Exelon Generation Company, LLC; Oyster Creek Nuclear Generating Station, 28595-28600 [2019-13013]
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Federal Register / Vol. 84, No. 118 / Wednesday, June 19, 2019 / Notices
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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
$1.06 billion, 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.
The NRC staff finds that compliance
with the existing rule 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.
E. Environmental Considerations
The NRC approval of the 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
§ 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.
As the Director, Division of
Decommissioning, Uranium Recovery,
and Waste Programs, Office of Nuclear
Material Safety and Safeguards, I have
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determined that reissuing the exemption
involves no significant hazards
consideration because reducing the
licensee’s onsite property damage
insurance for Oyster Creek 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 Oyster
Creek. 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.
In addition, 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.
Moreover, the requirement for onsite
property damage insurance involves
surety, insurance, and indemnity
matters. Accordingly, the exemption
request meets the eligibility criteria for
categorical exclusion set forth in 10 CFR
51.22(c)(25). Therefore, pursuant to 10
CFR 51.22(b) and 51.22(c)(25), no
environmental impact statement or
environmental assessment need be
prepared in connection with the reissue
of this exemption.
IV. Conclusions
Accordingly, the Commission has
determined that, pursuant to 10 CFR
50.12(a), reissuing the exemption
originally granted on December 19,
2018, 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 as set
forth in 10 CFR 50.12.
Therefore, the Commission hereby
reissues Exelon an exemption from the
requirements of 10 CFR 50.54(w)(1) for
Oyster Creek. Exelon certified that it
permanently ceased power operations at
Oyster Creek on September 17, 2018.
The reissued exemption will permit
Oyster Creek to lower the minimum
required onsite insurance to $50 million
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28595
no earlier than 9.38 months (285 days)
after the permanent cessation of power
operations.
The exemption is effective on June 29,
2019 (9.38 months (285 days) after
Oyster Creek permanently ceased power
operations on September 17, 2019).
Dated at Rockville, Maryland, this 12 day
of June 2019.
For the Nuclear Regulatory Commission.
/RA/
John R. Tappert,
Director, Division of Decommissioning,
Uranium Recovery and Waste Programs,
Office of Nuclear Material Safety and
Safeguards.
[FR Doc. 2019–12997 Filed 6–18–19; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–219; NRC–2018–0288]
Exelon Generation Company, LLC;
Oyster Creek Nuclear Generating
Station
Nuclear Regulatory
Commission.
ACTION: Exemption; reissuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is reissuing an
exemption, originally approved on
December 19, 2018, that allowed Exelon
to reduce the required level of primary
off-site liability insurance for Oyster
Creek Nuclear Generating Station
(Oyster Creek) from $450 million to
$100 million and eliminate the
requirement to carry secondary financial
protection. The December 19, 2018,
exemption originally had an effective
date of 12 months (365 days) from the
certification of permanent cessation of
power operations. The reissued
exemption has a new effective date of
9.38 months (285 days) after the
docketing of the certification of
permanent cessation of power
operations at Oyster Creek.
DATES: The exemption was issued on
June 12, 2019.
ADDRESSES: Please refer to Docket ID
NRC–2018–0288 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–2018–0288. Address
questions about NRC docket IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; email:
Jennifer.Borges@nrc.gov. For technical
SUMMARY:
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Federal Register / Vol. 84, No. 118 / Wednesday, June 19, 2019 / Notices
questions, contact the individual listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘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 e-mail 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:
Amy M. Snyder, Office of Nuclear
Material Safety and Safeguards, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–6822; e-mail: Amy.Snyder@
nrc.gov.
SUPPLEMENTARY INFORMATION: The text of
the exemption is attached.
Dated at Rockville, Maryland, this 14th day
of June, 2019.
For the Nuclear Regulatory Commission.
Bruce A. Watson,
Chief, Reactor Decommissioning Branch,
Division of Decommissioning, Uranium
Recovery and Waste Programs, Office of
Nuclear Material Safety and Safeguards.
Attachment—Exemption
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–219]
Exelon Generation Company, LLC
Oyster Creek Nuclear Generating
Station
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Exemption
I. Background.
Exelon Generation Company, LLC
(Exelon, the licensee), is the holder of
Renewed Facility Operating License No.
DPR-16 for Oyster Creek Nuclear
Generating Station (Oyster Creek). By
letter dated February 14, 2018
(Agencywide Documents Access and
Management System [ADAMS]
Accession No. ML18045A084), Exelon
submitted to the U.S. Nuclear
Regulatory Commission (NRC) a
certification in accordance with
Sections 50.82(a)(1)(i) of Title 10 of the
Code of Federal Regulations (10 CFR),
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indicating that it plans to cease
permanent operation no later than
October 31, 2018. By letter dated
September 25, 2018 (ADAMS Accession
No. ML18268A258), Exelon submitted
to the NRC a certification in accordance
with 10 CFR 50.82(a)(1)(ii), stating that
Oyster Creek permanently ceased power
operations on September 17, 2018, and
that, as of September 25, 2018, all fuel
had been permanently removed from
the Oyster Creek reactor vessel. The
facility consists of a permanently
shutdown and defueled boiling-water
reactor located in the town of Forked
River, Ocean County, New Jersey.
II. Request/Action.
On December 19, 2018, the NRC
exempted Exelon from 10 CFR
140.11(a)(4) to allow Exelon to reduce
the required level of primary off-site
liability insurance for Oyster Creek from
$450,000,000 to $100,000,000, and
eliminate the requirement for Oyster
Creek to carry secondary financial
protection (ADAMS Accession Nos.
ML18229A005 [Cover Letter] and
ML18229A006 [Exemption]). The
December 19, 2018, exemption
originally had an effective date of 12
months (365 days) from the certification
of permanent cessation of power
operations under 10 CFR 50.82(a)(1).
By letter dated April 4, 2019 (ADAMS
Accession No. ML19094B776), Exelon
requested to change the effective date of
the December 19, 2018, exemption from
12 months (365 days) to 9.38 months
(285 days) from the certification of
permanent cessation of power
operations under 10 CFR 50.82(a)(1).
Exelon certified that Oyster Creek
permanently ceased power operations
on September 17, 2018. Therefore, the
revised effective date of the exemption
would be June 29, 2019.
To provide a complete record of the
NRC staff’s review, the NRC is reissuing
the December 19, 2018, exemption from
10 CFR 140.11(a)(4) with a revised
effective date of 9.38 months (285 days)
from the certification of permanent
cessation of power operations under 10
CFR 50.82(a)(1). This reissued
exemption supersedes the exemption
issued on December 19, 2018.
The regulation at 10 CFR 140.11(a)(4)
requires each licensee to have and
maintain primary financial protection in
an amount of $450 million. In addition,
the licensee is required to participate in
an industry retrospective rating plan
(secondary financial protection) that
commits each licensee to pay into an
insurance pool to be used for damages
that may exceed primary insurance
coverage. Participation in the industry
retrospective rating plan will subject
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Exelon to deferred premium charges up
to a maximum total deferred premium
of $131,056,000 with respect to any
nuclear incident at any operating
nuclear power plant, and up to a
maximum annual deferred premium of
$20,496,000 per incident.
The licensee states that the risk of an
offsite radiological release is
significantly lower at a nuclear power
reactor that has permanently shut down
and defueled, when compared to an
operating power reactor. Similarly, the
associated risk of offsite liability
damages that would require insurance
or indemnification is commensurately
lower for permanently shut down and
defueled plants. Therefore, Exelon
requested an exemption from 10 CFR
140.11(a)(4), to permit a reduction in
primary offsite liability insurance and to
withdraw from participation in the
industry retrospective rating plan.
III. Discussion.
Pursuant to 10 CFR 140.8, ‘‘Specific
exemptions,’’ the Commission may,
upon application of any interested
person or upon its own initiative, grant
such exemptions from the requirements
of the regulations in 10 CFR part 140,
when the exemptions are authorized by
law and are otherwise in the public
interest. The NRC staff has reviewed
Exelon’s request for an exemption from
10 CFR 140.11(a)(4) and has concluded
that the requested exemption is
authorized by law and is otherwise in
the public interest.
