37532 Federal Register / Vol. 83, No. 148 / Wednesday, August 1, 2018 / Notices 

conference call was held between the 

Ohio SHPO, the ACHP, and the NRC to 

discuss the concerns expressed in the 

SHPO’s May 16, 2018, letter. During the 

call the ACHP expressed its agreement 

with the NRC that the requested action 

falls under 36 CFR 800.3(a)(1), No 

potential to cause effects, which states, 

‘‘If the undertaking is a type of activity 

that does not have the potential to cause 

effects on historic properties, assuming 

such properties were present, the 

agency official has no further 

obligations under Section 106 or this 

part’’. The NRC sent a letter, dated July 

16, 2018, to the Ohio SHPO 

summarizing the conference call and 

concluding Section 106 consultation 

(ADAMS Accession Number 

ML18171A218). By letter dated April 

11, 2018, the NRC initiated Section 106 

consultation under the National Historic 

Preservation Act with the Osage Nation. 

In their reply, the Osage Nation stated 

it concurred with the NRC 

determination that the proposed DP 

most likely would not adversely affect 

any sacred properties and/or properties 

of cultural significance to the Nation, 

and also stated, ‘‘[t]he Osage Nation has 

no further concern with this project’’ 

(ADAMS Accession Number 

ML18158A263). 

III. Finding of No Significant Impact 

In accordance with the requirements 

in 10 CFR part 51, the NRC staff has 

concluded that the proposed action will 

not significantly affect the quality of the 

human environment. Therefore, the staff 

finds, pursuant to 10 CFR 51.31, that 

preparation of an environmental impact 

statement is not required for the 

proposed action, and that a finding of 

no significant impact is appropriate. 

Dated at Rockville, Maryland, this 26th day 

of July 2018. 

For the Nuclear Regulatory Commission. 

Craig G. Erlanger, 

Director, Division of Fuel Cycle Safety, 

Safeguards, and Environmental Review, 

Office of Nuclear Material Safety, and 

Safeguards. 

[FR Doc. 2018–16404 Filed 7–31–18; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–409; NRC–2018–0157] 

LaCrosse Solutions, LLC; Dairyland 

Power Cooperative La Crosse Boiling 

Water Reactor 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Exemption; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing an 

exemption in response to a February 22, 

2018, request from LaCrosseSolutions, 

LLC (LS) from the regulatory 

requirement to maintain a specified 

level of onsite property damage 

insurance to permit the La Crosse 

Boiling Water Reactor (LACBWR) to 

reduce its onsite insurance coverage 

from $180 million to $50 million. 

DATES: The exemption was issued on 

July 24, 2018. 

ADDRESSES: Please refer to Docket ID 

NRC–2018–0157 when contacting the 

NRC about the availability of 

information regarding this document. 

You may obtain publicly-available 

information related to this document 

using any of the following methods: 

• Federal Rulemaking Website: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2018–0157. Address 

questions about NRC dockets to Jennifer 

Borges; telephone: 301–287–9127; 

email: Jennifer.Borges@nrc.gov. For 

technical questions, contact the 

individual listed in the FOR FURTHER

INFORMATION CONTACT section of this 

document. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may obtain publicly 

available documents online in the 

ADAMS Public Documents collection at 

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 pdr.resource@nrc.gov. The 

ADAMS accession number for each 

document referenced (if it is available in 

ADAMS) is provided the first time that 

it is mentioned in this document. 

• 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: 

Marlayna G. Vaaler, Office of Nuclear 

Material Safety and Safeguards, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001; telephone: 

301–415–3178, email: 

Marlayna.Vaaler@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Background 

The La Crosse Boiling Water Reactor 

was an Atomic Energy Commission 

(AEC) Demonstration Project Reactor 

that first went critical in 1967, 

commenced commercial operation in 

November 1969, and was capable of 

producing 50 megawatts of electric 

power. The LACBWR site is located on 

the east bank of the Mississippi River in 

Vernon County, Wisconsin, and is colocated with the Genoa Generating 

Station, which is a coal-fired electrical 

power plant that is still in operation. 

