Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit No. 3; Use of AXIOM Fuel Rod Cladding Material, 22862-22865 [2017-10073]
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not impact remaining decommissioning
activities; plant operations,
configuration, and/or radiological
effluents; or nuclear security. The NRC
has determined that the destruction of
the identified records does not involve
information or activities that could
potentially impact the common defense
and security of the United States.
The purpose for the record keeping
regulations is to assist the NRC in
carrying out its mission to protect the
public health and safety by ensuring
that the licensing and design basis of the
facility is understood, documented,
preserved and retrievable in such a way
that will aid the NRC in determining
compliance and noncompliance, taking
action on possible noncompliance, and
examining facts following an incident.
Since the HBPP–3 SSCs that were
safety-related or important to safety
during operations have been removed
from the licensing basis and removed
from the plant, the staff finds that the
records associated with the HBPP–3
licensing basis requirements previously
applicable to the nuclear power unit,
safe storage of fuel in the SFP and
associated SSCs that no longer remain
on site will no longer be required to
achieve the underlying purpose of the
records retention rule.
Accordingly, the Commission has
determined that, pursuant to 10 CFR
50.12, 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, and that special
circumstances are present. Therefore,
the Commission hereby grants Pacific
Gas and Electric Company a one-time
partial exemption from the record
keeping requirements of 10 CFR
50.71(c); 10 CFR part 50, appendix B,
Criterion XVII; and 10 CFR 50.59(d)(3)
for the Humboldt Bay Power Plant, Unit
3, to allow removal of records associated
with the HBPP–3 licensing basis
requirements previously applicable to
the nuclear power unit, safe storage of
fuel in the SFP and associated SSCs that
no longer remain on site.
Records associated with residual
radiological activity and with
programmatic controls necessary to
support decommissioning, such as
security, emergency planning, spent fuel
management and quality assurance are
not affected by the exemption request
and are required to be retained
consistent with existing requirements as
decommissioning records until the
termination of the HBPP–3 license.
This exemption is effective upon
issuance.
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Dated at Rockville, Maryland, this 10th day
of May 2017.
For the Nuclear Regulatory Commission.
John R. Tappert,
Director, Division of Decommissioning,
Uranium Recovery and Waste Programs,
Office of Nuclear Material Safety and
Safeguards.
[FR Doc. 2017–10071 Filed 5–17–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–423; NRC–2017–0118]
Dominion Nuclear Connecticut, Inc.;
Millstone Power Station, Unit No. 3;
Use of AXIOM Fuel Rod Cladding
Material
Nuclear Regulatory
Commission.
ACTION: Exemption; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing an
exemption in response to a June 30,
2016, request, as supplemented by letter
dated March 27, 2017, from Dominion
Nuclear Connecticut, Inc. (DNC or the
licensee) in order to use AXIOM fuel
rod cladding material at Millstone
Power Station, Unit No. 3 (MPS–3).
DATES: The exemption was issued on
May 10, 2017.
ADDRESSES: Please refer to Docket ID
NRC–2017–0118 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly-available
information related to this document
using any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2017–0118. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. The
ADAMS accession number for each
document referenced (if it is available in
SUMMARY:
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ADAMS) is provided the first time that
it is mentioned in this document.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT:
Richard V. Guzman, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington DC
20555–0001; telephone: 301–415–1030,
email: Richard.Guzman@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
Dominion Nuclear Connecticut, Inc. is
the holder of Renewed Facility
Operating License No. NPF–49, which
authorizes operation of MPS–3, a
pressurized-water reactor. The license
provides, among other things, that the
facility is subject to all rules,
regulations, and orders of the NRC now
or hereafter in effect. Millstone Power
Station, Unit No. 3, shares the site with
Millstone Power Station, Unit No. 1, a
permanently defueled boiling water
reactor nuclear unit, and Millstone
Power Station, Unit No. 2, a
pressurized-water reactor. The facility is
located in Waterford, Connecticut,
approximately 2.3 miles southwest of
New London, Connecticut. This
exemption applies to MSP–3 only. The
other Millstone Power Station units, No.
1 and No. 2, are not covered by this
exemption.
II. Request/Action
Pursuant to § 50.12 of title 10 of the
Code of Federal Regulations (10 CFR),
‘‘Specific exemptions,’’ the licensee
requested, by letter dated June 30, 2016
(ADAMS Accession No. ML16189A104),
as supplemented by letter dated March
27, 2017 (ADAMS Accession No.
