Holtec Decommissioning International, LLC, Holtec Indian Point 2, LLC, and Holtec Indian Point 3, LLC, Indian Point Nuclear Energy Center, 74536-74540 [2023-23971]
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Federal Register / Vol. 88, No. 209 / Tuesday, October 31, 2023 / Notices
any persons (petitioner) whose interest
may be affected by this action may file
a request for a hearing and petition for
leave to intervene (petition) with respect
to the action. Petitions shall be filed in
accordance with the guidance
concerning the Commission’s ‘‘Agency
Rules of Practice and Procedure’’ in 10
CFR part 2 as discussed in section II.A
of this document.
Unless otherwise indicated, the
Commission has determined that the
amendments satisfy the criteria for
categorical exclusion in accordance
with 10 CFR 51.22. Therefore, pursuant
to 10 CFR 51.22(b), no environmental
impact statement or environmental
assessment need be prepared for these
amendments. If the Commission has
prepared an environmental assessment
under the special circumstances
provision in 10 CFR 51.12(b) and has
made a determination based on that
assessment, it is so indicated in the
safety evaluation for the amendment.
For further details with respect to
these actions, see the amendment and
associated documents such as the
Commission’s letter and safety
evaluation, which may be obtained
using the ADAMS accession numbers
indicated in the following table. The
safety evaluation will provide the
ADAMS accession numbers for the
application for amendment and the
Federal Register citation for any
environmental assessment. All of these
items can be accessed as described in
the ‘‘Obtaining Information and
Submitting Comments’’ section of this
document.
LICENSE AMENDMENT ISSUANCE(S)—EXIGENT/EMERGENCY CIRCUMSTANCES
DTE Electric Company; Fermi, Unit 2; Monroe County, MI
Docket No ..........................................................................
Amendment Date ...............................................................
ADAMS Accession No .......................................................
Amendment No ..................................................................
Brief Description of Amendment(s) ....................................
Local Media Notice (Yes/No) .............................................
Public Comments Requested as to Proposed NSHC
(Yes/No).
50–341.
September 18, 2023.
ML23243A885.
225.
This exigent amendment allowed a one-time extension of the Condition A, completion time, in Fermi 2 Technical Specifications 3.7.2, ‘‘Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS),’’ from 72 hours to 7 days to allow online repairs to the Division I Mechanical Draft Cooling Tower A and C fan pedestals. The one-time extension would be used twice, once for each fan, and will expire at 11:59 p.m. on November 19, 2023.
No.
No.
Southern Nuclear Operating Company, Inc.; Joseph M. Farley Nuclear Plant, Units 1 and 2; Houston County, AL
Docket No(s) ......................................................................
Amendment Date ...............................................................
ADAMS Accession No .......................................................
Amendment No(s) ..............................................................
Brief Description of Amendment(s) ....................................
Local Media Notice (Yes/No) .............................................
Public Comments Requested as to Proposed NSHC
(Yes/No).
Dated: October 18, 2023.
For the Nuclear Regulatory Commission.
Victor G. Cusumano,
Acting Deputy Director, Division of Operating
Reactor Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2023–23382 Filed 10–30–23; 8:45 am]
BILLING CODE 7590–01–P
50–348, 50–364.
August 24, 2023.
ML23235A296.
247 (Unit 1) and 244 (Unit 2).
The amendments revised Technical Specification (TS) 3.6.5, ‘‘Containment Air Temperature.’’ Specifically, the amendments revised the operating license and approved a one-time NOTE to Appendix A TS 3.6.5, ‘‘Limiting Condition for Operation,’’ to revise the limit on containment average air temperature from ≤120°F to
≤122°F (Fahrenheit) effective until 0600 hours central time on September 9, 2023.
The license amendments were issued under emergency circumstances as described in the provisions of 10 CFR 50.91(a)(5), due to the time critical nature of
the amendment.
Yes.
No.
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–003, 50–247, and 50–286;
NRC–2022–0223]
Holtec Decommissioning International,
LLC, Holtec Indian Point 2, LLC, and
Holtec Indian Point 3, LLC, Indian Point
Nuclear Energy Center
Nuclear Regulatory
Commission.
ACTION: Environmental assessment and
finding of no significant impact;
issuance.
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AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of exemptions that would
SUMMARY:
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permit the licensee to reduce its
emergency planning (EP) activities at
the Indian Point Nuclear Generating
Unit Nos. 1, 2, and 3, collectively
referred to as the Indian Point Energy
Center (IPEC). Specifically, Holtec
Decommissioning International, LLC
(HDI), an indirect wholly owned
subsidiary of Holtec International
(Holtec) is seeking exemptions on behalf
of Holtec Indian Point 2, LLC (‘‘Holtec
IP2’’) and Holtec Indian Point 3, LLC
(‘‘Holtec IP3’’), the licensees, that would
eliminate the requirements to maintain
formal offsite radiological emergency
plans, as well as reduce the scope of
some of the onsite EP activities based on
the reduced risks at IPEC, which is
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permanently shut down and defueled.
However, requirements for an onsite
radiological emergency plan and for
certain onsite capabilities to
communicate and coordinate with
offsite response authorities would be
retained. In addition, offsite EP
provisions would still exist through
State and local government use of a
comprehensive emergency management
plan process, in accordance with the
Federal Emergency Management
Agency’s (FEMA’s) Comprehensive
Preparedness Guide (CPG) 101,
‘‘Developing and Maintaining
Emergency Operations Plans.’’ The NRC
staff is issuing an Environmental
Assessment (EA) and Finding of No
Significant Impact (FONSI) associated
with the proposed exemptions.
DATES: The EA and FONSI referenced in
this document are available on October
31, 2023.
ADDRESSES: Please refer to Docket ID
NRC–2022–0223 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–2022–0223. 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, at
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 of
this document.
• NRC’s PDR: The PDR, where you
may examine and order copies of
publicly available documents, is open
by appointment. 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 a.m. and 4 p.m. eastern
time (ET), Monday through Friday,
except Federal holidays.
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Karl
Sturzebecher, Office of Nuclear Material
Safety and Safeguards, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–415–
8534, email: Karl.Sturzebecher@nrc.gov.
