81_FR_75030 81 FR 74822 - Purdue University Reactor

81 FR 74822 - Purdue University Reactor

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 81, Issue 208 (October 27, 2016)

Page Range74822-74828
FR Document2016-25993

The U.S. Nuclear Regulatory Commission (NRC) is considering renewal of Facility Operating License No. R-87, held by Purdue University (the applicant), for the continued operation of the Purdue University Reactor (PUR-1), located in West Lafayette, Tippecanoe County, Indiana for an additional 20 years. In connection with the renewed license, the applicant is also seeking a power increase from 1 kilowatt thermal (kW(t)) to a licensed power level of 12 kW(t). The NRC is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) associated with the renewal of the license.

Federal Register, Volume 81 Issue 208 (Thursday, October 27, 2016)
[Federal Register Volume 81, Number 208 (Thursday, October 27, 2016)]
[Notices]
[Pages 74822-74828]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2016-25993]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-182; NRC-2011-0186]


Purdue University Reactor

AGENCY: Nuclear Regulatory Commission.

[[Page 74823]]


ACTION: Environmental assessment and finding of no significant impact; 
issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering 
renewal of Facility Operating License No. R-87, held by Purdue 
University (the applicant), for the continued operation of the Purdue 
University Reactor (PUR-1), located in West Lafayette, Tippecanoe 
County, Indiana for an additional 20 years. In connection with the 
renewed license, the applicant is also seeking a power increase from 1 
kilowatt thermal (kW(t)) to a licensed power level of 12 kW(t). The NRC 
is issuing an environmental assessment (EA) and finding of no 
significant impact (FONSI) associated with the renewal of the license.

DATES: The EA and FONSI referenced in this document is available on 
October 27, 2016.

ADDRESSES: Please refer to Docket ID NRC-2011-0186 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-2011-0186. 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: Cindy K. Montgomery, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-3398; email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Introduction

    The NRC is considering issuance of a renewed Facility Operating 
License No. R-87, held by Purdue University, which would authorize 
continued operation of PUR-1, located in West Lafayette, Tippecanoe 
County, Indiana, for an additional 20 years. In connection with the 
renewed license, the applicant is also seeking a power increase from 1 
kW(t) to 12 kW(t). As required by section 51.21 of title 10 of the Code 
of Federal Regulations (10 CFR), ``Criteria for and identification of 
licensing and regulatory actions requiring environmental assessments,'' 
the NRC performed an EA. Based on the results of the EA that follows, 
the NRC has determined not to prepare an environmental impact statement 
for the proposed action and is issuing a FONSI.

II. Environmental Assessment

Description of the Proposed Action

    The proposed action would renew Facility Operating License No. R-87 
for a period of 20 years from the date of issuance of the renewed 
license. The proposed action would also authorize a power increase from 
1 kW(t) to 12 kW(t). The proposed action is in accordance with Purdue 
University's application dated July 7, 2008, as supplemented by letters 
dated June 30, 2008; June 3, and June 4, 2010; November 15, 2011; 
January 4, January 30, January 31, June 1, June 15, June 29, July 13, 
and August 11, 2012; April 10, 2013; July 24, 2015; and January 29, 
February 26, March 31, May 9, July 7, July 19, September 19, and 
September 29, 2016 (collectively referred to as ``the renewal 
application''). In accordance with Sec.  2.109, ``Effect of timely 
renewal application,'' the existing license remains in effect until the 
NRC takes final action on the renewal application.

Need for the Proposed Action

    The proposed action is needed to allow the continued operation of 
the PUR-1, which is used for teaching and research to support the 
mission of Purdue University, for a period of 20 years. Operation of 
the PUR-1 at the requested higher power level would expand the 
educational and research uses of the facility.

Environmental Impacts of the Proposed Action

    Separate from the environmental assessment referenced in this 
document, the NRC is writing a safety evaluation (SE) of the proposed 
action to issue renewed Facility Operating License No. R-87 to allow 
continued operation of the PUR-1 for a period of 20 years. The details 
of the NRC's SE will be provided with the renewed license, if approved. 
This document contains the EA of the proposed action.
    The applicant has requested a power increase from 1 kW(t) to 12 
kW(t) maximum allowed licensed power. The applicant performed analyses 
at 18 kW(t) to bound the requested power increase. The applicant's 
required annual reports from 2011 through 2015 indicate that no 
measurable amount of radioactive effluent was released from the PUR-1 
to the environment.

Facility Site and Environs

    The PUR-1 is a heterogeneous, pool-type non-power reactor that has 
been in operation since 1962 for teaching and research purposes. The 
PUR-1 is located in the Duncan Annex of the Electrical Engineering 
Building on the eastern edge of the Purdue University campus. The 
building was originally designed as a high voltage laboratory, and the 
space was later converted into classrooms, laboratories, and offices. 
The building is constructed of brick, concrete block, and reinforced 
concrete. Within the Duncan Annex, the PUR-1 is located within a 6,400-
gallon cylindrical water tank that is 17 feet deep and 8 feet in 
diameter. The tank is enclosed by a concrete shielding structure.
    The PUR-1 operates about 90 times per year on average. The reactor 
is fueled with standard low-enriched uranium plate-type fuel and is 
cooled by natural convection of light water. The reactor coolant system 
includes a process system, which controls the pool water temperature, 
and a purification system, which is designed to maintain pool water 
quality by limiting corrosion and coolant activation by the use of 
microfilters and ion exchange resins. Water from the pool is drawn out 
from the scupper drain or suction line via polyvinyl chloride piping 
leading to the circulating pump; a second source of water for the pump 
is a water supply tank supplied with city service water and controlled 
by a float valve. Ball valves for water shutoff and a vacuum cleaning 
connection are provided in the pump supply line. From the pump, a pipe 
with a ball valve installed leads first to the filter and then to a 
demineralizer. An adjustable by-pass or throttling valve is inserted in 
the system to regulate water flow through the demineralizer. A flow 
indicator and a conductivity indicator are installed as a check on flow 
rate and water purity

[[Page 74824]]

from the demineralizer. The water next flows through a stainless steel 
heat exchanger. The water from the heat exchanger is then returned to 
the reactor pool. A magnetrol water-level control is located in the 
reactor pool; this unit controls a solenoid valve in the line from the 
water supply tank to ensure that the prescribed pool water level is 
maintained. However, this system is manually controlled by the PUR-1 
staff to allow markup water to be inventoried. Makeup pool water is 
provided by the city public water supply.
    A detailed description of the reactor can be found in the PUR-1 
Safety Analysis Report (SAR) submitted by the applicant with its 
renewal application.
A. Radiological Impacts
Environmental Effects of Reactor Operations
    During normal operations at the PUR-1 facility, the two primary 
airborne sources of radiation are argon-41 (Ar-41) and nitrogen-16 (N-
16). N-16 is produced when oxygen in the pool water is irradiated in 
the reactor core, and must then diffuse to the pool surface before it 
is released to the atmosphere. The applicant estimates that, due to its 
short half-life (about 7 seconds), any N-16 produced by the reactor at 
the bounding power level of 18 kW(t) would decay before reaching the 
surface of the pool. The primary source of Ar-41 at the PUR-1 is from 
irradiation of air containing argon dissolved in the reactor pool. At 
the current 1 kW(t) steady-state operation, effluent samples in the 
reactor room have not contained detectable traces of Ar-41. At the 
bounding power level of 18 kW(t), the applicant estimates that steady-
state operation of the reactor would produce an equilibrium 
concentration of 2.08 x 10-7 [mu]Ci/cm\3\ of Ar-41 in the 
exhaust air and the reactor room, which is lower than the 3.0 x 
10-6 [mu]Ci/cm\3\ Derived Air Concentration (DAC) limit for 
occupational workers found in 10 CFR part 20. Due to the DAC being 
below regulatory limits, the estimated occupational radioactivity 
exposure levels will also be below the 10 CFR part 20 limit of 5 
reontgen equivalent man (rem). The estimated dose rate to a worker at 
the bounding power level of 18 kW(t) was calculated by the applicant to 
be 0.167 milli roentgen equivalent man per hour (mrem/hr) (0.00167 
millisievert/hour (mSv/hr)). Using the calculated dose rate, the total 
effective dose equivalent to a worker in the reactor room for an entire 
year would be less than 334 mrem (3.34 mSv), assuming a hypothetical 
2,000-hour steady state, full power operation, since the reactor 
license contains no restriction on operating hours. The reactor 
normally operates for much less than the assumed 8 hours per day and 
the conservatively calculated dose is still well below the 5,000-mrem 
(50 mSv) limit established in Sec.  20.1201, ``Occupational dose limits 
for adults.'' The applicant also calculated, at the bounding 18 kW(t) 
power level, an environmental public dose rate from normal operations 
to a person in the unrestricted area due to Ar-41 released from the 
building ventilation opening. The release point is on the roof vent on 
the top of the building 15 meters above ground. Assuming a hypothetical 
continuous steady state, full power operation for a year, the applicant 
calculated the public dose rate to be 3.17 x 10-4 mrem/hr 
(3.17 x 0-6 mSv/hr) or 2.8 mrem/yr (0.28 mSv/yr), which is 
well below the limit in Sec.  20.1301 of 100 mrem/yr (1 mSv/yr). This 
calculated public dose rate would also meet the as low as is reasonably 
achievable (ALARA) dose constraint of 10 mrem/yr (0.1 mSv/yr) found in 
Sec.  20.1101(d).
    Purdue University has a structured radiation safety program. 
Policies for the program are determined by the University Radiation 
Safety Committee, which has the mission to ensure the safety of the 
University and community in the utilization of all radioactive 
materials and radiation-producing devices at the University by faculty, 
staff, or students. The program is administered by the Radiation Safety 
Officer and his staff, as part of Radiological and Environmental 
Management. The staff is equipped with radiation detection 
instrumentation to determine, control, and document occupational 
radiation exposures at the reactor facility under the broad scope 
byproduct materials license held by Purdue University.
    Only very limited contaminated materials are generated by PUR-1. 
Any contaminated material is disposed of under the Purdue University 
broad scope license. No wastes have been released to the environment in 
an uncontrolled manner. During the past 5-year period from 2011 through 
2015, the applicant reported no routine releases of liquid radioactive 
waste by any disposal method. The NRC assumes that any changes due to 
the requested power increase from 1 kW(t) to 12 kW(t) are expected to 
be minimal and capable of being handled by the existing systems and 
procedures.
    As described in Chapter 11 of the PUR-1 SAR, personnel exposures 
are well within the limits set by Sec.  20.1201, ``Occupational dose 
limits for adults,'' and the ALARA dose criteria in Sec.  20.1101(b). 
The University is committed to the principle of ALARA and it makes 
every effort to keep doses to a minimum. All unanticipated or unusual 
exposures are investigated. According to annual reports for the past 5 
years of operation from 2011 through 2015, there were no radiation 
exposures greater than 25 percent of limits set forth in Sec.  20.1201. 
The change in occupational dose from the proposed power uprate from 1 
kW(t) to 12 kW(t) is discussed previously in this notice.
    The applicant monitors dose to the public by placing 
thermoluminescent dosimeters (TLD) at the boundaries of the facility. 
The TLDs are checked for exposure every other month. Doses measured 
from the TLDs at the current operating power level of 1 kW(t) have been 
at background levels, therefore, the applicant concludes that the 
public has not received exposures greater than the limits set forth in 
Sec.  20.1301, ``Dose limits for individual members of the public.'' As 
stated previously, this should not change for the proposed power 
increase of 12 kW(t). Additionally, the potential radiation dose from 
current operations at 1kW(t) also demonstrates compliance with the 
ALARA dose constraints specified in Sec.  20.1101(d), ``Radiation 
protection programs.'' As stated previously, this should not change for 
the proposed power increase of 12 kW(t).
    Over the past 5 years of operation from 2011 through 2015, results 
from the applicant's survey program indicate that radiation exposures 
at the current operating power level of 1 kW(t) at the monitoring 
locations were not significantly higher than those measured at the 
control locations. This should not change for the proposed power 
increase of 12 kW(t). Therefore, the NRC concludes that the proposed 
action would not have a significant radiological impact.
Environmental Effects of Accidents
    The maximum hypothetical accident (MHA) is an event involving the 
cladding failure of an irradiated fuel element in air. The MHA is 
considered the worst-case fuel failure scenario for PUR-1 that would 
lead to the maximum potential radiation hazard to facility personnel 
and to members of the public. The results of the MHA are used by the 
NRC to evaluate the ability of the applicant to respond and mitigate 
the consequences of this postulated radioactive release.
    The applicant conservatively calculated doses to facility personnel

