[Federal Register Volume 87, Number 209 (Monday, October 31, 2022)]
[Notices]
[Pages 65613-65617]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2022-23657]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 72-51, 72-1014, 50-247, and 50-286; NRC-2022-0152]


Holtec Decommissioning International, LLC; Indian Point Energy 
Center; Independent Spent Fuel Storage Installation

AGENCY: Nuclear Regulatory Commission.

ACTION: Environmental assessment and finding of no significant impact; 
issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering an 
exemption request from Holtec Decommissioning International, LLC (HDI) 
for the Indian Point Energy Center Independent Spent Fuel Storage 
Installation. This exemption would, if granted, allow HDI to load up to 
three MPC-32Ms, using Amendment No. 15 for Certificate of Compliance 
(CoC) No. 1014 for the HI-STORM 100 storage system, with either up to 
thirty-two fuel assemblies having either Californium (Cf-252) or 
Antimony-Beryllium (Sb-Be) neutron source assemblies (NSAs) with 
sufficient cooling time, or a combination of up to five fuel assemblies 
having primary Plutonium Beryllium (Pu-Be) NSAs and the remaining 
basket locations with fuel assemblies having either Cf-252 or Sb-Be 
NSAs with sufficient cooling time. As discussed further, the proposed 
exemption would permit HDI to load the fuel assemblies having either 
Cf-252 or Sb-Be NSAs in any location in the basket and the fuel 
assemblies having Pu-Be NSAs such that one is located in the center of 
the basket and one is located in each of the four basket quadrants. The 
NRC prepared an environmental assessment (EA) and concluded that the 
proposed action would have no significant environmental impact. 
Accordingly, the NRC staff is issuing a finding of no significant 
impact (FONSI) associated with the proposed exemption.

DATES: The EA and FONSI referenced in this document are available 
October 31, 2022.

ADDRESSES: Please refer to Docket ID NRC-2022-0152 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-2022-0152. 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 
a.m. and 4 p.m. eastern time (ET), Monday through Friday, except 
Federal holidays.

FOR FURTHER INFORMATION CONTACT: Chris Allen, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555; telephone: 301-415-6877; email: 
[email protected].

SUPPLEMENTARY INFORMATION:

I. Introduction

    The NRC is reviewing an exemption request from Holtec 
Decommissioning International, LLC (HDI) dated March 24, 2022, as 
supplemented via a June 16, 2022, Microsoft Teams conversation and a 
September 20, 2022, Microsoft Teams call. Therefore, as required by 
sections 51.21 and 51.30(a) of title 10 of the Code of Federal 
Regulations (10 CFR), the NRC performed an environmental assessment 
(EA). Based on the results of the EA, discussed further, the NRC has 
determined not to prepare an environmental impact statement for the 
exemption request and is issuing a finding of no significant impact 
(FONSI).
    In its exemption request, HDI stated that it intends to store 
Pressurized Water Reactor spent fuel at the Indian Point Energy Center 
Independent Spent Fuel Storage Installation (ISFSI) using the HI-STORM 
100 storage system, Certificate of Compliance (CoC) No. 1014, Amendment 
No. 15 under the

[[Page 65614]]