SUPPLEMENTARY INFORMATION:
FOR FURTHER INFORMATION CONTACT:
I. Introduction
By letter dated February 8, 2017, in
accordance with sections 50.4(b)(8) and
50.82(a)(1)(i) to title 10 of the Code of
Federal Regulations (10 CFR) part 50,
‘‘Domestic Licensing of Production and
Utilization Facilities,’’ Entergy Nuclear
Operations, Inc., Entergy Nuclear Indian
Point 2, LLC, and Entergy Nuclear
Indian Point 3, LLC (the IPEC licensees
at that time, collectively, Entergy)
notified the NRC that they had decided
to permanently cease power operations
at the Indian Point Nuclear Generating
Unit No. 2 (IP2) by April 30, 2020, and
at the Indian Point Nuclear Generating
Unit No. 3 (IP3) by April 30, 2021.
Pursuant to 10 CFR 50.82(a)(1)(ii), by
letters dated May 12, 2020, and May 11,
2021, Entergy certified to the NRC that
the fuel had been permanently removed
from the IP2 and IP3 reactor vessels and
placed in the IP2 and IP3 spent fuel
pools (SFPs). Upon the docketing of
these certifications, under 10 CFR
50.82(a)(2), the IP2 and IP3 licenses no
longer authorize operation of the
reactors or emplacement or retention of
fuel into the reactor vessels. The spent
fuel from IP2 and IP3 is stored in the
SFPs and in dry cask storage at the
onsite independent spent fuel storage
installation (ISFSI) until it is shipped
offsite.
Indian Point Nuclear Generating Unit
No. 1 (IP1) permanently ceased
operations on October 31, 1974, and all
fuel was removed from the IP1 reactor
vessel by January 1976. In 1996, the
NRC issued an Order approving the
safe-storage condition of IP1. In 2003,
the NRC issued Amendment No. 52 to
IP1’s provisional operating license that
changed the license’s expiration date to
be consistent with that of the IP2 license
at that time. Pursuant to 10 CFR
50.82(a)(2), the IP1 license no longer
authorizes operation of the reactor or
emplacement or retention of fuel into
the reactor vessel. There is no IP1 spent
fuel in wet storage at the IPEC site; IP1
spent fuel is stored onsite in dry cask
storage in an ISFSI.
By Order dated November 23, 2020,
the NRC approved a transfer of the IP
licenses from Entergy to Holtec
Decommissioning International, LLC,
Holtec IP2, LLC (which became the
licensee of IP1 and IP2), and Holtec IP3,
LLC (which became the licensee of IP3).
By letter dated December 22, 2021, as
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supplemented by letters dated February
1, 2022, February 2, 2022, and May 12,
2022, HDI, who conducts the
decommissioning operating services on
behalf of Holtec IP2 and Holtec IP3,
requested exemptions from specific
portions of 10 CFR 50.47, ‘‘Emergency
plans,’’ and appendix E, ‘‘Emergency
Planning and Preparedness for
Production and Utilization Facilities,’’
to 10 CFR part 50 for the IPEC licenses.
More specifically, HDI requested
exemptions from certain planning
standards in 10 CFR 50.47(b) regarding
onsite and offsite radiological
emergency preparedness (REP) plans for
nuclear power reactors; from certain
requirements in 10 CFR 50.47(c)(2) for
establishment of plume exposure
pathway and ingestion pathway
emergency planning zones (EPZs) for
nuclear power reactors; and from certain
requirements in 10 CFR part 50,
appendix E, section IV, ‘‘Content of
Emergency Plans.’’
HDI’s requested exemptions would
eliminate the NRC requirements to
maintain formal offsite REP plans in
accordance with 44 CFR, ‘‘Emergency
Management and Assistance,’’ part 350,
‘‘Review and Approval of State and
Local Radiological Emergency Plans and
Preparedness,’’ and would reduce the
scope of the onsite EP activities at IPEC.
HDI based its request on the reduced
risks of an offsite radiological release at
IPEC after permanent cessation of power
operations and all spent fuel has
decayed for at least 15 months. The
exemptions would maintain the
requirements for an onsite radiological
emergency plan and would continue to
ensure the capability to communicate
and coordinate with offsite response
authorities.
The EP requirements of 10 CFR 50.47
and appendix E to 10 CFR part 50 do
not distinguish between operating
reactors and those that have ceased
operations and defueled. As such, a
permanently shut down and defueled
reactor must continue to maintain the
same EP requirements as an operating
power reactor under the existing
regulatory requirements. To establish a
level of EP commensurate with the
reduced risks of a permanently shut
down and defueled reactor, the licensee
must seek exemptions from certain EP
regulatory requirements before it can
change its emergency plans.
The NRC is therefore considering
issuing to the licensee the proposed
exemptions from portions of 10 CFR
50.47 and appendix E to 10 CFR part 50,
which would eliminate the
requirements for the licensee to
maintain offsite radiological emergency
plans and reduce some of the onsite EP
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activities based on the reduced
radiological risks as IPEC has
permanently ceased power operations
and all spent fuel has decayed for more
than 15 months.
Consistent with 10 CFR 51.21,
‘‘Criteria for and identification of
licensing and regulatory actions
requiring environmental assessments,’’
the NRC has determined that an EA is
the appropriate form of environmental
review for the requested action. Based
on the results of the EA, which is
provided in Section II of this document,
the NRC has determined not to prepare
an environmental impact statement for
the proposed action and is issuing a
FONSI.
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II. Environmental Assessment
Description of the Proposed Action
The proposed action would exempt
the licensee from: (1) certain standards
as set forth in 10 CFR 50.47(b) regarding
onsite and offsite emergency response
plans for nuclear power reactors; (2)
requirements in 10 CFR 50.47(c)(2) to
establish plume exposure and ingestion
pathway EPZs for nuclear power
reactors; and (3) certain requirements in
10 CFR part 50, appendix E, section IV,
which establishes the elements that
make up the content of emergency
plans. The proposed action of granting
these exemptions would eliminate the
NRC requirements for the licensee to
maintain offsite radiological emergency
plans in accordance with 44 CFR part
350 and reduce some of the onsite EP
activities at IPEC. However,
requirements for certain onsite
capabilities to communicate and
coordinate with offsite response
authorities would be retained.
Additionally, if necessary, offsite
protective actions could still be
implemented using a comprehensive
emergency management plan (CEMP)
process. A CEMP in this context, also
referred to as an emergency operations
plan, is addressed in FEMA’s CPG 101.
