Notice of Environmental Assessment and Finding of No Significant Impact for Approval of Decommissioning Plan for Test Area C-74L at Eglin Air Force Base, FL, 39804-39808 [E5-3629]
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Federal Register / Vol. 70, No. 131 / Monday, July 11, 2005 / Notices
Domestic Licensing Proceedings’’ in 10
CFR Part 2. Interested persons should
consult current copies of 10 CFR 2.309,
2.304, and 2.305, which are available at
the Commission’s Public Document
Room (PDR), located at One White Flint
North, Public File Area 01F21, 11555
Rockville Pike (first floor), Rockville,
Maryland. Publicly available records
will be accessible from the Agencywide
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System’s (ADAMS) Public Electronic
Reading Room on the Internet at the
NRC Web site, https://www.nrc.gov/
reading-rm/doc-collections/cfr/. If a
request for a hearing and petition for
leave to intervene is filed by the above
date, the Commission or a presiding
officer designated by the Commission or
by the Chief Administrative Judge of the
Atomic Safety and Licensing Board
Panel will rule on the request and
petition; and the Secretary or the Chief
Administrative Judge of the Atomic
Safety and Licensing Board will issue a
notice of a hearing or an appropriate
order.
As required by 10 CFR 2.309, a
petition for leave to intervene shall set
forth with particularity the interest of
the petitioner/requestor in the
proceeding, and how that interest may
be affected by the results of the
proceeding. The petition should
specifically explain the reasons why
intervention should be permitted with
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the requestor’s/petitioner’s right under
the Act to be made a party to the
proceeding; (3) the nature and extent of
the requestor’s/petitioner’s property,
financial, or other interest in the
proceeding; and (4) the possible effect of
any decision or order which may be
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requestor’s/petitioner’s interest. The
petition must also identify the specific
contentions which the petitioner/
requestor seeks to have litigated in the
proceeding.
Each contention must consist of a
specific statement of the issue of law or
fact to be raised or controverted. In
addition, the petitioner/requestor shall
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rely in proving the contention at the
hearing. The petitioner must also
provide references to those specific
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petitioner intends to rely to establish
those facts or expert opinion. The
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petition must include sufficient
information to show that a genuine
dispute exists with the applicant on a
material issue of law or fact.
Contentions shall be limited to matters
within the scope of the amendment
under consideration. The contention
must be one which, if proven, would
entitle the petitioner/requestor to relief.
A petitioner/requestor who fails to
satisfy these requirements with respect
to at least one contention will not be
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Those permitted to intervene become
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intervene, and have the opportunity to
participate fully in the conduct of the
hearing.
Nontimely requests and petitions and
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absent a determination by the
Commission or the presiding officer of
the Atomic Safety and Licensing Board
that the petition, request and/or the
contentions should be granted based on
a balancing of the factors specified in 10
CFR 2.309(a)(1)(I)–(viii).
A request for a hearing and petition
for leave to intervene must be filed by:
(1) First class mail addressed to the
Office of the Secretary of the
Commission, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, Attention: Rulemaking and
Adjudications Staff; (2) courier, express
mail, or expedited delivery services:
Office of the Secretary, Sixteenth Floor,
One White Flint North, 11555 Rockville
Pike, Rockville, Maryland, 20852,
Attention: Rulemaking and
Adjudications Staff; (3) e-mail
addressed to the Office of the Secretary,
U.S. Nuclear Regulatory Commission,
HEARINGDOCKET@NRC.GOV; or (4)
facsimile transmission addressed to the
Office of the Secretary, U.S. Nuclear
Regulatory Commission, Washington,
DC, 20555–0001, Attention:
Rulemakings and Adjudications Staff at
(301) 415–1101, verification number is
(301) 415–1966. A request for hearing
and petition for leave to intervene need
not comply with 10 CFR 2.304(b)(c) and
(d) if an original and two copies
otherwise complying with the
requirements of that section are mailed
within two (2) days after filing by e-mail
or facsimile transmission to the
Secretary, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, Attention: Rulemakings and
Adjudications Staff. A copy of the
request for hearing and petition for
leave to intervene should also be sent to
the Office of the General Counsel, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, and it is
requested that copies be transmitted
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either by means of facsimile
transmission to (301) 415–3725 or by email to OGCMailCenter@nrc.gov. A copy
of the request for hearing and petition
for leave to intervene should also be
sent to General Counsel, Tennessee
Valley Authority, ET 11A, 400 West
Summit Hill Drive, Knoxville,
Tennessee, 37902, attorney for the
licensee.
For further details with respect to this
action, see the application for
amendment dated June 28, 2004, which
is available for public inspection at the
Commission’s PDR, located at One
White Flint North, Public File Area O1
F21, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available
records will be accessible electronically
from the ADAMS Public Electronic
Reading Room on the Internet at the
NRC Web site, https://www.nrc.gov/
reading-rm/adams.html. 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, (301)
415–4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 29th day
of June, 2005.
For the Nuclear Regulatory Commission.
Margaret H. Chernoff,
Project Manager, Section 2, Project
Directorate II, Division of Licensing Project
Management, Office of Nuclear Reactor
Regulation.
[FR Doc. E5–3633 Filed 7–8–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 030–28641]
Notice of Environmental Assessment
and Finding of No Significant Impact
for Approval of Decommissioning Plan
for Test Area C–74L at Eglin Air Force
Base, FL
Nuclear Regulatory
Commission.
AGENCY:
Environmental Assessment and
Finding of No Significant Impact for
License Amendment.
ACTION:
D.
Blair Spitzberg, Ph.D., Chief, Fuel Cycle
and Decommissioning Branch, Division
of Nuclear Materials Safety, Region IV,
U.S. Nuclear Regulatory Commission,
611 Ryan Plaza Drive, Suite 400,
Arlington, TX 76011. Telephone: (817)
860–8100; e-mail: dbs@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
SUPPLEMENTARY INFORMATION:
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Federal Register / Vol. 70, No. 131 / Monday, July 11, 2005 / Notices
I. Introduction
The Department of the Air Force (the
licensee) submitted a decommissioning
plan (DP) to the U.S. Nuclear Regulatory
Commission (NRC) by Memorandum
dated May 24, 2002. Supplemental
information was provided by
Memoranda dated November 1, 2002,
August 21, 2003, October 27, 2004, and
January 13, 2005. The licensee
requested that the DP for Test Area C–
74L at Eglin Air Force Base (AFB) be
approved. The NRC is considering the
issuance of an amendment to Master
Materials License 42–23539–01AF
which will approve the DP. If approved
by the NRC, the licensee will be
authorized to conduct decommissioning
activities in accordance with the DP.
