Union Electric Company, dba Ameren Missouri, Callaway Plant, Unit No. 1, 52816-52821 [2022-18498]
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Federal Register / Vol. 87, No. 166 / Monday, August 29, 2022 / Notices
develop and submit their comments.
Public comments on DG–8060 and the
staff responses to the public comments
are available in ADAMS under
Accession No. ML22117A049.
III. Congressional Review Act
This RG is a rule as defined in the
Congressional Review Act (5 U.S.C.
801–808). However, the Office of
Management and Budget has not found
this RG to be a major rule as defined in
the Congressional Review Act.
IV. Backfitting, Forward Fitting, and
Issue Finality
RG 8.34, Revision 1, will provide
updated guidance for reactor and nonreactor applicants and licensees
regarding acceptable methods for
calculating radiation doses. Issuance of
RG 8.34, Revision 1 would not
constitute backfitting, as that term is
defined in 10 CFR 50.109, ‘‘Backfitting,’’
and as described in NRC Management
Directive (MD) 8.4, ‘‘Management of
Backfitting, Forward Fitting, Issue
Finality, and Information Requests’’;
constitute forward fitting, as that term is
defined and described in MD 8.4; or
affect the issue finality of any approval
issued under 10 CFR part 52.
V. Submitting Suggestions for
Improvement of Regulatory Guides
A member of the public may, at any
time, submit suggestions to the NRC for
improvement of existing RGs or for the
development of new RGs. Suggestions
can be submitted on the NRC’s public
website at https://www.nrc.gov/readingrm/doc-collections/reg-guides/
contactus.html. Suggestions will be
considered in future updates and
enhancements to the ‘‘Regulatory
Guide’’ series.
Dated: August 24, 2022.
For the Nuclear Regulatory Commission.
Meraj Rahimi,
Chief, Regulatory Guide and Programs
Management Branch, Division of Engineering,
Office of Nuclear Regulatory Research.
[FR Doc. 2022–18525 Filed 8–26–22; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
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[NRC–2022–0001]
Sunshine Act Meetings
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12, 19, 26, October 3, 10, 2022. The
schedule for Commission meetings is
subject to change on short notice. The
NRC Commission Meeting Schedule can
be found on the internet at: https://
TIME AND DATE:
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www.nrc.gov/public-involve/publicmeetings/schedule.html.
PLACE: The NRC provides reasonable
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need this meeting notice or the
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MATTERS TO BE CONSIDERED:
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There are no meetings scheduled for
the week of September 5, 2022.
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There are no meetings scheduled for
the week of September 12, 2022.
Week of September 19, 2022—Tentative
Monday, September 19, 2022
10:00 a.m. Briefing on NRC
International Activities (Closed—
Ex. 1 & 9)
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There are no meetings scheduled for
the week of September 26, 2022.
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the week of October 3, 2022.
Week of October 10, 2022—Tentative
Tuesday, October 11, 2022
10:00 a.m. NRC All Employees
Meeting (Public Meeting) (Contact:
Anthony DeJesus: 301–287–9219)
Additional Information: The meeting
will be held at the Bethesda North
Marriott Hotel & Conference Center,
5701 Marinelli Road, North Bethesda,
Maryland. The public is invited to
attend the Commission’s meeting live by
webcast at the Web address—https://
video.nrc.gov/.
Thursday, October 13, 2022
9:00 a.m. Strategic Programmatic
Overview of the Operating Reactors
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and New Reactors Business Lines
(Public Meeting) (Contact: Jennie
Rankin, 301–415–1530)
Additional Information: The meeting
will be held in the Commissioners’
Conference Room, 11555 Rockville Pike,
Rockville, Maryland. The public is
invited to attend the Commission’s
meeting live by webcast at the Web
address—https://video.nrc.gov/.
CONTACT PERSON FOR MORE INFORMATION:
For more information or to verify the
status of meetings, contact Wesley Held
at 301–287–3591 or via email at
Wesley.Held@nrc.gov.
The NRC is holding the meetings
under the authority of the Government
in the Sunshine Act, 5 U.S.C. 552b.
Dated: August 24, 2022.
For the Nuclear Regulatory Commission.
Monika G. Coflin,
Technical Coordinator, Office of the
Secretary.
[FR Doc. 2022–18612 Filed 8–25–22; 11:15 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–483; NRC–2022–0139]
Union Electric Company, dba Ameren
Missouri, Callaway Plant, Unit No. 1
Nuclear Regulatory
Commission.
ACTION: Environmental assessment and
finding of no significant impact;
issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is issuing an
environmental assessment (EA)
prepared under the National
Environmental Policy Act of 1969
(NEPA) and NRC’s regulations. This EA
summarizes the results of the NRC
staff’s environmental review, which
evaluates the potential environmental
impacts of granting exemptions from
NRC regulations and issuing an
associated license amendment in
response to a request from the Union
Electric Company, doing business as
(dba) Ameren Missouri (Ameren, the
licensee) for Renewed Facility
Operating License NPF–30, for the
Callaway Plant, Unit No. 1 (Callaway).
Specifically, the licensee is seeking a
license amendment and regulatory
exemptions that would, if granted, allow
the licensee to use both a deterministic
and risk-informed approach to address
safety issues discussed in Generic Safety
Issue (GSI)–191, ‘‘Assessment of Debris
Accumulation in PWR [Pressurized
Water Reactor] Sump Pump
Performance’’ and to close Generic
SUMMARY:
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Letter (GL) 2004–02, ‘‘Potential Impact
of Debris Blockage on Emergency
Recirculation During Design Basis
Accidents at Pressurized-Water
Reactors.’’ The NRC staff is issuing a
final EA and finding of no significant
impact (FONSI) associated with the
proposed exemptions.
DATES: The EA and FONSI referenced in
this document is available on August
29, 2022.
ADDRESSES: Please refer to Docket ID
NRC–2022–0139 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–2022–0139. Address
questions about Docket IDs in
Regulations.gov to Stacy Schumann;
telephone: 301–415–0624; email:
Stacy.Schumann@nrc.gov. For technical
questions, contact the individual listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publicly
available documents online in the
ADAMS Public Documents collection at
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. For the
convenience of the reader, instructions
about obtaining materials referenced in
this document are provided in the
‘‘Availability of Documents’’ section.
• NRC’s PDR: You may examine and
purchase copies of public documents,
by appointment, at the NRC’s PDR,
Room P1 B35, One White Flint North,
11555 Rockville Pike, Rockville,
Maryland 20852. To make an
appointment to visit the PDR, please
send an email to PDR.Resource@nrc.gov
or call 1–800–397–4209 or 301–415–
4737, between 8:00 a.m. and 4:00 p.m.
Eastern Time (ET), Monday through
Friday, except Federal holidays.
FOR FURTHER INFORMATION CONTACT:
Mahesh Chawla, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 301–415–
8371, email: Mahesh.Chawla@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering a request to
grant certain regulatory exemptions and
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issue a license amendment for Renewed
Facility Operating License NPF–30,
issued to Ameren, for Callaway, located
in Callaway County, Missouri. The
regulatory exemptions and associated
license amendment, if granted, would
allow Ameren to incorporate the use of
a risk-informed approach to address
safety issues discussed in GSI–191 and
respond to GL 2004–02. Pursuant to
Section 51.21 of title 10 of the Code of
Federal Regulations (10 CFR), ‘‘Criteria
for and identification of licensing and
regulatory actions requiring
environmental assessments,’’ the NRC
has prepared an EA summarizing the
findings of the NEPA review of the
proposed action. The NRC concluded
that the proposed action will have no
significant environmental impact. In
accordance with 10 CFR 51.31(a), the
NRC has determined not to prepare an
environmental impact statement for the
proposed licensing actions and is
issuing a FONSI.