ML17090A428), an exemption from
§ 50.46, ‘‘Acceptance criteria for
emergency core cooling systems [ECCS]
for light-water nuclear power reactors,’’
and 10 CFR part 50, appendix K, ‘‘ECCS
Evaluation Models,’’ to allow the use of
fuel rod cladding with AXIOM alloy for
future reload applications. The
regulations in § 50.46 contain
acceptance criteria for the ECCS for
reactors fueled with Zircaloy or
ZIRLOTM fuel rod cladding material. In
addition, 10 CFR part 50, 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 Baker-Just equation
assumes the use of a zirconium alloy,
which is a material different from
AXIOM. Therefore, the strict application
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of these regulations does not permit the
use of fuel rod cladding material other
than Zircaloy or ZIRLOTM. Because the
material specifications of AXIOM differ
from the specificaitons for Zircaloy or
ZIRLOTM, and the regulations specify a
cladding material other than AXIOM, a
plant-specific exemption is required to
allow the use of, and application of
these regulations to, AXIOM at MPS–3.
The exemption request relates solely
to the cladding material specified in
these regulations (i.e., fuel rods with
Zircaloy or ZIRLOTM cladding material).
This exemption would allow
application of the acceptance criteria of
§ 50.46 and appendix K to 10 CFR part
50, for fuel assembly designs using
AXIOM fuel rod cladding material. The
licensee is not seeking an exemption
from the acceptance and analytical
criteria of these regulations. The intent
of the request is to allow the use of the
criteria set forth in these regulations for
application of the AXIOM fuel road
cladding material at MPS–3.
jstallworth on DSK7TPTVN1PROD with NOTICES
III. 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 or safety, and are
consistent with the common defense
and security; and (2) when special
circumstances are present. Under
§ 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.
A. Authorized by Law
This exemption would allow the use
of AXIOM fuel rod cladding material for
future reload applications at MPS–3. 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 special
circumstances exist to grant the
requested exemption and that granting
the licensee’s requested exemption
would 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.
B. No Undue Risk to Public Health and
Safety
Section 50.46 requires that each
boiling or pressurized light-water
nuclear power reactor fueled with
uranium oxide pellets within
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cylindrical Zircaloy or ZIRLOTM
cladding must be provided with an
ECCS that must be designed so that its
calculated cooling performance
following a postulated loss-of-coolant
accident (LOCA) conforms to the criteria
set forth in § 50.46(b). The underlying
purpose of § 50.46 is to establish
acceptance criteria for adequate ECCS
performance in response to LOCAs.
The licensee states that there will be
up to eight lead test assemblies (LTAs)
containing fuel rods fabricated with
AXIOM cladding inserted into the core
for MPS–3, Cycle 19. These LTAs will
be placed in non-limiting locations.
Westinghouse performed preliminary
high temperature steam oxidation tests
on AXIOM cladding and confirmed that
AXIOM cladding exhibits a ductile
response to ring compression tests for
peak cladding temperature and
equivalent cladding reacted values up to
and beyond the §§ 50.46(b)(1) and (b)(2)
acceptance criteria, therefore satisfying
the underlying cladding performance
metric used to judge ECCS performance.
This evidence supports the use of the
existing acceptance criteria for fuel rods
fabricated with AXIOM cladding.
Paragraph I.A.5 of appendix K to 10
CFR part 50 states that the rates of
energy, hydrogen concentration, 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 AXIOM cladding. The
Baker-Just equation predicts
conservatively high oxidation rates
compared with modern correlations
(i.e., Cathcart-Pawell) and has been
shown to remain conservative and
applicable for many modern zirconium
alloys. The licensee provided the
nominal alloying composition for
ZIRLOTM, Optimized ZIRLOTM, and
AXIOM cladding material. The licensee
provided evidence that the Baker-Just
equation conservatively predicts the rate
of energy release, hydrogen generation,
and cladding oxidation for the AXIOM
material. Based upon similar material
composition, the high temperature
metal-water reaction rates are expected
to be similar, and the continued use of
the Baker-Just equation is judged by the
NRC staff to be acceptable. Additionally,
the licensee performs cycle-specific
reload evaluations to assure that § 50.46
acceptance criteria are satisfied and will
include the LTAs in such analysis.
Therefore, the NRC staff determined that
the application of paragraph I.A.5 of 10
CFR part 50, appendix K, related to
cladding material is not necessary to
achieve the underlying purpose of the
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rule in these circumstances. Since these
evaluations demonstrate that the
underlying purpose of the rule will be
met, there will be no undue risk to the
public health and safety. Based on the
regulatory review of the exemption
request, the NRC staff concludes that the
intent of § 50.46 and 10 CFR part 50,
appendix K, will continue to be satisfied
for the planned operation of MPS–3
with Westinghouse AXIOM fuel
cladding and fuel assembly material
used for non-limiting LTAs.
