Pacific Gas and Electric Company; Humboldt Bay Power Plant, Unit 3, 16677-16680 [2020-06111]
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Federal Register / Vol. 85, No. 57 / Tuesday, March 24, 2020 / Notices
Week of March 23, 2020
There are no meetings scheduled for
the week of March 23, 2020.
Week of March 30, 2020—Tentative
[FR Doc. 2020–06206 Filed 3–20–20; 11:15 am]
BILLING CODE 7590–01–P
There are no meetings scheduled for
the week of March 30, 2020.
Week of April 6, 2020—Tentative
NUCLEAR REGULATORY
COMMISSION
There are no meetings scheduled for
the week of April 6, 2020.
[Docket No. 50–133; NRC–2020–0081]
Week of April 13, 2020—Tentative
Pacific Gas and Electric Company;
Humboldt Bay Power Plant, Unit 3
There are no meetings scheduled for
the week of April 13, 2020.
AGENCY:
Week of April 20, 2020—Tentative
There are no meetings scheduled for
the week of April 20, 2020.
lotter on DSKBCFDHB2PROD with NOTICES
For the Nuclear Regulatory Commission.
Wesley W. Held,
Policy Coordinator, Office of the Secretary.
Nuclear Regulatory
Commission.
ACTION: Exemption; issuance.
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Safety and Safeguards, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 301–415–
3017, email: john.hickman@nrc.gov.
SUPPLEMENTARY INFORMATION: The text of
the exemption is attached.
Dated at Rockville, Maryland, this 18th day
of March 2020.
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
The U.S. Nuclear Regulatory
Commission (NRC) is issuing an
exemption in response to a January 13,
Week of April 27, 2020—Tentative
2020, request from Pacific Gas and
There are no meetings scheduled for
Electric Company (PG&E or the
the week of April 27, 2020.
licensee). The exemption permits PG&E
ADDITIONAL INFORMATION: The Meeting on to reduce the minimum coverage limit
the Strategic Programmatic Overview of for onsite property damage insurance
from $63.16 million to $50 million for
the Operating Reactors and New
Humboldt Bay Power Plant, Unit 3.
Reactors Business Lines scheduled for
April 2, 2020, has been postponed.
ADDRESSES: Please refer to Docket ID
CONTACT PERSON FOR MORE INFORMATION: NRC–2020–0081 when contacting the
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Dated at Rockville, Maryland, this 19th day FOR FURTHER INFORMATION CONTACT: John
B. Hickman, Office of Nuclear Material
of March 2020.
SUMMARY:
16677
Docket No. 50–133, Pacific Gas and
Electric Company, Humboldt Bay Power
Plant Unit No. 3, Exemption
I. Background
The Humboldt Bay Power Plant, Unit
3 (HBPP 3) facility is a
decommissioning power reactor located
in Humboldt County, California. Pacific
Gas and Electric Company (PG&E) is the
holder of HBPP 3 Facility Operating
License No. DPR–7. On July 2, 1976,
HBPP 3 was shut down for annual
refueling and to conduct seismic
modifications. In 1983, updated
economic analyses indicated that
restarting HBPP 3 probably would not
be cost-effective, and on June 27, 1983,
PG&E announced its intention to
decommission the unit. In 1984, PG&E
submitted the HBPP 3 SAFSTOR [Safe
Storage] Decommissioning Plan in
support of the application to amend the
HBPP 3 operating license to a
possession-only license. On July 16,
1985, the NRC issued Amendment No.
19 to the HBPP Unit 3 Operating
License (Agencywide Documents
Access and Management System
(ADAMS) Legacy No. 507260040) to
change the status to possess-but-notoperate, and the plant was placed into
a SAFSTOR status. On December 11,
2008, PG&E completed the transfer of
spent nuclear fuel (SNF) from the HBPP
3 spent fuel pool (SFP) into the
Humboldt Bay Independent Spent Fuel
Storage Installation (HB ISFSI). All
Greater-Than-Class-C (GTCC) waste was
transferred to the HB ISFSI in 2013.
PG&E began decontamination and
dismantlement of HBPP 3 in June 2009,
and currently plans to terminate the 10
CFR part 50 license in 2021.
II. Request/Action
Pursuant to 10 CFR 50.12, ‘‘Specific
exemptions,’’ PG&E has requested an
exemption from 10 CFR 50.54(w)(1) by
letter dated January 13, 2020 (ADAMS
Accession No. ML20013G734). The
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exemption from the requirements of 10
CFR 50.54(w)(1) would permit PG&E to
reduce its onsite property damage
insurance from $63.16 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
HBPP 3 site currently maintains $63.16
million in onsite insurance coverage in
accordance with a previous exemption
approved by the NRC on August 22,
1989 (54 FR 35738).
