Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 2; Environmental Assessment and Finding of No Significant Impact, 13757-13762 [2024-03665]
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Federal Register / Vol. 89, No. 37 / Friday, February 23, 2024 / Notices
laboratory studies, and include at-scale
tests in the field, ensuring that ocean
observations are robust, sustained, and
verifiable. The research program will
support the effective regulation of
marine CDR and inform decisions about
the possible deployment and
commercial application of marine CDR
approaches in the future. It will identify
the most urgent research priorities for
Federal support and take into account
related efforts by academia, industry,
philanthropy, non-governmental
organizations, and other governments.
• Clarify permitting, regulatory, and
other standards and policies, and
establish guidelines for marine CDR
research. The Marine CDR Plan will
identify relevant domestic and
international regulatory frameworks and
clarify how they apply to marine CDR
research, including at-scale tests in the
field. The guidelines will identify
considerations for measuring,
monitoring, reporting, and verifying
(MMRV) marine CDR to support
permitting and regulation and the
development of standards for carbon
accounting. The Marine CDR Plan will
also identify any critical gaps in
knowledge and capabilities necessary to
effectively regulate marine CDR.
• Establish a Marine CDR Initiative to
enable public-private partnerships and
establish mechanisms to strengthen
interagency coordination and promote
public awareness and engagement. The
Marine CDR Plan will establish a
mechanism or mechanisms to: (1)
strengthen the ability of Departments
and Agencies across the Federal
Government to collaborate on marine
CDR research and regulation; (2)
facilitate information sharing and
stakeholder engagement, including with
Indigenous communities and
communities that may be affected by
marine CDR; and (3) enable partnerships
between the Federal Government and
academia, industry, philanthropy, nongovernmental organizations and other
governments, including to fund research
jointly, such as through a Marine CDR
Initiative.
In developing these three actions in
the Marine CDR Plan, the MCDR–FTAC
will seek to harmonize and streamline
existing Federal research efforts, the
regulatory process, and public
engagement and partnerships for marine
CDR.
Questions To Inform Development of
the Strategy
You may provide information for one
or as many topics below as you choose.
Clearly indicate in your submission
which questions are being addressed.
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The MCDR–FTAC is seeking input from
the public on the following:
1. How would a Marine CDR Plan
affect you, your organization, or your
community?
2. What questions or concerns do you
have about the regulation of marine
CDR, including marine CDR research?
What tools or resources should the
Federal Government provide to support
the safety and effectiveness of marine
CDR research, including testing at scale
in the field? What knowledge exists, and
what additional knowledge is needed to
inform the safe and effective regulation
of marine CDR research? What
knowledge exists and what additional
knowledge will be needed to inform
decisions about the readiness of any
marine CDR approach for full-scale
deployment or commercial application?
3. Which marine CDR techniques or
what aspects of marine CDR do you
believe the Federal Government should
prioritize for research? Are there
particular marine CDR approaches that
you believe are especially promising
with regard to climate change
mitigation, ocean acidification, or other
benefits? Are there particular marine
CDR approaches that you believe are
particularly more or less risky with
regard to the environment, public health
and communities, or other uses of the
sea?
4. What kinds of information about
marine CDR would be most helpful for
the Federal Government to make
available to the public, research
community, and other stakeholders?
How should the government engage
marine CDR stakeholders and the
public, including Indigenous
communities and communities that may
be affected by marine CDR?
5. What are the most significant
marine CDR efforts being undertaken by
academia, industry, philanthropy, nongovernmental organizations, and other
governments that the Federal
Government should be aware of? What
factors should the Federal Government
take into account when considering
potential partnerships between these
entities and the Federal Government?
What are the biggest challenges that the
Federal Government and potential
partners may face in collaborating, and
how could the Federal Government help
overcome these challenges? What
examples of partnerships are most
relevant to potential marine CDR
partnerships?
6. What else would you like the
Federal Government to consider as it
develops a Marine CDR Plan?
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Dated: February 20, 2024.
Suzanne H. Plimpton,
Reports Clearance Officer, National Science
Foundation.
[FR Doc. 2024–03758 Filed 2–22–24; 8:45 am]
BILLING CODE 7555–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–390 and 50–391; NRC–
2024–0035]
Tennessee Valley Authority; Watts Bar
Nuclear Plant, Units 1 and 2;
Environmental Assessment and
Finding of No Significant Impact
Nuclear Regulatory
Commission.
ACTION: Notice; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of amendments to Facility
Operating License Nos. NPF–90 and
NPF–96, issued on February 7, 1996,
and October 22, 2015, respectively, and
held by Tennessee Valley Authority
(TVA, the licensee) for the operation of
Watts Bar Nuclear Plant (Watts Bar),
Units 1 and 2. The proposed
amendments would revise the Watts
Bar, Units 1 and 2, Technical
Specification (TS) 4.2.1, ‘‘Fuel
Assemblies,’’ and TS 5.9.6, ‘‘Reactor
Coolant System (RCS) Pressure and
Temperature Limits Report (PTLR),’’ to
increase the maximum number of
tritium producing burnable absorber
rods (TPBARs) and to add supporting
methodologies. The proposed
amendments would also revise the
Watts Bar Dual-Unit Updated Final
Safety Analysis Report to modify the
source term for design basis accident
analyses. The NRC is issuing an
environmental assessment (EA) and
finding of no significant impact (FONSI)
associated with the proposed
amendments.
DATES: The EA and FONSI referenced in
this document are available on February
23, 2024.
ADDRESSES: Please refer to Docket ID
NRC–2024–0035 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 website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2024–0035. Address
questions about Docket IDs in
Regulations.gov to Stacy Schumann;
telephone: 301–415–0624; email:
Stacy.Schumann@nrc.gov. For technical
SUMMARY:
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Federal Register / Vol. 89, No. 37 / Friday, February 23, 2024 / Notices
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
‘‘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, at
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. In
addition, for the convenience of the
reader, the ADAMS accession numbers
are provided in a table in the
‘‘Availability of Documents’’ section of
this document.
• NRC’s PDR: The PDR, where you
may examine and order copies of
publicly available documents, is open
by appointment. To make an
appointment to visit the PDR, please
send an email to PDR.Resource@nrc.gov
or call 1–800–397–4209 or 301–415–
4737, between 8 a.m. and 4 p.m. eastern
time (ET), Monday through Friday,
except Federal holidays.
FOR FURTHER INFORMATION CONTACT:
Kimberly Green, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–415–
1627; email: Kimberly.Green@nrc.gov.
SUPPLEMENTARY INFORMATION:
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I. Introduction
The NRC is considering issuance of
amendments to Facility Operating
License Nos. NPF–90 and NPF–96,
issued to TVA, for the operation of
Watts Bar, Units 1 and 2, located in
Rhea County, Tennessee. Therefore, as
required by section 51.21, ‘‘Criteria for
and identification of licensing and
regulatory actions requiring
environmental assessments,’’ of title 10
of the Code of Federal Regulations (10
CFR), the NRC performed an EA that
analyzes the environmental impacts of
the proposed licensing action and
alternatives as appropriate. Based on the
results of the EA that follows, and in
accordance with 10 CFR 51.31(a), the
NRC has determined not to prepare an
environmental impact statement for the
proposed licensing action and is issuing
a FONSI.
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II. Environmental Assessment
Description of the Proposed Action
The proposed action would revise
Watts Bar, Units 1 and 2, TS 4.2.1 to
increase the limit on the maximum
number of TPBARs that can be
irradiated in the reactor core in an
operating cycle from 1,792 to 2,496. The
proposed action would also revise Watts
Bar, Units 1 and 2, TS 5.9.6 to add
supporting methodologies.
Additionally, the proposed action
would revise the Watts Bar Dual-Unit
Updated Final Safety Analysis Report to
modify the source term for design basis
accident analyses to allow the core
fission product inventory to be
calculated using an updated version of
the ORIGEN computer code.
The proposed action is in accordance
with the licensee’s application dated
March 20, 2023 (ADAMS Accession No.