C. Consistent With the Common Defense
and Security
The licensee’s exemption request is to
allow the application of the
aforementioned regulations to an
improved fuel rod cladding material. In
its letter dated June 30, 2016, the
licensee stated that all the requirements
and acceptance criteria will be
maintained. The licensee is required to
handle and control special nuclear
material in these assemblies in
accordance with its approved
procedures. The use of LTAs with
AXIOM fuel rod cladding in the MPS–
3 core is not related to and does not
raise security issues. Therefore, the NRC
staff has determined that this exemption
does not impact common defense and
security.
D. Special Circumstances
Special circumstances, in accordance
with § 50.12(a)(2)(ii), 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 § 50.46 and 10 CFR part 50,
appendix K, is to establish acceptance
criteria for ECCS performance to
provide reasonable assurance of safety
in the event of a LOCA. The regulations
in § 50.46 and 10 CFR part 50, appendix
K, are not directly applicable to AXIOM,
even though the evaluations described
in the following sections of this
exemption show that the intent of the
regulation is met. Therefore, since the
underlying purposes of § 50.46 and 10
CFR part 50, appendix K, are achieved
through the use of AXIOM fuel rod
cladding material, the special
circumstances required by
§ 50.12(a)(2)(ii) for the granting of an
exemption exist.
E. Environmental Considerations
The NRC staff determined that the
exemption discussed herein meets the
eligibility criteria for the categorical
exclusion set forth in § 51.22(c)(9)
because it is related to a requirement
concerning the installation or use of a
facility component located within the
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restricted area, as defined in 10 CFR
part 20, and the granting of this
exemption involves: (i) No significant
hazards consideration, (ii) no significant
change in the types or a significant
increase in the amounts of any effluents
that may be released offsite, and (iii) no
significant increase in individual or
cumulative occupational radiation
exposure. Therefore, in accordance with
§ 51.22(b), no environmental impact
statement or environmental assessment
need to be prepared in connection with
the NRC’s consideration of this
exemption request. The basis for the
NRC staff’s determination is discussed
as follows with an evaluation against
each of the requirements in
§ 51.22(c)(9).
Requirements in § 51.22(c)(9)(i)
The NRC staff evaluated the issue of
no significant hazards consideration,
using the standards described in
§ 50.92(c), as presented below:
1. Does the proposed exemption
involve a significant increase in the
probability or consequences of an
accident previously evaluated?
Response: No.
The proposed exemption would allow
DNC to insert up to eight LTAs with
AXIOM fuel rod cladding at MPS–3.
The proposed exemption from the
requirements of § 50.46 and 10 CFR part
50, appendix K, to permit the use of the
AXIOM cladding material in the MPS–
3 core does not adversely affect any
fission product barrier, nor does it alter
the safety function of safety systems,
structures, or components, or their roles
in accident prevention or mitigation.
AXIOM cladding material is not an
accident initiator. The response of the
fuel to an accident is analyzed using
conservative techniques, and the results
are compared to NRC-approved
acceptance criteria. Reload specific
analyses conducted by DNC and the fuel
vendor demonstrate that the design
limits of the fuel cladding are met.
Station operation and analysis will
continue to be in compliance with NRC
regulations. Westinghouse will perform
a cycle-specific analysis of the MPS–3
core using LOCA methods approved for
the site to ensure that assemblies with
AXIOM fuel rod cladding material meet
the LOCA safety criteria. Therefore, the
plant will continue to meet applicable
design criteria and safety analysis
acceptance criteria.
Consequently, permitting the
insertion of up to eight LTAs with
AXIOM fuel rod cladding in the MPS–
3 core does not affect the probability of
an accident or the consequences thereof.
Therefore, the proposed change does
not involve a significant increase in the
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probability or consequences of an
accident previously evaluated.
2. Does the proposed exemption
create the possibility of a new or
different kind of accident from any
accident previously evaluated?
Response: No.