The NRC has prepared an
Environmental Assessment (EA) in
support of this licensing action in
accordance with the requirements of 10
CFR Part 51. The EA was developed to
provide sufficient evidence and analysis
for determining whether to prepare an
Environmental Impact Statement or
Finding of No Significant Impact
(FONSI). Based on the results of the EA,
the NRC has determined that a FONSI
is appropriate.
II. Environmental Assessment
Proposed Action
The proposed action is to approve the
DP which will allow the licensee to
conduct decommissioning in
accordance with the procedures and
processes provided in the DP. The
approval of the DP would be
accomplished by license amendment to
NRC Materials License 42–23539–01AF
following the NRC decision that the DP
meets the standards specified in 10 CFR
Part 20 and related NRC guidance
documents.
The Need for the Proposed Action
The licensee intends to remediate
Test Area C–74L and ultimately remove
the site from its license (and the
associated AFB radioactive material
permit) because it no longer conducts
NRC-licensed activities at this location.
If the site is properly decommissioned,
the licensee would then be in
compliance with the Timeliness Rule
requirements of 10 CFR 30.36,
‘‘Expiration and Termination of
Licenses and Decommissioning of Sites
and Separate Buildings or Outdoor
Areas.’’
Environmental Impacts of the Proposed
Action
Test Area C–74L is located in Walton
County, Florida, within the northcentral portion of Eglin AFB. The site is
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located approximately 14 miles
northwest of the city of Niceville,
Florida. The test area lies within Section
11 of Range 21 West, Township 2 North.
The test area currently consists of a 4acre radiologically controlled area, fire
control/ballistics building, gun corridor,
target area, well house building, drum
storage area, and surrounding land.
From late-1974 to 1978, the area was
used for pre-production testing of a gun
system which used depleted uranium
(DU) ammunition. The licensee elected
to discontinue DU munitions testing at
this location. An estimated 16,315
pounds of DU was expended at the site.
Approximately 9,257 pounds of DU
were collected and disposed of during
remediation activities conducted
between March 1978 and June 1987.
The remainder of the material has since
been remediated, was dispersed or
vaporized as part of DU ordinance
testing, or remains onsite and requires
remediation.
The portions of the site that may have
been contaminated with DU fragments
include the ballistic building interior,
ballistic and well house building
exteriors, target area, 4-acre
radiologically restricted grounds, and
two drainage ditches. Previous
radiological investigations included at
least six soil sampling events that
occurred between 1976–1999. Limited
reclamation activities have been
conducted several times since 1980. A
detailed site characterization study was
conducted during 1999 followed by
additional limited characterization
studies during 2000–2001. At that time,
the only area remaining to be
remediated was the 4-acre radiologically
controlled area.
The ballistic building interior was not
expected to contain radioactive material
in measurable quantities, in part,
because the building was not used to
store DU munitions. The well house
building was constructed after
completion of DU testing although the
land beneath the building was not
radiologically surveyed prior to
construction. The exteriors of these two
buildings may contain small amounts of
contamination as a result of possible
wind dispersion of DU fragments.
Two drainage ditches are located on
site property. Sample results indicated
measurable quantities of radionuclides
above background values. The licensee
does not expect to conduct remediation
activities in these ditches because the
residual radioactivity is expected to be
at levels below the NRC-approved
release criteria.
The radiological criteria for
unrestricted use is provided in 10 CFR
20.1402. This regulation states that a
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site will be considered acceptable for
unrestricted use if the residual
radioactivity that is distinguishable
from background radiation results in a
total effective dose equivalent to an
average member of the public that does
not exceed 25 millirems (0.25 mSv) per
year, including that from groundwater
sources of drinking water, and that the
residual radioactivity has been reduced
to levels that are as low as reasonably
achievable (ALARA).
Current NRC guidance (Section 2.5 of
NUREG–1757, Volume 2, ‘‘Consolidated
NMSS Decommissioning Guidance’’)
recommends that licensees demonstrate
compliance with the dose criteria by
using dose modeling or derived
concentration guideline levels (DCGLs)
and final status survey results. The
licensee’s request to release the site for
unrestricted use will be based on use of
DCGLs and final status survey results. In
the DP, the licensee proposes DCGLs for
building interiors, building exteriors,
equipment, and site soils. Through an
internal review process, the NRC
accepted the licensee’s proposed
building and equipment DCGLs, but
rejected the licensee’s proposed soil
DCGL. By Memorandum dated August
21, 2003, the licensee accepted the
NRC’s alternate proposal for soil DCGL.
Upon completion of the
decommissioning project, the licensee is
expected to submit the final status
survey results to the NRC for review and
approval. In addition, the NRC will
conduct confirmatory sampling. If the
results of the final status survey and any
confirmatory surveys performed are
below the NRC-approved DCGLs, the
site will be found to be in compliance
with the annual dose limit provided in
10 CFR 20.1402. If the surveys indicate
that the results are above the DCGLs,
then additional remediation may be
necessary. Alternatively, the licensee
will have to conduct an analysis to
demonstrate that the survey results
demonstrate compliance with the dose
criteria.
The remediation activities will result
in potential exposure of workers to
radioactive material. The primary
radionuclide of concern is uranium-238.
The DU is expected to be in the form of
solid uranium oxide or uranium metal
fragments. The primary health hazard is
inhalation of DU. The health effects
from DU include both chemical and
radiological toxicity with the two
important target organs being the
kidneys and the lungs. In general, the
health consequences are determined by
the physical and chemical form of the
DU as well as the level and duration of
exposure.
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Federal Register / Vol. 70, No. 131 / Monday, July 11, 2005 / Notices
To prevent potential health
consequences from exposure to DU, the
licensee has initiated a radiological
safety program. External occupational
exposure rates to DU is expected to be
minimal based on previous exposure
data. The internal exposure pathways
will be controlled and monitored as
necessary by the use of personnel
protective equipment, strict hygiene
practices, and air particulate and
bioassay sampling. The licensee’s
proposed program for control of
exposure to radioactive materials is
typical for the type of work being
conducted and is considered acceptable
to the NRC to maintain occupational
exposures within NRC limits.
The Air Force, or a contractor for the
Air Force, will be responsible for
packaging and transporting the lowlevel radioactive wastes. Remediation of
the site may have short-term nonradiological health and safety risks
caused by the excavation, packaging,
and shipping of the residual radioactive
material. These non-radiological
impacts include the normal risks of
exhuming the wastes with earth-moving
equipment and transportation of the
material to an out-of-state disposal
facility. The risks include injury or
death from a construction or
transportation accident.
There should be minimal risk to
members of the public from exposure to
radioactive wastes during transport
because the radionuclides of concern
will be dispersed within the soil,
contained in authorized shipping
containers, and shipped in accordance
with U.S. Department of Transportation
requirements.
