Calvert Cliffs Independent Spent Fuel Storage Installation Issuance of Environmental Assessment and Finding of No Significant Impact Regarding a License Amendment, 53812-53813 [05-17971]
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Federal Register / Vol. 70, No. 175 / Monday, September 12, 2005 / Notices
We will not officially file the plat
until the day after we have accepted or
dismissed all protests and they have
become final, including decisions on
appeals.
Dated: September 1, 2005.
Stephen D. Douglas,
Chief Cadastral Surveyor.
[FR Doc. 05–17975 Filed 9–9–05; 8:45 am]
BILLING CODE 4310–GJ–P
DEPARTMENT OF THE INTERIOR
Bureau of Land Management
[ES–960–1910–BJ–4789] ES–053725, Group
No. 35, Missouri
Eastern States: Filing of Plat of Survey
Bureau of Land Management.
Notice of Filing of Plat of
Survey; Missouri.
AGENCY:
ACTION:
SUMMARY: The Bureau of Land
Management (BLM) will file the plat of
survey of the lands described below in
the BLM-Eastern States, Springfield,
Virginia, 30 calendar days from the date
of publication in the Federal Register.
FOR FURTHER INFORMATION CONTACT:
Bureau of Land Management, 7450
Boston Boulevard, Springfield, Virginia
22153. Attn: Cadastral Survey.
SUPPLEMENTARY INFORMATION: This
survey was requested by the U.S. Army
Corps of Engineers.
The lands we surveyed are:
Fifth Principal Meridian, Missouri
T. 48 N., Rs. 4 and 5 E.
The plat of survey represents the
survey of a portion of the Lock and Dam
No. 26 acquisition boundary on an
island in the Mississippi River in
Township 48 North, Range 4 and 5 East,
of the Fifth Principal Meridian, in the
State of Missouri, and was accepted
September 2, 2005. We will place a copy
of the plat we described in the open
files. It will be made available to the
public as a matter of information.
Dated: September 2, 2005.
Stephen D. Douglas,
Chief Cadastral Surveyor.
[FR Doc. 05–17973 Filed 9–9–05; 8:45 am]
Board Room, 7th Floor, Room
7074, 1775 Duke Street, Alexandria, VA
22314–3428.
STATUS: Open.
MATTERS TO BE CONSIDERED:
1. Request from a Federal Credit
Union to Convert to a Community
Charter.
2. Proposed Rule: Section 741.6(a) of
NCUA’s Rules and Regulations,
Financial and Statistical and Other
Reports.
3. Final Rule: Part 712 of NCUA’s
Rules and Regulations, Credit Union
Service Organizations.
TIME AND DATE: 9 a.m., Thursday,
September 15, 2005.
PLACE: Board Room, 7th Floor, Room
7047, 1775 Duke Street, Alexandria, VA
22314–3428.
STATUS: Closed.
MATTERS TO BE CONSIDERED:
1. One (1) Insurance Appeal. Closed
pursuant to Exemption (6).
2. Internal Board Procedures and
Technical Corrections. Closed pursuant
to Exemption (2).
RECESS: 9:30 a.m.
FOR FURTHER INFORMATION CONTACT:
Mary Rupp, Secretary of the Board,
Telephone: (703) 518–6304.
PLACE:
Mary Rupp,
Secretary of the Board.
[FR Doc. 05–18173 Filed 9–8–05; 3:39 pm]
BILLING CODE 7535–01–M
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–8]
Calvert Cliffs Independent Spent Fuel
Storage Installation Issuance of
Environmental Assessment and
Finding of No Significant Impact
Regarding a License Amendment
Nuclear Regulatory
Commission (NRC).
ACTION: Issuance of an Environmental
Assessment and Finding of No
Significant Impact.
AGENCY:
FOR FURTHER INFORMATION CONTACT:
NATIONAL CREDIT UNION
ADMINISTRATION
Joseph M. Sebrosky, Senior Project
Manager, Spent Fuel Project Office,
Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555.
Telephone: (301) 415–1132; Fax
number: (301) 415–8555; E-mail:
jms3@nrc.gov.
