PPL Susquehanna, LLC; Independent Spent Fuel Storage Installation; Environmental Assessment and Finding of No Significant Impact, 18367-18369 [06-3416]
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18367
Federal Register / Vol. 71, No. 69 / Tuesday, April 11, 2006 / Notices
you can access the NRC’’s Agencywide
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this notice are: Environmental
Assessment [ML060820173]; Request for
Amendment dated August 19, 2005
[ML060550247]; NRC’s request for
additional information dated September
28, 2005 [ML052720490]; and Final
Status Survey Results dated November
7, 2005 [ML060550248]. If you do not
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Dated at King of Prussia, Pennsylvania this
23rd day of March, 2006.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region 1.
[FR Doc. E6–5261 Filed 4–10–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–28]
PPL Susquehanna, LLC; Independent
Spent Fuel Storage Installation;
Environmental Assessment and
Finding of No Significant Impact
Nuclear Regulatory
Commission.
ACTION: Issuance of an environmental
assessment and Finding of No
Significant Impact.
wwhite on PROD1PC61 with NOTICES
AGENCY:
FOR FURTHER INFORMATION CONTACT:
Joseph M. Sebrosky, Senior Project
Manager, Spent Fuel Project Office,
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19:37 Apr 10, 2006
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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.
The U.S.
Nuclear Regulatory Commission (NRC
or Commission) is considering issuance
of an exemption to PPL Susquehanna,
LLC (PPL) pursuant to 10 CFR 72.7,
from specific provisions of 10 CFR
72.212(a)(2), 72.212(b)(2)(i)(A),
72.212(b)(7), and 72.214. The licensee
wants to use the Transnuclear, Inc. (TN)
NUHOMS Storage System, Certificate
of Compliance No. 1004 (CoC or
Certificate) Amendment No. 8 (61BT dry
shielded canister), to store spent nuclear
fuel under a general license in an
Independent Spent Fuel Storage
Installation (ISFSI) associated with the
operation of the Susquehanna Steam
Electric Station (SSES), Units 1 and 2,
located in Luzerne County,
Pennsylvania. PPL is requesting an
exemption from CoC No. 1004 to allow
loading of Framatome ANP 9x9–2 fuel
assemblies in the NUHOMS–61BT dry
shielded canister (DSC).
SUPPLEMENTARY INFORMATION:
Environmental Assessment (EA)
Identification of Proposed Action: The
proposed action would exempt PPL
from the requirements of 10 CFR
72.212(a)(2), 72.212(b)(2)(i)(A),
72.212(b)(7), and 72.214 and enable PPL
to use the TN NUHOMS–61BT DSC
with modifications at SSES. These
regulations specifically require storage
in casks approved under the provisions
of 10 CFR part 72 and compliance with
the conditions set forth in the CoC for
each dry spent fuel storage cask used by
an ISFSI general licensee. The TN
NUHOMS CoC provides requirements,
conditions, and operating limits in
Attachment A, Technical Specifications.
The proposed action would exempt PPL
from the requirements of 10 CFR
72.212(a)(2), 10 CFR 72.212(b)(7) and 10
CFR 72.214 from a condition in
Amendment 8 to CoC No. 1004 so that
Framatome ANP 9x9–2 fuel assemblies
can be loaded in a NUHOMS–61BT
DSC. Specifically, the exemption would
be from CoC No. 1004 Attachment A,
Technical Specification, Table 1–1d,
‘‘BWR Fuel Assembly Design
Characteristics for the NUHOMS–61BT
DSC,’’ which allows for the storage of
General Electric (or equivalent) 9x9–2
fuel assemblies that contain 66 full and
8 partial fuel rods. The exemption
would allow PPL to store Framatome
ANP 9x9—2 fuel assemblies that
contain 79 full fuel rods and no partial
fuel rods in the NUHOMS–61BT DSC.
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Fmt 4703
Sfmt 4703
PPL committed in its January 31,
2006, submittal to a maximum decay
heat load per fuel assembly of 210 watts.
This is less than the CoC No. 1004
Attachment A, Technical Specification,
Table 1–1c maximum decay heat limit
of 300 watts per assembly. In addition,
in its March 6, 2006, supplement PPL
provided the parameters found in Table
1 below associated with the Framatome
ANP 9x9–2 fuel assembly.
