Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1, 43656-43661 [2016-15867]
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Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices
Southern Nuclear Operating Company,
Inc., Docket Nos. 50–424 and 50–425,
Vogtle Electric Generating Plant, Units 1
and 2, Burke County, Georgia
Date of amendment request: July 18,
2014, as supplemented by letters dated
February 27, 2015, and May 2, 2016.
Brief description of amendments: The
amendments revised 22 Technical
Specifications (TSs) by adopting
multiple previously NRC-approved
Technical Specifications Task Force
(TSTF) Travelers. One proposed change
is not included in this license
amendment and will be addressed by
further correspondence. Southern
Nuclear Operating Company, Inc. (SNC)
stated that these TSTF Travelers are
generic changes chosen to increase the
consistency between the Vogtle Electric
Generating Plant TSs, the Improved
Standard Technical Specifications for
Westinghouse plants (NUREG–1431),
and the TSs of the other plants in the
SNC fleet.
Date of issuance: June 9, 2016.
Effective date: As of the date of
issuance and shall be implemented
within 120 days of issuance.
Amendment Nos.: 180 (Unit 1) and
161 (Unit 2). A publicly-available
version is in ADAMS under Accession
No. ML15132A569; documents related
to these amendments are listed in the
Safety Evaluation enclosed with the
amendments.
Facility Operating License Nos. NPF–
68 and NPF–81: Amendments revised
the Facility Operating Licenses and TSs.
Date of initial notice in Federal
Register: March 3, 2015 (80 FR 11480).
The supplemental letters dated February
27, 2015, and May 2, 2016, provided
additional information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the staff’s original
proposal no significant hazards
consideration determination as
published in the Federal Register.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated June 9, 2016.
No significant hazards consideration
comments received: No.
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Southern Nuclear Operating Company,
Docket Nos. 50–348 and 50–364, Joseph
M. Farley Nuclear Plant, Units 1 and 2,
Houston County, Alabama
Date of amendment request: April 13,
2015, as supplemented by letters dated
September 17, 2015, and April 13, 2016.
Brief description of amendments: The
amendments consist of changes to the
Technical Specifications consistent with
the NRC-approved Technical
Specification Task Force Improved
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Standard Technical Specifications
Change Traveler-432, Revision 1,
‘‘Change in Technical Specifications
End States (WCAP–16294),’’ dated
November 29, 2010.
Date of issuance: June 10, 2016.
Effective date: As of its date of
issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 202 (Unit 1) and
198 (Unit 2). A publicly-available
version is in ADAMS under Accession
No. ML15289A227; documents related
to these amendments are listed in the
Safety Evaluation enclosed with the
amendments.
Facility Operating License Nos. NPF–
2 and NPF–8: The amendments revised
the Renewed Facility Operating
Licenses and Technical Specifications.
Date of initial notice in Federal
Register: May 26, 2015 (80 FR 30102).
The supplemental letters dated
September 17, 2015, and April 13, 2016,
provided additional information that
clarified the application, did not expand
the scope of the application as originally
noticed, and did not change the staff’s
original proposed no significant hazards
consideration determination as
published in the Federal Register.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated June 10, 2016.
No significant hazards consideration
comments received: No.
Dated at Rockville, Maryland, this 22nd
day of June 2016.
For the Nuclear Regulatory Commission.
Anne T. Boland,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2016–15659 Filed 7–1–16; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–390; NRC–2016–0131]
Tennessee Valley Authority Watts Bar
Nuclear Plant, Unit 1
Nuclear Regulatory
Commission.
ACTION: Environmental assessment and
finding of no significant impact;
issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is considering the
issuance of an amendment to Facility
Operating License No. NFP–90, issued
February 7, 1996, and held by the
Tennessee Valley Authority (TVA, the
licensee) for the operation of Watts Bar
Nuclear Plant (WBN), Unit 1. The
SUMMARY:
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proposed amendment would revise
Technical Specification (TS) 4.2.1,
‘‘Fuel Assemblies’’; TS 3.5.1
‘‘Accumulators’’; Surveillance
Requirement (SR) 3.5.1.4; TS 3.5.4,
‘‘Refueling Water Storage Tank’’; and SR
3.5.4.3, to increase the maximum
number of tritium producing burnable
absorber rods (TPBARs) and to delete
outdated information related to the
tritium production program. The NRC
staff is issuing an environmental
assessment (EA) and finding of no
significant impact (FONSI) associated
with the proposed license amendment.
The Environmental assessment
referenced in this document is available
on July 5, 2016.
DATES:
Please refer to Docket ID
NRC–2016–0131 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly-available
information related to this document
using any of the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0131. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. 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.
ADDRESSES:
FOR FURTHER INFORMATION CONTACT:
Robert Schaaf, Office of Nuclear Reactor
Regulation, Nuclear Regulatory
Commission, Washington, DC 20555–
0001; telephone: 301–415–6020, email:
Robert.Schaaf@nrc.gov.
SUPPLEMENTARY INFORMATION:
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Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices
I. Introduction
The NRC is considering issuance of an
amendment to Facility Operating
License No. NFP–90, issued to TVA for
operation of the WBN, Unit 1, located in
Rhea County, Tennessee. The proposed
action would allow TVA to make
changes to the TSs to increase the
maximum number of TPBARs that can
be irradiated, per cycle, in the WBN,
Unit 1 core from 704 to 1,792. In
accordance with National
Environmental Policy Act of 1969, as
amended (42 U.S.C. 4321 et seq.) and
section 51.21 of title 10 of the Code of
Federal Regulations (10 CFR), the NRC
performed an EA. Based on the
following EA, the NRC has concluded
that the proposed actions will have no
significant environmental impact, and is
issuing a FONSI.