The Price Anderson Act of 1957
(PAA) requires that nuclear power
reactor licensees have insurance to
compensate the public for damages
arising from a nuclear incident.
Specifically, the PAA requires licensees
of facilities with a ‘‘rated capacity of
100,000 electrical kilowatts or more’’ to
maintain the maximum amount of
primary offsite liability insurance
commercially available (currently $450
million) and a specified amount of
secondary insurance coverage (currently
up to $131,056,000 per reactor). In the
event of an accident causing offsite
damages in excess of $450 million, each
licensee would be assessed a prorated
share of the excess damages, up to
$131,056,000 per reactor, for a total of
approximately $13 billion per nuclear
incident. The NRC’s regulations at 10
CFR 140.11(a)(4) implement these PAA
insurance requirements and set forth the
amount of primary and secondary
insurance each power reactor licensee
must have.
As noted above, the PAA
requirements with respect to primary
and secondary insurance, and the
implementing regulations at 10 CFR
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140.11(a)(4), apply to licensees of
facilities with a ‘‘rated capacity of
100,000 electrical kilowatts or more.’’
When the NRC issues a license
amendment to a decommissioning
licensee to reflect the defueled status of
the facility, the license amendment
includes removal of the rated capacity
of the reactor from the license.
Accordingly, a reactor that is
undergoing decommissioning has no
‘‘rated capacity.’’ Removal of the rated
capacity from the facility of a
decommissioning licensee, thus, allows
the NRC to take the reactor licensee out
of the category of reactor licensees that
are required to maintain the maximum
available insurance and to participate in
the secondary retrospective insurance
pool under the PAA, subject to a
technical finding that lesser potential
hazards exist at the facility after
termination of operations.
The financial protection limits of 10
CFR 140.11(a)(4) were established to
require a licensee to maintain sufficient
insurance, as specified under the PAA,
to satisfy liability claims by members of
the public for personal injury, property
damage, and the legal cost associated
with lawsuits, as the result of a nuclear
accident at an operating reactor with a
rated capacity of 100,000 kilowatts
electric (or greater). Thus, the insurance
levels established by this regulation, as
required by the PAA, were associated
with the risks and potential
consequences of an accident at an
operating reactor with a rated capacity
of 100,000 kilowatts electric (or greater).
The legal and associated technical
basis for granting exemptions from 10
CFR part 140 is set forth in SECY-93127, ‘‘Financial Protection Required of
Licensees of Large Nuclear Power Plants
During Decommissioning,’’ dated May
10, 1993 (ADAMS Accession No.
ML12257A628). The legal analysis
underlying SECY-93-127 concluded
that, upon a technical finding that lesser
potential hazards exist after termination
of operations (and removal of the rated
capacity), the Commission has the
discretion under the PAA to reduce the
amount of insurance required of a
licensee undergoing decommissioning.
As a technical matter, the fact that a
reactor has permanently ceased
operations is not itself determinative as
to whether a licensee may cease
providing the offsite liability coverage
required by the PAA and 10 CFR
140.11(a)(4). In light of the presence of
freshly discharged irradiated fuel in the
spent fuel pool (SFP) at a recently
shutdown reactor, the primary
consideration is the risk of offsite
radiological release from a zirconium
fire. That risk generally remains for
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about 10-16 months of decay time for
the fuel used in the last cycle of power
operation. After that time, the offsite
consequences of an offsite radiological
release from a zirconium fire are
negligible for shutdown reactors, but the
SFP is still operational and an inventory
of radioactive materials still exists
onsite. Therefore, an evaluation of the
potential for offsite damage is necessary
to determine the appropriate level of
offsite insurance post shutdown, in
accordance with the Commission’s
discretionary authority under the PAA
to establish an appropriate level of
required financial protection for such
shutdown facilities.
The NRC staff has conducted an
evaluation and concluded that, aside
from the handling, storage, and
transportation of spent fuel and
radioactive materials for a permanently
shut down and defueled reactor, no
reasonably conceivable potential
accident exists that could cause
significant offsite damage. During
normal power reactor operations, the
forced flow of water through the reactor
coolant system removes heat generated
by the reactor. The reactor coolant
system transfers this heat away from the
reactor core by converting reactor
feedwater to steam, which then flows to
the main turbine generator to produce
electricity. Most of the accident
scenarios postulated for operating
power reactors involve failures or
malfunctions of systems that could
affect the fuel in the reactor core, which
in the most severe postulated accidents,
would involve the release of large
quantities of fission products. With the
permanent cessation of reactor
operations at Oyster Creek and the
permanent removal of the fuel from the
reactor core, such accidents are no
longer possible. The reactor, reactor
coolant system, and supporting systems
no longer operate and have no function
related to the storage of the irradiated
fuel. Therefore, postulated accidents
involving failure or malfunction of the
reactor, reactor coolant system, or
supporting systems are no longer
applicable.
During reactor decommissioning, the
principal radiological risks are
associated with the storage of spent fuel
onsite. On a case-by-case basis,
licensees undergoing decommissioning
have been granted permission to reduce
the required amount of primary offsite
liability insurance coverage from $450
million to $100 million and to withdraw
from the secondary insurance pool. One
of the technical criteria for granting the
exemption is that the possibility of a
design-basis event that could cause
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28597
significant offsite damage has been
eliminated.
The NRC staff performed an
evaluation of the design-basis accidents
for Oyster Creek being permanently
defueled as part of SECY-18-0062,
‘‘Request by the Exelon Generation
Company, LLC for Exemptions from
Certain Emergency Planning
Requirements for the Oyster Creek
Nuclear Generating Station,’’ dated May
31, 2018 (ADAMS Accession No.
ML18030B340).
The licensee has stated, and the NRC
staff agrees, that while spent fuel
remains in the SFP, the only postulated
design-basis accident that would remain
applicable to Oyster Creek in the
permanently defueled condition that
could contribute a significant dose will
be a fuel handling accident (FHA) in the
Reactor Building, where the SFP is
located. For completeness, the NRC staff
also evaluated the applicability of other
design-basis accidents documented in
the Oyster Creek Updated Final Safety
Analysis Report (UFSAR) (ADAMS
Accession No. ML15307A558), to
ensure that these accidents would not
have consequences that could
potentially exceed the 10 CFR 50.67
dose limits and Regulatory Guide 1.183,
‘‘Alternative Radiological Source Terms
for Evaluating Design Basis Accidents at
Nuclear Power Reactors,’’ dose
acceptance criteria or approach the U.S.
Environmental Protection Agency (EPA)
early phase protective action guides
(PAGs).
In the Oyster Creek UFSAR, the
licensee has determined that within 33
days after shutdown, the FHA doses
would decrease to a level that would not
warrant protective actions under the
EPA early phase PAG framework,
notwithstanding meeting the dose limit
requirements under 10 CFR 50.67 and
dose acceptance criteria under
Regulatory Guide 1.183.
The NRC staff notes that the doses
from an FHA are dominated by the
isotope Iodine-131. The date of
cessation of power operations of Oyster
Creek occurred on September 17, 2018.
With 9.38 months of decay, the thyroid
dose from an FHA would be negligible.
After 9.38 months of decay, the only
isotope remaining in significant
amounts, among those postulated to be
released in a design-basis accident FHA,
would be Krypton-85. Since Krypton-85
primarily decays by beta emission, the
calculated skin dose from an FHA
analysis would make an insignificant
contribution to the total effective dose
equivalent (TEDE), which is the
parameter of interest in the
determination of the EPA early phase
PAGs for sheltering or evacuation. The
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NRC staff concludes that the dose
consequence from an FHA for the
permanently defueled Oyster Creek
would not approach the EPA early
phase PAGs. Therefore, any offsite
consequence from a design-basis
radiological release is unlikely, and a
significant amount of offsite liability
insurance coverage is not required.
