Pacific Gas and Electric Company; Diablo Canyon Independent Spent Fuel Storage Installation, 11833-11834 [2014-04597]
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Federal Register / Vol. 79, No. 41 / Monday, March 3, 2014 / Notices
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circumstances noted in 3 above. A
License Verification System (LVS) has
been developed, providing an electronic
method for fulfilling this requirement.
In cases where a licensee is unable to
use the LVS to perform verification,
they will provide NRC Form 749 for
manual license verification.
7. An estimate of the number of
annual responses: 91.
8. The estimated number of annual
respondents: 91.
9. An estimate of the total number of
hours needed annually to complete the
requirement or request: 9.1 hours.
10. Abstract: When a licensee is
unable to use the License Verification
System to perform their license
verification prior to transfer, a manual
process has been developed; in which
licensees submit the NRC Form 749,
‘‘Manual License Verification Report.’’
The form provides the information
necessary for the issuing agencies to
perform the verification on behalf of the
transferring licensee.
The public may examine and have
copied for a fee publicly-available
documents, including the final
supporting statement, at the NRC’s
Public Document Room, Room O–1F21,
One White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852. The
OMB clearance requests are available at
the NRC’s Web site: https://www.nrc.gov/
public-involve/doc-comment/omb/.
The document will be available on the
NRC’s home page site for 60 days after
the signature date of this notice.
Comments and questions should be
directed to the OMB reviewer listed
below by April 2, 2014. Comments
received after this date will be
considered if it is practical to do so, but
assurance of consideration cannot be
given to comments received after this
date.
Danielle Y. Jones, Desk Officer, Office
of Information and Regulatory Affairs
(3150–XXXX), NEOB–10202, Office of
Management and Budget, Washington,
DC 20503.
Comments can also be emailed to
Danielle_Y_Jones@omb.eop.gov or
submitted by telephone at 202–395–
1741.
The Acting NRC Clearance Officer is
Kristen Benney, telephone: 301–415–
6355.
Dated at Rockville, Maryland, this 25th day
of February, 2014.
For the Nuclear Regulatory Commission.
Kristen Benney,
Acting NRC Clearance Officer, Office of
Information Services.
[FR Doc. 2014–04478 Filed 2–28–14; 8:45 am]
BILLING CODE 7590–01–P
VerDate Mar<15>2010
19:40 Feb 28, 2014
Jkt 232001
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–26; NRC–2012–0312]
Pacific Gas and Electric Company;
Diablo Canyon Independent Spent Fuel
Storage Installation
Nuclear Regulatory
Commission.
ACTION: License amendment; issuance.
AGENCY:
SUMMARY: The U.S. Nuclear Regulatory
Commission (NRC) is amending
Materials License No. SNM–2511 for the
Diablo Canyon (DC) independent spent
fuel storage installation (ISFSI).
Amendment No. 3 provides the
following: (1) Changes the maximum
allowable decay heat per storage
location; (2) adds a new helium backfill
pressure range for multipurpose
canisters (MPCs) with heat loads less
than or equal to 28.74kW, (3) clarifies
that supplemental cooling was only
applicable for unloading of high burnup
fuel loaded in 2012 under the
provisions of License Amendment No.
2, and (4) provides a maximum average
yearly temperature of 65 °F as the basis
for a loaded overpack in the cask
transfer facility, or storage on the ISFSI
pad, and a maximum temperature of
100 °F, averaged over a 3-day period, as
the basis for transfer activities in the
transfer cask to support revised thermal
analyses.
ADDRESSES: Please refer to Docket ID:
NRC–2012–0312 when contacting the
NRC about the availability of
information regarding this document.
You may access 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–2012–0312. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual(s) 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. For the
PO 00000
Frm 00084
Fmt 4703
Sfmt 4703
11833
convenience of the reader, the ADAMS
accession numbers are provided in a
table in the ‘‘Availability of Documents’’
section of this document.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: John
Goshen, Office of Nuclear Material
Safety and Safeguards, telephone: 301–
287–9250, email: John.Goshen@nrc.gov;
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001.
SUPPLEMENTARY INFORMATION:
I. Introduction
By letter dated July 31, 2012, as
supplemented March 14, May 23, and
September 5, 2013, PG&E submitted
license amendment request (LAR) 12–
003 (ADAMS Accession No.
