Southern Nuclear Operating Company, Inc.; Edwin I. Hatch Nuclear Plant, Units 1 and 2; Exemption, 8738-8740 [2014-03215]
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Federal Register / Vol. 79, No. 30 / Thursday, February 13, 2014 / Notices
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[FR Doc. 2014–03183 Filed 2–12–14; 8:45 am]
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emcdonald on DSK67QTVN1PROD with NOTICES
SUMMARY:
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Jkt 232001
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[FR Doc. 2014–03148 Filed 2–12–14; 8:45 am]
BILLING CODE 7555–01–P
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NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–321 and 50–366; NRC–
2008–0585]
Southern Nuclear Operating Company,
Inc.; Edwin I. Hatch Nuclear Plant,
Units 1 and 2; Exemption
1.0 Background
The Southern Nuclear Operating
Company, Inc. (SNC, the licensee) is the
holder of the Renewed Facility
Operating License Nos. DPR–57 and
NPF–5 which authorize operation of the
Edwin I. Hatch Nuclear Plant, Units 1
and 2 (HNP). The licenses provide,
among other things, that the facility is
subject to the rules, regulations, and
orders of the U.S. Nuclear Regulatory
Commission (NRC) now or hereafter in
effect.
The HNP facility consists of two
boiling-water reactors located in
Appling County, Georgia.
2.0 Request/Action
Pursuant to § 50.12 of Title 10 of the
Code of Federal Regulations (10 CFR),
Specific Exemptions, SNC has, by letter
dated April 23, 2013, requested an
exemption from the fuel cladding
material requirements in 10 CFR 50.46,
‘‘Acceptance criteria for emergency core
cooling systems [ECCS] for light-water
nuclear power reactors,’’ and Appendix
K to 10 CFR Part 50, ‘‘ECCS Evaluation
Models,’’ (Appendix K).
The SNC’s letter of April 23, 2013,
constitutes the licensee’s second request
for an exemption from the above fuel
cladding material requirements in order
to irradiate two GE14 Lead Test
Assemblies (LTAs) in the HNP. The
LTAs include a limited number of fuel
rods manufactured with an advanced
cladding alloy, known as Global Nuclear
Fuel (GNF) Ziron, which is outside of
the cladding materials specified in the
regulations (i.e. zircaloy or ZIRLOTM).
By letter dated November 7, 2008, the
NRC approved an earlier SNC request
for an exemption in order to irradiate
these two GE14 LTAs in the HNP Unit
2 reactor for cycles 21, 22 and 23. These
two LTAs have now completed
operation in cycles 21 and 22; however,
SNC decided not to include them in the
Unit 2 cycle 23 core loading in order to
allow sufficient time to perform poolside inspections. Since the original
exemption request applied only to the
operation of the LTAs in the Unit 2
reactor for cycles 21–23, SNC has
requested a second exemption in order
to continue irradiation of the LTAs in
either of the HNP reactors for one or
more additional cycles, up to GNF’s
approved peak pellet exposure.
E:\FR\FM\13FEN1.SGM
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Federal Register / Vol. 79, No. 30 / Thursday, February 13, 2014 / Notices
The regulation in 10 CFR 50.46
contains acceptance criteria for an ECCS
for reactors fueled with zircaloy or
ZIRLOTM cladding. In addition,
Appendix K 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 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
a lead test assembly (LTA) comprised of
different cladding alloys at HNP.
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
the public health and safety, and are
consistent with the common defense
and security; and (2) when special
circumstances are present. Under 10
CFR 50.12(a)(2), special circumstances
include, among other things, when
application of the regulation in the
particular circumstances would not
serve, or is not necessary to achieve, the
underlying purpose of the rule.
emcdonald on DSK67QTVN1PROD with NOTICES
Authorized by Law
This exemption would allow the
licensee to insert two lead test fuel
assemblies with fuel rod cladding that
does not meet the definition of zircaloy
or ZIRLOTM, as specified by 10 CFR
50.46, and Appendix K, in either of the
HNP reactors for one or more additional
cycles, up to GNF’s approved peak
pellet exposure. 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 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 exemption request relates
solely to the specific types of cladding
material specified in the regulations.
