Arizona Public Service Company, et al.; Palo Verde Nuclear Generating Station, Unit 1; Temporary Exemption, 63024-63025 [E8-25152]
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63024
Federal Register / Vol. 73, No. 205 / Wednesday, October 22, 2008 / Notices
For the Atomic Safety and Licensing
Board.
Rockville, Maryland, October 16, 2008.
William J. Froehlich,
Chairman, Administrative Judge.
[FR Doc. E8–25148 Filed 10–21–08; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. STN 50–528]
Arizona Public Service Company, et
al.; Palo Verde Nuclear Generating
Station, Unit 1; Temporary Exemption
1.0
Background
The Arizona Public Service Company
(APS, the licensee) is the holder of the
Renewed Facility Operating License No.
NPF–41 which authorizes operation of
the Palo Verde Nuclear Generating
Station (PVNGS), Unit 1. The license
provides, among other things, that the
facility is subject to all rules,
regulations, and orders of the Nuclear
Regulatory Commission (NRC or the
Commission) now or hereafter in effect.
The facility consists of a pressurizedwater reactor located in Maricopa
County, Arizona.
sroberts on PROD1PC70 with NOTICES
2.0
Request/Action
Pursuant to Title 10 of the Code of
Federal Regulations (10 CFR), Section
50.12, ‘‘Specific exemptions,’’ APS has,
by letter dated March 8, 2008, and
supplemented by letter dated September
10, 2008 (Agencywide Documents
Access and Management System
(ADAMS) Accession Nos. ML080790524
and ML082620212, respectively),
requested a temporary exemption from
10 CFR 50.46, ‘‘Acceptance criteria for
emergency core cooling systems for
light-water nuclear power reactors,’’ and
Appendix K to 10 CFR 50, ‘‘ECCS
Evaluation Models,’’ (Appendix K). The
regulation in 10 CFR 50.46 contains
acceptance criteria for the emergency
core cooling system (ECCS) for reactors
fueled with zircaloy or ZIRLOTM
cladding. In addition, Appendix K to 10
CFR Part 50 requires that the Baker-Just
equation be used to predict the rates of
energy release, hydrogen concentration,
and cladding oxidation from the metalwater reaction. The temporary
exemption request relates solely to the
specific types of cladding material
specified in these regulations. As
written, the regulations presume the use
of zircaloy or ZIRLOTM fuel rod
cladding. Thus, an exemption from the
requirements of 10 CFR 50.46, and
Appendix K is needed to irradiate lead
fuel assemblies (LFAs) comprised of
VerDate Aug<31>2005
17:50 Oct 21, 2008
Jkt 217001
different cladding alloys at PVNGS, Unit
1. The scope of the staff’s review of this
temporary exemption request is limited
to the current burnup limits; i.e., 60
gigawatt days per metric ton unit (GWD/
MTU). Extending the burnup of these
LFAs will require further NRC staff
review.
The temporary exemption requested
by the licensee would allow up to eight
LFAs manufactured by AREVA NP
consisting of fuel rods with M5 cladding
material to be inserted into the PVNGS,
Unit 1 reactor core in non-limiting
locations during operating Cycles 15,
16, and 17. The use of M5 LFAs will
allow APS to evaluate cladding for
future fuel assemblies that need to be of
a more robust design than the current
fuel assemblies to allow for possible
higher duty or extended burnup.
3.0
Discussion
Pursuant to 10 CFR 50.12, the
Commission may, upon application by
any interested person or upon its own
initiative, grant exemptions from the
requirements of 10 CFR Part 50, when
(1) the exemptions are authorized by
law, will not present an undue risk to
public health and safety, and are
consistent with the common defense
and security; and (2) special
circumstances are present. Under 10
CFR 50.12(a)(2), special circumstances
include, among other things, when
application of the specific regulation in
the particular circumstance would not
serve, or is not necessary to achieve, the
underlying purpose of the rule.
Authorized by Law
This temporary exemption would
allow the licensee the use of M5 LFAs
to evaluate cladding for future fuel
assemblies that may need to be of a
more robust design than the current fuel
assemblies to allow for possible higher
duty or extended burnup. The
regulations specify standards and
acceptance criteria only for fuel rod
clads with Zircaloy or ZIRLOTM. Thus,
a temporary exemption is required to
use fuel rods clad with an advanced
alloy that is not Zircaloy or ZIRLOTM.