The NRC established GSI–191 to
determine whether the transport and
accumulation of debris from a loss-ofcoolant accident (LOCA) in the PWR
containment structure would impede
the operation of the emergency core
cooling system (ECCS) or containment
spray system (CSS). A LOCA within the
containment structure is assumed to be
caused by a break in the primary coolant
loop piping. Water discharged from the
pipe break and debris would collect on
the containment structure floor and
within the containment emergency
sump. During this type of accident, the
ECCS and CSS would initially draw
cooling water from the refueling water
storage tank. However, realigning the
ECCS pumps to the containment
emergency sump would provide longterm cooling of the reactor core.
Therefore, successful long-term cooling
depends on the ability of the
containment emergency sump to
provide adequate flow to the residual
heat removal (RHR) recirculation pumps
for extended periods of time.
One of the concerns addressed by the
implementation of GSI–191 is that
debris material, such as insulation
installed on piping and components,
within the containment structure, could
be dislodged by a jet of high-pressure
water and steam during the LOCA.
Water, along with debris, would
accumulate at the bottom of the
containment structure and flow towards
the emergency sump pumps. Insulation
and other fibrous debris material could
block the emergency sump screens and
suction strainers, which in turn could
prevent the ability of the containment
emergency sump to provide adequate
water flow to the RHR pumps (for more
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information, see NUREG–0897,
‘‘Containment Emergency Sump
Performance: Technical Finding Related
to Unresolved Safety Issue A–43,’’
Revision 1).
The NRC issued GL 2004–02 to
address this safety concern by
requesting PWR licensees, pursuant to
10 CFR 50.54(f), to use an NRCapproved methodology to perform a
‘‘mechanistic evaluation of the potential
for the adverse effects of post-accident
debris blockage and operation with
debris-laden fluids to impede or prevent
the recirculation functions of the ECCS
and CSS following all postulated
accidents for which the recirculation of
these systems is required’’ and submit
this information to the NRC for
evaluation.
In 2012, the NRC staff developed
options for resolution of GSI–191,
which are discussed in SECY–12–0093,
‘‘Closure Options for Generic Safety
Issue 191, Assessment of Debris
Accumulation on Pressurized-Water
Reactor Sump Performance,’’ dated July
9, 2012. The licensee has proposed to
use both a deterministic method, with
plant-specific testing, and a riskinformed approach to demonstrate
compliance with 10 CFR 50.46,
‘‘Acceptance criteria for emergency core
colling systems for light-water nuclear
power reactors,’’ and 10 CFR part 50,
appendix A, General Design Criteria
(GDC) 35, ‘‘Emergency core cooling,’’
GDC 38, ‘‘Containment heat removal,’’
and GDC 41, ‘‘Containment atmosphere
cleanup,’’ and to resolve GSI–191 for
Callaway. Because, historically, the NRC
staff has not allowed licensees to use a
risk-informed approach to show
compliance with the requirements of 10
CFR 50.46, the licensee requested
exemptions from 10 CFR 50.46(a)(1) and
GDC 35, 38, and 41, as well as an
amendment to the associated technical
specifications to allow the use of a riskinformed approach to resolve GSI–191.
If approved, the proposed action would
not authorize any modifications within
the containment structure, physical
changes to the ECCS, or other
modifications to the plant. Rather, the
proposed action would only allow the
use of an alternate methodology to show
compliance with the regulations that
require the ECCS and CSS function
during certain LOCA events.
II. Environmental Assessment
Description of the Proposed Action
The proposed action as requested by
the licensee is to grant certain regulatory
exemptions and amend Facility
Operating License NPF–30. The
regulatory exemptions would allow
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Ameren to change the licensing basis
LOCA analysis identified in the updated
final safety analysis report to use a riskinformed approach to address safety
issues discussed in GSI–191 and to
close GL 2004 02. If approved, no
physical modifications to the nuclear
plant or changes to reactor operations
involving the ECCS would be required.
The proposed action is in response to
the licensee’s application dated March
31, 2021, as supplemented by letters
dated May 27, 2021; July 22, 2021;
August 23, 2021; October 7, 2021;
January 27, 2022; March 8, 2022; and
May 26, 2022.
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Need for the Proposed Action
The proposed action is needed
because, as the holder of Renewed
Facility Operating License No. NPF–30,
Ameren is expected to address the
safety issues discussed in GSI–191 and
to close GL 2004–02 for Callaway.
Consistent with SECY–12–0093, the
licensee chose an approach, which
requires, in part, that Ameren request
that the NRC amend the renewed
facility operating license and grant
certain regulatory exemptions for
Callaway.
Environmental Impacts of the Proposed
Action
Callaway is located on an
approximately 7,354-acre (2,976
hectare) site in Callaway County,
Missouri, approximately 10 miles (16
kilometers) southeast of Fulton,
Missouri, and 80 miles (129 kilometers)
west of the St. Louis metropolitan area.
Callaway consists of a single four-loop
Westinghouse PWR unit. The reactor
core of the unit heats water, which is
pumped to four steam generators, where
the heated water is converted to steam.
The steam is then used to turn turbines,
which are connected to electrical
generators that produce electricity. A
simplified drawing of a PWR can be
viewed at https://www.nrc.gov/reactors/
pwrs.html.
The reactor, steam generators, and
other components are housed in a
concrete and steel containment
structure (building). The containment
structure is a reinforced concrete
cylinder with a concrete slab base and
hemispherical dome. A welded steel
liner is attached to the inside face of the
concrete shell to ensure a high degree of
leak tightness. In addition, the 4-foot
(1.2-meter)-thick concrete walls of the
containment structure serve as a
radiation shield. Additional information
on the plant structures and systems, as
well as the environmental impact
statement for license renewal, can be
found in NUREG–1437, Supplement 51,
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‘‘Generic Environmental Impact
Statement for License Renewal of
Nuclear Plants: Supplement 51
Regarding Callaway Plant, Unit 1: Final
Report.’’
Radiological and non-radiological
impacts on the environment that may
result from granting the regulatory
exemptions and issuing the license
amendment are summarized in the
following sections.
Non-Radiological Impacts
No changes would be made to
structures or land use within the
Callaway site as a result of the proposed
action, and non-radiological liquid
effluents or gaseous emissions would
not change. In addition, the license
amendment and regulatory exemptions
would not result in any changes to the
use of resources or create any new
environmental impacts. Therefore, there
would be no non-radiological impacts to
environmental resources or any
irreversible and irretrievable
commitments.
Since granting the regulatory
exemptions and issuing the license
amendment would not result in
environmental effects, there would be
no non-radiological cumulative impact.
Radiological Impacts
Radioactive Gaseous and Liquid
Effluents and Solid Waste
Callaway uses waste treatment
systems to collect, process, recycle, and
dispose of gaseous, liquid, and solid
wastes that contain radioactive material
in a safe and controlled manner within
NRC and Environmental Protection
Agency (EPA) radiation safety
standards.
The license amendment and
regulatory exemptions, if granted,
would not require any physical change
to the nuclear plant or reactor
operations; therefore, there would be no
changes to the plant radioactive waste
treatment systems. A detailed
description of the Callaway radioactive
waste handling and disposal activities is
presented in chapter 2.1.2 of
Supplement 51 to NUREG–1437.
Radioactive Gaseous Effluents
The objectives of the Callaway
gaseous waste management system
(GWMS) are to process and control the
release of radioactive gaseous effluents
into the environment to be within the
requirements of 10 CFR 20.1301, ‘‘Dose
limits for individual members of the
public,’’ and to be consistent with the as
low as reasonably achievable (ALARA)
dose objectives set forth in Appendix I
to 10 CFR part 50. The GWMS is
designed so that radiation exposure to
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plant workers is within the dose limits
in 10 CFR 20.1201, ‘‘Occupational dose
limits for adults.’’