The proposed exemption from the
requirements of § 50.46 and 10 CFR part
50, appendix K, does not impact the
plant configuration or system
performance. The proposed exemption
does not modify any interfaces with
existing equipment, change the
equipment’s function, or change the
method of operating the equipment. Use
of the AXIOM fuel rod cladding material
in the MPS–3 core does not adversely
affect any fission product barrier, nor
does it alter the safety function of safety
systems, structures, or components, or
their roles in accident prevention or
mitigation. Westinghouse will perform a
cycle-specific analysis of the MPS–3
core using LOCA methods approved for
the site to ensure that assemblies with
AXIOM fuel rod cladding material meet
the LOCA safety criteria. Prior to each
cycle, the AXIOM LTAs will be
evaluated to ensure that current design
criteria are met for the projected
burnup. Current NRC-approved models
will be conservatively applied to bound
AXIOM cladding material properties
and expected behavior. If any current
design criteria are not met, the LTAs
with AXIOM fuel rod cladding will not
be inserted into the core. The proposed
exemption assures there is adequate
margin available to meet safety analysis
criteria and does not introduce any
failure modes, accident initiators, or
equipment malfunctions that would
cause a new or different kind of
accident.
Therefore, the proposed change does
not create the possibility of a new or
different kind of accident from any
previously evaluated.
3. Does the proposed exemption
involve a significant reduction in a
margin of safety?
Response: No.
The proposed exemption from the
requirements of § 50.46 and 10 CFR part
50, appendix K, does not impact the
plant configuration or system
performance, and use of the AXIOM
cladding material in the MPS–3 core
does not adversely affect any fission
product barrier. Current NRC-approved
models will be conservatively applied to
bound AXIOM cladding material
properties and expected behavior to
ensure the plant continues to meet
applicable design criteria and safety
analysis acceptance criteria. The
proposed exemption does not alter the
manner in which safety limits, limiting
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safety system settings, or limiting
conditions for operation are determined,
and the dose analysis acceptance
criteria are not affected. The proposed
exemption does not result in plant
operation in a configuration outside the
analysis or design basis and does not
adversely affect systems that respond to
safely shut down the plant and maintain
the plant in a safe shutdown condition.
Westinghouse will perform a cyclespecific analysis of the MPS–3 core
using LOCA methods approved for the
site to ensure that assemblies with
AXIOM fuel rod cladding material meet
the LOCA safety criteria. Prior to each
cycle, the AXIOM LTAs will be
evaluated to ensure that current design
criteria are met for the projected
burnup. Current NRC-approved models
will be conservatively applied to bound
AXIOM cladding material properties
and expected behavior. If any current
design criteria are not met, the AXIOM
cladding LTAs will not be inserted into
the core.
Therefore, the proposed change does
not involve a significant reduction in a
margin of safety.
Based on the above, the NRC staff
concludes that the proposed exemption
presents no significant hazards
consideration under the standards set
forth in § 50.92(c), and, accordingly, a
finding of no significant hazards
consideration is justified (i.e., satisfies
the provisions of § 51.22(c)(9)(i)).
Requirements in § 51.22(c)(9)(ii)
The proposed exemption would allow
the use of AXIOM fuel rod cladding
material in the MPS–3 reactor. AXIOM
material has essentially the same
properties as the currently licensed
Optimized ZIRLOTM cladding and
standard ZIRLOTM alloys. The use of the
AXIOM fuel rod cladding material will
not significantly change the types of
effluents that may be released offsite or
significantly increase the amount of
effluents that may be released offsite.
Therefore, the provisions of
§ 51.22(c)(9)(ii) are satisfied.
Requirements in § 51.22(c)(9)(iii)
The proposed exemption would allow
the use of AXIOM fuel rod cladding
material in the reactors. AXIOM
material has essentially the same
properties as the currently licensed
Optimized ZIRLOTM cladding and
standard ZIRLOTM alloys. The use of the
AXIOM fuel rod cladding material will
not significantly increase individual
occupational radiation exposure or
significantly increase cumulative
occupational radiation exposure.
Therefore, the provisions of
§ 51.22(c)(9)(iii) are satisfied.
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Conclusion
Based on the above, the NRC staff
concludes that the proposed exemption
meets the eligibility criteria for the
categorical exclusion set forth in
§ 51.22(c)(9). Therefore, in accordance
with § 51.22(b), no environmental
impact statement or environmental
assessment need to be prepared in
connection with the NRC’s proposed
issuance of this exemption.
IV. Conclusion
Accordingly, the Commission has
determined that pursuant to 10 CFR
50.12, 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 DNC an
exemption from the requirements of 10
CFR 50.46 and appendix K of 10 CFR
part 50, to allow the use of AXIOM fuel
rod cladding material at MPS–3. As
stated above, this exemption relates
solely to the cladding material specified
in these regulations.
Dated at Rockville, Maryland, this 10th day
of May 2017.
For the Nuclear Regulatory Commission.
MaryJane Ross-Lee,
Acting Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2017–10073 Filed 5–17–17; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2016–0156]
Information Collection: Solicitation of
Non-Power Reactor Operator
Licensing Examination Data
Nuclear Regulatory
Commission.