As stated above, 10 CFR 50.12 allows
the NRC to grant exemptions from the
requirements of 10 CFR part 50. The
NRC staff has determined that granting
of the licensee’s proposed temporary
exemption will not result in a violation
of the Atomic Energy Act of 1954, as
amended, or the Commission’s
regulations. Therefore, the exemption is
authorized by law.
PO 00000
Frm 00076
Fmt 4703
Sfmt 4703
No Undue Risk to Public Health and
Safety
In regard to the fuel mechanical
design, the PVNGS, Unit 1 temporary
exemption request relates solely to the
specific types of cladding material
specified in the regulations. No new or
altered design limits for purposes of 10
CFR 50, Appendix A, General Design
Criterion 10, ‘‘Reactor Design,’’ need to
be applied or are required for this
program. Also, the NRC staff’s review
was limited to the exemption request
and does not address the core physics,
core thermal hydraulics, fuel thermalmechanical design, or the safety
analysis aspects of the LFAs associated
with the Updated Safety Analysis
Report nor their placement in a nonlimiting core location. APS has notified
the staff of their intent to evaluate the
LFAs as a change to the plant in
accordance with 10 CFR 50.59.
Furthermore, APS has provided
information related to their planned
evaluation of the LFAs as part of their
exemption request (letter dated March 8,
2008) and in response to RAIs (letter
dated September 10, 2008).
The underlying purpose of 10 CFR
50.46 is to establish acceptance criteria
for ECCS performance. The staff’s
review and approval of topical report
BAW–10227P–A, ‘‘Evaluation of
Advanced Cladding and Structural
Material (M5) in PWR Reactor Fuel,’’
dated February 4, 2000 (ADAMS
Accession Nos. ML003681479 and
ML003681490), addressed all of the
important aspects of M5 with respect to
ECCS performance requirements: (1)
Applicability of 10 CFR 50.46(b) fuel
acceptance criteria, (2) M5 material
properties including fuel rod ballooning
and rupture strains, and (3) steam
oxidation kinetics and applicability of
Baker-Just weight gain correlation. A
subsequent NRC-approved topical
report, BAW–10240P–A, ‘‘Incorporation
of M5 Properties in Framatome ANP
Approved Methods,’’ May 5, 2004
(ADAMS Accession No. ML041260560),
further addressed M5 material
properties with respect to loss-ofcoolant accident (LOCA) applications.
Based on an ongoing LOCA research
program at Argonne National Laboratory
(ANL) and Research Information Letter
0801, titled, ‘‘Technical Basis for
Revision of Embrittlement Criteria in 10
CFR 50.46,’’ dated May 30, 2008
(ADAMS Accession No.
ML0813502251), cladding corrosion
(and associated hydrogen pickup) has a
significant impact on post-quench
ductility. Pre-test characterization of
irradiated M5 fuel cladding segments at
ANL provide further evidence of
E:\FR\FM\22OCN1.SGM
22OCN1
sroberts on PROD1PC70 with NOTICES
Federal Register / Vol. 73, No. 205 / Wednesday, October 22, 2008 / Notices
favorable corrosion and hydrogen
pickup characteristics of M5 as
compared with standard Zircaloy-4.
Hence, the M5 fuel rods would be less
susceptible to the detrimental effects of
hydrogen uptake during normal
operation and their impact on postquench ductility. Furthermore, ANL
post-quench ductility tests on unirradiated and irradiated M5 cladding
segments demonstrate that the 10 CFR
50.46(b) fuel criteria (i.e., 2200 degrees
Fahrenheit and 17 percent equivalent
cladding reacted) remain conservative
up to current burnup limits.
Information provided in the
previously approved M5 topical reports,
as well as recent ANL LOCA research,
demonstrate that the acceptance criteria
within 10 CFR 50.46 remain valid for
M5 alloy and meet the underlying
purpose of the rule—maintain a degree
of post-quench ductility in the fuel
cladding material.
