Proposed Model Safety Evaluation for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-535, Revision 0, “Revise Shutdown Margin Definition To Address Advanced Fuel Designs”, 69507-69508 [2012-28078]

Download as PDF Federal Register / Vol. 77, No. 223 / Monday, November 19, 2012 / Notices south end basement area and the hydrogen seal oil unit’’ to ‘‘The closed head automatic sprinkler system in the condenser bay area was designed, installed and tested in accordance with NFPA 13, 1976 Edition, which was the latest edition of this code at the time of design.’’ Dated in Rockville, Maryland, this 9th day of November 2012. For the Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2012–28074 Filed 11–16–12; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Project No. 753; NRC–2012–0280] Proposed Model Safety Evaluation for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF–535, Revision 0, ‘‘Revise Shutdown Margin Definition To Address Advanced Fuel Designs’’ Nuclear Regulatory Commission. ACTION: Notice of opportunity for public comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is requesting public comment on the proposed model safety evaluation (SE) for plant-specific adoption of Technical Specifications (TS) Task Force (TSTF) Traveler TSTF– 535, Revision 0, ‘‘Revise Shutdown Margin Definition to Address Advanced Fuel Designs.’’ DATES: Comment period expires on December 19, 2012. Comments received after this date will be considered, if it is practical to do so, but the Commission is able to ensure consideration only for comments received on or before this date. ADDRESSES: You may access information and comment submissions related to this document, which the NRC possesses and are publically available, by searching on https:// www.regulations.gov under Docket ID NRC–2012–0280. You may submit comments by any of the following methods: • Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2012–0280. Address questions about NRC dockets to Carol Gallagher; telephone: 301–492–3668; email: Carol.Gallagher@nrc.gov. • Mail comments to: Cindy Bladey, Chief, Rules, Announcements, and pmangrum on DSK3VPTVN1PROD with NOTICES SUMMARY: VerDate Mar<15>2010 14:04 Nov 16, 2012 Jkt 229001 Directives Branch (RADB), Office of Administration, Mail Stop: TWB–05– B01M, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. • Fax comments to: RADB at 301– 492–3446. For additional direction on accessing information and submitting comments, see ‘‘Accessing Information and Submitting Comments’’ in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: Ms. Michelle C. Honcharik, Senior Project Manager, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC, 20555– 0001; telephone 301–415–1774 or email at Michelle.Honcharik@nrc.gov. For technical questions please contact Mr. Ravinder Grover, Reactor Systems Engineer, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone 301–415–2166 or email at Ravinder.Grover@nrc.gov. SUPPLEMENTARY INFORMATION: Accessing Information and Submitting Comments A. Accessing Information Please refer to Docket ID NRC–2012– 0280 when contacting the NRC about the availability of information regarding this document. You may access information related to this document by the following methods: • Federal Rulemaking Web Site: Go to https://www.regulations.gov and search for Docket ID NRC–2012–0280. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may access publiclyavailable documents online in the NRC Library at https://www.nrc.gov/readingrm/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. TSTF– 535, Revision 0, includes a model application and is available under ADAMS Accession Number ML112200436. The proposed model SE for plant-specific adoption of TSTF– 535, Revision 0, is also available under ADAMS Accession Number ML12219A145. • 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. PO 00000 Frm 00074 Fmt 4703 Sfmt 4703 69507 B. Submitting Comments Please include Docket ID NRC–2012– 0280 in the subject line of your comment submission, in order to ensure that the NRC is able to make your comment submission available to the public in this docket. The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at https:// www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment submissions into ADAMS. Background TSTF–535, Revision 0, is applicable to all boiling water reactor (BWR) power plants. The proposed change revises the Standard Technical Specification (STS), NUREG–1433, ‘‘Standard Technical Specifications General Electric Plants BWR/4,’’ and NUREG–1434, ‘‘Standard Technical Specifications General Electric Plants, BWR/6.’’ Specifically, the proposed change revises the STS definition of shutdown margin (SDM) to require calculation of SDM at the reactor moderator temperature corresponding to the most reactive state throughout the operating cycle (68 °F or higher). The purpose is to address newer BWR fuel designs, which may be more reactive at shutdown temperatures above 68 °F. This STS improvement is part of the consolidated line item improvement process (CLIIP). Additional Details This notice provides an opportunity for the public to comment on proposed changes to the STS after a preliminary assessment and finding by the NRC staff that the agency will likely offer the changes for adoption by licensees. This notice solicits comment on proposed changes to the STS, which if implemented by a licensee will modify the plant-specific TS. The NRC staff will evaluate any comments received for the E:\FR\FM\19NON1.SGM 19NON1 69508 Federal Register / Vol. 77, No. 223 / Monday, November 19, 2012 / Notices proposed changes and reconsider the changes or announce the availability of the changes for adoption by licensees as part of the CLIIP. Licensees opting to apply for this TS change are responsible for reviewing the NRC staff’s SE, and the applicable technical justifications, providing any necessary plant-specific information, and