The reclaimed material will be
transported to an out-of-state low level
radioactive waste disposal facility
licensed to accept and dispose of the
wastes. The radiological health risks
would be minimal to the workers of the
disposal facility, in part, because the
facility would have a radiation
protection program in place to protect
its workers. However, there is still a
small risk of an occupational accident
occurring while handling the waste
material.
In summary, the combination of the
NRC-approved DCGLs, the licensee’s
proposed final status survey results, and
the NRC’s confirmatory survey results
should demonstrate that annual doses to
future occupants of the site will be less
than the NRC’s radiological criteria for
unrestricted use of the facility.
Additional details of the licensee’s
radiation safety program and NRCapproved DCGLs will be provided in the
NRC’s Safety Analysis Report that will
be used to support the licensing
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decision. Furthermore, the radiological
impacts of releasing the site for
unrestricted use are bounded by the
impacts evaluated in NUREG–1496,
‘‘Generic Environmental Impact
Statement in Support of Rulemaking on
Radiological Criteria for License
Termination of NRC-Licensed Nuclear
Facilities.’’
The proposed action will have a
short-term detrimental effect on the
impacted area. The licensee plans to
scrap portions of the ground surface to
remove any residual radioactive
material. This action will result in
destruction of the cover vegetation and
top soil, and may create airborne dust.
In response, the licensee plans to
implement a program that will
minimize any long term damage. Dust
suppression methods will be utilized as
necessary. The area will be backfilled
and revegetated if scraped.
The site includes two drainage
ditches. One ditch is located on the
south side of the property and drains to
the south-south east. The second ditch
is located in the northeastern portion of
the property and drains towards the
northeast. There are two streams in the
vicinity of Test Area C–74L. Rocky
Creek is located about 700 feet (213
meters) south of the controlled area. A
tributary to Rocky Creek is located about
1800 feet (549 meters) to the west of the
site. A small dammed pond is located
within the western tributary. The
groundwater flow is anticipated to have
a southward component towards Rocky
Creek. Therefore, the remediation of the
site has the potential for impacting the
wildlife habitat in and around Rocky
Creek.
The NRC consulted with the U.S. Fish
& Wildlife Service because the
reclamation of the site could have an
impact on the habitat of a endangered
species, the Okaloosa darter. Okaloosa
darters are found only in the
Choctawhatchee Bay drainage in
Florida, where they inhabit vegetated
sand runs of clear creeks. According to
the U.S. Fish & Wildlife Service,
approximately 90 percent of the
watershed drainage area in which the
Okaloosa darter occurs is under the
management of Eglin AFB.
To protect the darter’s habitat, the
licensee has taken or plans to take
several actions. First, an earthen berm
currently exists on the southern portion
of the radiologically restricted area. This
berm is expected to help prevent
contaminated soil from leaving the
controlled area. Silt fencing will be used
as necessary to supplement the berm.
Manual remediation of areas of elevated
activities in lieu of heavy equipment
will help reduce the need for
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mechanical removal of the top six
inches of soil in some areas. Dust
suppression methods, including water
trucks, will be utilized as necessary to
prevent the spread of windblown
contamination during reclamation. A
decontamination pad will be used as
necessary to decontaminate equipment.
The licensee believes that light rain will
percolate into the ground, although
heavy rains may transport some soil
material into the two drainage ditches.
Scraped surface areas will be covered
with plastic sheeting as necessary until
backfilled.
With respect to other potentially
endangered or threatened species, the
licensee claims that the indigo snake
has been seen in the vicinity of Test
Area C–74L but does not live within the
radiologically controlled area.
Reclamation activities are not expected
to adversely impact the habitat of the
indigo snake on Eglin AFB ranges.
Further, the licensee claims that there
are no red cockaded woodpecker
colonies within Test Area C–74L. The
U.S. Fish and Wildlife Service
ultimately decided that the proposed
action (reclamation of the site) was not
likely to adversely affect resources
protected by the Endangered Species
Act of 1973, as amended. This
conclusion was reported to the NRC by
letter dated February 25, 2004.
The surficial groundwater is about
50–60 feet (15–18 meters) below land
surface. Geologic literature indicates
that the surficial aquifer beneath the site
extends to approximately 125 feet (38
meters) below land surface. The
Pensacola Clay separates the surficial
aquifer from the underlying Floridian
aquifer system. The Pensacola Clay
layer is about 160 feet (49 meters) thick,
meaning that the drinking water aquifer
is no less than 285 feet (87 meters)
below the land surface. The
hydraulically impenetrable Pensacola
Clay layer would be expected to prevent
any contamination that might be present
in the surficial groundwater from
reaching the Floridian aquifer system
even if the surficial groundwater was
contaminated with DU.
The licensee has conducted site
characterization studies and concluded
that the land surface contamination of
DU has not impacted the groundwater.
Most contamination is found within the
first 6 inches (15 centimeters) of soil
except in selected locations. In these
discrete locations, contamination is no
more than 4 feet (1.2 meters) below the
land surface. There are two drinking
water wells in the vicinity of the site.
One is located onsite and is 644 feet
(196 meters) deep. The second is located
a half-mile (0.8 kilometers) away and
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Federal Register / Vol. 70, No. 131 / Monday, July 11, 2005 / Notices
has been permanently abandoned. The
onsite drinking water well was sampled
during 1983, and the sample result
indicated no measurable quantities of
radioactive materials above background
values. Because the surficial
groundwater is located 50–60 feet (15–
18 meters) below surface, and the
drinking water aquifer is located at least
285 feet (87 meters) below surface, the
NRC concluded that the probability that
DU contamination has impacted either
the surficial or drinking water aquifer is
highly unlikely.
Environmental Impacts of the
Alternatives to the Proposed Action
The licensee seeks NRC approval of
the DP. The alternatives to the proposed
action are: (1) The no-action alternative,
or (2) to deny the amendment request
and require the licensee to take some
alternate action.
1. No-Action Alternative
One alternative available to the NRC
is to take no action by denying the
amendment request. Denial of the DP
submittal would result in no change in
current environmental conditions. The
no-action alternative is not a feasible
alternative because it will result in
violation of the NRC’s Timeliness Rule
(10 CFR 30.36), which requires licensees
to decommission their facilities when
licensed activities cease.
2. Environmental Impacts of Alternative
2
A second alternative is to deny the
licensee’s request in favor of alternate
release criteria as allowed by § 20.1403
(criteria for restricted conditions) or
§ 20.1404 (alternate criteria). However,
the NRC’s analysis confirmed that the
proposed action (approval of the DP as
submitted) meets the license
termination requirements of § 20.1402.
Accordingly, the NRC has determined
that the second alternative is not
reasonable. Therefore, this alternative
action is eliminated from further
consideration in this EA.