Notice of Meeting
SUPPLEMENTARY INFORMATION:
BILLING CODE 4310–GJ–P
10 a.m., Thursday,
September 15, 2005.
TIME AND DATE:
VerDate Aug<18>2005
15:25 Sep 09, 2005
Jkt 205001
The U.S.
Nuclear Regulatory Commission (NRC
or the Commission) is considering
issuance of an amendment to Special
PO 00000
Frm 00040
Fmt 4703
Sfmt 4703
Nuclear Materials License No. 2505 that
would incorporate changes to the
updated safety analysis report to alter
the design basis limit for the dry
shielded canister (DSC) internal
pressure from 50 psig to 100 psig.
Calvert Cliffs Nuclear Power Plant, Inc.
(CCNPP) is currently storing spent
nuclear fuel at the Calvert Cliffs
independent spent fuel storage
installation (ISFSI) located in Calvert
County, Maryland.
Environmental Assessment (EA)
Identification of Proposed Action: By
letter dated May 16, 2005, CCNPP
submitted a request to the NRC to
amend license SNM–2505 in order to
incorporate changes to the updated
safety analysis report to alter the design
basis limit for the DSC internal pressure
from 50 psig to 100 psig. The design
basis limit change is being made to
support CCNPP adding the NUHOMS–
32P as an optional design to the existing
NUHOMS–24P design for dry storage of
spent fuel. The NUHOMS–32P design
stores eight more spent fuel assemblies
than the NUHOMS–24P design.
The proposed action before the NRC
is whether to approve the amendment.
Need for the Proposed Action: The
proposed action would allow CCNPP to
optimize its dry spent fuel storage
capacity by upgrading portions of its
ISFSI to use the NUHOMS–32P DSC.
The proposed action would allow
CCNPP to reduce the minimum number
of canister loadings each year from four
(using the NUHOMS–24P design) to
three (with the NUHOMS–32P design).
Environmental Impacts of the
Proposed Action: By letter dated
December 12, 2003, CCNPP submitted a
request to amend license SNM–2505 to
add the NUHOMS–32P as an optional
design to the existing NUHOMS–24P
design for dry storage of spent fuel. An
EA and Finding of No Significant
Impact (FONSI) were published in the
Federal Register on May 24, 2005 (70
FR 29784) for CCNPP’s December 12,
2003, license amendment request which
concluded that adding the NUHOMS–
32P as an optional design to the existing
NUHOMS–24P design for dry storage of
spent nuclear fuel would have no
significant impact on the environment.
The proposed action contained in
CCNPP’s May 16, 2005, request is to
incorporate changes to the updated
safety analysis report to alter the design
basis limit for the DSC internal pressure
from 50 psig to 100 psig. The DSC
provides confinement, an inert
environment, structural support, and
criticality control for 32 pressurized
water reactor fuel assemblies. The DSC
shell is a welded stainless steel pressure
E:\FR\FM\12SEN1.SGM
12SEN1
Federal Register / Vol. 70, No. 175 / Monday, September 12, 2005 / Notices
vessel that includes thick shield plugs at
either end. To support the pressure
increase structural design changes were
made to the DSC to ensure that the
confinement boundary for the spent
nuclear fuel is maintained under the
proposed design pressure limit of 100
psig for all specified normal operation,
off-normal operation, and accident
conditions. The staff has determined
that the proposed action would not
endanger life or property. No effluents
are released from the ISFSI during
operation and the proposed changes
have no impact to DSC loading
activities. Therefore, there is no
significant change in the type or
significant increase in the amounts of
any effluents that may be released
offsite. There is also no significant
increase with regard to individual or
cumulative occupational radiation
exposures because of the proposed
action. There are no significant
radiological environmental impacts
associated with the proposed action
because the NUHOMS–32P DSC
includes design changes to ensure the
confinement boundary for the spent
nuclear fuel is maintained under the
proposed design pressure limit of 100
psig.
The amendment only affects the
requirements associated with the
loading of the casks and does not affect
non-radiological plant effluents or any
other aspects of the environment.
