Fort St. Vrain Independent Spent Fuel Storage Installation, 9002-9003 [2016-03810]
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Federal Register / Vol. 81, No. 35 / Tuesday, February 23, 2016 / Notices
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grant applicants, the meetings will be
closed to the public pursuant to sections
552b(c)(4) and 552b(c)(6) of Title 5,
U.S.C., as amended. I have made this
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granted me by the Chairman’s
Delegation of Authority to Close
Advisory Committee Meetings dated
July 19, 1993.
Dated: February 17, 2016.
Elizabeth Voyatzis,
Committee Management Officer.
[FR Doc. 2016–03688 Filed 2–22–16; 8:45 am]
BILLING CODE 7536–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–09; NRC–2016–0036]
Fort St. Vrain Independent Spent Fuel
Storage Installation
Nuclear Regulatory
Commission.
ACTION: Environmental assessment and
finding of no significant impact;
issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is considering a
license amendment request for the
Special Nuclear Materials License
SNM–2504 for the Fort St. Vrain (FSV)
independent spent fuel storage
installation (ISFSI) located in Weld
County, Colorado. The NRC staff is
issuing an environmental assessment
(EA) and finding of no significant
impact (FONSI) associated with the
proposed action.
DATES: The EA and FONSI referenced in
this document are available on February
23, 2016.
ADDRESSES: Please refer to Docket ID
NRC–2016–0036 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 Web Site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0036. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@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 publiclyavailable documents online in the
mstockstill on DSK4VPTVN1PROD with NOTICES
SUMMARY:
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17:06 Feb 22, 2016
Jkt 238001
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff
at: 1–800–397–4209, 301–415–4737, or
by email to pdr.resource@nrc.gov. The
ADAMS accession number for each
document referenced (if that document
is available in ADAMS) is provided the
first time that a document is referenced.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Jean
Trefethen, Office of Nuclear Material
Safety and Safeguards, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001; telephone: 301–415–
0867, email: Jean.Trefethen@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering a license
amendment request for Special Nuclear
Materials License Number SNM–2504
for the FSV ISFSI located in Weld
County, Colorado (ADAMS Accession
Nos.: ML15069A007, ML15084A014,
and ML15331A359, respectively). The
applicant, the U.S. Department of
Energy (DOE) Idaho Operations Office,
is proposing to amend Technical
Specifications (TS) 3.3.1, ‘‘Seal Leak
Rate,’’ to revise the response time to
complete some of the corrective actions
in TS 3.3.1 if the leak rate limit is
exceeded. Also proposed is: (i) Addition
of Section 5.5.5, ‘‘Aging Management
Program,’’ to the TS Table of Contents
of Appendix A to license SNM–2504,
(ii) clarification to language in Item 6 of
Section 5.5.2, ‘‘Essential Programs
Control Program,’’ and (iii) addition of
a notation that the license was renewed.
The NRC staff has prepared a final EA
as part of its review of this proposed
license amendment in accordance with
the requirements in part 51 of title 10 of
the Code of Federal Regulations (10
CFR). Based on the final EA, the NRC
has determined that a FONSI is
appropriate. The NRC is also conducting
a safety evaluation of the proposed
license amendment pursuant to 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,’’ and the results will be
documented in a separate Safety
Evaluation Report (SER). If DOE’s
request is approved, the NRC will issue
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the license amendment following
publication of this final EA and FONSI
and completion of the SER.
II. Final Environmental Assessment
Summary
The irradiated fuel in the ISFSI is
contained in fuel storage containers
(FSC), which are sealed with double
metal O-ring seals between the FSC
body and the lid. TS 3.3.1 in Appendix
A of license SNM–2504 requires that the
FSC or storage well seal leakage rate not
exceed 1 × 103 reference cubic
centimeters per second (ref-cm3/s). The
TS requires the licensee to test the leak
rate of one FSC from each vault every
5 years. The TS also calls for specific
corrective actions to be performed
within a specified amount of time if the
leak rate limit is exceeded for one or
two seals on FSCs or storage wells. If
approved, the proposed license
amendment would allow DOE to revise
the response time to complete the
following corrective actions in TS 3.3.1
if the leak rate limit is exceeded: (i)
Lengthen the response time for
completing corrective actions A.1.1,
A.1.2.1, and A.1.2.2 from seven days to
21 days, and (ii) lengthen the response
time for completing corrective action
A.2 from 30 days to 45 days. In
addition, the amendment would include
the following changes that are
administrative in nature: (i) addition of
Section 5.5.5, ‘‘Aging Management
Program,’’ to the TS Table of Contents
of Appendix A to license SNM–2504,
(ii) clarification to language in item 6 of
section 5.5.2, ‘‘Essential Programs
Control Program,’’ and (iii) addition of
a notation that the license was renewed.