[[Page 74825]]

during evacuation and the maximum potential doses to members of the 
public at various locations around the PUR-1 facility. The license 
estimated an occupational dose of 317 mrem (3.17 mSv), for a one minute 
(evacuation) duration, and 47 mrem (0.47 mSv) for the maximum exposed 
member of the public. The NRC performed independent calculations to 
verify that the applicant's calculated doses represented conservative 
estimates for the MHA. The NRC, using conservative assumptions, 
estimated a dose to a worker of 294 mrem (2.94 mSv) for a one minute 
duration, and 4 mrem (0.04 mSv) for the maximum exposed member of the 
public. The details of these calculations are provided in the NRC's SER 
that will be issued with the renewed license. The occupational 
radiation doses resulting from the postulated MHA would be well below 
the 10 CFR 20.1201 limit of 5,000 mrem (50 mSv). The maximum calculated 
radiation doses for members of the public resulting from the postulated 
MHA would be below the 10 CFR 20.1301 limit of 100 mrem (1 mSv).
    Because the NRC concludes in the SE that the radiological 
consequences of the MHA are within the NRC's 10 CFR part 20 dose 
limits, the proposed action will not have a significant impact with 
respect to the radiological consequences of the MHA.
Conclusions--Radiological Impacts
    As discussed previously in this notice, the applicant has requested 
a power increase from 1kW to 12 kW maximum allowed licensed power. In 
addition, as previously described, while there is a potential increase 
in routine occupational and public radiation exposure as a result of 
license renewal at the higher power level, all exposure rates and doses 
would be within regulatory limits. There would be no changes in the 
types of effluents that may be released off site, and any potential 
increase in their quantities would be within regulatory limits. The 
applicant has systems in place for controlling the release of 
radiological effluents and implements a radiation protection program to 
monitor personnel exposures and releases of radioactive effluents, and 
the systems and radiation protection program are appropriate for the 
types and quantities of effluents expected to be generated by continued 
operation of the reactor. The proposed action will not significantly 
increase the probability or consequences of accidents. Therefore, 
license renewal and the proposed power increase would not change the 
environmental impact of facility operation. The NRC evaluated 
information contained in the renewal application and data reported to 
the NRC by the applicant for the last 5 years of operation to determine 
the projected radiological impact of the facility on the environment 
during the period of the renewed license. The NRC found that releases 
of radioactive material and personnel exposures were all well within 
applicable regulatory limits. Based on this evaluation, the NRC 
concludes that the proposed action would not have a significant 
environmental impact.
B. Non-Radiological Impacts
    The proposed action would not result in any land use changes, 
visual resource impacts, or increases in noise. No significant changes 
in air emissions would occur as a result of the proposed license 
renewal and power increase. Because water is supplied through the city, 
the proposed action would not affect surface water or groundwater 
resources. There is no potential for the proposed action to affect 
aquatic or terrestrial resources. Therefore, the NRC concludes that the 
proposed action would have no significant non-radiological impacts.
Other Applicable Environmental Laws
    In addition to the National Environmental Policy Act (NEPA), the 
NRC has responsibilities that are derived from other environmental 
laws, which include the Endangered Species Act (ESA), Coastal Zone 
Management Act, National Historic Preservation Act (NHPA), Fish and 
Wildlife Coordination Act, and Executive Order 12898 Environmental 
Justice. Preparing this EA satisfies the agency's obligations under 
NEPA. The following presents a brief discussion of impacts associated 
with resources protected by these laws.
Endangered Species Act
    The NRC staff conducted a search of Federally listed species and 
critical habitats that have the potential to occur in the vicinity of 
the PUR-1 using the U.S. Fish and Wildlife Service's (FWS) 
Environmental Conservation Online System Information for Planning and 
Conservation (IPaC) system. Five Federally-listed mussels--clubshell 
(Pleurobema clava), fanshell (Cyprogenia stegaria), snuffbox 
(Epioblasma triquetra), rabbitsfoot (Quadrula cylindrical cylindrical), 
and sheepnose (Plethobasus cyphus)--and the Indiana bat (Myotis 
sodalis) occur in Tippecanoe County. However, none of these species are 
likely to occur near the PUR-1 because the facility is located on the 
Purdue University Campus, which has been developed since the 1960s and 
does not provide suitable habitat for Federally-listed species. 
Additionally, operation of PUR-1 has no direct nexus to the natural 
environment that would affect Federally-listed species. Accordingly, 
the NRC concludes that the proposed license renewal of the PUR-1 would 
have no effect on Federally-listed species or critical habitats. 
Federal agencies are not required to consult with the FWS if they 
determine that an action will not affect listed species or critical 
habitats (ADAMS Accession No. ML16120A505). Thus, the ESA does not 
require consultation for the proposed PUR-1 license renewal and 
proposed power uprate, and the NRC considers its obligations under ESA 
section 7 to be fulfilled for the proposed action.
Costal Zone Management Act
    Tippecanoe County, Indiana does not contain any coastal zones. 
Because the PUR-1 is not located within or near any managed coastal 
zones, the proposed action would not affect any coastal zones and 
Coastal Zone Management Act consistency certification does not apply.
National Historic Preservation Act
    The NHPA requires Federal agencies to consider the effects of their 
undertakings on historic properties. As stated in the Act, historic 
properties are any prehistoric or historic district, site, building, 
structure, or object included in, or eligible for inclusion in the 
National Register of Historic Places (NRHP). The NRHP lists several 
historic districts and properties within 0.5 miles of PUR-1 in the 
Duncan Annex of the Electrical Engineering Building on the campus of 
Purdue University. Operation of PUR-1 has not likely had any impact on 
these districts and properties. Based on this information, the NRC 
staff finds that the potential impacts of license renewal and the 
continued operation of PUR-1 would have no adverse effect on historic 
properties located near PUR-1.
Fish and Wildlife Coordination Act
    The proposed action does not involve any water resource development 
projects, including any of the modifications relating to impounding a 
body of water, damming, diverting a stream or river, deepening a 
channel, irrigation, or altering a body of water for navigation or 
drainage. Therefore, no coordination with FWS pursuant to the Fish and 
Wildlife Coordination Act is required for the proposed action.

[[Page 74826]]

Executive Order 12898--Environmental Justice
    The environmental justice impact analysis evaluates the potential 
for disproportionately high and adverse human health and environmental 
effects on minority and low-income populations that could result from 
the relicensing and the continued operation of PUR-1. Such effects may 
include human health, biological, cultural, economic, or social 
impacts.
    Minority Populations in the Vicinity of PUR-1. According to U.S. 
Census Bureau's 2010 Census, approximately 21 percent of the total 
population (approximately 164,000 individuals) residing within a 10-
mile radius of PUR-1 identified themselves as minorities. The largest 
minority population were Hispanic, Latino, or Spanish origin of any 
race at (approximately 12,800 or 8 percent), followed by Asian 
(approximately 10,700 persons or 7 percent). According to the 2010 
Census, about 20 percent of the Tippecanoe County population identified 
themselves as minorities, with persons of Hispanic, Latino, or Spanish 
origin and Asians comprising the largest minority populations 
(approximately 8 and 7 percent, respectively). According to the U.S. 
Census Bureau's 2014 American Community Survey 1-year Estimates, the 
minority population of Tippecanoe County, as a percent of the total 
population, had increased to about 22 percent.
    Low-income Populations in the Vicinity of PUR-1. According to the 
U.S. Census Bureau's 2010-2014 American Community Survey 5-Year 
Estimates, approximately 36,000 persons and 4,000 families 
(approximately 22.7 and 11.7 percent, respectively) residing within a 
10-mile radius of PUR-1 were identified as living below the Federal 
poverty threshold. The 2014 Federal poverty threshold was $24,230 for a 
family of four.
    According to the U.S. Census Bureau's 2014 American Community 
Survey Census 1-Year Estimates, the median household income for Indiana 
was $49,446, while 11 percent of families and 15.2 percent of the state 
population were found to be living below the Federal poverty threshold. 
Tippecanoe County had a lower median household income average ($45,771) 
and a higher percent of families and people living below the poverty 
level (12.2 and 23.6 percent, respectively).
    Impact Analysis. Potential impacts to minority and low-income 
populations would mostly consist of radiological effects, however, 
radiation doses from continued operations associated with the license 
renewal and the proposed power increase are expected to continue at 
current levels, and would be well below regulatory limits.
    Based on this information and the analysis of human health and 
environmental impacts presented in this EA, the proposed action would 
not have disproportionately high and adverse human health and 
environmental effects on minority and low-income populations residing 
in the vicinity of PUR-1.
Environmental Impacts of the Alternatives to the Proposed Action
    As an alternative to license renewal, the NRC considered denying 
the proposed action (i.e., the ``no-action'' alternative). If the NRC 
denied the request for license renewal, reactor operations would cease 
and decommissioning would be required. The NRC notes that, even with a 
renewed license, PUR-1 will eventually be decommissioned, at which time 
the environmental effects of decommissioning would occur. 
Decommissioning would be conducted in accordance with an NRC-approved 
decommissioning plan, which would require a separate environmental 
review under Sec.  51.21. Cessation of reactor operations would reduce 
or eliminate radioactive effluents. However, as previously discussed in 
this EA, radioactive effluents from reactor operations constitute a 
small fraction of the applicable regulatory limits. Therefore, the 
environmental impacts of license renewal, including the proposed power 
uprate, and the denial of the request for license renewal would be 
similar. In addition, denying the request for license renewal would 
eliminate the benefits of teaching, research, and services provided by 
the PUR-1 facility.
Alternative Use of Resources
    The proposed action does not involve the use of any different 
resources or significant quantities of resources beyond those 
previously considered in the issuance of Facility Operating License No. 
R-87 for the PUR-1 in August 1988, which renewed the Facility Operating 
License for a period of 20 years.
Agencies and Persons Consulted
    The NRC did not enter into consultation with any other Federal 
agencies or with the State of Indiana regarding the environmental 
impact of the proposed action. However, on October 21, 2016, the NRC 
notified the Indiana State official, Ms. Laura Dresen, Radiation 
Programs Director, of the Indiana Department of Homeland Security of 
the proposed action. The State official had no comments.