Therefore, there are no significant nonradiological impacts associated with the
proposed action.
Accordingly, the Commission
concludes that there are no significant
environmental impacts associated with
the proposed action.
Alternative to the Proposed Action:
As an alternative to the proposed action,
the staff considered denial of the
amendment request (i.e., the ‘‘noaction’’ alternative). Approval or denial
of the amendment request would result
in minimal change in the environmental
impacts. Therefore, the environmental
impacts of the proposed action and the
alternative action are similar.
Agencies and Persons Consulted: On
August 11, 2005, Richard McLean of the
State of Maryland was contacted
regarding the proposed action and had
no concerns. The NRC staff has
determined that consultation under
Section 7 of the Endangered Species Act
is not required for this specific
amendment and will not affect listed
species or critical habitat. The NRC staff
has also determined that the proposed
action is not a type of activity having
the potential to cause effects on historic
properties. Therefore, no consultation is
VerDate Aug<18>2005
15:25 Sep 09, 2005
Jkt 205001
required under Section 106 of the
National Historic Preservation Act.
Conclusions: The staff has reviewed
the amendment request submitted by
CCNPP and changing the DSC design
basis pressure limit would have no
significant impact on the environment.
Finding of No Significant Impact
The environmental impacts of the
proposed action have been reviewed in
accordance with the requirements set
forth in 10 CFR part 51. Based upon the
foregoing EA, the NRC finds that the
proposed action of approving the
amendment to the license will not
significantly impact the quality of the
human environment. Accordingly, the
NRC has determined that an
environmental impact statement for the
proposed license amendment is not
warranted.
The request for amendment was
docketed under 10 CFR part 72, Docket
72–8. For further details with respect to
this action, see the proposed license
amendment dated May 16, 2005. The
NRC maintains an Agencywide
Documents Access Management System
(ADAMS), which provides text and
image files of NRC’s public documents.
These documents may be accessed
through the NRC’s Public Electronic
Reading Room on the Internet at: http:
//www.nrc.gov/reading-rm/adams.html.
Copies of the referenced documents will
also be available for review at the NRC
Public Document Room (PDR), located
at 11555 Rockville Pike, Rockville, MD,
20852. PDR reference staff can be
contacted at 1–800–397–4209, 301–415–
4737 or by e-mail to pdr@nrc.gov. The
PDR reproduction contractor will copy
documents for a fee.
Dated at Rockville, Maryland, this 31st of
August, 2005.
For the Nuclear Regulatory Commission.
Joseph M. Sebrosky,
Senior Project Manager, Spent Fuel Project
Office, Office of Nuclear Material Safety and
Safeguards.
[FR Doc. 05–17971 Filed 9–9–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–39]
Connecticut Yankee Atomic Power
Company Haddam Neck Plant
Independent Spent Fuel Storage
Installation Environmental Assessment
and Finding of No Significant Impact
The U.S. Nuclear Regulatory
Commission (NRC or Commission) is
considering issuance of an exemption to
PO 00000
Frm 00041
Fmt 4703
Sfmt 4703
53813
Connecticut Yankee Atomic Power
Company (CYAPCO or licensee),
pursuant to 10 CFR 72.7, from the
specific provisions of 10 CFR
72.212(a)(2), 72.212(b)(2)(I),
72.212(b)(7), and 72.214. The licensee is
using the NAC Multi-Purpose Canister
System (NAC–MPC), Certificate of
Compliance (CoC) No. 1025, to store
spent fuel under a general license in an
independent spent fuel storage
installation (ISFSI) associated with the
operation of the Haddam Neck Plant,
located in Middlesex County,
Connecticut. The requested exemption
would allow CYAPCO to deviate from
requirements of the NAC–MPC CoC No.
1025, Amendment No. 4, Appendix A,
Technical Specifications for the NAC–
MPC System, Section A 5.1, Training
Program. Specifically, the exemption
would relieve the licensee from the
requirement to develop training
modules under its Systems Approach to
Training (SAT) that includes
comprehensive instructions for the
operation and maintenance of the ISFSI,
except for the NAC–MPC System.