ACTION: Proposed information
collection; request for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) invites public
comment on this proposed collection of
information. The information collection
is entitled, ‘‘Solicitation of Non-Power
Reactor Operator Licensing Examination
Data.’’
DATES: Submit comments by July 17,
2017. Comments received after this date
will be considered if it is practical to do
so, but the Commission is able to ensure
consideration only for comments
received on or before this date.
ADDRESSES: You may submit comments
by any of the following methods:
jstallworth on DSK7TPTVN1PROD with NOTICES
SUMMARY:
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• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0156. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: David Cullison,
Office of the Chief Information Officer,
Mail Stop: T–5 F53, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
For additional direction on obtaining
information and submitting comments,
see ‘‘Obtaining Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
FOR FURTHER INFORMATION CONTACT:
David Cullison, Office of the Chief
Information Officer, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 301–415–
2084; email: INFOCOLLECTS.Resource@
nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2016–
0156 when contacting the NRC about
the availability of information for this
action. You may obtain publiclyavailable information related to this
action by any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0156. A copy
of the collection of information and
related instructions may be obtained
without charge by accessing Docket ID
NRC–2016–0156 on this Web site.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. A copy
of the collection of information and
related instructions may be obtained
without charge by accessing ADAMS
Accession No. ML17011A068. The
supporting statement is available in
ADAMS under Accession No.
ML17011A063.
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• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
• NRC’s Clearance Officer: A copy of
the collection of information and related
instructions may be obtained without
charge by contacting NRC’s Clearance
Officer, David Cullison, Office of the
Chief Information Officer, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 301–415–
2084; email: INFOCOLLECTS.Resource@
nrc.gov.
B. Submitting Comments
Please include Docket ID NRC–2016–
0156 in the subject line of your
comment submission, in order to ensure
that the NRC is able to make your
comment submission available to the
public in this docket.
The NRC cautions you not to include
identifying or contact information in
comment submissions that you do not
want to be publicly disclosed in your
comment submission. All comment
submissions are posted at https://
www.regulations.gov and entered into
ADAMS. Comment submissions are not
routinely edited to remove identifying
or contact information.
If you are requesting or aggregating
comments from other persons for
submission to the NRC, then you should
inform those persons not to include
identifying or contact information that
they do not want to be publicly
disclosed in their comment submission.
Your request should state that comment
submissions are not routinely edited to
remove such information before making
the comment submissions available to
the public or entering the comment into
ADAMS.
II. Background
In accordance with the Paperwork
Reduction Act of 1995 (44 U.S.C.
Chapter 35), the NRC is requesting
public comment on its intention to
request the OMB’s approval for the
information collection summarized
below.
1. The title of the information
collection: Solicitation of Non-Power
Reactor Operator Licensing Examination
Data.
2. OMB approval number: An OMB
control number has not yet been
assigned to this proposed information
collection.
3. Type of submission: New.
4. The form number, if applicable:
Not applicable.
5. How often the collection is required
or requested: Annually.
E:\FR\FM\18MYN1.SGM
18MYN1
Agencies
[Federal Register Volume 82, Number 95 (Thursday, May 18, 2017)]
[Notices]
[Pages 22862-22865]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-10073]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-423; NRC-2017-0118]
Dominion Nuclear Connecticut, Inc.; Millstone Power Station, Unit
No. 3; Use of AXIOM Fuel Rod Cladding Material
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption; issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an
exemption in response to a June 30, 2016, request, as supplemented by
letter dated March 27, 2017, from Dominion Nuclear Connecticut, Inc.
(DNC or the licensee) in order to use AXIOM fuel rod cladding material
at Millstone Power Station, Unit No. 3 (MPS-3).
DATES: The exemption was issued on May 10, 2017.
ADDRESSES: Please refer to Docket ID NRC-2017-0118 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0118. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. The
ADAMS accession number for each document referenced (if it is available
in ADAMS) is provided the first time that it is mentioned in this
document.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Richard V. Guzman, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC
20555-0001; telephone: 301-415-1030, email: Richard.Guzman@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
Dominion Nuclear Connecticut, Inc. is the holder of Renewed
Facility Operating License No. NPF-49, which authorizes operation of
MPS-3, a pressurized-water reactor. The license provides, among other
things, that the facility is subject to all rules, regulations, and
orders of the NRC now or hereafter in effect. Millstone Power Station,
Unit No. 3, shares the site with Millstone Power Station, Unit No. 1, a
permanently defueled boiling water reactor nuclear unit, and Millstone
Power Station, Unit No. 2, a pressurized-water reactor. The facility is
located in Waterford, Connecticut, approximately 2.3 miles southwest of
New London, Connecticut. This exemption applies to MSP-3 only. The
other Millstone Power Station units, No. 1 and No. 2, are not covered
by this exemption.