III. Finding of No Significant Impact

    The NRC is considering issuance of a renewed Facility Operating 
License No. R-87, held by Purdue University, which would authorize the 
continued operation of PUR-1 for an additional 20 years.
    On the basis of the EA included in Section II of this notice and 
incorporated by reference in this finding, the NRC concludes that the 
proposed action would not have significant effects on the quality of 
the human environment. Section IV lists the environmental documents 
related to the proposed action and includes information on the 
availability of these documents. Based on its findings, the NRC has 
decided not to prepare an environmental impact statement for the 
proposed action.

IV. Availability of Documents

    The documents identified in the following tables are available to 
interested persons as indicated.

------------------------------------------------------------------------
                                                               ADAMS
                        Document                           accession No.
------------------------------------------------------------------------
Purdue University, School of Nuclear Engineering.            ML083040443
 Application for relicense of License Number R-87 with
 Power Uprate, July 7, 2008.............................
Purdue University Safety Analysis Report, June 30, 2008      ML111890201
 [Redacted Version].....................................
Purdue University--Request for Additional Information        ML101620125
 (RAI) Regarding License Renewal, [Decommissioning
 Funding Statement of Intent], June 3, 2010.............
Purdue University--Request For Additional Information        ML101620184
 Regarding the Purdue University Reactor License Renewal
 (Tac No. Me 1594), Responses to RAIs Dated 24 March
 2010, [Responses To ML100820019, financial assurance,
 statement of intent, signature authority, financial
 report], June 4, 2010..................................
Response to Request for Additional Information Regarding     ML11320A287
 the Purdue University Reactor License Renewal (TAC
 ME1594), Response to RAIs Dated 6 July 2011
 (ML101460429), November 15, 2011.......................

[[Page 74827]]

 
Purdue University--Request for Additional Information        ML12006A193
 Regarding the License Renewal, Responses to RAIs Dated
 6 July 2011, [Responses 11, 12, 13, 15, 16, 18, 21, 23,
 25, 27, 28, 30, 31, 33, 35, 36, and 37], January 4,
 2012...................................................
Purdue University--Responses to the Request for              ML12031A223
 Additional Information Regarding the Purdue University
 Reactor License Renewal dated July 6, 2011, [Responses
 3, 4, 7, 10, 17, 19, 20, 22, 24, 29, 34, and 40],
 January 30, 2012.......................................
Purdue University--Request for Additional Information        ML14234A109
 Regarding the Purdue University Reactor License Renewal
 (TAC NO. ME 1594), Responses to RAIS (ML103400115 and
 ML103400250) (Redacted Version), [Responses 45, 55, 62,
 65, 66, 67, 68, 70, and 73], January 31, 2012..........
Request for Additional Information Regarding the Purdue      ML12156A364
 University Reactor License Renewal (TAC ME1594),
 Responses to RAIs (ML103400115 and ML103400250),
 [Responses 43, 51, 56, 60, and 61], June 1, 2012.......
Purdue University--Request for Additional Information        ML12170B018
 Regarding the Purdue University Reactor License Renewal
 (TAC No. ME1594), Responses to RAIs (ML103400115 and
 ML103400250), [Response 46, 47, 52, 57, and 59], June
 15, 2012...............................................
Purdue University--Request for Additional Information        ML12170B018
 Regarding the Purdue University Reactor License
 Renewal, Responses to RAIs (ML103400115 and
 ML103400250), [Response 48, 58, 96, 97 and 98], June
 29, 2012...............................................
Purdue University--Request for Additional Information        ML12201A070
 Regarding the Purdue University Reactor License
 Renewal, Response to RAI, [Response 49, 50, 53, 64, and
 72], July 13, 2012.....................................
Purdue University--Response to Request for Additional        ML12226A400
 Information Regarding Purdue University Reactor License
 Renewal (TAC No. ME1594, Responses to RAIs (ML103400115
 and ML103400250), [Responses 54, 69, 77, 78, and 92],
 August 11, 2012........................................
Purdue University--Response to Request Request for           ML13101A044
 Additional Information Regarding the Purdue University
 Reactor License Renewal (TAC ME1594), [Responses 54,
 69, 77, 78, and 92], April 10, 2013....................
U.S. Fish and Wildlife Service, Endangered Species           ML16120A505
 Consultations Frequently Asked Questions, July 15, 2013
Purdue University Research Reactor, Report on Reactor        ML13203A081
 Operations For the Period January 1, 2011 to December
 31, 2011, July 18, 2013................................
Purdue University Research Reactor, Report on Reactor        ML13203A082
 Operations For the Period January 1, 2012 to December
 31, 2012, July 18, 2013................................
Purdue University Research Reactor, Report on Reactor        ML14154A123
 Operations For the Period January 1, 2013 to December
 31, 2013, May 22, 2014.................................
Purdue University Research Reactor, Report on Reactor        ML15092A160
 Operations For the Period January 1, 2014 to December
 31, 2014, March 30, 2015...............................
Purdue University--Request for Additional Information        ML15210A280
 Regarding the Purdue University Reactor License Renewal
 Application (TAC No. ME1594), Responses to Letter Dated
 August 29, 2014 (ML14115A221), [RAI cover letter for
 responses to August 29, 2015 NRC letter], July 24, 2015
Purdue University--Request for Additional Information        ML15210A282
 Regarding the Purdue University Reactor License Renewal
 Application (TAC No. ME1594), Responses to Letter Dated
 August 29, 2014 (ML14115A221), Part 1 of 5, [RAI
 Responses part 1 of 5: responses (1-29), TS (30-64), d/
 c cost estimate (65-68), Requal (69-73), SAR Chs. 1-5
 (70-162)], July 24, 2015...............................
Purdue University--Request for Additional Information        ML15210A283
 Regarding the Purdue University Reactor License Renewal
 Application (TAC No. ME1594), Responses to Letter Dated
 August 29, 2014 (ML14115A221), Part 2 of 5, [RAI
 Responses part 2 of 5 (SAR Chs. 6-15)], July 24, 2015..
Purdue University--Request for Additional Information        ML15210A285
 Regarding the Purdue University Reactor License Renewal
 Application (TAC No. ME1594), Responses to Letter Dated
 August 29, 2014 (ML14115A221), Part 3 of 5, [RAI
 Responses Part 3 of 5 (drawings)], July 24, 2015.......
Purdue University--Request for Additional Information        ML15210A287
 Regarding the Purdue University Reactor License Renewal
 Application (TAC No. ME1594), Responses to Letter Dated
 August 29, 2014 (ML14115A221), Part 4 of 5, [RAI
 Responses Part 4 of 5 (drawings)], July 24, 2015.......
Purdue University--Request for Additional Information        ML15210A288
 Regarding the Purdue University Reactor License Renewal
 Application (TAC No. ME1594), Responses to Letter Dated
 August 29, 2014 (ML14115A221), Part 5 of 5, [RAI
 Responses part 5 of 5 (NATCON, Procedures, Drawings)],
 July 24, 2015..........................................
Purdue University--Response to NRC Request for               ML16047A382
 Additional Information Regarding Physical Security Plan
 Review for License Renewal, January 29, 2016...........
Purdue University--Re-Submittal Response to NRC Request      ML16083A219
 for Additional Information Regarding Physical Security
 Plan Review for License Renewal, February 26, 2016.....
Purdue Re-Submittal of Response to NRC Request for           ML16102A123
 Additional Information Re: Physical Security Plan
 Review for License Renewal, March 31, 2016.............
Purdue University Research Reactor, Report on Reactor        ML16102A119
 Operations For the Period January 1, 2015 to December
 31, 2015, March 31, 2016...............................
Purdue University--Second Re-Submittal of Response to        ML16134A143
 NRC Request for Additional Information Regarding
 Physical Security Plan Review for License Renewal, May
 9, 2016................................................
Purdue University School of Nuclear Engineering Notice       ML16193A681
 of ADAMS Document Correction, PUR-1, Docket 50-182,
 ML16187A371, Technical Specifications, Proposed
 Amendment 13 Enclosed, [Correction of the TSs,
 originally submitted under ML16187A371], July 7, 2016..
Purdue University Responses to Request for Additional        ML16207A426
 Information re PUR-1 License Renewal and Power Uprate,
 [Responses to RAIs ML15328A314], July 19, 2016.........
Purdue University--Response to Request for Additional        ML16267A465
 Information Regarding the Reactor License Renewal
 Application, Responses to Letter dated July 25, 2016,
 September 19, 2016.....................................
Purdue University--Explanation of Technical                  ML16277A165
 Specification Changes and Emergency Operator Action,
 September 29, 2016.....................................
------------------------------------------------------------------------



[[Page 74828]]

    Dated at Rockville, Maryland, this 21st day October, 2016.