Conclusion
Based on its review, the NRC staff has
concluded that the environmental
impacts associated with the proposed
action do not warrant denial of the
license amendment request. The NRC
staff believes that the proposed action
will result in minimal environmental
impacts, including those to endangered
species and critical habitats. The staff
has determined that the proposed
action, approval of the DP, is the
appropriate alternative for selection.
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Agencies and Persons Contacted
The NRC staff consulted with both the
Florida State Historic Preservation
Officer and the local U.S. Fish &
Wildlife Service office. The Florida
Department of State, Division of
Historical Resources stated that no
historic properties were known to exist
in the area; therefore, the proposed
decommissioning will have no effect on
historic properties. The U.S. Fish &
Wildlife Service has informed the NRC
that the proposed action (site
reclamation) is not likely to adversely
affect protected resources including
endangered species and critical habitats.
The NRC staff also consulted with the
Florida Department of Health, Bureau of
Radiation Control. By letter dated May
19, 2005, the State responded that it had
no objections to the proposed EA and
FONSI.
III. Finding of No Significant Impact
The NRC staff has concluded that the
proposed action (amend the Air Force’s
license to approve the DP) complies
with both the Timeliness Rule
requirements of 10 CFR 30.36 and
License Termination Rule requirements
of 10 CFR 20.1402. On the basis of this
EA, the NRC has concluded that there
are no significant environmental
impacts and the license amendment
does not warrant the preparation of an
Environmental Impact Statement.
Accordingly, it has been determined
that a Finding of No Significant Impact
is appropriate.
IV. Further Information
A copy of this document will be
available electronically for public
inspection in the NRC Public Document
Room or from the Publicly Available
Records (PARS) component of the
NRC’s document system. 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 following references are
available for inspection at NRC’s Public
Electronic Reading Room at https://
www.nrc.gov/reading-rm/adams.html
(the Public Electronic Reading Room).
ADAMS accession numbers are located
in parentheses following the reference.
1. NRC, ‘‘Generic Environmental Impact
Statement in Support of Rulemaking on
Radiological Criteria for License Termination
of NRC-Licensed Nuclear Facilities,’’
NUREG–1496, July 1997 (ML042310492).
2. Pugh, Capt. David L., Department of the
Air Force Memorandum, ‘‘Review of
Decommissioning Plan for Eglin AFB,
Florida,’’ May 24, 2002 (ML021970666,
ML021970669, ML021980188,
ML021980239, ML021990724,
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Sfmt 4703
39807
ML021990330, ML021990377,
ML021990737, ML021990743).
3. Pugh, Capt. David L., Department of the
Air Force Memorandum, ‘‘Clarification
Request For C–74L Decommissioning Plan,’’
November 1, 2002 (ML023370482,
ML023370535, ML023370648,
ML023370660, ML023370675,
ML023380282, ML023380332).
4. Brockman, Ken E., NRC Letter to Air
Force, ‘‘Acknowledgment of Receipt of
Decommissioning Plan,’’ November 25, 2002
(ML023290265).
5. Spitzberg, D. Blair, NRC Memorandum,
‘‘Notice of Consideration of Amendment
Request for Department of the Air Force,
Eglin Air Force Base, Florida, and
Opportunity for Providing Comments and
Requesting a Hearing,’’ January 27, 2003
(ML030270180).
6. Brockman, Ken E., NRC Memorandum,
‘‘Regional Technical Assistance Request
Form,’’ January 29, 2003 (ML030300253).
7. Cain, Charles L., ‘‘NRC Inspection
Report 030–28641/2003–01,’’ February 11,
2003 (ML030420534).
8. Kokajko, Lawrence E., NRC
Memorandum, ‘‘Review of Derived
Concentration Guideline Levels (DCGLs) for
Eglin Air Force Base,’’ April 10, 2003
(ML031000111).
9. Cain, Charles L., NRC Letter to Air
Force, ‘‘Request for Additional Information
Regarding Eglin Air Force Base
Decommissioning Plan,’’ April 24, 2003
(ML031140240).
10. Spitzberg, D. Blair, NRC Letter to U.S.
Fish & Wildlife Service, ‘‘Request for
Comments Regarding Endangered/
Threatened Species and Critical Habitats,’’
June 9, 2003 (ML031600579).
11. Spitzberg, D. Blair, NRC Letter to
Florida State Historic Preservation Officer,
‘‘Request for Comments Regarding Cultural
and Historical Resources at Eglin Air Force
Base,’’ June 9, 2003 (ML031600613).
12. Carmody, Gail A., U.S. Fish & Wildlife
Service Letter to NRC, ‘‘Reclamation and
Decommissioning Uranium Munitions Site,
Area C–74L,’’ July 7, 2003 (ML031920346).
13. Matthews, Janet Snyder, Florida
Department of State Letter to NRC,
‘‘Reclamation Activities Within a Four-Acre
Property at Test Area C–74L, Walton
County,’’ July 8, 2003 (ML032050604).
14. NRC, NUREG–1748, ‘‘Environmental
Review Guidance for Licensing Actions
Associated With NMSS Programs,’’ July 2003
(ML032540811).
15. Mather, Lt. Col. Kali K., Air Force
Memorandum to NRC, ‘‘Supplement to the
Decommissioning Plan for Test Area C–74L,
Eglin AFB, FL,’’ August 21, 2003
(ML032450123).
16. NRC, NUREG–1757, ‘‘Consolidated
NMSS Decommissioning Guidance,’’
Volumes 1–3, September 2003
(ML032530410, ML032530405,
ML032471471).
17. Seiber, Stephen M., Air Force Letter to
NRC, ‘‘No Effect Determination,’’ February
11, 2004 (ML040430157).
18. Spitzberg, D. Blair, NRC letter to U.S.
Fish & Wildlife Services, ‘‘Request for
Comments Regarding Department of Air
Force’s Determination of No Effect,’’
February 18, 2004 (ML040690296).
E:\FR\FM\11JYN1.SGM
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39808
Federal Register / Vol. 70, No. 131 / Monday, July 11, 2005 / Notices
19. Carmody, Gail A., U.S. Fish & Wildlife
Service’s Response to NRC’s Letter ‘‘Request
for Comments Regarding Department of Air
Force’s Determination of No Effect,’’
February 25, 2004 (ML040690296).
20. Whitten, Jack E., NRC Letter to Air
Force, ‘‘Request for Additional Information
Regarding Eglin Air Force Base
Decommissioning Plan,’’ February 19, 2004
(ML040500864).
21. Whitten, Jack E., ‘‘NRC Inspection
Report 030–28641/04–001,’’ February 25,
2004 (ML040570122).
22. Abell, Capt. Clint E., Air Force
Memorandum to NRC, ‘‘Decommissioning
Plan for Test Area C–74L, Eglin AFB,
Florida,’’ October 27, 2004 (ML043410237).