The underlying purpose of 10 CFR 50.46
is to establish acceptance criteria for
ECCS. In Section VI of its letter dated
April 23, 2013, SNC provides a
technical basis supporting the
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applicability of the 50.46 Paragraph (b)
fuel criteria to GNF-Ziron. Experimental
results from tests conducted on GNFZiron samples exposed to loss-ofcoolant accident (LOCA) conditions
were provided by SNC. While these
tests differ from the post-steam oxidized
ring-compression testing (which forms
the basis of the 10 CFR 50.46 postquench ductility criteria), these results
provide reasonable assurance that the 17
percent oxidation and 2200 degree
Farenheit criteria are valid for GNFZiron and meet the underlying purpose
of the rule, which is to maintain a
degree of post-quench ductility in the
fuel cladding material.
As discussed in the NRC Research
Information Letter 0801, ‘‘Technical
Basis for Revision of Embrittlement
Criteria in 10 CFR 50.46,’’ ADAMS
Accession No. ML081350225, based on
an ongoing LOCA research program at
Argonne National Laboratory, cladding
corrosion (and associated hydrogen
pickup) has a significant impact on
post-quench ductility. Post-irradiation
examinations provided by the licensee
demonstrate the favorable hydrogen
pickup characteristics of GNF-Ziron as
compared with standard zircaloy.
Hence, the GNF-Ziron fuel rods would
be less susceptible to the detrimental
effects of hydrogen uptake during
normal operation and their impact on
post-quench ductility.
Paragraph I.A.5 of Appendix K to 10
CFR Part 50 states that the rate of energy
release, hydrogen generation, and
cladding oxidation from the metal/water
reaction shall be calculated using the
Baker-Just equation. Since the BakerJust equation presumes the use of
zircaloy clad fuel, strict application of
the rule would not permit use of the
equation for the LTA cladding for
determining acceptable fuel
performance. Metal-water reaction tests
performed by GNF on GNF-Ziron, as
described in the application for
exemption, 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.
High temperature perforation test
results were included in the application.
These test results illustrate similar burst
characteristics of GNF-Ziron as
compared with standard zircaloy. In
addition, the licensee provides further
comparisons of material properties
between GNF-Ziron and zircaloy. Based
upon this comparison of material
properties, GNF and SNC believe that
currently approved methods and models
are directly applicable to GNF-Ziron.
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8739
Based upon the material properties
provided in SNC’s letter dated April 23,
2013, the NRC staff finds the use of
current LOCA models and methods
acceptable for the purpose of evaluating
LTAs containing a limited number of
GNF-Ziron fuel rods. The staff notes that
Section V of GNF’s technical basis
document (Enclosure 2 of the April 23,
2013 application) states that the GNF
fuel rod thermal mechanical code
PRIME03 is now being used to assess
fuel rod performance. The PRIME03
code, which accounts for exposuredependent fuel thermal conductivity,
replaces the legacy GESTRM fuel rod
performance code. While not explicitly
approved for GNF-Ziron, the use of
PRIME03 is consistent with the
approved GNF reload methodology and
therefore acceptable.
Through the mechanical testing and a
comparison of material properties
provided by SNC, the staff has
reasonable assurance that anticipated
in-reactor performance will be
acceptable. Further, the licensee has
demonstrated that the use of current
methods and models are reasonable for
evaluating the cladding’s performance
in response to anticipated operational
occurrences and accidents.
Nevertheless, as with any
developmental cladding alloy, the NRC
staff requires a limitation on the total
number of fuel rods clad in a
developmental alloy in order to ensure
a minimal impact on the simulated
progression and calculated
consequences of postulated accidents.