The U.S. Department of Energy (DOE)
and TVA will cooperate in a program to
produce tritium for the National
Security Stockpile by irradiating
TPBARs in the WBN, Unit 1 reactor
core. 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.
By letter dated September 23, 2002,
the NRC approved Amendment No. 40
to Facility Operating License No. NPF–
90 for WBN, Unit 1. The amendment
allowed TVA to irradiate up to 2,304
TPBARs in the WBN, Unit 1 reactor core
each fuel cycle. This approval was
based, in part, on NRC’s approval of
DOE topical report ‘‘Tritium Production
Core Topical Report,’’ NPD–98–181,
dated July 30, 1998, revised February
10, 1999, which assumed that an
average of 1 Curie (Ci) per year of
tritium would be released from each
TPBAR into the reactor coolant, thereby
establishing a design basis source term
for impact evaluation of 2,304 Ci/year
attributable to TPBARs.
Because of issues related to the
reactor coolant boron concentration, and
a higher than expected permeability of
tritium from the TPBARs, the TVA
requested, and the NRC approved,
Amendment 48 to the WBN, Unit 1
operating license, issued October 8,
2003. Amendment 48 limited the
number of TPBARs to be irradiated in
WBN, Unit 1, fuel cycle number 6 to 240
TPBARs. Subsequently, a series of
amendments limiting the number of
TPBARs allowed to be loaded into the
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WBN, Unit 1, reactor core were
reviewed and approved by the NRC.
Currently, Amendment 77, issued May
4, 2009, limits the maximum loading of
the WBN, Unit 1 reactor core to 704
TPBARs. This limit reflects the average
tritium permeation of approximately
3.27 Ci/TPBAR/year experienced during
TPBAR operations in fuel cycles 6
through 8, which limits the number of
TPBARs that could be loaded without
exceeding the original design basis
source term of 2,304 Ci/year attributable
to TPBARs.
The current request to allow core
loadings up to 1,792 TPBARs will
support TVA’s ability to meet the DOE
agreement and national security
stockpile needs.
II. Environmental Assessment
Description of the Proposed Action
The proposed action would revise TS
4.2.1, ‘‘Fuel Assemblies’’; TS 3.5.1
‘‘Accumulators’’; SR 3.5.1.4; TS 3.5.4,
‘‘Refueling Water Storage Tank’’; and SR
3.5.4.3, to increase the maximum
number of TPBARs and to delete
outdated information related to the
tritium production program.
The proposed action is in accordance
with the licensee’s application dated
March 31, 2015, as supplemented by
letters dated April 28, May 27, June 15,
September 14, September 25, November
30, December 22, December 29, 2015,
February 22, and March 31, 2016.
Need for the Proposed Action
The proposed action would allow
WBN, Unit 1, to support the DOE,
National Nuclear Security
Administration, national security
stockpile needs in accordance with
Public Law (PL) 106–65. Section 3134 of
PL 106–65 directs the Secretary of
Energy to produce new tritium at TVA’s
Watts Bar power plant.
Environmental Impacts of the Proposed
Action
The radiological and non-radiological
impacts on the environment that may
result from the proposed action are
summarized below.
Non-Radiological Impacts
The proposed action would not
change the types and amounts of any
non-radiological liquid or gaseous
effluents that may be released offsite.
There would also be no physical
changes to any structures or land use
within the WBN site, and the proposed
action would not impact air quality,
water resources, or aquatic resources. In
addition, the proposed action would not
result in any socioeconomic or
environmental justice impacts or
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impacts to historic and cultural
resources.
Therefore, there would be no
significant non-radiological
environmental impacts to any resource
or any irreversible and irretrievable
commitments of resources.
Radiological Impacts
Radioactive Gaseous and Liquid
Effluents and Solid Waste
The WBN, Unit 1, includes waste
treatment systems to collect, process,
recycle, and dispose of gaseous, liquid,
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 an increase in the
maximum number of TPBARs that can
be irradiated, per cycle, in the WBN,
Unit 1 core, from 704 to 1,792. This
would affect the quantities of
radioactive material generated during
plant operations as some tritium
permeates through the TPBAR cladding
and is released into the reactor coolant
system. The historical average observed
TPBAR tritium permeation rate through
cycle 12 is 3.4 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 its license amendment
request, TVA assumed a core load of
1,900 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, TVA has stated that
the current radioactive waste treatment
systems will be able to handle that
increase.
Radioactive Gaseous Effluents
The WBN, Unit 1, 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 is
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 1,900 TPBARs
with a permeation rate of 5.0 Ci/TPBAR/
year of tritium, which is a conservative
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source term that bounds the observed
and maximum TPBAR tritium
permeation rate. For its analysis of
radioactive gaseous effluents, TVA
assumed that 10 percent of the tritium
is released as gaseous effluent.
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 8 and 9 of the license
amendment request demonstrate that
TVA’s calculated C/ECL sums for
gaseous effluent releases from an
assumed core load of 1,900 TPBARs for
containment purge without filtration
would be 3.15 × 10¥1 and would be 2.73
× 10¥1 with continuous filtration. Both
numbers are within the maximum C/
ECL limit of 1.0.
To determine whether the gaseous
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 1,900
TPBARs and the methods and
assumptions in the current WBN Offsite
Dose Calculation Manual (ODCM),
(documented in the ‘‘Watts Bar Nuclear
Plant Unit 1, Annual Radioactive
Effluent Release Report—2014’’). TVA
calculated that the Whole Body dose to
a Maximally Exposed Individual would
be 0.55 millirem (mrem) (0.0055
millisievert (mSv)), which is much less
than the Whole Body dose criterion 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 would
be 10.6 mrem (0.106 mSv), which is less
than the Organ dose criterion in
Appendix I to 10 CFR part 50 of 15.00
mrem (0.15 mSv).