ML23079A270).
Need for the Proposed Action
The U.S. Department of Energy (DOE)
and TVA are cooperating in a program
to produce tritium for the National
Security Stockpile by irradiating
TPBARs in the Watts Bar, Units 1 and
2, reactor cores. Tritium is produced
when the neutrons produced by nuclear
fission in the core are absorbed by the
lithium target material of the TPBARs.
A solid zirconium metal cladding
covering the TPBARs (called a ‘‘getter’’)
captures the tritium produced.
This proposed action is needed to
support the DOE, National Nuclear
Security Administration, National
Security Stockpile, in accordance with
Public Law (Pub. L.) 106–65. Section
3134 of Public Law 106–65 directs the
Secretary of Energy to produce new
tritium at Watts Bar. By letters dated
July 29, 2016 (ADAMS Accession No.
ML16159A057), and May 22, 2019
(ADAMS Accession No. ML18347B330),
the NRC approved similar amendments
to irradiate up to 1,792 TPBARs in the
Watts Bar reactor cores. The EA and
FONSI for those licensing actions,
completed on June 23, 2016, and
February 6, 2019, can be found in
ADAMS under Accession Nos.
ML16138A045 and ML18332A013,
respectively.
Environmental Impacts of the Proposed
Action
The NRC staff has assessed the
potential environmental impacts from
the proposed increase in the maximum
number of TPBARs that can be
irradiated in the Watts Bar reactor cores.
The non-radiological and radiological
impacts on the environment that may
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result from the proposed action are
summarized as follows.
Non-Radiological Impacts
The proposed action involves no new
construction or modification of Watts
Bar, Units 1 and 2, operational systems
and would have no direct impact on
land and water use or water quality,
including terrestrial and aquatic biota.
There would also be no change in the
quality or quantity of non-radiological
effluents and no need to modify the
nuclear plant’s National Pollutant
Discharge Elimination System permit.
The proposed action would have no
effect on air pollutant emissions or
ambient air quality. In addition, the
proposed action would have no
noticeable effect on socioeconomic and
environmental justice conditions in the
region, and no adverse effect on historic
and cultural resources. Therefore, the
proposed action would have no
significant non-radiological effect on the
quality of the human environment.
Radiological Impacts
All nuclear power plants, including
Watts Bar, Units 1 and 2, release small
amounts of radioactive material to the
environment as liquid or gaseous
effluents as part of normal operations.
The NRC summarizes U.S. nuclear
power plant effluent data on its public
website [https://www.nrc.gov/readingrm/doc-collections/nuregs/contract/
cr2907/]. These effluents are
controlled, monitored, and reported per
NRC requirements to ensure that doses
to the public are known and within
acceptable guidelines that are as low as
is reasonably achievable (ALARA). The
Watts Bar Offsite Dose Calculation
Manual (ODCM), documented in the
Watts Bar Nuclear Power Plant 2022,
Annual Radioactive Effluent Release
Report (ADAMS Accession No.
ML23117A100), provides the limits and
methods used by TVA to ensure
compliance with requirements that
apply to radioactive effluents. Watts
Bar, Units 1 and 2, use waste treatment
systems to collect, process, and recycle
plant fluids that contain radioactive
material and to dispose of gaseous and
liquid effluents and solid wastes in a
safe and controlled manner within NRC
and U.S. Environmental Protection
Agency radiation safety standards.
Implementation of the proposed action
would allow up to 2,496 TPBARs per
cycle to be irradiated in the Watts Bar,
Units 1 and 2, reactor cores. Increasing
the number of TPBARs irradiated from
1,792 to 2,496 per reactor core could
increase the quantities of radioactive
material released from Watts Bar to the
environment because some of the
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tritium that is produced permeates
through the TPBAR cladding and is
released into the reactor coolant system
(RCS) fluid. Radioactive material in RCS
fluid can be released as gaseous or
liquid effluent. For the purposes of
assessing the environmental impacts
and the regulatory compliance of this
proposed action for tritium production,
TVA assumed a core load of 2,496
TPBARs with a permeation rate of 5.0
curies per TPBAR per year (Ci/TPBAR/
year) of tritium and was able to
demonstrate that liquid and gaseous
effluents would be within applicable
limits. The assumed permeation rate is
conservative in that it bounds the
observed and maximum TPBAR tritium
permeation rates at Watts Bar, Units 1
and 2. Specifically, based on the
licensee’s experience with TPBARs
dating back to 2004, the licensee has
observed a permeation rate for tritium
production of less than 3.5 Ci/TPBAR/
year. Additionally, as provided in this
document, the licensee demonstrated
that other changes to the radioisotope
inventory that can impact effluent levels
would be minor and would not impact
the licensee’s ability to meet applicable
limits. Therefore, while the quantity of
tritium generated during plant
operations would increase under the
proposed action, radioactive effluents
from Watts Bar would remain within
applicable limits.
Radioactive Gaseous Effluents
The Watts Bar units maintain a
gaseous waste management system
(GWMS) that is designed to process and
control the release of radioactive
gaseous effluents into the environment
in accordance with the requirements of
10 CFR 20.1301, ‘‘Dose limits for
individual members of the public,’’ and
to ensure consistency with the ALARA
dose objectives set forth in appendix I,
‘‘Numerical Guides for Design
Objectives and Limiting Conditions for
Operation to Meet the Criterion ‘As Low
as is Reasonably Achievable’ for
Radioactive Material in Light-WaterCooled Nuclear Power Reactor
Effluents,’’ to 10 CFR part 50, ‘‘Domestic
Licensing of Production and Utilization
Facilities.’’
As stated in the license amendment
request, TVA assumed a core load of
2,496 TPBARs with a permeation rate of
5.0 Ci/TPBAR/year of tritium, which is
a conservative source term that bounds
the observed and maximum TPBAR
tritium permeation rate as seen from
historic Watts Bar, Units 1 and 2,
tritium production.
To determine whether the resultant
gaseous effluents would fall within the
requirements of 10 CFR 20.1301, TVA
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calculated the sum of the ratios of each
isotope concentration (C) to its
corresponding gaseous Effluent
Concentration Limit (ECL, as listed in
10 CFR part 20, ‘‘Standards for
Protection against Radiation,’’ appendix
B, ‘‘Annual Limits on Intake (ALIs) and
Derived Air Concentrations (DACs) of
Radionuclides for Occupational
Exposure; Effluent Concentrations;
Concentrations for Release to
Sewerage,’’ table 2, ‘‘Effluent
Concentration,’’ column 1). Consistent
with the requirements of 10 CFR
20.1302(b)(2)(i), a C/ECL sum of less
than 1.0 indicates that the annual
average effluent release is within the
limits of 10 CFR 20.1301. Tables 4.11–
6 and 4.11–7 of the license amendment
request demonstrate that TVA’s
calculated C/ECL sums for gaseous
effluent releases at the Watts Bar units
from an assumed core load of 2,496
TPBARs for containment purge without
filtration would be 0.458 (single unit)
and with continuous filtration would be
0.402 (single unit). TVA’s calculated C/
ECL sums for gaseous effluent releases
for both Watts Bar, Units 1 and 2 (dualunit operation) for containment purge
without filtration would be 0.915 and
with continuous filtration would be
0.805. Therefore, the licensee
demonstrated that the C/ECL ratios are
less than 1.0 indicating that gaseous
effluent releases from an assumed core
load of 2,496 TPBARs would be within
the limits of 10 CFR part 20.
To determine whether the gaseous
effluent releases would be consistent
with the ALARA dose objectives set
forth in appendix I to 10 CFR part 50
(which are per-unit numbers), TVA
calculated bounding public doses from
the applicable plant effluent dose
pathways with the tritium release
attributable to TPBAR permeability.