23. Abell, Capt. Clint E., Air Force
Memorandum to NRC, ‘‘Response to NRC
Query of Decommissioning of Test Area C–
74L, Eglin Air Force Base, Florida,’’ January
13, 2005 (ML050320251).
24. Passetti, William A., Florida
Department of Health Letter to NRC,
‘‘Environmental Assessment for
Decommissioning of Test Area C–74L at
Eglin Air Force Base,’’ May 19, 2005
(ML051640567).
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 (800) 397–4209, (301)
415–4737 or by e-mail to pdr@nrc.gov.
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 Arlington, Texas this 28th day of
June, 2005.
For the Nuclear Regulatory Commission.
D. Blair Spitzberg,
Chief, Fuel Cycle & Decommissioning Branch,
Division of Nuclear Materials Safety, Region
IV.
[FR Doc. E5–3629 Filed 7–8–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 030–30429]
Notice of Availability of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment for Core Laboratories,
Houston, TX
Nuclear Regulatory
Commission.
ACTION: Notice of Availability.
AGENCY:
Jack
E. Whitten, Branch Chief, Nuclear
Materials Licensing Branch, Division of
Nuclear Materials Safety, Region RIV,
U.S. Nuclear Regulatory Commission,
FOR FURTHER INFORMATION CONTACT:
VerDate jul<14>2003
16:03 Jul 08, 2005
Jkt 205001
611 Ryan Plaza Drive, Suite 400,
Arlington, TX 76011. Telephone: (817)
860–8197; fax number (817) 860–8263;
e-mail: jew1@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is considering the
issuance of a license amendment to
Material License No. 42–26928–01
issued to Core Laboratories, Inc., (dba
ProTechnics) to authorize the utilization
of cesium–137 in quantities in excess of
limits listed in 10 CFR 30.71 for well
logging activities at temporary job sites
where NRC maintains jurisdiction. The
NRC has prepared an Environmental
Assessment (EA) in support of this
action in accordance with the
requirements of 10 CFR Part 51. Based
on the EA, the NRC has determined that
a Finding of No Significant Impact
(FONSI) is appropriate. The amendment
will be issued following the publication
of this Notice.
II. Environmental Assessment
Background
Core Laboratories, Inc., (Core
Laboratories) is a well logging licensee
based in Houston, Texas, and conducts
tracer operations using radioactive
materials in oil and natural gas fields
worldwide. Core Laboratories is
licensed by both the NRC and
Agreement States (Louisiana, New
Mexico, and Texas) to conduct well
logging operations.
By letter dated July 14, 1997, Core
Laboratories requested that NRC grant
an amendment to allow the use of
radioactive collar markers containing
activities of byproduct material
exceeding the limits listed in 10 CFR
30.71. An EA was written and based on
the EA, the NRC concluded that a
finding of no significant impact (FONSI)
was appropriate. The EA and the FONSI
were published in the 67 Federal
Register (FR) 5320, February 5, 2002.
On March 9, 2002, Core Laboratories
was granted an amendment authorizing
an exemption to 10 CFR 30.71. This
amendment authorized Core
Laboratories to use pipe collar markers
containing iridium–192, scandium–46,
antimony–124, cobalt–60, and cesium–
137 with activities up to 50 micro curies
(µCi).
On February 23, 2004, Core
Laboratories requested an amendment to
increase the activity of radioactive
markers containing cesium–137 from
the 50 µCi, previously approved, with
activities up to 100 µCi. This 100 µCi
activity exceeds the quantities of
byproduct material listed for use as pipe
PO 00000
Frm 00094
Fmt 4703
Sfmt 4703
collar markers in oil and gas wells in 10
CFR 39.47, 10 CFR 30.71, and the
activities authorized in the March 9,
2002, license amendment to Core
Laboratories’ byproduct material
license. The NRC has reviewed the
licensee’s amendment request and has
developed this EA to assess the
environmental consequences of this
licensing action using the guidance
provided in NUREG–1748,
Environmental Review Guidance for
Licensing Actions Associated with
NMSS Programs.
Proposed Action
The proposed action is to amend the
license and modify the previous
exemption by approving the licensee’s
request to use radioactive markers
containing 100 µCi cesium–137 for use
as pipe collar markers in oil and gas
wells. This proposed activity exceeds
the limits of radioactive markers
authorized in 10 CFR 39.47 and 10 CFR
30.71.
The radioactive markers Core
Laboratories requested authorization to
use in well logging activities are either
installed directly in the pipe collars or
are placed on the pipe collar threads
and secured between the pipe casing
joints and are not easily removed. Once
installed in a well bore, the pipe casing
and collars are cemented into place.
By letter dated July 14, 1997, Core
Laboratories in its correspondence to
NRC, describes the procedures it will
have in place involving the customer or
well owner/operator. These procedures
state, in part, that the customer or well
owner/operator must contact Core
Laboratories in the event the radioactive
pipe collar markers must be removed.
Core Laboratories will be available on
site to secure and take possession of the
collar markers upon their return to the
surface. Additionally, Core Laboratories
will provide the customer or well
owner/operator a copy of Attachment
XII–1 (Core Laboratories’ Radioactive
Collar Marker Utilization Log) as a
written record of the requirement to
notify Core Laboratories if markers
returned to the surface before a
specified date.
The Need for the Proposed Action
The proposed action is necessary so
that Core Laboratories can efficiently
carry out its business of well logging in
the oil and gas industry. The need for
an increase in activity for cesium-137 is
due to the heavier density of the
materials being used in the well logging
application. The higher activity
radioactive markers will allow, when
logging certain oil and gas wells, for
more accurate pipe collar location
E:\FR\FM\11JYN1.SGM
11JYN1
]]>Agencies
[Federal Register Volume 70, Number 131 (Monday, July 11, 2005)]
[Notices]
[Pages 39804-39808]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-3629]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 030-28641]
Notice of Environmental Assessment and Finding of No Significant
Impact for Approval of Decommissioning Plan for Test Area C-74L at
Eglin Air Force Base, FL
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental Assessment and Finding of No Significant Impact
for License Amendment.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: D. Blair Spitzberg, Ph.D., Chief, Fuel
Cycle and Decommissioning Branch, Division of Nuclear Materials Safety,
Region IV, U.S. Nuclear Regulatory Commission, 611 Ryan Plaza Drive,
Suite 400, Arlington, TX 76011. Telephone: (817) 860-8100; e-mail:
dbs@nrc.gov.
SUPPLEMENTARY INFORMATION:
[[Page 39805]]
I. Introduction
The Department of the Air Force (the licensee) submitted a
decommissioning plan (DP) to the U.S. Nuclear Regulatory Commission
(NRC) by Memorandum dated May 24, 2002. Supplemental information was
provided by Memoranda dated November 1, 2002, August 21, 2003, October
27, 2004, and January 13, 2005. The licensee requested that the DP for
Test Area C-74L at Eglin Air Force Base (AFB) be approved. The NRC is
considering the issuance of an amendment to Master Materials License
42-23539-01AF which will approve the DP. If approved by the NRC, the
licensee will be authorized to conduct decommissioning activities in
accordance with the DP.