Granting the regulatory exemptions
and issuing the license amendment
would not require any physical changes
to the nuclear plant or reactor
operations that would affect the release
of radioactive gaseous effluents into the
environment; therefore, there would be
no changes to the GWMS. The existing
equipment and plant procedures that
control radioactive releases to the
environment would continue to be used
to maintain radioactive gaseous releases
within the dose limits in 10 CFR
20.1301 and the ALARA dose objectives
in Appendix I to 10 CFR part 50.
Radioactive Liquid Effluents
The function of the Callaway liquid
waste processing system (LWPS) is to
collect and process radioactive liquid
wastes to reduce radioactivity and
chemical concentrations to levels
acceptable for discharge to the
environment or to recycle the liquids for
use in plant systems. The principal
objectives of the LWPS are to collect
liquid effluents (wastes) that may
contain radioactive material and to
maintain sufficient processing
capability so that liquid waste may be
discharged to the environment below
the regulatory limits in 10 CFR 20.1301
and consistent with the ALARA dose
objectives in Appendix I to 10 CFR part
50. The liquid effluent is routed through
a monitor that measures the
radioactivity and can automatically
terminate the release in the event
radioactivity exceeds predetermined
levels. The liquid effluent is discharged
from the plant into the Missouri River
via a pipeline.
Granting the regulatory exemptions
and issuing the license amendment
would not require any physical change
to the nuclear plant or reactor
operations; therefore, there would be no
changes to the LWPS. The existing
equipment and plant procedures that
control radioactive releases to the
environment will continue to be used to
maintain radioactive liquid releases
within the dose limits in 10 CFR
20.1301 and the ALARA dose objectives
in Appendix I to 10 CFR part 50.
Radioactive Solid Wastes
The function of the Callaway solid
waste processing system (SWPS) is to
process, package, and store the solid
radioactive wastes generated by nuclear
plant operations until they are shipped
off site to a vendor for further
processing or for permanent disposal at
a licensed burial facility, or both. The
storage areas have restricted access and
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shielding to reduce radiation rates to
plant workers. The principal objectives
of the SWPS are to package and
transport the waste in compliance with
NRC regulations in 10 CFR part 61,
‘‘Licensing Requirements for Land
Disposal of Radioactive Waste,’’ and 10
CFR part 71, ‘‘Packaging and
Transportation of Radioactive Material,’’
and the U.S. Department of
Transportation regulations in 49 CFR
parts 170 through 179; and to maintain
the dose limits in 10 CFR 20.1201, 10
CFR 20.1301, and Appendix I to 10 CFR
part 50.
The existing equipment and plant
procedures that control radioactive solid
waste handling would continue to be
used to maintain exposures within the
dose limits in 10 CFR 20.1201, 10 CFR
20.1301, and 10 CFR part, 50 appendix
I. Therefore, there will be no changes to
the SWPS and issuing the license
amendment and granting the regulatory
exemptions will not result in any
physical changes to the nuclear plant or
reactor operations that would affect the
release of radioactive solid wastes into
the environment.
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Occupational Radiation Doses
The license amendment and
regulatory exemptions, if granted,
would not require any physical change
to the nuclear plant or changes to
reactor operations; therefore, there
would be no change to any in-plant
radiation sources. In addition, no new
operator actions would be implemented
that could affect occupational radiation
exposure. The licensee’s radiation
protection program monitors radiation
levels throughout the nuclear plant to
establish appropriate work controls,
training, temporary shielding, and
protective equipment requirements so
that worker doses remain within the
dose limits in 10 CFR part 20,
‘‘Standards for Protection Against
Radiation,’’ subpart C, ‘‘Occupational
Dose Limits.’’ The license amendment
and regulatory exemptions would not
change radiation levels within the
nuclear plant and, therefore, there
would be no increased radiological
impact to the workers.
Offsite Radiation Dose
The primary sources of offsite dose to
members of the public from Callaway
are radioactive gaseous and liquid
effluents. As discussed previously, there
would be no change to the operation of
Callaway radioactive GWMS and LWPS
or their ability to perform their intended
functions. Also, there would be no
change to the Callaway radiation
monitoring system and procedures used
to control the release of radioactive
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effluents in accordance with radiation
protection standards in 10 CFR 20.1301,
40 CFR part 190, ‘‘Environmental
Radiation Protection Standards for
Nuclear Power Operations,’’ and the
ALARA dose objectives in appendix I to
10 CFR part 50.
Based on this information, the offsite
radiation dose to members of the public
would not change and would continue
to be within regulatory limits.
Therefore, the license amendment and
regulatory exemptions would not
change offsite dose levels and,
consequently, there would be no
significant health effects from the
proposed action.
Design-Basis Accidents
Design-basis accidents at Callaway,
are evaluated by both the licensee and
the NRC to ensure that the unit would
continue to withstand the spectrum of
postulated accidents without undue
hazard to the public health and safety
and to ensure the protection of the
environment.
Separate from its environmental
review, the NRC is evaluating the
licensee’s technical and safety analyses
provided in support of the proposed
action. The results of the NRC staff’s
safety review and conclusion will be
documented in a publicly available
safety evaluation. The NRC staff must
conclude in its safety evaluation that
taking the proposed action will (1)
provide reasonable assurance that the
health and safety of the public will not
be endangered by operation in the
proposed manner, (2) provide
reasonable assurance that such activities
will be conducted in compliance with
the Commission’s regulations, and (3)
not be inimical to the common defense
and security or to the health and safety
of the public. The NRC will not take the
proposed action absent such a safety
conclusion.
Radiological Cumulative Impacts
The radiological dose limits for
protection of the public and plant
workers have been developed by the
NRC and the EPA to address the
cumulative impact of acute and longterm exposure to radiation and
radioactive material. These dose limits
are codified in 10 CFR part 20 and 40
CFR part 190.
Cumulative radiation doses are
required to be within the limits set forth
in the regulations cited in the previous
paragraph. The license amendment and
exemptions would not require physical
changes to the plant or changes to plant
activities; in-plant radiation sources
would not change and offsite radiation
dose to members of the public would
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not change. Therefore, the NRC staff
concludes that there would be no
significant cumulative radiological
impact from the proposed action.
Radiological Impacts Summary
Based on these evaluations, the
license amendment and exemptions
would not result in any significant
radiological impacts. Therefore, the
safety evaluation must conclude that the
proposed action will (1) provide
reasonable assurance that the health and
safety of the public will not be
endangered by operation in the
proposed manner, (2) provide
reasonable assurance that such activities
will be conducted in compliance with
the Commission’s regulations, and (3)
not be inimical to the common defense
and security or to the health and safety
of the public. The NRC would not take
the proposed action absent such a safety
conclusion.
Environmental Impacts of the
Alternatives to the Proposed Action
As discussed earlier, licensees have
options for responding to GL 2004–02
and for demonstrating compliance with
10 CFR 50.46. Consistent with these
options and as an alternative to the
proposed action, the licensee could
choose to remove and replace insulation
within the reactor containment
building. This alternative would require
the physical removal and disposal of
significant amounts of insulation from a
radiation area within the reactor
containment building, and the
installation of new insulation less likely
to impact sump performance.
The removal of the existing insulation
from the containment building would
generate radiologically contaminated
waste. Ameren estimated that
approximately 5,500 cubic feet (6.6
tons) of fiberglass insulation would have
to be removed from the Callaway
containment. The removed insulation
would require special handling and
packaging so that it could be safely
transported from the site. The licensee
would likely use existing facilities to
process and store this material until it
could be transported to a low-level
radioactive or hazardous waste disposal
site. Energy (fuel) would be expended to
transport the insulation and land would
be expended at the disposal site.