The CPG 101 is the foundation for State,
territorial, Tribal, and local EP in the
United States under the National
Preparedness System. It promotes a
common understanding of the
fundamentals of risk-informed planning
and decision making and assists
planners at all levels of government in
their efforts to develop and maintain
viable, all-hazards, all-threats
emergency plans. A CEMP is flexible
enough for use in all emergencies. It
describes how people and property will
be protected; details who is responsible
for carrying out specific actions;
identifies the personnel, equipment,
facilities, supplies, and other resources
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available; and outlines how all actions
will be coordinated. A CEMP is often
referred to as a synonym for ‘‘allhazards’’ planning. The proposed action
is in accordance with the licensee’s
exemption request dated December 22,
2021, as supplemented by letters dated
February 1, 2022, February 2, 2022, and
May 12, 2022.
Need for the Proposed Action
The proposed action is needed for the
licensee to revise the IPEC Emergency
Plan. Since the certifications for
permanent cessation of operations and
permanent removal of fuel from the
reactor vessels have been docketed,
pursuant to 10 CFR 50.82(a)(2), the IPEC
licenses no longer authorize use of the
facility for power operation or
emplacement or retention of fuel into
the reactor vessels and, therefore, the
occurrence of postulated accidents
associated with IPEC reactor operation
is no longer credible. As the EP
requirements do not distinguish
between operating reactors and a power
reactor that has been permanently shut
down and defueled, the licensee
requests an exemption from certain EP
requirements commensurate with the
radiological risks at the site.
In its exemption request, the licensee
identified three possible design-basis
accidents (DBAs) at IPEC in its
permanently shut down and defueled
condition. These are: (1) a fuel handling
accident in the fuel storage buildings;
(2) an accidental release of waste gas;
and (3) an accidental release of waste
liquid. The licensee also considered the
consequences of a beyond DBA
involving a complete loss of SFP water
inventory and no accompanying heat
loss (i.e., adiabatic heat up). The NRC
staff evaluated these possible
radiological accidents, as well as the
associated analyses provided by the
licensee, in the Commission Paper
(SECY) 22–0102, ‘‘Request by Holtec
Decommissioning International, LLC for
Exemptions from Certain EP
Requirements for the Indian Point
Nuclear Generating Unit Nos. 1, 2, and
3,’’ dated November 18, 2022.
In SECY–22–0102, the NRC staff
verified that the licensee’s analyses and
calculations provided reasonable
assurance that if the requested
exemptions were granted, then: (1) for a
DBA, an offsite radiological release will
not exceed the early phase protective
action guides (PAGs) at the exclusion
area boundary, as detailed in Table 1–
1, ‘‘Summary Table for PAGs,
Guidelines, and Planning Guidance for
Radiological Incidents,’’ to the EPA’s
‘‘PAG Manual: Protective Action Guides
and Planning Guidance for Radiological
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Incidents,’’ EPA–400/R–17/001, dated
January 2017; (2) in the highly unlikely
event of a beyond DBA resulting in a
loss of all SFP cooling, there is
sufficient time to initiate appropriate
mitigating actions; and (3) in the event
a radiological release has or is projected
to occur, there would be sufficient time
for offsite agencies to take protective
actions using a CEMP to protect the
health and safety of the public if offsite
governmental officials determine that
such action is warranted. The
Commission approved the NRC staff’s
recommendation to grant the
exemptions based on this evaluation in
its Staff Requirements Memorandum to
SECY–22–0102, dated October 24, 2023.
Based on the licensee’s analyses and
reduced radiological risks, the licensee
states that complete application of the
EP regulations to IPEC 15 months after
its permanent cessation of power
operations would not serve the
underlying purpose of the regulations or
is not necessary to achieve the
underlying purpose of the regulations.
The licensee also states that it would
incur undue costs in the application of
operating plant EP requirements for the
maintenance of an emergency response
organization in excess of that actually
needed to respond to the diminished
scope of credible accidents for IPEC 15
months after its permanent cessation of
power operations.
Environmental Impacts of the Proposed
Action
The NRC staff has completed its
evaluation of the environmental impacts
of the proposed action.
The proposed action consists mainly
of changes related to the elimination of
NRC requirements for the licensee to
maintain offsite radiological emergency
plans in accordance with 44 CFR part
350 and reduce some of the onsite EP
activities at IPEC, based on the reduced
risks once the reactor has been
permanently shut down for a period of
15 months. However, requirements for
certain onsite capabilities to
communicate and coordinate with
offsite response authorities will be
retained and offsite EP provisions to
protect public health and safety will
still exist through State and local
government use of a CEMP.
With regard to potential
nonradiological environmental impacts,
the proposed action would have no
direct impacts on land use or water
resources, including terrestrial and
aquatic biota, as it involves no new
construction, land disturbance, or
modification of plant operational
systems. There would be no changes to
the quality or quantity of
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nonradiological effluents and no
changes to the plants’ National Pollutant
Discharge Elimination System permits
would be needed. In addition, there
would be no noticeable effect on
socioeconomic conditions in the region,
no environmental justice impacts, no air
quality impacts, and no impacts to
historic and cultural resources from the
proposed action. Therefore, there are no
significant nonradiological
environmental impacts associated with
the proposed action.
With regard to potential radiological
environmental impacts, the proposed
action would not significantly increase
the probability or consequences of
radiological accidents. Additionally, the
NRC staff has concluded that the
proposed action would have no direct
radiological environmental impacts.
There would be no change to the types
or amounts of radioactive effluents that
may be released and, therefore, no
change in occupational or public
radiation exposure from the proposed
action. Moreover, no changes would be
made to plant buildings or to the site
property from the proposed action. For
these reasons, there are no significant
radiological environmental impacts
associated with the proposed action.
Environmental Impacts of the
Alternatives to the Proposed Action
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As an alternative to the proposed
action, the NRC staff considered the
denial of the proposed action (i.e., the
‘‘no-action’’ alternative). The denial of
the application would result in no
change in current environmental
impacts. Therefore, the environmental
impacts of the proposed action and the
alternative action are similar.
Alternative Use of Resources
The proposed action does not involve
the use of any different resources than
those previously considered in the
‘‘Generic Environmental Impact
Statement for License Renewal of
Nuclear Plants: Regarding Indian Point
Nuclear Generating Unit Nos. 2 and 3,
Final Report,’’ NUREG–1437,
Supplement 38, dated December 2010,
as supplemented in June 2013 and April
2018.