general license provisions in 10 CFR part 72, ``Licensing Requirements 
for the Independent Storage of Spent Nuclear Fuel, High-Level 
Radioactive Waste, and Reactor-Related Greater Than Class C Waste.'' 
HDI requested an exemption from the requirements of 10 CFR 
72.212(b)(3), and the portion of 10 CFR 72.212(b)(11) that states 
``[t]he licensee shall comply with the terms, conditions, and 
specifications of the certificate of compliance (CoC).''
    Specifically, HDI requested an exemption that, if granted, would 
allow it to load up to three MPC-32Ms, using Amendment No. 15 for CoC 
No. 1014, with either up to thirty-two fuel assemblies having either 
Californium-252 (Cf-252) or Antimony-Beryllium (Sb-Be) NSAs with 
sufficient cooling time, or a combination of up to five fuel assemblies 
having primary Plutonium Beryllium (Pu-Be) NSAs and the remaining 
basket locations with fuel assemblies having either Cf-252 or Sb-Be 
NSAs with sufficient cooling time. Further, as discussed in this 
notice, the exemption would permit HDI to load the fuel assemblies 
having either Cf-252 or Sb-Be NSAs in any location in the basket and 
the fuel assemblies having Pu-Be NSAs such that one is located in the 
center of the basket and one is located in each of the four basket 
quadrants. Additionally, although HDI's analysis included information 
about fuel assemblies having Polonium-Beryllium (Po-Be) NSAs, based on 
the September 20, 2022 Microsoft Teams call, the NRC staff understands 
that HDI does not have fuel assemblies with Po-Be NSAs.
    Although HDI only requested exemptions from 10 CFR 72.12(b)(3) and 
(b)(11), to carry out this action, the NRC would also need to grant 
exemptions from 72.212(a)(2), (b)(5)(i), and 72.214. Consequently, in 
evaluating the request, the NRC also considered, pursuant to its 
authority in 10 CFR 72.7, exempting HDI from the requirements in 10 CFR 
72.212(a)(2), 10 CFR 72.212(b)(5)(i); and 10 CFR 72.214. For clarity, 
when this Federal Register notice refers to HDI's requested exemption, 
it means both the two provisions from which HDI requested exemption and 
the additional provisions from which the NRC staff is considering 
exempting HDI on its own initiative.

II. Environmental Assessment

Description of the Proposed Action

    The proposed action, if granted, would permit HDI to load up to 
three MPC-32Ms with multiple fuel assemblies that have NSAs, that 
cannot be removed from the fuel assembly, under Amendment No. 15 of CoC 
No. 1014. More specifically, the exemption would, if granted, allow HDI 
to load up to three MPC-32Ms, using Amendment No. 15 for CoC No. 1014, 
with either up to thirty-two fuel assemblies having either Cf-252 or 
Sb-Be NSAs with sufficient cooling time, or a combination of up to five 
fuel assemblies having primary Pu-Be NSAs and the remaining basket 
locations with fuel assemblies having either Cf-252 or Sb-Be NSAs with 
sufficient cooling time. Appendix D, table 2.1-1, section V, ``MPC 
MODEL: MPC-32M,'' Item C of Amendment No. 15 for CoC No. 1014 only 
permits general licensees to load a single NSA per cask. Further, per 
FSAR table 2.II.1.1, Rev. 22, the single NSA must be located in a cell 
in the inner part of the basket (i.e., fuel storage location 13, 14, 
19, or 20). Accordingly, the exemption, if granted, would also permit 
HDI to load the fuel assemblies having either Cf-252 or Sb-Be NSAs in 
any location in the basket and the fuel assemblies having Pu-Be NSAs 
such that one is located in the center of the basket and one is located 
in each of the four basket quadrants.
    Under the requirements of 10 CFR 51.21 and 10 CFR 51.30(a), the NRC 
staff developed an EA to evaluate the proposed action. The EA defines 
the NRC's proposed action (i.e., to grant, if appropriate, an exemption 
from the requirements of 10 CFR 72.212(a)(2), (b)(3), (b)(5)(i) and 10 
CFR 72.214 per 10 CFR 72.7) and the purpose of and need for the 
proposed action. Evaluations of the potential environmental impacts of 
the proposed action and alternatives to the proposed action are 
presented further, followed by the NRC's conclusion.

Need for the Proposed Action

    HDI is currently decommissioning Indian Point Unit 2 and Indian 
Point Unit 3 and, as part of that decommissioning, is transferring all 
spent fuel assemblies from the Indian Point Energy Center (Indian 
Point) Units 2 and 3 spent fuel pools to the ISFSI. HDI currently plans 
to load Indian Point Unit 2 spent fuel assemblies and the NSAs during 
the fall of 2022. HDI also plans to commence loading Indian Point Unit 
3 spent fuel assemblies and the NSAs in February 2023. Without this 
exemption, the licensee would have to pause loading until the NRC staff 
could process a CoC amendment. This would require the licensee to 
prolong the use of the spent fuel pools and their cleaning system. 
Longer use of the spent fuel pool cleaning system would generate 
additional low-level waste in the form of ion exchange resins. Granting 
an exemption now, if appropriate, would avoid the additional production 
of waste.