The removal of the old insulation and
installation of new insulation would
expose workers to radiation. Based on
planning documents prepared in 2010,
Ameren estimated that the expected
total dose for replacing insulation in
Callaway, would be between 350 and
400 person-rem. This estimate was
considered in line with estimates from
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Federal Register / Vol. 87, No. 166 / Monday, August 29, 2022 / Notices
other utilities impacted by this same
issue. Ameren also indicated that this
initial estimate would now likely be
higher due to the intervening 12 years
of continuous plant operation. The NRC
reviewed NUREG–0713, Volume 41,
‘‘Occupational Radiation Exposure at
Commercial Nuclear Power Reactors
and Other Facilities: Fifty-Second
Annual Report,’’ and determined that
Ameren’s average baseline collective
radiation exposure is approximately 22
person-rem. The additional 350 to 400plus person-rem collective exposure
would be shared across the entire work
force involved with removing and
reinstalling insulation. In SECY–12–
0093, the NRC staff attempted to
develop a total occupational dose
estimate for the work involved in
insulation removal and replacement
associated with GSI–191. Due to
uncertainties in the scope of work
required to remove and replace
insulation at a specific nuclear plant
and other site-specific factors such as
source term and hazardous materials,
the NRC staff was unable to estimate the
total occupational dose associated with
this work. However, dose estimates
were provided by the Nuclear Energy
Institute (NEI) in a letter to the NRC
dated March 30, 2012, based on
information collected on occupational
radiation exposures that have been, or
could be, incurred during insulation
removal and replacement. In the letter,
NEI noted similar difficulties in
estimating the potential amount of
radiation exposure, but provided a ‘‘per
unit’’ estimate of between 80 and 525
person-rem. Given uncertainties in the
scope of work and other nuclear plantspecific factors such as source term and
hazardous materials, the NRC staff
found no basis to conclude that the NEI
estimates were unreasonable.
Accordingly, because Ameren’s estimate
of potential additional radiation
exposure resulting from the alternative
approach of removing and replacing
insulation is consistent with the NEI
estimated range, the NRC staff considers
Ameren’s estimate to be reasonable.
As stated in the ‘‘Occupational
Radiation Doses’’ section of this
document, Ameren’s radiation
protection program monitors radiation
levels throughout the nuclear plant to
establish appropriate work controls,
training, temporary shielding, and
protective equipment requirements so
that worker doses are expected to
remain within the dose limits in 10 CFR
20.1201.
In addition, as stated in the ‘‘Offsite
Radiation Dose’’ section of this
document, Ameren also has a radiation
monitoring system and procedures in
place to control the release of
radioactive effluents in accordance with
radiation protection standards in 10
CFR 20.1301, 40 CFR part 190, and the
ALARA dose objectives in appendix I to
10 CFR part 50. Therefore, radiation
exposure to members of the public
would be maintained within the NRC
dose criteria in 10 CFR 20.1301, 40 CFR
part 190, and the ALARA dose
objectives of appendix I to 10 CFR part
50.
Based on this information, impacts to
members of the public from removing
and replacing insulation within the
reactor containment building would not
be significant. However, impacts to
plant workers and the environment from
implementing this alternative would be
greater than implementing the proposed
action.
Alternative Use of Resources
The proposed action would not
involve the use of any different
resources (e.g., water, air, land, nuclear
fuel) not previously considered in
NUREG–1437, Supplement 51.
Agencies and Persons Consulted
In accordance with its stated policy,
on June 27, 2022, the NRC staff
consulted with the State of Missouri
official, Mr. Aaron Schmidt, regarding
the environmental impact of the
proposed action. The State of Missouri
official has not provided any comments
on the EA and FONSI.
III. Finding of No Significant Impact
The licensee requested to amend
Renewed Facility Operating License No.
NPF–30 to grant exemptions for
Callaway, from certain requirements of
10 CFR 50.46(a)(1) and 10 CFR part 50,
appendix A, GDC 35, 38, and 41. This
proposed action would not significantly
affect plant safety, would not have a
significant adverse effect on the
probability of an accident occurring,
and would not have any significant
radiological or non-radiological impacts.
It would also not result in any changes
to radioactive effluents or emissions,
exposures to nuclear plant workers and
members of the public, or any changes
to radiological and non-radiological
impacts to the environment.
Consistent with 10 CFR 51.21, the
NRC conducted an environmental
review of the proposed action. Based on
the EA included in Section II of this
notice and incorporated by reference in
this FONSI, the NRC staff finds that the
proposed action will not have a
significant effect on the quality of the
human environment. Accordingly, the
NRC has determined there is no need to
prepare an environmental impact
statement for the proposed action.
The NRC staff’s evaluation considered
the information provided in the
licensee’s application as supplemented,
and the NRC staff’s review of related
environmental documents. Section IV of
this notice lists documents related to the
proposed action and includes
information on the availability of the
documents, including the related
environmental document NUREG–1437,
Supplement 51, which provides the
latest environmental review of current
operations and description of
environmental conditions at Callaway.
This FONSI and other related
environmental documents may be
examined, and/or copied for a fee, at the
NRC’s PDR, located at One White Flint
North, 11555 Rockville Pike, Rockville,
Maryland 20852. Publicly available
records are also accessible online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. Persons who do not have
access to ADAMS or who encounter
problems in accessing the documents
located in ADAMS should contact the
NRC’s PDR reference staff by telephone
at 1–800–397–4209 or 301–415–4737, or
by email to PDR.Resource@nrc.gov.
IV. Availability of Documents.
The documents identified in the
following table are available to
interested persons through one or more
of the following methods, as indicated.
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Document
ADAMS accession No.
U.S. Nuclear Regulatory Commission. Generic Letter 2004–02: ‘‘Potential Impact of Debris Blockage on Emergency
Recirculation During Design Basis Accidents at Pressurized-Water Reactors,’’ dated September 13, 2004.
U.S. Nuclear Regulatory Commission. NUREG–0897, ‘‘Containment Emergency Sump Performance: Technical
Findings Related to Unresolved Safety Issue A–43, Revision 1, October 1985.
Ameren Missouri. Letter ULNRC–06526, ‘‘Request for License Amendment and Regulatory Exemptions for a
Risk-Informed Approach to Address GSI–191 and Respond to GL 2004–02,’’ dated March 31, 2021.
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Document
ADAMS accession No.
Ameren Missouri. Letter ULNRC–06664, ‘‘Supplement to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI–191 and Respond to GL 2004–02 (LDCN 19–0014),’’ dated
May 27, 2021.
Ameren Missouri. Letter ULNRC–06651, ‘‘Supplement to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI–191 and Respond to GL 2004–02 (LDCN 19–0014),’’ dated
July 22, 2021.
Ameren Missouri. Letter ULNRC–06683, ‘‘Transmittal of Documents Identified from NRC Audit of License Amendment Request Regarding Risk-Informed Approach to Closure of Generic Safety Issue 191 (EPID L–2021–LLA–
0059),’’ dated August 23, 2021.
Ameren Missouri. Letter ULNRC–06692, ‘‘Third Supplement to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI–191 and Respond to GL 2004–02 (LDCN 19–0014),’’
dated October 7, 2021.
Ameren Missouri. Letter ULNRC–06690, ‘‘Fourth (Post-Audit) Supplement to Request for License Amendment and
Regulatory Exemptions for a Risk-Informed Approach to Address GSI–191 and Respond to GL 2004–02 (LDCN
19–0014),’’ dated January 27, 2022.
Ameren Missouri. Letter ULNRC–06721, ‘‘Fifth (Post-Audit) Supplement to Request for License Amendment and
Regulatory Exemptions for a Risk-Informed Approach to Address GSI–191 and Respond to GL 2004–02 (LDCN
19–0014),’’ dated March 8, 2022.
Ameren Missouri. Letter ULNRC–06735, ‘‘Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI–191 and Respond to
Generic Letter 2004–02,’’ dated May 26, 2022.
Nuclear Energy Institute. GSI–191 Dose Estimates, dated March 30, 2012 ..................................................................
SECY–12–0093, ‘‘Closure Options for Generic Safety Issue—191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance,’’ dated July 9, 2012.
SRM–SECY–12–0093, ‘‘Staff Requirements—SECY–12–0093—Closure Options for Generic Safety Issue—191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance,’’ dated December 14, 2012.
