Energy Northwest, Columbia Generating Station Independent Spent Fuel Storage Installation Environmental Assessment and Finding of No Significant Impact Regarding a Proposed Exemption, 70551-70552 [E6-20568]
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Federal Register / Vol. 71, No. 233 / Tuesday, December 5, 2006 / Notices
Purpose: To discuss declassification
program issues.
This meeting will be open to the
public. However, due to space
limitations and access procedures, the
name and telephone number of
individuals planning to attend must be
submitted to the Information Security
Oversight Office (ISOO) no later than
Monday, December 11, 2006. ISOO will
provide additional instructions for
gaining access to the location of the
meeting.
J.
William Leonard, Director Information
Security Oversight Office, National
Archives Building, 700 Pennsylvania
Avenue, NW., Washington, DC 20408,
telephone number (202) 357–5250.
FOR FURTHER INFORMATION CONTACT:
Dated: November 30, 2006.
J. William Leonard,
Director, Information Security Oversight
Office.
[FR Doc. E6–20505 Filed 12–4–06; 8:45 am]
BILLING CODE 7515–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–35]
Energy Northwest, Columbia
Generating Station Independent Spent
Fuel Storage Installation
Environmental Assessment and
Finding of No Significant Impact
Regarding a Proposed Exemption
Nuclear Regulatory
Commission.
ACTION: Environmental Assessment and
Finding of No Significant Impact.
AGENCY:
ycherry on PROD1PC64 with NOTICES
FOR FURTHER INFORMATION CONTACT:
Christopher M. Regan, Senior Project
Manager, Division of Spent Fuel Storage
and Transportation, Office of Nuclear
Material Safety and Safeguards, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555. Telephone:
(301) 415–1179; fax number: (301) 415–
1179; e-mail: cmr1@nrc.gov.
SUPPLEMENTARY INFORMATION: The U.S.
Nuclear Regulatory Commission (NRC
or Commission) is considering a request
dated September 14, 2006, from Energy
Northwest (applicant or Energy
Northwest) for an exemption from
certain requirements of Title 10, Code of
Federal Regulations (CFR), Part 72 (10
CFR part 72), specifically, 10 CFR
72.212(a)(2), 72.212(b)(2)(i)(A),
72.212(b)(7), and 72.214, pursuant to 10
CFR 72.7, for the Columbia Generating
Station (CGS) Independent Spent Fuel
Storage Installation (ISFSI), located on
the CGS site in Benton County,
VerDate Aug<31>2005
15:14 Dec 04, 2006
Jkt 211001
Washington. The CGS ISFSI is an
existing facility constructed for interim
dry storage of spent nuclear fuel.
At the CGS ISFSI, Energy Northwest
has stored spent nuclear fuel in fifteen
Holtec International HI–STORM 100
storage casks. As set forth in 10 CFR
72.214, the NRC has approved use of the
HI–STORM 100 Cask System in
Certificate of Compliance (CoC) 1014.
The NRC has issued Amendments 1
(effective date July 15, 2002) and 2
(effective date June 7, 2005) to CoC
1014. Energy Northwest loaded the
spent nuclear fuel into the HI–STORM
100 storage casks at the CGS ISFSI
under Amendment 1. If approved by the
NRC, the exemption would apply to all
HI–STORM 100 storage casks fabricated
and used in accordance with
Amendment 1 of CoC 1014 at the CGS
ISFSI.
The exemption would authorize the
applicant to perform analyses consistent
with that granted by the NRC in
Amendment 2 to CoC 1014 in lieu of
certain analyses required by
Amendment 1 to CoC 1014, specifically,
Appendix B, Section 3.4.3.a., Site
Specific Parameters and Analyses
(concerning the determination of Holtec
HI–STORM 100/ISFSI pad interface
coefficient of friction under
environmental conditions that may
degrade the pad/cask interface, such as
those caused by icing).
The NRC has prepared an
environmental assessment for this
proposed action in accordance with the
requirements of 10 CFR part 51. Based
on the environmental assessment, the
NRC has concluded that a Finding of No
Significant Impact (FONSI) is
appropriate with respect to the
proposed action.
