Pacific Gas and Electric Company; Diablo Canyon Independent Spent Fuel Storage Installation, 11833-11834 [2014-04597]

Download as PDF Federal Register / Vol. 79, No. 41 / Monday, March 3, 2014 / Notices mstockstill on DSK4VPTVN1PROD with NOTICES 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: http://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 http://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 http://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 E:\FR\FM\03MRN1.SGM 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: http:// 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—http://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 Fmt 4703 Sfmt 4703 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—http://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—http://www.nrc.gov/. E:\FR\FM\03MRN1.SGM 03MRN1

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 http://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 http://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: http://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