The NRC staff finds that the TVA’s
analyses have demonstrated that WBN,
Unit 1, 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
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dose objectives set forth in appendix I
to 10 CFR part 50. Therefore, the NRC
staff concludes that there would not be
a significant radiological impact from
gaseous effluents under the proposed
action.
Radioactive Liquid Effluents
The WBN, Unit 1 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 WBN, Unit 1 has three large
tanks in the LRWS, which includes a
Tritiated Water Storage Tank with a
capacity of 500,000 gallons. This tank
supports managing large volume/high
tritium concentrations in the reactor
coolant system. These 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 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 be ultimately discharged into the
Tennessee River.
As previously described, TVA
assumed a core load of 1,900 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. For its analysis of
radioactive liquid effluents, TVA
assumed that 90 percent of the tritium
is released as liquid effluent.
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 5
through 7 of the license amendment
request supplement dated March 31,
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2016, show TVA’s calculated C/ECL
sums for liquid effluent releases from an
assumed core load of 1,900 TPBARs.
Table 5 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 is 3.37,
which is greater than the maximum
allowable C/ECL of 1.0. To ensure that
the effluent concentration limits of 10
CFR 20.1301 are met, TVA has revised
Section 11.2.6.5 of the Final Safety
Analysis Report to include the
statement that ‘‘No untreated wastes are
released unless they are below the
Lower Limit of Detection.’’ Table 6 of
the license amendment request
demonstrates that TVA’s calculated C/
ECL sum for liquid effluent releases
processed through the mobile
demineralizer would be 5.7 × 10¥1.
Table 7 demonstrates that TVA’s
calculated C/ECL for liquid effluents not
processed through the mobile
demineralizer, but sufficiently diluted
before release, would be 5.8 × 10¥1.
Both numbers 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 1,900
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 0.43 mrem
(0.0043 mSv), which is much less than
the Whole Body dose criterion 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 0.57 mrem
(0.0057 mSv), which is less than the
Organ dose criterion in appendix I to 10
CFR part 50 of 10.00 mrem (0.15 mSv).
The NRC staff finds that the TVA
analyses have demonstrated that WBN,
Unit 1, can be operated with the
proposed 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
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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 not be a
significant radiological impact from
gaseous effluents under the proposed
action.
Solid Radioactive Wastes
Solid radioactive wastes generated by
nuclear power plant operations at WBN,
Unit 1, 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
appendix I to 10 CFR part 50.
Implementation of the proposed
action would be expected to 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. TVA will
consolidate and temporarily store these
items on-site, and 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
per year. This additional volume
represents a slight increase in the WBN,
Unit 1, annual estimated solid waste
generation from 32,820 cubic feet per
year to 32,853 cubic feet 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 1,800 Ci/yr
to 5,530 Ci/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 exposures to plant
personnel within the dose limits of 10
CFR 20.1201, 10 CFR 20.1301, and 10
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CFR part 50, appendix I. Based on the
above, the NRC staff concludes that
there would not be a significant
radiological impact from solid
radioactive waste management under
the proposed action.
Spent Fuel Generation and Storage
The number of spent fuel bundles
would be expected to increase by
approximately four per cycle with
implementation of the proposed action.
WBN, Unit 1, currently stores spent fuel
in spent fuel pools on site, and under 10
CFR 72.210, TVA holds a general
license authorizing the operation of an
independent spent fuel storage
installation (ISFSI) at the Watts Bar site.
TVA has notified NRC of its intent to
construct an ISFSI under the general
license. There will be adequate spent
fuel storage available on-site, therefore,
the NRC staff concludes that there
would not be a significant radiological
impact from spent fuel generation and
storage under the proposed action.
Occupational Radiation Doses
At WBN, Unit 1, 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
increase in the maximum number of
TPBARs that can be irradiated, per
cycle, in the WBN, Unit 1, core from 704
to 1,792 continues to comply with NRC
regulations for occupational dose, then
granting the proposed license
amendment will not have a significant
radiological impact to workers.
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Design-Basis Accidents
Design-basis accidents are evaluated
by both TVA and the NRC staff to
ensure that WBN, Unit 1, can withstand
the spectrum of postulated accidents
without undue hazard to public health
and safety and ensure the protection of
the environment.
Separate from the environmental
review for this EA, the NRC staff is
evaluating the licensee’s technical and
safety analyses provided in the
proposed license amendment 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 the requested increase in the
maximum number of TPBARs that can
be irradiated, per cycle, in the WBN,
Unit 1, core continues to comply with
NRC regulations, and there is reasonable
assurance that public health and safety
will not be endangered, then granting
the proposed license amendment will
not have a significant environmental
impact.
Radiological Impacts Summary
Based on the radiological evaluations
associated with 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 its safety
evaluation that the requested increase in
the maximum number of TPBARs that
can be irradiated, per cycle, in the WBN,
Unit 1, core continues to comply with
the NRC’s regulations, and there is
reasonable assurance that public health
and safety will not be endangered, then
granting the proposed license
amendment 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 proposed action (i.e., the ‘‘noaction’’ alternative). Denial of the
license amendment request would result
in no change in current environmental
impacts.
Alternative Use of Resources
This action does not involve the use
of any different resources not previously
considered in NUREG–0498, ‘‘Final
Environmental Statement Related to
E:\FR\FM\05JYN1.SGM
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Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices
Operation of Watts Bar Nuclear Plant,
Units 1 and 2,’’ and NUREG–0498,
Supplement 1.
Agencies and Persons Consulted
In accordance with its stated policy,
on May 13, 2016, the staff consulted
with the State of Tennessee official,
regarding the environmental impact of
the proposed action. The state official
concurred with the EA and finding of no
significant impact.