This limitation is directly related to the
available material properties (both
unirradiated and irradiated) used to
judge the cladding alloy’s anticipated
in-reactor performance. Based on the
material properties data presented
within the application attachments, the
NRC staff finds the HNP LTA program
acceptable with respect to achieving the
underlying purpose of 10 CFR 50.46 and
Appendix K to 10 CFR Part 50.
Based upon results of metal-water
reaction tests and mechanical testing
which ensure the applicability of ECCS
models and acceptance criteria, the
limited number and anticipated
performance of the advanced cladding
fuel rods, and the use of approved
LOCA models to ensure that the LTAs
satisfy 10 CFR 50.46 acceptance criteria,
the NRC staff finds it acceptable to grant
an exemption from the requirements of
10 CFR 50.46 and Appendix K to 10
CFR Part 50 for the use of two LTAs in
either of the HNP reactors for one or
more additional cycles, up to GNF’s
approved peak pellet exposure.
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Federal Register / Vol. 79, No. 30 / Thursday, February 13, 2014 / Notices
Consistent With Common Defense and
Security
The proposed exemption would allow
the licensee to insert two lead test fuel
assemblies with fuel rod cladding that
does not meet the definition of zircaloy
or ZIRLOTM as specified by 10 CFR
50.46, and Appendix K, into either of
the HNP reactors for one or more
additional cycles, up to GNF’s approved
peak pellet exposure. This change has
no relation to security issues. Therefore,
the common defense and security is not
impacted by this exemption.
Special Circumstances
emcdonald on DSK67QTVN1PROD with NOTICES
Conclusion
Accordingly, the Commission has
determined that, pursuant to 10 CFR
50.12(a), the 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 SNC an
exemption from the requirements of 10
CFR 50.46, and 10 CFR Part 50,
Appendix K, to allow the limited use of
two LTAs with selected rods clad with
GNF-Ziron cladding in either of the
HNP reactors for one or more additional
cycles, up to GNF’s approved peak
pellet exposure.
Pursuant to 10 CFR 51.32, the
Commission has determined that the
granting of this exemption will not have
a significant effect on the quality of the
human environment (79 FR 4983;
January 30, 2014).
This exemption is effective upon
issuance.
Dated at Rockville, Maryland, this 4th day
of February 2014.
VerDate Mar<15>2010
18:44 Feb 12, 2014
[FR Doc. 2014–03215 Filed 2–12–14; 8:45 am]
BILLING CODE 7590–01–P
OFFICE OF PERSONNEL
MANAGEMENT
Excepted Service; Consolidated
Listing of Schedules A, B, and C
Exceptions
Office of Personnel
Management.
ACTION: Notice.
AGENCY:
Special circumstances, in accordance
with 10 CFR 50.12, are present
whenever application of the regulation
in the particular circumstances 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 emergency core
cooling system performance. The
wording of the regulations in 10 CFR
50.46 and Appendix K is not directly
applicable to Ziron, even though the
evaluations discussed above show that
the intent of the regulations is met.
Therefore, since the NRC staff finds that
the underlying purpose of 10 CFR 50.46
and Appendix K is achieved with the
use of Ziron, the special circumstances
required by 10 CFR 50.12 for the
granting of an exemption from 10 CFR
50.46 and Appendix K exist.
4.0
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
Jkt 232001
This provides the
consolidated notice of all agency
specific excepted authorities, approved
by the Office of Personnel Management
(OPM), under Schedule A, B, and C, as
of June 30, 2013, as required by Civil
Service Rule VI, Exceptions from the
Competitive Service.
FOR FURTHER INFORMATION CONTACT:
Senior Executive Resources Services,
Senior Executive Services and
Performance Management, Employee
Services, 202–606–2246.
SUPPLEMENTARY INFORMATION: Civil
Service Rule VI (5 CFR 6.1) requires the
U.S. Office of Personnel Management
(OPM) to publish notice of exceptions
granted under Schedule A, B, and C.