Environmental Assessment (EA)
I. Identification of Proposed Action
By letter dated September 14, 2006,
Energy Northwest requested an
exemption from the requirements of 10
CFR 72.212(a), 72.212(b)(2)(i),
72.212(b)(7) and 72.214, specifically,
exemption from complying with
Appendix B, Section 3.4.3.a., Site
Specific Parameters and Analyses of
Amendment 1 to CoC 1014, which
requires a determination of the HI–
STORM 100/ISFSI pad interface
coefficient of friction under
environmental conditions that may
degrade the pad/cask interface, such as
those caused by icing. Approval of the
exemption request would allow the
applicant to perform an analysis
consistent with that granted by the NRC
in Amendment 2 to CoC 1014 when
evaluating icing conditions between the
PO 00000
Frm 00051
Fmt 4703
Sfmt 4703
70551
bottom of the HI–STORM 100 storage
casks and the ISFSI pad in lieu of
determining the HI–STORM 100/ISFSI
interface coefficient of friction. The
presence of ice formation at the
interface between the bottom of the HI–
STORM 100 storage casks and the ISFSI
pad can result in the storage system
being in an unanalyzed condition.
Energy Northwest determined that the
HI–STORM 100 storage casks used at
the CGS ISFSI were susceptible to the
icing phenomena and developed
compensatory measures during cold
weather conditions to maintain the
friction coefficient in accordance with
Amendment 1 to CoC 1014.
For the NRC to permit Energy
Northwest to demonstrate the safe
condition of the HI–STORM 100 storage
casks at the CGS ISFSI during cold
weather conditions by performing
analyses consistent with methods
approved in Amendment 2 to CoC 1014,
the NRC must grant Energy Northwest
an exemption from certain general
license conditions defined in 10 CFR
72.212 and the list of approved casks in
10 CFR 72.214. The NRC regulation, 10
CFR 72.212(a)(2), states that the general
license for the storage of spent nuclear
fuel at power reactor sites is limited to
storage in casks approved under the
provisions in 10 CFR part 72. By
exempting Energy Northwest from 10
CFR 72.214, 10 CFR 72.212(a)(2) and
certain other regulations in 10 CFR part
72.212 that concern compliance with
the applicable CoC, namely,
72.212(b)(2)(i)(A) and 72.212(b)(7),
Energy Northwest will be authorized to
deviate from CoC 1014 (Amendment 1)
Appendix B, Section 3.4.3.a, which
requires determination of the HI–
STORM 100/ISFSI pad interface
coefficient of friction.
II. Need for the Proposed Action
Fifteen HI–STORM 100 storage casks
have been loaded under Amendment 1
of CoC 1014 and are stored at the CGS
ISFSI. Energy Northwest is currently
performing compensatory measures
during cold weather conditions,
including monitoring operator
walkdowns, de-icing, and clearing of a
pathway on the ISFSI for draining, to
maintain the friction coefficient in
accordance with Amendment 1 to CoC
1014. Elimination of the need to
continue implementation of these
compensatory measures would reduce
worker radiation dose and free operators
to be more responsive to other duties.
III. Environmental Impacts of the
Proposed Action
The potential environmental impact
of using the HI–STORM 100 Cask
E:\FR\FM\05DEN1.SGM
05DEN1
ycherry on PROD1PC64 with NOTICES
70552
Federal Register / Vol. 71, No. 233 / Tuesday, December 5, 2006 / Notices
System was initially analyzed in the
environmental assessment for the final
rule to add the HI–STORM 100 Cask
System to the list of approved spent fuel
storage casks in 10 CFR 72.214 (65 FR
25241; May 1, 2000). In addition, the
potential environmental impact of
Amendment 2 changes to CoC 1014 was
analyzed in the environmental
assessment for the final rule that
amended 10 CFR 72.214 to add
Amendment 2 to CoC 1014 (70 FR
32977; June 7, 2005). Both
environmental assessments concluded
that there would be no significant
environmental impacts as a result of the
respective actions, and as such, the NRC
made a finding of no significant impact.
The NRC staff finds that the conclusions
set forth in these environmental
assessments continue to be valid.
The HI–STORM 100 Cask System is
designed to mitigate the effects of design
basis accidents that could occur during
storage. Design basis accidents account
for human-induced events and the most
severe natural phenomena reported for
the site and surrounding area.