These doses were based on an assumed
core load of 2,496 TPBARs and the
methods and assumptions in the current
Watts Bar ODCM. TVA calculated that
the whole-body dose to a Maximally
Exposed Individual from a single Watts
Bar unit would be 0.60 millirem (mrem)
(0.0060 millisievert (mSv)), which is
much less than the whole-body dose
objective in appendix I to 10 CFR part
50 of 5.00 mrem (0.05 mSv). TVA also
calculated that the organ dose (bone) to
the Maximally Exposed Individual from
a single Watts Bar unit would be 11.30
mrem (0.113 mSv), which is less than
the organ dose objective in appendix I
to 10 CFR part 50 of 15.00 mrem (0.15
mSv).
Based on this information, TVA’s
analyses demonstrate that Watts Bar,
Units 1 and 2, can be operated with the
proposed maximum core loading of
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2,496 TPBARs such that the current
GWMS can maintain the gaseous
effluents within the Effluent
Concentration Limits listed in 10 CFR
part 20, appendix B, to meet the dose
limit requirements to members of the
public in 10 CFR 20.1301, as well as to
maintain doses to the public ALARA as
per the dose objectives set forth in
appendix I to 10 CFR part 50. Therefore,
there would be no significant
radiological effect on the quality of the
human environment from gaseous
effluents.
Radioactive Liquid Effluents
The Watts Bar units’ liquid
radioactive waste system (LRWS) is
used to collect and process radioactive
liquid wastes to reduce radioactivity
and chemical concentrations to levels
acceptable for discharge to the
environment. The LRWS maintains
sufficient processing capability so that
liquid waste may be discharged to the
environment below the regulatory limits
of 10 CFR 20.1301 and consistent with
the ALARA dose objectives in appendix
I to 10 CFR part 50. The Watts Bar units
share three large storage tanks in the
LRWS, which includes a tritiated water
storage tank with a capacity of 500,000
gallons. This storage tank supports
managing large volume/high tritium
concentrations in the RCS for both
units. These storage tanks can be used
for liquid effluent holdup, dilution, and
timing of releases to ensure that
regulatory requirements are met. The
release of radioactive liquids from the
LRWS only occurs after laboratory
analysis of the storage tank contents. If
the activity is found to be above ODCM
limits, the liquid waste streams are
returned to the system for further
processing by a mobile demineralizer. If
the activity is found to be below the
ODCM limits, the liquid waste stream is
pumped to a discharge pipe where it is
monitored for radiation levels and
flowrate before it enters the cooling
tower blowdown line, where it can
ultimately be discharged by permit into
the Tennessee River.
To determine whether the liquid
effluents from an assumed core load of
2,496 TPBARs would be within the
requirements of 10 CFR 20.1301, TVA
calculated the sum of the ratios of each
isotope concentration (C) to its
corresponding liquid Effluent
Concentration Limit (ECL, as listed in
10 CFR part 20, appendix B, table 2,
column 2). Consistent with the
requirements of 10 CFR 20.1302(b)(2)(i),
a C/ECL sum of less than 1.0 indicates
that the annual average effluent release
is within the limits of 10 CFR 20.1301.
Tables 4.11–3 through 4.11–5 of the
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license amendment request show TVA’s
calculated C/ECL sums for liquid
effluent releases from an assumed core
load of 2,496 TPBARs. Table 4.11–3
indicates that extended effluent
releases, without processing the liquid
radioactive waste streams through the
mobile demineralizer or allowing for
sufficient dilution of the radioactive
waste streams, would not meet the
regulatory requirements of 10 CFR
20.1301. The calculated C/ECL for a
single Watts Bar unit in this scenario is
5.28, which is greater than the
maximum allowable C/ECL of 1.0. The
operation of both Watts Bar, Units 1 and
2 in this scenario would yield a C/ECL
of 10.6.
Table 4.11–4 of the license
amendment request demonstrates that
TVA’s calculated C/ECL sum for liquid
effluent releases for a single Watts Bar
unit processed through the mobile
demineralizer would be 0.471. The
operation of both Watts Bar, Units 1 and
2 in this scenario would yield a C/ECL
of 0.942. Table 4.11–5 demonstrates that
TVA’s calculated C/ECL for liquid
effluents not processed through the
mobile demineralizer, but sufficiently
diluted before release, for a single Watts
Bar unit would be 0.476. The operation
of both Watts Bar, Units 1 and 2 in this
scenario would yield a C/ECL of 0.952.
Therefore, the licensee demonstrated
that the C/ECL ratios are less than 1.0
indicating that liquid effluent releases
from an assumed core load of 2,496
TPBARs would be within the limits of
10 CFR part 20.
To determine whether the liquid
effluent releases would be consistent
with the ALARA dose objectives set
forth in appendix I to 10 CFR part 50,
TVA calculated bounding public doses
from the applicable plant effluent dose
pathways with the tritium release
attributable to TPBAR permeability.
These doses were based on an assumed
core load of 2,496 TPBARs and the
methods and assumptions in the current
Watts Bar ODCM. TVA calculated that
the whole-body dose to a Maximally
Exposed Individual from liquid
effluents from a single Watts Bar unit
would be 0.39 mrem (0.0039 mSv),
which is much less than the whole-body
dose objective in appendix I to 10 CFR
part 50 of 3.00 mrem (0.03 mSv). TVA
also calculated that the organ dose
(liver) to the Maximally Exposed
Individual from liquid effluents from a
single Watts Bar unit would be 0.50
mrem (0.0050 mSv), which is much less
than the organ dose objective in
appendix I to 10 CFR part 50 of 10
mrem (0.10 mSv).
Based on this information, TVA’s
analyses demonstrate that by processing
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liquid radioactive waste streams
through the demineralizer or allowing
for proper dilution of the liquid
radioactive waste streams, the current
LRWS can maintain the liquid effluents
within the Effluent Concentration
Limits listed in 10 CFR part 20,
appendix B, such that Watts Bar, Units
1 and 2, can be operated with the
proposed maximum core loading of
2,496 TPBARs. Specifically, doses from
liquid effluents would meet the
requirements regarding members of the
public in 10 CFR 20.1301, as well as
maintain the public ALARA dose
objectives set forth in appendix I to 10
CFR part 50. Therefore, there would be
no significant radiological effect on the
quality of the human environment from
liquid effluents.
Solid Radioactive Wastes
Solid radioactive wastes generated by
nuclear power plant operations at Watts
Bar, Units 1 and 2, are processed,
packaged, and stored onsite until they
are shipped offsite for further processing
or permanent disposal, or both. The
storage areas have restricted access and
shielding to reduce radiation rates to
plant workers. Solid radioactive wastes
are packaged and transported in
compliance with the NRC’s regulations
in 10 CFR parts 20, 61, ‘‘Licensing
Requirements for Land Disposal of
Radioactive Waste,’’ and 71, ‘‘Packaging
and Transportation of Radioactive
Material,’’ and the U.S. Department of
Transportation’s regulations in 49 CFR
parts 170 through 179.
The implementation of the proposed
action of allowing an increase in the
number of TPBARs irradiated from
1,792 to 2,496 per reactor core would
increase the activity and volume of solid
radioactive waste due to the irradiation
of the TPBAR base plates and thimble
plugs, which remain after TPBAR
consolidation activities. As explained in
a previous license amendment request,
for the consolidation process, nuclear
plant operators remove the irradiated
TPBAR assemblies from the spent fuel
assemblies, disassemble all the
irradiated TPBARs for consolidation,
and place them into consolidation
canisters. The operators return the
loaded consolidation canisters to the
spent fuel racks, where they remain
until removed from the site (ADAMS
Accession No. ML17354B282). Offsite
shipment and ultimate disposal would
be conducted in accordance with
agreements between TVA and the DOE.