III. Finding of No Significant Impact
The NRC is considering the issuance
of an amendment to Facility Operating
License No. NFP–90, issued February 7,
1996, and held by TVA for the operation
of WBN, Unit 1. The proposed
amendment would revise TS 4.2.1,
‘‘Fuel Assemblies’’; TS 3.5.1
‘‘Accumulators’’; SR 3.5.1.4; TS 3.5.4,
‘‘Refueling Water Storage Tank’’; and SR
3.5.4.3, to increase the maximum
number of tritium producing burnable
absorber rods and to delete outdated
information related to the tritium
production program.
As previously discussed, the
proposed license amendment would not
result in any significant radiological or
non-radiological environmental
impacts, therefore the NRC has
concluded that a FONSI is appropriate.
The NRC’s EA, included in Section II of
this document, is incorporated by
reference into this finding.
On the basis of the EA, the NRC
concludes that the proposed action will
not have a significant effect on the
quality of the human environment.
Accordingly, the NRC has concluded
that an environmental impact statement
is not necessary for the evaluation of the
proposed action.
IV. Availability of Documents
The following table identifies the
environmental and other documents
cited in this document. These
documents are available for public
inspection online through ADAMS at
https://www.nrc.gov/reading-rm/
adams.html or in person at the NRC’s
PDR as previously described.
sradovich on DSK3GDR082PROD with NOTICES
Document
Date
NUREG–0498—Final Environmental Statement Related to Operation of Watts Bar Nuclear Plant, Units 1
and 2.
NUREG–0498—Final Environmental Statement Related to the Operation of Watts Bar Nuclear Plant, Units 1
and 2, Supplement 1.
Amendment No. 8—Authorized irradiation of 32 lead Test Assembly tritium-producing burnable absorber
rods (TPBARs) during Cycle 2.
Department of Energy NPD–98–181, Tritium Production Core Topical Report ..................................................
Amendment No. 40—Authorized loading up to 2,304 TPBARs ..........................................................................
Environmental Assessment for Amendment No. 40, (67 FR 54926) ..................................................................
Amendment No. 48—Authorized irradiation of 240 TPBARs during Cycle 6 ......................................................
Amendment No. 67—Authorized loading of 400 TPBARs during Cycle 9 ..........................................................
Amendment No. 77—Authorized an increase in the maximum number of TPBARs from 400 to 704 ...............
Department of Energy Final Supplemental Environmental Impact Statement for the Production of Tritium in a
Commercial Light Water Reactor. DOE/EIS–0288–S1.
TVA letter to NRC, Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’ .............................
TVA letter to NRC, Correction to Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’ .......
‘‘Watts Bar Nuclear Plant Unit 1, Annual Radioactive Effluent Release Report—2014’’ ....................................
NRC letter to TVA, Watts Bar Nuclear Plant, Unit 1—Supplemental Information Needed for Acceptance of
Requested Licensing Action Regarding Application to Increase Tritium Producing Absorbing Rods (TAC
No. MF6050).
TVA letter to NRC, Response to NRC Request to Supplement the Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’.
TVA letter to NRC, Response to NRC Request to Supplement Application to Revise Technical Specification
4.2.1, ‘‘Fuel Assemblies’’ (WBN–TS–15–03)—Radiological Protection and Radiological Consequences.
TVA letter to NRC, Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’ (WBN–TS–15–03)
(TAC No. MF6050)—Response to NRC Request for Additional Information—Reactor Systems Branch.
TVA letter to NRC, Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’ (WBN–TS–15–
03)—Response to NRC Request for Additional Information—Radiation Protection and Consequence
Branch.
TVA letter to NRC, Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’ (WBN–TS–15–
03)(TAC No. MF6050)—Response to NRC Request for Additional Information—Nuclear Performance and
Code Review Branch.
TVA letter to NRC, Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’ (WBN–TS–15–03)
(TAC No. MF6050)—Response to NRC Request for Additional Information—Radiation Protection and
Consequence Branch.
NRC letter to TVA, Audit Report Related to License Amendment Request to Revise Technical Specification
4.2.1, ‘‘Fuel Assemblies’’ (CAC No. MF6050).
TVA letter to NRC, Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’ (WBN–TS–15–
03)—Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory.
TVA letter to NRC, Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’ (WBN–TS–15–03)
(TAC No. MF6050)—Supplement to Response to NRC Request for Additional Information—Radiation Protection and Consequence Branch.
TVA letter to NRC, Application to Revise Technical Specification 4.2.1, ‘‘Fuel Assemblies’’ (WBN–TS–15–03)
(TAC No. MF6050)—Radioactive Waste System Design Basis Source Term Supplement to Response to
NRC Request for Additional Information—Radiation Protection and Consequence Branch.
12/1978
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ADAMS
Accession No.
Federal Register / Vol. 81, No. 128 / Tuesday, July 5, 2016 / Notices
Dated at Rockville, Maryland, this 23rd day
of June 2016.
For the Nuclear Regulatory Commission.
Jeanne A. Dion,
Project Manager, Plant Licensing Branch III–
2, Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. 2016–15867 Filed 7–1–16; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2016–0001]
Sunshine Act Meeting Notice
DATE:
July 4, 11, 18, 25, August 1, 8,
2016.
Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and Closed.
PLACE:
Week of July 4, 2016
Thursday, July 7, 2016
9:30 a.m.—Strategic Programmatic
Overview of the Reactors Operating
Business Line (Public Meeting)
(Contact: Trent Wertz: 301–415–
1568)
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
Week of July 11, 2016—Tentative
There are no meetings scheduled for
the week of July 11, 2016.
Week of July 18, 2016—Tentative
Thursday, July 21, 2016
9:30 a.m.—Briefing on Project Aim
(Public Meeting) (Contact: Janelle
Jessie: 301–415–6775)
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
notice. For more information or to verify
the status of meetings, contact Denise
McGovern at 301–415–0681 or via email
at Denise.McGovern@nrc.gov.
