finality provisions. If, in the future, the staff seeks to impose a
position in the SRP on holders of already issued licenses in a manner
which does not provide issue finality as described in the applicable
issue finality provision, then the staff must make the showing as set
forth in the Backfit Rule, or address the criteria for avoiding issue
finality as described applicable issue finality provision, as
applicable.
III. Congressional Review Act
In accordance with the Congressional Review Act, the NRC has
determined that this action is not a major rule and has verified this
determination with the Office of Information and Regulatory Affairs of
the Office of Management and Budget.
Dated at Rockville, Maryland, this 28th day of January 2014.
For the Nuclear Regulatory Commission.
Joseph Colaccino,
Chief, Policy Branch, Division of Advanced Reactors and Rulemaking,
Office of New Reactors.
[FR Doc. 2014-02317 Filed 2-3-14; 8:45 am]
BILLING CODE 7590-01-P