The Allis-Chalmers Company was the 

original licensee; the AEC later sold the 

plant to the Dairyland Power 

Cooperative (DPC) and granted it 

Provisional Operating License No. DPR– 

45 on August 28, 1973 (ADAMS 

Accession No. ML17080A423). 

The LACBWR permanently ceased 

operations on April 30, 1987 (ADAMS 

Accession No. ML17080A422), and 

reactor defueling was completed on 

June 11, 1987 (ADAMS Accession No. 

ML17080A420). In a letter dated August 

4, 1987 (ADAMS Accession No. 

ML17080A393), the NRC terminated 

DPC’s authority to operate LACBWR 

under Provisional Operating License 

No. DPR–45, and granted the licensee a 

possess-but-not-operate status. By letter 

dated August 18, 1988 (ADAMS 

Accession No. ML17080A421), the NRC 

amended DPC’s Provisional Operating 

License No. DPR–45 to Possession Only 

License No. DPR–45 to reflect the 

permanently defueled configuration at 

LACBWR. 

The NRC issued an order to authorize 

decommissioning of LACBWR and 

approve the licensee’s proposed 

Decommissioning Plan (DP) on August 

7, 1991 (ADAMS Accession No. 

ML17080A454). Because the NRC 

approved DPC’s DP before August 28, 

1996, pursuant to section 50.82 of title 

10 of the Code of Federal Regulations 

(10 CFR), the DP is considered the PostShutdown Decommissioning Activities 

Report (PSDAR) for LACBWR. The 

PSDAR public meeting was held on May 

13, 1998, and subsequent updates to the 

LACBWR decommissioning report have 

combined the DP and PSDAR into the 

‘‘LACBWR Decommissioning Plan and 

Post-Shutdown Decommissioning 

Activities Report’’ (D-Plan/PSDAR). 

This document is also considered the 

Final Safety Analysis Report (FSAR) for 

LACBWR and is updated every 24 

months in accordance with 10 CFR 

50.71(e). The DPC constructed an onsite 

Independent Spent Fuel Storage 

Installation (ISFSI) under its 10 CFR 

part 72 general license, and completed 

the movement of all 333 spent nuclear 

fuel elements from the Fuel Element 

Storage Well to dry cask storage at the 

ISFSI by September 19, 2012 (ADAMS 

Accession No. ML12290A027). The 

remaining associated buildings and 

structures are currently undergoing 


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Federal Register / Vol. 83, No. 148 / Wednesday, August 1, 2018 / Notices 37533 

1At the time the previous exemption was granted 

in 1986, 10 CFR 50.54(w)(1) required the licensee 

to maintain on-site property insurance in the 

amount of $500 million. Based on a finding that 

special circumstances were present, the 

Commission approved the licensee’s exemption 

request to permit LACBWR to reduce its onsite 

insurance coverage from $500 million to $180 

million. See 51 FR 24456. 

dismantlement and decommissioning 

activities. 

By order dated May 20, 2016 (ADAMS 

Accession No. ML16123A073), the NRC 

approved the direct transfer of 

Possession Only License No. DPR–45 for 

LACBWR from DPC to LS, a whollyowned subsidiary of EnergySolutions, 

LLC, and approved a conforming license 

amendment, pursuant to 10 CFR 50.80, 

‘‘Transfer of licenses,’’ and 10 CFR 

50.90, ‘‘Application for amendment of 

license, construction permit, or early 

site permit,’’ to reflect the change. The 

order was published in the Federal 

Register (FR) on June 2, 2016 (81 FR 

35383). The transfer assigns DPC’s 

licensed possession, maintenance, and 

decommissioning responsibilities for 

LACBWR to LS in order to implement 

expedited decommissioning at the 

LACBWR site. Decommissioning of the 

LACBWR facility and site is scheduled 

to be completed in 2018. 