    For the Nuclear Regulatory Commission.
Alexander Adams, Jr.,
Chief, Research and Test Reactors Branch, Division of Policy and 
Rulemaking, Office of Nuclear Reactor Regulation.
[FR Doc. 2016-25993 Filed 10-26-16; 8:45 am]
 BILLING CODE 7590-01-P



                                                74822                       Federal Register / Vol. 81, No. 208 / Thursday, October 27, 2016 / Notices

                                                removing the requirement for a licensed                 exemption would allow the licensee to                 types or significant increase in the
                                                senior operator to approve the                          designate an alternative position, with               amounts of any effluents that may be
                                                suspension of security measures in an                   qualifications appropriate for a                      released offsite; and no significant
                                                emergency or during severe weather, to                  permanently shutdown and defueled                     increase in individual or cumulative
                                                allow suspension of security measures                   reactor, to approve the suspension of                 public or occupational radiation
                                                to be authorized by a CFH, does not                     security measures during an emergency                 exposure. The exempted regulation is
                                                adversely affect public health and safety               to protect the public health and safety,              not associated with construction, so
                                                issues or the assurance of the common                   and during severe weather to protect the              there is no significant construction
                                                defense and security.                                   safety of the security force, consistent              impact. The exempted regulation does
                                                                                                        with the similar authority provided by                not concern the source term (i.e.,
                                                C. Is Otherwise in the Public Interest
                                                                                                        § 50.54(y). Therefore, the exemption is               potential amount of radiation in an
                                                   Entergy’s proposed exemption would                   in the public interest.                               accident), nor mitigation. Thus, there is
                                                allow a CFH, following permanent                                                                              no significant increase in the potential
                                                cessation of operation and permanent                    D. Environmental Considerations
                                                                                                                                                              for, or consequences of, a radiological
                                                removal of fuel from the reactor vessel,                   The NRC’s approval of the exemption                accident. The requirement to have a
                                                to approve suspension of security                       to security requirements belongs to a                 licensed senior operator approve
                                                measures in an emergency when                           category of actions that the Commission,              departure from security actions may be
                                                ‘‘immediately needed to protect the                     by rule or regulation, has declared to be             viewed as involving either safeguards,
                                                public health and safety’’ or during                    a categorical exclusion, after first                  materials control, or managerial matters.
                                                severe weather when ‘‘immediately                       finding that the category of actions does
                                                needed to protect the personal health                   not individually or cumulatively have a                  Therefore, pursuant to § 51.22(b) and
                                                and safety of security force personnel.’’               significant effect on the human                       (c)(25), no environmental impact
                                                Without the exemption, the licensee                     environment. Specifically, the                        statement or environmental assessment
                                                cannot implement changes to its                         exemption is categorically excluded                   need be prepared in connection with the
                                                security plan to authorize a CFH to                     from further analysis under                           approval of this exemption request.
                                                approve the temporary suspension of                     § 51.22(c)(25).                                       IV. Conclusions
                                                security regulations during an                             Under § 51.22(c)(25), the granting of
                                                emergency or severe weather,                            an exemption from the requirements of                   Accordingly, the Commission has
                                                comparable to the authority given to the                any regulation of Chapter I to 10 CFR is              determined that, pursuant to 10 CFR
                                                CFH by the NRC when it published                        a categorical exclusion provided that: (i)            73.5, the exemption is authorized by
                                                § 50.54(y). Instead, the regulations                    There is no significant hazards                       law and will not endanger life or
                                                would continue to require that a                        consideration; (ii) there is no significant           property or the common defense and
                                                licensed senior operator be available to                change in the types or significant                    security, and is otherwise in the public
                                                make decisions for a permanently                        increase in the amounts of any effluents              interest. Therefore, the Commission
                                                shutdown plant, even though JAF                         that may be released offsite; (iii) there is          hereby grants the licensee’s request for
                                                would no longer require a licensed                      no significant increase in individual or              an exemption from the requirements of
                                                senior operator. However, it is unclear                 cumulative public or occupational                     10 CFR 73.55(p)(1)(i) and (ii), which
                                                how the licensee would implement                        radiation exposure; (iv) there is no                  otherwise would require suspension of
                                                emergency or severe weather                             significant construction impact; (v)                  security measures during emergencies
                                                suspensions of security measures                        there is no significant increase in the               and severe weather, respectively, to be
                                                without a licensed senior operator. This                potential for or consequences from                    approved by a licensed senior operator
                                                exemption is in the public interest for                 radiological accidents; and (vi) the                  following permanent cessation of
                                                two reasons. First, without the                         requirements from which an exemption                  operations and permanent removal of
                                                exemption, there is uncertainty on how                  is sought involve: Safeguard plans, and               fuel from the reactor vessel. The
                                                the licensee will invoke temporary                      materials control and accounting                      exemption is effective upon the
                                                suspension of security matters that may                 inventory scheduling requirements; or                 docketing of the certification of
                                                be needed for protecting public health                  involve other requirements of an                      permanent removal of fuel in
                                                and safety or the safety of the security                administrative, managerial, or                        accordance with 10 CFR 50.82(a)(1)(ii).
                                                force during emergencies and severe                     organizational nature.
                                                                                                           The Director, Division of Operating                  Dated at Rockville, Maryland, this 20th day
                                                weather. The exemption would allow
                                                                                                        Reactor Licensing, Office of Nuclear                  of October 2016.
                                                the licensee to make decisions pursuant
                                                to § 73.55(p)(1)(i) and (ii) without                    Reactor Regulation, has determined that                 For the Nuclear Regulatory Commission.
                                                having to maintain a staff of licensed                  approval of the exemption request                     George A. Wilson,
                                                senior operators. The exemption would                   involves no significant hazards                       Deputy Director, Division of Operating
                                                also allow the licensee to have an                      consideration because expanding the                   Reactor Licensing, Office of Nuclear Reactor
                                                established procedure in place to allow                 requirement to allow a CFH to approve                 Regulation.
                                                a trained CFH to suspend security                       the security suspension at a defueled                 [FR Doc. 2016–25989 Filed 10–26–16; 8:45 am]
                                                measures in the event of an emergency                   shutdown power plant does not (1)                     BILLING CODE 7590–01–P
                                                or severe weather. Second, the                          involve a significant increase in the
                                                consistent and efficient regulation of                  probability or consequences of an
                                                nuclear power plants serves the public                  accident previously evaluated; or (2)                 NUCLEAR REGULATORY
                                                interest. This exemption would assure                   create the possibility of a new or                    COMMISSION
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                                                consistency between the security                        different kind of accident from any
                                                regulations in 10 CFR part 73 and the                   accident previously evaluated; or (3)                 [Docket No. 50–182; NRC–2011–0186]
                                                operating reactor regulations in 10 CFR                 involve a significant reduction in a
                                                part 50, and the requirements                           margin of safety. The exempted security               Purdue University Reactor
                                                concerning licensed operators in 10 CFR                 regulation is unrelated to any
                                                part 55. The NRC staff has determined                   operational restriction. Accordingly,                 AGENCY:Nuclear Regulatory
                                                that granting the licensee’s proposed                   there is no significant change in the                 Commission.


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                                                                            Federal Register / Vol. 81, No. 208 / Thursday, October 27, 2016 / Notices                                          74823