The NRC has prepared an Environmental Assessment (EA) in support of
this licensing action in accordance with the requirements of 10 CFR
Part 51. The EA was developed to provide sufficient evidence and
analysis for determining whether to prepare an Environmental Impact
Statement or Finding of No Significant Impact (FONSI). Based on the
results of the EA, the NRC has determined that a FONSI is appropriate.
II. Environmental Assessment
Proposed Action
The proposed action is to approve the DP which will allow the
licensee to conduct decommissioning in accordance with the procedures
and processes provided in the DP. The approval of the DP would be
accomplished by license amendment to NRC Materials License 42-23539-
01AF following the NRC decision that the DP meets the standards
specified in 10 CFR Part 20 and related NRC guidance documents.
The Need for the Proposed Action
The licensee intends to remediate Test Area C-74L and ultimately
remove the site from its license (and the associated AFB radioactive
material permit) because it no longer conducts NRC-licensed activities
at this location. If the site is properly decommissioned, the licensee
would then be in compliance with the Timeliness Rule requirements of 10
CFR 30.36, ``Expiration and Termination of Licenses and Decommissioning
of Sites and Separate Buildings or Outdoor Areas.''
Environmental Impacts of the Proposed Action
Test Area C-74L is located in Walton County, Florida, within the
north-central portion of Eglin AFB. The site is located approximately
14 miles northwest of the city of Niceville, Florida. The test area
lies within Section 11 of Range 21 West, Township 2 North. The test
area currently consists of a 4-acre radiologically controlled area,
fire control/ballistics building, gun corridor, target area, well house
building, drum storage area, and surrounding land.
From late-1974 to 1978, the area was used for pre-production
testing of a gun system which used depleted uranium (DU) ammunition.
The licensee elected to discontinue DU munitions testing at this
location. An estimated 16,315 pounds of DU was expended at the site.
Approximately 9,257 pounds of DU were collected and disposed of during
remediation activities conducted between March 1978 and June 1987. The
remainder of the material has since been remediated, was dispersed or
vaporized as part of DU ordinance testing, or remains onsite and
requires remediation.
The portions of the site that may have been contaminated with DU
fragments include the ballistic building interior, ballistic and well
house building exteriors, target area, 4-acre radiologically restricted
grounds, and two drainage ditches. Previous radiological investigations
included at least six soil sampling events that occurred between 1976-
1999. Limited reclamation activities have been conducted several times
since 1980. A detailed site characterization study was conducted during
1999 followed by additional limited characterization studies during
2000-2001. At that time, the only area remaining to be remediated was
the 4-acre radiologically controlled area.
The ballistic building interior was not expected to contain
radioactive material in measurable quantities, in part, because the
building was not used to store DU munitions. The well house building
was constructed after completion of DU testing although the land
beneath the building was not radiologically surveyed prior to
construction. The exteriors of these two buildings may contain small
amounts of contamination as a result of possible wind dispersion of DU
fragments.
Two drainage ditches are located on site property. Sample results
indicated measurable quantities of radionuclides above background
values. The licensee does not expect to conduct remediation activities
in these ditches because the residual radioactivity is expected to be
at levels below the NRC-approved release criteria.
The radiological criteria for unrestricted use is provided in 10
CFR 20.1402. This regulation states that a site will be considered
acceptable for unrestricted use if the residual radioactivity that is
distinguishable from background radiation results in a total effective
dose equivalent to an average member of the public that does not exceed
25 millirems (0.25 mSv) per year, including that from groundwater
sources of drinking water, and that the residual radioactivity has been
reduced to levels that are as low as reasonably achievable (ALARA).
Current NRC guidance (Section 2.5 of NUREG-1757, Volume 2,
``Consolidated NMSS Decommissioning Guidance'') recommends that
licensees demonstrate compliance with the dose criteria by using dose
modeling or derived concentration guideline levels (DCGLs) and final
status survey results. The licensee's request to release the site for
unrestricted use will be based on use of DCGLs and final status survey
results. In the DP, the licensee proposes DCGLs for building interiors,
building exteriors, equipment, and site soils. Through an internal
review process, the NRC accepted the licensee's proposed building and
equipment DCGLs, but rejected the licensee's proposed soil DCGL. By
Memorandum dated August 21, 2003, the licensee accepted the NRC's
alternate proposal for soil DCGL.
Upon completion of the decommissioning project, the licensee is
expected to submit the final status survey results to the NRC for
review and approval. In addition, the NRC will conduct confirmatory
sampling. If the results of the final status survey and any
confirmatory surveys performed are below the NRC-approved DCGLs, the
site will be found to be in compliance with the annual dose limit
provided in 10 CFR 20.1402. If the surveys indicate that the results
are above the DCGLs, then additional remediation may be necessary.
Alternatively, the licensee will have to conduct an analysis to
demonstrate that the survey results demonstrate compliance with the
dose criteria.
The remediation activities will result in potential exposure of
workers to radioactive material. The primary radionuclide of concern is
uranium-238. The DU is expected to be in the form of solid uranium
oxide or uranium metal fragments. The primary health hazard is
inhalation of DU. The health effects from DU include both chemical and
radiological toxicity with the two important target organs being the
kidneys and the lungs. In general, the health consequences are
determined by the physical and chemical form of the DU as well as the
level and duration of exposure.
[[Page 39806]]
To prevent potential health consequences from exposure to DU, the
licensee has initiated a radiological safety program. External
occupational exposure rates to DU is expected to be minimal based on
previous exposure data. The internal exposure pathways will be
controlled and monitored as necessary by the use of personnel
protective equipment, strict hygiene practices, and air particulate and
bioassay sampling. The licensee's proposed program for control of
exposure to radioactive materials is typical for the type of work being
conducted and is considered acceptable to the NRC to maintain
occupational exposures within NRC limits.
The Air Force, or a contractor for the Air Force, will be
responsible for packaging and transporting the low-level radioactive
wastes. Remediation of the site may have short-term non-radiological
health and safety risks caused by the excavation, packaging, and
shipping of the residual radioactive material. These non-radiological
impacts include the normal risks of exhuming the wastes with earth-
moving equipment and transportation of the material to an out-of-state
disposal facility. The risks include injury or death from a
construction or transportation accident.
There should be minimal risk to members of the public from exposure
to radioactive wastes during transport because the radionuclides of
concern will be dispersed within the soil, contained in authorized
shipping containers, and shipped in accordance with U.S. Department of
Transportation requirements.