II. Request/Action 

Pursuant to 10 CFR 50.12, ‘‘Specific 

exemptions,’’ LS has requested an 

exemption from 10 CFR 50.54(w)(1) by 

letter dated February 22, 2018 (ADAMS 

Accession No. ML18057A021). The 

exemption from the requirements of 10 

CFR 50.54(w)(1) would permit LS to 

reduce its onsite property damage 

insurance from $180 million to $50 

million. 

The regulation in 10 CFR 50.54(w)(1) 

requires each licensee to have and 

maintain onsite property damage 

insurance to stabilize and 

decontaminate the reactor and reactor 

site in the event of an accident. The 

onsite insurance coverage must be either 

$1.06 billion or whatever amount of 

insurance is generally available from 

private sources (whichever is less). The 

LACBWR site currently maintains $180 

million in onsite insurance coverage in 

accordance with a previous exemption 

approved by the NRC on June 26, 1986 

(51 FR 24456).1

The licensee stated that there is a 

reduced potential for, and consequences 

from, an accident at a permanently 

shutdown and defueled reactor when 

compared to the risks at an operating 

power reactor. In addition, since the 

license no longer authorizes reactor 

operation or emplacement or retention 

of fuel in the reactor vessel at LACBWR, 

there are no events that would require 

the stabilization of reactor conditions 

after an accident. Similarly, the risk of 

an accident that that would result in 

significant onsite contamination at 

LACBWR is also much lower than the 

risk of such an event at an operating 

reactor. Therefore, LS requested an 

exemption from 10 CFR 50.54(w)(1) that 

would permit a reduction in its onsite 

property damage insurance from $180 

million to $50 million, commensurate 

with the reduced risk of an accident at 

the permanently shutdown and 

defueled LACBWR reactor. 

III. Discussion 

Pursuant to 10 CFR 50.12, the 

Commission may, upon application by 

any interested person or upon its own 

initiative, grant exemptions from the 

requirements of 10 CFR part 50 when (1) 

the exemptions are authorized by law, 

will not present an undue risk to public 

health or safety, and are consistent with 

the common defense and security; and 

(2) any of the special circumstances 

listed in 10 CFR 50.12(a)(2) are present. 

The financial protection limits of 10 

CFR 50.54(w)(1) were established after 

the Three Mile Island accident out of 

concern that licensees may be unable to 

financially cover onsite cleanup costs in 

the event of a major nuclear accident. 

The specified coverage requirement was 

developed based on an analysis of an 

accident at a nuclear reactor operating at 

power, resulting in a large fission 

product release and requiring significant 

resource expenditures to stabilize the 

reactor conditions and ultimately 

decontaminate and clean up the site. 

The NRC developed these cost 

estimates from the spectrum of 

postulated accidents for an operating 

nuclear reactor and the consequences of 

any associated release of radioactive 

material from the reactor. Although the 

risk of an accident at an operating 

reactor is very low, the consequences 

can be large. In an operating plant, the 

high temperature and pressure of the 

reactor coolant system, as well as the 

inventory of relatively short-lived 

radionuclides, contribute to both the 

risk and consequences of an accident. 

With the permanent cessation of reactor 

operations at LACBWR, the permanent 

removal of the fuel from the reactor 

core, and the movement of all the 

irradiated fuel assemblies into storage at 

the onsite ISFSI, such accidents are no 

longer possible. As a result, the reactor, 

reactor coolant system, and supporting 

systems no longer operate, and the 

majority of these components have 

already been dismantled and removed 

from the site as part of the 

decommissioning process. Therefore, 

these systems and components no 

longer serve any function related to the 

storage of the irradiated fuel. As such, 

postulated accidents involving failure or 

malfunction of the reactor, reactor 

coolant system, or supporting systems 

are no longer applicable at LACBWR. 