                                                ACTION: Environmental assessment and                    DC 20555–0001; telephone: 301–415–                    the NRC is writing a safety evaluation
                                                finding of no significant impact;                       3398; email: Cindy.Montgomery@                        (SE) of the proposed action to issue
                                                issuance.                                               nrc.gov.                                              renewed Facility Operating License No.
                                                                                                        SUPPLEMENTARY INFORMATION:
                                                                                                                                                              R–87 to allow continued operation of
                                                SUMMARY:   The U.S. Nuclear Regulatory                                                                        the PUR–1 for a period of 20 years. The
                                                Commission (NRC) is considering                         I. Introduction                                       details of the NRC’s SE will be provided
                                                renewal of Facility Operating License                                                                         with the renewed license, if approved.
                                                                                                           The NRC is considering issuance of a
                                                No. R–87, held by Purdue University                                                                           This document contains the EA of the
                                                                                                        renewed Facility Operating License No.
                                                (the applicant), for the continued                                                                            proposed action.
                                                                                                        R–87, held by Purdue University, which
                                                operation of the Purdue University                                                                              The applicant has requested a power
                                                                                                        would authorize continued operation of
                                                Reactor (PUR–1), located in West                                                                              increase from 1 kW(t) to 12 kW(t)
                                                                                                        PUR–1, located in West Lafayette,
                                                Lafayette, Tippecanoe County, Indiana                                                                         maximum allowed licensed power. The
                                                                                                        Tippecanoe County, Indiana, for an
                                                for an additional 20 years. In connection                                                                     applicant performed analyses at 18
                                                                                                        additional 20 years. In connection with
                                                with the renewed license, the applicant                                                                       kW(t) to bound the requested power
                                                                                                        the renewed license, the applicant is
                                                is also seeking a power increase from 1                                                                       increase. The applicant’s required
                                                                                                        also seeking a power increase from 1
                                                kilowatt thermal (kW(t)) to a licensed                                                                        annual reports from 2011 through 2015
                                                                                                        kW(t) to 12 kW(t). As required by
                                                power level of 12 kW(t). The NRC is                                                                           indicate that no measurable amount of
                                                                                                        section 51.21 of title 10 of the Code of
                                                issuing an environmental assessment                                                                           radioactive effluent was released from
                                                                                                        Federal Regulations (10 CFR), ‘‘Criteria
                                                (EA) and finding of no significant                                                                            the PUR–1 to the environment.
                                                                                                        for and identification of licensing and
                                                impact (FONSI) associated with the
                                                                                                        regulatory actions requiring                          Facility Site and Environs
                                                renewal of the license.
                                                                                                        environmental assessments,’’ the NRC                     The PUR–1 is a heterogeneous, pool-
                                                DATES: The EA and FONSI referenced in                   performed an EA. Based on the results
                                                this document is available on October                                                                         type non-power reactor that has been in
                                                                                                        of the EA that follows, the NRC has                   operation since 1962 for teaching and
                                                27, 2016.                                               determined not to prepare an                          research purposes. The PUR–1 is
                                                ADDRESSES: Please refer to Docket ID                    environmental impact statement for the                located in the Duncan Annex of the
                                                NRC–2011–0186 when contacting the                       proposed action and is issuing a FONSI.               Electrical Engineering Building on the
                                                NRC about the availability of                                                                                 eastern edge of the Purdue University
                                                information regarding this document.                    II. Environmental Assessment
                                                                                                                                                              campus. The building was originally
                                                You may obtain publicly-available                       Description of the Proposed Action                    designed as a high voltage laboratory,
                                                information related to this document                       The proposed action would renew                    and the space was later converted into
                                                using any of the following methods:                     Facility Operating License No. R–87 for               classrooms, laboratories, and offices.
                                                   • Federal Rulemaking Web site: Go to                                                                       The building is constructed of brick,
                                                                                                        a period of 20 years from the date of
                                                http://www.regulations.gov and search                                                                         concrete block, and reinforced concrete.
                                                                                                        issuance of the renewed license. The
                                                for Docket ID NRC–2011–0186. Address                                                                          Within the Duncan Annex, the PUR–1 is
                                                                                                        proposed action would also authorize a
                                                questions about NRC dockets to Carol                                                                          located within a 6,400-gallon cylindrical
                                                                                                        power increase from 1 kW(t) to 12
                                                Gallagher; telephone: 301–415–3463;                                                                           water tank that is 17 feet deep and 8 feet
                                                                                                        kW(t). The proposed action is in
                                                email: Carol.Gallagher@nrc.gov. For                                                                           in diameter. The tank is enclosed by a
                                                                                                        accordance with Purdue University’s
                                                technical questions, contact the                                                                              concrete shielding structure.
                                                                                                        application dated July 7, 2008, as
                                                individual listed in the FOR FURTHER                                                                             The PUR–1 operates about 90 times
                                                                                                        supplemented by letters dated June 30,
                                                INFORMATION CONTACT section of this                                                                           per year on average. The reactor is
                                                                                                        2008; June 3, and June 4, 2010;
                                                document.                                                                                                     fueled with standard low-enriched
                                                                                                        November 15, 2011; January 4, January
                                                   • NRC’s Agencywide Documents                                                                               uranium plate-type fuel and is cooled by
                                                                                                        30, January 31, June 1, June 15, June 29,
                                                Access and Management System                                                                                  natural convection of light water. The
                                                                                                        July 13, and August 11, 2012; April 10,
                                                (ADAMS): You may obtain publicly-                                                                             reactor coolant system includes a
                                                                                                        2013; July 24, 2015; and January 29,
                                                available documents online in the                                                                             process system, which controls the pool
                                                                                                        February 26, March 31, May 9, July 7,
                                                ADAMS Public Documents collection at                                                                          water temperature, and a purification
                                                                                                        July 19, September 19, and September
                                                http://www.nrc.gov/reading-rm/                                                                                system, which is designed to maintain
                                                                                                        29, 2016 (collectively referred to as ‘‘the
                                                adams.html. To begin the search, select                                                                       pool water quality by limiting corrosion
                                                                                                        renewal application’’). In accordance
                                                ‘‘ADAMS Public Documents’’ and then                                                                           and coolant activation by the use of
                                                                                                        with § 2.109, ‘‘Effect of timely renewal
                                                select ‘‘Begin Web-based ADAMS                                                                                microfilters and ion exchange resins.
                                                                                                        application,’’ the existing license
                                                Search.’’ For problems with ADAMS,                                                                            Water from the pool is drawn out from
                                                                                                        remains in effect until the NRC takes
                                                please contact the NRC’s Public                                                                               the scupper drain or suction line via
                                                                                                        final action on the renewal application.
                                                Document Room (PDR) reference staff at                                                                        polyvinyl chloride piping leading to the
                                                1–800–397–4209, 301–415–4737, or by                     Need for the Proposed Action                          circulating pump; a second source of
                                                email to pdr.resource@nrc.gov. For the                     The proposed action is needed to                   water for the pump is a water supply
                                                convenience of the reader, the ADAMS                    allow the continued operation of the                  tank supplied with city service water
                                                accession numbers are provided in a                     PUR–1, which is used for teaching and                 and controlled by a float valve. Ball
                                                table in the ‘‘Availability of Documents’’              research to support the mission of                    valves for water shutoff and a vacuum
                                                section of this document.                               Purdue University, for a period of 20                 cleaning connection are provided in the
                                                   • NRC’s PDR: You may examine and                     years. Operation of the PUR–1 at the                  pump supply line. From the pump, a
                                                purchase copies of public documents at                                                                        pipe with a ball valve installed leads
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                                                                                                        requested higher power level would
                                                the NRC’s PDR, Room O1–F21, One                         expand the educational and research                   first to the filter and then to a
                                                White Flint North, 11555 Rockville                      uses of the facility.                                 demineralizer. An adjustable by-pass or
                                                Pike, Rockville, Maryland 20852.                                                                              throttling valve is inserted in the system
                                                FOR FURTHER INFORMATION CONTACT:                        Environmental Impacts of the Proposed                 to regulate water flow through the
                                                Cindy K. Montgomery, Office of Nuclear                  Action                                                demineralizer. A flow indicator and a
                                                Reactor Regulation, U.S. Nuclear                          Separate from the environmental                     conductivity indicator are installed as a
                                                Regulatory Commission, Washington,                      assessment referenced in this document,               check on flow rate and water purity


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                                                74824                       Federal Register / Vol. 81, No. 208 / Thursday, October 27, 2016 / Notices

                                                from the demineralizer. The water next                  mSv), assuming a hypothetical 2,000-                  well within the limits set by § 20.1201,
                                                flows through a stainless steel heat                    hour steady state, full power operation,              ‘‘Occupational dose limits for adults,’’
                                                exchanger. The water from the heat                      since the reactor license contains no                 and the ALARA dose criteria in
                                                exchanger is then returned to the reactor               restriction on operating hours. The                   § 20.1101(b). The University is
                                                pool. A magnetrol water-level control is                reactor normally operates for much less               committed to the principle of ALARA
                                                located in the reactor pool; this unit                  than the assumed 8 hours per day and                  and it makes every effort to keep doses
                                                controls a solenoid valve in the line                   the conservatively calculated dose is                 to a minimum. All unanticipated or
                                                from the water supply tank to ensure                    still well below the 5,000-mrem (50                   unusual exposures are investigated.
                                                that the prescribed pool water level is                 mSv) limit established in § 20.1201,                  According to annual reports for the past
                                                maintained. However, this system is                     ‘‘Occupational dose limits for adults.’’              5 years of operation from 2011 through
                                                manually controlled by the PUR–1 staff                  The applicant also calculated, at the                 2015, there were no radiation exposures
                                                to allow markup water to be                             bounding 18 kW(t) power level, an                     greater than 25 percent of limits set
                                                inventoried. Makeup pool water is                       environmental public dose rate from                   forth in § 20.1201. The change in
                                                provided by the city public water                       normal operations to a person in the                  occupational dose from the proposed
                                                supply.                                                 unrestricted area due to Ar-41 released               power uprate from 1 kW(t) to 12 kW(t)
                                                   A detailed description of the reactor                from the building ventilation opening.                is discussed previously in this notice.
                                                can be found in the PUR–1 Safety                        The release point is on the roof vent on                 The applicant monitors dose to the
                                                Analysis Report (SAR) submitted by the                  the top of the building 15 meters above               public by placing thermoluminescent
                                                applicant with its renewal application.                 ground. Assuming a hypothetical                       dosimeters (TLD) at the boundaries of
                                                                                                        continuous steady state, full power                   the facility. The TLDs are checked for
                                                A. Radiological Impacts                                 operation for a year, the applicant                   exposure every other month. Doses
                                                Environmental Effects of Reactor                        calculated the public dose rate to be                 measured from the TLDs at the current
                                                Operations                                              3.17 × 10¥4 mrem/hr (3.17 × 0¥6 mSv/                  operating power level of 1 kW(t) have
                                                                                                        hr) or 2.8 mrem/yr (0.28 mSv/yr), which               been at background levels, therefore, the
                                                   During normal operations at the PUR–
                                                                                                        is well below the limit in § 20.1301 of               applicant concludes that the public has
                                                1 facility, the two primary airborne
                                                                                                        100 mrem/yr (1 mSv/yr). This                          not received exposures greater than the
                                                sources of radiation are argon-41 (Ar-41)
                                                                                                        calculated public dose rate would also                limits set forth in § 20.1301, ‘‘Dose
                                                and nitrogen-16 (N–16). N–16 is
                                                                                                        meet the as low as is reasonably                      limits for individual members of the
                                                produced when oxygen in the pool                                                                              public.’’ As stated previously, this
                                                                                                        achievable (ALARA) dose constraint of
                                                water is irradiated in the reactor core,                                                                      should not change for the proposed
                                                                                                        10 mrem/yr (0.1 mSv/yr) found in
                                                and must then diffuse to the pool                                                                             power increase of 12 kW(t).
                                                                                                        § 20.1101(d).
                                                surface before it is released to the                       Purdue University has a structured                 Additionally, the potential radiation
                                                atmosphere. The applicant estimates                     radiation safety program. Policies for the            dose from current operations at 1kW(t)
                                                that, due to its short half-life (about 7               program are determined by the                         also demonstrates compliance with the
                                                seconds), any N–16 produced by the                      University Radiation Safety Committee,                ALARA dose constraints specified in
                                                reactor at the bounding power level of                  which has the mission to ensure the                   § 20.1101(d), ‘‘Radiation protection
                                                18 kW(t) would decay before reaching                    safety of the University and community                programs.’’ As stated previously, this
                                                the surface of the pool. The primary                    in the utilization of all radioactive                 should not change for the proposed
                                                source of Ar-41 at the PUR–1 is from                    materials and radiation-producing                     power increase of 12 kW(t).
                                                irradiation of air containing argon                     devices at the University by faculty,                    Over the past 5 years of operation
                                                dissolved in the reactor pool. At the                   staff, or students. The program is                    from 2011 through 2015, results from
                                                current 1 kW(t) steady-state operation,                 administered by the Radiation Safety                  the applicant’s survey program indicate
                                                effluent samples in the reactor room                    Officer and his staff, as part of                     that radiation exposures at the current
                                                have not contained detectable traces of                 Radiological and Environmental                        operating power level of 1 kW(t) at the
                                                Ar-41. At the bounding power level of                   Management. The staff is equipped with                monitoring locations were not
                                                18 kW(t), the applicant estimates that                  radiation detection instrumentation to                significantly higher than those
                                                steady-state operation of the reactor                   determine, control, and document                      measured at the control locations. This
                                                would produce an equilibrium                            occupational radiation exposures at the               should not change for the proposed
                                                concentration of 2.08 × 10¥7 mCi/cm3 of                 reactor facility under the broad scope                power increase of 12 kW(t). Therefore,
                                                Ar-41 in the exhaust air and the reactor                byproduct materials license held by                   the NRC concludes that the proposed
                                                room, which is lower than the 3.0 ×                     Purdue University.                                    action would not have a significant
                                                10¥6 mCi/cm3 Derived Air                                   Only very limited contaminated                     radiological impact.
                                                Concentration (DAC) limit for                           materials are generated by PUR–1. Any
                                                occupational workers found in 10 CFR                    contaminated material is disposed of                  Environmental Effects of Accidents
                                                part 20. Due to the DAC being below                     under the Purdue University broad                       The maximum hypothetical accident
                                                regulatory limits, the estimated                        scope license. No wastes have been                    (MHA) is an event involving the
                                                occupational radioactivity exposure                     released to the environment in an                     cladding failure of an irradiated fuel
                                                levels will also be below the 10 CFR                    uncontrolled manner. During the past 5-               element in air. The MHA is considered
                                                part 20 limit of 5 reontgen equivalent                  year period from 2011 through 2015, the               the worst-case fuel failure scenario for
                                                man (rem). The estimated dose rate to a                 applicant reported no routine releases of             PUR–1 that would lead to the maximum
                                                worker at the bounding power level of                   liquid radioactive waste by any disposal              potential radiation hazard to facility
                                                18 kW(t) was calculated by the
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                                                                                                        method. The NRC assumes that any                      personnel and to members of the public.
                                                applicant to be 0.167 milli roentgen                    changes due to the requested power                    The results of the MHA are used by the
                                                equivalent man per hour (mrem/hr)                       increase from 1 kW(t) to 12 kW(t) are                 NRC to evaluate the ability of the
                                                (0.00167 millisievert/hour (mSv/hr)).                   expected to be minimal and capable of                 applicant to respond and mitigate the
                                                Using the calculated dose rate, the total               being handled by the existing systems                 consequences of this postulated
                                                effective dose equivalent to a worker in                and procedures.                                       radioactive release.
                                                the reactor room for an entire year                        As described in Chapter 11 of the                    The applicant conservatively
                                                would be less than 334 mrem (3.34                       PUR–1 SAR, personnel exposures are                    calculated doses to facility personnel