The only beyond design-basis event
that has the potential to lead to a
significant radiological release at a
permanently shut down and defueled
(decommissioning) reactor is a
zirconium fire. The zirconium fire
scenario is a postulated, but highly
unlikely, accident scenario that involves
the loss of water inventory from the
SFP, resulting in a significant heatup of
the spent fuel and culminating in
substantial zirconium cladding
oxidation and fuel damage. The
probability of a zirconium fire scenario
is related to the decay heat of the
irradiated fuel stored in the SFP.
Therefore, the risks from a zirconium
fire scenario continue to decrease as a
function of the time that Oyster Creek
has been permanently shut down.
In the analysis provided in the
Attachment to its submittal dated
November 6, 2018, as supplemented by
letter dated February 13, 2019, with
Attachment 1, Response to NRC’s
Request for Additional Information and
Attachment 2, Zirconium Fire Analysis
for Drained Spent Fuel Pool, C-1302226-E310-457, Revision 2, (ADAMS
Accession Nos. ML18310A306, and
ML19044A643, respectively), the
licensee compared the conditions for
the hottest fuel assembly stored in the
SFP to a criterion proposed in
SECY-99-168, ‘‘Improving
Decommissioning Regulations for
Nuclear Power Plants’’ (ADAMS
Accession No. ML12265A598),
applicable to offsite emergency response
for the unit in the decommissioning
process. This criterion considers the
time for the hottest assembly to heat up
from 30 degrees Celsius (°C) to 900 °C
adiabatically. If the heatup time is
greater than 10 hours, then offsite
emergency preplanning involving the
plant is not necessary. Based on the
limiting fuel assembly for decay heat
and adiabatic heatup analysis presented
in Attachment 2, at 9.38 months (285
days) after permanent cessation of
power operations (i.e., 9.38 months
decay time), the time for the hottest fuel
assembly to reach 900 °C is 10 hours
after the assemblies have been
uncovered. As stated in NUREG-1738,
‘‘Technical Study of Spent Fuel Pool
Accident Risk at Decommissioning
Nuclear Power Plants,’’ February 2001
(ADAMS Accession No. ML010430066),
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900 °C is an acceptable temperature to
use for assessing onset of fission
product release under transient
conditions (to establish the critical
decay time for determining availability
of 10 hours for deployment of mitigation
equipment and, if necessary, for offsite
agencies to take appropriate action to
protect the health and safety of the
public, if fuel and cladding oxidation
occurs in air).
The NRC staff reviewed the
calculation to verify that important
physical properties of materials were
within acceptable ranges and the results
were accurate. The NRC staff
determined that physical properties
were appropriate. Therefore, the NRC
staff found that after 9.38 months (285
days), more than 10 hours would be
available before a significant offsite
release could begin. The NRC staff
concluded that the adiabatic heatup
calculation provided an acceptable
method for determining the minimum
time available for deployment of
mitigation equipment and, if necessary,
implementing measures under a
comprehensive general emergency plan.
In this regard, one technical criterion
for relieving decommissioning reactor
licensees from the insurance obligations
applicable to an operating reactor is a
finding that the heat generated by the
SFP has decayed to the point where the
possibility of a zirconium fire is highly
unlikely.
This was addressed in SECY-93-127,
where the NRC staff concluded that
there was a low likelihood and reduced
short-term public health consequences
of a zirconium fire once a
decommissioning plant’s spent fuel has
sufficiently decayed. In its Staff
Requirements Memorandum, ‘‘Financial
Protection Required of Licensees of
Large Nuclear Power Plants during
Decommissioning,’’ dated July 13, 1993
(ADAMS Accession No. ML003760936),
the Commission approved a policy that
authorized, through the exemption
process, withdrawal from participation
in the secondary insurance layer and a
reduction in commercial liability
insurance coverage to $100 million,
when a licensee is able to demonstrate
that the spent fuel could be air-cooled
if the SFP was drained of water.
The NRC 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]; Zion
Nuclear Power Station, published in the
Federal Register on December 28, 1999
[64 FR 72700]; Kewaunee Power
Station, published in the Federal
Register on March 24, 2015 [80 FR
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15638]; and Crystal River Unit 3 Nuclear
Generation Plant, published in the
Federal Register on May 6, 2015 [80 FR
26100]).
Additional discussions of other
decommissioning reactor licensees that
have received exemptions to reduce
their primary insurance level to $100
million are provided in SECY-96-256,
‘‘Changes to the Financial Protection
Requirements for Permanently
Shutdown Nuclear Power Reactors, 10
CFR 50.54(w) and 10 CFR 140.11,’’
dated December 17, 1996 (ADAMS
Accession No. ML15062A483). These
prior exemptions were based on the
licensee demonstrating that the SFP
could be air-cooled, consistent with the
technical criterion discussed above.
The NRC staff has evaluated the issue
of zirconium fires in SFPs and
presented an independent evaluation of
a SFP subject to a severe earthquake in
NUREG-2161, ‘‘Consequence Study of a
Beyond-Design-Basis Earthquake
Affecting the Spent Fuel Pool for a U.S.
Mark l Boiling Water Reactor,’’
September 2014 (ADAMS Accession No.
ML14255A365). This evaluation
concluded that, for a representative
boiling-water reactor, fuel in a dispersed
high-density configuration would be
adequately cooled by natural circulation
air flow within several months after
discharge from a reactor if the pool was
drained of water.
By letters dated August 22 and
December 6, 2017 (ADAMS Accession
Nos. ML17234A082 and ML17340A708,
respectively), Exelon confirmed that the
plant design and fuel storage
configuration considered in NUREG2161 were consistent with the Oyster
Creek plant design and fuel storage
configurations to be used in the
decommissioning of Oyster Creek. The
NRC staff independently confirmed that
the Oyster Creek fuel assembly decay
levels are also consistent with the spent
fuel considered in NUREG-2161. Thus,
the NRC staff has determined that after
9.38 months (285 days) decay, the fuel
stored in the Oyster Creek SFP will be
able to adequately be cooled by air in
the unlikely event of pool drainage.
In SECY-00-0145, ‘‘Integrated
Rulemaking Plan for Nuclear Power
Plant Decommissioning,’’ dated June 28,
2000, and SECY-01-0100, ‘‘Policy Issues
Related to Safeguards, Insurance, and
Emergency Preparedness Regulations at
Decommissioning Nuclear Power Plants
Storing Fuel in Spent Fuel Pools,’’ dated
June 4, 2001 (ADAMS Accession Nos.
ML003721626 and ML011450420,
respectively), the NRC staff discussed
additional information concerning SFP
zirconium fire risks at decommissioning
reactors and associated implications for
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offsite insurance. Analyzing when the
spent fuel stored in the SFP is capable
of adequate air-cooling is one measure
that demonstrates when the probability
of a zirconium fire would be
exceedingly low.
The licensee’s analyses demonstrate
that under conditions where the SFP
water inventory has drained and only
air cooling of the stored irradiated fuel
is available, there is reasonable
assurance that 9.38 months (285 days)
after the certification of permanent
cessation of operations that the Oyster
Creek spent fuel will remain at
temperatures far below those associated
with a significant radiological release.
In addition, the licensee performed
adiabatic heatup analyses, in which a
complete drainage of the SFP is
combined with rearrangement of spent
fuel rack geometry and/or the addition
of rubble to the SFP; this type of
analysis postulates that decay heat
transfer from the spent fuel via
conduction, convection, or radiation
would be impeded. The licensee’s
adiabatic heatup analyses demonstrate
that 9.38 months (285 days) after the
certification of permanent cessation of
operations, there would be at least 10
hours after the loss of all means of
cooling (both air and/or water), before
the spent fuel cladding would reach a
temperature where the potential for a
significant offsite radiological release
could occur.