Under 5 CFR 213.103(a) it is required
that all Schedule A, B, and C appointing
authorities available for use by all
agencies to be published as regulations
in the Federal Register (FR) and the
Code of Federal Regulations (CFR).
Excepted appointing authorities
established solely for use by one
specific agency do not meet the
standard of general applicability
prescribed by the Federal Register Act
for regulations published in either the
FR or the CFR. Therefore, 5 CFR
213.103(b) requires monthly
publication, in the Notices section of the
Federal Register, of any Schedule A, B,
and C appointing authorities applicable
to a single agency. Under 5 CFR
213.103(c) it is required that a
consolidated listing of all Schedule A,
B, and C authorities, current as of June
30 of each year, be published annually
in the Notices section of the Federal
Register at www.federalregister.gov/
agencies/personnel-management-office.
That notice follows. Governmentwide
authorities codified in the CFR are not
printed in this notice.
When making appointments under an
agency-specific authority, agencies
should first list the appropriate
SUMMARY:
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Sfmt 4703
Schedule A, B, or C, followed by the
applicable number, for example:
Schedule A, 213.3104(x)(x). Agencies
are reminded that all excepted
authorities are subject to the provisions
of 5 CFR part 302 unless specifically
exempted by OPM at the time of
approval. OPM maintains continuing
information on the status of all
Schedule A, B, and C appointing
authorities. Interested parties needing
information about specific authorities
during the year may obtain information
by writing to the Senior Executive
Resources Services, Office of Personnel
Management, 1900 E Street NW., Room
7412, Washington, DC 20415, or by
calling (202) 606–2246.
The following exceptions are current
as of June 30, 2013.
Schedule A
03. Executive Office of the President
(Sch. A, 213.3103)
(a) Office of Administration—
(1) Not to exceed 75 positions to
provide administrative services and
support to the White House Office.
(b) Office of Management and Budget—
(1) Not to exceed 20 positions at
grades GS–5/15.
(c) Council on Environmental Quality—
(1) Professional and technical
positions in grades GS–9 through 15 on
the staff of the Council.
(d)–(f) (Reserved)
(g) National Security Council—
(1) All positions on the staff of the
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(h) Office of Science and Technology
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(1) Thirty positions of Senior Policy
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E:\FR\FM\13FEN1.SGM
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Agencies
[Federal Register Volume 79, Number 30 (Thursday, February 13, 2014)]
[Notices]
[Pages 8738-8740]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-03215]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-321 and 50-366; NRC-2008-0585]
Southern Nuclear Operating Company, Inc.; Edwin I. Hatch Nuclear
Plant, Units 1 and 2; Exemption
1.0 Background
The Southern Nuclear Operating Company, Inc. (SNC, the licensee) is
the holder of the Renewed Facility Operating License Nos. DPR-57 and
NPF-5 which authorize operation of the Edwin I. Hatch Nuclear Plant,
Units 1 and 2 (HNP). The licenses provide, among other things, that the
facility is subject to the rules, regulations, and orders of the U.S.
Nuclear Regulatory Commission (NRC) now or hereafter in effect.
The HNP facility consists of two boiling-water reactors located in
Appling County, Georgia.
2.0 Request/Action
Pursuant to Sec. 50.12 of Title 10 of the Code of Federal
Regulations (10 CFR), Specific Exemptions, SNC has, by letter dated
April 23, 2013, requested an exemption from the fuel cladding material
requirements in 10 CFR 50.46, ``Acceptance criteria for emergency core
cooling systems [ECCS] for light-water nuclear power reactors,'' and
Appendix K to 10 CFR Part 50, ``ECCS Evaluation Models,'' (Appendix K).