*
*
*
*
*
The NRC Commission Meeting
Schedule can be found on the Internet
at: https://www.nrc.gov/public-involve/
public-meetings/schedule.html.
*
*
*
*
*
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
Kimberly Meyer, NRC Disability
Program Manager, at 301–287–0739, by
videophone at 240–428–3217, or by
email at Kimberly.Meyer-Chambers@
nrc.gov. Determinations on requests for
reasonable accommodation will be
made on a case-by-case basis.
*
*
*
*
*
Members of the public may request to
receive this information electronically.
If you would like to be added to the
distribution, please contact the Nuclear
Regulatory Commission, Office of the
Secretary, Washington, DC 20555 (301–
415–1969), or email
Brenda.Akstulewicz@nrc.gov or
Patricia.Jimenez@nrc.gov.
Dated: June 29, 2016.
Denise L. McGovern,
Policy Coordinator, Office of the Secretary.
[FR Doc. 2016–15922 Filed 6–30–16; 11:15 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2016–0118]
Thursday, July 28, 2016
9:00 a.m.—Hearing on Combined
Licenses for Levy Nuclear Plant,
Units 1 and 2: Section 189a. of the
Atomic Energy Act Proceeding
(Public Meeting) (Contact: Donald
Habib: 301–415–1035)
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
sradovich on DSK3GDR082PROD with NOTICES
Week of July 25, 2016—Tentative
Applications and Amendments to
Facility Operating Licenses and
Combined Licenses Involving
Proposed No Significant Hazards
Considerations and Containing
Sensitive Unclassified Non-Safeguards
Information and Order Imposing
Procedures for Access to Sensitive
Unclassified Non-Safeguards
Information
Week of August 1, 2016—Tentative
There are no meetings scheduled for
the week of August 1, 2016.
Week of August 8, 2016—Tentative
There are no meetings scheduled for
the week of August 8, 2016.
*
*
*
*
*
The schedule for Commission
meetings is subject to change on short
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Nuclear Regulatory
Commission.
ACTION: License amendment requests;
opportunity to comment, request a
hearing, and petition for leave to
intervene; order.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) received and is
considering approval of four
SUMMARY:
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43661
amendment requests. The amendment
requests are for the Cooper Nuclear
Station (CNS); Duane Arnold Energy
Center (DAEC); and Browns Ferry
Nuclear Plant (BFN), Units 1, 2, and 3.
For each amendment request, the NRC
proposes to determine that it involves
no significant hazards consideration. In
addition, each amendment request
contains sensitive unclassified nonsafeguards information (SUNSI).
DATES: Comments must be filed by
August 4, 2016. A request for a hearing
must be filed by September 6, 2016. Any
potential party as defined in § 2.4 of title
10 of the Code of Federal Regulations
(10 CFR), who believes access to SUNSI
is necessary to respond to this notice
must request document access by July
15, 2016.
ADDRESSES: You may submit comments
by any of the following methods (unless
this document describes a different
method for submitting comments on a
specific subject):
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0118. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: Cindy Bladey,
Office of Administration, Mail Stop:
OWFN–12–H08, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001.
For additional direction on obtaining
information and submitting comments,
see ‘‘Obtaining Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
FOR FURTHER INFORMATION CONTACT:
Lynn Ronewicz, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington DC
20555–0001; telephone: 301–415–1927,
email: Lynn.Ronewicz@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2016–
0118 when contacting the NRC about
the availability of information for this
action. You may obtain publiclyavailable information related to this
action by any of the following methods:
• Federal rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0118.
• NRC’s Agencywide Documents
Access and Management System
E:\FR\FM\05JYN1.SGM
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]]>Agencies
[Federal Register Volume 81, Number 128 (Tuesday, July 5, 2016)]
[Notices]
[Pages 43656-43661]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-15867]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-390; NRC-2016-0131]
Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental assessment and finding of no significant impact;
issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering
the issuance of an amendment to Facility Operating License No. NFP-90,
issued February 7, 1996, and held by the Tennessee Valley Authority
(TVA, the licensee) for the operation of Watts Bar Nuclear Plant (WBN),
Unit 1. The proposed amendment would revise Technical Specification
(TS) 4.2.1, ``Fuel Assemblies''; TS 3.5.1 ``Accumulators'';
Surveillance Requirement (SR) 3.5.1.4; TS 3.5.4, ``Refueling Water
Storage Tank''; and SR 3.5.4.3, to increase the maximum number of
tritium producing burnable absorber rods (TPBARs) and to delete
outdated information related to the tritium production program. The NRC
staff is issuing an environmental assessment (EA) and finding of no
significant impact (FONSI) associated with the proposed license
amendment.
DATES: The Environmental assessment referenced in this document is
available on July 5, 2016.
ADDRESSES: Please refer to Docket ID NRC-2016-0131 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2016-0131. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. 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: Robert Schaaf, Office of Nuclear
Reactor Regulation, Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-6020, email: Robert.Schaaf@nrc.gov.
SUPPLEMENTARY INFORMATION:
[[Page 43657]]
I. Introduction
The NRC is considering issuance of an amendment to Facility
Operating License No. NFP-90, issued to TVA for operation of the WBN,
Unit 1, located in Rhea County, Tennessee. The proposed action would
allow TVA to make changes to the TSs to increase the maximum number of
TPBARs that can be irradiated, per cycle, in the WBN, Unit 1 core from
704 to 1,792. In accordance with National Environmental Policy Act of
1969, as amended (42 U.S.C. 4321 et seq.) and section 51.21 of title 10
of the Code of Federal Regulations (10 CFR), the NRC performed an EA.