ML122270603) to the NRC to amend
Materials License No. SNM–2511 for the
DC ISFSI in accordance with 10 CFR
Part 72. PG&E’s application requested
that the ISFSI Technical Specifications
(TS) be revised as follows:
1. Tables 2.1–7, 2.1–8, and 2.1–9 in
TS 2.0, ‘‘Approved Contents,’’ are
revised allowing up to a 28.74kW heat
load for uniform loading and 25.572kW
heat load for regionalized loading. This
changes the maximum allowable decay
heat per storage location, in watts,
determined from Table 2.1–7 or 2.1–9 to
be consistent with this proposed license
amendment request. Table 2.1–8 is
revised to delete the note that limits
Zirlo clad fuel to a burnup of 45,000
MWD/MTU and replace the existing
Note 3 with a note that refers to TS 2.3,
‘‘Alternate MPC–32 Fuel Selection
Criteria.’’
2. TS 2.3, ‘‘Alternate MPC–32 Fuel
Selection Criteria,’’ is revised to add
reference to Table 2.1–9 as regionalized
loading of high burn-up fuel (HBF).
3. TS 3.1.1, ‘‘Multi-Purpose Canister
(MPC),’’ Surveillance Requirement (SR)
3.1.1.2 is revised to add a new helium
backfill pressure range for MPCs with
heat loads less than or equal to
28.74kW.
4. TS 3.1.4, ‘‘Supplemental Cooling
System,’’ Applicability is changed to
only be applicable for unloading of high
burnup fuel loaded in 2012 under the
provisions of License Amendment No.
2.
5. Addition of TS 4.1.3 Design
Features Important to Thermal Analysisa. A maximum average yearly
temperature of 65 °F is the basis for a
loaded overpack in the cask transfer
facility, or storage on the ISFSI pad.
b. A maximum temperature of 100 °F,
averaged over a 3-day period, is the
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03MRN1
11834
Federal Register / Vol. 79, No. 41 / Monday, March 3, 2014 / Notices
basis for transfer activities in the
transfer cask.
In accordance with 10 CFR 72.16, a
Notice of Docketing and Opportunity to
Request a hearing was published in the
Federal Register on January 2, 2013 (78
FR 123). On February 11, 2014, the NRC
approved and issued Amendment No.3
to Materials License No. SNM–2511
(ADAMS Accession No. ML14043A517),
held by PG&E for the receipt,
possession, transfer, and storage of
spent fuel at the DC ISFSI. Amendment
No. 3 was effective as of the date of
issuance. Pursuant to 10 CFR 72.46(d),
the NRC is providing notice of the
action taken.
Amendment No. 3 complies with the
standards and requirements of the
Atomic Energy Act of 1954, as amended
(the Act), and the NRC’s rules and
regulations. As required by the Act and
the NRC’s rules and regulations in 10
CFR Chapter I, the NRC has made
appropriate findings, which are set forth
in the Amendment No. 3 safety
evaluation report (SER) (ADAMS
Accession No. ML14049A476). Also as
described in the SER, the NRC
determined that issuance of
Amendment No. 3 meets the criteria
specified in 10 CFR 51.22(c)(11) for a
categorical exclusion. Thus, the
preparation of an environmental
assessment or an environmental impact
statement is not required. On February
11, 2014, the California Energy
Commission was informed of the NRC’s
action. The state had no comments.
II. Further information
The NRC has prepared an SER that
documents the staff’s review and
evaluation of the amendment. In
accordance with 10 CFR 2.390 of NRC’s
‘‘Rules of Practice,’’ final NRC records
and documents related to this action,
including the application for
amendment and supporting
documentation, and the SER, are
available electronically at the NRC’s
Electronic Reading Room, at: https://
www.nrc.gov/reading-rm/adams.html.
From this site, you can access NRC’s
ADAMS, which provides text and image
files of NRC’s public documents. The
ADAMS Accession Numbers for the
applicable documents are:
Document
Date
ADAMS Accession No.
License Amendment Request ......................................................................................
Response to First Request for Additional Information .................................................
Response to Second Request for Additional Information ............................................
Supplement to License Amendment Request .............................................................
License Amendment No. 3 Issuance Package ............................................................
SER ..............................................................................................................................
July 31, 2012 ............................................
March 14, 2013 .........................................
May 23, 2013 ............................................
September 5, 2013 ...................................
February 11, 2014 ....................................
February 11, 2014 ....................................
ML122270603
ML130860130
ML13175A184
ML13259A274
ML14043A517
ML14049A476
Dated at Rockville, Maryland, this 19th day
of February, 2014.
For the Nuclear Regulatory Commission.
Michele M. Sampson,
Chief, Licensing Branch, Division of Spent
Fuel Storage and Transportation, Office of
Nuclear Material Safety and Safeguards.
[FR Doc. 2014–04597 Filed 2–28–14; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
License Renewal Application for
Callaway Plant, Unit 1
Nuclear Regulatory
Commission.