Environmental Impacts of the Proposed Action

    This EA evaluates the potential environmental impacts of granting 
the exemption to allow HDI to load up to three MPC-32Ms, using 
Amendment No. 15 for CoC No. 1014, with either up to thirty-two fuel 
assemblies having either Cf-252 or Sb-Be NSAs with sufficient cooling 
time, or a combination of up to five fuel assemblies having primary Pu-
Be NSAs and the remaining basket locations with fuel assemblies having 
either Cf-252 or Sb-Be NSAs with sufficient cooling time. It also 
evaluates the potential environmental impacts of granting the exemption 
permitting HDI to load the fuel assemblies having either Cf-252 or Sb-
Be NSAs in any location in the basket and the fuel assemblies having 
Pu-Be NSAs such that one is located in the center of the basket and one 
is located in each of the four basket quadrants.
    On July 18, 1990 (55 FR 29181), the NRC amended 10 CFR part 72 to 
provide for the storage of spent fuel under a general license in cask 
designs approved by the NRC. The EA for the 1990 final rule analyzed 
the potential environmental impact of using NRC-approved storage casks. 
The NRC has also considered the potential environmental impacts of 
storing spent fuel in accordance with Amendment No. 15 to the CoC for 
the HI-STORM 100 storage cask when it issued the direct final rule 
adding Amendment No. 15 to the list of acceptable casks in 10 CFR 
72.214 (86 FR 16291). The EA accompanying the direct final rule 
determined the environmental impacts resulting from the implementation 
of Amendment No. 15 would not significantly differ from the 
environmental impacts evaluated in the EA supporting the July 18, 1990, 
final rule. The EA for HI-STORM 100, Amendment No. 15 (86 FR 16291), 
tiered off the EA issued for the July 18, 1990, final rule. The EA for 
this exemption tiers off the EA for HI-STORM 100, Amendment No. 15 
direct final rule. Tiering off earlier EAs is a standard process under 
the National Environmental Policy Act by which the impact analyses of 
previous EAs can be cited by a subsequent EA, such as this one, to 
include the impacts of the proposed action within the scope of the 
previous EA. Thus, for the proposed action, this EA will only consider 
the potential impacts from granting the exemption.

[[Page 65615]]