The disposal volume of the TPBAR base
plates and thimble plugs is estimated to
be 64 cubic feet (2.7 cubic meters) per
year. This additional volume represents
a slight increase in the Watts Bar, Units
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1 and 2, annual estimated solid waste
generation from approximately 32,854
cubic feet (930 cubic meters) per year to
32,918 cubic feet (933 cubic meters) per
year. This projected increase in volume
can be handled by the existing
equipment and plant procedures that
control radioactive solid waste handling
without modification. The licensee
estimated the TPBAR cycle scope of
work to evaluate the doses that are
expected to workers during the TPBAR
consolidation process. The TPBAR cycle
scope, estimated at 1,200 person-hours
per cycle, includes pre-cycle
preparation activities, post-cycle
removal and handling activities, TPBAR
consolidation and shipping activities,
and the processing, packaging, and
shipping of irradiated components. This
work will occur in an estimated 0.33
mrem/hour radiation field. Therefore,
while there would be an increase in
solid radioactive waste associated with
the implementation of the proposed
action, the existing equipment and plant
procedures that control radioactive solid
waste handling would continue to be
used to maintain doses to members of
the public and plant workers within
applicable dose limits. Therefore, based
on this information, there would be no
significant radiological effect on the
quality of the human environment from
solid radioactive waste management.
Spent Fuel Generation, Storage, and
Handling
The number of spent fuel bundles
would increase by approximately four to
eight per cycle with the implementation
of the proposed action. For Watts Bar,
Units 1 and 2, spent fuel is currently
stored in spent fuel pools on site and in
an independent spent fuel storage
installation. There would be adequate
spent fuel storage available on site;
therefore, based on this information,
there would be no significant
radiological effect on the quality of the
human environment from spent fuel
generation, storage, and handling.
Occupational Radiation Doses
At Watts Bar, Units 1 and 2, TVA
maintains a radiation protection
program to monitor radiation levels
throughout the nuclear power plant to
establish appropriate work controls,
training, temporary shielding, and
protective equipment requirements so
that worker doses remain within the
dose limits of 10 CFR part 20, subpart
C, ‘‘Occupational Dose Limits.’’ The
implementation of the proposed action
would affect the quantities of
radioactive material generated during
plant operations since some tritium
permeates through the TPBAR cladding
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Federal Register / Vol. 89, No. 37 / Friday, February 23, 2024 / Notices
and is released into the RCS, as
previously described.
Separate from the environmental
review for this EA, the NRC is reviewing
the technical and safety analyses
provided in TVA’s license amendment
request to ensure that the licensee
continues to meet NRC regulatory
requirements for occupational dose. The
results of this safety review will be
documented in a safety evaluation that
will be made publicly available
following the issuance of the EA. If the
NRC’s safety review determines that the
irradiation of 2,496 TPBARs, per cycle,
in Watts Bar, Units 1 and 2, complies
with the NRC’s regulations for
occupational dose, then the proposed
license amendments would not have a
significant radiological effect on
workers.
Design-Basis Accidents
Design-basis accidents are evaluated
to ensure that Watts Bar, Units 1 and 2,
can withstand the spectrum of
postulated accidents without undue
hazard to public health and safety and
ensure the protection of the
environment.
TVA’s technical and safety analyses
must meet the NRC’s regulatory
requirements for safe operation. The
results of the NRC’s safety review will
be made publicly available following
the issuance of the EA. If this safety
review determines that the irradiation of
2,496 TPBARs, per cycle, in the Watts
Bar, Units 1 and 2, cores comply with
the NRC’s regulations, and there is
reasonable assurance that public health
and safety will not be endangered, then
the proposed license amendments
would not have a significant
radiological effect on the quality of the
human environment from design-basis
accidents.
Radiological Impacts Summary
Based on the radiological evaluations
presented in this EA, except for the
impacts associated with occupational
radiation doses and design-basis
accidents which are being reviewed
separately, the implementation of the
proposed action would not have a
significant radiological effect on the
quality of the human environment. If
the NRC’s safety review determines that
2,496 TPBARs, per cycle, can be safely
irradiated in Watts Bar, Units 1 and 2,
and there is reasonable assurance that
public health and safety will not be
endangered, then implementing the
proposed license amendments would
not have a significant radiological effect
on workers and the quality of the
human environment.
Environmental Impacts of the
Alternatives to the Proposed Action
As an alternative to the proposed
action, the NRC considered denial of the
proposed action (i.e., the ‘‘no-action’’
alternative). Denial of the license
amendment request would mean that
TVA would be allowed to continue
irradiating the current allowable
number of TPBARs (i.e., 1,792) for Watts
Bar, Units 1 and 2. The environmental
impacts of irradiating 1,792 TPBARs
were previously considered and were
determined to not have any significant
radiological or non-radiological effect
on the quality of the human
environment. Therefore, the NRC
concludes that denial of the license
amendment request (i.e., the ‘‘noaction’’ alternative) would result in no
change in current environmental
effe cts, and would be not significant.
The impacts of the ‘‘no-action’’
alternative would be similar to the
impacts of the proposed action.
Alternative Use of Resources
There are no unresolved conflicts
concerning alternative uses of available
resources under the proposed action.
Agencies and Persons Consulted
On November 7, 2023, the NRC staff
consulted with the State of Tennessee,
regarding the environmental impact of
the proposed action. The state official
had no comments on the EA and FONSI.
III. Finding of No Significant Impact
TVA requests that the NRC approve
amendments that would revise the
Watts Bar, Units 1 and 2, TS 4.2.1 and
TS 5.9.6 to increase the maximum
number of TPBARs and to add
supporting methodologies. The
proposed amendments would also
revise the Watts Bar Dual-Unit Updated
Final Safety Analysis Report to modify
the source term for design basis accident
analyses to allow the core fission
product inventory to be calculated using
an updated version of the ORIGEN
computer code. Based on the review of
available information, the NRC
determined that the proposed action
would not have any significant
radiological or non-radiological
environmental impacts. Also, the
impacts of the ‘‘no-action’’ alternative
would be similar to the impacts of the
proposed action. The NRC also
considered the information provided in
the licensee’s application and related
TVA environmental documents.
This FONSI and related
environmental documents are available
for public inspection online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. Persons who do not have
access to ADAMS or who encounter
problems in accessing the documents
located in ADAMS should contact the
NRC’s PDR reference staff by telephone
at 1–800–397–4209 or 301–415–4737, or
by email to PDR.Resource@nrc.gov.
IV. Availability of Documents
The documents identified in the
following table are available to
interested persons through ADAMS, as
indicated.
ADAMS accession No./Federal
Register citation
ddrumheller on DSK120RN23PROD with NOTICES1
Document description
Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN–TS–21–02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedule for Units 1 and 2, dated March 20, 2023.
Watts Bar Nuclear Plant, Unit 1—Issuance of Amendment Regarding Revised Technical Specification 4.2.1 ‘‘Fuel Assemblies’’ to Increase the Maximum Number of Tritium Producing Burnable Absorber Rods (CAC No. MF6050), dated July 29,
2016.
Watts Bar Nuclear Plant, Units 1 and 2—Issuance of Amendment Regarding Revision to Watts Bar Nuclear Plant, Unit 2,
Technical Specification 4.2.1, ‘‘Fuel Assemblies,’’ and Watts Bar Nuclear Plant, Units 1 and 2, Technical Specifications Related to Fuel Storage (EPID L–2017–LLA–0427), dated May 22, 2019.
Watts Bar Nuclear Plant, Unit 1, Environmental Assessment and Finding of No Significant Impact Federal Register notice related to License Amendment Request to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies,’’ dated June 23, 2016.
Watts Bar Nuclear Plant, Units 1 and 2, Environmental Assessment and Finding of No Significant Impact Federal Register
notice related to License Amendment Request to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies,’’ dated February
6, 2019.
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ADAMS accession No./Federal
Register citation
Document description
Watts Bar Nuclear Power Plant, Units 1 and 2, 2022 Annual Radioactive Effluent Release Report, dated April 27, 2023 ..........
Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, ‘‘Fuel Assemblies,’’ and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN–TS–17–028), dated December 20, 2017.
Dated: February 16, 2024.
For the Nuclear Regulatory Commission.
Kimberly J. Green,
Senior Project Manager, Licensing Projects
Branch II–2, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2024–03665 Filed 2–22–24; 8:45 am]
NUCLEAR REGULATORY
COMMISSION
[NRC–2024–0001]
Sunshine Act Meetings
Weeks of February 26,
March 4, 11, 18, 25, and April 1, 2024.