U.S. Nuclear Regulatory Commission. NUREG–1437, Supplement 51, ‘‘Generic Environmental Impact Statement for
License Renewal of Nuclear Plants: Supplement 51 Regarding Callaway Plant, Unit 1: Final Report,’’ October
2014.
U.S. Nuclear Regulatory Commission. NUREG–0713, Volume 41, ‘‘Occupational Radiation Exposure at Commercial
Nuclear Power Reactors and Other Facilities 2019: Fifty-Second Annual Report,’’ April 2022.
Dated: August 23, 2022.
For the Nuclear Regulatory Commission.
Siva P. Lingam,
Project Manager, Plant Licensing Branch IV,
Division of Operator Reactor Licensing, Office
of Nuclear Reactor Regulation.
[FR Doc. 2022–18498 Filed 8–26–22; 8:45 am]
BILLING CODE 7590–01–P
PENSION BENEFIT GUARANTY
CORPORATION
Proposed Submission of Information
Collection for OMB Review; Comment
Request; Annual Reporting (Form 5500
Series)
Pension Benefit Guaranty
Corporation.
ACTION: Notice of intent to request
extension of OMB approval of
information collection.
AGENCY:
The Pension Benefit Guaranty
Corporation (PBGC) intends to request
that the Office of Management and
Budget (OMB) extend approval, with
modifications, under the Paperwork
Reduction Act, of a collection of
information for Annual Reporting under
OMB control number 1212–0057, which
expires on June 30, 2025. This notice
informs the public of PBGC’s intent and
solicits public comment on the
collection of information.
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Comments must be submitted on
or before October 28, 2022.
ADDRESSES: Comments may be
submitted by any of the following
methods:
• Federal eRulemaking Portal: https://
www.regulations.gov. Follow the online
instructions for submitting comments.
• Email: paperwork.comments@
pbgc.gov. Refer to OMB control number
1212–0057 in the subject line.
• Mail or Hand Delivery: Regulatory
Affairs Division, Office of the General
Counsel, Pension Benefit Guaranty
Corporation, 445 12th Street SW,
Washington, DC 20024–2101.
Commenters are strongly encouraged
to submit public comments
electronically. PBGC expects to have
limited personnel available to process
public comments that are submitted on
paper through mail. Until further notice,
any comments submitted on paper will
be considered to the extent practicable.
All submissions must include the
agency’s name (Pension Benefit
Guaranty Corporation, or PBGC) and
refer to OMB control number 1212–
0057. Comments received will be posted
without change to PBGC’s website,
www.pbgc.gov, including any personal
information provided. Do not submit
comments that include any personally
identifiable information or confidential
business information.
DATES:
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ML22146A337 (package).
ML12095A319
ML121320270 (package).
ML12349A378
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ML22111A013
Copies of the collection of
information may be obtained by writing
to Disclosure Division, Office of the
General Counsel, Pension Benefit
Guaranty Corporation, 445 12th Street
SW, Washington, DC 20024–2101, or
calling 202–229–4040 during normal
business hours. If you are deaf or hard
of hearing, or have a speech disability,
please dial 7–1–1 to access
telecommunications relay services.
FOR FURTHER INFORMATION CONTACT:
Karen Levin (levin.karen@pbgc.gov),
Attorney, Regulatory Affairs Division,
Office of the General Counsel, Pension
Benefit Guaranty Corporation, 445 12th
Street SW, Washington, DC 20024–2101,
202–229–3559. If you are deaf or hard
of hearing, or have a speech disability,
please dial 7–1–1 to access
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SUPPLEMENTARY INFORMATION: Annual
reporting to the Internal Revenue
Service (IRS), the Employee Benefits
Security Administration (EBSA), and
the Pension Benefit Guaranty
Corporation (PBGC) is required by law
for most employee benefit plans. For
example, section 4065 of the Employee
Retirement Income Security Act of 1974
(ERISA) requires annual reporting to
PBGC for pension plans covered by title
IV of ERISA. To accommodate these
filing requirements, IRS, EBSA, and
PBGC have jointly promulgated the
Form 5500 Series, which includes the
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[Federal Register Volume 87, Number 166 (Monday, August 29, 2022)]
[Notices]
[Pages 52816-52821]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2022-18498]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-483; NRC-2022-0139]
Union Electric Company, dba Ameren Missouri, Callaway Plant, Unit
No. 1
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental assessment and finding of no significant impact;
issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an
environmental assessment (EA) prepared under the National Environmental
Policy Act of 1969 (NEPA) and NRC's regulations. This EA summarizes the
results of the NRC staff's environmental review, which evaluates the
potential environmental impacts of granting exemptions from NRC
regulations and issuing an associated license amendment in response to
a request from the Union Electric Company, doing business as (dba)
Ameren Missouri (Ameren, the licensee) for Renewed Facility Operating
License NPF-30, for the Callaway Plant, Unit No. 1 (Callaway).
Specifically, the licensee is seeking a license amendment and
regulatory exemptions that would, if granted, allow the licensee to use
both a deterministic and risk-informed approach to address safety
issues discussed in Generic Safety Issue (GSI)-191, ``Assessment of
Debris Accumulation in PWR [Pressurized Water Reactor] Sump Pump
Performance'' and to close Generic
[[Page 52817]]
Letter (GL) 2004-02, ``Potential Impact of Debris Blockage on Emergency
Recirculation During Design Basis Accidents at Pressurized-Water
Reactors.'' The NRC staff is issuing a final EA and finding of no
significant impact (FONSI) associated with the proposed exemptions.
DATES: The EA and FONSI referenced in this document is available on
August 29, 2022.
ADDRESSES: Please refer to Docket ID NRC-2022-0139 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-2022-0139. Address
questions about Docket IDs in Regulations.gov to Stacy Schumann;
telephone: 301-415-0624; 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]. For the convenience of the reader,
instructions about obtaining materials referenced in this document are
provided in the ``Availability of Documents'' section.
NRC's PDR: You may examine and purchase copies of public
documents, by appointment, at the NRC's PDR, Room P1 B35, One White
Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. To make
an appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between
8:00 a.m. and 4:00 p.m. Eastern Time (ET), Monday through Friday,
except Federal holidays.
FOR FURTHER INFORMATION CONTACT: Mahesh Chawla, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-8371, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering a request to grant certain regulatory
exemptions and issue a license amendment for Renewed Facility Operating
License NPF-30, issued to Ameren, for Callaway, located in Callaway
County, Missouri. The regulatory exemptions and associated license
amendment, if granted, would allow Ameren to incorporate the use of a
risk-informed approach to address safety issues discussed in GSI-191
and respond to GL 2004-02. Pursuant to Section 51.21 of title 10 of the
Code of Federal Regulations (10 CFR), ``Criteria for and identification
of licensing and regulatory actions requiring environmental
assessments,'' the NRC has prepared an EA summarizing the findings of
the NEPA review of the proposed action. The NRC concluded that the
proposed action will have no significant environmental impact. In
accordance with 10 CFR 51.31(a), the NRC has determined not to prepare
an environmental impact statement for the proposed licensing actions
and is issuing a FONSI.
The NRC established GSI-191 to determine whether the transport and
accumulation of debris from a loss-of-coolant accident (LOCA) in the
PWR containment structure would impede the operation of the emergency
core cooling system (ECCS) or containment spray system (CSS). A LOCA
within the containment structure is assumed to be caused by a break in
the primary coolant loop piping. Water discharged from the pipe break
and debris would collect on the containment structure floor and within
the containment emergency sump. During this type of accident, the ECCS
and CSS would initially draw cooling water from the refueling water
storage tank. However, realigning the ECCS pumps to the containment
emergency sump would provide long-term cooling of the reactor core.
Therefore, successful long-term cooling depends on the ability of the
containment emergency sump to provide adequate flow to the residual
heat removal (RHR) recirculation pumps for extended periods of time.