Based on the following EA, the NRC has concluded that the proposed
actions will have no significant environmental impact, and is issuing a
FONSI.
The U.S. Department of Energy (DOE) and TVA will cooperate in a
program to produce tritium for the National Security Stockpile by
irradiating TPBARs in the WBN, Unit 1 reactor core. 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.
By letter dated September 23, 2002, the NRC approved Amendment No.
40 to Facility Operating License No. NPF-90 for WBN, Unit 1. The
amendment allowed TVA to irradiate up to 2,304 TPBARs in the WBN, Unit
1 reactor core each fuel cycle. This approval was based, in part, on
NRC's approval of DOE topical report ``Tritium Production Core Topical
Report,'' NPD-98-181, dated July 30, 1998, revised February 10, 1999,
which assumed that an average of 1 Curie (Ci) per year of tritium would
be released from each TPBAR into the reactor coolant, thereby
establishing a design basis source term for impact evaluation of 2,304
Ci/year attributable to TPBARs.
Because of issues related to the reactor coolant boron
concentration, and a higher than expected permeability of tritium from
the TPBARs, the TVA requested, and the NRC approved, Amendment 48 to
the WBN, Unit 1 operating license, issued October 8, 2003. Amendment 48
limited the number of TPBARs to be irradiated in WBN, Unit 1, fuel
cycle number 6 to 240 TPBARs. Subsequently, a series of amendments
limiting the number of TPBARs allowed to be loaded into the WBN, Unit
1, reactor core were reviewed and approved by the NRC. Currently,
Amendment 77, issued May 4, 2009, limits the maximum loading of the
WBN, Unit 1 reactor core to 704 TPBARs. This limit reflects the average
tritium permeation of approximately 3.27 Ci/TPBAR/year experienced
during TPBAR operations in fuel cycles 6 through 8, which limits the
number of TPBARs that could be loaded without exceeding the original
design basis source term of 2,304 Ci/year attributable to TPBARs.
The current request to allow core loadings up to 1,792 TPBARs will
support TVA's ability to meet the DOE agreement and national security
stockpile needs.
II. Environmental Assessment
Description of the Proposed Action
The proposed action would revise TS 4.2.1, ``Fuel Assemblies''; TS
3.5.1 ``Accumulators''; SR 3.5.1.4; TS 3.5.4, ``Refueling Water Storage
Tank''; and SR 3.5.4.3, to increase the maximum number of TPBARs and to
delete outdated information related to the tritium production program.
The proposed action is in accordance with the licensee's
application dated March 31, 2015, as supplemented by letters dated
April 28, May 27, June 15, September 14, September 25, November 30,
December 22, December 29, 2015, February 22, and March 31, 2016.
Need for the Proposed Action
The proposed action would allow WBN, Unit 1, to support the DOE,
National Nuclear Security Administration, national security stockpile
needs in accordance with Public Law (PL) 106-65. Section 3134 of PL
106-65 directs the Secretary of Energy to produce new tritium at TVA's
Watts Bar power plant.
Environmental Impacts of the Proposed Action
The radiological and non-radiological impacts on the environment
that may result from the proposed action are summarized below.
Non-Radiological Impacts
The proposed action would not change the types and amounts of any
non-radiological liquid or gaseous effluents that may be released
offsite. There would also be no physical changes to any structures or
land use within the WBN site, and the proposed action would not impact
air quality, water resources, or aquatic resources. In addition, the
proposed action would not result in any socioeconomic or environmental
justice impacts or impacts to historic and cultural resources.
Therefore, there would be no significant non-radiological
environmental impacts to any resource or any irreversible and
irretrievable commitments of resources.
Radiological Impacts
Radioactive Gaseous and Liquid Effluents and Solid Waste
The WBN, Unit 1, includes waste treatment systems to collect,
process, recycle, and dispose of gaseous, liquid, 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 an increase in
the maximum number of TPBARs that can be irradiated, per cycle, in the
WBN, Unit 1 core, from 704 to 1,792. This would affect the quantities
of radioactive material generated during plant operations as some
tritium permeates through the TPBAR cladding and is released into the
reactor coolant system. The historical average observed TPBAR tritium
permeation rate through cycle 12 is 3.4 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 its license amendment request, TVA assumed a core load of
1,900 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, TVA has stated that the current radioactive waste treatment
systems will be able to handle that increase.
Radioactive Gaseous Effluents
The WBN, Unit 1, 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 is
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 1,900 TPBARs with a permeation rate of 5.0 Ci/
TPBAR/year of tritium, which is a conservative
[[Page 43658]]
source term that bounds the observed and maximum TPBAR tritium
permeation rate. For its analysis of radioactive gaseous effluents, TVA
assumed that 10 percent of the tritium is released as gaseous effluent.
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 8 and 9 of the license amendment request demonstrate that TVA's
calculated C/ECL sums for gaseous effluent releases from an assumed
core load of 1,900 TPBARs for containment purge without filtration
would be 3.15 x 10-1 and would be 2.73 x 10-1
with continuous filtration. Both numbers are within the maximum C/ECL
limit of 1.0.
To determine whether the gaseous 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 1,900
TPBARs and the methods and assumptions in the current WBN Offsite Dose
Calculation Manual (ODCM), (documented in the ``Watts Bar Nuclear Plant
Unit 1, Annual Radioactive Effluent Release Report--2014''). TVA
calculated that the Whole Body dose to a Maximally Exposed Individual
would be 0.55 millirem (mrem) (0.0055 millisievert (mSv)), which is
much less than the Whole Body dose criterion 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 would be 10.6 mrem
(0.106 mSv), which is less than the Organ dose criterion in Appendix I
to 10 CFR part 50 of 15.00 mrem (0.15 mSv).
