[Federal Register Volume 84, Number 28 (Monday, February 11, 2019)]
[Notices]
[Pages 3259-3263]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-01859]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-390 and 50-391; NRC-2019-0046]
Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and
2
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental assessment and finding of no significant impact;
issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of amendments to licenses held by Tennessee Valley Authority
(TVA, the licensee) for the operation of Watts Bar Nuclear Power Plant
(WBN), Units 1 and 2. The proposed amendments would revise the WBN,
Unit 2 Technical Specification (TS) 4.2.1, Fuel Assemblies, to add a
limit on the number of tritium producing burnable absorber rods
(TPBARs) that can be irradiated. This license amendment request also
provides proposed changes to the WBN, Units 1 and 2 TSs related to the
new criticality analyses performed for the spent fuel storage racks.
The NRC is issuing an environmental assessment (EA) and finding of no
significant impact (FONSI) associated with the proposed license
amendments.
DATES: The EA and FONSI referenced in this document is available on
February 11, 2019.
ADDRESSES: Please refer to Docket ID NRC-2019-0046 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 http://www.regulations.gov and search for Docket ID NRC-2019-0046. Address
questions about NRC Docket IDs in Regulations.gov to Krupskaya
Castellon; telephone: 301-287-9221; email: [email protected].
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 http://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, 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: 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: John G. Lamb, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-3100; email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering issuance of amendments to Facility Operating
License Nos. NFP-90 and NFP-96, issued to TVA for operation of the WBN,
Units 1 and 2, located in Rhea County, Tennessee.
In accordance with section 51.21 of title 10 of the Code of Federal
Regulations (10 CFR), the NRC prepared the following EA that analyzes
the environmental impacts of the proposed licensing action. Based on
the results of this EA, 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 the WBN, Unit 2 TS 4.2.1, Fuel
Assemblies to allow up to 1,792 TPBARs to be irradiated in the reactor
core. The proposed action would also revise the WBN, Units 1 and 2 TS
3.7.15, Spent Fuel Assembly Storage, to simplify the fuel storage
limitations on fuel assemblies by eliminating the burnup-related
criteria; TS 3.9.9, Spent Fuel Pool Boron Concentration, to modify the
minimum fuel storage pool boron concentration during refueling
operations when fuel is stored in the pool; and TS 4.3, Fuel Storage,
to replace the storage limitations on fuel assembly burnup and storage
with a single requirement to maintain a specified boron concentration
in the spent fuel pool. The proposed action would also add the WBN,
Units 1 and 2 TS 3.7.18, Fuel Storage Pool Boron Concentration, to
specify the minimum fuel storage pool boron concentration when fuel is
stored in the pool, and TS 5.7.2.21, Spent Fuel Storage Rack Neutron
Absorber Monitoring Program, to monitor the condition of the neutron
absorber material used in the spent fuel pool storage racks to ensure
it will continue to perform its assumed design functions.
The proposed action is also described in the licensee's application
dated December 20, 2017 (ADAMS Accession No. ML17354B282), as
supplemented by letters dated February 15, 2018 (ADAMS Accession No.
ML18047A181), April 9, 2018 (ADAMS Accession No. ML18100A953) and
October 4, 2018 (ADAMS Accession No. ML18283A107).
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 at the WBN site. Tritium is produced when the
neutrons produced by nuclear fission in the core are absorbed by the
lithium target material of the TPBAR. A solid zirconium metal cladding
covering the TPBAR (called a getter) captures the tritium produced.
Most of the tritium is contained within the TPBAR, however, some
tritium permeates through the TPBAR cladding and is released into the
reactor coolant system.
This proposed action is needed to support the DOE, National Nuclear
Security Administration, national security stockpile needs in
accordance
[[Page 3260]]
with Public Law (Pub. L.) 106-65. Section 3134 of Public Law 106-65
directs the Secretary of Energy to produce new tritium at TVA's WBN
site. By letter dated June 23, 2016 (ADAMS Accession No. ML18283A107),
the NRC approved a similar amendment to irradiate 1,792 TPBARs in the
WBN, Unit 1 reactor core. The EA and FONSI for that licensing action
was completed June 23, 2016, and can be found in ADAMS (Accession No.
ML16138A045).
Environmental Impacts of the Proposed Action
The proposed action consists of revising the WBN, Unit 2 TSs to
allow and limit the number of TPBARs that can be irradiated in the
reactor core. This license amendment request also provides proposed
changes for both the WBN, Units 1 and 2 TSs related to the new
criticality analyses performed for the spent fuel storage racks to
allow the proper safe handling and storage of spent fuel, including
TPBARs, at the WBN site.