As documented in the EA, this portion
of the proposed action that includes
changes that are administrative in
nature meets the categorical exclusion
provision in 10 CFR 51.22(c)(11).
The NRC has assessed the potential
environmental impacts associated with
the proposed action of amending SNM–
2504 TS 3.3.1, as well as the no-action
alternative, and has documented the
results in the final EA (ADAMS
Accession No. ML16028A407). The NRC
staff performed its environmental
review in accordance with the
requirements in 10 CFR part 51. In
conducting the environmental review,
the NRC considered information in the
license amendment application;
information in the responses to the
NRC’s requests for additional
information (RAIs); and
communications with DOE, the
Colorado State Historic Preservation
Office, the U.S. Fish and Wildlife
Service, and the Colorado Department of
Public Health and Environment.
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Federal Register / Vol. 81, No. 35 / Tuesday, February 23, 2016 / Notices
As documented in the EA, the NRC
staff concluded that the proposed action
will not authorize or result in changes
to licensed operations, land-disturbing
activities, or changes in the types,
characteristics, or quantities of
radiological or non-radiological
effluents released into the environment
from the ISFSI. The staff also concluded
that the radiological or non-radiological
impacts from approval of the license
amendment request would be small, and
the proposed action would not
significantly contribute to cumulative
impacts. In addition, the staff does not
expect that the proposed action would
adversely affect any offsite population
and, thus, no special circumstances
were identified. The Colorado State
Historic Preservation Office concurred
with the NRC’s determination that the
proposed action would not affect
historic properties, and the U.S. Fish
and Wildlife Service concurred with the
NRC’s determination that the proposed
action would not affect listed species or
critical habitats. Furthermore, the NRC
determined that the proposed action is
more favorable than the no-action
alternative (denial of the license
amendment request), which would
require DOE to complete the required
corrective actions within the currently
specified response times. Therefore, the
NRC concluded that the proposed action
will not result in a significant effect on
the quality of the human environment.
III. Finding of No Significant Impact
mstockstill on DSK4VPTVN1PROD with NOTICES
Based on its review of the proposed
action, in accordance with the
requirements in 10 CFR part 51, the
NRC has concluded that the proposed
action, amendment of NRC Special
Nuclear Materials License No. SNM–
2504 for the FSV ISFSI located in Weld
County, Colorado, will not significantly
affect the quality of the human
environment. Therefore, the NRC has
determined, pursuant to 10 CFR 51.31,
that preparation of an environmental
impact statement is not required for the
proposed action and a FONSI is
appropriate.
Dated at Rockville, Maryland, this 16th day
of February 2016.
For the Nuclear Regulatory Commission.
Craig G. Erlanger,
Acting Director, Division of Fuel Cycle Safety,
Safeguards, and Environmental Review,
Office of Nuclear Material Safety and
Safeguards.
[FR Doc. 2016–03810 Filed 2–22–16; 8:45 am]
BILLING CODE 7590–01–P
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17:06 Feb 22, 2016
Jkt 238001
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–293; NRC–2016–0035]
Entergy Nuclear Operations, Inc.,
Pilgrim Nuclear Power Station
Nuclear Regulatory
Commission.
ACTION: Petition request; receipt.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is giving notice that
by petition dated June 24, 2015, as
supplemented, David Lochbaum of the
Union of Concerned Scientists and
others (the petitioners) requested that
the NRC take action with regard to the
Pilgrim Nuclear Power Station (Pilgrim).
The petitioner’s requests are included in
the SUPPLEMENTARY INFORMATION section
of this document.
ADDRESSES: Please refer to Docket ID
NRC–2016–0035 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 Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2016–0035. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–415–3463;
email: Carol.Gallagher@nrc.gov.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may obtain publiclyavailable documents online in the
ADAMS Public Documents collection at
https://www.nrc.gov/reading-rm/
adams.html. To begin the search, select
‘‘ADAMS Public Documents’’ and then
select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. The
ADAMS accession number for each
document referenced (if that document
is available in ADAMS) is provided the
first time that a document is referenced.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
SUPPLEMENTARY INFORMATION: On June
24, 2015, the petitioners requested that
the NRC take enforcement action with
regard to Pilgrim concerning the current
licensing basis on flooding (ADAMS
Accession No. ML16029A407). The
petitioners requested that the NRC take
enforcement action to require that the
current licensing basis for Pilgrim
explicitly include flooding caused by
SUMMARY:
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9003
local intense precipitation or probable
maximum precipitation events.