During reactor decommissioning, the 

principal radiological risks are 

associated with the storage of spent fuel 

onsite, as well as the inventory of 

radioactive liquids, activated reactor 

components, and contaminated 

materials. In its February 22, 2018, 

exemption request, LS noted that 

because all of the irradiated fuel 

assemblies are currently stored in the 

onsite ISFSI, a fuel handling accident 

and a zirconium fire caused by drain 

down of the spent fuel pool are no 

longer considered credible events. In the 

current state of decommissioning at 

LACBWR, with the reactor building 

being the only contaminated structure 

that still remains onsite, only minor 

liquid and airborne effluent releases 

resulting from dismantlement activities 

are considered credible events. The 

licensee determined that the minimal 

radioactive material remaining at the 

site that resulted from LACBWR’s 

operation is insufficient for any 

potential event to result in exceeding 

dose limits or otherwise involving a 

significant adverse effect on public 

health and safety. 

Specifically, there are no credible 

events at LACBWR that could result in 

a radiological release exceeding the 

limits established by the U.S. 

Environmental Protection Agency’s 

(EPA’s) early-phase Protective Action 

Guidelines (PAGs) of one roentgen 

equivalent man at the exclusion area 

boundary, which demonstrates that any 

possible radiological releases would be 

minimal and would not require 

precautionary protective actions (e.g., 

sheltering in place or evacuation). The 

staff evaluated the radiological 

consequences associated with various 

decommissioning activities, and 

credible accident events at LACBWR, in 

consideration of the permanently 

shutdown and defueled status of the 

facility. The possible accident scenarios 

at LACBWR have greatly reduced 

radiological consequences. Based on its 

review, the staff concluded that no 

reasonably conceivable radiological 

release event exists that could cause an 

offsite release greater than the EPA 

PAGs. 

In addition, given that all of the 

irradiated fuel assemblies at LACBWR 

have already been moved into storage at 

the onsite ISFSI, the fuel is no longer 

thermal-hydraulically capable of 

sustaining a zirconium fire, and can be 


sradovich on DSK3GMQ082PROD with NOTICES
37534 Federal Register / Vol. 83, No. 148 / Wednesday, August 1, 2018 / Notices 

air-cooled in all credible accident 

scenarios and fuel configurations. Since 

NRC approval of the previous 

exemption in 1986, which permitted 

LACBWR to reduce its onsite insurance 

coverage to $180 million, the NRC staff 

has authorized a lesser amount of onsite 

property damage insurance coverage 

based on an analysis of the zirconium 

fire risk. In SECY–96–256, ‘‘Changes to 

Financial Protection Requirements for 

Permanently Shutdown Nuclear Power 

Reactors, 10 CFR 50.54(w)(1) and 10 

CFR 140.11,’’ dated December 17, 1996 

(ADAMS Accession No. ML15062A483), 

the NRC staff recommended changes to 

the power reactor insurance regulations 

that would allow licensees to lower 

onsite insurance levels to $50 million 

upon demonstration that the fuel stored 

in the spent fuel pool can be air-cooled. 

In its Staff Requirements 

Memorandum to SECY–96–256, dated 

January 28, 1997 (ADAMS Accession 

No. ML15062A454), the Commission 

supported the staff’s recommendation 

that, among other things, would allow 

permanently shutdown power reactor 

licensees to reduce commercial onsite 

property damage insurance coverage to 

$50 million when the licensee was able 

to demonstrate the technical criterion 

that the spent fuel could be air-cooled 

if the spent fuel pool was drained of 

water. The staff has used this technical 

criterion to grant similar exemptions to 

other decommissioning reactors (e.g., 

Maine Yankee Atomic Power Station, 

published in the Federal Register on 

January 19, 1999 (64 FR 2920); and Zion 

Nuclear Power Station, published in the 

Federal Register on December 28, 1999 

(64 FR 72700)). These prior exemptions 

were based on the licensees 

demonstrating that the spent fuel could 

be air-cooled, consistent with the 

technical criterion discussed above. 