In the NRC staff’s safety evaluation
dated June 11, 2019, associated with the
NRC’s reissuance of exemptions from
certain emergency planning
requirements for Oyster Creek, with a
modified effective date of 9.38 months
(285 days) after the permanent cessation
of operations, the NRC staff assessed the
Exelon accident analyses associated
with the radiological risks from a
zirconium fire at a permanently shut
down and defueled Oyster Creek site.
Based on its evaluation of the licensee’s
adiabatic heatup analyses, the NRC staff
found that, for the very unlikely beyond
design-basis accident scenario where
the SFP coolant inventory is lost in such
a manner that all methods of heat
removal from the spent fuel are no
longer available, there will be a
minimum of 10 hours from the
initiation of the accident until the
cladding reaches a temperature where
offsite radiological release might occur.
The NRC staff found that 10 hours is
sufficient time to support deployment of
mitigation equipment, consistent with
plant conditions, to prevent the
zirconium cladding from reaching a
point of rapid oxidation.
The NRC staff has determined that the
licensee’s proposed reduction in
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19:06 Jun 18, 2019
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primary offsite liability coverage to a
level of $100 million, and the licensee’s
proposed withdrawal from participation
in the secondary insurance pool for
offsite financial protection, are
consistent with the policy established in
SECY-93-127 and subsequent insurance
considerations resulting from zirconium
fire risks, as discussed in SECY-00-0145
and SECY-01-0100. The NRC has
previously determined in SECY-00-0145
that the minimum offsite financial
protection requirement may be reduced
to $100 million and that secondary
insurance is not required, once it is
determined that the spent fuel in the
SFP is no longer thermal-hydraulically
capable of sustaining a zirconium fire
based on a plant-specific analysis. In
addition, the NRC staff notes that
similar exemptions from these
insurance requirements, have been
granted to other permanently shutdown
and defueled power reactors, upon
satisfactory demonstration that
zirconium fire risk from the irradiated
fuel stored in the SFP is of negligible
concern.
A. The Exemption is Authorized by Law
The PAA, and its implementing
regulations in 10 CFR 140.11(a)(4),
require licensees of nuclear reactors that
have a rated capacity of 100,000
kilowatts electric or more to have and
maintain $450 million in primary
financial protection and to participate in
a secondary retrospective insurance
pool. In accordance with 10 CFR 140.8,
the Commission may grant exemptions
from the regulations in 10 CFR part 140,
as the Commission determines are
authorized by law. The legal and
associated technical basis for granting
exemptions from 10 CFR part 140 are set
forth in SECY-93-127. The legal analysis
underlying SECY-93-127 concluded
that, upon a technical finding that lesser
potential hazards exist after termination
of operations, the Commission has the
discretion under the Price-Anderson Act
to reduce the amount of insurance
required of a licensee undergoing
decommissioning.
The NRC staff concludes that the
technical criteria for relieving Exelon
from its existing primary and secondary
insurance obligations have been met. As
explained above, the NRC staff has
concluded that no reasonably
conceivable design-basis accident exists
that could cause an offsite release
greater than the EPA PAGs, and
therefore, that any offsite consequence
from a design-basis radiological release
is unlikely, and the need for a
significant amount of offsite liability
insurance coverage is unwarranted.
Additionally, the NRC staff determined
PO 00000
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Fmt 4703
Sfmt 4703
28599
that, after 9.38 months (285 days) decay,
the fuel stored in the Oyster Creek SFP
will be able to adequately be cooled by
air in the unlikely event of pool
drainage. Moreover, in the very unlikely
beyond design-basis accident scenario
where the SFP coolant inventory is lost
in such a manner that all methods of
heat removal from the spent fuel are no
longer available, the NRC staff has
determined that 10 hours would be
available and is sufficient time to
support deployment of mitigation
equipment, consistent with plant
conditions, to prevent the zirconium
cladding from reaching a point of rapid
oxidation. Thus, the NRC staff
concludes that the fuel stored in the
Oyster Creek SFP will have decayed
sufficiently by the requested effective
exemption date of 9.38 months (285
days) after the certification of
permanent cessation of operations, to
support a reduction in the required
insurance consistent with SECY-000145.
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,
Section 170, or other laws, as amended,
which require licensees to maintain
adequate financial protection.
Accordingly, consistent with the legal
standard presented in SECY-93-127,
under which decommissioning reactor
licensees may be relieved of the
requirements to carry the maximum
amount of insurance available and to
participate in the secondary
retrospective premium pool where there
is sufficient technical justification, the
NRC staff concludes that the requested
exemption is authorized by law.
B. The Exemption is Otherwise in the
Public Interest
The financial protection limits of 10
CFR 140.11 were established to require
licensees to maintain sufficient offsite
liability insurance to ensure adequate
funding for offsite liability claims,
following an accident at an operating
reactor. However, the regulation does
not consider the reduced potential for
and consequence of nuclear incidents at
permanently shutdown and
decommissioning reactors.
The basis provided in SECY-93-127,
SECY-00-0145, and SECY-01-0100
allows licensees of decommissioning
plants to reduce their primary offsite
liability insurance and to withdraw
from participation in the retrospective
rating pool for deferred premium
charges. As discussed in these
documents, once the zirconium fire
concern is determined to be negligible,
possible accident scenario risks at
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permanently shutdown and defueled
reactors are greatly reduced, when
compared to the risks at operating
reactors, and the associated potential for
offsite financial liabilities from an
accident are commensurately less. The
licensee has analyzed and the NRC staff
has confirmed that the risks of accidents
that could result in an offsite
radiological risk are minimal, thereby
justifying the proposed reductions in
offsite primary liability insurance and
withdrawal from participation in the
secondary retrospective rating pool for
deferred premium charges.
Additionally, participation in the
secondary retrospective rating pool
could potentially have adverse
consequences on the safe and timely
completion of decommissioning. If a
nuclear incident sufficient to trigger the
secondary insurance layer occurred at
another nuclear power plant, the
licensee could incur financial liability
of up to $131,056,000. However,
because Oyster Creek is permanently
shut down, it cannot produce revenue
from electricity generation sales to cover
such a liability. Therefore, such liability
if subsequently incurred, could
significantly affect the ability of the
facility to conduct and complete timely
radiological decontamination and
decommissioning activities. In addition,
as SECY-93-127 concluded, the shared
financial risk exposure to Exelon is
greatly disproportionate to the
radiological risk posed by Oyster Creek,
when compared to operating reactors.
The reduced overall risk to the public at
decommissioning power plants does not
warrant that Exelon be required to carry
full operating reactor insurance
coverage, after the requisite spent fuel
cooling period has elapsed following
final reactor shutdown. The licensee’s
proposed financial protection limits will
maintain a level of liability insurance
coverage commensurate with the risk to
the public. These changes are consistent
with previous NRC policy as discussed
in SECY-00-0145, and exemptions
approved for other decommissioning
reactors. Thus, the underlying purpose
of the regulations will not be adversely
affected by the reductions in insurance
coverage. Accordingly, an exemption
from participation in the secondary
insurance pool and a reduction in the
primary insurance to $100 million, a
value more in line with the potential
consequences of accidents, would be in
the public interest in that this assures
there will be adequate funds to address
any of those consequences and helps to
assure the safe and timely
decommissioning of the reactor.
Therefore, the NRC staff has
concluded that the reissued exemption
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19:06 Jun 18, 2019
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from 10 CFR 140.11(a)(4), which would
permit Exelon to lower the Oyster Creek
primary insurance levels and to
withdraw from the secondary
retrospective premium pool at the
requested effective date of 9.38 months
(285 days) after the certification of
permanent cessation of operations, is in
the public interest.
C. Environmental Considerations
The NRC’s approval of an exemption
from 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 the requirement to prepare an
environmental assessment or
environmental impact statement, in
accordance with 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.