Postulated accidents analyzed for an
ISFSI include tornado winds and
tornado generated missiles, design basis
earthquake, design basis flood,
accidental cask drop, lightning effects,
fire, explosions, and other incidents.
Considering the specific design
requirements for each accident
condition, the design of the HI–STORM
100 Cask System, would prevent loss of
containment, shielding, and criticality
control.
Amendment 1 to CoC 1014, Appendix
B, Section 3.4.3.a, requires that the
Coulomb friction coefficient for the HI–
STORM 100/ISFSI pad interface be at
least 0.53 under all conditions.
Amendment 2 to CoC 1014, Appendix
B, Section 3.4.3.a. includes a provision,
that for free standing casks, the response
of the casks under the site’s Design
Basis Earthquake (DBE) could be
established using the best estimate of
the friction coefficient in an appropriate
analysis model. The analysis would
demonstrate that the DBE would not
result in cask tip-over or cause a cask to
fall off the pad, or cause an impact
between casks, or if an accident were to
occur, would demonstrate that the
maximum g-load experienced by the
stored spent nuclear fuel would be
limited to 45 g’s. The use of methods
described in Section 3.4.3.a of
Appendix B, approved by the NRC in
Amendment 2 to CoC 1014, in
demonstrating the safe storage of spent
nuclear fuel during environmental
conditions that might degrade the pad/
cask interface friction, such as those
caused by icing, will not result in any
VerDate Aug<31>2005
15:14 Dec 04, 2006
Jkt 211001
degradation of specific design
requirements, namely, containment,
shielding or criticality control. Without
the loss of either containment,
shielding, or criticality control, the risk
to public health and safety is not
compromised.
By permitting the use of methods
described in Section 3.4.3.a of
Appendix B, approved by the NRC in
Amendment 2 to CoC 1014, there will
be a reduction in occupational exposure
due to the relief from the performance
of compensatory measures. Therefore,
the NRC staff has determined that
acceptable safety margins are
maintained and that there are no
significant environmental impacts as a
result of using the methods described in
Section 3.4.3.a of Appendix B, approved
by the NRC in Amendment 2 to CoC
1014, to demonstrate safe storage of
spent nuclear fuel at the CGS ISFSI.
IV. Alternatives to the Proposed Action
The staff evaluated the no action
alternative, which would be a denial of
the exemption request. Denial of the
exemption request would result in
continued performance of compensatory
measures by Energy Northwest, thereby
continuing to subject workers to an
increased radiation dose than would be
the case if the compensatory measures
were not conducted.
V. Agencies and Persons Consulted
On October 27, 2006, Mr. Michael
Mills of the State of Washington Energy
Facility Site Evaluation Council was
contacted about the EA for the proposed
action and had no concerns.
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. The proposed
action will not have a significant effect
on the quality of the human
environment because the use of the
Amendment 2 methodology will reduce
worker radiation dose, and further, will
not result in any degradation to specific
cask design requirements, namely,
containment, shielding, or criticality
control. As described in the foregoing
EA, the Commission finds that the
proposed action of granting an
exemption from 10 CFR 72.212(a)(2),
72.212(b)(2)(i)(A), 72.212(b)(7), and
72.214, pursuant to 10 CFR 72.7, which
will permit Energy Northwest to
perform analyses consistent with that
granted by the NRC in Amendment 2 to
CoC 1014, Appendix B, Section 3.4.3.a
at the CGS ISFSI, is not a major Federal
action significantly affecting the quality
of the human environment and,
PO 00000
Frm 00052
Fmt 4703
Sfmt 4703
therefore, an environmental impact
statement is not required.
Further Information
In accordance with 10 CFR 2.390 of
NRC’s ‘‘Rules of Practice,’’ final NRC
records and documents regarding this
proposed action, including the
exemption request dated September 14,
2006, are publically available in the
records component of NRC’s
Agencywide Documents Access and
Management System (ADAMS). These
documents may be inspected at NRC’s
Public Electronic Reading Room at
https://www.nrc.gov/reading-rm/
adams.html. These documents may also
be viewed electronically on the public
computers located at the NRC’s Public
Document Room (PDR), O1F21, One
White Flint North, 11555 Rockville
Pike, Rockville, MD 20852. The PDR
reproduction contractor will copy
documents for a fee. Persons who do not
have access to ADAMS or who
encounter problems in accessing the
documents located in ADAMS, should
contact the NRC PDR Reference staff by
telephone at 1–800–397–4209 or (301)
415–4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 20th day
of November 2006.