TABLE 1.—PARAMETERS FOR
FRAMATOME ANP 9X9–2 FUEL ASSEMBLY
Manufacturer .............
Version ......................
Number of Fuel Rods
per Assembly.
Fuel Pellet Outside
Diameter (inches).
Clad Outside Diameter (inches).
Water Rod Inside Diameter (inches).
Array ..........................
Active Fuel Length
(inches).
Pitch (inches) ............
Clad Thickness
(inches).
Water Rod Outside
Diameter (inches).
Framatome ANP.
FANP9.
79 full.
0.3565.
0.424.
0.364.
9x9.
150.
0.572.
0.030.
0.425.
The NRC has determined that the
exemption, if granted, will contain the
following 3 conditions:
(1) PPL will be limited to loading a
total of five 61BT DSCs under this
exemption if granted,
(2) PPL shall limit the decay heat
level per fuel assembly to 210 watts to
ensure cask loadings are bounded by the
analyses supporting TN CoC No. 1004,
Amendment No. 8., and (3) the
exemption will pertain only to
Framatome ANP 9x9 –2 fuel assemblies
that meet the nominal un-irradiated
design parameters contained in Table 1
above.
The proposed action is in accordance
with the licensee’s request for
exemption dated January 31, 2006, as
supplemented March 6, 2006.
Need for the Proposed Action: The
proposed action is needed because SSES
will lose full core offload capability in
December 2006 following the receipt
and staging of new fuel for the
scheduled 2007 Unit 2 refueling outage.
PPL has determined that it is necessary
to start the dry fuel storage (DFS)
campaign in May 2006 to ensure full
core offload capability. PPL had
originally scheduled a DFS campaign to
begin in October of 2006. However,
because of recent SSES Unit 1 fuel
channel performance problems, 54 fuel
channels were replaced and stored in
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18368
Federal Register / Vol. 71, No. 69 / Tuesday, April 11, 2006 / Notices
the spent fuel pool. As a result of this
fuel channel problem, a possible Unit 2
mid-cycle maintenance outage may be
necessary to inspect and replace, if
necessary, any affected fuel channels.
This mid-cycle outage is tentatively
scheduled for the Fall of 2006 and
access to the spent fuel pool is needed
to store fuel channels that are replaced.
This activity would conflict with
loading dry fuel storage casks. There is
also a conflict with performing the DFS
campaign in the Summer of 2006.
Specifically, PPL has contracted to
perform a spent fuel pool cleanout
beginning in June 2006 so adequate pool
space is restored to support the Unit 2
2007 refueling outage. The DFS
campaign and the spent fuel pool
cleanout campaign cannot occur
simultaneously. Rescheduling the spent
fuel cleanout campaign for later in the
year is difficult. In summary, space
available in the spent fuel pool has
become limited much sooner than
anticipated, and PPL is requesting the
exemption to support a DFS campaign
in May 2006. A DFS campaign in May
2006 will also allow PPL flexibility for
fuel storage options related to managing
decay heat loads within the spent fuel
pool.
The proposed action is necessary
because the NRC has not yet received an
amendment to CoC No. 1004 to allow
loading of a Framatome ANP 9x9–2 in
a NUHOMS 61BT DSC. The staff
would have to review such an
amendment request and only after
making the appropriate findings would
the staff initiate 10 CFR 72.214
rulemaking to implement the change.
This process typically takes at least 10
months from the receipt of the
amendment request for simple license
amendments. Complex license
amendments can take over 30 months.
Therefore, an amendment to allow
loading of Framatome ANP 9x9–2 fuel
assemblies in the NUHOMS -61BT
DSC can not be completed in time to
support PPL’s stated needs.
Environmental Impacts of the
Proposed Action: The NRC has
completed its evaluation of the
proposed action and concludes that
there will be no significant
environmental impact if the exemption
is granted. The staff has determined that
the proposed action would not endanger
life or property. The potential
environmental impact of using the
NUHOMS system was initially
presented in the Environmental
Assessment (EA) for the Final Rule to
add the TN Standardized NUHOMS
Horizontal Modular Storage System for
Irradiated Nuclear Fuel to the list of
approved spent fuel storage casks in 10
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19:37 Apr 10, 2006
Jkt 208001
CFR 72.214 (59 FR 65898, dated
December 22, 1994). The potential
environmental impact of using the
NUHOMS -61BT DSC was initially
presented in the Environmental
Assessment (EA) for the Final Rule to
add the 61BT DSC to the Standardized
NUHOMS system, Amendment No. 3
(66 FR 34523, dated June 29, 2001).