II. Request/Action
Pursuant to Sec. 50.12 of title 10 of the Code of Federal
Regulations (10 CFR), ``Specific exemptions,'' the licensee requested,
by letter dated June 30, 2016 (ADAMS Accession No. ML16189A104), as
supplemented by letter dated March 27, 2017 (ADAMS Accession No.
ML17090A428), an exemption from Sec. 50.46, ``Acceptance criteria for
emergency core cooling systems [ECCS] for light-water nuclear power
reactors,'' and 10 CFR part 50, appendix K, ``ECCS Evaluation Models,''
to allow the use of fuel rod cladding with AXIOM alloy for future
reload applications. The regulations in Sec. 50.46 contain acceptance
criteria for the ECCS for reactors fueled with Zircaloy or
ZIRLOTM fuel rod cladding material. In addition, 10 CFR part
50, 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 Baker-Just
equation assumes the use of a zirconium alloy, which is a material
different from AXIOM. Therefore, the strict application
[[Page 22863]]
of these regulations does not permit the use of fuel rod cladding
material other than Zircaloy or ZIRLOTM. Because the
material specifications of AXIOM differ from the specificaitons for
Zircaloy or ZIRLOTM, and the regulations specify a cladding
material other than AXIOM, a plant-specific exemption is required to
allow the use of, and application of these regulations to, AXIOM at
MPS-3.
The exemption request relates solely to the cladding material
specified in these regulations (i.e., fuel rods with Zircaloy or
ZIRLOTM cladding material). This exemption would allow
application of the acceptance criteria of Sec. 50.46 and appendix K to
10 CFR part 50, for fuel assembly designs using AXIOM fuel rod cladding
material. The licensee is not seeking an exemption from the acceptance
and analytical criteria of these regulations. The intent of the request
is to allow the use of the criteria set forth in these regulations for
application of the AXIOM fuel road cladding material at MPS-3.
III. 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 or
safety, and are consistent with the common defense and security; and
(2) when special circumstances are present. Under Sec. 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.
A. Authorized by Law
This exemption would allow the use of AXIOM fuel rod cladding
material for future reload applications at MPS-3. 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 special circumstances
exist to grant the requested exemption and that granting the licensee's
requested exemption would 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.
B. No Undue Risk to Public Health and Safety
Section 50.46 requires that each boiling or pressurized light-water
nuclear power reactor fueled with uranium oxide pellets within
cylindrical Zircaloy or ZIRLOTM cladding must be provided
with an ECCS that must be designed so that its calculated cooling
performance following a postulated loss-of-coolant accident (LOCA)
conforms to the criteria set forth in Sec. 50.46(b). The underlying
purpose of Sec. 50.46 is to establish acceptance criteria for adequate
ECCS performance in response to LOCAs.
The licensee states that there will be up to eight lead test
assemblies (LTAs) containing fuel rods fabricated with AXIOM cladding
inserted into the core for MPS-3, Cycle 19. These LTAs will be placed
in non-limiting locations. Westinghouse performed preliminary high
temperature steam oxidation tests on AXIOM cladding and confirmed that
AXIOM cladding exhibits a ductile response to ring compression tests
for peak cladding temperature and equivalent cladding reacted values up
to and beyond the Sec. Sec. 50.46(b)(1) and (b)(2) acceptance
criteria, therefore satisfying the underlying cladding performance
metric used to judge ECCS performance. This evidence supports the use
of the existing acceptance criteria for fuel rods fabricated with AXIOM
cladding.
Paragraph I.A.5 of appendix K to 10 CFR part 50 states that the
rates of energy, hydrogen concentration, 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 AXIOM cladding. The Baker-Just equation predicts
conservatively high oxidation rates compared with modern correlations
(i.e., Cathcart-Pawell) and has been shown to remain conservative and
applicable for many modern zirconium alloys. The licensee provided the
nominal alloying composition for ZIRLOTM, Optimized
ZIRLOTM, and AXIOM cladding material. The licensee provided
evidence that the Baker-Just equation conservatively predicts the rate
of energy release, hydrogen generation, and cladding oxidation for the
AXIOM material. Based upon similar material composition, the high
temperature metal-water reaction rates are expected to be similar, and
the continued use of the Baker-Just equation is judged by the NRC staff
to be acceptable. Additionally, the licensee performs cycle-specific
reload evaluations to assure that Sec. 50.46 acceptance criteria are
satisfied and will include the LTAs in such analysis. Therefore, the
NRC staff determined that the application of paragraph I.A.5 of 10 CFR
part 50, appendix K, related to cladding material is not necessary to
achieve the underlying purpose of the rule in these circumstances.
