LaCrosse Solutions, LLC; Dairyland Power Cooperative La Crosse Boiling Water Reactor, 37532-37535 [2018-16393]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 83, Number 148 (Wednesday, August 1, 2018)]
[Notices]
[Pages 37532-37535]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-16393]


-----------------------------------------------------------------------

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 https://www.regulations.gov and search for Docket ID NRC-2018-0157. Address 
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; 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 https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to [email protected]. The 
ADAMS accession number for each document referenced (if it is available 
in ADAMS) is provided the first time that it is mentioned in this 
document.
     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: 
[email protected].

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 co-located 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 Post-
Shutdown 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

[[Page 37533]]

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 wholly-owned 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\
---------------------------------------------------------------------------

    \1\ At 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.
---------------------------------------------------------------------------

    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

[[Page 37534]]

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 non-mechanistic 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

[[Page 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 design-basis 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