As the Director, Division of
Decommissioning, Uranium Recovery,
and Waste Programs, Office of Nuclear
Material Safety and Safeguards, I have
determined that reissuing the exemption
involves no significant hazards
consideration, as defined in 10 CFR
50.92, because reducing a licensee’s
offsite liability requirements at Oyster
Creek does not: (1) Involve a significant
increase in the probability or
consequences of an accident previously
evaluated; (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 Oyster
Creek or site activities. 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
PO 00000
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Fmt 4703
Sfmt 9990
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 any activities conducted
at the site. 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 resulting from issuance of
the requested exemption. The
requirement for offsite liability
insurance involves surety, insurance, or
indemnity matters only.
Therefore, pursuant to 10 CFR
51.22(b) and 51.22(c)(25), no
environmental impact statement or
environmental assessment need be
prepared in connection with the
reissuance of this exemption.
IV. Conclusions.
Accordingly, the Commission has
determined that, pursuant to 10 CFR
140.8, reissuing the exemption
originally granted on December 19,
2018, is authorized by law and is
otherwise in the public interest.
Therefore, the Commission hereby
reissues Exelon an exemption from the
requirements of 10 CFR 140.11(a)(4) for
Oyster Creek. Exelon certified that it
permanently ceased operation at Oyster
Creek on September 17, 2018. The
exemption from 10 CFR 140.11(a)(4)
permits Oyster Creek to reduce the
required level of primary financial
protection, from $450 million to $100
million and to withdraw from
participation in the secondary layer of
financial protection 9.38 months (285
days) after the certification of
permanent cessation of operations.
Therefore, the exemption is effective
on June 29, 2019 (9.38 months (285
days) after Oyster Creek permanently
ceased power operations on September
17, 2019)
Dated at Rockville, Maryland, this 12 day of
June 2019.
For the Nuclear Regulatory Commission.
RA/
John R. Tappert,
Director, Division of Decommissioning,
Uranium Recovery and Waste Programs,
Office of Nuclear Material Safety and
Safeguards.
[FR Doc. 2019–13013 Filed 6–18–19; 8:45 am]
BILLING CODE 7590–01–P
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Agencies
[Federal Register Volume 84, Number 118 (Wednesday, June 19, 2019)]
[Notices]
[Pages 28595-28600]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-13013]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-219; NRC-2018-0288]
Exelon Generation Company, LLC; Oyster Creek Nuclear Generating
Station
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption; reissuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is reissuing an
exemption, originally approved on December 19, 2018, that allowed
Exelon to reduce the required level of primary off[dash]site liability
insurance for Oyster Creek Nuclear Generating Station (Oyster Creek)
from $450 million to $100 million and eliminate the requirement to
carry secondary financial protection. The December 19, 2018, exemption
originally had an effective date of 12 months (365 days) from the
certification of permanent cessation of power operations. The reissued
exemption has a new effective date of 9.38 months (285 days) after the
docketing of the certification of permanent cessation of power
operations at Oyster Creek.
DATES: The exemption was issued on June 12, 2019.
ADDRESSES: Please refer to Docket ID NRC-2018-0288 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly[dash]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-2018-0288. Address
questions about NRC docket IDs in Regulations.gov to Jennifer Borges;
telephone: 301-287-9127; email: [email protected]. For technical
[[Page 28596]]
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 ``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 e-mail 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: Amy M. Snyder, Office of Nuclear
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001; telephone: 301-415-6822; e-mail:
[email protected].
SUPPLEMENTARY INFORMATION: The text of the exemption is attached.
Dated at Rockville, Maryland, this 14th day of June, 2019.
For the Nuclear Regulatory Commission.
Bruce A. Watson,
Chief, Reactor Decommissioning Branch, Division of Decommissioning,
Uranium Recovery and Waste Programs, Office of Nuclear Material Safety
and Safeguards.
Attachment--Exemption
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-219]
Exelon Generation Company, LLC
Oyster Creek Nuclear Generating Station
Exemption
I. Background.
Exelon Generation Company, LLC (Exelon, the licensee), is the
holder of Renewed Facility Operating License No. DPR-16 for Oyster
Creek Nuclear Generating Station (Oyster Creek). By letter dated
February 14, 2018 (Agencywide Documents Access and Management System
[ADAMS] Accession No. ML18045A084), Exelon submitted to the U.S.
Nuclear Regulatory Commission (NRC) a certification in accordance with
Sections 50.82(a)(1)(i) of Title 10 of the Code of Federal Regulations
(10 CFR), indicating that it plans to cease permanent operation no
later than October 31, 2018. By letter dated September 25, 2018 (ADAMS
Accession No. ML18268A258), Exelon submitted to the NRC a certification
in accordance with 10 CFR 50.82(a)(1)(ii), stating that Oyster Creek
permanently ceased power operations on September 17, 2018, and that, as
of September 25, 2018, all fuel had been permanently removed from the
Oyster Creek reactor vessel. The facility consists of a permanently
shutdown and defueled boiling-water reactor located in the town of
Forked River, Ocean County, New Jersey.
II. Request/Action.
On December 19, 2018, the NRC exempted Exelon from 10 CFR
140.11(a)(4) to allow Exelon to reduce the required level of primary
off[dash]site liability insurance for Oyster Creek from $450,000,000 to
$100,000,000, and eliminate the requirement for Oyster Creek to carry
secondary financial protection (ADAMS Accession Nos. ML18229A005 [Cover
Letter] and ML18229A006 [Exemption]). The December 19, 2018, exemption
originally had an effective date of 12 months (365 days) from the
certification of permanent cessation of power operations under 10 CFR
50.82(a)(1).
By letter dated April 4, 2019 (ADAMS Accession No. ML19094B776),
Exelon requested to change the effective date of the December 19, 2018,
exemption from 12 months (365 days) to 9.38 months (285 days) from the
certification of permanent cessation of power operations under 10 CFR
50.82(a)(1). Exelon certified that Oyster Creek permanently ceased
power operations on September 17, 2018. Therefore, the revised
effective date of the exemption would be June 29, 2019.
To provide a complete record of the NRC staff's review, the NRC is
reissuing the December 19, 2018, exemption from 10 CFR 140.11(a)(4)
with a revised effective date of 9.38 months (285 days) from the
certification of permanent cessation of power operations under 10 CFR
50.82(a)(1). This reissued exemption supersedes the exemption issued on
December 19, 2018.
The regulation at 10 CFR 140.11(a)(4) requires each licensee to
have and maintain primary financial protection in an amount of $450
million. In addition, the licensee is required to participate in an
industry retrospective rating plan (secondary financial protection)
that commits each licensee to pay into an insurance pool to be used for
damages that may exceed primary insurance coverage. Participation in
the industry retrospective rating plan will subject Exelon to deferred
premium charges up to a maximum total deferred premium of $131,056,000
with respect to any nuclear incident at any operating nuclear power
plant, and up to a maximum annual deferred premium of $20,496,000 per
incident.
The licensee states that the risk of an offsite radiological
release is significantly lower at a nuclear power reactor that has
permanently shut down and defueled, when compared to an operating power
reactor. Similarly, the associated risk of offsite liability damages
that would require insurance or indemnification is commensurately lower
for permanently shut down and defueled plants. Therefore, Exelon
requested an exemption from 10 CFR 140.11(a)(4), to permit a reduction
in primary offsite liability insurance and to withdraw from
participation in the industry retrospective rating plan.
III. Discussion.
Pursuant to 10 CFR 140.8, ``Specific exemptions,'' the Commission
may, upon application of any interested person or upon its own
initiative, grant such exemptions from the requirements of the
regulations in 10 CFR part 140, when the exemptions are authorized by
law and are otherwise in the public interest. The NRC staff has
reviewed Exelon's request for an exemption from 10 CFR 140.11(a)(4) and
has concluded that the requested exemption is authorized by law and is
otherwise in the public interest.
The Price Anderson Act of 1957 (PAA) requires that nuclear power
reactor licensees have insurance to compensate the public for damages
arising from a nuclear incident. Specifically, the PAA requires
licensees of facilities with a ``rated capacity of 100,000 electrical
kilowatts or more'' to maintain the maximum amount of primary offsite
liability insurance commercially available (currently $450 million) and
a specified amount of secondary insurance coverage (currently up to
$131,056,000 per reactor). In the event of an accident causing offsite
damages in excess of $450 million, each licensee would be assessed a
prorated share of the excess damages, up to $131,056,000 per reactor,
for a total of approximately $13 billion per nuclear incident. The
NRC's regulations at 10 CFR 140.11(a)(4) implement these PAA insurance
requirements and set forth the amount of primary and secondary
insurance each power reactor licensee must have.