Paragraph I.A.5 of Appendix K to 10
CFR Part 50 states that the rates of
energy release, hydrogen generation,
and cladding oxidation from the metalwater reaction shall be calculated using
the Baker-Just equation. Since the
Baker-Just equation presumes the use of
zircaloy clad fuel, strict application of
the rule would not permit use of the
equation for the LFA cladding for
determining acceptable fuel
performance. Metal-water reaction tests
performed by AREVA (topical report
BAW–10227–P–A) demonstrate
conservative reaction rates relative to
the Baker-Just equation. Thus,
application of Appendix K, Paragraph
I.A.5 is not necessary for the licensee to
achieve its underlying purpose in these
circumstances.
In addition, APS states that the eight
LFAs will be placed in non-limiting
core locations (e.g., lower power
assembly locations), which provide
further margin to ECCS performance
requirements and ensure that the
behavior of the LFAs is bounded by the
safety analyses performed for the
standard fuel rods. Based upon results
of metal-water reaction testing and
mechanical testing, which ensure the
applicability of 10 CFR 50.46
acceptance criteria and 10 CFR 50
Appendix K methods and the placement
of LFAs in non-limiting locations, the
staff finds it acceptable to grant a
temporary exemption from the
requirements of 10 CFR 50.46 and
Appendix K to 10 CFR Part 50 for the
use of eight AREVA LFAs within
PVNGS, Unit 1.
Based on the above, no new accident
precursors are created by allowing the
use of LFAs with M5 cladding material
in PVNGS, Unit 1 reactor core during
VerDate Aug<31>2005
17:50 Oct 21, 2008
Jkt 217001
operating Cycles 15, 16, and 17, thus,
the probability of postulated accidents
is not increased. Also, based on the
above, the consequences of postulated
accidents are not increased. Therefore,
there is no undue risk to public health
and safety.
Consistent With Common Defense and
Security
The proposed temporary exemption
would allow the use of up to eight LFAs
with advanced cladding materials. This
change to the plant core configuration
has no relation to security issues.
Therefore, the common defense and
security is not impacted by this
temporary exemption.
Special Circumstances
Conclusion
Accordingly, the Commission has
determined that, pursuant to 10 CFR
50.12(a), the temporary exemption is
authorized by law, will not present an
undue risk to the public health and
safety, and is consistent with the
common defense and security. Also,
special circumstances are present.
Therefore, the Commission hereby
grants APS temporary exemption from
the requirements of 10 CFR 50.46 and
Appendix K to 10 CFR Part 50, to allow
the use of fuel rods clad with an
advanced alloy that is not Zircaloy or
ZIRLOTM to be inserted into the PVNGS,
Unit 1 reactor core in non-limiting
locations during operating Cycles 15,
16, and 17.
Pursuant to 10 CFR 51.32, the
Commission has determined that the
granting of this temporary exemption
will not have a significant effect on the
PO 00000
Frm 00077
Fmt 4703
Sfmt 4703
quality of the human environment (73
FR 57386, October 2, 2008).
This temporary exemption is effective
upon issuance.
Dated at Rockville, Maryland, this 14th day
of October 2008.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. E8–25152 Filed 10–21–08; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–483]
Special circumstances, in accordance
with 10 CFR 50.12(a)(2)(ii), are present
whenever application of the specific
regulation in the particular
circumstance would not serve, or is not
necessary to achieve, the underlying
purpose of the rule. The underlying
purpose of 10 CFR 50.46 and Appendix
K to 10 CFR Part 50 is to establish
acceptance criteria for ECCS
performance. The wording of the
regulations in 10 CFR 50.46 and
Appendix K is not directly applicable to
these advanced cladding alloys, even
though the evaluations discussed above
show that the intent of the regulations
are met. Therefore, since the underlying
purposes of 10 CFR 50.46 and Appendix
K are achieved with the use of these
advanced cladding alloys, the special
circumstances required by 10 CFR
50.12(a)(2)(ii) for granting of an
exemption from 10 CFR 50.46 and
Appendix K exist.