For the Nuclear Regulatory Commission.
Christopher M. Regan,
Senior Project Manager, Division of Spent
Fuel Storage and Transportation, Office of
Nuclear Material Safety and Safeguards.
[FR Doc. E6–20568 Filed 12–4–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Nuclear
Waste; Meeting on Planning and
Procedures; Notice of Meeting
The Advisory Committee on Nuclear
Waste (ACNW) will hold a Planning and
Procedures meeting on December 12,
2006, Room T–2B1, 11545 Rockville
Pike, Rockville, Maryland. The entire
meeting will be open to public
attendance, with the exception of a
portion that may be closed pursuant to
5 U.S.C. 552b (c) (2) and (6) to discuss
organizational and personnel matters
that relate solely to internal personnel
rules and practices of ACNW, and
information the release of which would
constitute a clearly unwarranted
invasion of personal privacy.
The agenda for the subject meeting
shall be as follows:
Tuesday, December 12, 2006—8:30
a.m.–9:30 a.m.
The Committee will discuss proposed
ACNW activities and related matters.
E:\FR\FM\05DEN1.SGM
05DEN1
]]>Agencies
[Federal Register Volume 71, Number 233 (Tuesday, December 5, 2006)]
[Notices]
[Pages 70551-70552]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-20568]
=======================================================================
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NUCLEAR REGULATORY COMMISSION
[Docket No. 72-35]
Energy Northwest, Columbia Generating Station Independent Spent
Fuel Storage Installation Environmental Assessment and Finding of No
Significant Impact Regarding a Proposed Exemption
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental Assessment and Finding of No Significant Impact.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Christopher M. Regan, Senior Project
Manager, Division of Spent Fuel Storage and Transportation, Office of
Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555. Telephone: (301) 415-1179; fax
number: (301) 415-1179; e-mail: cmr1@nrc.gov.
SUPPLEMENTARY INFORMATION: The U.S. Nuclear Regulatory Commission (NRC
or Commission) is considering a request dated September 14, 2006, from
Energy Northwest (applicant or Energy Northwest) for an exemption from
certain requirements of Title 10, Code of Federal Regulations (CFR),
Part 72 (10 CFR part 72), specifically, 10 CFR 72.212(a)(2),
72.212(b)(2)(i)(A), 72.212(b)(7), and 72.214, pursuant to 10 CFR 72.7,
for the Columbia Generating Station (CGS) Independent Spent Fuel
Storage Installation (ISFSI), located on the CGS site in Benton County,
Washington. The CGS ISFSI is an existing facility constructed for
interim dry storage of spent nuclear fuel.
At the CGS ISFSI, Energy Northwest has stored spent nuclear fuel in
fifteen Holtec International HI-STORM 100 storage casks. As set forth
in 10 CFR 72.214, the NRC has approved use of the HI-STORM 100 Cask
System in Certificate of Compliance (CoC) 1014. The NRC has issued
Amendments 1 (effective date July 15, 2002) and 2 (effective date June
7, 2005) to CoC 1014. Energy Northwest loaded the spent nuclear fuel
into the HI-STORM 100 storage casks at the CGS ISFSI under Amendment 1.
If approved by the NRC, the exemption would apply to all HI-STORM 100
storage casks fabricated and used in accordance with Amendment 1 of CoC
1014 at the CGS ISFSI.
The exemption would authorize the applicant to perform analyses
consistent with that granted by the NRC in Amendment 2 to CoC 1014 in
lieu of certain analyses required by Amendment 1 to CoC 1014,
specifically, Appendix B, Section 3.4.3.a., Site Specific Parameters
and Analyses (concerning the determination of Holtec HI-STORM 100/ISFSI
pad interface coefficient of friction under environmental conditions
that may degrade the pad/cask interface, such as those caused by
icing).
The NRC has prepared an environmental assessment for this proposed
action in accordance with the requirements of 10 CFR part 51. Based on
the environmental assessment, the NRC has concluded that a Finding of
No Significant Impact (FONSI) is appropriate with respect to the
proposed action.