The reclaimed material will be transported to an out-of-state low
level radioactive waste disposal facility licensed to accept and
dispose of the wastes. The radiological health risks would be minimal
to the workers of the disposal facility, in part, because the facility
would have a radiation protection program in place to protect its
workers. However, there is still a small risk of an occupational
accident occurring while handling the waste material.
In summary, the combination of the NRC-approved DCGLs, the
licensee's proposed final status survey results, and the NRC's
confirmatory survey results should demonstrate that annual doses to
future occupants of the site will be less than the NRC's radiological
criteria for unrestricted use of the facility. Additional details of
the licensee's radiation safety program and NRC-approved DCGLs will be
provided in the NRC's Safety Analysis Report that will be used to
support the licensing decision. Furthermore, the radiological impacts
of releasing the site for unrestricted use are bounded by the impacts
evaluated in NUREG-1496, ``Generic Environmental Impact Statement in
Support of Rulemaking on Radiological Criteria for License Termination
of NRC-Licensed Nuclear Facilities.''
The proposed action will have a short-term detrimental effect on
the impacted area. The licensee plans to scrap portions of the ground
surface to remove any residual radioactive material. This action will
result in destruction of the cover vegetation and top soil, and may
create airborne dust. In response, the licensee plans to implement a
program that will minimize any long term damage. Dust suppression
methods will be utilized as necessary. The area will be backfilled and
revegetated if scraped.
The site includes two drainage ditches. One ditch is located on the
south side of the property and drains to the south-south east. The
second ditch is located in the northeastern portion of the property and
drains towards the northeast. There are two streams in the vicinity of
Test Area C-74L. Rocky Creek is located about 700 feet (213 meters)
south of the controlled area. A tributary to Rocky Creek is located
about 1800 feet (549 meters) to the west of the site. A small dammed
pond is located within the western tributary. The groundwater flow is
anticipated to have a southward component towards Rocky Creek.
Therefore, the remediation of the site has the potential for impacting
the wildlife habitat in and around Rocky Creek.
The NRC consulted with the U.S. Fish & Wildlife Service because the
reclamation of the site could have an impact on the habitat of a
endangered species, the Okaloosa darter. Okaloosa darters are found
only in the Choctawhatchee Bay drainage in Florida, where they inhabit
vegetated sand runs of clear creeks. According to the U.S. Fish &
Wildlife Service, approximately 90 percent of the watershed drainage
area in which the Okaloosa darter occurs is under the management of
Eglin AFB.
To protect the darter's habitat, the licensee has taken or plans to
take several actions. First, an earthen berm currently exists on the
southern portion of the radiologically restricted area. This berm is
expected to help prevent contaminated soil from leaving the controlled
area. Silt fencing will be used as necessary to supplement the berm.
Manual remediation of areas of elevated activities in lieu of heavy
equipment will help reduce the need for mechanical removal of the top
six inches of soil in some areas. Dust suppression methods, including
water trucks, will be utilized as necessary to prevent the spread of
windblown contamination during reclamation. A decontamination pad will
be used as necessary to decontaminate equipment. The licensee believes
that light rain will percolate into the ground, although heavy rains
may transport some soil material into the two drainage ditches. Scraped
surface areas will be covered with plastic sheeting as necessary until
backfilled.
With respect to other potentially endangered or threatened species,
the licensee claims that the indigo snake has been seen in the vicinity
of Test Area C-74L but does not live within the radiologically
controlled area. Reclamation activities are not expected to adversely
impact the habitat of the indigo snake on Eglin AFB ranges. Further,
the licensee claims that there are no red cockaded woodpecker colonies
within Test Area C-74L. The U.S. Fish and Wildlife Service ultimately
decided that the proposed action (reclamation of the site) was not
likely to adversely affect resources protected by the Endangered
Species Act of 1973, as amended. This conclusion was reported to the
NRC by letter dated February 25, 2004.
The surficial groundwater is about 50-60 feet (15-18 meters) below
land surface. Geologic literature indicates that the surficial aquifer
beneath the site extends to approximately 125 feet (38 meters) below
land surface. The Pensacola Clay separates the surficial aquifer from
the underlying Floridian aquifer system. The Pensacola Clay layer is
about 160 feet (49 meters) thick, meaning that the drinking water
aquifer is no less than 285 feet (87 meters) below the land surface.
The hydraulically impenetrable Pensacola Clay layer would be expected
to prevent any contamination that might be present in the surficial
groundwater from reaching the Floridian aquifer system even if the
surficial groundwater was contaminated with DU.
The licensee has conducted site characterization studies and
concluded that the land surface contamination of DU has not impacted
the groundwater. Most contamination is found within the first 6 inches
(15 centimeters) of soil except in selected locations. In these
discrete locations, contamination is no more than 4 feet (1.2 meters)
below the land surface. There are two drinking water wells in the
vicinity of the site. One is located onsite and is 644 feet (196
meters) deep. The second is located a half-mile (0.8 kilometers) away
and
[[Page 39807]]
has been permanently abandoned. The onsite drinking water well was
sampled during 1983, and the sample result indicated no measurable
quantities of radioactive materials above background values. Because
the surficial groundwater is located 50-60 feet (15-18 meters) below
surface, and the drinking water aquifer is located at least 285 feet
(87 meters) below surface, the NRC concluded that the probability that
DU contamination has impacted either the surficial or drinking water
aquifer is highly unlikely.
Environmental Impacts of the Alternatives to the Proposed Action
The licensee seeks NRC approval of the DP. The alternatives to the
proposed action are: (1) The no-action alternative, or (2) to deny the
amendment request and require the licensee to take some alternate
action.
1. No-Action Alternative
One alternative available to the NRC is to take no action by
denying the amendment request. Denial of the DP submittal would result
in no change in current environmental conditions. The no-action
alternative is not a feasible alternative because it will result in
violation of the NRC's Timeliness Rule (10 CFR 30.36), which requires
licensees to decommission their facilities when licensed activities
cease.
2. Environmental Impacts of Alternative 2
A second alternative is to deny the licensee's request in favor of
alternate release criteria as allowed by Sec. 20.1403 (criteria for
restricted conditions) or Sec. 20.1404 (alternate criteria). However,
the NRC's analysis confirmed that the proposed action (approval of the
DP as submitted) meets the license termination requirements of Sec.
20.1402. Accordingly, the NRC has determined that the second
alternative is not reasonable. Therefore, this alternative action is
eliminated from further consideration in this EA.
Conclusion
Based on its review, the NRC staff has concluded that the
environmental impacts associated with the proposed action do not
warrant denial of the license amendment request. The NRC staff believes
that the proposed action will result in minimal environmental impacts,
including those to endangered species and critical habitats. The staff
has determined that the proposed action, approval of the DP, is the
appropriate alternative for selection.