The NRC staff finds that the TVA's analyses have demonstrated that
WBN, Unit 1, 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 dose objectives set forth in appendix I to 10 CFR part 50.
Therefore, the NRC staff concludes that there would not be a
significant radiological impact from gaseous effluents under the
proposed action.
Radioactive Liquid Effluents
The WBN, Unit 1 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 WBN, Unit 1 has three
large tanks in the LRWS, which includes a Tritiated Water Storage Tank
with a capacity of 500,000 gallons. This tank supports managing large
volume/high tritium concentrations in the reactor coolant system. These
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 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 be ultimately
discharged into the Tennessee River.
As previously described, TVA assumed a core load of 1,900 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. For its analysis of radioactive liquid
effluents, TVA assumed that 90 percent of the tritium is released as
liquid effluent.
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 5 through 7 of the license amendment request supplement dated
March 31, 2016, show TVA's calculated C/ECL sums for liquid effluent
releases from an assumed core load of 1,900 TPBARs. Table 5 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 is
3.37, which is greater than the maximum allowable C/ECL of 1.0. To
ensure that the effluent concentration limits of 10 CFR 20.1301 are
met, TVA has revised Section 11.2.6.5 of the Final Safety Analysis
Report to include the statement that ``No untreated wastes are released
unless they are below the Lower Limit of Detection.'' Table 6 of the
license amendment request demonstrates that TVA's calculated C/ECL sum
for liquid effluent releases processed through the mobile demineralizer
would be 5.7 x 10-1. Table 7 demonstrates that TVA's
calculated C/ECL for liquid effluents not processed through the mobile
demineralizer, but sufficiently diluted before release, would be 5.8 x
10-1. Both numbers 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 1,900
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 0.43 mrem (0.0043 mSv), which is much
less than the Whole Body dose criterion 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 0.57 mrem (0.0057 mSv), which is less than the Organ dose criterion
in appendix I to 10 CFR part 50 of 10.00 mrem (0.15 mSv).
The NRC staff finds that the TVA analyses have demonstrated that
WBN, Unit 1, can be operated with the proposed 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
[[Page 43659]]
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 not
be a significant radiological impact from gaseous effluents under the
proposed action.
Solid Radioactive Wastes
Solid radioactive wastes generated by nuclear power plant
operations at WBN, Unit 1, 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 appendix I to 10 CFR part 50.
Implementation of the proposed action would be expected to 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. TVA will consolidate and
temporarily store these items on-site, and 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 per year. This
additional volume represents a slight increase in the WBN, Unit 1,
annual estimated solid waste generation from 32,820 cubic feet per year
to 32,853 cubic feet 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 1,800 Ci/
yr to 5,530 Ci/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 exposures to plant personnel within the
dose limits of 10 CFR 20.1201, 10 CFR 20.1301, and 10 CFR part 50,
appendix I. Based on the above, the NRC staff concludes that there
would not be a significant radiological impact from solid radioactive
waste management under the proposed action.
Spent Fuel Generation and Storage
The number of spent fuel bundles would be expected to increase by
approximately four per cycle with implementation of the proposed
action. WBN, Unit 1, currently stores spent fuel in spent fuel pools on
site, and under 10 CFR 72.210, TVA holds a general license authorizing
the operation of an independent spent fuel storage installation (ISFSI)
at the Watts Bar site. TVA has notified NRC of its intent to construct
an ISFSI under the general license. There will be adequate spent fuel
storage available on-site, therefore, the NRC staff concludes that
there would not be a significant radiological impact from spent fuel
generation and storage under the proposed action.
Occupational Radiation Doses
At WBN, Unit 1, 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 increase in the maximum number of TPBARs that can be
irradiated, per cycle, in the WBN, Unit 1, core from 704 to 1,792
continues to comply with NRC regulations for occupational dose, then
granting the proposed license amendment 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, Unit 1, can withstand the spectrum of postulated
accidents without undue hazard to public health and safety and ensure
the protection of the environment.
Separate from the environmental review for this EA, the NRC staff
is evaluating the licensee's technical and safety analyses provided in
the proposed license amendment 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 the
requested increase in the maximum number of TPBARs that can be
irradiated, per cycle, in the WBN, Unit 1, core continues to comply
with NRC regulations, and there is reasonable assurance that public
health and safety will not be endangered, then granting the proposed
license amendment will not have a significant environmental impact.
Radiological Impacts Summary
Based on the radiological evaluations associated with 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 its
safety evaluation that the requested increase in the maximum number of
TPBARs that can be irradiated, per cycle, in the WBN, Unit 1, core
continues to comply with the NRC's regulations, and there is reasonable
assurance that public health and safety will not be endangered, then
granting the proposed license amendment 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 proposed action (i.e., the ``no-action'' alternative).
Denial of the license amendment request would result in no change in
current environmental impacts.
Alternative Use of Resources
This action does not involve the use of any different resources not
previously considered in NUREG-0498, ``Final Environmental Statement
Related to
[[Page 43660]]
Operation of Watts Bar Nuclear Plant, Units 1 and 2,'' and NUREG-0498,
Supplement 1.
Agencies and Persons Consulted
In accordance with its stated policy, on May 13, 2016, the staff
consulted with the State of Tennessee official, regarding the
environmental impact of the proposed action. The state official
concurred with the EA and finding of no significant impact.
III. Finding of No Significant Impact
The NRC is considering the issuance of an amendment to Facility
Operating License No. NFP-90, issued February 7, 1996, and held by TVA
for the operation of WBN, Unit 1. The proposed amendment would revise
TS 4.2.1, ``Fuel Assemblies''; TS 3.5.1 ``Accumulators''; SR 3.5.1.4;
TS 3.5.4, ``Refueling Water Storage Tank''; and SR 3.5.4.3, to increase
the maximum number of tritium producing burnable absorber rods and to
delete outdated information related to the tritium production program.