Agencies or Persons Consulted
No additional agencies or persons
were consulted regarding the
environmental impact of the proposed
action. On October 25, 2023, the State
of New York representative was notified
of this EA and FONSI.
State of New York Comments
By letters dated November 22, 2022,
and January 6, 2023, the New York State
Energy Research Development
Authority, and the New York
Department of Public Service along with
the Indian Point Decommissioning
Oversight Board, respectively submitted
comments regarding the proposed
exemptions. Although the comments
were not specific to this EA, the NRC
staff reviewed the comments and did
not identify any information that was
not previously considered in the
preparation of this EA.
III. Finding of No Significant Impact
The licensee has proposed
exemptions from: (1) certain standards
in 10 CFR 50.47(b) regarding onsite and
offsite emergency response plans for
nuclear power reactors; (2) the
requirements in 10 CFR 50.47(c)(2) to
establish plume exposure and ingestion
74539
pathway EPZs for nuclear power
reactors; and (3) certain requirements in
10 CFR part 50, appendix E, section IV,
which establishes the elements that
make up the content of emergency
plans. The proposed action of granting
these exemptions would eliminate the
NRC requirements for the licensee to
maintain offsite radiological emergency
plans in accordance with 44 CFR part
350 and reduce some of the onsite EP
activities at IPEC, based on the reduced
risks once the reactor has been
permanently shut down for a period of
15 months. However, requirements for
certain onsite capabilities to
communicate and coordinate with
offsite response authorities will be
retained and offsite EP provisions to
protect public health and safety will
still exist through State and local
government use of a CEMP.
The NRC is considering issuing the
exemptions. The 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
nonradiological impacts. This FONSI is
a final finding and incorporates by
reference the EA in Section II of this
document. Therefore, the NRC
concludes that the proposed action will
not have a significant effect on the
quality of the human environment.
Accordingly, the NRC has determined
not to prepare an environmental impact
statement for the proposed action.
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 description
ADAMS Accession No./weblink
Federal Emergency Management Agency, ‘‘Developing and Maintaining Emergency Operations Plans,’’
Comprehensive Preparedness Guide (CPG) 101, Version 2.0, November 2010.
https://www.fema.gov/media-librarydata/20130726-1828-250450014/cpg_101_comprehensive_
preparedness_guide_developing_
and_maintaining_emergency_operations_plans_2010.pdf.
ML21356B693.
Fleming, Jean A., Holtec Decommissioning International, LLC, letter to NRC, ‘‘Request for Exemptions
from Certain Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR part 50, appendix E,’’
dated December 22, 2021.
Fleming, Jean A., Holtec Decommissioning International, LLC, letter to NRC, ‘‘Supplement to Holtec Decommissioning International, LLC (HDI) Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR part 50, appendix E for Indian Point Unit Nos. 1, 2, and 3 Including Site-Specific Calculations,’’ dated February 1, 2022.
NRC Order on Indian Point Nuclear Generating Unit Nos. 1, 2, and 3, Order Approving Transfer of Facility
Operating Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC Operator, dated November 23, 2020.
Fleming, Jean A., Holtec Decommissioning International, LLC, letter to NRC, ‘‘Revision to Holtec Decommissioning International, LLC (HDI) Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR part 50, Appendix E for Indian Point Unit Nos. 1, 2, and 3,’’ dated
February 2, 2022.
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Document description
ADAMS Accession No./weblink
Fleming, Jean A., Holtec Decommissioning International, LLC, letter to NRC, ‘‘Response to Requests for
Additional Information Related to Exemption Request and License Amendment Request to Revise the
Facility’s Emergency Plan,’’ dated May 12, 2022.
Vitale, Anthony J., Entergy Nuclear Operations, Inc., letter to NRC, ‘‘Notification of Permanent Cessation of
Power Operations Indian Point Nuclear Generating Unit Nos. 2 and 3, Docket Nos. 50–247 and 50–286,
License Nos. DPR–26 and DPR–64,’’ dated February 8, 2017.
Vitale, Anthony J., Entergy Nuclear Operations, Inc., letter to NRC, ‘‘Certifications of Permanent Cessation
of Power Operations and Permanent Removal of Fuel from the Reactor Vessel Indian Point Nuclear
Generating Unit No. 2 NRC, Docket No. 50–247, Renewed Facility Operating License No. DPR–26,’’
dated May 12, 2020.
Vitale, Anthony J., Entergy Nuclear Operations, Inc., letter to NRC, ‘‘Certifications of Permanent Cessation
of Power Operations and Permanent Removal of Fuel from the Reactor Vessel Indian Point Nuclear
Generating Unit No. 3, NRC Docket No. 50–286, Renewed Facility Operating License No. DPR–64,’’
dated May 11, 2021.
U.S. Environmental Protection Agency (EPA), EPA–400/R–17/001, ‘‘PAG Manual: Protective Action Guides
and Planning Guidance for Radiological Incidents,’’ January 2017.
New York State Energy Research and Development Authority, ‘‘Emergency Planning Exemption Request
and License Amendment Request for the Indian Point Site,’’ dated November 22, 2022.
New York State Department of Public Service, ‘‘Public Statement Hearing regarding the Exemption Requests and License Amendment Requests for the Indian Point Site,’’ dated January 6, 2023.
SECY–22–0102, ‘‘Request by Holtec Decommissioning International, LLC for Exemptions from Certain
Emergency Planning Requirements for the Indian Point Nuclear Generating Unit Nos. 1, 2, and 3,’’ dated
November 18, 2022.
Staff Requirements Memorandum to SECY–22–0102, ‘‘Request by Holtec Decommissioning International,
LLC for Exemptions from Certain Emergency Planning Requirements for the Indian Point Nuclear Generating Unit Nos. 1, 2, and 3,’’ dated October 24, 2023.
NUREG–1437, Supplement 38, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear
Plants: Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3, Final Report,’’ December 2010.
Dated: October 26, 2023.
For the Nuclear Regulatory Commission.
Shaun M. Anderson,
Chief, Reactor Decommissioning Branch,
Division of Decommissioning, Uranium
Recovery and Waste Programs, Office of
Nuclear Material Safety and Safeguards.