As noted above, the PAA requirements with respect to primary and
secondary insurance, and the implementing regulations at 10 CFR
[[Page 28597]]
140.11(a)(4), apply to licensees of facilities with a ``rated capacity
of 100,000 electrical kilowatts or more.'' When the NRC issues a
license amendment to a decommissioning licensee to reflect the defueled
status of the facility, the license amendment includes removal of the
rated capacity of the reactor from the license.
Accordingly, a reactor that is undergoing decommissioning has no
``rated capacity.'' Removal of the rated capacity from the facility of
a decommissioning licensee, thus, allows the NRC to take the reactor
licensee out of the category of reactor licensees that are required to
maintain the maximum available insurance and to participate in the
secondary retrospective insurance pool under the PAA, subject to a
technical finding that lesser potential hazards exist at the facility
after termination of operations.
The financial protection limits of 10 CFR 140.11(a)(4) were
established to require a licensee to maintain sufficient insurance, as
specified under the PAA, to satisfy liability claims by members of the
public for personal injury, property damage, and the legal cost
associated with lawsuits, as the result of a nuclear accident at an
operating reactor with a rated capacity of 100,000 kilowatts electric
(or greater). Thus, the insurance levels established by this
regulation, as required by the PAA, were associated with the risks and
potential consequences of an accident at an operating reactor with a
rated capacity of 100,000 kilowatts electric (or greater).
The legal and associated technical basis for granting exemptions
from 10 CFR part 140 is set forth in SECY-93-127, ``Financial
Protection Required of Licensees of Large Nuclear Power Plants During
Decommissioning,'' dated May 10, 1993 (ADAMS Accession No.
ML12257A628). The legal analysis underlying SECY-93-127 concluded that,
upon a technical finding that lesser potential hazards exist after
termination of operations (and removal of the rated capacity), the
Commission has the discretion under the PAA to reduce the amount of
insurance required of a licensee undergoing decommissioning.
As a technical matter, the fact that a reactor has permanently
ceased operations is not itself determinative as to whether a licensee
may cease providing the offsite liability coverage required by the PAA
and 10 CFR 140.11(a)(4). In light of the presence of freshly discharged
irradiated fuel in the spent fuel pool (SFP) at a recently shutdown
reactor, the primary consideration is the risk of offsite radiological
release from a zirconium fire. That risk generally remains for about
10-16 months of decay time for the fuel used in the last cycle of power
operation. After that time, the offsite consequences of an offsite
radiological release from a zirconium fire are negligible for shutdown
reactors, but the SFP is still operational and an inventory of
radioactive materials still exists onsite. Therefore, an evaluation of
the potential for offsite damage is necessary to determine the
appropriate level of offsite insurance post shutdown, in accordance
with the Commission's discretionary authority under the PAA to
establish an appropriate level of required financial protection for
such shutdown facilities.
The NRC staff has conducted an evaluation and concluded that, aside
from the handling, storage, and transportation of spent fuel and
radioactive materials for a permanently shut down and defueled reactor,
no reasonably conceivable potential accident exists that could cause
significant offsite damage. During normal power reactor operations, the
forced flow of water through the reactor coolant system removes heat
generated by the reactor. The reactor coolant system transfers this
heat away from the reactor core by converting reactor feedwater to
steam, which then flows to the main turbine generator to produce
electricity. Most of the accident scenarios postulated for operating
power reactors involve failures or malfunctions of systems that could
affect the fuel in the reactor core, which in the most severe
postulated accidents, would involve the release of large quantities of
fission products. With the permanent cessation of reactor operations at
Oyster Creek and the permanent removal of the fuel from the reactor
core, such accidents are no longer possible. The reactor, reactor
coolant system, and supporting systems no longer operate and have no
function related to the storage of the irradiated fuel. Therefore,
postulated accidents involving failure or malfunction of the reactor,
reactor coolant system, or supporting systems are no longer applicable.
During reactor decommissioning, the principal radiological risks
are associated with the storage of spent fuel onsite. On a case-by-case
basis, licensees undergoing decommissioning have been granted
permission to reduce the required amount of primary offsite liability
insurance coverage from $450 million to $100 million and to withdraw
from the secondary insurance pool. One of the technical criteria for
granting the exemption is that the possibility of a design-basis event
that could cause significant offsite damage has been eliminated.
The NRC staff performed an evaluation of the design-basis accidents
for Oyster Creek being permanently defueled as part of SECY-18-0062,
``Request by the Exelon Generation Company, LLC for Exemptions from
Certain Emergency Planning Requirements for the Oyster Creek Nuclear
Generating Station,'' dated May 31, 2018 (ADAMS Accession No.
ML18030B340).
The licensee has stated, and the NRC staff agrees, that while spent
fuel remains in the SFP, the only postulated design-basis accident that
would remain applicable to Oyster Creek in the permanently defueled
condition that could contribute a significant dose will be a fuel
handling accident (FHA) in the Reactor Building, where the SFP is
located. For completeness, the NRC staff also evaluated the
applicability of other design-basis accidents documented in the Oyster
Creek Updated Final Safety Analysis Report (UFSAR) (ADAMS Accession No.
ML15307A558), to ensure that these accidents would not have
consequences that could potentially exceed the 10 CFR 50.67 dose limits
and Regulatory Guide 1.183, ``Alternative Radiological Source Terms for
Evaluating Design Basis Accidents at Nuclear Power Reactors,'' dose
acceptance criteria or approach the U.S. Environmental Protection
Agency (EPA) early phase protective action guides (PAGs).
In the Oyster Creek UFSAR, the licensee has determined that within
33 days after shutdown, the FHA doses would decrease to a level that
would not warrant protective actions under the EPA early phase PAG
framework, notwithstanding meeting the dose limit requirements under 10
CFR 50.67 and dose acceptance criteria under Regulatory Guide 1.183.
The NRC staff notes that the doses from an FHA are dominated by the
isotope Iodine-131. The date of cessation of power operations of Oyster
Creek occurred on September 17, 2018. With 9.38 months of decay, the
thyroid dose from an FHA would be negligible. After 9.38 months of
decay, the only isotope remaining in significant amounts, among those
postulated to be released in a design-basis accident FHA, would be
Krypton-85. Since Krypton-85 primarily decays by beta emission, the
calculated skin dose from an FHA analysis would make an insignificant
contribution to the total effective dose equivalent (TEDE), which is
the parameter of interest in the determination of the EPA early phase
PAGs for sheltering or evacuation. The
[[Page 28598]]
NRC staff concludes that the dose consequence from an FHA for the
permanently defueled Oyster Creek would not approach the EPA early
phase PAGs. Therefore, any offsite consequence from a design-basis
radiological release is unlikely, and a significant amount of offsite
liability insurance coverage is not required.
The only beyond design-basis event that has the potential to lead
to a significant radiological release at a permanently shut down and
defueled (decommissioning) reactor is a zirconium fire. The zirconium
fire scenario is a postulated, but highly unlikely, accident scenario
that involves the loss of water inventory from the SFP, resulting in a
significant heatup of the spent fuel and culminating in substantial
zirconium cladding oxidation and fuel damage. The probability of a
zirconium fire scenario is related to the decay heat of the irradiated
fuel stored in the SFP. Therefore, the risks from a zirconium fire
scenario continue to decrease as a function of the time that Oyster
Creek has been permanently shut down.