The radiological and nonradiological impacts on the environment
that may result from the proposed action are summarized below.
Non-Radiological Impacts
The proposed changes would have no direct impacts on land use or
water resources, including terrestrial and aquatic biota, as they
involve no new construction or modification of plant operational
systems. There would be no changes to the quality or quantity of
nonradiological effluents and no need to change the plant's National
Pollutant Discharge Elimination System permit. There would be no
changes in air pollutant emissions or ambient air quality from the
proposed changes. In addition, there would be no noticeable effect on
socioeconomic conditions in the region, no environment justice impacts,
and no impacts to historic and cultural resources from the proposed TS
changes. Therefore, there are no significant nonradiological
environmental impacts associated with the proposed action.
Radiological Impacts
Radioactive Gaseous and Liquid Effluents and Solid Waste
The WBN, Units 1 and 2, utilize waste treatment systems to collect,
process, recycle, and dispose of gaseous and liquid effluents and solid
wastes that contain radioactive material in a safe and controlled
manner within NRC and U.S. Environmental Protection Agency's radiation
safety standards. Implementation of the proposed action would result in
allowing the WBN, Unit 2, to irradiate up to 1,792 TPBARs, per cycle in
the reactor core. This is the same number of TPBARs authorized by the
NRC for the WBN, Unit 1 reactor core. This would also affect the
quantities of radioactive material generated from WBN, Unit 2 as some
tritium permeates through the TPBAR cladding and is released into the
reactor coolant system. The average observed TPBAR tritium permeation
rate for the WBN, Unit 1 tritium production is approximately 3 Curi per
TPBAR per year (Ci/TPBAR/year), with the maximum observed permeation
rate being approximately 4.8 Ci/TPBAR/year. For the purposes of
assessing the environmental impacts and regulatory compliance of this
proposed action for the WBN, Unit 2 tritium production, TVA assumed a
core load of 1,792 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. While the quantity
of tritium generated during plant operations will increase under the
proposed action, current radioactive waste treatment systems will be
able to handle that increase according to TVA.
Radioactive Gaseous Effluents
The WBN, Unit 2, maintains 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 as low as reasonably
achievable (ALARA) dose objectives set forth in appendix I to 10 CFR
part 50.
As stated above relative to TVA's license amendment request, TVA
assumed a core load of 1,792 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 the
WBN, Unit 1 tritium production.
To determine whether the 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, appendix B,
Table 2, 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 4.1-31 and 32 of the license amendment request demonstrate that
TVA's calculated C/ECL sums for gaseous effluent releases at the WBN,
Unit 2 from an assumed core load of 1,792 TPBARs for containment purge
without filtration would be 4.52x10-1 and would be
4.01x10-1 with continuous filtration. TVA's calculated C/ECL
sums for gaseous effluent releases for both of the WBN, Units 1 and 2
(dual operation) for containment purge without filtration would be
9.12x10-1 and would be 8.02x10-1 with continuous
filtration. Both sets of numbers are within the maximum C/ECL limit of
1.0 according to TVA.
To determine whether the gaseous effluents are 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 1,792 TPBARs and the methods and assumptions in
the current WBN Offsite Dose Calculation Manual (ODCM), (documented in
the Watts Bar Nuclear Plant 2017, Annual Radioactive Effluent Release
Report (ADAMS Accession No. ML18120A138). TVA calculated that the Whole
Body dose to a Maximally Exposed Individual from the WBN, Unit 2 would
be 0.63 millirem (mrem) (0.0063 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 (Thyroid)
to the Maximally Exposed Individual from the WBN, Unit 2 would be 8.30
mrem (0.083 mSv), which is less than the Organ dose objective in
appendix I to 10 CFR part 50 of 15.00 mrem (0.15 mSv).
Doses would be assumed to double (1.26 mrem or 0.0126 mSv Whole
Body and 16.6 mrem or 0.166 mSv Organ Dose (Thyroid)) for dual reactor
tritium production at both the WBN, Units 1 and 2, which would be
within the appendix I to 10 CFR part 50 dose objective as they are per-
unit numbers as stated above, and would also double according to TVA.
Based on the above, the NRC staff finds that the TVA's analyses
have demonstrated that WBN, Unit 2, can be operated with the proposed
maximum core loading of 1,792 TPBARs and 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
maintain doses to the public ALARA as per the dose objectives set forth
in
[[Page 3261]]
appendix I to 10 CFR part 50. Therefore, the NRC staff concludes that
there would be no significant radiological impact from gaseous
effluents under the proposed action.