[FR Doc. 2023–23971 Filed 10–30–23; 8:45 am]
BILLING CODE 7590–01–P
OFFICE OF PERSONNEL
MANAGEMENT
Submission for Review: Renewal of an
Existing Information Collection,
(Generic Clearance for Improving
Customer Experience), OMB Control
No. 3206–0276.
U.S. Office of Personnel
Management.
ACTION: 60-Day Notice and request for
comments.
AGENCY:
The Office of Personnel
Management (OPM) offers the general
public and other Federal agencies the
opportunity to comment on a previously
approved information collection request
(ICR) 3206–0276, (Generic Clearance for
Improving Customer Experience).
DATES: Comments are encouraged and
will be accepted until January 2, 2024.
This process is conducted in accordance
with 5 CFR 1320.1.
ADDRESSES: Interested persons are
invited to submit written comments on
lotter on DSK11XQN23PROD with NOTICES1
SUMMARY:
VerDate Sep<11>2014
17:18 Oct 30, 2023
Jkt 262001
the proposed information collection by
one of the following means:
Federal Rulemaking Portal: https://
www.regulations.gov All submissions
received must include the agency name
and docket number for this Federal
Register document. The general policy
for comments and other submissions
from members of the public is to make
these submissions available for public
viewing on the internet at https://
www.regulations.gov as they are
received without change, including any
personal identifiers or contact
information.
• Email michelle.earley@opm.gov.
Please put ‘‘OPM Customer Experience’’
in the subject line of the email.
FOR FURTHER INFORMATION CONTACT: A
copy of this information collection
request, with applicable supporting
documentation, may be obtained by
contacting the Human Resources
Solution, Office of Personnel
Management, 1900 E Street NW,
Washington, DC 20415, Attention:
Michelle Earley, 202–936–2034, or via
electronic mail to michelle.earley@
opm.gov.
Under the
PRA, (44 U.S.C. 3501–3520) Federal
Agencies must obtain approval from the
Office of Management and Budget
(OMB) for each collection of
information they conduct or sponsor.
‘‘Collection of information’’ is defined
in 44 U.S.C. 3502(3) and 5 CFR
SUPPLEMENTARY INFORMATION:
PO 00000
Frm 00140
Fmt 4703
Sfmt 4703
ML22132A169.
ML17044A004.
ML20133J902.
ML21131A157.
ML17044A073.
ML22332A048.
ML23009B687.
ML22231A155 (Package).
ML23297A027.
https://www.nrc.gov/reading-rm/doccollections/nuregs/staff/sr1437/
supplement38/.
1320.3(c) and includes Agency requests
or requirements that members of the
public submit reports, keep records, or
provide information to a third party.
Section 3506(c)(2)(A) of the PRA
requires Federal Agencies to provide a
60-day notice in the Federal Register
concerning each proposed collection of
information, including each proposed
extension of an existing collection of
information, before submitting the
collection to OMB for approval.
A modern, streamlined and
responsive customer experience means:
Raising government-wide customer
experience to the average of the private
sector service industry; developing
indicators for high-impact Federal
programs to monitor progress towards
excellent customer experience and
mature digital services; and providing
the structure (including increasing
transparency) and resources to ensure
customer experience is a focal point for
agency leadership. To support this,
OMB Circular A–11 Section 280
established government-wide standards
for mature customer experience
organizations in government and
measurement. To enable Federal
programs to deliver the experience
taxpayers deserve, they must undertake
three general categories of activities:
Conduct ongoing customer research,
gather and share customer feedback, and
test services and digital products.
These data collection efforts may be
either qualitative or quantitative in
E:\FR\FM\31OCN1.SGM
31OCN1
]]>Agencies
[Federal Register Volume 88, Number 209 (Tuesday, October 31, 2023)]
[Notices]
[Pages 74536-74540]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2023-23971]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-003, 50-247, and 50-286; NRC-2022-0223]
Holtec Decommissioning International, LLC, Holtec Indian Point 2,
LLC, and Holtec Indian Point 3, LLC, Indian Point Nuclear Energy Center
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental assessment and finding of no significant impact;
issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of exemptions that would permit the licensee to reduce its
emergency planning (EP) activities at the Indian Point Nuclear
Generating Unit Nos. 1, 2, and 3, collectively referred to as the
Indian Point Energy Center (IPEC). Specifically, Holtec Decommissioning
International, LLC (HDI), an indirect wholly owned subsidiary of Holtec
International (Holtec) is seeking exemptions on behalf of Holtec Indian
Point 2, LLC (``Holtec IP2'') and Holtec Indian Point 3, LLC (``Holtec
IP3''), the licensees, that would eliminate the requirements to
maintain formal offsite radiological emergency plans, as well as reduce
the scope of some of the onsite EP activities based on the reduced
risks at IPEC, which is
[[Page 74537]]
permanently shut down and defueled. However, requirements for an onsite
radiological emergency plan and for certain onsite capabilities to
communicate and coordinate with offsite response authorities would be
retained. In addition, offsite EP provisions would still exist through
State and local government use of a comprehensive emergency management
plan process, in accordance with the Federal Emergency Management
Agency's (FEMA's) Comprehensive Preparedness Guide (CPG) 101,
``Developing and Maintaining Emergency Operations Plans.'' The NRC
staff is issuing an Environmental Assessment (EA) and Finding of No
Significant Impact (FONSI) associated with the proposed exemptions.
DATES: The EA and FONSI referenced in this document are available on
October 31, 2023.
ADDRESSES: Please refer to Docket ID NRC-2022-0223 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-2022-0223. 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, at 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 of this document.
NRC's PDR: The PDR, where you may examine and order copies
of publicly available documents, is open by appointment. 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
a.m. and 4 p.m. eastern time (ET), Monday through Friday, except
Federal holidays.
FOR FURTHER INFORMATION CONTACT: Karl Sturzebecher, Office of Nuclear
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, telephone: 301-415-8534, email:
[email protected].
SUPPLEMENTARY INFORMATION:
I. Introduction
By letter dated February 8, 2017, in accordance with sections
50.4(b)(8) and 50.82(a)(1)(i) to title 10 of the Code of Federal
Regulations (10 CFR) part 50, ``Domestic Licensing of Production and
Utilization Facilities,'' Entergy Nuclear Operations, Inc., Entergy
Nuclear Indian Point 2, LLC, and Entergy Nuclear Indian Point 3, LLC
(the IPEC licensees at that time, collectively, Entergy) notified the
NRC that they had decided to permanently cease power operations at the
Indian Point Nuclear Generating Unit No. 2 (IP2) by April 30, 2020, and
at the Indian Point Nuclear Generating Unit No. 3 (IP3) by April 30,
2021.
