Draft Regulatory Guide: Issuance, Availability, 74764-74765 [E8-29099]
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Federal Register / Vol. 73, No. 237 / Tuesday, December 9, 2008 / Notices
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part 20 for unrestricted release. The
Licensee’s final status survey results
were below these DCGLs and are in
compliance with the As Low As
Reasonably Achievable (ALARA)
requirement of 10 CFR 20.1402. The
NRC thus finds that the Licensee’s final
status survey results are acceptable.
Based on its review, the staff has
determined that the affected
environment and any environmental
impacts associated with the proposed
action are bounded by the impacts
evaluated by the ‘‘Generic
Environmental Impact Statement in
Support of Rulemaking on Radiological
Criteria for License Termination of NRCLicensed Nuclear Facilities’’ (NUREG–
1496) Volumes 1–3 (ML042310492,
ML042320379, and ML042330385). The
staff finds there were no significant
environmental impacts from the use of
radioactive material at the Facility. The
NRC staff reviewed the docket file
records and the final status survey
report to identify any non-radiological
hazards that may have impacted the
environment surrounding the Facility.
No such hazards or impacts to the
environment were identified. The NRC
has identified no other radiological or
non-radiological activities in the area
that could result in cumulative
environmental impacts.
The NRC staff finds that the proposed
release of the Facility for unrestricted
use and the termination of the NRC
materials license is in compliance with
10 CFR 20.1402. Based on its review,
the staff considered the impact of the
residual radioactivity at the Facility and
concluded that the proposed action will
not have a significant effect on the
quality of the human environment.
Environmental Impacts of the
Alternatives to the Proposed Action
Due to the largely administrative
nature of the proposed action, its
environmental impacts are small.
Therefore, the only alternative the staff
considered is the no-action alternative,
under which the staff would leave
things as they are by simply denying the
amendment request. This no-action
alternative is not feasible because it
conflicts with 10 CFR 30.36(d),
requiring that decommissioning of
byproduct material facilities be
completed and approved by the NRC
after licensed activities cease. The
NRC’s analysis of the Licensee’s final
status survey data confirmed that the
Facility meets the requirements of 10
CFR 20.1402 for unrestricted release and
for license termination. Additionally,
denying the amendment request would
result in no change in current
environmental impacts. The
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17:00 Dec 08, 2008
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environmental impacts of the proposed
action and the no-action alternative are
therefore similar, and the no-action
alternative is accordingly not further
considered.
Conclusion
The NRC staff has concluded that the
proposed action is consistent with the
NRC’s unrestricted release criteria
specified in 10 CFR 20.1402. Because
the proposed action will not
significantly impact the quality of the
human environment, the NRC staff
concludes that the proposed action is
the preferred alternative.
Agencies and Persons Consulted
NRC provided a draft of this
Environmental Assessment to the State
of Connecticut Department of
Environmental Protection (DEP) for
review on October 9, 2008. On
November 6, 2008, DEP responded by email. The State agreed with the
conclusions of the EA, and otherwise
had no comments.
The NRC staff has determined that the
proposed action is of a procedural
nature, and will not affect listed species
or critical habitat. Therefore, no further
consultation is required under Section 7
of the Endangered Species Act. The
NRC staff has also determined that the
proposed action is not the type of
activity that has the potential to cause
effects on historic properties. Therefore,
no further consultation is required
under Section 106 of the National
Historic Preservation Act.
III. Finding of No Significant Impact
The NRC staff has prepared this EA in
support of the proposed action. On the
basis of this EA, the NRC finds that
there are no significant environmental
impacts from the proposed action, and
that preparation of an environmental
impact statement is not warranted.
Accordingly, the NRC has determined
that a Finding of No Significant Impact
is appropriate.
IV. Further Information
Documents related to this action,
including the application for license
amendment and supporting
documentation, are available
electronically at the NRC(s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this site,
you can access the NRC’s Agencywide
Document Access and Management
System (ADAMS), which provides text
and image files of NRC’s public
documents. The documents related to
this action are listed below, along with
their ADAMS accession numbers.
PO 00000
Frm 00082
Fmt 4703
Sfmt 4703
1. Letter dated September 1, 2008,
with ‘‘Radiological Assessment Report,
Neurogen Corporation, Northeast
Industrial Road, Branford, CT 06504,’’
dated August 26, 2008;
2. NUREG–1757, ‘‘Consolidated
NMSS Decommissioning Guidance;’’
3. Title 10, Code of Federal
Regulations, Part 20, Subpart E,
‘‘Radiological Criteria for License
Termination;’’
4. Title 10, Code of Federal
Regulations, Part 51, ‘‘Environmental
Protection Regulations for Domestic
Licensing and Related Regulatory
Functions;’’ and
5. NUREG–1496, ‘‘Generic
Environmental Impact Statement in
Support of Rulemaking on Radiological
Criteria for License Termination of NRCLicensed Nuclear Facilities.’’