The licensee stated that the HBPP 3
reactor has been removed and all SNF
and GTCC waste is stored in the onsite
ISFSI. In addition, plant structures
associated with reactor operations have
been removed from the site. This results
in a significant reduction in the
potential for and severity of onsite
property damage because, with the
HBPP 3 reactor removed, there are no
events that would require the
stabilization of reactor conditions after
an accident. Similarly, the risk of an
accident that would result in significant
onsite contamination at the HBPP 3 site
is also much lower than the risk of such
an event at an operating reactor.
Therefore, PG&E requested an
exemption from 10 CFR 50.54(w)(1) that
would permit a reduction in its onsite
property damage insurance from $63.16
million to $50 million, commensurate
with the reduced risk of an accident at
the decommissioned HBPP 3 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
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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 decommissioning of the
reactor at HBPP 3, and the movement of
all the irradiated fuel assemblies into
storage at the onsite ISFSI, such
accidents are no longer possible. The
reactor, reactor coolant system, and
supporting systems 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
irradiated fuel. As such, postulated
accidents involving failure or
malfunction of the reactor, reactor
coolant system, or supporting systems
are no longer applicable at HBPP 3.
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 January 13, 2020,
exemption request, PG&E noted that all
SNF and GTCC waste is stored at the HB
ISFSI. Plant structures have been
removed, and the site, including the
remaining buildings, has been
remediated for radioactive material. The
licensee determined that the minimal
radioactive material remaining at the
site that resulted from HBPP 3’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 HBPP 3 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 credible accident events
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at HBPP 3, in consideration of the
permanently shutdown and
decommissioned status of the facility.
The possible accident scenarios at HBPP
3 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 HBPP 3
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
air-cooled in all credible accident
scenarios and fuel configurations. Since
NRC approval of the previous
exemption in 1989, which permitted
HBPP 3 to reduce its onsite insurance
coverage to $63.16 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.,
Fort Calhoun Station, published in the
Federal Register on April 6, 2018 (83 FR
14898); and La Crosse Boiling Water
Reactor, published in the Federal
Register on August 1, 2018 (83 FR
37532)). 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
HBPP 3 site, given that the spent fuel is
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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 HBPP 3 have progressed to
such an extent that there are no longer
any large radiological waste storage
tanks onsite. The staff concludes that
there are no radioactive material sources
that could be released from the HBPP 3
site 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.
A. The Exemption Is 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 1989, the Commission granted
HBPP 3 an exemption from 10 CFR
50.54(w)(1), permitting the reduction of
onsite insurance coverage from $100
million to $63.16 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, as
amended, or other laws. Therefore,
based on its review of PG&E’s
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exemption request, as discussed above,
and consistent with SECY–96–256, the
NRC staff concludes that the exemption
is authorized by law.
B. The Exemption Presents 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 existing level
of onsite insurance coverage for HBPP 3
is predicated on the assumption that the
reactor is permanently shutdown and
defueled and the site is being actively
decommissioned with significant
residual activity remaining. However,
the fully decommissioned 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 HBPP 3.
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. The Exemption Is 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 PG&E’s
ability to physically secure the site or
protect special nuclear material.
Physical security measures at HBPP 3
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
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
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16679
release of a significant amount of
radiological material.
Because HBPP 3 is permanently
shutdown and defueled, with all
irradiated fuel assemblies stored in the
onsite ISFSI, and decommissioning
complete, it is no longer possible for the
radiological consequences of designbasis accidents or other credible events
at HBPP 3 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 PG&E to maintain $63.16
million in onsite insurance coverage is
not necessary to achieve the underlying
purpose of the rule for the permanently
shutdown and defueled HBPP 3 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
$63.16 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 HBPP 3 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
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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 HBPP 3
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 HBPP 3.
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 NRC has determined
that, pursuant to 10 CFR 50.12(a), the
exemption is authorized by law, will not
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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 PG&E an exemption from the
requirements of 10 CFR 50.54(w)(1) to
permit the licensee to reduce its onsite
property damage insurance coverage at
the HBPP 3 facility to a level of $50
million. The exemption is effective
March 18, 2020.
Dated at Rockville, Maryland, this 18th day
of March 2020.
For the Nuclear Regulatory Commission.
Patricia Holahan,
Director, Division of Decommissioning,
Uranium Recovery, and Waste Programs,
Office of Nuclear Material Safety and
Safeguards.
[FR Doc. 2020–06111 Filed 3–23–20; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2020–0078]
Biweekly Notice; Applications and
Amendments to Facility Operating
Licenses and Combined Licenses
Involving No Significant Hazards
Considerations
Nuclear Regulatory
Commission.
ACTION: Biweekly notice.