Environmental Assessment (EA)
I. Identification of Proposed Action
By letter dated September 14, 2006, Energy Northwest requested an
exemption from the requirements of 10 CFR 72.212(a), 72.212(b)(2)(i),
72.212(b)(7) and 72.214, specifically, exemption from complying with
Appendix B, Section 3.4.3.a., Site Specific Parameters and Analyses of
Amendment 1 to CoC 1014, which requires a determination of the HI-STORM
100/ISFSI pad interface coefficient of friction under environmental
conditions that may degrade the pad/cask interface, such as those
caused by icing. Approval of the exemption request would allow the
applicant to perform an analysis consistent with that granted by the
NRC in Amendment 2 to CoC 1014 when evaluating icing conditions between
the bottom of the HI-STORM 100 storage casks and the ISFSI pad in lieu
of determining the HI-STORM 100/ISFSI interface coefficient of
friction. The presence of ice formation at the interface between the
bottom of the HI-STORM 100 storage casks and the ISFSI pad can result
in the storage system being in an unanalyzed condition. Energy
Northwest determined that the HI-STORM 100 storage casks used at the
CGS ISFSI were susceptible to the icing phenomena and developed
compensatory measures during cold weather conditions to maintain the
friction coefficient in accordance with Amendment 1 to CoC 1014.
For the NRC to permit Energy Northwest to demonstrate the safe
condition of the HI-STORM 100 storage casks at the CGS ISFSI during
cold weather conditions by performing analyses consistent with methods
approved in Amendment 2 to CoC 1014, the NRC must grant Energy
Northwest an exemption from certain general license conditions defined
in 10 CFR 72.212 and the list of approved casks in 10 CFR 72.214. The
NRC regulation, 10 CFR 72.212(a)(2), states that the general license
for the storage of spent nuclear fuel at power reactor sites is limited
to storage in casks approved under the provisions in 10 CFR part 72. By
exempting Energy Northwest from 10 CFR 72.214, 10 CFR 72.212(a)(2) and
certain other regulations in 10 CFR part 72.212 that concern compliance
with the applicable CoC, namely, 72.212(b)(2)(i)(A) and 72.212(b)(7),
Energy Northwest will be authorized to deviate from CoC 1014 (Amendment
1) Appendix B, Section 3.4.3.a, which requires determination of the HI-
STORM 100/ISFSI pad interface coefficient of friction.
II. Need for the Proposed Action
Fifteen HI-STORM 100 storage casks have been loaded under Amendment
1 of CoC 1014 and are stored at the CGS ISFSI. Energy Northwest is
currently performing compensatory measures during cold weather
conditions, including monitoring operator walkdowns, de-icing, and
clearing of a pathway on the ISFSI for draining, to maintain the
friction coefficient in accordance with Amendment 1 to CoC 1014.
Elimination of the need to continue implementation of these
compensatory measures would reduce worker radiation dose and free
operators to be more responsive to other duties.
III. Environmental Impacts of the Proposed Action
The potential environmental impact of using the HI-STORM 100 Cask
[[Page 70552]]
System was initially analyzed in the environmental assessment for the
final rule to add the HI-STORM 100 Cask System to the list of approved
spent fuel storage casks in 10 CFR 72.214 (65 FR 25241; May 1, 2000).
In addition, the potential environmental impact of Amendment 2 changes
to CoC 1014 was analyzed in the environmental assessment for the final
rule that amended 10 CFR 72.214 to add Amendment 2 to CoC 1014 (70 FR
32977; June 7, 2005). Both environmental assessments concluded that
there would be no significant environmental impacts as a result of the
respective actions, and as such, the NRC made a finding of no
significant impact. The NRC staff finds that the conclusions set forth
in these environmental assessments continue to be valid.
The HI-STORM 100 Cask System is designed to mitigate the effects of
design basis accidents that could occur during storage. Design basis
accidents account for human-induced events and the most severe natural
phenomena reported for the site and surrounding area. Postulated
accidents analyzed for an ISFSI include tornado winds and tornado
generated missiles, design basis earthquake, design basis flood,
accidental cask drop, lightning effects, fire, explosions, and other
incidents. Considering the specific design requirements for each
accident condition, the design of the HI-STORM 100 Cask System, would
prevent loss of containment, shielding, and criticality control.