    This exemption request involves neither the disturbance of land, 
the construction of new facilities, nor modifications to current 
operating practices. The EA for Holtec's HI-STORM 100, Amendment No. 15 
analyzed the effects of design-basis accidents that could occur during 
storage operations. Design-basis accidents account for human-induced 
events and the most severe natural phenomena reported for the site and 
surrounding area as well as the resultant effects on the storage cask. 
The NRC staff evaluated the exemption request and concluded that HDI's 
proposed exemption did not reflect any structural design changes or 
fabrication requirement changes; therefore, there is no additional risk 
of loss of structure or confinement in the event a design-basis 
accident occurs. Further, because there is no increased risk in the 
loss of structure or confinement, there is no significant increase in 
the consequences of design-basis accidents. As a result, the proposed 
action will result in no change in the types or amounts of any effluent 
released.
    Additionally, this exemption, if granted, would neither introduce 
shielding design changes nor operational changes. Although the 
requested exemption would change the source term, HDI submitted dose 
rate calculations as part of its exemption request, which the NRC staff 
reviewed and will discuss in its safety evaluation. As will be 
discussed further in the staff's safety evaluation, HDI submitted dose 
rate calculations for the same locations for which it calculated dose 
for Amendment No. 15 to CoC 1014. These calculations demonstrate that, 
in most instances, the source term change would only increase the dose 
rate by small amounts (e.g., a few millirem/hour at the cask surface 
and less than a millirem/hour at a distance of 1 meter). The greatest 
dose rate increase at one of these locations occurred when the canister 
is in the transfer cask at the axial midplane of the transfer cask 
radial surface. The dose rate would increase by approximately 28 
percent, which works out to an increase of 1099.92 millirem/hour and a 
total dose of 5033.67 millirem/hour. However, most cask operations are 
not performed at this location. Cask operations that are performed at 
this location are typically not performed at the surface, but rather 
approximately 1 meter from the surface. At that distance, the increase 
in dose rate would fall to approximately 122.69 millirem/hour and the 
total dose rate, including the increase, would fall to 1445.59 
millirem/hour. Given that the workers would only be exposed to this 
increased dose rate for relatively short periods of time, the NRC staff 
does not consider this increase significant. Importantly, dose will 
remain within the applicable limits of 10 CFR part 20. Consequently, 
the exemption, if granted, will not cause a significant increase in 
either individual or cumulative radiation exposure to workers.
    With regard to public dose rate increases, as previously noted, 
most of the dose rate increases are only a few millirem/hour at the 
cask surface and are less than a millirem/hour at a distance of 1 
meter. HDI's dose calculations demonstrate that even the highest dose 
rate increase (at the surface of the transfer cask) would be 
significantly less at a distance of 1 meter. The dose rates will 
continue to fall off at even greater distances. Thus, the dose increase 
at the site boundary--which, under 10 CFR 72.106, must be at least 100 
meters from the spent fuel, will be even smaller and, therefore, not 
significant. Importantly, dose will remain within applicable 10 CFR 
part 20 limits as well as the 72.104 and 72.106 limits. Consequently, 
the proposed exemption would not significantly affect the exposure to 
the public.
    Therefore, the proposed exemption request, if granted, will not 
result in radiological or non-radiological environmental impacts that 
significantly differ from impacts evaluated in the EA supporting the 
HI-STORM 100, Amendment No. 15 direct final rule. Accordingly, the NRC 
finds that granting the exemption will not significantly impact the 
quality of the human environment. Based on the foregoing discussion, 
the NRC staff finds that HDI's requested action, if approved is bounded 
by the EA for CoC No. 1014, Amendment No. 15.

Environmental Impacts of the Proposed Alternatives to the Proposed 
Action

    In addition to the proposed action, the staff also considered the 
no-action alternative--the denial of the proposed exemption request. 
Denial of the exemption would preserve the status quo, i.e., the 
licensee could continue loading one fuel assembly having an NSA in 
baskets but could not load multiple fuel assemblies having NSAs in the 
same basket and could only load that one fuel assembly having an NSA in 
the inner part of the basket. The NRC staff has previously found that 
the Indian Point Post-Shutdown Decommissioning Activities Report 
(PSDAR) contained a discussion providing the reasons for concluding 
that the environmental impacts associated with site-specific 
decommissioning activities will be bounded by appropriate previously 
issued environmental impact statements. Further, the NRC staff has 
previously found that the licensee provided adequate reasons in its 
PSDAR and associated request for additional information responses to 
conclude that, for generic issues, the environmental impacts of 
decommissioning Indian Point Units 2 and 3 are bounded by the previous 
environmental reviews. The effects of preserving the status quo would 
be bounded by these previous reviews. This is because preserving the 
status quo, in this regard, would preserve the status considered when 
the NRC staff reviewed the PSDAR. Under this alternative, the licensee 
would need to maintain the spent fuel pools for longer periods of time. 
This would lead to the generation of additional low-level waste from 
fuel pool cleaning activities. The licensee would need to dispose of 
this low-level waste, which would itself have environmental impacts. 
Based on that additional waste, the NRC staff has determined that the 
environmental impact of the no-action alternative would either be the 
same or may be greater than the proposed action.
    The NRC staff also considered a different alternative to granting 
the exemption. The licensee could request that the certificate holder, 
in this case Holtec International, request an amendment to CoC No. 
1014. Under this alternative, the licensee could either continue 
loading canisters with only one fuel assembly having an NSA in the 
inner part of the basket or postpone loading of multiple spent fuel 
assemblies that contain NSAs and not load spent fuel assemblies that 
contain NSAs in basket cells not located in the inner part of the 
baskets while the CoC holder prepared the request and the NRC staff 
reviewed it. In either scenario, HDI would extend the timeframe for 
which it maintained the Indian Point Units 2 and 3 spent fuel pools. 
Thus, the environmental impacts of the licensee requesting the 
certificate holder request an amendment, would be the generation of 
additional low-level waste from fuel pool cleaning activities. The 
licensee would need to dispose of this low-level waste, which would 
itself have environmental impacts. Further, if the CoC holder did seek 
an amendment and the NRC staff granted that requested amendment, the 
licensee would then load multiple fuel assemblies having NSAs in a 
single canister, in basket cells not located in the inner part of the 
baskets, thus ultimately leading to the environmental impacts caused by