The SNC's letter of April 23, 2013, constitutes the licensee's
second request for an exemption from the above fuel cladding material
requirements in order to irradiate two GE14 Lead Test Assemblies (LTAs)
in the HNP. The LTAs include a limited number of fuel rods manufactured
with an advanced cladding alloy, known as Global Nuclear Fuel (GNF)
Ziron, which is outside of the cladding materials specified in the
regulations (i.e. zircaloy or ZIRLO\TM\). By letter dated November 7,
2008, the NRC approved an earlier SNC request for an exemption in order
to irradiate these two GE14 LTAs in the HNP Unit 2 reactor for cycles
21, 22 and 23. These two LTAs have now completed operation in cycles 21
and 22; however, SNC decided not to include them in the Unit 2 cycle 23
core loading in order to allow sufficient time to perform pool-side
inspections. Since the original exemption request applied only to the
operation of the LTAs in the Unit 2 reactor for cycles 21-23, SNC has
requested a second exemption in order to continue irradiation of the
LTAs in either of the HNP reactors for one or more additional cycles,
up to GNF's approved peak pellet exposure.
[[Page 8739]]
The regulation in 10 CFR 50.46 contains acceptance criteria for an
ECCS for reactors fueled with zircaloy or ZIRLO\TM\ cladding. In
addition, Appendix K 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 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 a
lead test assembly (LTA) comprised of different cladding alloys at HNP.
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 the public health
and safety, and are consistent with the common defense and security;
and (2) when special circumstances are present. Under 10 CFR
50.12(a)(2), special circumstances include, among other things, when
application of the regulation in the particular circumstances would not
serve, or is not necessary to achieve, the underlying purpose of the
rule.
Authorized by Law
This exemption would allow the licensee to insert two lead test
fuel assemblies with fuel rod cladding that does not meet the
definition of zircaloy or ZIRLO\TM\, as specified by 10 CFR 50.46, and
Appendix K, in either of the HNP reactors for one or more additional
cycles, up to GNF's approved peak pellet exposure. 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 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 exemption request
relates solely to the specific types of cladding material specified in
the regulations. The underlying purpose of 10 CFR 50.46 is to establish
acceptance criteria for ECCS. In Section VI of its letter dated April
23, 2013, SNC provides a technical basis supporting the applicability
of the 50.46 Paragraph (b) fuel criteria to GNF-Ziron. Experimental
results from tests conducted on GNF-Ziron samples exposed to loss-of-
coolant accident (LOCA) conditions were provided by SNC. While these
tests differ from the post-steam oxidized ring-compression testing
(which forms the basis of the 10 CFR 50.46 post-quench ductility
criteria), these results provide reasonable assurance that the 17
percent oxidation and 2200 degree Farenheit criteria are valid for GNF-
Ziron and meet the underlying purpose of the rule, which is to maintain
a degree of post-quench ductility in the fuel cladding material.
As discussed in the NRC Research Information Letter 0801,
``Technical Basis for Revision of Embrittlement Criteria in 10 CFR
50.46,'' ADAMS Accession No. ML081350225, based on an ongoing LOCA
research program at Argonne National Laboratory, cladding corrosion
(and associated hydrogen pickup) has a significant impact on post-
quench ductility. Post-irradiation examinations provided by the
licensee demonstrate the favorable hydrogen pickup characteristics of
GNF-Ziron as compared with standard zircaloy. Hence, the GNF-Ziron fuel
rods would be less susceptible to the detrimental effects of hydrogen
uptake during normal operation and their impact on post-quench
ductility.
Paragraph I.A.5 of Appendix K to 10 CFR Part 50 states that the
rate 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 LTA cladding for determining acceptable fuel
performance. Metal-water reaction tests performed by GNF on GNF-Ziron,
as described in the application for exemption, 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.