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.
These documents may also be viewed
electronically on the public computers
located at the NRC’s PDR, O 1 F21, One
White Flint North, 11555 Rockville
Pike, Rockville, MD 20852. The PDR
reproduction contractor will copy
documents for a fee.
Dated at 475 Allendale Road, King of
Prussia, Pennsylvania this 2nd day of
December 2008.
For the Nuclear Regulatory Commission.
James Dwyer,
Chief, Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region I.
[FR Doc. E8–29083 Filed 12–8–08; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Draft Regulatory Guide: Issuance,
Availability
AGENCY: Nuclear Regulatory
Commission.
ACTION: Notice of Issuance and
Availability of Draft Regulatory Guide,
DG–1203.
FOR FURTHER INFORMATION CONTACT:
Syed K. Shaukat, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, Telephone: (301) 251–
7646; e-mail to Syed.Shaukat@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) has issued for public
comment a draft guide in the agency’s
‘‘Regulatory Guide’’ series. This series
E:\FR\FM\09DEN1.SGM
09DEN1
Federal Register / Vol. 73, No. 237 / Tuesday, December 9, 2008 / Notices
pwalker on PROD1PC71 with NOTICES
was 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.
The draft regulatory guide, entitled,
‘‘Containment Performance for Pressure
Loads,’’ is temporarily identified by its
task number, DG–1203, which should be
mentioned in all related
correspondence. This guide describes
methods that the staff of the NRC
considers acceptable for demonstrating
containment performance in nuclear
power plants, in accordance with
regulatory requirements and
Commission’s performance goals for
pressure loadings of containment
structures. To meet these objectives, the
NRC has developed formal regulatory
requirements and has established
several performance goals related to
evaluating the maximum internal
pressure capacity.
II. Further Information
The NRC staff is soliciting comments
on DG–1203. Comments may be
accompanied by relevant information or
supporting data, and should mention
DG–1203 in the subject line. Comments
submitted in writing or in electronic
form will be made available to the
public in their entirety through the
NRC’s Agencywide Documents Access
and Management System (ADAMS).
Personal information will not be
removed from your comments. You may
submit comments by any of the
following methods:
1. Mail comments to: Rulemaking,
Directives, and Editing Branch, Office of
Administration, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
2. E-mail comments to:
nrcrep.resource@nrc.gov.
3. 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.
4. 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 DG–1203 may be directed to Syed
K. Shaukat at (301) 251–7646 or by
e-mail to Syed.Shaukat@nrc.gov.
Comments would be most helpful if
received by February 9, 2009.
VerDate Aug<31>2005
17:00 Dec 08, 2008
Jkt 217001
Comments received after that date will
be considered if it is practical to do so,
but the NRC is able to ensure
consideration only for comments
received on or before February 9, 2009.
Although a time limit is given,
comments and suggestions in
connection with items for inclusion in
guides currently being developed or
improvements in all published guides
are encouraged at any time.
Electronic copies of DG–1203 are
available through the NRC’s public Web
site under Draft Regulatory Guides in
the ‘‘Regulatory Guides’’ collection of
the NRC’s Electronic Reading Room at
https://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also
available in ADAMS (https://
www.nrc.gov/reading-rm/adams.html),
under Accession No. ML082050539.
In addition, regulatory guides are
available for inspection at the NRC’s
Public Document Room (PDR), which is
located at 11555 Rockville Pike,
Rockville, Maryland. 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.resource@nrc.gov.
Regulatory guides are not
copyrighted, and Commission approval
is not required to reproduce them.
Dated at Rockville, Maryland, this 1st day
of December 2008.
For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch,
Division of Engineering, Office of Nuclear
Regulatory Research.
[FR Doc. E8–29099 Filed 12–8–08; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Draft Regulatory Guide: Issuance,
Availability
AGENCY: Nuclear Regulatory
Commission.
ACTION: Notice of Issuance and
Availability of Draft Regulatory Guide
(DG)–1189.
FOR FURTHER INFORMATION CONTACT: John
Voglewede, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone: (301) 251–7555 or email to John.Voglewede@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) has issued for public
comment a draft guide in the agency’s
PO 00000
Frm 00083
Fmt 4703
Sfmt 4703
74765
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.