In the analysis provided in the Attachment to its submittal dated
November 6, 2018, as supplemented by letter dated February 13, 2019,
with Attachment 1, Response to NRC's Request for Additional Information
and Attachment 2, Zirconium Fire Analysis for Drained Spent Fuel Pool,
C-1302-226-E310-457, Revision 2, (ADAMS Accession Nos. ML18310A306, and
ML19044A643, respectively), the licensee compared the conditions for
the hottest fuel assembly stored in the SFP to a criterion proposed in
SECY[dash]99[dash]168, ``Improving Decommissioning Regulations for
Nuclear Power Plants'' (ADAMS Accession No. ML12265A598), applicable to
offsite emergency response for the unit in the decommissioning process.
This criterion considers the time for the hottest assembly to heat up
from 30 degrees Celsius ([deg]C) to 900 [deg]C adiabatically. If the
heatup time is greater than 10 hours, then offsite emergency
preplanning involving the plant is not necessary. Based on the limiting
fuel assembly for decay heat and adiabatic heatup analysis presented in
Attachment 2, at 9.38 months (285 days) after permanent cessation of
power operations (i.e., 9.38 months decay time), the time for the
hottest fuel assembly to reach 900 [deg]C is 10 hours after the
assemblies have been uncovered. As stated in NUREG-1738, ``Technical
Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power
Plants,'' February 2001 (ADAMS Accession No. ML010430066), 900 [deg]C
is an acceptable temperature to use for assessing onset of fission
product release under transient conditions (to establish the critical
decay time for determining availability of 10 hours for deployment of
mitigation equipment and, if necessary, for offsite agencies to take
appropriate action to protect the health and safety of the public, if
fuel and cladding oxidation occurs in air).
The NRC staff reviewed the calculation to verify that important
physical properties of materials were within acceptable ranges and the
results were accurate. The NRC staff determined that physical
properties were appropriate. Therefore, the NRC staff found that after
9.38 months (285 days), more than 10 hours would be available before a
significant offsite release could begin. The NRC staff concluded that
the adiabatic heatup calculation provided an acceptable method for
determining the minimum time available for deployment of mitigation
equipment and, if necessary, implementing measures under a
comprehensive general emergency plan.
In this regard, one technical criterion for relieving
decommissioning reactor licensees from the insurance obligations
applicable to an operating reactor is a finding that the heat generated
by the SFP has decayed to the point where the possibility of a
zirconium fire is highly unlikely.
This was addressed in SECY-93-127, where the NRC staff concluded
that there was a low likelihood and reduced short-term public health
consequences of a zirconium fire once a decommissioning plant's spent
fuel has sufficiently decayed. In its Staff Requirements Memorandum,
``Financial Protection Required of Licensees of Large Nuclear Power
Plants during Decommissioning,'' dated July 13, 1993 (ADAMS Accession
No. ML003760936), the Commission approved a policy that authorized,
through the exemption process, withdrawal from participation in the
secondary insurance layer and a reduction in commercial liability
insurance coverage to $100 million, when a licensee is able to
demonstrate that the spent fuel could be air-cooled if the SFP was
drained of water.
The NRC 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]; Zion Nuclear Power Station, published in the Federal
Register on December 28, 1999 [64 FR 72700]; Kewaunee Power Station,
published in the Federal Register on March 24, 2015 [80 FR 15638]; and
Crystal River Unit 3 Nuclear Generation Plant, published in the Federal
Register on May 6, 2015 [80 FR 26100]).
Additional discussions of other decommissioning reactor licensees
that have received exemptions to reduce their primary insurance level
to $100 million are provided in SECY[dash]96[dash]256, ``Changes to the
Financial Protection Requirements for Permanently Shutdown Nuclear
Power Reactors, 10 CFR 50.54(w) and 10 CFR 140.11,'' dated December 17,
1996 (ADAMS Accession No. ML15062A483). These prior exemptions were
based on the licensee demonstrating that the SFP could be air-cooled,
consistent with the technical criterion discussed above.
The NRC staff has evaluated the issue of zirconium fires in SFPs
and presented an independent evaluation of a SFP subject to a severe
earthquake in NUREG-2161, ``Consequence Study of a Beyond-Design-Basis
Earthquake Affecting the Spent Fuel Pool for a U.S. Mark l Boiling
Water Reactor,'' September 2014 (ADAMS Accession No. ML14255A365). This
evaluation concluded that, for a representative boiling-water reactor,
fuel in a dispersed high-density configuration would be adequately
cooled by natural circulation air flow within several months after
discharge from a reactor if the pool was drained of water.
By letters dated August 22 and December 6, 2017 (ADAMS Accession
Nos. ML17234A082 and ML17340A708, respectively), Exelon confirmed that
the plant design and fuel storage configuration considered in NUREG-
2161 were consistent with the Oyster Creek plant design and fuel
storage configurations to be used in the decommissioning of Oyster
Creek. The NRC staff independently confirmed that the Oyster Creek fuel
assembly decay levels are also consistent with the spent fuel
considered in NUREG-2161. Thus, the NRC staff has determined that after
9.38 months (285 days) decay, the fuel stored in the Oyster Creek SFP
will be able to adequately be cooled by air in the unlikely event of
pool drainage.
In SECY-00-0145, ``Integrated Rulemaking Plan for Nuclear Power
Plant Decommissioning,'' dated June 28, 2000, and SECY-01-0100,
``Policy Issues Related to Safeguards, Insurance, and Emergency
Preparedness Regulations at Decommissioning Nuclear Power Plants
Storing Fuel in Spent Fuel Pools,'' dated June 4, 2001 (ADAMS Accession
Nos. ML003721626 and ML011450420, respectively), the NRC staff
discussed additional information concerning SFP zirconium fire risks at
decommissioning reactors and associated implications for
[[Page 28599]]
offsite insurance. Analyzing when the spent fuel stored in the SFP is
capable of adequate air-cooling is one measure that demonstrates when
the probability of a zirconium fire would be exceedingly low.
The licensee's analyses demonstrate that under conditions where the
SFP water inventory has drained and only air cooling of the stored
irradiated fuel is available, there is reasonable assurance that 9.38
months (285 days) after the certification of permanent cessation of
operations that the Oyster Creek spent fuel will remain at temperatures
far below those associated with a significant radiological release.
In addition, the licensee performed adiabatic heatup analyses, in
which a complete drainage of the SFP is combined with rearrangement of
spent fuel rack geometry and/or the addition of rubble to the SFP; this
type of analysis postulates that decay heat transfer from the spent
fuel via conduction, convection, or radiation would be impeded. The
licensee's adiabatic heatup analyses demonstrate that 9.38 months (285
days) after the certification of permanent cessation of operations,
there would be at least 10 hours after the loss of all means of cooling
(both air and/or water), before the spent fuel cladding would reach a
temperature where the potential for a significant offsite radiological
release could occur.
In the NRC staff's safety evaluation dated June 11, 2019,
associated with the NRC's reissuance of exemptions from certain
emergency planning requirements for Oyster Creek, with a modified
effective date of 9.38 months (285 days) after the permanent cessation
of operations, the NRC staff assessed the Exelon accident analyses
associated with the radiological risks from a zirconium fire at a
permanently shut down and defueled Oyster Creek site. Based on its
evaluation of the licensee's adiabatic heatup analyses, the NRC staff
found that, for the very unlikely beyond design-basis accident scenario
where the SFP coolant inventory is lost in such a manner that all
methods of heat removal from the spent fuel are no longer available,
there will be a minimum of 10 hours from the initiation of the accident
until the cladding reaches a temperature where offsite radiological
release might occur. The NRC staff found that 10 hours is sufficient
time to support deployment of mitigation equipment, consistent with
plant conditions, to prevent the zirconium cladding from reaching a
point of rapid oxidation.