One of the concerns addressed by the implementation of GSI-191 is
that debris material, such as insulation installed on piping and
components, within the containment structure, could be dislodged by a
jet of high-pressure water and steam during the LOCA. Water, along with
debris, would accumulate at the bottom of the containment structure and
flow towards the emergency sump pumps. Insulation and other fibrous
debris material could block the emergency sump screens and suction
strainers, which in turn could prevent the ability of the containment
emergency sump to provide adequate water flow to the RHR pumps (for
more information, see NUREG-0897, ``Containment Emergency Sump
Performance: Technical Finding Related to Unresolved Safety Issue A-
43,'' Revision 1).
The NRC issued GL 2004-02 to address this safety concern by
requesting PWR licensees, pursuant to 10 CFR 50.54(f), to use an NRC-
approved methodology to perform a ``mechanistic evaluation of the
potential for the adverse effects of post-accident debris blockage and
operation with debris-laden fluids to impede or prevent the
recirculation functions of the ECCS and CSS following all postulated
accidents for which the recirculation of these systems is required''
and submit this information to the NRC for evaluation.
In 2012, the NRC staff developed options for resolution of GSI-191,
which are discussed in SECY-12-0093, ``Closure Options for Generic
Safety Issue 191, Assessment of Debris Accumulation on Pressurized-
Water Reactor Sump Performance,'' dated July 9, 2012. The licensee has
proposed to use both a deterministic method, with plant-specific
testing, and a risk-informed approach to demonstrate compliance with 10
CFR 50.46, ``Acceptance criteria for emergency core colling systems for
light-water nuclear power reactors,'' and 10 CFR part 50, appendix A,
General Design Criteria (GDC) 35, ``Emergency core cooling,'' GDC 38,
``Containment heat removal,'' and GDC 41, ``Containment atmosphere
cleanup,'' and to resolve GSI-191 for Callaway. Because, historically,
the NRC staff has not allowed licensees to use a risk-informed approach
to show compliance with the requirements of 10 CFR 50.46, the licensee
requested exemptions from 10 CFR 50.46(a)(1) and GDC 35, 38, and 41, as
well as an amendment to the associated technical specifications to
allow the use of a risk-informed approach to resolve GSI-191. If
approved, the proposed action would not authorize any modifications
within the containment structure, physical changes to the ECCS, or
other modifications to the plant. Rather, the proposed action would
only allow the use of an alternate methodology to show compliance with
the regulations that require the ECCS and CSS function during certain
LOCA events.
II. Environmental Assessment
Description of the Proposed Action
The proposed action as requested by the licensee is to grant
certain regulatory exemptions and amend Facility Operating License NPF-
30. The regulatory exemptions would allow
[[Page 52818]]
Ameren to change the licensing basis LOCA analysis identified in the
updated final safety analysis report to use a risk-informed approach to
address safety issues discussed in GSI-191 and to close GL 2004 02. If
approved, no physical modifications to the nuclear plant or changes to
reactor operations involving the ECCS would be required. The proposed
action is in response to the licensee's application dated March 31,
2021, as supplemented by letters dated May 27, 2021; July 22, 2021;
August 23, 2021; October 7, 2021; January 27, 2022; March 8, 2022; and
May 26, 2022.
Need for the Proposed Action
The proposed action is needed because, as the holder of Renewed
Facility Operating License No. NPF-30, Ameren is expected to address
the safety issues discussed in GSI-191 and to close GL 2004-02 for
Callaway. Consistent with SECY-12-0093, the licensee chose an approach,
which requires, in part, that Ameren request that the NRC amend the
renewed facility operating license and grant certain regulatory
exemptions for Callaway.
Environmental Impacts of the Proposed Action
Callaway is located on an approximately 7,354-acre (2,976 hectare)
site in Callaway County, Missouri, approximately 10 miles (16
kilometers) southeast of Fulton, Missouri, and 80 miles (129
kilometers) west of the St. Louis metropolitan area.
Callaway consists of a single four-loop Westinghouse PWR unit. The
reactor core of the unit heats water, which is pumped to four steam
generators, where the heated water is converted to steam. The steam is
then used to turn turbines, which are connected to electrical
generators that produce electricity. A simplified drawing of a PWR can
be viewed at https://www.nrc.gov/reactors/pwrs.html.
The reactor, steam generators, and other components are housed in a
concrete and steel containment structure (building). The containment
structure is a reinforced concrete cylinder with a concrete slab base
and hemispherical dome. A welded steel liner is attached to the inside
face of the concrete shell to ensure a high degree of leak tightness.
In addition, the 4-foot (1.2-meter)-thick concrete walls of the
containment structure serve as a radiation shield. Additional
information on the plant structures and systems, as well as the
environmental impact statement for license renewal, can be found in
NUREG-1437, Supplement 51, ``Generic Environmental Impact Statement for
License Renewal of Nuclear Plants: Supplement 51 Regarding Callaway
Plant, Unit 1: Final Report.''
Radiological and non-radiological impacts on the environment that
may result from granting the regulatory exemptions and issuing the
license amendment are summarized in the following sections.
Non-Radiological Impacts
No changes would be made to structures or land use within the
Callaway site as a result of the proposed action, and non-radiological
liquid effluents or gaseous emissions would not change. In addition,
the license amendment and regulatory exemptions would not result in any
changes to the use of resources or create any new environmental
impacts. Therefore, there would be no non-radiological impacts to
environmental resources or any irreversible and irretrievable
commitments.
Since granting the regulatory exemptions and issuing the license
amendment would not result in environmental effects, there would be no
non-radiological cumulative impact.
Radiological Impacts
Radioactive Gaseous and Liquid Effluents and Solid Waste
Callaway uses waste treatment systems to collect, process, recycle,
and dispose of gaseous, liquid, and solid wastes that contain
radioactive material in a safe and controlled manner within NRC and
Environmental Protection Agency (EPA) radiation safety standards.
The license amendment and regulatory exemptions, if granted, would
not require any physical change to the nuclear plant or reactor
operations; therefore, there would be no changes to the plant
radioactive waste treatment systems. A detailed description of the
Callaway radioactive waste handling and disposal activities is
presented in chapter 2.1.2 of Supplement 51 to NUREG-1437.
Radioactive Gaseous Effluents
The objectives of the Callaway gaseous waste management system
(GWMS) are to process and control the release of radioactive gaseous
effluents into the environment to be within the requirements of 10 CFR
20.1301, ``Dose limits for individual members of the public,'' and to
be consistent with the as low as reasonably achievable (ALARA) dose
objectives set forth in Appendix I to 10 CFR part 50. The GWMS is
designed so that radiation exposure to plant workers is within the dose
limits in 10 CFR 20.1201, ``Occupational dose limits for adults.''
Granting the regulatory exemptions and issuing the license
amendment would not require any physical changes to the nuclear plant
or reactor operations that would affect the release of radioactive
gaseous effluents into the environment; therefore, there would be no
changes to the GWMS. The existing equipment and plant procedures that
control radioactive releases to the environment would continue to be
used to maintain radioactive gaseous releases within the dose limits in
10 CFR 20.1301 and the ALARA dose objectives in Appendix I to 10 CFR
part 50.
Radioactive Liquid Effluents
The function of the Callaway liquid waste processing system (LWPS)
is to collect and process radioactive liquid wastes to reduce
radioactivity and chemical concentrations to levels acceptable for
discharge to the environment or to recycle the liquids for use in plant
systems. The principal objectives of the LWPS are to collect liquid
effluents (wastes) that may contain radioactive material and to
maintain sufficient processing capability so that liquid waste may be
discharged to the environment below the regulatory limits in 10 CFR
20.1301 and consistent with the ALARA dose objectives in Appendix I to
10 CFR part 50. The liquid effluent is routed through a monitor that
measures the radioactivity and can automatically terminate the release
in the event radioactivity exceeds predetermined levels. The liquid
effluent is discharged from the plant into the Missouri River via a
pipeline.