Since these evaluations demonstrate that the underlying purpose of the
rule will be met, there will be no undue risk to the public health and
safety. Based on the regulatory review of the exemption request, the
NRC staff concludes that the intent of Sec. 50.46 and 10 CFR part 50,
appendix K, will continue to be satisfied for the planned operation of
MPS-3 with Westinghouse AXIOM fuel cladding and fuel assembly material
used for non-limiting LTAs.
C. Consistent With the Common Defense and Security
The licensee's exemption request is to allow the application of the
aforementioned regulations to an improved fuel rod cladding material.
In its letter dated June 30, 2016, the licensee stated that all the
requirements and acceptance criteria will be maintained. The licensee
is required to handle and control special nuclear material in these
assemblies in accordance with its approved procedures. The use of LTAs
with AXIOM fuel rod cladding in the MPS-3 core is not related to and
does not raise security issues. Therefore, the NRC staff has determined
that this exemption does not impact common defense and security.
D. Special Circumstances
Special circumstances, in accordance with Sec. 50.12(a)(2)(ii),
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 Sec. 50.46 and 10 CFR part 50,
appendix K, is to establish acceptance criteria for ECCS performance to
provide reasonable assurance of safety in the event of a LOCA. The
regulations in Sec. 50.46 and 10 CFR part 50, appendix K, are not
directly applicable to AXIOM, even though the evaluations described in
the following sections of this exemption show that the intent of the
regulation is met. Therefore, since the underlying purposes of Sec.
50.46 and 10 CFR part 50, appendix K, are achieved through the use of
AXIOM fuel rod cladding material, the special circumstances required by
Sec. 50.12(a)(2)(ii) for the granting of an exemption exist.
E. Environmental Considerations
The NRC staff determined that the exemption discussed herein meets
the eligibility criteria for the categorical exclusion set forth in
Sec. 51.22(c)(9) because it is related to a requirement concerning the
installation or use of a facility component located within the
[[Page 22864]]
restricted area, as defined in 10 CFR part 20, and the granting of this
exemption involves: (i) No significant hazards consideration, (ii) no
significant change in the types or a significant increase in the
amounts of any effluents that may be released offsite, and (iii) no
significant increase in individual or cumulative occupational radiation
exposure. Therefore, in accordance with Sec. 51.22(b), no
environmental impact statement or environmental assessment need to be
prepared in connection with the NRC's consideration of this exemption
request. The basis for the NRC staff's determination is discussed as
follows with an evaluation against each of the requirements in Sec.
51.22(c)(9).
Requirements in Sec. 51.22(c)(9)(i)
The NRC staff evaluated the issue of no significant hazards
consideration, using the standards described in Sec. 50.92(c), as
presented below:
1. Does the proposed exemption involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed exemption would allow DNC to insert up to eight LTAs
with AXIOM fuel rod cladding at MPS-3. The proposed exemption from the
requirements of Sec. 50.46 and 10 CFR part 50, appendix K, to permit
the use of the AXIOM cladding material in the MPS-3 core does not
adversely affect any fission product barrier, nor does it alter the
safety function of safety systems, structures, or components, or their
roles in accident prevention or mitigation. AXIOM cladding material is
not an accident initiator. The response of the fuel to an accident is
analyzed using conservative techniques, and the results are compared to
NRC-approved acceptance criteria. Reload specific analyses conducted by
DNC and the fuel vendor demonstrate that the design limits of the fuel
cladding are met. Station operation and analysis will continue to be in
compliance with NRC regulations. Westinghouse will perform a cycle-
specific analysis of the MPS-3 core using LOCA methods approved for the
site to ensure that assemblies with AXIOM fuel rod cladding material
meet the LOCA safety criteria. Therefore, the plant will continue to
meet applicable design criteria and safety analysis acceptance
criteria.
Consequently, permitting the insertion of up to eight LTAs with
AXIOM fuel rod cladding in the MPS-3 core does not affect the
probability of an accident or the consequences thereof.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident previously
evaluated.