assessing the completeness and accuracy of their license amendment request (LAR). The NRC will process each amendment application responding to the notice of availability according to applicable NRC rules and procedures. The proposed change does not prevent licensees from requesting an alternate approach or proposing changes other than those proposed in TSTF–535, Revision 0. However, significant deviations from the approach recommended in this notice or the inclusion of additional changes to the license require additional NRC staff review. This may increase the time and resources needed for the review or result in NRC staff rejection of the LAR. Licensees desiring significant deviations or additional changes should instead submit an LAR that does not claim to adopt TSTF–535, Revision 0. Dated at Rockville, Maryland, this 2nd day of November 2012. For the Nuclear Regulatory Commission. Sheldon D. Stuchell, Acting Chief, Licensing Processes Branch, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation. [FR Doc. 2012–28078 Filed 11–16–12; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2011–0096] Inservice Inspection of Prestressed Concrete Containment Structures With Grouted Tendons information regarding this document. You may access information related to this document, which the NRC possesses and are publicly-available, using any of the following methods: • Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2011–0096. Address questions about NRC dockets to Carol Gallagher; telephone: 301–492–3668; email: Carol.Gallagher@nrc.gov. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC Library at https://www.nrc.gov/readingrm/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 in this notice (if that document is available in ADAMS) is provided the first time that a document is referenced. Revision 2 of Regulatory Guide 1.90 is available in ADAMS under Accession No. ML11249A008. The regulatory analysis may be found in ADAMS under Accession No. ML11249A009. • 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. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. FOR FURTHER INFORMATION CONTACT: Mekonen Bayssie, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–251– 7489; email: Mekonen.Bayssie@nrc.gov. SUPPLEMENTARY INFORMATION: AGENCY: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision to Regulatory Guide (RG) 1.90, ‘‘Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons.’’ This guide describes a method that the NRC staff considers acceptable for use in developing an appropriate surveillance program for prestressed concrete containment structures with grouted tendons. ADDRESSES: Please refer to Docket ID NRC–2011–0096 when contacting the NRC about the availability of The NRC is issuing a revision to an existing guide in the NRC’s ‘‘Regulatory Guide’’ series. This series was developed to describe and make available to the public information such as methods that are acceptable to the NRC staff for implementing specific parts of the agency’s regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in its review of applications for permits and licenses. Revision 2 of RG 1.90 was issued with a temporary identification as Draft Regulatory Guide, DG–1197. The recommendations described in this Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance. pmangrum on DSK3VPTVN1PROD with NOTICES SUMMARY: VerDate Mar<15>2010 14:04 Nov 16, 2012 Jkt 229001 PO 00000 Frm 00075 Fmt 4703 Sfmt 4703 guide constitute an approach that the NRC staff finds acceptable for satisfying the requirements of General Design Criterion (GDC) 53, ‘‘Provisions for Containment Testing and Inspection,’’ of Appendix A, ‘‘General Design Criteria for Nuclear Power Plants,’’ part 50 of Title 10 of the Code of Federal Regulations (10 CFR), ‘‘Domestic Licensing of Production and Utilization Facilities,’’ and 10 CFR 50.55a’’ Codes and Standards’’ Paragraph (g)(4) ‘‘Inservice Inspection Requirements.’’ The previous Revision 1 of this RG was published in 1977. Since this publication, the industry and the NRC have been involved in research and testing to determine and evaluate the effectiveness of containment inservice inspection (ISI) programs, particularly the reliability of installed instrumentation and the use of periodic pressure tests. In addition, the NRC has reviewed containment tendon ISI programs as part of license applications. Revision 2 of RG 1.90 is a result of these efforts. It provides an ISI program that is based on a real-time, multiple-strategy approach (i.e., appropriate grout design and installation, installed instrumentation, periodic pressure tests, and visual examination). II. Further Information DG–1197 was published in the Federal Register on April 28, 2011 (76 FR 23845) for a 60-day public comment period. The public comment period closed on June 26, 2011. Public comments on DG–1197 and the NRC staff responses to the public comments are available under ADAMS Accession No. ML11249A010. III. Backfitting and Issue Finality Issuance of this final regulatory guide does not constitute backfitting as defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise inconsistent with the issue finality provisions in 10 CFR part 52. As discussed in the ‘‘Implementation’’ section of this regulatory guide, the NRC has no current intention to impose this regulatory guide on holders of current operating licenses or combined licenses. This regulatory guide may be applied to applications for operating licenses and combined licenses docketed by the NRC as of the date of issuance of the final regulatory guide, as well as future applications for operating licenses and combined licenses submitted after the issuance of the regulatory guide. Such action does not constitute backfitting as defined in 10 CRF 50.109(a)(1) or is otherwise inconsistent with the applicable issue finality provision in 10 CFR Part 52, inasmuch as such E:\FR\FM\19NON1.SGM 19NON1