The NRC staff has determined that the licensee's proposed reduction
in primary offsite liability coverage to a level of $100 million, and
the licensee's proposed withdrawal from participation in the secondary
insurance pool for offsite financial protection, are consistent with
the policy established in SECY-93-127 and subsequent insurance
considerations resulting from zirconium fire risks, as discussed in
SECY-00-0145 and SECY-01-0100. The NRC has previously determined in
SECY-00-0145 that the minimum offsite financial protection requirement
may be reduced to $100 million and that secondary insurance is not
required, once it is determined that the spent fuel in the SFP is no
longer thermal-hydraulically capable of sustaining a zirconium fire
based on a plant-specific analysis. In addition, the NRC staff notes
that similar exemptions from these insurance requirements, have been
granted to other permanently shutdown and defueled power reactors, upon
satisfactory demonstration that zirconium fire risk from the irradiated
fuel stored in the SFP is of negligible concern.
A. The Exemption is Authorized by Law
The PAA, and its implementing regulations in 10 CFR 140.11(a)(4),
require licensees of nuclear reactors that have a rated capacity of
100,000 kilowatts electric or more to have and maintain $450 million in
primary financial protection and to participate in a secondary
retrospective insurance pool. In accordance with 10 CFR 140.8, the
Commission may grant exemptions from the regulations in 10 CFR part
140, as the Commission determines are authorized by law. The legal and
associated technical basis for granting exemptions from 10 CFR part 140
are set forth in SECY-93-127. The legal analysis underlying SECY-93-127
concluded that, upon a technical finding that lesser potential hazards
exist after termination of operations, the Commission has the
discretion under the Price-Anderson Act to reduce the amount of
insurance required of a licensee undergoing decommissioning.
The NRC staff concludes that the technical criteria for relieving
Exelon from its existing primary and secondary insurance obligations
have been met. As explained above, the NRC staff has concluded that no
reasonably conceivable design-basis accident exists that could cause an
offsite release greater than the EPA PAGs, and therefore, that any
offsite consequence from a design-basis radiological release is
unlikely, and the need for a significant amount of offsite liability
insurance coverage is unwarranted. Additionally, the NRC staff
determined that, after 9.38 months (285 days) decay, the fuel stored in
the Oyster Creek SFP will be able to adequately be cooled by air in the
unlikely event of pool drainage. Moreover, in the very unlikely beyond
design-basis accident scenario where the SFP coolant inventory is lost
in such a manner that all methods of heat removal from the spent fuel
are no longer available, the NRC staff has determined that 10 hours
would be available and is sufficient time to support deployment of
mitigation equipment, consistent with plant conditions, to prevent the
zirconium cladding from reaching a point of rapid oxidation. Thus, the
NRC staff concludes that the fuel stored in the Oyster Creek SFP will
have decayed sufficiently by the requested effective exemption date of
9.38 months (285 days) after the certification of permanent cessation
of operations, to support a reduction in the required insurance
consistent with SECY-00-0145.
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, Section 170, or other laws, as amended, which require
licensees to maintain adequate financial protection. Accordingly,
consistent with the legal standard presented in SECY-93-127, under
which decommissioning reactor licensees may be relieved of the
requirements to carry the maximum amount of insurance available and to
participate in the secondary retrospective premium pool where there is
sufficient technical justification, the NRC staff concludes that the
requested exemption is authorized by law.
B. The Exemption is Otherwise in the Public Interest
The financial protection limits of 10 CFR 140.11 were established
to require licensees to maintain sufficient offsite liability insurance
to ensure adequate funding for offsite liability claims, following an
accident at an operating reactor. However, the regulation does not
consider the reduced potential for and consequence of nuclear incidents
at permanently shutdown and decommissioning reactors.
The basis provided in SECY-93-127, SECY-00-0145, and SECY-01-0100
allows licensees of decommissioning plants to reduce their primary
offsite liability insurance and to withdraw from participation in the
retrospective rating pool for deferred premium charges. As discussed in
these documents, once the zirconium fire concern is determined to be
negligible, possible accident scenario risks at
[[Page 28600]]
permanently shutdown and defueled reactors are greatly reduced, when
compared to the risks at operating reactors, and the associated
potential for offsite financial liabilities from an accident are
commensurately less. The licensee has analyzed and the NRC staff has
confirmed that the risks of accidents that could result in an offsite
radiological risk are minimal, thereby justifying the proposed
reductions in offsite primary liability insurance and withdrawal from
participation in the secondary retrospective rating pool for deferred
premium charges.
Additionally, participation in the secondary retrospective rating
pool could potentially have adverse consequences on the safe and timely
completion of decommissioning. If a nuclear incident sufficient to
trigger the secondary insurance layer occurred at another nuclear power
plant, the licensee could incur financial liability of up to
$131,056,000. However, because Oyster Creek is permanently shut down,
it cannot produce revenue from electricity generation sales to cover
such a liability. Therefore, such liability if subsequently incurred,
could significantly affect the ability of the facility to conduct and
complete timely radiological decontamination and decommissioning
activities. In addition, as SECY-93-127 concluded, the shared financial
risk exposure to Exelon is greatly disproportionate to the radiological
risk posed by Oyster Creek, when compared to operating reactors. The
reduced overall risk to the public at decommissioning power plants does
not warrant that Exelon be required to carry full operating reactor
insurance coverage, after the requisite spent fuel cooling period has
elapsed following final reactor shutdown. The licensee's proposed
financial protection limits will maintain a level of liability
insurance coverage commensurate with the risk to the public. These
changes are consistent with previous NRC policy as discussed in SECY-
00-0145, and exemptions approved for other decommissioning reactors.
Thus, the underlying purpose of the regulations will not be adversely
affected by the reductions in insurance coverage. Accordingly, an
exemption from participation in the secondary insurance pool and a
reduction in the primary insurance to $100 million, a value more in
line with the potential consequences of accidents, would be in the
public interest in that this assures there will be adequate funds to
address any of those consequences and helps to assure the safe and
timely decommissioning of the reactor.
Therefore, the NRC staff has concluded that the reissued exemption
from 10 CFR 140.11(a)(4), which would permit Exelon to lower the Oyster
Creek primary insurance levels and to withdraw from the secondary
retrospective premium pool at the requested effective date of 9.38
months (285 days) after the certification of permanent cessation of
operations, is in the public interest.
C. Environmental Considerations
The NRC's approval of an exemption from 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 the
requirement to prepare an environmental assessment or environmental
impact statement, in accordance with 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.
As the Director, Division of Decommissioning, Uranium Recovery, and
Waste Programs, Office of Nuclear Material Safety and Safeguards, I
have determined that reissuing the exemption involves no significant
hazards consideration, as defined in 10 CFR 50.92, because reducing a
licensee's offsite liability requirements at Oyster Creek does not: (1)
Involve a significant increase in the probability or consequences of an
accident previously evaluated; (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 Oyster
Creek or site activities. 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 any activities conducted at the site. 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 resulting from
issuance of the requested exemption. The requirement for offsite
liability insurance involves surety, insurance, or indemnity matters
only.
Therefore, pursuant to 10 CFR 51.22(b) and 51.22(c)(25), no
environmental impact statement or environmental assessment need be
prepared in connection with the reissuance of this exemption.
IV. Conclusions.
Accordingly, the Commission has determined that, pursuant to 10 CFR
140.8, reissuing the exemption originally granted on December 19, 2018,
is authorized by law and is otherwise in the public interest.
Therefore, the Commission hereby reissues Exelon an exemption from the
requirements of 10 CFR 140.11(a)(4) for Oyster Creek. Exelon certified
that it permanently ceased operation at Oyster Creek on September 17,
2018. The exemption from 10 CFR 140.11(a)(4) permits Oyster Creek to
reduce the required level of primary financial protection, from $450
million to $100 million and to withdraw from participation in the
secondary layer of financial protection 9.38 months (285 days) after
the certification of permanent cessation of operations.
Therefore, the exemption is effective on June 29, 2019 (9.38 months
(285 days) after Oyster Creek permanently ceased power operations on
September 17, 2019)
Dated at Rockville, Maryland, this 12 day of June 2019.
For the Nuclear Regulatory Commission.
RA/
John R. Tappert,
Director, Division of Decommissioning, Uranium Recovery and Waste
Programs, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2019-13013 Filed 6-18-19; 8:45 am]
BILLING CODE 7590-01-P