Radioactive Liquid Effluents
The WBN, Unit 2 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 according to TVA. 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 WBN, Units 1
and 2 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 reactor coolant system for both Units 1 and 2. These storage
tanks can be used for liquid effluent holdup, dilution, and timing of
releases to ensure that regulatory requirements are met. 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 are 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 4.1-28 through 30 of the license amendment request show TVA's
calculated C/ECL sums for liquid effluent releases from an assumed core
load of 1,792 TPBARs. Table 4.1-28 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 stream, would not meet the regulatory
requirements of 10 CFR 20.1301. The calculated C/ECL for the WBN, Unit
2 in this scenario is 5.23, which is greater than the maximum allowable
C/ECL of 1.0. Dual operation of both the WBN, Units 1 and 2 in this
scenario would yield a C/ECL of 10.5.
To ensure that the effluent concentration limits of 10 CFR 20.1301
are met, Section 11.2.6.5 of the Final Safety Analysis Report states
that ``No untreated wastes are released unless they are below the Lower
Limit of Detection.'' Table 4.1-29 of the license amendment request
demonstrates that TVA's calculated C/ECL sum for liquid effluent
releases for the WBN, Unit 2 processed through the mobile demineralizer
would be 4.18x10-\1\. Dual operation of both the WBN, Units
1 and 2 in this scenario would yield a C/ECL of 8.35x10-\1\.
Table 4.1-30 demonstrates that TVA's calculated C/ECL for liquid
effluents not processed through the mobile demineralizer, but
sufficiently diluted before release, would be 4.23x10-\1\.
Dual operation of both the WBN, Units 1 and 2 in this scenario would
yield a C/ECL of 8.47x10-\1\. All numbers for both scenarios
are within the maximum C/ECL limit of 1.0.
To determine whether the liquid effluents are 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 1,792
TPBARs and the methods and assumptions in the current ODCM. TVA
calculated that the Whole Body dose to a Maximally Exposed Individual
from liquid effluents would be 0.37 mrem (0.0037 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 would
be 0.49 mrem (0.0049 mSv), which is much less than the Organ dose
objective in appendix I to 10 CFR part 50 of 10.00 mrem (0.15 mSv).
Doses would be assumed to double (0.74 mrem or 0.0074 mSv Whole
Body and 0.98 mrem or 0.098 mSv Organ Dose (Liver)) for dual reactor
tritium production at both the WBN, Units 1 and 2, which would be
within the appendix I to 10 CFR part 50 dose objective as they are per-
unit numbers as stated above, and would also double according to TVA.
The NRC staff finds that TVA has demonstrated that WBN, Unit 2, can
be operated with the proposed maximum core loading of 1,792 TPBARs, and
that with processing of the 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. 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, the NRC staff concludes that
there would be no significant radiological impact from gaseous
effluents under the proposed action.
Solid Radioactive Wastes
Solid radioactive wastes generated by nuclear power plant
operations at WBN, Units 1 and 2, are processed, packaged, and stored
until they are shipped offsite to a vendor for further processing or to
a licensed facility for 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 NRC's regulations in 10 CFR parts 61, Licensing
Requirements for Land Disposal of Radioactive Waste, and 71, Packaging
and Transportation of Radioactive Material, and the U.S. Department of
Transportation regulations in 49 CFR parts 170 through 179; and to
maintain the dose limits of 10 CFR 20.1201, 10 CFR 20.1301, and design
objectives in appendix I to 10 CFR part 50.
Implementation of the proposed action 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. For the consolidation process, plant
operators will remove the irradiated TPBAR assemblies from the spent
fuel assemblies, disassemble all the irradiated TPBARs for
consolidation, and place them into consolidation canisters. Operators
will return the loaded consolidation canisters to the spent fuel racks,
where they will remain until removed from the site. Offsite shipment
and ultimate disposal would be conducted in accordance with agreements
between TVA and DOE. The disposal volume of the TPBAR base plates and
thimble plugs is estimated to be 33.3 cubic feet (0.942 cubic meters)
per year. This additional volume represents a slight increase in the
WBN, Units 1 and 2, annual estimated solid
[[Page 3262]]
waste generation from 65,640 cubic feet (1859 cubic meters) per year to
65,706 cubic feet (1861 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
estimated increase in activity inventory attributable to the handling
of the TPBAR base plates and thimble plugs ranges from approximately
3,600 Ci/yr (1.33x10\14\ Bq/yr) to 11,060 Ci/yr (4.09x10\14\ Bq/yr).