The schedule for Commission meetings
is subject to change on short notice. The
NRC Commission Meeting Schedule can
be found on the internet at: https://
www.nrc.gov/public-involve/publicmeetings/schedule.html.
PLACE: The NRC provides reasonable
accommodation to individuals with
disabilities where appropriate. If you
need a reasonable accommodation to
participate in these public meetings or
need this meeting notice or the
transcript or other information from the
public meetings in another format (e.g.,
braille, large print), please notify Anne
Silk, NRC Disability Program Specialist,
at 301–287–0745, by videophone at
240–428–3217, or by email at
Anne.Silk@nrc.gov. Determinations on
requests for reasonable accommodation
will be made on a case-by-case basis.
STATUS: Public.
Members of the public may request to
receive the information in these notices
electronically. If you would like to be
added to the distribution, please contact
the Nuclear Regulatory Commission,
Office of the Secretary, Washington, DC
20555, at 301–415–1969, or by email at
Betty.Thweatt@nrc.gov or
Samantha.Miklaszewski@nrc.gov.
MATTERS TO BE CONSIDERED:
ddrumheller on DSK120RN23PROD with NOTICES1
TIME AND DATE:
Week of February 26, 2024
There are no meetings scheduled for
the week of February 26, 2024.
Week of March 4, 2024—Tentative
There are no meetings scheduled for
the week of March 4, 2024.
VerDate Sep<11>2014
17:19 Feb 22, 2024
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Week of March 11, 2024—Tentative
There are no meetings scheduled for
the week of March 11, 2024.
Competitive Product List. Documents
are available at www.prc.gov, Docket
Nos. MC2024–193, CP2024–199.
Week of March 18, 2024—Tentative
There are no meetings scheduled for
the week of March 18, 2024.
Sean Robinson,
Attorney, Corporate and Postal Business Law.
Week of March 25, 2024—Tentative
There are no meetings scheduled for
the week of March 25, 2024.
BILLING CODE 7590–01–P
ML23117A100
ML17354B282
[FR Doc. 2024–03658 Filed 2–22–24; 8:45 am]
BILLING CODE 7710–12–P
POSTAL SERVICE
Week of April 1, 2024—Tentative
There are no meetings scheduled for
the week of April 1, 2024.
Product Change—Priority Mail and
USPS Ground Advantage® Negotiated
Service Agreement
CONTACT PERSON FOR MORE INFORMATION:
AGENCY:
For more information or to verify the
status of meetings, contact Wesley Held
at 301–287–3591 or via email at
Wesley.Held@nrc.gov.
The NRC is holding the meetings
under the authority of the Government
in the Sunshine Act, 5 U.S.C. 552b.
Dated: February 21, 2024.
For the Nuclear Regulatory Commission.
Wesley W. Held,
Policy Coordinator, Office of the Secretary.
[FR Doc. 2024–03909 Filed 2–21–24; 4:15 pm]
BILLING CODE 7590–01–P
POSTAL SERVICE
Product Change—Priority Mail and
USPS Ground Advantage® Negotiated
Service Agreement
Postal ServiceTM.
ACTION: Notice.
AGENCY:
The Postal Service gives
notice of filing a request with the Postal
Regulatory Commission to add a
domestic shipping services contract to
the list of Negotiated Service
Agreements in the Mail Classification
Schedule’s Competitive Products List.
DATES: Date of required notice: February
23, 2024.
FOR FURTHER INFORMATION CONTACT:
Sean Robinson, 202–268–8405.
SUPPLEMENTARY INFORMATION: The
United States Postal Service® hereby
gives notice that, pursuant to 39 U.S.C.
3642 and 3632(b)(3), on February 16,
2024, it filed with the Postal Regulatory
Commission a USPS Request to Add
Priority Mail & USPS Ground
Advantage® Contract 191 to
SUMMARY:
PO 00000
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Postal ServiceTM.
ACTION: Notice.
The Postal Service gives
notice of filing a request with the Postal
Regulatory Commission to add a
domestic shipping services contract to
the list of Negotiated Service
Agreements in the Mail Classification
Schedule’s Competitive Products List.
DATES: Date of required notice: February
23, 2024.
FOR FURTHER INFORMATION CONTACT:
Sean Robinson, 202–268–8405.
SUPPLEMENTARY INFORMATION: The
United States Postal Service® hereby
gives notice that, pursuant to 39 U.S.C.
3642 and 3632(b)(3), on February 14,
2024, it filed with the Postal Regulatory
Commission a USPS Request to Add
Priority Mail & USPS Ground
Advantage® Contract 190 to
Competitive Product List. Documents
are available at www.prc.gov, Docket
Nos. MC2024–191, CP2024–197.
SUMMARY:
Sean Robinson,
Attorney, Corporate and Postal Business Law.
[FR Doc. 2024–03657 Filed 2–22–24; 8:45 am]
BILLING CODE 7710–12–P
POSTAL SERVICE
Product Change—Priority Mail and
USPS Ground Advantage® Negotiated
Service Agreement
Postal ServiceTM.
Notice.
AGENCY:
ACTION:
The Postal Service gives
notice of filing a request with the Postal
Regulatory Commission to add a
domestic shipping services contract to
the list of Negotiated Service
SUMMARY:
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[Federal Register Volume 89, Number 37 (Friday, February 23, 2024)]
[Notices]
[Pages 13757-13762]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-03665]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-390 and 50-391; NRC-2024-0035]
Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and
2; Environmental Assessment and Finding of No Significant Impact
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of amendments to Facility Operating License Nos. NPF-90 and
NPF-96, issued on February 7, 1996, and October 22, 2015, respectively,
and held by Tennessee Valley Authority (TVA, the licensee) for the
operation of Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2. The
proposed amendments would revise the Watts Bar, Units 1 and 2,
Technical Specification (TS) 4.2.1, ``Fuel Assemblies,'' and TS 5.9.6,
``Reactor Coolant System (RCS) Pressure and Temperature Limits Report
(PTLR),'' to increase the maximum number of tritium producing burnable
absorber rods (TPBARs) and to add supporting methodologies. The
proposed amendments would also revise the Watts Bar Dual-Unit Updated
Final Safety Analysis Report to modify the source term for design basis
accident analyses. The NRC is issuing an environmental assessment (EA)
and finding of no significant impact (FONSI) associated with the
proposed amendments.
DATES: The EA and FONSI referenced in this document are available on
February 23, 2024.
ADDRESSES: Please refer to Docket ID NRC-2024-0035 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 website: Go to https://www.regulations.gov and search for Docket ID NRC-2024-0035. Address
questions about Docket IDs in Regulations.gov to Stacy Schumann;
telephone: 301-415-0624; email: [email protected]. For technical
[[Page 13758]]
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 ``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, at 301-415-4737,
or by email to [email protected]. 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. In addition, for the
convenience of the reader, the ADAMS accession numbers are provided in
a table in the ``Availability of Documents'' section of this document.
NRC's PDR: The PDR, where you may examine and order copies
of publicly available documents, is open by appointment. To make an
appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between 8
a.m. and 4 p.m. eastern time (ET), Monday through Friday, except
Federal holidays.
FOR FURTHER INFORMATION CONTACT: Kimberly Green, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone: 301-415-1627; email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering issuance of amendments to Facility Operating
License Nos. NPF-90 and NPF-96, issued to TVA, for the operation of
Watts Bar, Units 1 and 2, located in Rhea County, Tennessee. Therefore,
as required by section 51.21, ``Criteria for and identification of
licensing and regulatory actions requiring environmental assessments,''
of title 10 of the Code of Federal Regulations (10 CFR), the NRC
performed an EA that analyzes the environmental impacts of the proposed
licensing action and alternatives as appropriate. Based on the results
of the EA that follows, and in accordance with 10 CFR 51.31(a), the NRC
has determined not to prepare an environmental impact statement for the
proposed licensing action and is issuing a FONSI.