Amendment 1 to CoC 1014, Appendix B, Section 3.4.3.a, requires that
the Coulomb friction coefficient for the HI-STORM 100/ISFSI pad
interface be at least 0.53 under all conditions. Amendment 2 to CoC
1014, Appendix B, Section 3.4.3.a. includes a provision, that for free
standing casks, the response of the casks under the site's Design Basis
Earthquake (DBE) could be established using the best estimate of the
friction coefficient in an appropriate analysis model. The analysis
would demonstrate that the DBE would not result in cask tip-over or
cause a cask to fall off the pad, or cause an impact between casks, or
if an accident were to occur, would demonstrate that the maximum g-load
experienced by the stored spent nuclear fuel would be limited to 45
g's. The use of methods described in Section 3.4.3.a of Appendix B,
approved by the NRC in Amendment 2 to CoC 1014, in demonstrating the
safe storage of spent nuclear fuel during environmental conditions that
might degrade the pad/cask interface friction, such as those caused by
icing, will not result in any degradation of specific design
requirements, namely, containment, shielding or criticality control.
Without the loss of either containment, shielding, or criticality
control, the risk to public health and safety is not compromised.
By permitting the use of methods described in Section 3.4.3.a of
Appendix B, approved by the NRC in Amendment 2 to CoC 1014, there will
be a reduction in occupational exposure due to the relief from the
performance of compensatory measures. Therefore, the NRC staff has
determined that acceptable safety margins are maintained and that there
are no significant environmental impacts as a result of using the
methods described in Section 3.4.3.a of Appendix B, approved by the NRC
in Amendment 2 to CoC 1014, to demonstrate safe storage of spent
nuclear fuel at the CGS ISFSI.
IV. Alternatives to the Proposed Action
The staff evaluated the no action alternative, which would be a
denial of the exemption request. Denial of the exemption request would
result in continued performance of compensatory measures by Energy
Northwest, thereby continuing to subject workers to an increased
radiation dose than would be the case if the compensatory measures were
not conducted.
V. Agencies and Persons Consulted
On October 27, 2006, Mr. Michael Mills of the State of Washington
Energy Facility Site Evaluation Council was contacted about the EA for
the proposed action and had no concerns.
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. The
proposed action will not have a significant effect on the quality of
the human environment because the use of the Amendment 2 methodology
will reduce worker radiation dose, and further, will not result in any
degradation to specific cask design requirements, namely, containment,
shielding, or criticality control. As described in the foregoing EA,
the Commission finds that the proposed action of granting an exemption
from 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A), 72.212(b)(7), and 72.214,
pursuant to 10 CFR 72.7, which will permit Energy Northwest to perform
analyses consistent with that granted by the NRC in Amendment 2 to CoC
1014, Appendix B, Section 3.4.3.a at the CGS ISFSI, is not a major
Federal action significantly affecting the quality of the human
environment and, therefore, an environmental impact statement is not
required.
Further Information
In accordance with 10 CFR 2.390 of NRC's ``Rules of Practice,''
final NRC records and documents regarding this proposed action,
including the exemption request dated September 14, 2006, are
publically available in the records component of NRC's Agencywide
Documents Access and Management System (ADAMS). These documents may be
inspected at NRC's Public Electronic Reading Room at https://
www.nrc.gov/reading-rm/adams.html. These documents may also be viewed
electronically on the public computers located at the NRC's Public
Document Room (PDR), O1F21, One White Flint North, 11555 Rockville
Pike, Rockville, MD 20852. The PDR reproduction contractor will copy
documents for a fee. Persons who do not have access to ADAMS or who
encounter problems in accessing the documents located in ADAMS, should
contact the NRC PDR Reference staff by telephone at 1-800-397-4209 or
(301) 415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 20th day of November 2006.
For the Nuclear Regulatory Commission.
Christopher M. Regan,
Senior Project Manager, Division of Spent Fuel Storage and
Transportation, Office of Nuclear Material Safety and Safeguards.
[FR Doc. E6-20568 Filed 12-4-06; 8:45 am]
BILLING CODE 7590-01-P