Based on this criterion, the NRC staff 

determined $50 million to be an 

adequate level of onsite property 

damage insurance coverage for the 

LACBWR site, given that the spent fuel 

is no longer susceptible to a zirconium 

fire. 

In addition, the staff has postulated 

that there is still a potential for other 

radiological incidents at a 

decommissioning reactor that could 

result in significant onsite 

contamination besides a zirconium fire. 

In SECY–96–256, the NRC staff cited the 

rupture of a large contaminated liquid 

storage tank, causing soil contamination 

and potential groundwater 

contamination, as the most costly 

postulated event to decontaminate and 

remediate (other than a zirconium fire). 

The postulated large liquid radiological 

waste storage tank rupture event was 

determined to have a bounding onsite 

cleanup cost of approximately $50 

million. However, decommissioning 

activities at LACBWR have progressed 

to such an extent that there are no 

longer any large radiological waste 

storage tanks onsite, as described in the 

most recent update to the D-Plan/ 

PSDAR (ADAMS Accession No. 

ML18155A395). The only potential 

source of radioactive liquid remaining at 

LACBWR is water generated during 

decommissioning and decontamination 

activities (e.g., draining, 

decontamination, and cutting 

processes), including the retention tank 

used to store this water, which has a 

total capacity of 6000 gallons and is 

therefore considerably less that the 

450,000 gallon large contaminated 

liquid storage tank postulated in SECY– 

96–256. According to the analysis 

described in the LACBWR D-Plan/ 

PSDAR, in the event that 80 percent of 

the retention tank volume were to be 

released from the tank via a nonmechanistic rupture, the normal effluent 

concentration limits of 10 CFR part 20, 

‘‘Standards for Protection Against 

Radiation,’’ appendix B, table 2, would 

not be exceeded. The staff has examined 

this analysis and concluded that there 

are no credible phenomena that could 

reasonably be postulated to cause a 

release from the LACBWR retention 

tank that would challenge the 

assumptions made in SECY–96–256 

regarding the rupture of a large 

contaminated liquid storage tank. 

Therefore, the staff determined that the 

licensee’s proposal to reduce onsite 

insurance to a level of $50 million 

would be consistent with the bounding 

cleanup and decontamination cost, as 

discussed in SECY–96–256, to account 

for the postulated rupture of the 

retention tank at the LACBWR site. 

A. Authorized by Law 

The regulation in 10 CFR 50.54(w)(1) 

requires each licensee to have and 

maintain onsite property damage 

insurance of either $1.06 billion or 

whatever amount of insurance is 

generally available from private sources, 

whichever is less. In accordance with 10 

CFR 50.12, the Commission may grant 

exemptions from the regulations in 10 

CFR part 50, as the Commission 

determines are authorized by law. 

In 1986, the Commission granted 

LACBWR an exemption from 10 CFR 

50.54(w)(1), permitting the reduction of 

onsite insurance coverage from $500 

million to $180 million. As explained 

above, the NRC staff has determined 

that the licensee’s proposed reduction 

in onsite property damage insurance 

coverage to a level of $50 million is 

consistent with SECY–96–256 because 

there is no credible risk of a zirconium 

fire with all irradiated fuel stored in the 

onsite ISFSI, where it is air-cooled in all 

accident scenarios. 

The NRC staff has determined that 

granting of the licensee’s proposed 

exemption will not result in a violation 

of the Atomic Energy Act of 1954, or 

other laws, as amended. Therefore, 

based on its review of LS’s exemption 

request, as discussed above, and 

consistent with SECY–96–256, the NRC 

staff concludes that the exemption is 

authorized by law. 

B. No Undue Risk to Public Health and 

Safety 

The onsite property damage insurance 

requirements of 10 CFR 50.54(w)(1) 

were established to provide financial 

assurance that following a significant 

nuclear accident, onsite reactor 

conditions could be stabilized and the 

site decontaminated. The requirements 

of 10 CFR 50.54(w)(1) and the existing 

level of onsite insurance coverage for 

LACBWR are predicated on the 

assumption that the reactor is operating. 