Environmental Assessment
Identification of the Proposed Action
The proposed action would exempt
CYAPCO from regulatory requirements
to develop certain training. By letter
dated June 1, 2005, the licensee
requested exemptions from certain
regulatory requirements of 10 CFR
72.212(a)(2), 72.212(b)(2)(I),
72.212(b)(7), and 72.214 which require
a general license to store spent fuel in
a NRC-certified spent fuel storage cask
under the terms and conditions set forth
in the CoC. The proposed exemption
would allow the licensee to deviate
from the requirements in CoC No. 1025,
Amendment No. 4, Appendix A,
Technical Specifications for the NAC–
MPC System, Section A 5.1, Training
Program.
CoC No. 1025, Amendment 4,
Appendix A, Technical Specifications
for the NAC–MPC System, Section A
5.1, Training Program, requires that a
training program for the NAC–MPC
System be developed under the general
licensee’s SAT Program. Further, the
training modules must include
comprehensive instructions for the
operation and maintenance of both the
NAC-MPC System and the ISFSI. By
exempting the licensee from the
requirements of 10 CFR 72.212(a)(2),
72.212(b)(2)(I), 72.212(b)(7), and 72.214
for this request, the licensee will not be
required to develop training modules
that include comprehensive instructions
for the operation and maintenance of
the ISFSI.
E:\FR\FM\12SEN1.SGM
12SEN1
]]>Agencies
[Federal Register Volume 70, Number 175 (Monday, September 12, 2005)]
[Notices]
[Pages 53812-53813]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 05-17971]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 72-8]
Calvert Cliffs Independent Spent Fuel Storage Installation
Issuance of Environmental Assessment and Finding of No Significant
Impact Regarding a License Amendment
AGENCY: Nuclear Regulatory Commission (NRC).
ACTION: Issuance of an Environmental Assessment and Finding of No
Significant Impact.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Joseph M. Sebrosky, Senior Project
Manager, Spent Fuel Project Office, Office of Nuclear Material Safety
and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC
20555. Telephone: (301) 415-1132; Fax number: (301) 415-8555; E-mail:
jms3@nrc.gov.
SUPPLEMENTARY INFORMATION: The U.S. Nuclear Regulatory Commission (NRC
or the Commission) is considering issuance of an amendment to Special
Nuclear Materials License No. 2505 that would incorporate changes to
the updated safety analysis report to alter the design basis limit for
the dry shielded canister (DSC) internal pressure from 50 psig to 100
psig. Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP) is currently
storing spent nuclear fuel at the Calvert Cliffs independent spent fuel
storage installation (ISFSI) located in Calvert County, Maryland.
Environmental Assessment (EA)
Identification of Proposed Action: By letter dated May 16, 2005,
CCNPP submitted a request to the NRC to amend license SNM-2505 in order
to incorporate changes to the updated safety analysis report to alter
the design basis limit for the DSC internal pressure from 50 psig to
100 psig. The design basis limit change is being made to support CCNPP
adding the NUHOMS-32P as an optional design to the existing NUHOMS-24P
design for dry storage of spent fuel. The NUHOMS-32P design stores
eight more spent fuel assemblies than the NUHOMS-24P design.
The proposed action before the NRC is whether to approve the
amendment.
Need for the Proposed Action: The proposed action would allow CCNPP
to optimize its dry spent fuel storage capacity by upgrading portions
of its ISFSI to use the NUHOMS-32P DSC. The proposed action would allow
CCNPP to reduce the minimum number of canister loadings each year from
four (using the NUHOMS-24P design) to three (with the NUHOMS-32P
design).
Environmental Impacts of the Proposed Action: By letter dated
December 12, 2003, CCNPP submitted a request to amend license SNM-2505
to add the NUHOMS-32P as an optional design to the existing NUHOMS-24P
design for dry storage of spent fuel. An EA and Finding of No
Significant Impact (FONSI) were published in the Federal Register on
May 24, 2005 (70 FR 29784) for CCNPP's December 12, 2003, license
amendment request which concluded that adding the NUHOMS-32P as an
optional design to the existing NUHOMS-24P design for dry storage of
spent nuclear fuel would have no significant impact on the environment.