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                                                                            Federal Register / Vol. 81, No. 208 / Thursday, October 27, 2016 / Notices                                           74825

                                                during evacuation and the maximum                       information contained in the renewal                  does not provide suitable habitat for
                                                potential doses to members of the public                application and data reported to the                  Federally-listed species. Additionally,
                                                at various locations around the PUR–1                   NRC by the applicant for the last 5 years             operation of PUR–1 has no direct nexus
                                                facility. The license estimated an                      of operation to determine the projected               to the natural environment that would
                                                occupational dose of 317 mrem (3.17                     radiological impact of the facility on the            affect Federally-listed species.
                                                mSv), for a one minute (evacuation)                     environment during the period of the                  Accordingly, the NRC concludes that
                                                duration, and 47 mrem (0.47 mSv) for                    renewed license. The NRC found that                   the proposed license renewal of the
                                                the maximum exposed member of the                       releases of radioactive material and                  PUR–1 would have no effect on
                                                public. The NRC performed                               personnel exposures were all well                     Federally-listed species or critical
                                                independent calculations to verify that                 within applicable regulatory limits.                  habitats. Federal agencies are not
                                                the applicant’s calculated doses                        Based on this evaluation, the NRC
                                                                                                                                                              required to consult with the FWS if they
                                                represented conservative estimates for                  concludes that the proposed action
                                                the MHA. The NRC, using conservative                    would not have a significant                          determine that an action will not affect
                                                assumptions, estimated a dose to a                      environmental impact.                                 listed species or critical habitats
                                                worker of 294 mrem (2.94 mSv) for a                                                                           (ADAMS Accession No. ML16120A505).
                                                                                                        B. Non-Radiological Impacts                           Thus, the ESA does not require
                                                one minute duration, and 4 mrem (0.04
                                                mSv) for the maximum exposed member                        The proposed action would not result               consultation for the proposed PUR–1
                                                of the public. The details of these                     in any land use changes, visual resource              license renewal and proposed power
                                                calculations are provided in the NRC’s                  impacts, or increases in noise. No                    uprate, and the NRC considers its
                                                SER that will be issued with the                        significant changes in air emissions                  obligations under ESA section 7 to be
                                                renewed license. The occupational                       would occur as a result of the proposed               fulfilled for the proposed action.
                                                radiation doses resulting from the                      license renewal and power increase.
                                                postulated MHA would be well below                      Because water is supplied through the                 Costal Zone Management Act
                                                the 10 CFR 20.1201 limit of 5,000 mrem                  city, the proposed action would not
                                                                                                                                                                Tippecanoe County, Indiana does not
                                                (50 mSv). The maximum calculated                        affect surface water or groundwater
                                                                                                                                                              contain any coastal zones. Because the
                                                radiation doses for members of the                      resources. There is no potential for the
                                                                                                                                                              PUR–1 is not located within or near any
                                                public resulting from the postulated                    proposed action to affect aquatic or
                                                                                                        terrestrial resources. Therefore, the NRC             managed coastal zones, the proposed
                                                MHA would be below the 10 CFR
                                                                                                        concludes that the proposed action                    action would not affect any coastal
                                                20.1301 limit of 100 mrem (1 mSv).
                                                   Because the NRC concludes in the SE                  would have no significant non-                        zones and Coastal Zone Management
                                                that the radiological consequences of                   radiological impacts.                                 Act consistency certification does not
                                                the MHA are within the NRC’s 10 CFR                                                                           apply.
                                                                                                        Other Applicable Environmental Laws
                                                part 20 dose limits, the proposed action                                                                      National Historic Preservation Act
                                                will not have a significant impact with                   In addition to the National
                                                respect to the radiological consequences                Environmental Policy Act (NEPA), the                    The NHPA requires Federal agencies
                                                of the MHA.                                             NRC has responsibilities that are                     to consider the effects of their
                                                                                                        derived from other environmental laws,                undertakings on historic properties. As
                                                Conclusions—Radiological Impacts                        which include the Endangered Species                  stated in the Act, historic properties are
                                                   As discussed previously in this                      Act (ESA), Coastal Zone Management                    any prehistoric or historic district, site,
                                                notice, the applicant has requested a                   Act, National Historic Preservation Act               building, structure, or object included
                                                power increase from 1kW to 12 kW                        (NHPA), Fish and Wildlife Coordination
                                                                                                                                                              in, or eligible for inclusion in the
                                                maximum allowed licensed power. In                      Act, and Executive Order 12898
                                                addition, as previously described, while                                                                      National Register of Historic Places
                                                                                                        Environmental Justice. Preparing this
                                                there is a potential increase in routine                EA satisfies the agency’s obligations                 (NRHP). The NRHP lists several historic
                                                occupational and public radiation                       under NEPA. The following presents a                  districts and properties within 0.5 miles
                                                exposure as a result of license renewal                 brief discussion of impacts associated                of PUR–1 in the Duncan Annex of the
                                                at the higher power level, all exposure                 with resources protected by these laws.               Electrical Engineering Building on the
                                                rates and doses would be within                                                                               campus of Purdue University. Operation
                                                regulatory limits. There would be no                    Endangered Species Act                                of PUR–1 has not likely had any impact
                                                changes in the types of effluents that                    The NRC staff conducted a search of                 on these districts and properties. Based
                                                may be released off site, and any                       Federally listed species and critical                 on this information, the NRC staff finds
                                                potential increase in their quantities                  habitats that have the potential to occur             that the potential impacts of license
                                                would be within regulatory limits. The                  in the vicinity of the PUR–1 using the                renewal and the continued operation of
                                                applicant has systems in place for                      U.S. Fish and Wildlife Service’s (FWS)                PUR–1 would have no adverse effect on
                                                controlling the release of radiological                 Environmental Conservation Online                     historic properties located near PUR–1.
                                                effluents and implements a radiation                    System Information for Planning and
                                                protection program to monitor                           Conservation (IPaC) system. Five                      Fish and Wildlife Coordination Act
                                                personnel exposures and releases of                     Federally-listed mussels—clubshell
                                                                                                                                                                 The proposed action does not involve
                                                radioactive effluents, and the systems                  (Pleurobema clava), fanshell
                                                and radiation protection program are                    (Cyprogenia stegaria), snuffbox                       any water resource development
                                                appropriate for the types and quantities                (Epioblasma triquetra), rabbitsfoot                   projects, including any of the
                                                of effluents expected to be generated by                (Quadrula cylindrical cylindrical), and               modifications relating to impounding a
sradovich on DSK3GMQ082PROD with NOTICES




                                                continued operation of the reactor. The                 sheepnose (Plethobasus cyphus)—and                    body of water, damming, diverting a
                                                proposed action will not significantly                  the Indiana bat (Myotis sodalis) occur in             stream or river, deepening a channel,
                                                increase the probability or consequences                Tippecanoe County. However, none of                   irrigation, or altering a body of water for
                                                of accidents. Therefore, license renewal                these species are likely to occur near the            navigation or drainage. Therefore, no
                                                and the proposed power increase would                   PUR–1 because the facility is located on              coordination with FWS pursuant to the
                                                not change the environmental impact of                  the Purdue University Campus, which                   Fish and Wildlife Coordination Act is
                                                facility operation. The NRC evaluated                   has been developed since the 1960s and                required for the proposed action.