The staff performed a safety
evaluation of the proposed exemption.
The staff has determined that the
Framatome ANP 9x9–2 assemblies,
which PPL plans to load into the 61BT
DSC are bounded by the design basis
fuel assemblies for the 61BT DSC
previously evaluated by the staff. The
staff’s thermal safety evaluation review
notes that PPL committed to only
loading Framatome ANP 9x9–2 fuel
assemblies with a maximum decay heat
load per assembly of 210 watts. This is
less than the CoC No. 1004 Attachment
A, Technical Specification, Table 1–1c
maximum decay heat limit of 300 watts
per assembly and is therefore bounding.
In the criticality area, the staff evaluated
the criticality code and the selected
cross sectional data that were used by
PPL and determined that they were
sufficiently documented and validated,
and that they are appropriate for the
Framatome 9x9–2 fuel assembly. The
staff also performed independent
confirmatory criticality calculations for
normal conditions of storage and
transfer based on the parameters for the
Framatome ANP 9x9–2 fuel assembly
identified in Table 1 above. Based on its
review of the representations and
information supplied by the applicant,
and the confirmatory analyses
performed by staff, the staff concludes
that the nuclear criticality safety design
has been adequately described and
evaluated by the applicant, and finds
reasonable assurance that the
Framatome ANP 9x9–2 fuel meets the
criticality safety requirements of 10 CFR
part 72.
The loading of Framatome ANP 9x9–
2 fuel assemblies in the NUHOMS
61BT DSC does not increase the
probability or consequences of
accidents, no changes are being made in
the types of any effluents that may be
released offsite, and there is no
significant increase in occupational or
public radiation exposure. Therefore,
there are no significant radiological
environmental impacts associated with
the proposed action.
The exemption only affects the
requirements associated with the fuel
assemblies that can be loaded in the
casks and does not affect nonradiological plant effluents or any other
aspects of the environment. Therefore,
there are no significant non-radiological
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Sfmt 4703
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:
Because there is no significant
environmental impact associated with
the proposed action, alternatives with
equal or greater environmental impact
were not evaluated. As an alternative to
the proposed action, the staff considered
denial of the proposed action. Denial of
the exemption would result in no
change in the current environmental
impact.
Agencies and Persons Consulted: This
exemption request was discussed with
Mr. Brad Fuller of the Pennsylvania
Department of Environmental Protection
Bureau of Radiation Protection on
March 6, 2006. He stated that the State
had no comments on the technical
aspects of the exemption. The NRC staff
has determined that a consultation
under Section 7 of the Endangered
Species Act is not required because the
proposed action 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 further
consultation is required under Section
106 of the National Historic
Preservation Act.
Conclusion: The staff has reviewed
the exemption request submitted by
PPL. Allowing loading of Framatome
9x9–2 fuel assemblies in the NUHOMS
61BT DSC 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 Environmental Assessment,
the Commission finds that the proposed
action of granting the exemption from
specific provisions of 10 CFR
72.212(a)(2), 72.212(b)(2)(i)(A),
72.212(b)(7), and 10 CFR 72.214, to
allow PPL to load of Framatome ANP
9x9–2 fuel assemblies in the NUHOMS
61BT DSC, subject to conditions, will
not significantly impact the quality of
the human environment. Accordingly,
the Commission has determined that an
environmental impact statement for the
proposed exemption is not warranted.
In accordance with 10 CFR 2.390 of
NRC’s ‘‘Rules of Practice,’’ final NRC
records and documents regarding this
proposed action are publically available
in the records component of NRC’s
Agencywide Documents Access and
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Federal Register / Vol. 71, No. 69 / Tuesday, April 11, 2006 / Notices
Management System (ADAMS). The
request for exemption dated January 31,
2006, and March 6, 2006, was docketed
under 10 CFR part 72, Docket No. 72–
28. These documents may be inspected
at NRC’s Public Electronic Reading
Room at https://www.nrc.gov/readingrm/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 31st day
of March, 2006.
For the Nuclear Regulatory Commission.
Joseph M. Sebrosky,
Senior Project Manager, Spent Fuel Project
Office, Office of Nuclear Material Safety and
Safeguards.