Granting the regulatory exemptions and issuing the license
amendment would not require any physical change to the nuclear plant or
reactor operations; therefore, there would be no changes to the LWPS.
The existing equipment and plant procedures that control radioactive
releases to the environment will continue to be used to maintain
radioactive liquid releases within the dose limits in 10 CFR 20.1301
and the ALARA dose objectives in Appendix I to 10 CFR part 50.
Radioactive Solid Wastes
The function of the Callaway solid waste processing system (SWPS)
is to process, package, and store the solid radioactive wastes
generated by nuclear plant operations until they are shipped off site
to a vendor for further processing or for permanent disposal at a
licensed burial facility, or both. The storage areas have restricted
access and
[[Page 52819]]
shielding to reduce radiation rates to plant workers. The principal
objectives of the SWPS are to package and transport the waste in
compliance with NRC regulations in 10 CFR part 61, ``Licensing
Requirements for Land Disposal of Radioactive Waste,'' and 10 CFR part
71, ``Packaging and Transportation of Radioactive Material,'' and the
U.S. Department of Transportation regulations in 49 CFR parts 170
through 179; and to maintain the dose limits in 10 CFR 20.1201, 10 CFR
20.1301, and Appendix I to 10 CFR part 50.
The existing equipment and plant procedures that control
radioactive solid waste handling would continue to be used to maintain
exposures within the dose limits in 10 CFR 20.1201, 10 CFR 20.1301, and
10 CFR part, 50 appendix I. Therefore, there will be no changes to the
SWPS and issuing the license amendment and granting the regulatory
exemptions will not result in any physical changes to the nuclear plant
or reactor operations that would affect the release of radioactive
solid wastes into the environment.
Occupational Radiation Doses
The license amendment and regulatory exemptions, if granted, would
not require any physical change to the nuclear plant or changes to
reactor operations; therefore, there would be no change to any in-plant
radiation sources. In addition, no new operator actions would be
implemented that could affect occupational radiation exposure. The
licensee's radiation protection program monitors radiation levels
throughout the nuclear plant to establish appropriate work controls,
training, temporary shielding, and protective equipment requirements so
that worker doses remain within the dose limits in 10 CFR part 20,
``Standards for Protection Against Radiation,'' subpart C,
``Occupational Dose Limits.'' The license amendment and regulatory
exemptions would not change radiation levels within the nuclear plant
and, therefore, there would be no increased radiological impact to the
workers.
Offsite Radiation Dose
The primary sources of offsite dose to members of the public from
Callaway are radioactive gaseous and liquid effluents. As discussed
previously, there would be no change to the operation of Callaway
radioactive GWMS and LWPS or their ability to perform their intended
functions. Also, there would be no change to the Callaway radiation
monitoring system and procedures used to control the release of
radioactive effluents in accordance with radiation protection standards
in 10 CFR 20.1301, 40 CFR part 190, ``Environmental Radiation
Protection Standards for Nuclear Power Operations,'' and the ALARA dose
objectives in appendix I to 10 CFR part 50.
Based on this information, the offsite radiation dose to members of
the public would not change and would continue to be within regulatory
limits. Therefore, the license amendment and regulatory exemptions
would not change offsite dose levels and, consequently, there would be
no significant health effects from the proposed action.
Design-Basis Accidents
Design-basis accidents at Callaway, are evaluated by both the
licensee and the NRC to ensure that the unit would continue to
withstand the spectrum of postulated accidents without undue hazard to
the public health and safety and to ensure the protection of the
environment.
Separate from its environmental review, the NRC is evaluating the
licensee's technical and safety analyses provided in support of the
proposed action. The results of the NRC staff's safety review and
conclusion will be documented in a publicly available safety
evaluation. The NRC staff must conclude in its safety evaluation that
taking the proposed action will (1) provide reasonable assurance that
the health and safety of the public will not be endangered by operation
in the proposed manner, (2) provide reasonable assurance that such
activities will be conducted in compliance with the Commission's
regulations, and (3) not be inimical to the common defense and security
or to the health and safety of the public. The NRC will not take the
proposed action absent such a safety conclusion.
Radiological Cumulative Impacts
The radiological dose limits for protection of the public and plant
workers have been developed by the NRC and the EPA to address the
cumulative impact of acute and long-term exposure to radiation and
radioactive material. These dose limits are codified in 10 CFR part 20
and 40 CFR part 190.
Cumulative radiation doses are required to be within the limits set
forth in the regulations cited in the previous paragraph. The license
amendment and exemptions would not require physical changes to the
plant or changes to plant activities; in-plant radiation sources would
not change and offsite radiation dose to members of the public would
not change. Therefore, the NRC staff concludes that there would be no
significant cumulative radiological impact from the proposed action.
Radiological Impacts Summary
Based on these evaluations, the license amendment and exemptions
would not result in any significant radiological impacts. Therefore,
the safety evaluation must conclude that the proposed action will (1)
provide reasonable assurance that the health and safety of the public
will not be endangered by operation in the proposed manner, (2) provide
reasonable assurance that such activities will be conducted in
compliance with the Commission's regulations, and (3) not be inimical
to the common defense and security or to the health and safety of the
public. The NRC would not take the proposed action absent such a safety
conclusion.
Environmental Impacts of the Alternatives to the Proposed Action
As discussed earlier, licensees have options for responding to GL
2004-02 and for demonstrating compliance with 10 CFR 50.46. Consistent
with these options and as an alternative to the proposed action, the
licensee could choose to remove and replace insulation within the
reactor containment building. This alternative would require the
physical removal and disposal of significant amounts of insulation from
a radiation area within the reactor containment building, and the
installation of new insulation less likely to impact sump performance.
The removal of the existing insulation from the containment
building would generate radiologically contaminated waste. Ameren
estimated that approximately 5,500 cubic feet (6.6 tons) of fiberglass
insulation would have to be removed from the Callaway containment. The
removed insulation would require special handling and packaging so that
it could be safely transported from the site. The licensee would likely
use existing facilities to process and store this material until it
could be transported to a low-level radioactive or hazardous waste
disposal site. Energy (fuel) would be expended to transport the
insulation and land would be expended at the disposal site.
The removal of the old insulation and installation of new
insulation would expose workers to radiation. Based on planning
documents prepared in 2010, Ameren estimated that the expected total
dose for replacing insulation in Callaway, would be between 350 and 400
person-rem. This estimate was considered in line with estimates from
[[Page 52820]]
other utilities impacted by this same issue. Ameren also indicated that
this initial estimate would now likely be higher due to the intervening
12 years of continuous plant operation. The NRC reviewed NUREG-0713,
Volume 41, ``Occupational Radiation Exposure at Commercial Nuclear
Power Reactors and Other Facilities: Fifty-Second Annual Report,'' and
determined that Ameren's average baseline collective radiation exposure
is approximately 22 person-rem. The additional 350 to 400-plus person-
rem collective exposure would be shared across the entire work force
involved with removing and reinstalling insulation. In SECY-12-0093,
the NRC staff attempted to develop a total occupational dose estimate
for the work involved in insulation removal and replacement associated
with GSI-191. Due to uncertainties in the scope of work required to
remove and replace insulation at a specific nuclear plant and other
site-specific factors such as source term and hazardous materials, the
NRC staff was unable to estimate the total occupational dose associated
with this work. However, dose estimates were provided by the Nuclear
Energy Institute (NEI) in a letter to the NRC dated March 30, 2012,
based on information collected on occupational radiation exposures that
have been, or could be, incurred during insulation removal and
replacement. In the letter, NEI noted similar difficulties in
estimating the potential amount of radiation exposure, but provided a
``per unit'' estimate of between 80 and 525 person-rem. Given
uncertainties in the scope of work and other nuclear plant-specific
factors such as source term and hazardous materials, the NRC staff
found no basis to conclude that the NEI estimates were unreasonable.