ACTION: Draft supplemental generic
environmental impact statement;
issuance, public meeting, and request
for comment; correction.
AGENCY:
mstockstill on DSK4VPTVN1PROD with NOTICES
19:40 Feb 28, 2014
Jkt 232001
Monday, March 3, 2014
1:30 p.m. Briefing on Human
Reliability Program Activities and
Analyses (Public Meeting);
(Contact: Sean Peters, 301–251–
7582).
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
In Fr. Doc. 2014–03845, on page
10200, in the first column, in the DATES:
section, the date is changed from ‘‘April
10, 2014,’’ to read ‘‘April 7, 2014.’’ This
change is necessary in order to coincide
with the comment expiration date noted
in the U.S. Environmental Protection
Agency’s notice appearing in the
Federal Register on February 21, 2014
(79 FR 9898; FR Doc. 2014–03726).
[FR Doc. 2014–04582 Filed 2–28–14; 8:45 am]
BILLING CODE 7590–01–P
This document corrects a
notice appearing in the Federal Register
on February 24, 2014 (79 FR 10200; FR
Doc. 2014–03845). This action is
necessary to correct an erroneous date
for submission of comments.
FOR FURTHER INFORMATION CONTACT:
Carmen Fells, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone: 301–415–6337 or by
email at Carmen.Fells@nrc.gov.
VerDate Mar<15>2010
Week of March 3, 2014
Correction
Dated at Rockville, Maryland, this 26th day
of February, 2014.
For the Nuclear Regulatory Commission.
Cindy Bladey,
Chief, Rules, Announcements, and Directives
Branch, Division of Administrative Services,
Office of Administration.
[NRC–2012–0001]
SUMMARY:
SUPPLEMENTARY INFORMATION:
NUCLEAR REGULATORY
COMMISSION
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10:00 a.m. Meeting with the Advisory
Committee on Reactor Safeguards
(ACRS) (Public Meeting); (Contact:
Ed Hackett, 301–415–7360).
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
Week of March 17, 2014—Tentative
Friday, March 21, 2014
Weeks of March 3, 10, 17, 24, 31,
April 7, 2014.
PLACE: Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and Closed.
Frm 00085
Friday, March 7, 2014
There are no meetings scheduled for
the week of March 10, 2014.
Sunshine Act Meeting Notice
PO 00000
9:00 a.m. Briefing on Security Issues
(Closed—Ex. 1).
1:30 p.m. Briefing on Security Issues
(Closed—Ex. 1).
Week of March 10, 2014—Tentative
[NRC–2014–0001]
DATE:
Tuesday, March 4, 2014
1:00 p.m. Briefing on Waste
Confidence Rulemaking (Public
Meeting); (Contact: Andrew
Imboden, 301–287–9220).
This meeting will be webcast live at
the Web address—https://www.nrc.gov/.
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Agencies
[Federal Register Volume 79, Number 41 (Monday, March 3, 2014)]
[Notices]
[Pages 11833-11834]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-04597]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 72-26; NRC-2012-0312]
Pacific Gas and Electric Company; Diablo Canyon Independent Spent
Fuel Storage Installation
AGENCY: Nuclear Regulatory Commission.
ACTION: License amendment; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending
Materials License No. SNM-2511 for the Diablo Canyon (DC) independent
spent fuel storage installation (ISFSI). Amendment No. 3 provides the
following: (1) Changes the maximum allowable decay heat per storage
location; (2) adds a new helium backfill pressure range for
multipurpose canisters (MPCs) with heat loads less than or equal to
28.74kW, (3) clarifies that supplemental cooling was only applicable
for unloading of high burnup fuel loaded in 2012 under the provisions
of License Amendment No. 2, and (4) provides a maximum average yearly
temperature of 65[emsp14][deg]F as the basis for a loaded overpack in
the cask transfer facility, or storage on the ISFSI pad, and a maximum
temperature of 100[emsp14][deg]F, averaged over a 3-day period, as the
basis for transfer activities in the transfer cask to support revised
thermal analyses.
