Burnup Credit in the Criticality Safety Analyses of Pressurized Water Reactor Spent Fuel in Transportation and Storage Casks, 60479-60480 [2012-24396]

Download as PDF Federal Register / Vol. 77, No. 192 / Wednesday, October 3, 2012 / Notices regulatory guide is available electronically under ADAMS Accession No. ML12024A004. The regulatory analysis may be found in ADAMS under Accession No. ML12024A014. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. • 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– 0231 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 in comment submissions that you do not want to be publicly disclosed. The NRC posts all comment submissions at http: //www.regulations.gov as well as enters the comment submissions into ADAMS. The NRC does not 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 in their comment submissions that they do not want to be publicly disclosed. Your request should state that the NRC will not edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment submissions into ADAMS. erowe on DSK2VPTVN1PROD with II. Further Information The NRC is issuing for public comment a draft guide in the NRC’s ‘‘Regulatory Guide’’ series. This series was developed to describe and make available to the public such information as methods that are acceptable to the NRC staff for implementing specific parts of the NRC’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. The draft regulatory guide, entitled, ‘‘Control of Ferrite Content in Stainless Steel Weld Metal,’’ is temporarily identified by its task number, DG–1279. The DG–1279 is proposed revision 4 of Regulatory Guide 1.31, dated April 1978. Revision 4 updates the guide to remove references to outdated standards and to remove an appendix that has VerDate Mar<15>2010 18:36 Oct 02, 2012 Jkt 229001 been incorporated into relevant specifications. This guide describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for controlling ferrite content in stainless steel weld metal. This guide is intended to supplement the ASME Code requirements to ensure control of delta ferrite in welds in austenitic stainless steel core support structures, reactor internals, and Class 1, 2, and 3 components. The NRC staff seeking input on the latest technical standards that should be in this guide. Dated at Rockville, Maryland, this 26th day of September, 2012. Dated at Rockville, Maryland, this 26th day of September, 2012. For the Nuclear Regulatory Commission. Thomas H. Boyce, Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2012–24390 Filed 10–2–12; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2012–0100] Burnup Credit in the Criticality Safety Analyses of Pressurized Water Reactor Spent Fuel in Transportation and Storage Casks Nuclear Regulatory Commission. ACTION: Interim staff guidance; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC or the Commission) is issuing a Spent Fuel Storage and Transportation Interim Staff Guidance (SFST–ISG)–8, Revision 3, entitled, ‘‘Burnup Credit in the Criticality Safety Analyses of PWR [Pressurized Water Reactor] Spent Fuel in Transportation and Storage Casks.’’ This SFST–ISG provides guidance for use by NRC staff when reviewing applications requesting burnup credit in the criticality safety analyses of pressurized water reactor spent nuclear fuel (SNF) in transportation packages and storage casks. SFST–ISG–8, Revision 3, includes two major changes in the staff recommendations: (1) optional credit for fission product and minor actinide neutron absorbing isotopes in the SNF composition, and (2) misload analyses and additional administrative procedures in lieu of a burnup measurement at the time of loading. ADDRESSES: Please refer to Docket ID NRC–2012–0100 when contacting the NRC about the availability of SUMMARY: PO 00000 Frm 00107 Fmt 4703 Sfmt 4703 60479 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–2012–0100. Address questions about NRC dockets to Carol Gallagher; telephone: 301–492–3668; email: Carol.Gallagher@nrc.gov. • NRC’s Interim Staff Guidance Web Site: The SFST–ISG documents are also available online under the ‘‘Spent Fuel Storage and Transportation’’ heading at https://www.nrc.gov/reading-rm/doccollections/#int. • 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 SFST–ISG–8, Revision 3, is available in ADAMS under Accession No. ML12261A433. • 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: Mr. Andrew Barto, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–492–3336; email: Andrew.Barto@ nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The NRC issues SFST–ISGs to communicate insights and lessons learned and to address emergent issues not covered in SFST Standard Review Plans. In this way, the NRC staff and stakeholders may use the guidance in an SFST–ISG document before it is incorporated into a formal SRP revision. The NRC staff has developed SFST– ISG–8, Revision 3 to (a) incorporate the results of burnup credit criticality safety research performed since the last SFST– ISG–8 revision in 2002 into the limits for the licensing basis, (b) provide recommendations regarding advanced isotopic depletion and criticality code validation techniques, (c) provide recommendations regarding credit for fission product neutron absorbing nuclides in the criticality analysis for E:\FR\FM\03OCN1.SGM 03OCN1 60480 Federal Register / Vol. 77, No. 192 / Wednesday, October 3, 2012 / Notices SNF systems, (d) add a recommendation for an optional misload analysis coupled with additional administrative SNF system loading procedures, in lieu of a direct burnup measurement, and (e) make miscellaneous and editorial changes. II. Further Information The draft SFST–ISG–8, Revision 3, was