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                                                74826                                 Federal Register / Vol. 81, No. 208 / Thursday, October 27, 2016 / Notices

                                                Executive Order 12898—Environmental                                         families and 15.2 percent of the state                                       similar. In addition, denying the request
                                                Justice                                                                     population were found to be living                                           for license renewal would eliminate the
                                                  The environmental justice impact                                          below the Federal poverty threshold.                                         benefits of teaching, research, and
                                                analysis evaluates the potential for                                        Tippecanoe County had a lower median                                         services provided by the PUR–1 facility.
                                                disproportionately high and adverse                                         household income average ($45,771)
                                                                                                                                                                                                         Alternative Use of Resources
                                                human health and environmental effects                                      and a higher percent of families and
                                                on minority and low-income                                                  people living below the poverty level                                          The proposed action does not involve
                                                populations that could result from the                                      (12.2 and 23.6 percent, respectively).                                       the use of any different resources or
                                                relicensing and the continued operation                                        Impact Analysis. Potential impacts to                                     significant quantities of resources
                                                of PUR–1. Such effects may include                                          minority and low-income populations                                          beyond those previously considered in
                                                human health, biological, cultural,                                         would mostly consist of radiological                                         the issuance of Facility Operating
                                                economic, or social impacts.                                                effects, however, radiation doses from                                       License No. R–87 for the PUR–1 in
                                                  Minority Populations in the Vicinity                                      continued operations associated with                                         August 1988, which renewed the
                                                of PUR–1. According to U.S. Census                                          the license renewal and the proposed                                         Facility Operating License for a period
                                                Bureau’s 2010 Census, approximately 21                                      power increase are expected to continue                                      of 20 years.
                                                percent of the total population                                             at current levels, and would be well
                                                                                                                            below regulatory limits.                                                     Agencies and Persons Consulted
                                                (approximately 164,000 individuals)
                                                residing within a 10-mile radius of                                            Based on this information and the                                           The NRC did not enter into
                                                PUR–1 identified themselves as                                              analysis of human health and                                                 consultation with any other Federal
                                                minorities. The largest minority                                            environmental impacts presented in this                                      agencies or with the State of Indiana
                                                population were Hispanic, Latino, or                                        EA, the proposed action would not have                                       regarding the environmental impact of
                                                Spanish origin of any race at                                               disproportionately high and adverse                                          the proposed action. However, on
                                                (approximately 12,800 or 8 percent),                                        human health and environmental effects                                       October 21, 2016, the NRC notified the
                                                followed by Asian (approximately                                            on minority and low-income                                                   Indiana State official, Ms. Laura Dresen,
                                                10,700 persons or 7 percent). According                                     populations residing in the vicinity of                                      Radiation Programs Director, of the
                                                to the 2010 Census, about 20 percent of                                     PUR–1.                                                                       Indiana Department of Homeland
                                                the Tippecanoe County population                                            Environmental Impacts of the                                                 Security of the proposed action. The
                                                identified themselves as minorities,                                        Alternatives to the Proposed Action                                          State official had no comments.
                                                with persons of Hispanic, Latino, or
                                                Spanish origin and Asians comprising                                           As an alternative to license renewal,                                     III. Finding of No Significant Impact
                                                the largest minority populations                                            the NRC considered denying the
                                                                                                                            proposed action (i.e., the ‘‘no-action’’                                        The NRC is considering issuance of a
                                                (approximately 8 and 7 percent,                                                                                                                          renewed Facility Operating License No.
                                                respectively). According to the U.S.                                        alternative). If the NRC denied the
                                                                                                                            request for license renewal, reactor                                         R–87, held by Purdue University, which
                                                Census Bureau’s 2014 American                                                                                                                            would authorize the continued
                                                Community Survey 1-year Estimates,                                          operations would cease and
                                                                                                                            decommissioning would be required.                                           operation of PUR–1 for an additional 20
                                                the minority population of Tippecanoe                                                                                                                    years.
                                                County, as a percent of the total                                           The NRC notes that, even with a
                                                population, had increased to about 22                                       renewed license, PUR–1 will eventually                                          On the basis of the EA included in
                                                percent.                                                                    be decommissioned, at which time the                                         Section II of this notice and
                                                  Low-income Populations in the                                             environmental effects of                                                     incorporated by reference in this
                                                Vicinity of PUR–1. According to the U.S.                                    decommissioning would occur.                                                 finding, the NRC concludes that the
                                                Census Bureau’s 2010–2014 American                                          Decommissioning would be conducted                                           proposed action would not have
                                                Community Survey 5-Year Estimates,                                          in accordance with an NRC-approved                                           significant effects on the quality of the
                                                approximately 36,000 persons and 4,000                                      decommissioning plan, which would                                            human environment. Section IV lists the
                                                families (approximately 22.7 and 11.7                                       require a separate environmental review                                      environmental documents related to the
                                                percent, respectively) residing within a                                    under § 51.21. Cessation of reactor                                          proposed action and includes
                                                10-mile radius of PUR–1 were identified                                     operations would reduce or eliminate                                         information on the availability of these
                                                as living below the Federal poverty                                         radioactive effluents. However, as                                           documents. Based on its findings, the
                                                threshold. The 2014 Federal poverty                                         previously discussed in this EA,                                             NRC has decided not to prepare an
                                                threshold was $24,230 for a family of                                       radioactive effluents from reactor                                           environmental impact statement for the
                                                four.                                                                       operations constitute a small fraction of                                    proposed action.
                                                  According to the U.S. Census                                              the applicable regulatory limits.                                            IV. Availability of Documents
                                                Bureau’s 2014 American Community                                            Therefore, the environmental impacts of
                                                Survey Census 1-Year Estimates, the                                         license renewal, including the proposed                                        The documents identified in the
                                                median household income for Indiana                                         power uprate, and the denial of the                                          following tables are available to
                                                was $49,446, while 11 percent of                                            request for license renewal would be                                         interested persons as indicated.

                                                                                                                                                                                                                                                              ADAMS
                                                                                                                                           Document                                                                                                        accession No.

                                                Purdue University, School of Nuclear Engineering. Application for relicense of License Number R–87 with Power Uprate, July 7,
                                                  2008 .................................................................................................................................................................................................   ML083040443
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                                                Purdue University Safety Analysis Report, June 30, 2008 [Redacted Version] .................................................................................                                               ML111890201
                                                Purdue University—Request for Additional Information (RAI) Regarding License Renewal, [Decommissioning Funding Statement
                                                  of Intent], June 3, 2010 ....................................................................................................................................................................            ML101620125
                                                Purdue University—Request For Additional Information Regarding the Purdue University Reactor License Renewal (Tac No. Me
                                                  1594), Responses to RAIs Dated 24 March 2010, [Responses To ML100820019, financial assurance, statement of intent, sig-
                                                  nature authority, financial report], June 4, 2010 ..............................................................................................................................                         ML101620184
                                                Response to Request for Additional Information Regarding the Purdue University Reactor License Renewal (TAC ME1594), Re-
                                                  sponse to RAIs Dated 6 July 2011 (ML101460429), November 15, 2011 .....................................................................................                                                  ML11320A287



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                                                                                      Federal Register / Vol. 81, No. 208 / Thursday, October 27, 2016 / Notices                                                                                                74827

                                                                                                                                                                                                                                                              ADAMS
                                                                                                                                            Document                                                                                                       accession No.

                                                Purdue University—Request for Additional Information Regarding the License Renewal, Responses to RAIs Dated 6 July 2011,
                                                  [Responses 11, 12, 13, 15, 16, 18, 21, 23, 25, 27, 28, 30, 31, 33, 35, 36, and 37], January 4, 2012 .........................................                                                            ML12006A193
                                                Purdue University—Responses to the Request for Additional Information Regarding the Purdue University Reactor License Re-
                                                  newal dated July 6, 2011, [Responses 3, 4, 7, 10, 17, 19, 20, 22, 24, 29, 34, and 40], January 30, 2012 ..................................                                                               ML12031A223
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal (TAC NO.
                                                  ME 1594), Responses to RAIS (ML103400115 and ML103400250) (Redacted Version), [Responses 45, 55, 62, 65, 66, 67,
                                                  68, 70, and 73], January 31, 2012 ..................................................................................................................................................                     ML14234A109
                                                Request for Additional Information Regarding the Purdue University Reactor License Renewal (TAC ME1594), Responses to
                                                  RAIs (ML103400115 and ML103400250), [Responses 43, 51, 56, 60, and 61], June 1, 2012 .....................................................                                                               ML12156A364
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal (TAC No.
                                                  ME1594), Responses to RAIs (ML103400115 and ML103400250), [Response 46, 47, 52, 57, and 59], June 15, 2012 ............                                                                                  ML12170B018
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal, Responses
                                                  to RAIs (ML103400115 and ML103400250), [Response 48, 58, 96, 97 and 98], June 29, 2012 .................................................                                                                 ML12170B018
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal, Response to
                                                  RAI, [Response 49, 50, 53, 64, and 72], July 13, 2012 ..................................................................................................................                                 ML12201A070
                                                Purdue University—Response to Request for Additional Information Regarding Purdue University Reactor License Renewal
                                                  (TAC No. ME1594, Responses to RAIs (ML103400115 and ML103400250), [Responses 54, 69, 77, 78, and 92], August 11,
                                                  2012 .................................................................................................................................................................................................   ML12226A400
                                                Purdue University—Response to Request Request for Additional Information Regarding the Purdue University Reactor License
                                                  Renewal (TAC ME1594), [Responses 54, 69, 77, 78, and 92], April 10, 2013 ..............................................................................                                                  ML13101A044
                                                U.S. Fish and Wildlife Service, Endangered Species Consultations Frequently Asked Questions, July 15, 2013 ...........................                                                                     ML16120A505
                                                Purdue University Research Reactor, Report on Reactor Operations For the Period January 1, 2011 to December 31, 2011,
                                                  July 18, 2013 ....................................................................................................................................................................................       ML13203A081
                                                Purdue University Research Reactor, Report on Reactor Operations For the Period January 1, 2012 to December 31, 2012,
                                                  July 18, 2013 ....................................................................................................................................................................................       ML13203A082
                                                Purdue University Research Reactor, Report on Reactor Operations For the Period January 1, 2013 to December 31, 2013,
                                                  May 22, 2014 ...................................................................................................................................................................................         ML14154A123
                                                Purdue University Research Reactor, Report on Reactor Operations For the Period January 1, 2014 to December 31, 2014,
                                                  March 30, 2015 ................................................................................................................................................................................          ML15092A160
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal Application
                                                  (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221), [RAI cover letter for responses to August
                                                  29, 2015 NRC letter], July 24, 2015 ................................................................................................................................................                     ML15210A280
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal Application
                                                  (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221), Part 1 of 5, [RAI Responses part 1 of 5:
                                                  responses (1–29), TS (30–64), d/c cost estimate (65–68), Requal (69–73), SAR Chs. 1–5 (70–162)], July 24, 2015 ................                                                                          ML15210A282
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal Application
                                                  (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221), Part 2 of 5, [RAI Responses part 2 of 5
                                                  (SAR Chs. 6–15)], July 24, 2015 .....................................................................................................................................................                    ML15210A283
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal Application
                                                  (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221), Part 3 of 5, [RAI Responses Part 3 of 5
                                                  (drawings)], July 24, 2015 ................................................................................................................................................................              ML15210A285
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal Application
                                                  (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221), Part 4 of 5, [RAI Responses Part 4 of 5
                                                  (drawings)], July 24, 2015 ................................................................................................................................................................              ML15210A287
                                                Purdue University—Request for Additional Information Regarding the Purdue University Reactor License Renewal Application
                                                  (TAC No. ME1594), Responses to Letter Dated August 29, 2014 (ML14115A221), Part 5 of 5, [RAI Responses part 5 of 5
                                                  (NATCON, Procedures, Drawings)], July 24, 2015 .........................................................................................................................                                 ML15210A288
                                                Purdue University—Response to NRC Request for Additional Information Regarding Physical Security Plan Review for License
                                                  Renewal, January 29, 2016 .............................................................................................................................................................                  ML16047A382
                                                Purdue University—Re-Submittal Response to NRC Request for Additional Information Regarding Physical Security Plan Re-
                                                  view for License Renewal, February 26, 2016 ................................................................................................................................                             ML16083A219
                                                Purdue Re-Submittal of Response to NRC Request for Additional Information Re: Physical Security Plan Review for License
                                                  Renewal, March 31, 2016 ................................................................................................................................................................                 ML16102A123
                                                Purdue University Research Reactor, Report on Reactor Operations For the Period January 1, 2015 to December 31, 2015,
                                                  March 31, 2016 ................................................................................................................................................................................          ML16102A119
                                                Purdue University—Second Re-Submittal of Response to NRC Request for Additional Information Regarding Physical Security
                                                  Plan Review for License Renewal, May 9, 2016 .............................................................................................................................                               ML16134A143
                                                Purdue University School of Nuclear Engineering Notice of ADAMS Document Correction, PUR–1, Docket 50–182,
                                                  ML16187A371, Technical Specifications, Proposed Amendment 13 Enclosed, [Correction of the TSs, originally submitted
                                                  under ML16187A371], July 7, 2016 .................................................................................................................................................                       ML16193A681
                                                Purdue University Responses to Request for Additional Information re PUR–1 License Renewal and Power Uprate, [Responses
                                                  to RAIs ML15328A314], July 19, 2016 ............................................................................................................................................                         ML16207A426
                                                Purdue University—Response to Request for Additional Information Regarding the Reactor License Renewal Application, Re-
                                                  sponses to Letter dated July 25, 2016, September 19, 2016 .........................................................................................................                                      ML16267A465
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                                                Purdue University—Explanation of Technical Specification Changes and Emergency Operator Action, September 29, 2016 ........                                                                                ML16277A165