High temperature perforation test results were included in the
application. These test results illustrate similar burst
characteristics of GNF-Ziron as compared with standard zircaloy. In
addition, the licensee provides further comparisons of material
properties between GNF-Ziron and zircaloy. Based upon this comparison
of material properties, GNF and SNC believe that currently approved
methods and models are directly applicable to GNF-Ziron. Based upon the
material properties provided in SNC's letter dated April 23, 2013, the
NRC staff finds the use of current LOCA models and methods acceptable
for the purpose of evaluating LTAs containing a limited number of GNF-
Ziron fuel rods. The staff notes that Section V of GNF's technical
basis document (Enclosure 2 of the April 23, 2013 application) states
that the GNF fuel rod thermal mechanical code PRIME03 is now being used
to assess fuel rod performance. The PRIME03 code, which accounts for
exposure-dependent fuel thermal conductivity, replaces the legacy
GESTRM fuel rod performance code. While not explicitly approved for
GNF-Ziron, the use of PRIME03 is consistent with the approved GNF
reload methodology and therefore acceptable.
Through the mechanical testing and a comparison of material
properties provided by SNC, the staff has reasonable assurance that
anticipated in-reactor performance will be acceptable. Further, the
licensee has demonstrated that the use of current methods and models
are reasonable for evaluating the cladding's performance in response to
anticipated operational occurrences and accidents. Nevertheless, as
with any developmental cladding alloy, the NRC staff requires a
limitation on the total number of fuel rods clad in a developmental
alloy in order to ensure a minimal impact on the simulated progression
and calculated consequences of postulated accidents. This limitation is
directly related to the available material properties (both
unirradiated and irradiated) used to judge the cladding alloy's
anticipated in-reactor performance. Based on the material properties
data presented within the application attachments, the NRC staff finds
the HNP LTA program acceptable with respect to achieving the underlying
purpose of 10 CFR 50.46 and Appendix K to 10 CFR Part 50.
Based upon results of metal-water reaction tests and mechanical
testing which ensure the applicability of ECCS models and acceptance
criteria, the limited number and anticipated performance of the
advanced cladding fuel rods, and the use of approved LOCA models to
ensure that the LTAs satisfy 10 CFR 50.46 acceptance criteria, the NRC
staff finds it acceptable to grant an exemption from the requirements
of 10 CFR 50.46 and Appendix K to 10 CFR Part 50 for the use of two
LTAs in either of the HNP reactors for one or more additional cycles,
up to GNF's approved peak pellet exposure.
[[Page 8740]]
Consistent With Common Defense and Security
The proposed exemption would allow the licensee to insert two lead
test fuel assemblies with fuel rod cladding that does not meet the
definition of zircaloy or ZIRLO\TM\ as specified by 10 CFR 50.46, and
Appendix K, into either of the HNP reactors for one or more additional
cycles, up to GNF's approved peak pellet exposure. This change has no
relation to security issues. Therefore, the common defense and security
is not impacted by this exemption.
Special Circumstances
Special circumstances, in accordance with 10 CFR 50.12, are present
whenever application of the regulation in the particular circumstances
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 emergency core cooling system
performance. The wording of the regulations in 10 CFR 50.46 and
Appendix K is not directly applicable to Ziron, even though the
evaluations discussed above show that the intent of the regulations is
met. Therefore, since the NRC staff finds that the underlying purpose
of 10 CFR 50.46 and Appendix K is achieved with the use of Ziron, the
special circumstances required by 10 CFR 50.12 for the 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 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 SNC an exemption from the
requirements of 10 CFR 50.46, and 10 CFR Part 50, Appendix K, to allow
the limited use of two LTAs with selected rods clad with GNF-Ziron
cladding in either of the HNP reactors for one or more additional
cycles, up to GNF's approved peak pellet exposure.
Pursuant to 10 CFR 51.32, the Commission has determined that the
granting of this exemption will not have a significant effect on the
quality of the human environment (79 FR 4983; January 30, 2014).
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 4th day of February 2014.
For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2014-03215 Filed 2-12-14; 8:45 am]
BILLING CODE 7590-01-P