However, LACBWR is a permanently 

shutdown and defueled facility. The 

permanently defueled status of the 

facility has resulted in a significant 

reduction in the number and severity of 

potential accidents, and 

correspondingly, a significant reduction 

in the potential for and severity of 

onsite property damage. The proposed 

reduction in the amount of onsite 

insurance coverage does not impact the 

probability or consequences of potential 

accidents. The proposed level of 

insurance coverage is commensurate 

with the reduced consequences of 

credible nuclear accidents at LACBWR. 

Therefore, the NRC staff concludes that 

granting the requested exemption will 

not present an undue risk to the health 

and safety of the public. 

C. Consistent With the Common Defense 

and Security 

The proposed exemption would not 

eliminate any requirements associated 

with physical protection of the site and 

would not adversely affect LS’s ability 

to physically secure the site or protect 

special nuclear material. Physical 

security measures at LACBWR are not 

affected by the requested exemption. 

Therefore, the proposed exemption is 

consistent with the common defense 

and security. 

D. Special Circumstances 

Under 10 CFR 50.12(a)(2)(ii), special 

circumstances are present if the 

application of the regulation in the 

particular circumstances would not 


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Federal Register / Vol. 83, No. 148 / Wednesday, August 1, 2018 / Notices 37535 

serve the underlying purpose of the rule 

or is not necessary to achieve the 

underlying purpose of the rule. The 

underlying purpose of 10 CFR 

50.54(w)(1) is to provide reasonable 

assurance that adequate funds will be 

available to stabilize reactor conditions 

and cover onsite cleanup costs 

associated with site decontamination, 

following an accident that results in the 

release of a significant amount of 

radiological material. 

Because LACBWR is permanently 

shutdown and defueled, with all 

irradiated fuel assemblies stored in the 

onsite ISFSI, and a very small 

radioactive source term remaining at the 

site given the progress of 

decommissioning and dismantlement 

activities, it is no longer possible for the 

radiological consequences of designbasis accidents or other credible events 

at LACBWR to exceed the limits of the 

EPA PAGs at the exclusion area 

boundary. Therefore, the staff concludes 

that the application of the current 

requirements in 10 CFR 50.54(w)(1), as 

exempted, for LS to maintain $180 

million in onsite insurance coverage is 

not necessary to achieve the underlying 

purpose of the rule for the permanently 

shutdown and defueled LACBWR 

facility. 

Under 10 CFR 50.12(a)(2)(iii), special 

circumstances are present whenever 

compliance would result in undue 

hardship or other costs that are 

significantly in excess of those 

contemplated when the regulation was 

adopted, or that are significantly in 

excess of those incurred by others 

similarly situated. 

The NRC staff concludes that if the 

licensee was required to continue to 

maintain an onsite insurance level of 

$180 million, the associated insurance 

premiums would be in excess of those 

necessary and commensurate with the 

radiological contamination risks posed 

by the site. In addition, such insurance 

levels would be significantly in excess 

of other decommissioning reactor 

facilities that have been granted similar 

exemptions by the NRC. 

As such, the NRC staff finds that 

compliance with the existing 

requirement would result in an undue 

hardship or other costs that are 

significantly in excess of those 

contemplated when the regulation was 

adopted and are significantly in excess 

of those incurred by others similarly 

situated. Therefore, the special 

circumstances required by 10 CFR 

50.12(a)(2)(ii) and 10 CFR 50.12(a)(2)(iii) 

exist for the LACBWR facility. 

E. Environmental Considerations 

The NRC approval of an exemption to 

insurance or indemnity requirements 

belongs to a category of actions that the 

Commission, by rule or regulation, has 

declared to be a categorical exclusion, 

after first finding that the category of 

actions does not individually or 

cumulatively have a significant effect on 

the human environment. Specifically, 

the exemption is categorically excluded 

from further analysis under 10 CFR 

51.22(c)(25). 