While there would be increased activity associated with implementation
of the proposed action, the existing equipment and plant procedures
that control radioactive solid waste handling will continue to be used
to maintain plant personnel exposures within the dose limits of 10 CFR
20.1201, 10 CFR 20.1301, and design objectives in 10 CFR part 50,
appendix I. Based on the above, the NRC staff concludes that there
would be no significant radiological impact from solid radioactive
waste management under the proposed action.
Spent Fuel Generation, Storage, and Handling
The number of spent fuel bundles would increase by approximately
four per cycle with implementation of the proposed action. WBN, Units 1
and 2, currently store spent fuel in spent fuel pools on site and in an
independent spent fuel storage installation. There will be adequate
spent fuel storage available on site, therefore, the NRC staff
concludes that there would be no significant radiological impact from
spent fuel generation and storage under the proposed action.
As stated above in Section II of this document, the proposed action
would also revise the WBN, Units 1 and 2 TS 3.7.15, Spent Fuel Assembly
Storage, to simplify the fuel storage limitations on fuel assemblies by
eliminating the burnup-related criteria; TS 3.9.9, Spent Fuel Pool
Boron Concentration, to modify the minimum fuel storage pool boron
concentration during refueling operations when fuel is stored in the
pool; and TS 4.3, Fuel Storage, to replace the storage limitations on
fuel assembly burnup and storage with a single requirement to maintain
a specified boron concentration in the spent fuel pool. The proposed
action would also add the WBN, Units 1 and 2 TS 3.7.18, Fuel Storage
Pool Boron Concentration, to specify the minimum fuel storage pool
boron concentration when fuel is stored in the pool, and TS 5.7.2.21,
Spent Fuel Storage Rack Neutron Absorber Monitoring Program, to monitor
the condition of the neutron absorber material used in the spent fuel
pool storage racks to ensure it will continue to perform its assumed
design functions. These proposed changes would have no direct
radiological environmental impacts. There would be no change to the
types or amounts of radioactive effluents that may be released and,
therefore, no change in occupational or public radiation exposure from
the proposed changes. No changes would be made to plant buildings or
the site property from these proposed changes. Therefore, there would
be no significant radiological environmental impacts associated with
these TS changes.
Occupational Radiation Doses
At WBN, 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 will remain
within the dose limits of 10 CFR part 20, subpart C, Occupational Dose
Limits. Implementation of the proposed action would affect the
quantities of radioactive material generated during plant operations
since some tritium permeates through the TPBAR cladding and is released
into the reactor coolant system, as previously described.
Separate from the environmental review for this EA, the NRC staff
is evaluating the licensee's technical and safety analyses provided in
TVA's license amendment request to ensure the licensee continues to
meet NRC regulatory requirements for occupational dose. The results of
the NRC staff's safety review and conclusion will be documented in a
safety evaluation that will be made publicly available following
issuance of the EA. If the NRC staff concludes in the safety evaluation
that the requested number of 1,792 TPBARs that can be irradiated, per
cycle, in the WBN, Unit 2 core and the proposed changes related to the
new criticality analyses performed for the spent fuel storage racks
comply with NRC regulations for occupational dose, then granting the
proposed license amendments will not have a significant radiological
impact to workers.
Design-Basis Accidents
Design-basis accidents are evaluated by both TVA and the NRC staff
to ensure that WBN, 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.
The NRC staff is evaluating the licensee's technical and safety
analyses provided in the proposed license amendments to ensure the
licensee continues to meet the NRC regulatory requirements for safe
operation. The results of the NRC staff's safety review and conclusion
will be documented in a safety evaluation that will be made publicly
available following issuance of the EA. If the NRC staff concludes in
the safety evaluation that 1,792 TPBARs irradiated, per cycle, in the
WBN, Unit 2 core and the proposed changes related to the new
criticality analyses performed for the spent fuel storage racks comply
with NRC regulations, and there is reasonable assurance that public
health and safety will not be endangered, then granting the proposed
license amendments will not have a significant environmental impact.
Radiological Impacts Summary
Based on the radiological evaluations presented in this EA, with
the exception of the impacts associated with occupational dose and
design-basis accidents, which the NRC staff are evaluating separately,
implementation of the proposed action would not result in any
significant radiological impacts. If the NRC staff concludes in the
safety evaluation that 1,792 TPBARs irradiated, per cycle, in the WBN,
Unit 2 core and the proposed changes related to the new criticality
analyses performed for the spent fuel storage racks comply with NRC
regulations, and there is reasonable assurance that public health and
safety will not be endangered, then granting the proposed license
amendments will not have a significant radiological impact to workers
or the environment.