4.0
63025
Union Electric Company; Notice of
Consideration of Issuance of
Amendment to Facility Operating
License, Proposed No Significant
Hazards Consideration Determination,
and Opportunity for a Hearing
The U.S. Nuclear Regulatory
Commission (the Commission) is
considering issuance of an amendment
to Facility Operating License No. NPF–
30 issued to Union Electric Company
(the licensee) for operation of the
Callaway Plant, Unit 1, located in
Callaway County, Missouri.
The proposed amendment would
revise Technical Specification (TS)
3.4.10, ‘‘Pressurizer Safety Valves,’’ TS
3.4.11, ‘‘Pressurizer Power Operated
Relief Valves (PORVs),’’ and TS 3.4.12,
‘‘Cold Overpressure Mitigation System
(COMS),’’ to adopt the NRC-approved
Technical Specification Task Force
(TSTF) travelers TSTF–247–A and
TSTF–352–A. In the Federal Register
(FR) notice of consideration published
on March 25, 2008 (73 FR 15791), the
NRC staff identified the proposed
changes to TSs 3.4.10 and 3.4.11 to
modify the completion times for default
conditions in both TSs and to allow
separate condition entry for PORV block
valves in TS 3.4.11, but did not identify
the proposed change to TS 3.4.12 to
extend the completion time for
Condition G. This notice is to identify
this proposed change to TS 3.4.12.
Before issuance of the proposed
license amendment, the Commission
will have made findings required by the
Atomic Energy Act of 1954, as amended
(the Act), and the Commission’s
regulations.
The Commission has made a
proposed determination that the
amendment request involves no
significant hazards consideration. Under
the Commission’s regulations in Title 10
E:\FR\FM\22OCN1.SGM
22OCN1
Agencies
[Federal Register Volume 73, Number 205 (Wednesday, October 22, 2008)]
[Notices]
[Pages 63024-63025]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-25152]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. STN 50-528]
Arizona Public Service Company, et al.; Palo Verde Nuclear
Generating Station, Unit 1; Temporary Exemption
1.0 Background
The Arizona Public Service Company (APS, the licensee) is the
holder of the Renewed Facility Operating License No. NPF-41 which
authorizes operation of the Palo Verde Nuclear Generating Station
(PVNGS), Unit 1. The license provides, among other things, that the
facility is subject to all rules, regulations, and orders of the
Nuclear Regulatory Commission (NRC or the Commission) now or hereafter
in effect.
The facility consists of a pressurized-water reactor located in
Maricopa County, Arizona.
2.0 Request/Action
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.12, ``Specific exemptions,'' APS has, by letter dated March
8, 2008, and supplemented by letter dated September 10, 2008
(Agencywide Documents Access and Management System (ADAMS) Accession
Nos. ML080790524 and ML082620212, respectively), requested a temporary
exemption from 10 CFR 50.46, ``Acceptance criteria for emergency core
cooling systems for light-water nuclear power reactors,'' and Appendix
K to 10 CFR 50, ``ECCS Evaluation Models,'' (Appendix K). The
regulation in 10 CFR 50.46 contains acceptance criteria for the
emergency core cooling system (ECCS) for reactors fueled with zircaloy
or ZIRLO\TM\ cladding. In addition, Appendix K to 10 CFR Part 50
requires that the Baker-Just equation be used to predict the rates of
energy release, hydrogen concentration, and cladding oxidation from the
metal-water reaction. The temporary exemption request relates solely to
the specific types of cladding material specified in these regulations.
As written, the regulations presume the use of zircaloy or ZIRLO\TM\
fuel rod cladding. Thus, an exemption from the requirements of 10 CFR
50.46, and Appendix K is needed to irradiate lead fuel assemblies
(LFAs) comprised of different cladding alloys at PVNGS, Unit 1. The
scope of the staff's review of this temporary exemption request is
limited to the current burnup limits; i.e., 60 gigawatt days per metric
ton unit (GWD/MTU). Extending the burnup of these LFAs will require
further NRC staff review.
The temporary exemption requested by the licensee would allow up to
eight LFAs manufactured by AREVA NP consisting of fuel rods with M5
cladding material to be inserted into the PVNGS, Unit 1 reactor core in
non-limiting locations during operating Cycles 15, 16, and 17. The use
of M5 LFAs will allow APS to evaluate cladding for future fuel
assemblies that need to be of a more robust design than the current
fuel assemblies to allow for possible higher duty or extended burnup.
