Notice of Renewal of Facility Operating License No. R-110; Idaho State University AGN-201M Research Reactor, 54529-54530 [E6-15310]
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Federal Register / Vol. 71, No. 179 / Friday, September 15, 2006 / Notices
the Atomic Energy Act of 1954, as
amended, and the Commission’s
regulations in 10 CFR 2.202, 10 CFR
50.5, and 10 CFR 150.20, it is hereby
ordered, effective immediately, that:
1. Mr. Nicholas A. Chaimov is
prohibited for three years from the date
of this Order from engaging in NRClicensed activities. NRC-licensed
activities are those activities that are
conducted pursuant to a specific or
general license issued by the NRC,
including, but not limited to, those
activities of Agreement State licensees
conducted pursuant to the authority
granted by 10 CFR 150.20.
2. If Mr. Nicholas A. Chaimov is
currently involved with another
licensee in NRC-licensed activities, he
must immediately cease those activities,
and inform the NRC of the name,
address, and telephone number of that
licensee, and provide a copy of this
Order to that licensee.
The Director, Office of Enforcement,
may, in writing, relax or rescind any of
the above conditions upon
demonstration by Mr. Nicholas A.
Chaimov of good cause.
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V
In accordance with 10 CFR 2.202, Mr.
Nicholas A. Chaimov must, and any
other person adversely affected by this
Order may, submit an answer to this
Order, and may request a hearing on
this Order, within 20 days of the date of
this Order. Where good cause is shown,
consideration will be given to extending
the time to request a hearing. A request
for extension of time must be made in
writing to the Director, Office of
Enforcement, U.S. Nuclear Regulatory
Commission, Washington, DC 20555,
and include a statement of good cause
for the extension. The answer may
consent to this Order. Unless the answer
consents to this Order, the answer shall,
in writing and under oath or
affirmation, specifically admit or deny
each allegation or charge made in this
Order and shall set forth the matters of
fact and law on which Mr. Nicholas A.
Chaimov or other person adversely
affected relies and the reasons as to why
the Order should not have been issued.
Any answer or request for a hearing
shall be submitted to the Secretary, U.S.
Nuclear Regulatory Commission, Attn:
Rulemakings and Adjudications Staff,
Washington, DC 20555. Copies also
shall be sent to the Director, Office of
Enforcement, U.S. Nuclear Regulatory
Commission, Washington, DC 20555,
the Assistant General Counsel for
Materials Litigation and Enforcement at
the same address, and Mr. Nicholas A.
Chaimov, if the answer or hearing
request is by a person other than Mr.
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Nicholas A. Chaimov. Because of
continuing disruptions in delivery of
mail to United States Government
offices, it is requested that answers and
requests for hearing be transmitted to
the Secretary of the Commission either
by means of facsimile transmission to
301–415–1101 or by e-mail to
hearingdocket@nrc.gov and also to the
Office of the General Counsel either by
means of facsimile transmission to 301–
415–3725 or by e-mail to
OGCMailCenter@nrc.gov. If a person
other than the licensee requests a
hearing, that person shall set forth with
particularity the manner in which his
interest is adversely affected by this
Order and shall address the criteria set
forth in 10 CFR 2.309(d).
If a hearing is requested by Mr.
Nicholas A. Chaimov or a person whose
interest is adversely affected, the
Commission will issue an Order
designating the time and place of any
hearing. If a hearing is held, the issue to
be considered at such hearing shall be
whether this Order should be sustained.
Pursuant to 10 CFR 2.202(c)(2)(i), Mr.
Nicholas A. Chaimov may, in addition
to demanding a hearing, at the time the
answer is filed or sooner, move the
Presiding Officer to set aside the
immediate effectiveness of the Order on
the ground that the Order, including the
need for immediate effectiveness, is not
based on adequate evidence but on mere
suspicion, unfounded allegations, or
error.
In the absence of any request for
hearing, or written approval of an
extension of time in which to request a
hearing, the provisions specified in
Section IV above shall be final 20 days
from the date of this Order without
further order or proceedings. If an
extension of time for requesting a
hearing has been approved, the
provisions specified in Section IV shall
be final when the extension expires if a
hearing request has not been received.
An answer or a request for hearing shall
not stay the immediate effectiveness of
this order.
Dated this 12th day of September 2006.
For the Nuclear Regulatory Commission.
Martin J. Virgilio,
Deputy Executive Director for Materials,
Research, State, and Compliance Programs,
Office of the Executive Director for
Operations.
[FR Doc. E6–15309 Filed 9–14–06; 8:45 am]
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54529
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–284]
Notice of Renewal of Facility Operating
License No. R–110; Idaho State
University AGN–201M Research
Reactor
The U.S. Nuclear Regulatory
Commission (the Commission) has
issued Amendment No. 6 to Facility
Operating License No. R–110 for the
Idaho State University (the licensee),
which renews the license for operation
of the Idaho State University AGN–
201M Research Reactor Facility located
at the Idaho State University in
Pocatello, Idaho.