2. Does the proposed exemption create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed exemption from the requirements of Sec. 50.46 and 10
CFR part 50, appendix K, does not impact the plant configuration or
system performance. The proposed exemption does not modify any
interfaces with existing equipment, change the equipment's function, or
change the method of operating the equipment. Use of the AXIOM fuel rod
cladding material in the MPS-3 core does not adversely affect any
fission product barrier, nor does it alter the safety function of
safety systems, structures, or components, or their roles in accident
prevention or mitigation. Westinghouse will perform a cycle-specific
analysis of the MPS-3 core using LOCA methods approved for the site to
ensure that assemblies with AXIOM fuel rod cladding material meet the
LOCA safety criteria. Prior to each cycle, the AXIOM LTAs will be
evaluated to ensure that current design criteria are met for the
projected burnup. Current NRC-approved models will be conservatively
applied to bound AXIOM cladding material properties and expected
behavior. If any current design criteria are not met, the LTAs with
AXIOM fuel rod cladding will not be inserted into the core. The
proposed exemption assures there is adequate margin available to meet
safety analysis criteria and does not introduce any failure modes,
accident initiators, or equipment malfunctions that would cause a new
or different kind of accident.
Therefore, the proposed change does not create the possibility of a
new or different kind of accident from any previously evaluated.
3. Does the proposed exemption involve a significant reduction in a
margin of safety?
Response: No.
The proposed exemption from the requirements of Sec. 50.46 and 10
CFR part 50, appendix K, does not impact the plant configuration or
system performance, and use of the AXIOM cladding material in the MPS-3
core does not adversely affect any fission product barrier. Current
NRC-approved models will be conservatively applied to bound AXIOM
cladding material properties and expected behavior to ensure the plant
continues to meet applicable design criteria and safety analysis
acceptance criteria. The proposed exemption does not alter the manner
in which safety limits, limiting safety system settings, or limiting
conditions for operation are determined, and the dose analysis
acceptance criteria are not affected. The proposed exemption does not
result in plant operation in a configuration outside the analysis or
design basis and does not adversely affect systems that respond to
safely shut down the plant and maintain the plant in a safe shutdown
condition. Westinghouse will perform a cycle-specific analysis of the
MPS-3 core using LOCA methods approved for the site to ensure that
assemblies with AXIOM fuel rod cladding material meet the LOCA safety
criteria. Prior to each cycle, the AXIOM LTAs will be evaluated to
ensure that current design criteria are met for the projected burnup.
Current NRC-approved models will be conservatively applied to bound
AXIOM cladding material properties and expected behavior. If any
current design criteria are not met, the AXIOM cladding LTAs will not
be inserted into the core.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
Based on the above, the NRC staff concludes that the proposed
exemption presents no significant hazards consideration under the
standards set forth in Sec. 50.92(c), and, accordingly, a finding of
no significant hazards consideration is justified (i.e., satisfies the
provisions of Sec. 51.22(c)(9)(i)).
Requirements in Sec. 51.22(c)(9)(ii)
The proposed exemption would allow the use of AXIOM fuel rod
cladding material in the MPS-3 reactor. AXIOM material has essentially
the same properties as the currently licensed Optimized
ZIRLOTM cladding and standard ZIRLOTM alloys. The
use of the AXIOM fuel rod cladding material will not significantly
change the types of effluents that may be released offsite or
significantly increase the amount of effluents that may be released
offsite. Therefore, the provisions of Sec. 51.22(c)(9)(ii) are
satisfied.
Requirements in Sec. 51.22(c)(9)(iii)
The proposed exemption would allow the use of AXIOM fuel rod
cladding material in the reactors. AXIOM material has essentially the
same properties as the currently licensed Optimized ZIRLOTM
cladding and standard ZIRLOTM alloys. The use of the AXIOM
fuel rod cladding material will not significantly increase individual
occupational radiation exposure or significantly increase cumulative
occupational radiation exposure. Therefore, the provisions of Sec.
51.22(c)(9)(iii) are satisfied.
[[Page 22865]]
Conclusion
Based on the above, the NRC staff concludes that the proposed
exemption meets the eligibility criteria for the categorical exclusion
set forth in Sec. 51.22(c)(9). Therefore, in accordance with Sec.
51.22(b), no environmental impact statement or environmental assessment
need to be prepared in connection with the NRC's proposed issuance of
this exemption.
IV. Conclusion
Accordingly, the Commission has determined that pursuant to 10 CFR
50.12, 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 DNC an exemption from the
requirements of 10 CFR 50.46 and appendix K of 10 CFR part 50, to allow
the use of AXIOM fuel rod cladding material at MPS-3. As stated above,
this exemption relates solely to the cladding material specified in
these regulations.
Dated at Rockville, Maryland, this 10th day of May 2017.
For the Nuclear Regulatory Commission.
MaryJane Ross-Lee,
Acting Director, Division of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2017-10073 Filed 5-17-17; 8:45 am]
BILLING CODE 7590-01-P