3.0 Discussion
Pursuant to 10 CFR 50.12, the Commission may, upon application by
any interested person or upon its own initiative, grant exemptions from
the requirements of 10 CFR Part 50, when (1) the exemptions are
authorized by law, will not present an undue risk to public health and
safety, and are consistent with the common defense and security; and
(2) special circumstances are present. Under 10 CFR 50.12(a)(2),
special circumstances include, among other things, when application of
the specific regulation in the particular circumstance would not serve,
or is not necessary to achieve, the underlying purpose of the rule.
Authorized by Law
This temporary exemption would allow the licensee the use of M5
LFAs to evaluate cladding for future fuel assemblies that may need to
be of a more robust design than the current fuel assemblies to allow
for possible higher duty or extended burnup. The regulations specify
standards and acceptance criteria only for fuel rod clads with Zircaloy
or ZIRLO\TM\. Thus, a temporary exemption is required to use fuel rods
clad with an advanced alloy that is not Zircaloy or ZIRLO\TM\. As
stated above, 10 CFR 50.12 allows the NRC to grant exemptions from the
requirements of 10 CFR part 50. The NRC staff has determined that
granting of the licensee's proposed temporary exemption will not result
in a violation of the Atomic Energy Act of 1954, as amended, or the
Commission's regulations. Therefore, the exemption is authorized by
law.
No Undue Risk to Public Health and Safety
In regard to the fuel mechanical design, the PVNGS, Unit 1
temporary exemption request relates solely to the specific types of
cladding material specified in the regulations. No new or altered
design limits for purposes of 10 CFR 50, Appendix A, General Design
Criterion 10, ``Reactor Design,'' need to be applied or are required
for this program. Also, the NRC staff's review was limited to the
exemption request and does not address the core physics, core thermal
hydraulics, fuel thermal-mechanical design, or the safety analysis
aspects of the LFAs associated with the Updated Safety Analysis Report
nor their placement in a non-limiting core location. APS has notified
the staff of their intent to evaluate the LFAs as a change to the plant
in accordance with 10 CFR 50.59. Furthermore, APS has provided
information related to their planned evaluation of the LFAs as part of
their exemption request (letter dated March 8, 2008) and in response to
RAIs (letter dated September 10, 2008).
The underlying purpose of 10 CFR 50.46 is to establish acceptance
criteria for ECCS performance. The staff's review and approval of
topical report BAW-10227P-A, ``Evaluation of Advanced Cladding and
Structural Material (M5) in PWR Reactor Fuel,'' dated February 4, 2000
(ADAMS Accession Nos. ML003681479 and ML003681490), addressed all of
the important aspects of M5 with respect to ECCS performance
requirements: (1) Applicability of 10 CFR 50.46(b) fuel acceptance
criteria, (2) M5 material properties including fuel rod ballooning and
rupture strains, and (3) steam oxidation kinetics and applicability of
Baker-Just weight gain correlation. A subsequent NRC-approved topical
report, BAW-10240P-A, ``Incorporation of M5 Properties in Framatome ANP
Approved Methods,'' May 5, 2004 (ADAMS Accession No. ML041260560),
further addressed M5 material properties with respect to loss-of-
coolant accident (LOCA) applications.
Based on an ongoing LOCA research program at Argonne National
Laboratory (ANL) and Research Information Letter 0801, titled,
``Technical Basis for Revision of Embrittlement Criteria in 10 CFR
50.46,'' dated May 30, 2008 (ADAMS Accession No. ML0813502251),
cladding corrosion (and associated hydrogen pickup) has a significant
impact on post-quench ductility. Pre-test characterization of
irradiated M5 fuel cladding segments at ANL provide further evidence of
[[Page 63025]]
favorable corrosion and hydrogen pickup characteristics of M5 as
compared with standard Zircaloy-4. Hence, the M5 fuel rods would be
less susceptible to the detrimental effects of hydrogen uptake during
normal operation and their impact on post-quench ductility.
Furthermore, ANL post-quench ductility tests on un-irradiated and
irradiated M5 cladding segments demonstrate that the 10 CFR 50.46(b)
fuel criteria (i.e., 2200 degrees Fahrenheit and 17 percent equivalent
cladding reacted) remain conservative up to current burnup limits.