Pursuant to 10 CFR 50.82(a)(1)(ii), by letters dated May 12, 2020,
and May 11, 2021, Entergy certified to the NRC that the fuel had been
permanently removed from the IP2 and IP3 reactor vessels and placed in
the IP2 and IP3 spent fuel pools (SFPs). Upon the docketing of these
certifications, under 10 CFR 50.82(a)(2), the IP2 and IP3 licenses no
longer authorize operation of the reactors or emplacement or retention
of fuel into the reactor vessels. The spent fuel from IP2 and IP3 is
stored in the SFPs and in dry cask storage at the onsite independent
spent fuel storage installation (ISFSI) until it is shipped offsite.
Indian Point Nuclear Generating Unit No. 1 (IP1) permanently ceased
operations on October 31, 1974, and all fuel was removed from the IP1
reactor vessel by January 1976. In 1996, the NRC issued an Order
approving the safe-storage condition of IP1. In 2003, the NRC issued
Amendment No. 52 to IP1's provisional operating license that changed
the license's expiration date to be consistent with that of the IP2
license at that time. Pursuant to 10 CFR 50.82(a)(2), the IP1 license
no longer authorizes operation of the reactor or emplacement or
retention of fuel into the reactor vessel. There is no IP1 spent fuel
in wet storage at the IPEC site; IP1 spent fuel is stored onsite in dry
cask storage in an ISFSI.
By Order dated November 23, 2020, the NRC approved a transfer of
the IP licenses from Entergy to Holtec Decommissioning International,
LLC, Holtec IP2, LLC (which became the licensee of IP1 and IP2), and
Holtec IP3, LLC (which became the licensee of IP3). By letter dated
December 22, 2021, as supplemented by letters dated February 1, 2022,
February 2, 2022, and May 12, 2022, HDI, who conducts the
decommissioning operating services on behalf of Holtec IP2 and Holtec
IP3, requested exemptions from specific portions of 10 CFR 50.47,
``Emergency plans,'' and appendix E, ``Emergency Planning and
Preparedness for Production and Utilization Facilities,'' to 10 CFR
part 50 for the IPEC licenses. More specifically, HDI requested
exemptions from certain planning standards in 10 CFR 50.47(b) regarding
onsite and offsite radiological emergency preparedness (REP) plans for
nuclear power reactors; from certain requirements in 10 CFR 50.47(c)(2)
for establishment of plume exposure pathway and ingestion pathway
emergency planning zones (EPZs) for nuclear power reactors; and from
certain requirements in 10 CFR part 50, appendix E, section IV,
``Content of Emergency Plans.''
HDI's requested exemptions would eliminate the NRC requirements to
maintain formal offsite REP plans in accordance with 44 CFR,
``Emergency Management and Assistance,'' part 350, ``Review and
Approval of State and Local Radiological Emergency Plans and
Preparedness,'' and would reduce the scope of the onsite EP activities
at IPEC. HDI based its request on the reduced risks of an offsite
radiological release at IPEC after permanent cessation of power
operations and all spent fuel has decayed for at least 15 months. The
exemptions would maintain the requirements for an onsite radiological
emergency plan and would continue to ensure the capability to
communicate and coordinate with offsite response authorities.
The EP requirements of 10 CFR 50.47 and appendix E to 10 CFR part
50 do not distinguish between operating reactors and those that have
ceased operations and defueled. As such, a permanently shut down and
defueled reactor must continue to maintain the same EP requirements as
an operating power reactor under the existing regulatory requirements.
To establish a level of EP commensurate with the reduced risks of a
permanently shut down and defueled reactor, the licensee must seek
exemptions from certain EP regulatory requirements before it can change
its emergency plans.
The NRC is therefore considering issuing to the licensee the
proposed exemptions from portions of 10 CFR 50.47 and appendix E to 10
CFR part 50, which would eliminate the requirements for the licensee to
maintain offsite radiological emergency plans and reduce some of the
onsite EP
[[Page 74538]]
activities based on the reduced radiological risks as IPEC has
permanently ceased power operations and all spent fuel has decayed for
more than 15 months.
Consistent with 10 CFR 51.21, ``Criteria for and identification of
licensing and regulatory actions requiring environmental assessments,''
the NRC has determined that an EA is the appropriate form of
environmental review for the requested action. Based on the results of
the EA, which is provided in Section II of this document, the NRC has
determined not to prepare an environmental impact statement for the
proposed action and is issuing a FONSI.
II. Environmental Assessment
Description of the Proposed Action
The proposed action would exempt the licensee from: (1) certain
standards as set forth in 10 CFR 50.47(b) regarding onsite and offsite
emergency response plans for nuclear power reactors; (2) requirements
in 10 CFR 50.47(c)(2) to establish plume exposure and ingestion pathway
EPZs for nuclear power reactors; and (3) certain requirements in 10 CFR
part 50, appendix E, section IV, which establishes the elements that
make up the content of emergency plans. The proposed action of granting
these exemptions would eliminate the NRC requirements for the licensee
to maintain offsite radiological emergency plans in accordance with 44
CFR part 350 and reduce some of the onsite EP activities at IPEC.
However, requirements for certain onsite capabilities to communicate
and coordinate with offsite response authorities would be retained.
Additionally, if necessary, offsite protective actions could still
be implemented using a comprehensive emergency management plan (CEMP)
process. A CEMP in this context, also referred to as an emergency
operations plan, is addressed in FEMA's CPG 101. The CPG 101 is the
foundation for State, territorial, Tribal, and local EP in the United
States under the National Preparedness System. It promotes a common
understanding of the fundamentals of risk-informed planning and
decision making and assists planners at all levels of government in
their efforts to develop and maintain viable, all-hazards, all-threats
emergency plans. A CEMP is flexible enough for use in all emergencies.