The facility is a research reactor that
has been operating at a power level not
in excess of 5 watts (thermal). The
renewed Facility Operating License No.
R–110 will expire twenty years from its
date of issuance.
The amended license complies with
the standards and requirements of the
Atomic Energy Act of 1954, as amended
(the Act), and the Commission’s rules
and regulations. The Commission has
made appropriate findings as required
by the Act and the Commission’s
regulations in 10 CFR Chapter I. Those
findings are set forth in the license
amendment. Opportunity for hearing
was afforded in the notice of the
proposed issuance of this renewal in the
Federal Register on January 8, 1996 (61
FR 563). No request for a hearing or
petition for leave to intervene was filed
following notice of the proposed action.
Continued operation of the reactor
will not require alteration of buildings
or structures, will not lead to significant
changes in effluents released from the
facility to the environment, will not
increase the probability or consequences
of accidents, and will not involve any
unresolved issues concerning
alternative uses of available resources.
Based on the foregoing and on the
Environmental Assessment, the
Commission concludes that renewal of
the license will not result in any
significant environmental impacts.
The Commission has prepared a
‘‘Safety Evaluation Report Related to the
Renewal of the Operating License for
the Research Reactor at Idaho State
University’’ for the renewal of Facility
Operating License No. R–110 and has,
based on that evaluation, concluded that
the facility can continue to be operated
by the licensee without endangering the
health and safety of the public.
The Commission also prepared an
Environmental Assessment which was
published in the Federal Register on
April 9, 2004, (69 FR 18988) for the
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Federal Register / Vol. 71, No. 179 / Friday, September 15, 2006 / Notices
renewal of Facility Operating License
No. R–110 and has concluded that this
action will not have a significant effect
on the quality of the human
environment.
For further details with respect to this
action, see: (1) The application for
amendment dated November 21, 1995,
as supplemented on January 31, 2003
and July 10, 2003, (2) Amendment No.
6 to Facility Operating License No. R–
110; (3) the related Safety Evaluation
Report and (4) the Environmental
Assessment dated March 30, 2004.
Documents may be examined, and/or
copied for a fee, at the NRC’s Public
Document Room, located at One White
Flint North, 11555 Rockville Pike (first
floor), Rockville, Maryland. The NRC
maintains an Agencywide Documents
Access and Management System
(ADAMS), which provides text and
image files of NRC’s public documents.
Documents related to this license
renewal dated on or after November 24,
1999, may be accessed through the
NRC’s Public Electronic Reading Room
on the Internet at https://www.nrc.gov. If
you do not have access to ADAMS or if
there are problems in accessing the
documents located in ADAMS, contact
the NRC Public Document Room (PDR)
Reference staff at 1–800–397–4209, 301–
415–4737 or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 14th day
of August 2006.
For the U.S. Nuclear Regulatory
Commission.
Brian E. Thomas,
Chief, Research and Test Reactors Branch,
Division of Policy and Rulemaking, Office
of Nuclear Reactor Regulation.
[FR Doc. E6–15310 Filed 9–14–06; 8:45 am]
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NUCLEAR REGULATORY
COMMISSION
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Draft Regulatory Guide and Associated
Standard Review Plan: Issuance,
Availability
The U.S. Nuclear Regulatory
Commission (NRC) has issued for public
comment a draft proposed revision of 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 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.
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This draft Revision 1 of Regulatory
Guide 1.200, ‘‘An Approach for
Determining the Technical Adequacy of
Probabilistic Risk Assessment Results
for Risk-Informed Activities,’’ is
temporarily identified as Draft
Regulatory Guide DG–1161, which
should be mentioned in all related
correspondence. Like its predecessors,
this proposed revision 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, Draft Regulatory Guide
DG–1161 provides guidance in four
areas:
(1) A minimal set of functional
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.
Draft Regulatory Guide DG–1161 is
also intended to be consistent with the
more detailed, guidance in Regulatory
Guide 1.174, ‘‘An Approach for Using
Probabilistic Risk Assessment in RiskInformed Decisions on Plant-Specific
Changes to the Licensing Basis,’’ which
the NRC issued in November 2002. In
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addition, Draft Regulatory Guide DG–
1161 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–Sa–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,’’
Addendum B to ASME RA–S–2002,
dated December 30, 2005.
• NEI–00–02, ‘‘Probabilistic Risk
Assessment Peer Review Process
Guidance,’’ Revision A3, dated March
20, 2000, with its supplemental
guidance on industry self-assessment,
dated August 16, 2002, and Revision 1,
dated May 19, 2006.