[FR Doc. 06–3416 Filed 4–10–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 52–009]
wwhite on PROD1PC61 with NOTICES
System Energy Resources, Inc. Notice
of Availability of the Final
Environmental Impact Statement for an
Early Site Permit (ESP) at the Grand
Gulf ESP Site
Notice is hereby given that the U.S.
Nuclear Regulatory Commission (NRC
or the Commission) has published
NUREG–1817, ‘‘Environmental Impact
Statement for an Early Site Permit (ESP)
at the Grand Gulf ESP Site—Final
Report.’’ The site is located near the
Town of Port Gibson in Claiborne
County, Mississippi. The application for
the ESP was submitted by letter dated
October 16, 2003, pursuant to Title 10
of the Code of Federal Regulations Part
52 (10 CFR Part 52). A notice of receipt
and availability of the application,
which included the environmental
report (ER), was published in the
Federal Register on November 14, 2003
(68 FR 64665). A notice of acceptance
for docketing of the application for the
ESP was published in the Federal
Register on December 1, 2003 (68 FR
67219). A notice of intent to prepare an
environmental impact statement (EIS)
and to conduct the scoping process was
published in the Federal Register on
December 31, 2003 (68 FR 75656). A
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19:37 Apr 10, 2006
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notice of availability of the draft EIS was
published in the Federal Register on
April 28, 2005 (70 FR 22155).
The purpose of this notice is to inform
the public that NUREG–1817,
‘‘Environmental Impact Statement for an
Early Site Permit (ESP) at the Grand
Gulf ESP Site—Final Report,’’ is
available for public inspection in the
NRC Public Document Room (PDR)
located at One White Flint North, 11555
Rockville Pike (first floor), Rockville,
Maryland, 20852, or from the Publicly
Available Records (PARS) component of
NRC’s Agencywide Documents Access
and Management System (ADAMS), and
will also be placed directly on the NRC
Web site at https://www.nrc.gov. ADAMS
is accessible from the NRC Web site at
https://www.nrc.gov/reading-rm/
adams.html (the Public Electronic
Reading Room). Persons who do not
have access to ADAMS, or who
encounter problems in accessing the
documents located in ADAMS, should
contact the PDR reference staff at
1–800–397–4209, 301–415–4737, or by
e-mail to pdr@nrc.gov. In addition,
the Harriette Person Memorial Library,
located at 606 Main Street, Port Gibson,
Mississippi, has agreed to make the final
EIS available for public inspection.
FOR FURTHER INFORMATION CONTACT:
James H. Wilson, Environmental Branch
A, Division of License Renewal, U.S.
Nuclear Regulatory Commission,
Washington, DC, 20555–0001. Mr.
Wilson may be contacted by telephone
at 301–415–1108 or by e-mail at
jhw1@nrc.gov.
18369
Accelerator-Produced Radioactive
Materials in 10 CFR Part 35; (2) RIS on
Visitor Dose Limits; (3) Part 35, Training
and Experience; (4) Supply of High
Enriched Uranium for Molybdenum-99
Generation; (5) Training and Experience
for Use of Microspheres for Therapy; (6)
ACMUI Review of Medical Events
Involving I–131. To review the agenda
see: https://www.nrc.gov/reading-rm/
doc-collections/acmui/agenda/ or
contact, via e-mail: mss@nrc.gov.
Purpose: Discuss issues related to 10
CFR 35, Medical Use of Byproduct
Material.
Date and Time for Closed Session
Meeting: April 25, 2006, from 8 a.m. to
10:15 a.m. This session will be closed so
that NRC staff can brief the ACMUI on
information relating solely to internal
personnel rules and can discuss
protected information of an
investigatory nature. Time may be
added to the closed session or an
additional closed session may be added
as needed.
Dates and Times for Public Meetings:
April 25, 2006, from 10:30 a.m. to 5
p.m.; and April 26, 2006, from 8 a.m. to
11:30 a.m.
ADDRESSES: Address for Public
Meetings: The meeting will be held at
National Institute of Health (NIH). The
address and room number is below:
National Institute of Health, Natcher
Conference Center, 45 Center Drive,
Bethesda, MD 20892.
April 25—Balcony B.
April 26—Room E1/E2.