It describes how people and property will be protected; details who is
responsible for carrying out specific actions; identifies the
personnel, equipment, facilities, supplies, and other resources
available; and outlines how all actions will be coordinated. A CEMP is
often referred to as a synonym for ``all-hazards'' planning. The
proposed action is in accordance with the licensee's exemption request
dated December 22, 2021, as supplemented by letters dated February 1,
2022, February 2, 2022, and May 12, 2022.
Need for the Proposed Action
The proposed action is needed for the licensee to revise the IPEC
Emergency Plan. Since the certifications for permanent cessation of
operations and permanent removal of fuel from the reactor vessels have
been docketed, pursuant to 10 CFR 50.82(a)(2), the IPEC licenses no
longer authorize use of the facility for power operation or emplacement
or retention of fuel into the reactor vessels and, therefore, the
occurrence of postulated accidents associated with IPEC reactor
operation is no longer credible. As the EP requirements do not
distinguish between operating reactors and a power reactor that has
been permanently shut down and defueled, the licensee requests an
exemption from certain EP requirements commensurate with the
radiological risks at the site.
In its exemption request, the licensee identified three possible
design-basis accidents (DBAs) at IPEC in its permanently shut down and
defueled condition. These are: (1) a fuel handling accident in the fuel
storage buildings; (2) an accidental release of waste gas; and (3) an
accidental release of waste liquid. The licensee also considered the
consequences of a beyond DBA involving a complete loss of SFP water
inventory and no accompanying heat loss (i.e., adiabatic heat up). The
NRC staff evaluated these possible radiological accidents, as well as
the associated analyses provided by the licensee, in the Commission
Paper (SECY) 22-0102, ``Request by Holtec Decommissioning
International, LLC for Exemptions from Certain EP Requirements for the
Indian Point Nuclear Generating Unit Nos. 1, 2, and 3,'' dated November
18, 2022.
In SECY-22-0102, the NRC staff verified that the licensee's
analyses and calculations provided reasonable assurance that if the
requested exemptions were granted, then: (1) for a DBA, an offsite
radiological release will not exceed the early phase protective action
guides (PAGs) at the exclusion area boundary, as detailed in Table 1-1,
``Summary Table for PAGs, Guidelines, and Planning Guidance for
Radiological Incidents,'' to the EPA's ``PAG Manual: Protective Action
Guides and Planning Guidance for Radiological Incidents,'' EPA-400/R-
17/001, dated January 2017; (2) in the highly unlikely event of a
beyond DBA resulting in a loss of all SFP cooling, there is sufficient
time to initiate appropriate mitigating actions; and (3) in the event a
radiological release has or is projected to occur, there would be
sufficient time for offsite agencies to take protective actions using a
CEMP to protect the health and safety of the public if offsite
governmental officials determine that such action is warranted. The
Commission approved the NRC staff's recommendation to grant the
exemptions based on this evaluation in its Staff Requirements
Memorandum to SECY-22-0102, dated October 24, 2023.
Based on the licensee's analyses and reduced radiological risks,
the licensee states that complete application of the EP regulations to
IPEC 15 months after its permanent cessation of power operations would
not serve the underlying purpose of the regulations or is not necessary
to achieve the underlying purpose of the regulations. The licensee also
states that it would incur undue costs in the application of operating
plant EP requirements for the maintenance of an emergency response
organization in excess of that actually needed to respond to the
diminished scope of credible accidents for IPEC 15 months after its
permanent cessation of power operations.
Environmental Impacts of the Proposed Action
The NRC staff has completed its evaluation of the environmental
impacts of the proposed action.
The proposed action consists mainly of changes related to the
elimination of NRC requirements for the licensee to maintain offsite
radiological emergency plans in accordance with 44 CFR part 350 and
reduce some of the onsite EP activities at IPEC, based on the reduced
risks once the reactor has been permanently shut down for a period of
15 months. However, requirements for certain onsite capabilities to
communicate and coordinate with offsite response authorities will be
retained and offsite EP provisions to protect public health and safety
will still exist through State and local government use of a CEMP.
With regard to potential nonradiological environmental impacts, the
proposed action would have no direct impacts on land use or water
resources, including terrestrial and aquatic biota, as it involves no
new construction, land disturbance, or modification of plant
operational systems. There would be no changes to the quality or
quantity of
[[Page 74539]]
nonradiological effluents and no changes to the plants' National
Pollutant Discharge Elimination System permits would be needed. In
addition, there would be no noticeable effect on socioeconomic
conditions in the region, no environmental justice impacts, no air
quality impacts, and no impacts to historic and cultural resources from
the proposed action. Therefore, there are no significant
nonradiological environmental impacts associated with the proposed
action.
With regard to potential radiological environmental impacts, the
proposed action would not significantly increase the probability or
consequences of radiological accidents. Additionally, the NRC staff has
concluded that the proposed action would have no direct radiological
environmental impacts. There would be no change to the types or amounts
of radioactive effluents that may be released and, therefore, no change
in occupational or public radiation exposure from the proposed action.
Moreover, no changes would be made to plant buildings or to the site
property from the proposed action. For these reasons, there are no
significant radiological environmental impacts associated with the
proposed action.
Environmental Impacts of the Alternatives to the Proposed Action
As an alternative to the proposed action, the NRC staff considered
the denial of the proposed action (i.e., the ``no-action''
alternative). The denial of the application would result in no change
in current environmental impacts. Therefore, the environmental impacts
of the proposed action and the alternative action are similar.
Alternative Use of Resources
The proposed action does not involve the use of any different
resources than those previously considered in the ``Generic
Environmental Impact Statement for License Renewal of Nuclear Plants:
Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3, Final
Report,'' NUREG-1437, Supplement 38, dated December 2010, as
supplemented in June 2013 and April 2018.
Agencies or Persons Consulted
No additional agencies or persons were consulted regarding the
environmental impact of the proposed action. On October 25, 2023, the
State of New York representative was notified of this EA and FONSI.
State of New York Comments
By letters dated November 22, 2022, and January 6, 2023, the New
York State Energy Research Development Authority, and the New York
Department of Public Service along with the Indian Point
Decommissioning Oversight Board, respectively submitted comments
regarding the proposed exemptions. Although the comments were not
specific to this EA, the NRC staff reviewed the comments and did not
identify any information that was not previously considered in the
preparation of this EA.