ADDRESSES: Please refer to Docket ID: NRC-2012-0312 when contacting the
NRC about the availability of information regarding this document. You
may access 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-2012-0312. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual(s) 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. For
the convenience of the reader, the ADAMS accession numbers are provided
in a table in the ``Availability of Documents'' section of this
document.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: John Goshen, Office of Nuclear
Material Safety and Safeguards, telephone: 301-287-9250, email:
John.Goshen@nrc.gov; U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
SUPPLEMENTARY INFORMATION:
I. Introduction
By letter dated July 31, 2012, as supplemented March 14, May 23,
and September 5, 2013, PG&E submitted license amendment request (LAR)
12-003 (ADAMS Accession No. ML122270603) to the NRC to amend Materials
License No. SNM-2511 for the DC ISFSI in accordance with 10 CFR Part
72. PG&E's application requested that the ISFSI Technical
Specifications (TS) be revised as follows:
1. Tables 2.1-7, 2.1-8, and 2.1-9 in TS 2.0, ``Approved Contents,''
are revised allowing up to a 28.74kW heat load for uniform loading and
25.572kW heat load for regionalized loading. This changes the maximum
allowable decay heat per storage location, in watts, determined from
Table 2.1-7 or 2.1-9 to be consistent with this proposed license
amendment request. Table 2.1-8 is revised to delete the note that
limits Zirlo clad fuel to a burnup of 45,000 MWD/MTU and replace the
existing Note 3 with a note that refers to TS 2.3, ``Alternate MPC-32
Fuel Selection Criteria.''
2. TS 2.3, ``Alternate MPC-32 Fuel Selection Criteria,'' is revised
to add reference to Table 2.1-9 as regionalized loading of high burn-up
fuel (HBF).
3. TS 3.1.1, ``Multi-Purpose Canister (MPC),'' Surveillance
Requirement (SR) 3.1.1.2 is revised to add a new helium backfill
pressure range for MPCs with heat loads less than or equal to 28.74kW.
4. TS 3.1.4, ``Supplemental Cooling System,'' Applicability is
changed to only be applicable for unloading of high burnup fuel loaded
in 2012 under the provisions of License Amendment No. 2.
5. Addition of TS 4.1.3 Design Features Important to Thermal
Analysis-
a. A maximum average yearly temperature of 65[emsp14][deg]F is the
basis for a loaded overpack in the cask transfer facility, or storage
on the ISFSI pad.
b. A maximum temperature of 100[emsp14][deg]F, averaged over a 3-
day period, is the
[[Page 11834]]
basis for transfer activities in the transfer cask.
In accordance with 10 CFR 72.16, a Notice of Docketing and
Opportunity to Request a hearing was published in the Federal Register
on January 2, 2013 (78 FR 123). On February 11, 2014, the NRC approved
and issued Amendment No.3 to Materials License No. SNM-2511 (ADAMS
Accession No. ML14043A517), held by PG&E for the receipt, possession,
transfer, and storage of spent fuel at the DC ISFSI. Amendment No. 3
was effective as of the date of issuance. Pursuant to 10 CFR 72.46(d),
the NRC is providing notice of the action taken.
Amendment No. 3 complies with the standards and requirements of the
Atomic Energy Act of 1954, as amended (the Act), and the NRC's rules
and regulations. As required by the Act and the NRC's rules and
regulations in 10 CFR Chapter I, the NRC has made appropriate findings,
which are set forth in the Amendment No. 3 safety evaluation report
(SER) (ADAMS Accession No. ML14049A476). Also as described in the SER,
the NRC determined that issuance of Amendment No. 3 meets the criteria
specified in 10 CFR 51.22(c)(11) for a categorical exclusion. Thus, the
preparation of an environmental assessment or an environmental impact
statement is not required. On February 11, 2014, the California Energy
Commission was informed of the NRC's action. The state had no comments.
II. Further information
The NRC has prepared an SER that documents the staff's review and
evaluation of the amendment. In accordance with 10 CFR 2.390 of NRC's
``Rules of Practice,'' final NRC records and documents related to this
action, including the application for amendment and supporting
documentation, and the SER, are available electronically at the NRC's
Electronic Reading Room, at: https://www.nrc.gov/reading-rm/adams.html.
From this site, you can access NRC's ADAMS, which provides text and
image files of NRC's public documents. The ADAMS Accession Numbers for
the applicable documents are:
------------------------------------------------------------------------
ADAMS
Document Date Accession No.
------------------------------------------------------------------------
License Amendment Request......... July 31, 2012....... ML122270603
Response to First Request for March 14, 2013...... ML130860130
Additional Information.
Response to Second Request for May 23, 2013........ ML13175A184
Additional Information.
Supplement to License Amendment September 5, 2013... ML13259A274
Request.
License Amendment No. 3 Issuance February 11, 2014... ML14043A517
Package.
SER............................... February 11, 2014... ML14049A476
------------------------------------------------------------------------
Dated at Rockville, Maryland, this 19th day of February, 2014.
For the Nuclear Regulatory Commission.
Michele M. Sampson,
Chief, Licensing Branch, Division of Spent Fuel Storage and
Transportation, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2014-04597 Filed 2-28-14; 8:45 am]
BILLING CODE 7590-01-P