AGENCY:
Security on the NIH Campus
All non-NIH employees are required
to provide picture IDs upon entering the
campus whether walking on to campus
or driving on to campus, and all
belongings are subject to searches.
Increased security procedures are in
place at all entrances to the NIH
campus, including drive-in and walk-in
access gates. Please allow adequate time
when making your plans to attend the
conference functions at the Natcher
Conference Center. Preregistration will
expedite the security process. Visitor
parking is extremely limited and driving
to the NIH campus for this event is not
recommended.
SUMMARY: The U.S. Nuclear Regulatory
Commission will convene a meeting of
the Advisory Committee on the Medical
Uses of Isotopes (ACMUI) on April 25
and 26, 2006. A sample of agenda items
to be discussed during the public
sessions includes: (1) Updates on
Proposed Regulations to Include
Discrete Radium Sources and
Metrorail Service and Map
The NIH Campus is very accessible by
the Washington D.C. area Metrorail
(Metro) system. The Natcher Conference
Center (Building 45) is located a short
walk from the Medical Center Metro
stop located on the Red Line. Note the
signs and directions to the gated campus
security entrance located behind the
metro stop. For more details about the
Washington DC area Metrorail services
Dated at Rockville, Maryland, this 3rd day
of April 2006.
For the Nuclear Regulatory Commission
Frank P. Gillespie,
Director, Division of License Renewal, Office
of Nuclear Reactor Regulation.
[FR Doc. E6–5256 Filed 4–10–06; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on the Medical
Uses of Isotopes: Meeting Notice
Nuclear Regulatory
Commission.
ACTION: Updated notice of meeting.
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]]>Agencies
[Federal Register Volume 71, Number 69 (Tuesday, April 11, 2006)]
[Notices]
[Pages 18367-18369]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 06-3416]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 72-28]
PPL Susquehanna, LLC; Independent Spent Fuel Storage
Installation; Environmental Assessment and Finding of No Significant
Impact
AGENCY: Nuclear Regulatory Commission.
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 Commission) is considering issuance of an exemption to PPL
Susquehanna, LLC (PPL) pursuant to 10 CFR 72.7, from specific
provisions of 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A), 72.212(b)(7),
and 72.214. The licensee wants to use the Transnuclear, Inc. (TN)
NUHOMS[supreg] Storage System, Certificate of Compliance No. 1004 (CoC
or Certificate) Amendment No. 8 (61BT dry shielded canister), to store
spent nuclear fuel under a general license in an Independent Spent Fuel
Storage Installation (ISFSI) associated with the operation of the
Susquehanna Steam Electric Station (SSES), Units 1 and 2, located in
Luzerne County, Pennsylvania. PPL is requesting an exemption from CoC
No. 1004 to allow loading of Framatome ANP 9x9-2 fuel assemblies in the
NUHOMS[supreg]-61BT dry shielded canister (DSC).
Environmental Assessment (EA)
Identification of Proposed Action: The proposed action would exempt
PPL from the requirements of 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A),
72.212(b)(7), and 72.214 and enable PPL to use the TN NUHOMS[supreg]-
61BT DSC with modifications at SSES. These regulations specifically
require storage in casks approved under the provisions of 10 CFR part
72 and compliance with the conditions set forth in the CoC for each dry
spent fuel storage cask used by an ISFSI general licensee. The TN
NUHOMS[supreg] CoC provides requirements, conditions, and operating
limits in Attachment A, Technical Specifications. The proposed action
would exempt PPL from the requirements of 10 CFR 72.212(a)(2), 10 CFR
72.212(b)(7) and 10 CFR 72.214 from a condition in Amendment 8 to CoC
No. 1004 so that Framatome ANP 9x9-2 fuel assemblies can be loaded in a
NUHOMS[supreg]-61BT DSC. Specifically, the exemption would be from CoC
No. 1004 Attachment A, Technical Specification, Table 1-1d, ``BWR Fuel
Assembly Design Characteristics for the NUHOMS[supreg]-61BT DSC,''
which allows for the storage of General Electric (or equivalent) 9x9-2
fuel assemblies that contain 66 full and 8 partial fuel rods. The
exemption would allow PPL to store Framatome ANP 9x9--2 fuel assemblies
that contain 79 full fuel rods and no partial fuel rods in the
NUHOMS[supreg]-61BT DSC.