Accordingly, because Ameren's estimate of potential additional
radiation exposure resulting from the alternative approach of removing
and replacing insulation is consistent with the NEI estimated range,
the NRC staff considers Ameren's estimate to be reasonable.
As stated in the ``Occupational Radiation Doses'' section of this
document, Ameren's radiation protection program monitors radiation
levels throughout the nuclear plant to establish appropriate work
controls, training, temporary shielding, and protective equipment
requirements so that worker doses are expected to remain within the
dose limits in 10 CFR 20.1201.
In addition, as stated in the ``Offsite Radiation Dose'' section of
this document, Ameren also has a radiation monitoring system and
procedures in place to control the release of radioactive effluents in
accordance with radiation protection standards in 10 CFR 20.1301, 40
CFR part 190, and the ALARA dose objectives in appendix I to 10 CFR
part 50. Therefore, radiation exposure to members of the public would
be maintained within the NRC dose criteria in 10 CFR 20.1301, 40 CFR
part 190, and the ALARA dose objectives of appendix I to 10 CFR part
50.
Based on this information, impacts to members of the public from
removing and replacing insulation within the reactor containment
building would not be significant. However, impacts to plant workers
and the environment from implementing this alternative would be greater
than implementing the proposed action.
Alternative Use of Resources
The proposed action would not involve the use of any different
resources (e.g., water, air, land, nuclear fuel) not previously
considered in NUREG-1437, Supplement 51.
Agencies and Persons Consulted
In accordance with its stated policy, on June 27, 2022, the NRC
staff consulted with the State of Missouri official, Mr. Aaron Schmidt,
regarding the environmental impact of the proposed action. The State of
Missouri official has not provided any comments on the EA and FONSI.
III. Finding of No Significant Impact
The licensee requested to amend Renewed Facility Operating License
No. NPF-30 to grant exemptions for Callaway, from certain requirements
of 10 CFR 50.46(a)(1) and 10 CFR part 50, appendix A, GDC 35, 38, and
41. This proposed action would not significantly affect plant safety,
would not have a significant adverse effect on the probability of an
accident occurring, and would not have any significant radiological or
non-radiological impacts. It would also not result in any changes to
radioactive effluents or emissions, exposures to nuclear plant workers
and members of the public, or any changes to radiological and non-
radiological impacts to the environment.
Consistent with 10 CFR 51.21, the NRC conducted an environmental
review of the proposed action. Based on the EA included in Section II
of this notice and incorporated by reference in this FONSI, the NRC
staff finds that the proposed action will not have a significant effect
on the quality of the human environment. Accordingly, the NRC has
determined there is no need to prepare an environmental impact
statement for the proposed action.
The NRC staff's evaluation considered the information provided in
the licensee's application as supplemented, and the NRC staff's review
of related environmental documents. Section IV of this notice lists
documents related to the proposed action and includes information on
the availability of the documents, including the related environmental
document NUREG-1437, Supplement 51, which provides the latest
environmental review of current operations and description of
environmental conditions at Callaway.
This FONSI and other related environmental documents may be
examined, and/or copied for a fee, at the NRC's PDR, located at One
White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
Publicly available records are also accessible online in the ADAMS
Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter
problems in accessing the documents located in ADAMS should contact the
NRC's PDR reference staff by telephone at 1-800-397-4209 or 301-415-
4737, or by email to [email protected].
IV. Availability of Documents.
The documents identified in the following table are available to
interested persons through one or more of the following methods, as
indicated.
----------------------------------------------------------------------------------------------------------------
Document ADAMS accession No.
----------------------------------------------------------------------------------------------------------------
U.S. Nuclear Regulatory Commission. Generic Letter 2004-02: ML042360586
``Potential Impact of Debris Blockage on Emergency
Recirculation During Design Basis Accidents at Pressurized-
Water Reactors,'' dated September 13, 2004.
U.S. Nuclear Regulatory Commission. NUREG-0897, ML112440046
``Containment Emergency Sump Performance: Technical
Findings Related to Unresolved Safety Issue A-43, Revision
1, October 1985.
Ameren Missouri. Letter ULNRC-06526, ``Request for License ML21090A184 (package).
Amendment and Regulatory Exemptions for a
Risk[dash]Informed Approach to Address GSI-191 and Respond
to GL 2004-02,'' dated March 31, 2021.
[[Page 52821]]
Ameren Missouri. Letter ULNRC-06664, ``Supplement to ML21147A222
Request for License Amendment and Regulatory Exemptions
for a Risk-Informed Approach to Address GSI-191 and
Respond to GL 2004-02 (LDCN 19-0014),'' dated May 27, 2021.
Ameren Missouri. Letter ULNRC-06651, ``Supplement to ML21203A192 (package).
Request for License Amendment and Regulatory Exemptions
for a Risk-Informed Approach to Address GSI-191 and
Respond to GL 2004-02 (LDCN 19-0014),'' dated July 22,
2021.
Ameren Missouri. Letter ULNRC-06683, ``Transmittal of ML21237A135 (package).
Documents Identified from NRC Audit of License Amendment
Request Regarding Risk-Informed Approach to Closure of
Generic Safety Issue 191 (EPID L-2021-LLA-0059),'' dated
August 23, 2021.
Ameren Missouri. Letter ULNRC-06692, ``Third Supplement to ML21280A378 (package).
Request for License Amendment and Regulatory Exemptions
for a Risk-Informed Approach to Address GSI-191 and
Respond to GL 2004-02 (LDCN 19-0014),'' dated October 7,
2021.
Ameren Missouri. Letter ULNRC-06690, ``Fourth (Post-Audit) ML22027A804 (package).
Supplement to Request for License Amendment and Regulatory
Exemptions for a Risk-Informed Approach to Address GSI-191
and Respond to GL 2004-02 (LDCN 19-0014),'' dated January
27, 2022.
Ameren Missouri. Letter ULNRC-06721, ``Fifth (Post-Audit) ML22068A027 (package).
Supplement to Request for License Amendment and Regulatory
Exemptions for a Risk-Informed Approach to Address GSI-191
and Respond to GL 2004-02 (LDCN 19-0014),'' dated March 8,
2022.
Ameren Missouri. Letter ULNRC-06735, ``Response to Request ML22146A337 (package).
for Additional Information Regarding Request for License
Amendment and Regulatory Exemptions for Risk[dash]Informed
Approach to Address GSI-191 and Respond to Generic Letter
2004-02,'' dated May 26, 2022.
Nuclear Energy Institute. GSI-191 Dose Estimates, dated ML12095A319
March 30, 2012.
SECY-12-0093, ``Closure Options for Generic Safety Issue-- ML121320270 (package).
191, Assessment of Debris Accumulation on Pressurized-
Water Reactor Sump Performance,'' dated July 9, 2012.
SRM-SECY-12-0093, ``Staff Requirements--SECY-12-0093-- ML12349A378
Closure Options for Generic Safety Issue--191, Assessment
of Debris Accumulation on Pressurized-Water Reactor Sump
Performance,'' dated December 14, 2012.
U.S. Nuclear Regulatory Commission. NUREG-1437, Supplement ML14289A140
51, ``Generic Environmental Impact Statement for License
Renewal of Nuclear Plants: Supplement 51 Regarding
Callaway Plant, Unit 1: Final Report,'' October 2014.
U.S. Nuclear Regulatory Commission. NUREG-0713, Volume 41, ML22111A013
``Occupational Radiation Exposure at Commercial Nuclear
Power Reactors and Other Facilities 2019: Fifty-Second
Annual Report,'' April 2022.
----------------------------------------------------------------------------------------------------------------
Dated: August 23, 2022.
For the Nuclear Regulatory Commission.
Siva P. Lingam,
Project Manager, Plant Licensing Branch IV, Division of Operator
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2022-18498 Filed 8-26-22; 8:45 am]
BILLING CODE 7590-01-P