Agencies

[Federal Register Volume 77, Number 223 (Monday, November 19, 2012)]
[Notices]
[Pages 69507-69508]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-28078]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[Project No. 753; NRC-2012-0280]


Proposed Model Safety Evaluation for Plant-Specific Adoption of 
Technical Specifications Task Force Traveler TSTF-535, Revision 0, 
``Revise Shutdown Margin Definition To Address Advanced Fuel Designs''

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of opportunity for public comment.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is requesting 
public comment on the proposed model safety evaluation (SE) for plant-
specific adoption of Technical Specifications (TS) Task Force (TSTF) 
Traveler TSTF-535, Revision 0, ``Revise Shutdown Margin Definition to 
Address Advanced Fuel Designs.''

DATES: Comment period expires on December 19, 2012. Comments received 
after this date will be considered, if it is practical to do so, but 
the Commission is able to ensure consideration only for comments 
received on or before this date.

ADDRESSES: You may access information and comment submissions related 
to this document, which the NRC possesses and are publically available, 
by searching on https://www.regulations.gov under Docket ID NRC-2012-
0280. You may submit comments by any of the following methods:
     Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0280. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: Carol.Gallagher@nrc.gov.
     Mail comments to: Cindy Bladey, Chief, Rules, 
Announcements, and Directives Branch (RADB), Office of Administration, 
Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
     Fax comments to: RADB at 301-492-3446.
    For additional direction on accessing information and submitting 
comments, see ``Accessing Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Ms. Michelle C. Honcharik, Senior 
Project Manager, Office of Nuclear Reactor Regulation, U.S. Nuclear 
Regulatory Commission, Washington, DC, 20555-0001; telephone 301-415-
1774 or email at Michelle.Honcharik@nrc.gov. For technical questions 
please contact Mr. Ravinder Grover, Reactor Systems Engineer, Office of 
Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001; telephone 301-415-2166 or email at 
Ravinder.Grover@nrc.gov.

SUPPLEMENTARY INFORMATION:

Accessing Information and Submitting Comments

A. Accessing Information

    Please refer to Docket ID NRC-2012-0280 when contacting the NRC 
about the availability of information regarding this document. You may 
access information related to this document by the following methods:
     Federal Rulemaking Web Site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0280.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may access publicly-available documents online in the NRC 
Library 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. TSTF-535, Revision 0, 
includes a model application and is available under ADAMS Accession 
Number ML112200436. The proposed model SE for plant-specific adoption 
of TSTF-535, Revision 0, is also available under ADAMS Accession Number 
ML12219A145.
     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.

B. Submitting Comments

    Please include Docket ID NRC-2012-0280 in the subject line of your 
comment submission, in order to ensure that the NRC is able to make 
your comment submission available to the public in this docket.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at https://www.regulations.gov as well as enter the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment submissions into ADAMS.

Background

    TSTF-535, Revision 0, is applicable to all boiling water reactor 
(BWR) power plants. The proposed change revises the Standard Technical 
Specification (STS), NUREG-1433, ``Standard Technical Specifications 
General Electric Plants BWR/4,'' and NUREG-1434, ``Standard Technical 
Specifications General Electric Plants, BWR/6.'' Specifically, the 
proposed change revises the STS definition of shutdown margin (SDM) to 
require calculation of SDM at the reactor moderator temperature 
corresponding to the most reactive state throughout the operating cycle 
(68[emsp14][deg]F or higher). The purpose is to address newer BWR fuel 
designs, which may be more reactive at shutdown temperatures above 
68[emsp14][deg]F. This STS improvement is part of the consolidated line 
item improvement process (CLIIP).

Additional Details

    This notice provides an opportunity for the public to comment on 
proposed changes to the STS after a preliminary assessment and finding 
by the NRC staff that the agency will likely offer the changes for 
adoption by licensees. This notice solicits comment on proposed changes 
to the STS, which if implemented by a licensee will modify the plant-
specific TS. The NRC staff will evaluate any comments received for the

[[Page 69508]]

proposed changes and reconsider the changes or announce the 
availability of the changes for adoption by licensees as part of the 
CLIIP. Licensees opting to apply for this TS change are responsible for 
reviewing the NRC staff's SE, and the applicable technical 
justifications, providing any necessary plant-specific information, and 
assessing the completeness and accuracy of their license amendment 
request (LAR). The NRC will process each amendment application 
responding to the notice of availability according to applicable NRC 
rules and procedures.
    The proposed change does not prevent licensees from requesting an 
alternate approach or proposing changes other than those proposed in 
TSTF-535, Revision 0. However, significant deviations from the approach 
recommended in this notice or the inclusion of additional changes to 
the license require additional NRC staff review. This may increase the 
time and resources needed for the review or result in NRC staff 
rejection of the LAR. Licensees desiring significant deviations or 
additional changes should instead submit an LAR that does not claim to 
adopt TSTF-535, Revision 0.

    Dated at Rockville, Maryland, this 2nd day of November 2012.

    For the Nuclear Regulatory Commission.

Sheldon D. Stuchell,
Acting Chief, Licensing Processes Branch, Division of Policy and 
Rulemaking, Office of Nuclear Reactor Regulation.
[FR Doc. 2012-28078 Filed 11-16-12; 8:45 am]
BILLING CODE 7590-01-P
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