PPL committed in its January 31, 2006, submittal to a maximum decay
heat load per fuel assembly of 210 watts. This is less than the CoC No.
1004 Attachment A, Technical Specification, Table 1-1c maximum decay
heat limit of 300 watts per assembly. In addition, in its March 6,
2006, supplement PPL provided the parameters found in Table 1 below
associated with the Framatome ANP 9x9-2 fuel assembly.
Table 1.--Parameters for Framatome ANP 9x9-2 Fuel Assembly
------------------------------------------------------------------------
------------------------------------------------------------------------
Manufacturer.............................. Framatome ANP.
Version................................... FANP9.
Number of Fuel Rods per Assembly.......... 79 full.
Fuel Pellet Outside Diameter (inches)..... 0.3565.
Clad Outside Diameter (inches)............ 0.424.
Water Rod Inside Diameter (inches)........ 0.364.
Array..................................... 9x9.
Active Fuel Length (inches)............... 150.
Pitch (inches)............................ 0.572.
Clad Thickness (inches)................... 0.030.
Water Rod Outside Diameter (inches)....... 0.425.
------------------------------------------------------------------------
The NRC has determined that the exemption, if granted, will contain
the following 3 conditions:
(1) PPL will be limited to loading a total of five 61BT DSCs under
this exemption if granted,
(2) PPL shall limit the decay heat level per fuel assembly to 210
watts to ensure cask loadings are bounded by the analyses supporting TN
CoC No. 1004, Amendment No. 8., and (3) the exemption will pertain only
to Framatome ANP 9x9 -2 fuel assemblies that meet the nominal un-
irradiated design parameters contained in Table 1 above.
The proposed action is in accordance with the licensee's request
for exemption dated January 31, 2006, as supplemented March 6, 2006.
Need for the Proposed Action: The proposed action is needed because
SSES will lose full core offload capability in December 2006 following
the receipt and staging of new fuel for the scheduled 2007 Unit 2
refueling outage. PPL has determined that it is necessary to start the
dry fuel storage (DFS) campaign in May 2006 to ensure full core offload
capability. PPL had originally scheduled a DFS campaign to begin in
October of 2006. However, because of recent SSES Unit 1 fuel channel
performance problems, 54 fuel channels were replaced and stored in
[[Page 18368]]
the spent fuel pool. As a result of this fuel channel problem, a
possible Unit 2 mid-cycle maintenance outage may be necessary to
inspect and replace, if necessary, any affected fuel channels. This
mid-cycle outage is tentatively scheduled for the Fall of 2006 and
access to the spent fuel pool is needed to store fuel channels that are
replaced. This activity would conflict with loading dry fuel storage
casks. There is also a conflict with performing the DFS campaign in the
Summer of 2006. Specifically, PPL has contracted to perform a spent
fuel pool cleanout beginning in June 2006 so adequate pool space is
restored to support the Unit 2 2007 refueling outage. The DFS campaign
and the spent fuel pool cleanout campaign cannot occur simultaneously.
Rescheduling the spent fuel cleanout campaign for later in the year is
difficult. In summary, space available in the spent fuel pool has
become limited much sooner than anticipated, and PPL is requesting the
exemption to support a DFS campaign in May 2006. A DFS campaign in May
2006 will also allow PPL flexibility for fuel storage options related
to managing decay heat loads within the spent fuel pool.
The proposed action is necessary because the NRC has not yet
received an amendment to CoC No. 1004 to allow loading of a Framatome
ANP 9x9-2 in a NUHOMS[supreg] 61BT DSC. The staff would have to review
such an amendment request and only after making the appropriate
findings would the staff initiate 10 CFR 72.214 rulemaking to implement
the change. This process typically takes at least 10 months from the
receipt of the amendment request for simple license amendments. Complex
license amendments can take over 30 months. Therefore, an amendment to
allow loading of Framatome ANP 9x9-2 fuel assemblies in the
NUHOMS[supreg] -61BT DSC can not be completed in time to support PPL's
stated needs.