As previously discussed, the proposed license amendment would not
result in any significant radiological or non-radiological
environmental impacts, therefore the NRC has concluded that a FONSI is
appropriate. The NRC's EA, included in Section II of this document, is
incorporated by reference into this finding.
On the basis of the EA, the NRC concludes that the proposed action
will not have a significant effect on the quality of the human
environment. Accordingly, the NRC has concluded that an environmental
impact statement is not necessary for the evaluation of the proposed
action.
IV. Availability of Documents
The following table identifies the environmental and other
documents cited in this document. These documents are available for
public inspection online through ADAMS at https://www.nrc.gov/reading-rm/adams.html or in person at the NRC's PDR as previously described.
------------------------------------------------------------------------
Document Date ADAMS Accession No.
------------------------------------------------------------------------
NUREG-0498--Final Environmental 12/1978 ML082540803
Statement Related to Operation
of Watts Bar Nuclear Plant,
Units 1 and 2.
NUREG-0498--Final Environmental 4/1995 ML081430592
Statement Related to the
Operation of Watts Bar Nuclear
Plant, Units 1 and 2,
Supplement 1.
Amendment No. 8--Authorized 9/15/1997 ML020780128
irradiation of 32 lead Test
Assembly tritium-producing
burnable absorber rods
(TPBARs) during Cycle 2.
Department of Energy NPD-98- 2/8/1999 ML16077A093
181, Tritium Production Core
Topical Report.
Amendment No. 40--Authorized 9/23/2002 ML022540925
loading up to 2,304 TPBARs.
Environmental Assessment for 8/26/2002 ML022320905
Amendment No. 40, (67 FR
54926).
Amendment No. 48--Authorized 10/8/2003 ML032880062
irradiation of 240 TPBARs
during Cycle 6.
Amendment No. 67--Authorized 1/18/2008 ML073520546
loading of 400 TPBARs during
Cycle 9.
Amendment No. 77--Authorized an 5/4/2009 ML090920506
increase in the maximum number
of TPBARs from 400 to 704.
Department of Energy Final 2016 (\1\)
Supplemental Environmental
Impact Statement for the
Production of Tritium in a
Commercial Light Water
Reactor. DOE/EIS-0288-S1.
TVA letter to NRC, Application 3/31/2015 ML15098A446
to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies''.
TVA letter to NRC, Correction 4/28/2015 ML15124A334
to Application to Revise
Technical Specification 4.2.1,
``Fuel Assemblies''.
``Watts Bar Nuclear Plant Unit 5/1/2015 ML15121A826
1, Annual Radioactive Effluent
Release Report--2014''.
NRC letter to TVA, Watts Bar 5/14/2015 ML15127A250
Nuclear Plant, Unit 1--
Supplemental Information
Needed for Acceptance of
Requested Licensing Action
Regarding Application to
Increase Tritium Producing
Absorbing Rods (TAC No.
MF6050).
TVA letter to NRC, Response to 5/27/2015 ML15147A611
NRC Request to Supplement the
Application to Revise
Technical Specification 4.2.1,
``Fuel Assemblies''.
TVA letter to NRC, Response to 6/15/2015 ML15167A359
NRC Request to Supplement
Application to Revise
Technical Specification 4.2.1,
``Fuel Assemblies'' (WBN-TS-15-
03)--Radiological Protection
and Radiological Consequences.
TVA letter to NRC, Application 9/14/2015 ML15258A204
to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies'' (WBN-TS-15-03)
(TAC No. MF6050)--Response to
NRC Request for Additional
Information--Reactor Systems
Branch.
TVA letter to NRC, Application 9/25/2015 ML15268A568
to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies'' (WBN-TS-15-03)--
Response to NRC Request for
Additional Information--
Radiation Protection and
Consequence Branch.
TVA letter to NRC, Application 11/30/2015 ML15335A468
to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies'' (WBN-TS-15-
03)(TAC No. MF6050)--Response
to NRC Request for Additional
Information--Nuclear
Performance and Code Review
Branch.
TVA letter to NRC, Application 12/22/2015 ML16054A661
to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies'' (WBN-TS-15-03)
(TAC No. MF6050)--Response to
NRC Request for Additional
Information--Radiation
Protection and Consequence
Branch.
NRC letter to TVA, Audit Report 12/23/2015 ML15345A424
Related to License Amendment
Request to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies'' (CAC No. MF6050).
TVA letter to NRC, Application 12/29/2015 ML16004A161
to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies'' (WBN-TS-15-03)--
Supplemental Information
Related to the Onsite
Regulatory Audit at Pacific
Northwest National Laboratory.
TVA letter to NRC, Application 2/22/2016 ML16053A513
to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies'' (WBN-TS-15-03)
(TAC No. MF6050)--Supplement
to Response to NRC Request for
Additional Information--
Radiation Protection and
Consequence Branch.
TVA letter to NRC, Application 3/31/2016 ML16095A064
to Revise Technical
Specification 4.2.1, ``Fuel
Assemblies'' (WBN-TS-15-03)
(TAC No. MF6050)--Radioactive
Waste System Design Basis
Source Term Supplement to
Response to NRC Request for
Additional Information--
Radiation Protection and
Consequence Branch.
------------------------------------------------------------------------
\1\ https://energy.gov/nepa/downloads/eis-0288-s1-epa-notice-availability-final-supplemental-environmental-impact-statement.
[[Page 43661]]
Dated at Rockville, Maryland, this 23rd day of June 2016.
For the Nuclear Regulatory Commission.
Jeanne A. Dion,
Project Manager, Plant Licensing Branch III-2, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2016-15867 Filed 7-1-16; 8:45 am]
BILLING CODE 7590-01-P