III. Finding of No Significant Impact
The licensee has proposed exemptions from: (1) certain standards in
10 CFR 50.47(b) regarding onsite and offsite emergency response plans
for nuclear power reactors; (2) the requirements in 10 CFR 50.47(c)(2)
to establish plume exposure and ingestion pathway EPZs for nuclear
power reactors; and (3) certain requirements in 10 CFR part 50,
appendix E, section IV, which establishes the elements that make up the
content of emergency plans. The proposed action of granting these
exemptions would eliminate the NRC requirements for the licensee to
maintain offsite radiological emergency plans in accordance with 44 CFR
part 350 and reduce some of the onsite EP activities at IPEC, based on
the reduced risks once the reactor has been permanently shut down for a
period of 15 months. However, requirements for certain onsite
capabilities to communicate and coordinate with offsite response
authorities will be retained and offsite EP provisions to protect
public health and safety will still exist through State and local
government use of a CEMP.
The NRC is considering issuing the exemptions. The 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 nonradiological
impacts. This FONSI is a final finding and incorporates by reference
the EA in Section II of this document. Therefore, the NRC concludes
that the proposed action will not have a significant effect on the
quality of the human environment. Accordingly, the NRC has determined
not to prepare an environmental impact statement for the proposed
action.
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 description ADAMS Accession No./weblink
------------------------------------------------------------------------
Federal Emergency Management Agency, https://www.fema.gov/media-
``Developing and Maintaining Emergency library-data/20130726-1828-
Operations Plans,'' Comprehensive 25045-0014/
Preparedness Guide (CPG) 101, Version 2.0, cpg_101_comprehensive_prep
November 2010. aredness_guide_developing_
and_maintaining_emergency_
operations_plans_2010.pdf.
Fleming, Jean A., Holtec Decommissioning ML21356B693.
International, LLC, letter to NRC,
``Request for Exemptions from Certain
Emergency Planning Requirements of 10 CFR
50.47 and 10 CFR part 50, appendix E,''
dated December 22, 2021.
Fleming, Jean A., Holtec Decommissioning ML22032A017.
International, LLC, letter to NRC,
``Supplement to Holtec Decommissioning
International, LLC (HDI) Request for
Exemptions from Certain Emergency Planning
Requirements of 10 CFR 50.47 and 10 CFR
part 50, appendix E for Indian Point Unit
Nos. 1, 2, and 3 Including Site-Specific
Calculations,'' dated February 1, 2022.
NRC Order on Indian Point Nuclear ML20297A325.
Generating Unit Nos. 1, 2, and 3, Order
Approving Transfer of Facility Operating
Licenses to Holtec International, Owner,
and Holtec Decommissioning International,
LLC Operator, dated November 23, 2020.
Fleming, Jean A., Holtec Decommissioning ML22033A348.
International, LLC, letter to NRC,
``Revision to Holtec Decommissioning
International, LLC (HDI) Request for
Exemptions from Certain Emergency Planning
Requirements of 10 CFR 50.47 and 10 CFR
part 50, Appendix E for Indian Point Unit
Nos. 1, 2, and 3,'' dated February 2, 2022.
[[Page 74540]]
Fleming, Jean A., Holtec Decommissioning ML22132A169.
International, LLC, letter to NRC,
``Response to Requests for Additional
Information Related to Exemption Request
and License Amendment Request to Revise
the Facility's Emergency Plan,'' dated May
12, 2022.
Vitale, Anthony J., Entergy Nuclear ML17044A004.
Operations, Inc., letter to NRC,
``Notification of Permanent Cessation of
Power Operations Indian Point Nuclear
Generating Unit Nos. 2 and 3, Docket Nos.
50-247 and 50-286, License Nos. DPR-26 and
DPR-64,'' dated February 8, 2017.
Vitale, Anthony J., Entergy Nuclear ML20133J902.
Operations, Inc., letter to NRC,
``Certifications of Permanent Cessation of
Power Operations and Permanent Removal of
Fuel from the Reactor Vessel Indian Point
Nuclear Generating Unit No. 2 NRC, Docket
No. 50-247, Renewed Facility Operating
License No. DPR-26,'' dated May 12, 2020.
Vitale, Anthony J., Entergy Nuclear ML21131A157.
Operations, Inc., letter to NRC,
``Certifications of Permanent Cessation of
Power Operations and Permanent Removal of
Fuel from the Reactor Vessel Indian Point
Nuclear Generating Unit No. 3, NRC Docket
No. 50-286, Renewed Facility Operating
License No. DPR-64,'' dated May 11, 2021.
U.S. Environmental Protection Agency (EPA), ML17044A073.
EPA-400/R-17/001, ``PAG Manual: Protective
Action Guides and Planning Guidance for
Radiological Incidents,'' January 2017.
New York State Energy Research and ML22332A048.
Development Authority, ``Emergency
Planning Exemption Request and License
Amendment Request for the Indian Point
Site,'' dated November 22, 2022.
New York State Department of Public ML23009B687.
Service, ``Public Statement Hearing
regarding the Exemption Requests and
License Amendment Requests for the Indian
Point Site,'' dated January 6, 2023.
SECY-22-0102, ``Request by Holtec ML22231A155 (Package).
Decommissioning International, LLC for
Exemptions from Certain Emergency Planning
Requirements for the Indian Point Nuclear
Generating Unit Nos. 1, 2, and 3,'' dated
November 18, 2022.
Staff Requirements Memorandum to SECY-22- ML23297A027.
0102, ``Request by Holtec Decommissioning
International, LLC for Exemptions from
Certain Emergency Planning Requirements
for the Indian Point Nuclear Generating
Unit Nos. 1, 2, and 3,'' dated October 24,
2023.
NUREG-1437, Supplement 38, ``Generic https://www.nrc.gov/reading-
Environmental Impact Statement for License rm/doc-collections/nuregs/
Renewal of Nuclear Plants: Regarding staff/sr1437/supplement38/
Indian Point Nuclear Generating Unit Nos. index.html.
2 and 3, Final Report,'' December 2010.
------------------------------------------------------------------------
Dated: October 26, 2023.
For the Nuclear Regulatory Commission.
Shaun M. Anderson,
Chief, Reactor Decommissioning Branch, Division of Decommissioning,
Uranium Recovery and Waste Programs, Office of Nuclear Material Safety
and Safeguards.
[FR Doc. 2023-23971 Filed 10-30-23; 8:45 am]
BILLING CODE 7590-01-P