Agencies and Persons Contacted
The NRC staff consulted with both the Florida State Historic
Preservation Officer and the local U.S. Fish & Wildlife Service office.
The Florida Department of State, Division of Historical Resources
stated that no historic properties were known to exist in the area;
therefore, the proposed decommissioning will have no effect on historic
properties. The U.S. Fish & Wildlife Service has informed the NRC that
the proposed action (site reclamation) is not likely to adversely
affect protected resources including endangered species and critical
habitats. The NRC staff also consulted with the Florida Department of
Health, Bureau of Radiation Control. By letter dated May 19, 2005, the
State responded that it had no objections to the proposed EA and FONSI.
III. Finding of No Significant Impact
The NRC staff has concluded that the proposed action (amend the Air
Force's license to approve the DP) complies with both the Timeliness
Rule requirements of 10 CFR 30.36 and License Termination Rule
requirements of 10 CFR 20.1402. On the basis of this EA, the NRC has
concluded that there are no significant environmental impacts and the
license amendment does not warrant the preparation of an Environmental
Impact Statement. Accordingly, it has been determined that a Finding of
No Significant Impact is appropriate.
IV. Further Information
A copy of this document will be available electronically for public
inspection in the NRC Public Document Room or from the Publicly
Available Records (PARS) component of the NRC's document system. 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 following references are available for inspection
at NRC's Public Electronic Reading Room at https://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room). ADAMS accession
numbers are located in parentheses following the reference.
1. NRC, ``Generic Environmental Impact Statement in Support of
Rulemaking on Radiological Criteria for License Termination of NRC-
Licensed Nuclear Facilities,'' NUREG-1496, July 1997 (ML042310492).
2. Pugh, Capt. David L., Department of the Air Force Memorandum,
``Review of Decommissioning Plan for Eglin AFB, Florida,'' May 24,
2002 (ML021970666, ML021970669, ML021980188, ML021980239,
ML021990724, ML021990330, ML021990377, ML021990737, ML021990743).
3. Pugh, Capt. David L., Department of the Air Force Memorandum,
``Clarification Request For C-74L Decommissioning Plan,'' November
1, 2002 (ML023370482, ML023370535, ML023370648, ML023370660,
ML023370675, ML023380282, ML023380332).
4. Brockman, Ken E., NRC Letter to Air Force, ``Acknowledgment
of Receipt of Decommissioning Plan,'' November 25, 2002
(ML023290265).
5. Spitzberg, D. Blair, NRC Memorandum, ``Notice of
Consideration of Amendment Request for Department of the Air Force,
Eglin Air Force Base, Florida, and Opportunity for Providing
Comments and Requesting a Hearing,'' January 27, 2003 (ML030270180).
6. Brockman, Ken E., NRC Memorandum, ``Regional Technical
Assistance Request Form,'' January 29, 2003 (ML030300253).
7. Cain, Charles L., ``NRC Inspection Report 030-28641/2003-
01,'' February 11, 2003 (ML030420534).
8. Kokajko, Lawrence E., NRC Memorandum, ``Review of Derived
Concentration Guideline Levels (DCGLs) for Eglin Air Force Base,''
April 10, 2003 (ML031000111).
9. Cain, Charles L., NRC Letter to Air Force, ``Request for
Additional Information Regarding Eglin Air Force Base
Decommissioning Plan,'' April 24, 2003 (ML031140240).
10. Spitzberg, D. Blair, NRC Letter to U.S. Fish & Wildlife
Service, ``Request for Comments Regarding Endangered/Threatened
Species and Critical Habitats,'' June 9, 2003 (ML031600579).
11. Spitzberg, D. Blair, NRC Letter to Florida State Historic
Preservation Officer, ``Request for Comments Regarding Cultural and
Historical Resources at Eglin Air Force Base,'' June 9, 2003
(ML031600613).
12. Carmody, Gail A., U.S. Fish & Wildlife Service Letter to
NRC, ``Reclamation and Decommissioning Uranium Munitions Site, Area
C-74L,'' July 7, 2003 (ML031920346).
13. Matthews, Janet Snyder, Florida Department of State Letter
to NRC, ``Reclamation Activities Within a Four-Acre Property at Test
Area C-74L, Walton County,'' July 8, 2003 (ML032050604).
14. NRC, NUREG-1748, ``Environmental Review Guidance for
Licensing Actions Associated With NMSS Programs,'' July 2003
(ML032540811).
15. Mather, Lt. Col. Kali K., Air Force Memorandum to NRC,
``Supplement to the Decommissioning Plan for Test Area C-74L, Eglin
AFB, FL,'' August 21, 2003 (ML032450123).
16. NRC, NUREG-1757, ``Consolidated NMSS Decommissioning
Guidance,'' Volumes 1-3, September 2003 (ML032530410, ML032530405,
ML032471471).
17. Seiber, Stephen M., Air Force Letter to NRC, ``No Effect
Determination,'' February 11, 2004 (ML040430157).
18. Spitzberg, D. Blair, NRC letter to U.S. Fish & Wildlife
Services, ``Request for Comments Regarding Department of Air Force's
Determination of No Effect,'' February 18, 2004 (ML040690296).
[[Page 39808]]
19. Carmody, Gail A., U.S. Fish & Wildlife Service's Response to
NRC's Letter ``Request for Comments Regarding Department of Air
Force's Determination of No Effect,'' February 25, 2004
(ML040690296).
20. Whitten, Jack E., NRC Letter to Air Force, ``Request for
Additional Information Regarding Eglin Air Force Base
Decommissioning Plan,'' February 19, 2004 (ML040500864).
21. Whitten, Jack E., ``NRC Inspection Report 030-28641/04-
001,'' February 25, 2004 (ML040570122).
22. Abell, Capt. Clint E., Air Force Memorandum to NRC,
``Decommissioning Plan for Test Area C-74L, Eglin AFB, Florida,''
October 27, 2004 (ML043410237).
23. Abell, Capt. Clint E., Air Force Memorandum to NRC,
``Response to NRC Query of Decommissioning of Test Area C-74L, Eglin
Air Force Base, Florida,'' January 13, 2005 (ML050320251).
24. Passetti, William A., Florida Department of Health Letter to
NRC, ``Environmental Assessment for Decommissioning of Test Area C-
74L at Eglin Air Force Base,'' May 19, 2005 (ML051640567).
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 (800) 397-4209, (301) 415-4737
or by e-mail to pdr@nrc.gov. 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 Arlington, Texas this 28th day of June, 2005.
For the Nuclear Regulatory Commission.
D. Blair Spitzberg,
Chief, Fuel Cycle & Decommissioning Branch, Division of Nuclear
Materials Safety, Region IV.
[FR Doc. E5-3629 Filed 7-8-05; 8:45 am]
BILLING CODE 7590-01-P