II. Environmental Assessment
Description of the Proposed Action
The proposed action would revise Watts Bar, Units 1 and 2, TS 4.2.1
to increase the limit on the maximum number of TPBARs that can be
irradiated in the reactor core in an operating cycle from 1,792 to
2,496. The proposed action would also revise Watts Bar, Units 1 and 2,
TS 5.9.6 to add supporting methodologies. Additionally, the proposed
action would revise the Watts Bar Dual-Unit Updated Final Safety
Analysis Report to modify the source term for design basis accident
analyses to allow the core fission product inventory to be calculated
using an updated version of the ORIGEN computer code.
The proposed action is in accordance with the licensee's
application dated March 20, 2023 (ADAMS Accession No. ML23079A270).
Need for the Proposed Action
The U.S. Department of Energy (DOE) and TVA are cooperating in a
program to produce tritium for the National Security Stockpile by
irradiating TPBARs in the Watts Bar, Units 1 and 2, reactor cores.
Tritium is produced when the neutrons produced by nuclear fission in
the core are absorbed by the lithium target material of the TPBARs. A
solid zirconium metal cladding covering the TPBARs (called a
``getter'') captures the tritium produced.
This proposed action is needed to support the DOE, National Nuclear
Security Administration, National Security Stockpile, in accordance
with Public Law (Pub. L.) 106-65. Section 3134 of Public Law 106-65
directs the Secretary of Energy to produce new tritium at Watts Bar. By
letters dated July 29, 2016 (ADAMS Accession No. ML16159A057), and May
22, 2019 (ADAMS Accession No. ML18347B330), the NRC approved similar
amendments to irradiate up to 1,792 TPBARs in the Watts Bar reactor
cores. The EA and FONSI for those licensing actions, completed on June
23, 2016, and February 6, 2019, can be found in ADAMS under Accession
Nos. ML16138A045 and ML18332A013, respectively.
Environmental Impacts of the Proposed Action
The NRC staff has assessed the potential environmental impacts from
the proposed increase in the maximum number of TPBARs that can be
irradiated in the Watts Bar reactor cores.
The non-radiological and radiological impacts on the environment
that may result from the proposed action are summarized as follows.
Non-Radiological Impacts
The proposed action involves no new construction or modification of
Watts Bar, Units 1 and 2, operational systems and would have no direct
impact on land and water use or water quality, including terrestrial
and aquatic biota. There would also be no change in the quality or
quantity of non-radiological effluents and no need to modify the
nuclear plant's National Pollutant Discharge Elimination System permit.
The proposed action would have no effect on air pollutant emissions or
ambient air quality. In addition, the proposed action would have no
noticeable effect on socioeconomic and environmental justice conditions
in the region, and no adverse effect on historic and cultural
resources. Therefore, the proposed action would have no significant
non-radiological effect on the quality of the human environment.
Radiological Impacts
All nuclear power plants, including Watts Bar, Units 1 and 2,
release small amounts of radioactive material to the environment as
liquid or gaseous effluents as part of normal operations. The NRC
summarizes U.S. nuclear power plant effluent data on its public website
[https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr2907/]. These effluents are controlled, monitored, and reported
per NRC requirements to ensure that doses to the public are known and
within acceptable guidelines that are as low as is reasonably
achievable (ALARA). The Watts Bar Offsite Dose Calculation Manual
(ODCM), documented in the Watts Bar Nuclear Power Plant 2022, Annual
Radioactive Effluent Release Report (ADAMS Accession No. ML23117A100),
provides the limits and methods used by TVA to ensure compliance with
requirements that apply to radioactive effluents. Watts Bar, Units 1
and 2, use waste treatment systems to collect, process, and recycle
plant fluids that contain radioactive material and to dispose of
gaseous and liquid effluents and solid wastes in a safe and controlled
manner within NRC and U.S. Environmental Protection Agency radiation
safety standards. Implementation of the proposed action would allow up
to 2,496 TPBARs per cycle to be irradiated in the Watts Bar, Units 1
and 2, reactor cores. Increasing the number of TPBARs irradiated from
1,792 to 2,496 per reactor core could increase the quantities of
radioactive material released from Watts Bar to the environment because
some of the
[[Page 13759]]
tritium that is produced permeates through the TPBAR cladding and is
released into the reactor coolant system (RCS) fluid. Radioactive
material in RCS fluid can be released as gaseous or liquid effluent.
For the purposes of assessing the environmental impacts and the
regulatory compliance of this proposed action for tritium production,
TVA assumed a core load of 2,496 TPBARs with a permeation rate of 5.0
curies per TPBAR per year (Ci/TPBAR/year) of tritium and was able to
demonstrate that liquid and gaseous effluents would be within
applicable limits. The assumed permeation rate is conservative in that
it bounds the observed and maximum TPBAR tritium permeation rates at
Watts Bar, Units 1 and 2. Specifically, based on the licensee's
experience with TPBARs dating back to 2004, the licensee has observed a
permeation rate for tritium production of less than 3.5 Ci/TPBAR/year.
Additionally, as provided in this document, the licensee demonstrated
that other changes to the radioisotope inventory that can impact
effluent levels would be minor and would not impact the licensee's
ability to meet applicable limits. Therefore, while the quantity of
tritium generated during plant operations would increase under the
proposed action, radioactive effluents from Watts Bar would remain
within applicable limits.
Radioactive Gaseous Effluents
The Watts Bar units maintain a gaseous waste management system
(GWMS) that is designed to process and control the release of
radioactive gaseous effluents into the environment in accordance with
the requirements of 10 CFR 20.1301, ``Dose limits for individual
members of the public,'' and to ensure consistency with the ALARA dose
objectives set forth in appendix I, ``Numerical Guides for Design
Objectives and Limiting Conditions for Operation to Meet the Criterion
`As Low as is Reasonably Achievable' for Radioactive Material in Light-
Water-Cooled Nuclear Power Reactor Effluents,'' to 10 CFR part 50,
``Domestic Licensing of Production and Utilization Facilities.''
As stated in the license amendment request, TVA assumed a core load
of 2,496 TPBARs with a permeation rate of 5.0 Ci/TPBAR/year of tritium,
which is a conservative source term that bounds the observed and
maximum TPBAR tritium permeation rate as seen from historic Watts Bar,
Units 1 and 2, tritium production.
To determine whether the resultant gaseous effluents would fall
within the requirements of 10 CFR 20.1301, TVA calculated the sum of
the ratios of each isotope concentration (C) to its corresponding
gaseous Effluent Concentration Limit (ECL, as listed in 10 CFR part 20,
``Standards for Protection against Radiation,'' appendix B, ``Annual
Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of
Radionuclides for Occupational Exposure; Effluent Concentrations;
Concentrations for Release to Sewerage,'' table 2, ``Effluent
Concentration,'' column 1). Consistent with the requirements of 10 CFR
20.1302(b)(2)(i), a C/ECL sum of less than 1.0 indicates that the
annual average effluent release is within the limits of 10 CFR 20.1301.
Tables 4.11-6 and 4.11-7 of the license amendment request demonstrate
that TVA's calculated C/ECL sums for gaseous effluent releases at the
Watts Bar units from an assumed core load of 2,496 TPBARs for
containment purge without filtration would be 0.458 (single unit) and
with continuous filtration would be 0.402 (single unit). TVA's
calculated C/ECL sums for gaseous effluent releases for both Watts Bar,
Units 1 and 2 (dual-unit operation) for containment purge without
filtration would be 0.915 and with continuous filtration would be
0.805. Therefore, the licensee demonstrated that the C/ECL ratios are
less than 1.0 indicating that gaseous effluent releases from an assumed
core load of 2,496 TPBARs would be within the limits of 10 CFR part 20.
