[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]


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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.

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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outdated information related to the tritium production program.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 http://www.regulations.gov and search for Docket ID NRC-2016-0131. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; 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 ``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 [email protected]. 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: [email protected].

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 http://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\ http://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