The draft regulatory guide (DG),
entitled, ‘‘An Acceptable Model and
Related Statistical Methods for the
Analysis of Fuel Densification,’’ is
temporarily identified by its task
number, DG–1189, which should be
mentioned in all related
correspondence. DG–1189 is proposed
Revision 2 of Regulatory Guide 1.126.
This guide describes an analytical
model and related assumptions and
procedures that the staff of the NRC
considers acceptable for predicting the
effects of fuel densification in lightwater-cooled nuclear power reactors. To
meet these objectives, the guide
describes statistical methods related to
product sampling that will ensure that
this and other approved analytical
models will adequately describe the
effects of densification for each initial
core and reload fuel quantity produced.
II. Further Information
The NRC staff is soliciting comments
on DG–1189. Comments may be
accompanied by relevant information or
supporting data and should mention
DG–1189 in the subject line. Comments
submitted in writing or in electronic
form will be made available to the
public in their entirety through the
NRC’s Agencywide Documents Access
and Management System (ADAMS).
Personal information will not be
removed from your comments. You may
submit comments by any of the
following methods:
1. Mail comments to: Rulemaking,
Directives, and Editing Branch, Office of
Administration, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
2. E-mail comments to:
nrcrep.resource@nrc.gov.
3. 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.
4. 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 DG–1189 may be directed to the
E:\FR\FM\09DEN1.SGM
09DEN1
Agencies
[Federal Register Volume 73, Number 237 (Tuesday, December 9, 2008)]
[Notices]
[Pages 74764-74765]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-29099]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Draft Regulatory Guide: Issuance, Availability
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of Issuance and Availability of Draft Regulatory Guide,
DG-1203.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Syed K. Shaukat, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, Telephone: (301) 251-
7646; e-mail to Syed.Shaukat@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC) has issued for public
comment a draft guide in the agency's ``Regulatory Guide'' series. This
series
[[Page 74765]]
was 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.
The draft regulatory guide, entitled, ``Containment Performance for
Pressure Loads,'' is temporarily identified by its task number, DG-
1203, which should be mentioned in all related correspondence. This
guide describes methods that the staff of the NRC considers acceptable
for demonstrating containment performance in nuclear power plants, in
accordance with regulatory requirements and Commission's performance
goals for pressure loadings of containment structures. To meet these
objectives, the NRC has developed formal regulatory requirements and
has established several performance goals related to evaluating the
maximum internal pressure capacity.
II. Further Information
The NRC staff is soliciting comments on DG-1203. Comments may be
accompanied by relevant information or supporting data, and should
mention DG-1203 in the subject line. Comments submitted in writing or
in electronic form will be made available to the public in their
entirety through the NRC's Agencywide Documents Access and Management
System (ADAMS). Personal information will not be removed from your
comments. You may submit comments by any of the following methods:
1. Mail comments to: Rulemaking, Directives, and Editing Branch,
Office of Administration, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001.
2. E-mail comments to: nrcrep.resource@nrc.gov.
3. 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.
4. 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 DG-1203 may be directed to
Syed K. Shaukat at (301) 251-7646 or by e-mail to Syed.Shaukat@nrc.gov.
Comments would be most helpful if received by February 9, 2009.
Comments received after that date will be considered if it is practical
to do so, but the NRC is able to ensure consideration only for comments
received on or before February 9, 2009. Although a time limit is given,
comments and suggestions in connection with items for inclusion in
guides currently being developed or improvements in all published
guides are encouraged at any time.
Electronic copies of DG-1203 are available through the NRC's public
Web site under Draft Regulatory Guides in the ``Regulatory Guides''
collection of the NRC's Electronic Reading Room at https://www.nrc.gov/
reading-rm/doc-collections/. Electronic copies are also available in
ADAMS (https://www.nrc.gov/reading-rm/adams.html), under Accession No.
ML082050539.
In addition, regulatory guides are available for inspection at the
NRC's Public Document Room (PDR), which is located at 11555 Rockville
Pike, Rockville, Maryland. 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.resource@nrc.gov.
Regulatory guides are not copyrighted, and Commission approval is
not required to reproduce them.
Dated at Rockville, Maryland, this 1st day of December 2008.
For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch, Division of Engineering,
Office of Nuclear Regulatory Research.
[FR Doc. E8-29099 Filed 12-8-08; 8:45 am]
BILLING CODE 7590-01-P