Information provided in the previously approved M5 topical reports,
as well as recent ANL LOCA research, demonstrate that the acceptance
criteria within 10 CFR 50.46 remain valid for M5 alloy and meet the
underlying purpose of the rule--maintain a degree of post-quench
ductility in the fuel cladding material.
Paragraph I.A.5 of Appendix K to 10 CFR Part 50 states that the
rates of energy release, hydrogen generation, and cladding oxidation
from the metal-water reaction shall be calculated using the Baker-Just
equation. Since the Baker-Just equation presumes the use of zircaloy
clad fuel, strict application of the rule would not permit use of the
equation for the LFA cladding for determining acceptable fuel
performance. Metal-water reaction tests performed by AREVA (topical
report BAW-10227-P-A) demonstrate conservative reaction rates relative
to the Baker-Just equation. Thus, application of Appendix K, Paragraph
I.A.5 is not necessary for the licensee to achieve its underlying
purpose in these circumstances.
In addition, APS states that the eight LFAs will be placed in non-
limiting core locations (e.g., lower power assembly locations), which
provide further margin to ECCS performance requirements and ensure that
the behavior of the LFAs is bounded by the safety analyses performed
for the standard fuel rods. Based upon results of metal-water reaction
testing and mechanical testing, which ensure the applicability of 10
CFR 50.46 acceptance criteria and 10 CFR 50 Appendix K methods and the
placement of LFAs in non-limiting locations, the staff finds it
acceptable to grant a temporary exemption from the requirements of 10
CFR 50.46 and Appendix K to 10 CFR Part 50 for the use of eight AREVA
LFAs within PVNGS, Unit 1.
Based on the above, no new accident precursors are created by
allowing the use of LFAs with M5 cladding material in PVNGS, Unit 1
reactor core during operating Cycles 15, 16, and 17, thus, the
probability of postulated accidents is not increased. Also, based on
the above, the consequences of postulated accidents are not increased.
Therefore, there is no undue risk to public health and safety.
Consistent With Common Defense and Security
The proposed temporary exemption would allow the use of up to eight
LFAs with advanced cladding materials. This change to the plant core
configuration has no relation to security issues. Therefore, the common
defense and security is not impacted by this temporary exemption.
Special Circumstances
Special circumstances, in accordance with 10 CFR 50.12(a)(2)(ii),
are present whenever application of the specific regulation in the
particular circumstance would not serve, or is not necessary to
achieve, the underlying purpose of the rule. The underlying purpose of
10 CFR 50.46 and Appendix K to 10 CFR Part 50 is to establish
acceptance criteria for ECCS performance. The wording of the
regulations in 10 CFR 50.46 and Appendix K is not directly applicable
to these advanced cladding alloys, even though the evaluations
discussed above show that the intent of the regulations are met.
Therefore, since the underlying purposes of 10 CFR 50.46 and Appendix K
are achieved with the use of these advanced cladding alloys, the
special circumstances required by 10 CFR 50.12(a)(2)(ii) for granting
of an exemption from 10 CFR 50.46 and Appendix K exist.
4.0 Conclusion
Accordingly, the Commission has determined that, pursuant to 10 CFR
50.12(a), the temporary exemption is authorized by law, will not
present an undue risk to the public health and safety, and is
consistent with the common defense and security. Also, special
circumstances are present. Therefore, the Commission hereby grants APS
temporary exemption from the requirements of 10 CFR 50.46 and Appendix
K to 10 CFR Part 50, to allow the use of fuel rods clad with an
advanced alloy that is not Zircaloy or ZIRLO\TM\ to be inserted into
the PVNGS, Unit 1 reactor core in non-limiting locations during
operating Cycles 15, 16, and 17.
Pursuant to 10 CFR 51.32, the Commission has determined that the
granting of this temporary exemption will not have a significant effect
on the quality of the human environment (73 FR 57386, October 2, 2008).
This temporary exemption is effective upon issuance.
Dated at Rockville, Maryland, this 14th day of October 2008.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. E8-25152 Filed 10-21-08; 8:45 am]
BILLING CODE 7590-01-P