As the basis for this request, the
petitioners referred to Pilgrim’s flood
reevaluation report provided by Entergy
Nuclear Operations, Inc. (Entergy, the
licensee) to the NRC in a letter dated
March 12, 2015 (ADAMS Accession No.
ML15075A082). The petitioners state
that Pilgrim’s reevaluations indicate that
the site could experience flood levels
from heavy rainfall events nearly ten
feet higher than anticipated when the
plant was originally licensed. Although
existing doors protect important
equipment from being submerged and
damaged, the petitioners assert that
neither regulatory requirements nor
enforceable commitments exist that
ensure the continued reliability of flood
protection features that are currently
installed at the site to protect important
equipment from being submerged and
damaged. The petition states in relevant
part ‘‘the petitioners seek to rectify
safety shortcoming by revising the
current licensing basis to include
flooding caused by heavy rainfall
events.’’
The request is being treated pursuant
to Section 2.206 of title 10 of the Code
of Federal Regulations (10 CFR) of the
NRC’s regulations. A conference call
was held between the petitioner and the
Petition Review Board (PRB) on August
5, 2015, to discuss the petition; the
transcript of that teleconference is an
additional supplement to the petition
(ADAMS Accession No. ML15230A017).
The PRB has reviewed the petition, and
its supplement, and referred the request
to the Director of the Office of Nuclear
Reactor Regulation. The Director
partially granted for review the
petitioners’ concerns that the current
licensing basis be revised to include
specific beyond-design-basis flood
events at Pilgrim. The parts of the
petitioners’ concerns not granted for
review are the impact of precipitation
events on safety-related submerged
cables as this was previously reviewed
and resolved in a prior 10 CFR 2.206
Director’s Decision (ADAMS Accession
No. ML13255A191), and the request for
an updated site plan of Pilgrim, because
this request is outside of the scope of
the 10 CFR 2.206 process. The NRC staff
will hold the petition until a resolution
of ongoing reviews associated with the
subject of the petitioners’ concerns is
achieved.
Dated at Rockville, Maryland, this 11th day
of February 2016.
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Agencies
[Federal Register Volume 81, Number 35 (Tuesday, February 23, 2016)]
[Notices]
[Pages 9002-9003]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-03810]
=======================================================================
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NUCLEAR REGULATORY COMMISSION
[Docket No. 72-09; NRC-2016-0036]
Fort St. Vrain Independent Spent Fuel Storage Installation
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental assessment and finding of no significant impact;
issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering a
license amendment request for the Special Nuclear Materials License
SNM-2504 for the Fort St. Vrain (FSV) independent spent fuel storage
installation (ISFSI) located in Weld County, Colorado. The NRC staff is
issuing an environmental assessment (EA) and finding of no significant
impact (FONSI) associated with the proposed action.
DATES: The EA and FONSI referenced in this document are available on
February 23, 2016.
ADDRESSES: Please refer to Docket ID NRC-2016-0036 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 Web Site: Go to https://www.regulations.gov and search for Docket ID NRC-2016-0036. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@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 ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at:
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. The
ADAMS accession number for each document referenced (if that document
is available in ADAMS) is provided the first time that a document is
referenced.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Jean Trefethen, Office of Nuclear
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001; telephone: 301-415-0867, email:
Jean.Trefethen@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering a license amendment request for Special
Nuclear Materials License Number SNM-2504 for the FSV ISFSI located in
Weld County, Colorado (ADAMS Accession Nos.: ML15069A007, ML15084A014,
and ML15331A359, respectively). The applicant, the U.S. Department of
Energy (DOE) Idaho Operations Office, is proposing to amend Technical
Specifications (TS) 3.3.1, ``Seal Leak Rate,'' to revise the response
time to complete some of the corrective actions in TS 3.3.1 if the leak
rate limit is exceeded. Also proposed is: (i) Addition of Section
5.5.5, ``Aging Management Program,'' to the TS Table of Contents of
Appendix A to license SNM-2504, (ii) clarification to language in Item
6 of Section 5.5.2, ``Essential Programs Control Program,'' and (iii)
addition of a notation that the license was renewed. The NRC staff has
prepared a final EA as part of its review of this proposed license
amendment in accordance with the requirements in part 51 of title 10 of
the Code of Federal Regulations (10 CFR). Based on the final EA, the
NRC has determined that a FONSI is appropriate. The NRC is also
conducting a safety evaluation of the proposed license amendment
pursuant to 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,'' and the
results will be documented in a separate Safety Evaluation Report
(SER). If DOE's request is approved, the NRC will issue the license
amendment following publication of this final EA and FONSI and
completion of the SER.