To determine whether the gaseous effluent releases would be
consistent with the ALARA dose objectives set forth in appendix I to 10
CFR part 50 (which are per-unit numbers), TVA calculated bounding
public doses from the applicable plant effluent dose pathways with the
tritium release attributable to TPBAR permeability. These doses were
based on an assumed core load of 2,496 TPBARs and the methods and
assumptions in the current Watts Bar ODCM. TVA calculated that the
whole-body dose to a Maximally Exposed Individual from a single Watts
Bar unit would be 0.60 millirem (mrem) (0.0060 millisievert (mSv)),
which is much less than the whole-body dose objective in appendix I to
10 CFR part 50 of 5.00 mrem (0.05 mSv). TVA also calculated that the
organ dose (bone) to the Maximally Exposed Individual from a single
Watts Bar unit would be 11.30 mrem (0.113 mSv), which is less than the
organ dose objective in appendix I to 10 CFR part 50 of 15.00 mrem
(0.15 mSv).
Based on this information, TVA's analyses demonstrate that Watts
Bar, Units 1 and 2, can be operated with the proposed maximum core
loading of 2,496 TPBARs such that the current GWMS can maintain the
gaseous effluents within the Effluent Concentration Limits listed in 10
CFR part 20, appendix B, to meet the dose limit requirements to members
of the public in 10 CFR 20.1301, as well as to maintain doses to the
public ALARA as per the dose objectives set forth in appendix I to 10
CFR part 50. Therefore, there would be no significant radiological
effect on the quality of the human environment from gaseous effluents.
Radioactive Liquid Effluents
The Watts Bar units' liquid radioactive waste system (LRWS) is used
to collect and process radioactive liquid wastes to reduce
radioactivity and chemical concentrations to levels acceptable for
discharge to the environment. The LRWS maintains sufficient processing
capability so that liquid waste may be discharged to the environment
below the regulatory limits of 10 CFR 20.1301 and consistent with the
ALARA dose objectives in appendix I to 10 CFR part 50. The Watts Bar
units share three large storage tanks in the LRWS, which includes a
tritiated water storage tank with a capacity of 500,000 gallons. This
storage tank supports managing large volume/high tritium concentrations
in the RCS for both units. These storage tanks can be used for liquid
effluent holdup, dilution, and timing of releases to ensure that
regulatory requirements are met. The release of radioactive liquids
from the LRWS only occurs after laboratory analysis of the storage tank
contents. If the activity is found to be above ODCM limits, the liquid
waste streams are returned to the system for further processing by a
mobile demineralizer. If the activity is found to be below the ODCM
limits, the liquid waste stream is pumped to a discharge pipe where it
is monitored for radiation levels and flowrate before it enters the
cooling tower blowdown line, where it can ultimately be discharged by
permit into the Tennessee River.
To determine whether the liquid effluents from an assumed core load
of 2,496 TPBARs would be within the requirements of 10 CFR 20.1301, TVA
calculated the sum of the ratios of each isotope concentration (C) to
its corresponding liquid Effluent Concentration Limit (ECL, as listed
in 10 CFR part 20, appendix B, table 2, column 2). Consistent with the
requirements of 10 CFR 20.1302(b)(2)(i), a C/ECL sum of less than 1.0
indicates that the annual average effluent release is within the limits
of 10 CFR 20.1301. Tables 4.11-3 through 4.11-5 of the
[[Page 13760]]
license amendment request show TVA's calculated C/ECL sums for liquid
effluent releases from an assumed core load of 2,496 TPBARs. Table
4.11-3 indicates that extended effluent releases, without processing
the liquid radioactive waste streams through the mobile demineralizer
or allowing for sufficient dilution of the radioactive waste streams,
would not meet the regulatory requirements of 10 CFR 20.1301. The
calculated C/ECL for a single Watts Bar unit in this scenario is 5.28,
which is greater than the maximum allowable C/ECL of 1.0. The operation
of both Watts Bar, Units 1 and 2 in this scenario would yield a C/ECL
of 10.6.
Table 4.11-4 of the license amendment request demonstrates that
TVA's calculated C/ECL sum for liquid effluent releases for a single
Watts Bar unit processed through the mobile demineralizer would be
0.471. The operation of both Watts Bar, Units 1 and 2 in this scenario
would yield a C/ECL of 0.942. Table 4.11-5 demonstrates that TVA's
calculated C/ECL for liquid effluents not processed through the mobile
demineralizer, but sufficiently diluted before release, for a single
Watts Bar unit would be 0.476. The operation of both Watts Bar, Units 1
and 2 in this scenario would yield a C/ECL of 0.952. Therefore, the
licensee demonstrated that the C/ECL ratios are less than 1.0
indicating that liquid effluent releases from an assumed core load of
2,496 TPBARs would be within the limits of 10 CFR part 20.
To determine whether the liquid effluent releases would be
consistent with the ALARA dose objectives set forth in appendix I to 10
CFR part 50, TVA calculated bounding public doses from the applicable
plant effluent dose pathways with the tritium release attributable to
TPBAR permeability. These doses were based on an assumed core load of
2,496 TPBARs and the methods and assumptions in the current Watts Bar
ODCM. TVA calculated that the whole-body dose to a Maximally Exposed
Individual from liquid effluents from a single Watts Bar unit would be
0.39 mrem (0.0039 mSv), which is much less than the whole-body dose
objective in appendix I to 10 CFR part 50 of 3.00 mrem (0.03 mSv). TVA
also calculated that the organ dose (liver) to the Maximally Exposed
Individual from liquid effluents from a single Watts Bar unit would be
0.50 mrem (0.0050 mSv), which is much less than the organ dose
objective in appendix I to 10 CFR part 50 of 10 mrem (0.10 mSv).
Based on this information, TVA's analyses demonstrate that by
processing liquid radioactive waste streams through the demineralizer
or allowing for proper dilution of the liquid radioactive waste
streams, the current LRWS can maintain the liquid effluents within the
Effluent Concentration Limits listed in 10 CFR part 20, appendix B,
such that Watts Bar, Units 1 and 2, can be operated with the proposed
maximum core loading of 2,496 TPBARs. Specifically, doses from liquid
effluents would meet the requirements regarding members of the public
in 10 CFR 20.1301, as well as maintain the public ALARA dose objectives
set forth in appendix I to 10 CFR part 50. Therefore, there would be no
significant radiological effect on the quality of the human environment
from liquid effluents.
Solid Radioactive Wastes
Solid radioactive wastes generated by nuclear power plant
operations at Watts Bar, Units 1 and 2, are processed, packaged, and
stored onsite until they are shipped offsite for further processing or
permanent disposal, or both. The storage areas have restricted access
and shielding to reduce radiation rates to plant workers. Solid
radioactive wastes are packaged and transported in compliance with the
NRC's regulations in 10 CFR parts 20, 61, ``Licensing Requirements for
Land Disposal of Radioactive Waste,'' and 71, ``Packaging and
Transportation of Radioactive Material,'' and the U.S. Department of
Transportation's regulations in 49 CFR parts 170 through 179.
The implementation of the proposed action of allowing an increase
in the number of TPBARs irradiated from 1,792 to 2,496 per reactor core
would increase the activity and volume of solid radioactive waste due
to the irradiation of the TPBAR base plates and thimble plugs, which
remain after TPBAR consolidation activities. As explained in a previous
license amendment request, for the consolidation process, nuclear plant
operators remove the irradiated TPBAR assemblies from the spent fuel
assemblies, disassemble all the irradiated TPBARs for consolidation,
and place them into consolidation canisters. The operators return the
loaded consolidation canisters to the spent fuel racks, where they
remain until removed from the site (ADAMS Accession No. ML17354B282).
Offsite shipment and ultimate disposal would be conducted in accordance
with agreements between TVA and the DOE. The disposal volume of the
TPBAR base plates and thimble plugs is estimated to be 64 cubic feet
(2.7 cubic meters) per year. This additional volume represents a slight
increase in the Watts Bar, Units 1 and 2, annual estimated solid waste
generation from approximately 32,854 cubic feet (930 cubic meters) per
year to 32,918 cubic feet (933 cubic meters) per year. This projected
increase in volume can be handled by the existing equipment and plant
procedures that control radioactive solid waste handling without
modification. The licensee estimated the TPBAR cycle scope of work to
evaluate the doses that are expected to workers during the TPBAR
consolidation process. The TPBAR cycle scope, estimated at 1,200
person-hours per cycle, includes pre-cycle preparation activities,
post-cycle removal and handling activities, TPBAR consolidation and
shipping activities, and the processing, packaging, and shipping of
irradiated components. This work will occur in an estimated 0.33 mrem/
hour radiation field. Therefore, while there would be an increase in
solid radioactive waste associated with the implementation of the
proposed action, the existing equipment and plant procedures that
control radioactive solid waste handling would continue to be used to
maintain doses to members of the public and plant workers within
applicable dose limits. Therefore, based on this information, there
would be no significant radiological effect on the quality of the human
environment from solid radioactive waste management.