Environmental Impacts of the Proposed Action: The NRC has completed
its evaluation of the proposed action and concludes that there will be
no significant environmental impact if the exemption is granted. The
staff has determined that the proposed action would not endanger life
or property. The potential environmental impact of using the
NUHOMS[supreg] system was initially presented in the Environmental
Assessment (EA) for the Final Rule to add the TN Standardized
NUHOMS[supreg] Horizontal Modular Storage System for Irradiated Nuclear
Fuel to the list of approved spent fuel storage casks in 10 CFR 72.214
(59 FR 65898, dated December 22, 1994). The potential environmental
impact of using the NUHOMS[supreg] -61BT DSC was initially presented in
the Environmental Assessment (EA) for the Final Rule to add the 61BT
DSC to the Standardized NUHOMS[supreg] system, Amendment No. 3 (66 FR
34523, dated June 29, 2001).
The staff performed a safety evaluation of the proposed exemption.
The staff has determined that the Framatome ANP 9x9-2 assemblies, which
PPL plans to load into the 61BT DSC are bounded by the design basis
fuel assemblies for the 61BT DSC previously evaluated by the staff. The
staff's thermal safety evaluation review notes that PPL committed to
only loading Framatome ANP 9x9-2 fuel assemblies with a maximum decay
heat load per assembly of 210 watts. This is less than the CoC No. 1004
Attachment A, Technical Specification, Table 1-1c maximum decay heat
limit of 300 watts per assembly and is therefore bounding. In the
criticality area, the staff evaluated the criticality code and the
selected cross sectional data that were used by PPL and determined that
they were sufficiently documented and validated, and that they are
appropriate for the Framatome 9x9-2 fuel assembly. The staff also
performed independent confirmatory criticality calculations for normal
conditions of storage and transfer based on the parameters for the
Framatome ANP 9x9-2 fuel assembly identified in Table 1 above. Based on
its review of the representations and information supplied by the
applicant, and the confirmatory analyses performed by staff, the staff
concludes that the nuclear criticality safety design has been
adequately described and evaluated by the applicant, and finds
reasonable assurance that the Framatome ANP 9x9-2 fuel meets the
criticality safety requirements of 10 CFR part 72.
The loading of Framatome ANP 9x9-2 fuel assemblies in the
NUHOMS[supreg] 61BT DSC does not increase the probability or
consequences of accidents, no changes are being made in the types of
any effluents that may be released offsite, and there is no significant
increase in occupational or public radiation exposure. Therefore, there
are no significant radiological environmental impacts associated with
the proposed action.
The exemption only affects the requirements associated with the
fuel assemblies that can be loaded in 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: Because there is no significant
environmental impact associated with the proposed action, alternatives
with equal or greater environmental impact were not evaluated. As an
alternative to the proposed action, the staff considered denial of the
proposed action. Denial of the exemption would result in no change in
the current environmental impact.
Agencies and Persons Consulted: This exemption request was
discussed with Mr. Brad Fuller of the Pennsylvania Department of
Environmental Protection Bureau of Radiation Protection on March 6,
2006. He stated that the State had no comments on the technical aspects
of the exemption. The NRC staff has determined that a consultation
under Section 7 of the Endangered Species Act is not required because
the proposed action 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 further consultation is required under
Section 106 of the National Historic Preservation Act.
Conclusion: The staff has reviewed the exemption request submitted
by PPL. Allowing loading of Framatome 9x9-2 fuel assemblies in the
NUHOMS[supreg] 61BT DSC 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 Environmental Assessment, the Commission finds that
the proposed action of granting the exemption from specific provisions
of 10 CFR 72.212(a)(2), 72.212(b)(2)(i)(A), 72.212(b)(7), and 10 CFR
72.214, to allow PPL to load of Framatome ANP 9x9-2 fuel assemblies in
the NUHOMS[supreg] 61BT DSC, subject to conditions, will not
significantly impact the quality of the human environment. Accordingly,
the Commission has determined that an environmental impact statement
for the proposed exemption is not warranted.
In accordance with 10 CFR 2.390 of NRC's ``Rules of Practice,''
final NRC records and documents regarding this proposed action are
publically available in the records component of NRC's Agencywide
Documents Access and
[[Page 18369]]
Management System (ADAMS). The request for exemption dated January 31,
2006, and March 6, 2006, was docketed under 10 CFR part 72, Docket No.
72-28. 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 31st day of March, 2006.
For the Nuclear Regulatory Commission.
Joseph M. Sebrosky,
Senior Project Manager, Spent Fuel Project Office, Office of Nuclear
Material Safety and Safeguards.
[FR Doc. 06-3416 Filed 4-10-06; 8:45 am]
BILLING CODE 7590-01-P