Environmental Impacts of the Alternatives to the Proposed Action
As an alternative to the proposed action, the NRC staff considered
denial of the license amendment request (i.e., the no-action
alternative). Denial of the license amendment request would result in
no change in current environmental impacts. Accordingly, the
environmental impacts of the proposed action and the no-action
alternative are similar.
Alternative Use of Resources
There are no unresolved conflicts concerning alternative uses of
available resources under the proposed action.
Agencies and Persons Consulted
An official of the State of the Tennessee was notified about the
environmental assessment and the state official had no comments.
[[Page 3263]]
III. Finding of No Significant Impact
The licensee has requested license amendments pursuant to 10 CFR
50.90, Application for amendment of license, construction permit, or
early site permit, to revise the WBN, Unit 2 TSs to allow up to 1,792
TPBARs to be irradiated in the reactor core. The license amendments
also provide proposed changes for both the WBN, Units 1 and 2 TSs
related to the new criticality analyses performed for the spent fuel
storage racks to allow the proper safe handling and storage of spent
fuel, including TPBARs, at the WBN site. The NRC is considering issuing
the requested amendments. The proposed action would not significantly
affect plant safety, would not have a significant adverse effect on the
probability of an accident occurring, and would not have any
significant radiological or nonradiological impacts. The reason the
environment would not be significantly affected is because while the
proposed changes would result in increased radiological plant effluents
and offsite doses, those numbers would still be within the regulatory
limits as stated in 10 CFR part 20 and design objectives in appendix I
to 10 CFR part 50. This FONSI incorporates by reference the EA in
Section II of this notice. Therefore, the NRC concludes that the
proposed action will not have a significant effect on the quality of
the human environment. Accordingly, the NRC has determined there is no
need to prepare an environmental impact statement for the proposed
action.
Previous considerations regarding the environmental impacts of
operating Watts Bar, Units 1 and 2, in accordance with their operating
licenses, are described in NUREG-0498, Final Environmental Statement
Related to Operation of Watts Bar Nuclear Plant, Units 1 and 2, dated
December 1978, and NUREG-0498, Supplement 1, dated April 1995, and
NUREG-0498, Supplement 2, Final Environmental Statement Related to
Operation of Watts Bar Nuclear Plant, Unit 2, dated May 2013 (ADAMS
Package Accession Nos. ML082540803, ML081430592, and ML13144A092).
This FONSI and other related environmental documents may be
examined, and/or copied for a fee, at the NRC's PDR, located at One
White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
Publicly-available records are also accessible online in the ADAMS
Public Documents collection at http://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.
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Document ADAMS accession No.
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NUREG-0498--Final Environmental Statement ML082540803
Related to Operation of Watts Bar
Nuclear Plant, Units 1 and 2, dated
December 1978.
NUREG-0498--Final Environmental Statement ML081430592
Related to the Operation of Watts Bar
Nuclear Plant, Units 1 and 2, Supplement
1, dated April 1995.
NUREG-0498--Final Environmental Statement ML13144A092
Related to the Operation of Watts Bar
Nuclear Plant, Unit 2, Supplement 2,
dated May 2013.
Watts Bar Nuclear Plant, Unit 1: ML16138A045
Environmental Assessment and Finding of
No Significant Impact Related to License
Amendment Request to Revise Technical
Specification 4.2.1, Fuel Assemblies,
dated June 23, 2016.
TVA letter to NRC, Application to Revise ML17354B282
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.
TVA letter to NRC, Correction to ML18100A953
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 April 9,
2018.
TVA letter to NRC, Response to Request ML18283A107
for Additional Information Regarding
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) (EPID L-2017-LLA-
0427), dated October 4, 2018.
WBN Offsite Dose Calculation Manual, as ML18120A138
documented in the Watts Bar Nuclear
Plant Annual Radioactive Effluent
Release Report--2017, dated April 30,
2018.
------------------------------------------------------------------------
Dated at Rockville, Maryland, this 6th day of February 2019.
For the Nuclear Regulatory Commission.
John G. Lamb,
Senior Project Manager, Special Projects and Process Branch, Division
of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2019-01859 Filed 2-8-19; 8:45 am]
BILLING CODE 7590-01-P