II. Final Environmental Assessment Summary
The irradiated fuel in the ISFSI is contained in fuel storage
containers (FSC), which are sealed with double metal O-ring seals
between the FSC body and the lid. TS 3.3.1 in Appendix A of license
SNM-2504 requires that the FSC or storage well seal leakage rate not
exceed 1 x 10\3\ reference cubic centimeters per second (ref-cm\3\/s).
The TS requires the licensee to test the leak rate of one FSC from each
vault every 5 years. The TS also calls for specific corrective actions
to be performed within a specified amount of time if the leak rate
limit is exceeded for one or two seals on FSCs or storage wells. If
approved, the proposed license amendment would allow DOE to revise the
response time to complete the following corrective actions in TS 3.3.1
if the leak rate limit is exceeded: (i) Lengthen the response time for
completing corrective actions A.1.1, A.1.2.1, and A.1.2.2 from seven
days to 21 days, and (ii) lengthen the response time for completing
corrective action A.2 from 30 days to 45 days. In addition, the
amendment would include the following changes that are administrative
in nature: (i) addition of Section 5.5.5, ``Aging Management Program,''
to the TS Table of Contents of Appendix A to license SNM-2504, (ii)
clarification to language in item 6 of section 5.5.2, ``Essential
Programs Control Program,'' and (iii) addition of a notation that the
license was renewed. As documented in the EA, this portion of the
proposed action that includes changes that are administrative in nature
meets the categorical exclusion provision in 10 CFR 51.22(c)(11).
The NRC has assessed the potential environmental impacts associated
with the proposed action of amending SNM-2504 TS 3.3.1, as well as the
no-action alternative, and has documented the results in the final EA
(ADAMS Accession No. ML16028A407). The NRC staff performed its
environmental review in accordance with the requirements in 10 CFR part
51. In conducting the environmental review, the NRC considered
information in the license amendment application; information in the
responses to the NRC's requests for additional information (RAIs); and
communications with DOE, the Colorado State Historic Preservation
Office, the U.S. Fish and Wildlife Service, and the Colorado Department
of Public Health and Environment.
[[Page 9003]]
As documented in the EA, the NRC staff concluded that the proposed
action will not authorize or result in changes to licensed operations,
land-disturbing activities, or changes in the types, characteristics,
or quantities of radiological or non-radiological effluents released
into the environment from the ISFSI. The staff also concluded that the
radiological or non-radiological impacts from approval of the license
amendment request would be small, and the proposed action would not
significantly contribute to cumulative impacts. In addition, the staff
does not expect that the proposed action would adversely affect any
offsite population and, thus, no special circumstances were identified.
The Colorado State Historic Preservation Office concurred with the
NRC's determination that the proposed action would not affect historic
properties, and the U.S. Fish and Wildlife Service concurred with the
NRC's determination that the proposed action would not affect listed
species or critical habitats. Furthermore, the NRC determined that the
proposed action is more favorable than the no-action alternative
(denial of the license amendment request), which would require DOE to
complete the required corrective actions within the currently specified
response times. Therefore, the NRC concluded that the proposed action
will not result in a significant effect on the quality of the human
environment.
III. Finding of No Significant Impact
Based on its review of the proposed action, in accordance with the
requirements in 10 CFR part 51, the NRC has concluded that the proposed
action, amendment of NRC Special Nuclear Materials License No. SNM-2504
for the FSV ISFSI located in Weld County, Colorado, will not
significantly affect the quality of the human environment. Therefore,
the NRC has determined, pursuant to 10 CFR 51.31, that preparation of
an environmental impact statement is not required for the proposed
action and a FONSI is appropriate.
Dated at Rockville, Maryland, this 16th day of February 2016.
For the Nuclear Regulatory Commission.
Craig G. Erlanger,
Acting Director, Division of Fuel Cycle Safety, Safeguards, and
Environmental Review, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2016-03810 Filed 2-22-16; 8:45 am]
BILLING CODE 7590-01-P