published in the Federal Register on May 2, 2012 (77 FR 26050) for a 30day public comment period. The public comment period closed on June 1, 2012. A table containing the comments received from external stakeholders and the staff responses to these comments is available in ADAMS under Accession No. ML12261A432. Dated at Rockville, Maryland, this 26th day of September, 2012. For the Nuclear Regulatory Commission. Mark Lombard, Director, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2012–24396 Filed 10–2–12; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Digital Instrumentation and Control Systems; Notice of Meeting erowe on DSK2VPTVN1PROD with The ACRS Subcommittee on Digital Instrumentation and Control Systems (DI&C) will hold a meeting on October 30, 2012, Room T–2B1, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public attendance. The agenda for the subject meeting shall be as follows: Tuesday, October 30, 2012–8:30 a.m. until 5 p.m. The Subcommittee will review and discuss the Design Specific Review Standard (DSRS) for Instrumentation and Control of the Babcock & Wilcox (B&W) mPower reactor. The Subcommittee will hear presentations by and hold discussions with the NRC staff and other interested persons regarding this matter. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the Full Committee. Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official (DFO), Christina VerDate Mar<15>2010 15:03 Oct 02, 2012 Jkt 229001 Antonescu (Telephone 301–415–6792 or Email: Christina.Antonescu@nrc.gov) five days prior to the meeting, if possible, so that appropriate arrangements can be made. Thirty-five hard copies of each presentation or handout should be provided to the DFO thirty minutes before the meeting. In addition, one electronic copy of each presentation should be emailed to the DFO one day before the meeting. If an electronic copy cannot be provided within this timeframe, presenters should provide the DFO with a CD containing each presentation at least thirty minutes before the meeting. Electronic recordings will be permitted only during those portions of the meeting that are open to the public. Detailed procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on October 17, 2011, (76 FR 64126– 64127). Detailed meeting agendas and meeting transcripts are available on the NRC Web site at https://www.nrc.gov/readingrm/doc-collections/acrs. Information regarding topics to be discussed, changes to the agenda, whether the meeting has been canceled or rescheduled, and the time allotted to present oral statements can be obtained from the Web site cited above or by contacting the identified DFO. Moreover, in view of the possibility that the schedule for ACRS meetings may be adjusted by the Chairman as necessary to facilitate the conduct of the meeting, persons planning to attend should check with these references if such rescheduling would result in a major inconvenience. If attending this meeting, please enter through the One White Flint North building, 11555 Rockville Pike, Rockville, MD. After registering with security, please contact Mr. Theron Brown (Telephone 240–888–9835) to be escorted to the meeting room. Dated: September 26, 2012. Antonio Dias, Technical Advisor, Advisory Committee on Reactor Safeguards. [FR Doc. 2012–24345 Filed 10–2–12; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the ACRS Subcommittee on Reliability and PRA; Notice of Meeting The ACRS Subcommittee on Reliability and PRA will hold a meeting on October 19, 2012, Room T–2B1, PO 00000 Frm 00108 Fmt 4703 Sfmt 4703 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public attendance. The agenda for the subject meeting shall be as follows: Friday, October 19, 2012–1 p.m. until 5 p.m. The Subcommittee will be briefed on the guidance on the treatment of uncertainties associated with Probabilistic Risk Assessments (PRAs) in risk-informed applications. The Subcommittee will hear presentations by and hold discussions with the NRC staff, Industry, and other interested persons regarding this matter. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the Full Committee. Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official (DFO), John Lai (Telephone 301–415–5197 or Email: John.Lai@nrc.gov) five days prior to the meeting, if possible, so that appropriate arrangements can be made. Thirty-five hard copies of each presentation or handout should be provided to the DFO thirty minutes before the meeting. In addition, one electronic copy of each presentation should be emailed to the DFO one day before the meeting. If an electronic copy cannot be provided within this timeframe, presenters should provide the DFO with a CD containing each presentation at least thirty minutes before the meeting. Electronic recordings will be permitted only during those portions of the meeting that are open to the public. Detailed procedures for the conduct of and participation in ACRS meetings were published in the Federal Register on October 17, 2011, (76 FR 64126– 64127). Detailed meeting agendas and meeting transcripts are available on the NRC Web site at https://www.nrc.gov/readingrm/doc-collections/acrs. Information regarding topics to be discussed, changes to the agenda, whether the meeting has been canceled or rescheduled, and the time allotted to present oral statements can be obtained from the Web site cited above or by contacting the identified DFO. Moreover, in view of the possibility that the schedule for ACRS meetings may be adjusted by the Chairman as necessary to facilitate the conduct of the meeting, persons planning to attend should check with these references if such rescheduling would result in a major inconvenience. E:\FR\FM\03OCN1.SGM 03OCN1