Under 10 CFR 51.22(c)(25), granting 

of an exemption from the requirements 

of any regulation of chapter I to 10 CFR 

is a categorical exclusion provided that 

(i) there is no significant hazards 

consideration; (ii) there is no significant 

change in the types or significant 

increase in the amounts of any effluents 

that may be released offsite; (iii) there is 

no significant increase in individual or 

cumulative public or occupational 

radiation exposure; (iv) there is no 

significant construction impact; (v) 

there is no significant increase in the 

potential for or consequences from 

radiological accidents; and (vi) the 

requirements from which an exemption 

is sought involve: Surety, insurance, or 

indemnity requirements. 

The Director, Division of 

Decommissioning, Uranium Recovery, 

and Waste Programs, Office of Nuclear 

Material Safety and Safeguards, has 

determined that approval of the 

exemption request involves no 

significant hazards consideration 

because reducing the licensee’s onsite 

property damage insurance for 

LACBWR does not (1) involve a 

significant increase in the probability or 

consequences of an accident previously 

evaluated; or (2) create the possibility of 

a new or different kind of accident from 

any accident previously evaluated; or 

(3) involve a significant reduction in a 

margin of safety. The exempted 

financial protection regulation is 

unrelated to the operation of LACBWR. 

Accordingly, there is no significant 

change in the types or significant 

increase in the amounts of any effluents 

that may be released offsite; and no 

significant increase in individual or 

cumulative public or occupational 

radiation exposure. 

The exempted regulation is not 

associated with construction, so there is 

no significant construction impact. The 

exempted regulation does not concern 

the source term (i.e., potential amount 

of radiation in an accident), nor 

mitigation. Therefore, there is no 

significant increase in the potential for, 

or consequences of, a radiological 

accident. In addition, there would be no 

significant impacts to biota, water 

resources, historic properties, cultural 

resources, or socioeconomic conditions 

in the region. The requirement for onsite 

property damage insurance involves 

surety, insurance, and indemnity 

matters. Therefore, pursuant to 10 CFR 

51.22(b) and 10 CFR 51.22(c)(25), no 

environmental impact statement or 

environmental assessment need be 

prepared in connection with the 

approval of this exemption request. 

IV. Conclusions 

Accordingly, the Commission has 

determined that, pursuant to 10 CFR 

50.12(a), the exemption is authorized by 

law, will not present an undue risk to 

the public health and safety, and is 

consistent with the common defense 

and security. Also, special 

circumstances are present. Therefore, 

the Commission hereby grants LS an 

exemption from the requirements of 10 

CFR 50.54(w)(1), to permit the licensee 

to reduce its onsite property damage 

insurance coverage to a level of $50 

million. 

Dated at Rockville, Maryland, this 26th day 

of July 2018. 

For the Nuclear Regulatory Commission. 

John R. Tappert, 

Director, Division of Decommissioning, 

Uranium Recovery, and Waste Programs, 

Office of Nuclear Material Safety and 

Safeguards. 

[FR Doc. 2018–16393 Filed 7–31–18; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2018–0156] 

Information Collection: NRC Form 748, 

National Source Tracking Transaction 

Report 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Renewal of existing information 

collection; request for comment. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) invites public 

comment on the renewal of Office of 

Management and Budget (OMB) 

approval for an existing collection of 

information. The information collection 

is entitled, ‘‘NRC Form 748, National 

Source Tracking Transaction Report.’’ 

DATES: Submit comments by October 1, 

2018. Comments received after this date 

will be considered if it is practical to do 

so, but the Commission is able to ensure 

consideration only for comments 

received on or before this date. 

ADDRESSES: You may submit comments 

by any of the following methods: 


sradovich on DSK3GMQ082PROD with NOTICES