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                                                74828                       Federal Register / Vol. 81, No. 208 / Thursday, October 27, 2016 / Notices

                                                   Dated at Rockville, Maryland, this 21st day             • NRC’s Agencywide Documents                       a hearing was published in the Federal
                                                October, 2016.                                          Access and Management System                          Register on February 3, 2015 (80 FR
                                                   For the Nuclear Regulatory Commission.               (ADAMS): You may obtain publicly-                     5822).
                                                Alexander Adams, Jr.,                                   available documents online in the                        The NRC’s FSEIS, NUREG–1437,
                                                Chief, Research and Test Reactors Branch,               ADAMS Public Documents collection at                  Supplement 57, ‘‘Generic
                                                Division of Policy and Rulemaking, Office               http://www.nrc.gov/reading-rm/                        Environmental Impact Statement for
                                                of Nuclear Reactor Regulation.                          adams.html. To begin the search, select               License Renewal of Nuclear Plants
                                                [FR Doc. 2016–25993 Filed 10–26–16; 8:45 am]            ‘‘ADAMS Public Documents’’ and then                   Regarding LaSalle County Station, Units
                                                BILLING CODE 7590–01–P                                  select ‘‘Begin Web-based ADAMS                        1 and 2,’’ and ROD that support the
                                                                                                        Search.’’ For problems with ADAMS,                    NRC’s issuance of renewed facility
                                                                                                        please contact the NRC’s Public                       operating license Nos. NPF–11 and
                                                NUCLEAR REGULATORY                                      Document Room (PDR) reference staff at                NPF–18 are available in ADAMS under
                                                COMMISSION                                              1–800–397–4209, 301–415–4737, or by                   Accession Nos. ML16264A222 and
                                                [Docket Nos. 50–373 and 50–374; NRC–                    email to pdr.resource@nrc.gov. The                    ML16238A029, respectively. As
                                                2014–0268]                                              ADAMS accession number for each                       discussed in the FSEIS and ROD, the
                                                                                                        document referenced (if it is available in            NRC considered a range of reasonable
                                                Exelon Generation Company, LLC.;                        ADAMS) is provided the first time that                alternatives to the issuance of the
                                                LaSalle County Station, Units 1 and 2;                  it is mentioned in this document.                     renewed licenses that included new
                                                License Renewal                                            • NRC’s PDR: You may examine and                   nuclear power generation, coal-
                                                AGENCY:  Nuclear Regulatory                             purchase copies of public documents at                integrated gasification combined-cycle,
                                                Commission.                                             the NRC’s PDR, Room O1–F21, One                       natural gas combined-cycle (NGCC), a
                                                                                                        White Flint North, 11555 Rockville                    combination of wind, solar, and NGCC,
                                                ACTION: License renewal and record of
                                                                                                        Pike, Rockville, Maryland 20852.                      purchased power, and the no-action
                                                decision; issuance.
                                                                                                        FOR FURTHER INFORMATION CONTACT:                      alternative. The FSEIS and ROD
                                                SUMMARY:   The U.S. Nuclear Regulatory                  Jeffrey Mitchell, Office of Nuclear                   document the NRC’s decision with
                                                Commission (NRC) has issued renewed                     Reactor Regulation, U.S. Nuclear                      respect to its environmental review that
                                                facility operating license Nos. NPF–11                  Regulatory Commission, Washington,                    the adverse environmental impacts of
                                                and NPF–18 to Exelon Generation                         DC 20555–0001; telephone: 301–415–                    issuing the renewed licenses are not so
                                                Company, LLC (Exelon or the licensee),                  3019; email: Jeffrey.Mitchell2@nrc.gov.               great that preserving the option of
                                                the operator of LaSalle County Station,                 SUPPLEMENTARY INFORMATION: Notice is                  license renewal for energy-planning
                                                Units 1 and 2. Renewed facility                         hereby given that the NRC has issued                  decisionmakers would be unreasonable.
                                                operating license Nos. NPF–11 and                       renewed facility operating license Nos.                  For further details with respect to this
                                                NPF–18 authorize the operation of                       NPF–11 and NPF–18 to Exelon                           action, see: (1) The Exelon Generation
                                                LaSalle County Station, Units 1 and 2 by                Generation Company, LLC, the operator                 Company, LLC license renewal
                                                the licensee at reactor core power levels               of LaSalle County Station, Units 1 and                application for LaSalle County Station,
                                                not in excess of 3546 megawatts thermal                 2. Renewed facility operating license                 Units 1 and 2, dated December 9, 2014,
                                                in accordance with the provisions of the                Nos. NPF–11 and NPF–18 authorize the                  as supplemented by letters dated
                                                renewed licenses and technical                          operation of LaSalle County Station,                  through June 8, 2016; (2) the NRC safety
                                                specifications until April 17, 2042 and                 Units 1 and 2 by the licensee at reactor              evaluation report dated September 2016
                                                December 16, 2043, respectively. The                    core power levels not in excess of 3546               (ADAMS Accession No. ML16271A039);
                                                NRC prepared a safety evaluation report,                megawatts thermal in accordance with                  (3) the NRC FSEIS dated August 2016;
                                                a final supplemental environmental                      the provisions of the renewed licenses                and (4) the NRC ROD dated October
                                                impact statement (FSEIS), and a record                  and technical specifications until April              2016.
                                                of decision (ROD) that support its                      17, 2042 and December 16, 2043,                         Dated at Rockville, Maryland, this 19th day
                                                decision to issue renewed facility                      respectively.                                         of October, 2016.
                                                operating license Nos. NPF–11 and                          LaSalle County Station, Units 1 and 2,               For the Nuclear Regulatory Commission.
                                                NPF–18.                                                 are boiling-water reactors located in                 Jane E. Marshall,
                                                DATES: Renewed facility operating                       Brookfield Township, LaSalle County,                  Acting Director, Division of License Renewal,
                                                license Nos. NPF–11 and NPF–18 were                     Illinois. The NRC determined that the                 Office of Nuclear Reactor Regulation.
                                                issued and effective on October 19,                     application for the renewed licenses,                 [FR Doc. 2016–25988 Filed 10–26–16; 8:45 am]
                                                2016.                                                   ‘‘License Renewal Application, LaSalle                BILLING CODE 7590–01–P
                                                ADDRESSES: Please refer to Docket ID                    County Station, Units 1 and 2, Facility
                                                NRC–2014–0268 when contacting the                       Operating License Nos. NPF–11 and
                                                NRC about the availability of                           NPF–18,’’ dated December 9, 2014                      SECURITIES AND EXCHANGE
                                                information regarding this document.                    (ADAMS Accession No. ML14343A849),                    COMMISSION
                                                You may obtain publicly-available                       as supplemented by letters dated
                                                                                                        through June 8, 2016, complied with the               [Release No. 34–79133; File No. SR–CBOE–
                                                information related to this document
                                                                                                                                                              2016–071]
                                                using any of the following methods:                     standards and requirements of the
                                                   • Federal Rulemaking Web site: Go to                 Atomic Energy Act of 1954, as amended                 Self-Regulatory Organizations;
                                                http://www.regulations.gov and search                   (the Act), and the NRC’s regulations set              Chicago Board Options Exchange,
                                                for Docket ID NRC–2014–0268. Address                    forth in Chapter I of title 10 of the Code
sradovich on DSK3GMQ082PROD with NOTICES




                                                                                                                                                              Incorporated; Notice of Filing of a
                                                questions about NRC dockets to Carol                    of Federal Regulations (10 CFR). As                   Proposed Rule Change Relating to
                                                Gallagher; telephone: 301–415–3463;                     required by the Act and the NRC’s                     Opening and Closing Rotations Under
                                                email: Carol.Gallagher@nrc.gov. For                     regulations, the NRC has made the                     the HOSS System
                                                technical questions, contact the                        appropriate findings, which are set forth
                                                individual listed in the FOR FURTHER                    in the renewed licenses. A public notice              October 21, 2016.
                                                INFORMATION CONTACT section of this                     of the proposed issuance of the renewed                 Pursuant to Section 19(b)(1) of the
                                                document.                                               licenses and an opportunity to request                Securities Exchange Act of 1934


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Document Created: 2016-10-27 01:52:58
Document Modified: 2016-10-27 01:52:58
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionNotices
ActionEnvironmental assessment and finding of no significant impact; issuance.
DatesThe EA and FONSI referenced in this document is available on October 27, 2016.
ContactCindy K. Montgomery, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-3398; email: [email protected]
FR Citation81 FR 74822 

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