AGENCY:
Pursuant to section 189.a.(2)
of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear
Regulatory Commission (NRC) is
publishing this regular biweekly notice.
The Act requires the Commission to
publish notice of any amendments
issued, or proposed to be issued, and
grants the Commission the authority to
issue and make immediately effective
any amendment to an operating license
or combined license, as applicable,
upon a determination by the
Commission that such amendment
involves no significant hazards
consideration, notwithstanding the
pendency before the Commission of a
request for a hearing from any person.
This biweekly notice includes all
amendments issued, or proposed to be
issued, from February 25, 2020, to
March 9, 2020. The last biweekly notice
was published on March 10, 2020.
DATES: Comments must be filed by April
23, 2020. A request for a hearing or
petitions for leave to intervene must be
filed by May 26, 2020.
ADDRESSES: You may submit comments
by any of the following methods.
SUMMARY:
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• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2020–0078. Address
questions about NRC Docket IDs in
Regulations.gov to Jennifer Borges;
telephone: 301–287–9127; email:
Jennifer.Borges@nrc.gov. For technical
questions, contact the individual(s)
listed in the FOR FURTHER INFORMATION
CONTACT section of this document.
• Mail comments to: Office of
Administration, Mail Stop: TWFN–7–
A60M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, ATTN: Program Management,
Announcements and Editing Staff.
For additional direction on obtaining
information and submitting comments,
see ‘‘Obtaining Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
FOR FURTHER INFORMATION CONTACT:
Paula Blechman, Office of Nuclear
Reactor Regulation, telephone: 301–
415–2242, email: Paula.Blechman@
nrc.gov, U.S. Nuclear Regulatory
Commission, Washington DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2020–
0078, facility name, unit number(s),
docket number(s), application date, and
subject when contacting the NRC about
the availability of information for this
action. You may obtain publiclyavailable information related to this
action by any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2020–0078.
• 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 email to pdr.resource@
nrc.gov. The ADAMS accession number
for each document referenced (if it is
available in ADAMS) is provided the
first time that it is mentioned in this
document.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
E:\FR\FM\24MRN1.SGM
24MRN1
Agencies
[Federal Register Volume 85, Number 57 (Tuesday, March 24, 2020)]
[Notices]
[Pages 16677-16680]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2020-06111]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-133; NRC-2020-0081]
Pacific Gas and Electric Company; Humboldt Bay Power Plant, Unit
3
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption; issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an
exemption in response to a January 13, 2020, request from Pacific Gas
and Electric Company (PG&E or the licensee). The exemption permits PG&E
to reduce the minimum coverage limit for onsite property damage
insurance from $63.16 million to $50 million for Humboldt Bay Power
Plant, Unit 3.
ADDRESSES: Please refer to Docket ID NRC-2020-0081 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-2020-0081. Address
questions about NRC docket IDs in Regulations.gov 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 ``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: John B. Hickman, Office of Nuclear
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001; telephone: 301-415-3017, email:
[email protected].
SUPPLEMENTARY INFORMATION: The text of the exemption is attached.
Dated at Rockville, Maryland, this 18th day of March 2020.
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. 50-133, Pacific Gas and Electric Company, Humboldt Bay Power
Plant Unit No. 3, Exemption
I. Background
The Humboldt Bay Power Plant, Unit 3 (HBPP 3) facility is a
decommissioning power reactor located in Humboldt County, California.
Pacific Gas and Electric Company (PG&E) is the holder of HBPP 3
Facility Operating License No. DPR-7. On July 2, 1976, HBPP 3 was shut
down for annual refueling and to conduct seismic modifications. In
1983, updated economic analyses indicated that restarting HBPP 3
probably would not be cost-effective, and on June 27, 1983, PG&E
announced its intention to decommission the unit. In 1984, PG&E
submitted the HBPP 3 SAFSTOR [Safe Storage] Decommissioning Plan in
support of the application to amend the HBPP 3 operating license to a
possession-only license. On July 16, 1985, the NRC issued Amendment No.
19 to the HBPP Unit 3 Operating License (Agencywide Documents Access
and Management System (ADAMS) Legacy No. 507260040) to change the
status to possess-but-not-operate, and the plant was placed into a
SAFSTOR status. On December 11, 2008, PG&E completed the transfer of
spent nuclear fuel (SNF) from the HBPP 3 spent fuel pool (SFP) into the
Humboldt Bay Independent Spent Fuel Storage Installation (HB ISFSI).
All Greater-Than-Class-C (GTCC) waste was transferred to the HB ISFSI
in 2013. PG&E began decontamination and dismantlement of HBPP 3 in June
2009, and currently plans to terminate the 10 CFR part 50 license in
2021.