Spent Fuel Generation, Storage, and Handling
The number of spent fuel bundles would increase by approximately
four to eight per cycle with the implementation of the proposed action.
For Watts Bar, Units 1 and 2, spent fuel is currently stored in spent
fuel pools on site and in an independent spent fuel storage
installation. There would be adequate spent fuel storage available on
site; therefore, based on this information, there would be no
significant radiological effect on the quality of the human environment
from spent fuel generation, storage, and handling.
Occupational Radiation Doses
At Watts Bar, Units 1 and 2, TVA maintains a radiation protection
program to monitor radiation levels throughout the nuclear power plant
to establish appropriate work controls, training, temporary shielding,
and protective equipment requirements so that worker doses remain
within the dose limits of 10 CFR part 20, subpart C, ``Occupational
Dose Limits.'' The implementation of the proposed action would affect
the quantities of radioactive material generated during plant
operations since some tritium permeates through the TPBAR cladding
[[Page 13761]]
and is released into the RCS, as previously described.
Separate from the environmental review for this EA, the NRC is
reviewing the technical and safety analyses provided in TVA's license
amendment request to ensure that the licensee continues to meet NRC
regulatory requirements for occupational dose. The results of this
safety review will be documented in a safety evaluation that will be
made publicly available following the issuance of the EA. If the NRC's
safety review determines that the irradiation of 2,496 TPBARs, per
cycle, in Watts Bar, Units 1 and 2, complies with the NRC's regulations
for occupational dose, then the proposed license amendments would not
have a significant radiological effect on workers.
Design-Basis Accidents
Design-basis accidents are evaluated to ensure that Watts Bar,
Units 1 and 2, can withstand the spectrum of postulated accidents
without undue hazard to public health and safety and ensure the
protection of the environment.
TVA's technical and safety analyses must meet the NRC's regulatory
requirements for safe operation. The results of the NRC's safety review
will be made publicly available following the issuance of the EA. If
this safety review determines that the irradiation of 2,496 TPBARs, per
cycle, in the Watts Bar, Units 1 and 2, cores comply with the NRC's
regulations, and there is reasonable assurance that public health and
safety will not be endangered, then the proposed license amendments
would not have a significant radiological effect on the quality of the
human environment from design-basis accidents.
Radiological Impacts Summary
Based on the radiological evaluations presented in this EA, except
for the impacts associated with occupational radiation doses and
design-basis accidents which are being reviewed separately, the
implementation of the proposed action would not have a significant
radiological effect on the quality of the human environment. If the
NRC's safety review determines that 2,496 TPBARs, per cycle, can be
safely irradiated in Watts Bar, Units 1 and 2, and there is reasonable
assurance that public health and safety will not be endangered, then
implementing the proposed license amendments would not have a
significant radiological effect on workers and the quality of the human
environment.
Environmental Impacts of the Alternatives to the Proposed Action
As an alternative to the proposed action, the NRC considered denial
of the proposed action (i.e., the ``no-action'' alternative). Denial of
the license amendment request would mean that TVA would be allowed to
continue irradiating the current allowable number of TPBARs (i.e.,
1,792) for Watts Bar, Units 1 and 2. The environmental impacts of
irradiating 1,792 TPBARs were previously considered and were determined
to not have any significant radiological or non-radiological effect on
the quality of the human environment. Therefore, the NRC concludes that
denial of the license amendment request (i.e., the ``no-action''
alternative) would result in no change in current environmental effe
cts, and would be not significant. The impacts of the ``no-action''
alternative would be similar to the impacts of the proposed action.
Alternative Use of Resources
There are no unresolved conflicts concerning alternative uses of
available resources under the proposed action.
Agencies and Persons Consulted
On November 7, 2023, the NRC staff consulted with the State of
Tennessee, regarding the environmental impact of the proposed action.
The state official had no comments on the EA and FONSI.
III. Finding of No Significant Impact
TVA requests that the NRC approve amendments that would revise the
Watts Bar, Units 1 and 2, TS 4.2.1 and TS 5.9.6 to increase the maximum
number of TPBARs and to add supporting methodologies. The proposed
amendments would also revise the Watts Bar Dual-Unit Updated Final
Safety Analysis Report to modify the source term for design basis
accident analyses to allow the core fission product inventory to be
calculated using an updated version of the ORIGEN computer code. Based
on the review of available information, the NRC determined that the
proposed action would not have any significant radiological or non-
radiological environmental impacts. Also, the impacts of the ``no-
action'' alternative would be similar to the impacts of the proposed
action. The NRC also considered the information provided in the
licensee's application and related TVA environmental documents.
This FONSI and related environmental documents are available for
public inspection online in the ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/adams.html. Persons who do not have
access to ADAMS or who encounter problems in accessing the documents
located in ADAMS should contact the NRC's PDR reference staff by
telephone at 1-800-397-4209 or 301-415-4737, or by email to
[email protected].
IV. Availability of Documents
The documents identified in the following table are available to
interested persons through ADAMS, as indicated.
------------------------------------------------------------------------
ADAMS accession No./Federal
Document description Register citation
------------------------------------------------------------------------
Application to Revise Watts Bar Nuclear ML23079A270
Plant Units 1 and 2 Technical
Specifications to Change the Number of
Tritium Producing Burnable Absorber
Rods (WBN-TS-21-02) and Proposed
Revision to Reactor Vessel Surveillance
Capsule Removal Schedule for Units 1
and 2, dated March 20, 2023.
Watts Bar Nuclear Plant, Unit 1-- ML16159A057
Issuance of Amendment Regarding Revised
Technical Specification 4.2.1 ``Fuel
Assemblies'' to Increase the Maximum
Number of Tritium Producing Burnable
Absorber Rods (CAC No. MF6050), dated
July 29, 2016.
Watts Bar Nuclear Plant, Units 1 and 2-- ML18347B330
Issuance of Amendment Regarding
Revision to Watts Bar Nuclear Plant,
Unit 2, Technical Specification 4.2.1,
``Fuel Assemblies,'' and Watts Bar
Nuclear Plant, Units 1 and 2, Technical
Specifications Related to Fuel Storage
(EPID L-2017-LLA-0427), dated May 22,
2019.
Watts Bar Nuclear Plant, Unit 1, ML16138A045
Environmental Assessment and Finding of 81 FR 43656
No Significant Impact Federal Register
notice related to License Amendment
Request to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies,'' dated June 23, 2016.
Watts Bar Nuclear Plant, Units 1 and 2, ML18332A013
Environmental Assessment and Finding of 84 FR 3259
No Significant Impact Federal Register
notice related to License Amendment
Request to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies,'' dated February 6, 2019.
[[Page 13762]]
Watts Bar Nuclear Power Plant, Units 1 ML23117A100
and 2, 2022 Annual Radioactive Effluent
Release Report, dated April 27, 2023.
Application to Revise Watts Bar Unit 2 ML17354B282
Technical Specification 4.2.1, ``Fuel
Assemblies,'' and Watts Bar Units 1 and
2 Technical Specifications Related to
Fuel Storage (WBN-TS-17-028), dated
December 20, 2017.
------------------------------------------------------------------------
Dated: February 16, 2024.
For the Nuclear Regulatory Commission.
Kimberly J. Green,
Senior Project Manager, Licensing Projects Branch II-2, Division of
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2024-03665 Filed 2-22-24; 8:45 am]
BILLING CODE 7590-01-P