• NEI–05–04, ‘‘Process for Performing
Follow-on PRA Peer Reviews Using the
ASME PRA Standard,’’ dated January
2005.
When used in support of an
application, this regulatory guide will
obviate the need for an in-depth review
of the base PRA by NRC reviewers,
allowing them to focus their review on
key assumptions and areas identified by
peer reviewers as being of concern and
relevant to the application.
Consequently, this guide will provide
for a more focused and consistent
review process. In this regulatory guide,
as in RG 1.174, the quality of a PRA
analysis used to support an application
is measured in terms of its
appropriateness with respect to scope,
level of detail, and technical
acceptability.
This regulatory guide was issued for
trial use in February of 2004, and five
trial applications were conducted. This
revision incorporates lessons learned
from those pilot applications. In
addition, the appendices to this
regulatory guide have been revised to
address the changes made in the
professional society PRA standards and
industry PRA guidance documents.
To accompany Draft Regulatory Guide
DG–1161, the NRC is issuing proposed
Revision 2 of Section 19.1,
‘‘Determining the Technical Adequacy
of Probabilistic Risk Assessment Results
for Risk-Informed Activities,’’ of
NUREG–0800, ‘‘Standard Review Plan
for the Review of Safety Analysis
Reports for Nuclear Power Plants’’
(SRP). This SRP complements Draft
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[Federal Register Volume 71, Number 179 (Friday, September 15, 2006)]
[Notices]
[Pages 54529-54530]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-15310]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-284]
Notice of Renewal of Facility Operating License No. R-110; Idaho
State University AGN-201M Research Reactor
The U.S. Nuclear Regulatory Commission (the Commission) has issued
Amendment No. 6 to Facility Operating License No. R-110 for the Idaho
State University (the licensee), which renews the license for operation
of the Idaho State University AGN-201M Research Reactor Facility
located at the Idaho State University in Pocatello, Idaho.
The facility is a research reactor that has been operating at a
power level not in excess of 5 watts (thermal). The renewed Facility
Operating License No. R-110 will expire twenty years from its date of
issuance.
The amended license complies with the standards and requirements of
the Atomic Energy Act of 1954, as amended (the Act), and the
Commission's rules and regulations. The Commission has made appropriate
findings as required by the Act and the Commission's regulations in 10
CFR Chapter I. Those findings are set forth in the license amendment.
Opportunity for hearing was afforded in the notice of the proposed
issuance of this renewal in the Federal Register on January 8, 1996 (61
FR 563). No request for a hearing or petition for leave to intervene
was filed following notice of the proposed action.
Continued operation of the reactor will not require alteration of
buildings or structures, will not lead to significant changes in
effluents released from the facility to the environment, will not
increase the probability or consequences of accidents, and will not
involve any unresolved issues concerning alternative uses of available
resources. Based on the foregoing and on the Environmental Assessment,
the Commission concludes that renewal of the license will not result in
any significant environmental impacts.
The Commission has prepared a ``Safety Evaluation Report Related to
the Renewal of the Operating License for the Research Reactor at Idaho
State University'' for the renewal of Facility Operating License No. R-
110 and has, based on that evaluation, concluded that the facility can
continue to be operated by the licensee without endangering the health
and safety of the public.
The Commission also prepared an Environmental Assessment which was
published in the Federal Register on April 9, 2004, (69 FR 18988) for
the
[[Page 54530]]
renewal of Facility Operating License No. R-110 and has concluded that
this action will not have a significant effect on the quality of the
human environment.
For further details with respect to this action, see: (1) The
application for amendment dated November 21, 1995, as supplemented on
January 31, 2003 and July 10, 2003, (2) Amendment No. 6 to Facility
Operating License No. R-110; (3) the related Safety Evaluation Report
and (4) the Environmental Assessment dated March 30, 2004. Documents
may be examined, and/or copied for a fee, at the NRC's Public Document
Room, located at One White Flint North, 11555 Rockville Pike (first
floor), Rockville, Maryland. The NRC maintains an Agencywide Documents
Access and Management System (ADAMS), which provides text and image
files of NRC's public documents. Documents related to this license
renewal dated on or after November 24, 1999, may be accessed through
the NRC's Public Electronic Reading Room on the Internet at https://
www.nrc.gov. If you do not have access to ADAMS or if there are
problems in accessing the documents located in ADAMS, contact the NRC
Public Document Room (PDR) Reference staff at 1-800-397-4209, 301-415-
4737 or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 14th day of August 2006.
For the U.S. Nuclear Regulatory Commission.
Brian E. Thomas,
Chief, Research and Test Reactors Branch, Division of Policy and
Rulemaking, Office of Nuclear Reactor Regulation.
[FR Doc. E6-15310 Filed 9-14-06; 8:45 am]
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