Agencies

[Federal Register Volume 77, Number 192 (Wednesday, October 3, 2012)]
[Notices]
[Pages 60479-60480]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-24396]


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NUCLEAR REGULATORY COMMISSION

[NRC-2012-0100]


Burnup Credit in the Criticality Safety Analyses of Pressurized 
Water Reactor Spent Fuel in Transportation and Storage Casks

AGENCY: Nuclear Regulatory Commission.

ACTION: Interim staff guidance; issuance.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC or the Commission) 
is issuing a Spent Fuel Storage and Transportation Interim Staff 
Guidance (SFST-ISG)-8, Revision 3, entitled, ``Burnup Credit in the 
Criticality Safety Analyses of PWR [Pressurized Water Reactor] Spent 
Fuel in Transportation and Storage Casks.'' This SFST-ISG provides 
guidance for use by NRC staff when reviewing applications requesting 
burnup credit in the criticality safety analyses of pressurized water 
reactor spent nuclear fuel (SNF) in transportation packages and storage 
casks. SFST-ISG-8, Revision 3, includes two major changes in the staff 
recommendations: (1) optional credit for fission product and minor 
actinide neutron absorbing isotopes in the SNF composition, and (2) 
misload analyses and additional administrative procedures in lieu of a 
burnup measurement at the time of loading.

ADDRESSES: Please refer to Docket ID NRC-2012-0100 when contacting the 
NRC about the availability of 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-2012-0100. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: Carol.Gallagher@nrc.gov.
     NRC's Interim Staff Guidance Web Site: The SFST-ISG 
documents are also available online under the ``Spent Fuel Storage and 
Transportation'' heading at https://www.nrc.gov/reading-rm/doc-collections/#int.
     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. The SFST-ISG-8, Revision 3, 
is available in ADAMS under Accession No. ML12261A433.
     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: Mr. Andrew Barto, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001; telephone: 301-492-3336; email: 
Andrew.Barto@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Introduction

    The NRC issues SFST-ISGs to communicate insights and lessons 
learned and to address emergent issues not covered in SFST Standard 
Review Plans. In this way, the NRC staff and stakeholders may use the 
guidance in an SFST-ISG document before it is incorporated into a 
formal SRP revision.
    The NRC staff has developed SFST-ISG-8, Revision 3 to (a) 
incorporate the results of burnup credit criticality safety research 
performed since the last SFST-ISG-8 revision in 2002 into the limits 
for the licensing basis, (b) provide recommendations regarding advanced 
isotopic depletion and criticality code validation techniques, (c) 
provide recommendations regarding credit for fission product neutron 
absorbing nuclides in the criticality analysis for

[[Page 60480]]

SNF systems, (d) add a recommendation for an optional misload analysis 
coupled with additional administrative SNF system loading procedures, 
in lieu of a direct burnup measurement, and (e) make miscellaneous and 
editorial changes.

II. Further Information

    The draft SFST-ISG-8, Revision 3, was published in the Federal 
Register on May 2, 2012 (77 FR 26050) for a 30-day public comment 
period. The public comment period closed on June 1, 2012. A table 
containing the comments received from external stakeholders and the 
staff responses to these comments is available in ADAMS under Accession 
No. ML12261A432.

    Dated at Rockville, Maryland, this 26th day of September, 2012.

    For the Nuclear Regulatory Commission.
Mark Lombard,
Director, Division of Spent Fuel Storage and Transportation, Office of 
Nuclear Material Safety and Safeguards.
[FR Doc. 2012-24396 Filed 10-2-12; 8:45 am]
BILLING CODE 7590-01-P
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