[[Page 65616]]

granting this exemption. Therefore, the NRC staff has determined that 
the environmental impact of this alternative would either be the same 
or may be greater than the proposed action.

Alternative Use of Resources

    Issuance of this exemption does not impact the resource 
implications discussed in previous environmental reviews.

Agencies and Persons Consulted

    The NRC provided the New York State Energy Research and Development 
Authority (NYSERDA) a draft copy of this EA for review in an email 
dated July 19, 2022. In an email dated August 1, 2022, NYSERDA stated 
that it had completed its review. NYSERDA provided no comments 
explicitly addressing the NRC's assessment that granting the HDI 
exemption request has no significant impacts on the environment. 
However, NYSERDA noted that increasing the surface dose rate to 
approximately 3,934 millirem/hour, ``appears to be a very large 
increase.'' \1\ For the reasons previously stated, however, the NRC 
staff does not consider this increase significant from the perspective 
of this EA and FONSI.
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    \1\ The copy of this EA the NRC staff originally provided to 
NYSERDA, mistakenly listed the maximum total dose at the radial 
surface of the transfer cask at the axial midplane as approximately 
3,934 millirem/hour, rather than 5033.67 millirem/hour. The NRC 
staff is interpreting the comment to be referring to the maximum 
dose generally and responding as if the comment had said 5,034 
millirem/hour.
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    NYSERDA also provided three comments on the exemptions. The first 
two comments raised safety concerns with the exemption. The NRC staff 
will address these concerns, as appropriate, in the safety evaluation 
report it prepares as part of its review of the requested exemption. 
NYSERDA also raised a third comment related to transportability/
retrievability. The NRC staff responded to this comment in a letter to 
NYSERDA dated October 14, 2022.
    While preparing the safety evaluation, staff identified 
typographical errors in the draft EA provided to NYSERDA on July 19, 
2022, and as noted earlier, participated in a clarification call with 
HDI about the scope of the exemption. After correcting the 
typographical errors, as well as incorporating the clarification call 
information related to Cf-252 and Sb-Be NSAs, the NRC resubmitted the 
draft EA to NYSERDA for review on September 28, 2022. In an email dated 
September 29, 2022, NYSERDA reaffirmed their prior comments on the 
proposed exemption request, as submitted by letter on August 1, 2022, 
but did not provide additional comments.

Endangered Species Act Section 7 Consultation

    Section 7 of the Endangered Species Act (ESA) requires Federal 
agencies to consult with the U.S. Fish and Wildlife Service or National 
Marine Fisheries Service regarding actions that may affect listed 
species or designated critical habitats. The ESA is intended to prevent 
further decline of endangered and threatened species and restore those 
species and their critical habitat.
    The NRC staff determined that a consultation under section 7 of the 
ESA is not required because the proposed action will not affect listed 
species or critical habitat.

National Historic Preservation Act Section 106 Consultation

    Section 106 of the National Historic Preservation Act (NHPA) 
requires Federal agencies to consider the effects of their undertakings 
on historic properties. As stated in the NHPA, historic properties are 
any prehistoric or historic district, site, building, structure, or 
object included in, or eligible for inclusion in the National Register 
of Historic Places.
    The NRC determined that the scope of activities described in this 
exemption request do not have the potential to cause effects on 
historic properties because the NRC's approval of this exemption 
request will not authorize new construction or land-disturbing 
activities. The NRC staff also determined that the proposed action is 
not a type of activity that has the potential to impact historic 
properties because the proposed action would occur within the 
established Indian Point site boundary. Therefore, in accordance with 
36 CFR 800.3(a)(1), no consultation is required under section 106 of 
NHPA.