II. Request/Action
Pursuant to 10 CFR 50.12, ``Specific exemptions,'' PG&E has
requested an exemption from 10 CFR 50.54(w)(1) by letter dated January
13, 2020 (ADAMS Accession No. ML20013G734). The
[[Page 16678]]
exemption from the requirements of 10 CFR 50.54(w)(1) would permit PG&E
to reduce its onsite property damage insurance from $63.16 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 HBPP 3 site currently maintains $63.16 million
in onsite insurance coverage in accordance with a previous exemption
approved by the NRC on August 22, 1989 (54 FR 35738).
The licensee stated that the HBPP 3 reactor has been removed and
all SNF and GTCC waste is stored in the onsite ISFSI. In addition,
plant structures associated with reactor operations have been removed
from the site. This results in a significant reduction in the potential
for and severity of onsite property damage because, with the HBPP 3
reactor removed, there are no events that would require the
stabilization of reactor conditions after an accident. Similarly, the
risk of an accident that would result in significant onsite
contamination at the HBPP 3 site is also much lower than the risk of
such an event at an operating reactor. Therefore, PG&E requested an
exemption from 10 CFR 50.54(w)(1) that would permit a reduction in its
onsite property damage insurance from $63.16 million to $50 million,
commensurate with the reduced risk of an accident at the decommissioned
HBPP 3 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 decommissioning
of the reactor at HBPP 3, and the movement of all the irradiated fuel
assemblies into storage at the onsite ISFSI, such accidents are no
longer possible. The reactor, reactor coolant system, and supporting
systems 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 irradiated fuel.
As such, postulated accidents involving failure or malfunction of the
reactor, reactor coolant system, or supporting systems are no longer
applicable at HBPP 3.
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 January 13, 2020, exemption request,
PG&E noted that all SNF and GTCC waste is stored at the HB ISFSI. Plant
structures have been removed, and the site, including the remaining
buildings, has been remediated for radioactive material. The licensee
determined that the minimal radioactive material remaining at the site
that resulted from HBPP 3'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 HBPP 3 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 credible accident events at HBPP 3, in consideration of
the permanently shutdown and decommissioned status of the facility. The
possible accident scenarios at HBPP 3 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
HBPP 3 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 air-cooled in all credible accident scenarios
and fuel configurations. Since NRC approval of the previous exemption
in 1989, which permitted HBPP 3 to reduce its onsite insurance coverage
to $63.16 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., Fort Calhoun Station,
published in the Federal Register on April 6, 2018 (83 FR 14898); and
La Crosse Boiling Water Reactor, published in the Federal Register on
August 1, 2018 (83 FR 37532)). 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 HBPP 3 site, given
that the spent fuel is
[[Page 16679]]
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 HBPP 3 have
progressed to such an extent that there are no longer any large
radiological waste storage tanks onsite. The staff concludes that there
are no radioactive material sources that could be released from the
HBPP 3 site 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.
A. The Exemption Is 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 1989, the Commission granted HBPP 3 an exemption from 10 CFR
50.54(w)(1), permitting the reduction of onsite insurance coverage from
$100 million to $63.16 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, as amended, or other laws. Therefore, based on its review
of PG&E's exemption request, as discussed above, and consistent with
SECY-96-256, the NRC staff concludes that the exemption is authorized
by law.
B. The Exemption Presents 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 existing level of
onsite insurance coverage for HBPP 3 is predicated on the assumption
that the reactor is permanently shutdown and defueled and the site is
being actively decommissioned with significant residual activity
remaining. However, the fully decommissioned 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 HBPP 3. 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. The Exemption Is 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 PG&E's ability to physically secure the site or protect special
nuclear material. Physical security measures at HBPP 3 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 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 HBPP 3 is permanently shutdown and defueled, with all
irradiated fuel assemblies stored in the onsite ISFSI, and
decommissioning complete, it is no longer possible for the radiological
consequences of design-basis accidents or other credible events at HBPP
3 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 PG&E to maintain
$63.16 million in onsite insurance coverage is not necessary to achieve
the underlying purpose of the rule for the permanently shutdown and
defueled HBPP 3 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 $63.16 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 HBPP 3
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
[[Page 16680]]
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 HBPP 3 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 HBPP
3. 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 NRC 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 PG&E an exemption from the
requirements of 10 CFR 50.54(w)(1) to permit the licensee to reduce its
onsite property damage insurance coverage at the HBPP 3 facility to a
level of $50 million. The exemption is effective March 18, 2020.
Dated at Rockville, Maryland, this 18th day of March 2020.
For the Nuclear Regulatory Commission.
Patricia Holahan,
Director, Division of Decommissioning, Uranium Recovery, and Waste
Programs, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2020-06111 Filed 3-23-20; 8:45 am]
BILLING CODE 7590-01-P