The proposed action contained in CCNPP's May 16, 2005, request is
to incorporate changes to the updated safety analysis report to alter
the design basis limit for the DSC internal pressure from 50 psig to
100 psig. The DSC provides confinement, an inert environment,
structural support, and criticality control for 32 pressurized water
reactor fuel assemblies. The DSC shell is a welded stainless steel
pressure
[[Page 53813]]
vessel that includes thick shield plugs at either end. To support the
pressure increase structural design changes were made to the DSC to
ensure that the confinement boundary for the spent nuclear fuel is
maintained under the proposed design pressure limit of 100 psig for all
specified normal operation, off-normal operation, and accident
conditions. The staff has determined that the proposed action would not
endanger life or property. No effluents are released from the ISFSI
during operation and the proposed changes have no impact to DSC loading
activities. Therefore, there is no significant change in the type or
significant increase in the amounts of any effluents that may be
released offsite. There is also no significant increase with regard to
individual or cumulative occupational radiation exposures because of
the proposed action. There are no significant radiological
environmental impacts associated with the proposed action because the
NUHOMS-32P DSC includes design changes to ensure the confinement
boundary for the spent nuclear fuel is maintained under the proposed
design pressure limit of 100 psig.
The amendment only affects the requirements associated with the
loading of the casks and does not affect non-radiological plant
effluents or any other aspects of the environment. Therefore, there are
no significant non-radiological impacts associated with the proposed
action.
Accordingly, the Commission concludes that there are no significant
environmental impacts associated with the proposed action.
Alternative to the Proposed Action: As an alternative to the
proposed action, the staff considered denial of the amendment request
(i.e., the ``no-action'' alternative). Approval or denial of the
amendment request would result in minimal change in the environmental
impacts. Therefore, the environmental impacts of the proposed action
and the alternative action are similar.
Agencies and Persons Consulted: On August 11, 2005, Richard McLean
of the State of Maryland was contacted regarding the proposed action
and had no concerns. The NRC staff has determined that consultation
under Section 7 of the Endangered Species Act is not required for this
specific amendment and will not affect listed species or critical
habitat. The NRC staff has also determined that the proposed action is
not a type of activity having the potential to cause effects on
historic properties. Therefore, no consultation is required under
Section 106 of the National Historic Preservation Act.
Conclusions: The staff has reviewed the amendment request submitted
by CCNPP and changing the DSC design basis pressure limit would have no
significant impact on the environment.
Finding of No Significant Impact
The environmental impacts of the proposed action have been reviewed
in accordance with the requirements set forth in 10 CFR part 51. Based
upon the foregoing EA, the NRC finds that the proposed action of
approving the amendment to the license will not significantly impact
the quality of the human environment. Accordingly, the NRC has
determined that an environmental impact statement for the proposed
license amendment is not warranted.
The request for amendment was docketed under 10 CFR part 72, Docket
72-8. For further details with respect to this action, see the proposed
license amendment dated May 16, 2005. The NRC maintains an Agencywide
Documents Access Management System (ADAMS), which provides text and
image files of NRC's public documents. These documents may be accessed
through the NRC's Public Electronic Reading Room on the Internet at:
http: //www.nrc.gov/reading-rm/adams.html. Copies of the referenced
documents will also be available for review at the NRC Public Document
Room (PDR), located at 11555 Rockville Pike, Rockville, MD, 20852. PDR
reference staff can be contacted at 1-800-397-4209, 301-415-4737 or by
e-mail to pdr@nrc.gov. The PDR reproduction contractor will copy
documents for a fee.
Dated at Rockville, Maryland, this 31st of August, 2005.
For the Nuclear Regulatory Commission.
Joseph M. Sebrosky,
Senior Project Manager, Spent Fuel Project Office, Office of Nuclear
Material Safety and Safeguards.
[FR Doc. 05-17971 Filed 9-9-05; 8:45 am]
BILLING CODE 7590-01-P