III. Finding of No Significant Impact

    The NRC staff has prepared an EA and associated FONSI in support of 
the proposed action. As discussed in this notice the proposed action is 
for the NRC to grant the exemption requested by Indian Point Energy 
Center that would allow HDI to load up to three MPC-32Ms, using 
Amendment No. 15 for CoC No. 1014, with either up to thirty-two fuel 
assemblies having either Cf-252 or Sb-Be NSAs with sufficient cooling 
time, or a combination of up to five fuel assemblies having primary Pu-
Be NSAs and the remaining basket locations with fuel assemblies having 
either Cf-252 or Sb-Be NSAs with sufficient cooling time. It would also 
permit HDI to load the fuel assemblies having either Cf-252 or Sb-Be 
NSAs in any location in the basket and the fuel assemblies having Pu-Be 
NSAs such that one is located in the center of the basket and one is 
located in each of the four basket quadrants. The NRC staff has 
concluded that the proposed action will not result in radiological or 
non-radiological environmental impacts that significantly differ from 
impacts evaluated in the EA supporting the HI-STORM 100, Amendment No. 
15 direct final rule. In this EA, the NRC staff considered two 
alternatives and determined that the environmental impacts of granting 
this exemption will be less than or the same as both alternatives. No 
changes are being made in the types or quantities of effluents that may 
be released offsite, and there is no significant increase in 
occupational or public radiation exposures in granting this exemption 
request for HDI. Accordingly, the NRC finds that granting the exemption 
will not significantly impact the quality of the human environment.
    The NRC staff has determined that this exemption would have no 
impact on historic and cultural resources or ecological resources and 
therefore no consultations are necessary under section 7 of the ESA or 
section 106 of the NHPA.
    Therefore, based on the previously noted discussions, the NRC finds 
that there are no significant environmental impacts from the proposed 
action, and that preparation of an environmental impact statement is 
not warranted. Accordingly, the NRC has determined that a FONSI is 
appropriate.

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.
------------------------------------------------------------------------
Indian Point Energy Center--Request for           ML22083A191.
 Exemption from an Allowable Contents
 Requirement Contained in the Certificate of
 Compliance No. 1014 for the HI-STORM 100S
 Version E Cask, dated March 24, 2022.

[[Page 65617]]

 
Indian Point Exemption Environmental Assessment   ML22172A174.
 Conversation Record (6-16-22), date of contact
 June 16, 2022.
Neutron Source Assembly Loading Clarification     ML22264A045.
 Call, date of contact September 20, 2022.
Issuance of Certificate of Compliance No. 1014,   ML21118A862 (Package).
 Amendment No. 15 for the HI-STORM 100
 Multipurpose Canister Storage System, dated May
 13, 2021.
HI-2002444, Revision 22, Holtec International     ML21221A329.
 Final Safety Analysis Report for the HI-STORM
 100 Cask System, dated August 9, 2021.
Environmental Assessment and Finding of No        ML22215A098.
 Significant Impact, dated October 25, 2022.
Indian Point Energy Center--Review of Post-       ML22082A220.
 Shutdown Decommissioning Activities Report,
 dated May 2, 2022.
Email Transmitting Indian Point Exemption Draft   ML22208A029.
 EA, dated July 19, 2022.
New York State Neutron Source Assembly Exemption  ML22215A042 (Package).
 Comments & Draft Environmental Assessment
 Review, dated August 1, 2022.
Response to Comments on Exemption Related to      ML22234A063.
 Allowable Contents for the Certificate of
 Compliance No. 1014, HI-STORM 100S Version E
 Cask, dated October 14, 2022.
Email Transmitting Revised Indian Point           ML22271A849.
 Exemption Draft EA, dated September 28, 2022.
New York State Revised Draft EA Response Email,   ML22276A164.
 dated September 29, 2022.
------------------------------------------------------------------------


    Dated: October 26, 2022.

    For the Nuclear Regulatory Commission.
Yoira K. Diaz-Sanabria,
Chief, Storage and Transportation Licensing Branch, Division of Fuel 
Management, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2022-23657 Filed 10-28-22; 8:45 am]
BILLING CODE 7590-01-P