Final Interim Staff Guidance DC/COL-ISG-10: Review of Evaluation To Address Adverse Flow Effects in Equipment Other Than Reactor Internals, 22522-22523 [2019-10316]

Download as PDF 22522 Federal Register / Vol. 84, No. 96 / Friday, May 17, 2019 / Notices Government Shutdown Lessons Learned; Subcommittee on Cost Surveillance Policy and Procedures; Committee Business/Wrap Up/Virtual Hot Wash. Dated: May 13, 2019. Crystal Robinson, Committee Management Officer. [FR Doc. 2019–10222 Filed 5–16–19; 8:45 am] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION [NRC–2008–0089] Final Interim Staff Guidance DI&C– ISG–03: Probabilistic Risk Assessment Information To Support Design Certification and Combined License Applications Nuclear Regulatory Commission. ACTION: Interim staff guidance; withdrawal. AGENCY: The Nuclear Regulatory Commission (NRC) is withdrawing its Final Interim Staff Guidance (ISG) DI&C–ISG–03, ‘‘Interim Staff Guidance on Review of New Reactor Digital Instrumentation and Control Probabilistic Risk Assessment.’’ This ISG served to supplement the guidance provided to the staff in Section 19.0, ‘‘Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors,’’ of NUREG–0800, ‘‘Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,’’ concerning the probabilistic risk assessment associated with review of new reactor digital instrumentation and control to support the review of design certification and combined license (COL) applications. The NRC staff issues ISG to facilitate timely implementation of the current staff guidance and to facilitate activities associated with review of applications for DC and COLs by the Office of New Reactors. The NRC staff incorporated the approved DI&C–ISG–03 into Revision 3 to Section 19.0 of NUREG– 0800 dated January 2016. With the issuance of Revision 3 to Section 19.0 of NUREG–0800, the staff has determined that DI&C–ISG–03 is no longer necessary and should be withdrawn. DATES: The date of the withdrawal of Final Interim Staff Guidance DI&C–ISG– 03 is May 17, 2019. ADDRESSES: Please refer to Docket ID NRC–2008–0089 when contacting the NRC about the availability of information regarding this document. jbell on DSK3GLQ082PROD with NOTICES SUMMARY: VerDate Sep<11>2014 17:05 May 16, 2019 Jkt 247001 You may obtain publicly-available information related to this document using any of the following methods: • Federal Rulemaking website: Go to https://www.regulations.gov and search for Docket ID NRC–2008–0089. Address questions about Docket IDs in Regulations.gov to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Bogres@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 ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/ adams.html. To begin the search, 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. Mr. George Wunder, Office of the New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC, 20555– 0001; telephone 301–415–1494 or email at George.Wunder@nrc.gov. FOR FURTHER INFORMATION CONTACT: On August 11, 2008, the staff issued its Final Interim Staff Guidance, DI&C–ISG–03, ‘‘Interim Staff Guidance on Review of New Reactor Digital Instrumentation and Control Probabilistic Risk Assessment’’ (ADAMS Accession No. ML080570048). This document is being withdrawn because on January 21, 2016, the staff issued Revision 3 to Section 19.0 of NUREG–0800 (ADAMS Accession No. ML15085A093), incorporating the guidance of DI&C ISG–03 and, therefore, superseding it. Therefore, as of the date of this notice, DI&C–ISG–03 is withdrawn. SUPPLEMENTARY INFORMATION: Dated at Rockville, Maryland, this 14th day of May 2019. For the Nuclear Regulatory Commission, Jennivine K. Rankin, Acting Chief, Licensing Branch 3, Division of Licensing, Siting, and Environmental Analysis, Office of New Reactors. [FR Doc. 2019–10314 Filed 5–16–19; 8:45 am] BILLING CODE 7590–01–P PO 00000 Frm 00093 Fmt 4703 Sfmt 4703 NUCLEAR REGULATORY COMMISSION [NRC–2009–0110] Final Interim Staff Guidance DC/COL– ISG–10: Review of Evaluation To Address Adverse Flow Effects in Equipment Other Than Reactor Internals Nuclear Regulatory Commission. ACTION: Interim staff guidance; withdrawal. AGENCY: The Nuclear Regulatory Commission (NRC) is withdrawing its Final Interim Staff Guidance (ISG) DC/ COL–ISG–10, ‘‘Review of Evaluation to Address Adverse Flow Effects in Equipment Other than Reactor Internals.’’ This ISG served to supplement the guidance provided to the staff in Sections 3.9.2, ‘‘Dynamic Testing and Analysis of Systems, Structures, and Components,’’ and 3.9.5, ‘‘Reactor Pressure Vessel Internals,’’ of NUREG–0800, ‘‘Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,’’ concerning the review of probabilistic risk assessment information and severe accident assessment submitted to support design certification (DC) and combined license (COL) applications. The NRC staff issues ISG to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DC and COLs by the Office of New Reactors. The NRC staff incorporated the approved DC/COL–ISG into Revision 4 to Sections 3.9.2 and 3.9.5 of NUREG–0800 dated March 2017. With the issuance of Revision 4 to Sections 3.9.2 and 3.9.5 of NUREG– 0800, the staff has determined that DC/ COL–ISG–10 is no longer necessary and should be withdrawn. DATES: The date of the withdrawal of Final Interim Staff Guidance DC/COL– ISG–10 is May 17, 2019. ADDRESSES: Please refer to Docket ID NRC–2009–0110 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 Website: Go to https://www.regulations.gov and search for Docket ID NRC–2009–0110. Address questions about Docket IDs in Regulations.gov to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individuals listed in the FOR FURTHER INFORMATION CONTACT section of this document. SUMMARY: E:\FR\FM\17MYN1.SGM 17MYN1 Federal Register / Vol. 84, No. 96 / Friday, May 17, 2019 / Notices • 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 ‘‘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 FURTHER INFORMATION CONTACT: Mr. George Wunder, Office of the New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone 301–415–1494 or email at George.Wunder@nrc.gov. SUPPLEMENTARY INFORMATION: On November 3, 2009, as noticed in the Federal Register (74 FR 58323), the staff issued its Final Interim Staff Guidance, DC/COL–ISG–10, ‘‘Review of Evaluation to Address Adverse Flow Effects in Equipment Other than Reactor Internals’’ (ADAMS Accession No. ML092890285). This document is being withdrawn because on March 6, 2017, the staff issued Revision 4 to Sections 3.9.2 and 3.9.5 of NUREG–0800 (ADAMS Accession No. ML16133A418), incorporating the guidance of DC/COL– ISG–10 and, therefore, superseding it. Therefore, as of the date of this notice, DC/COL–ISG–10 is withdrawn. Dated at Rockville, Maryland, this 14th day of May 2019. For the Nuclear Regulatory Commission. Jennivine K. Rankin, Acting Chief, Licensing Branch 3, Division of Licensing, Siting, and Environmental Analysis, Office of New Reactors. [FR Doc. 2019–10316 Filed 5–16–19; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2008–0089] Final Interim Staff Guidance DC/COL– ISG–03: Probabilistic Risk Assessment Information To Support Design Certification and Combined License Applications Nuclear Regulatory Commission. ACTION: Interim staff guidance; withdrawal. jbell on DSK3GLQ082PROD with NOTICES AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is withdrawing its Final Interim Staff Guidance (ISG) DC/ COL–ISG–03, ‘‘Probabilistic Risk Assessment Information to Support Design Certification and Combined SUMMARY: VerDate Sep<11>2014 17:05 May 16, 2019 Jkt 247001 License Applications.’’ This ISG served to supplement the guidance provided to the staff in Section 19.0, ‘‘Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors,’’ of NUREG–0800, ‘‘Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,’’ concerning the review of probabilistic risk assessment information and severe accident assessment submitted to support design certification (DC) and combined license (COL) applications. The NRC staff issues ISG to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DC and COLs by the Office of New Reactors. The NRC staff incorporated the approved DC/COL–ISG into Revision 3 to Section 19.0 of NUREG–0800 dated December 2015. With the issuance of Revision 3 to Section 19.0 of NUREG–0800, the staff has determined that DC/COL–ISG–03 is no longer necessary and should be withdrawn. DATES: The date of the withdrawal of Final Interim Staff Guidance DC/COL– ISG–03 is May 17, 2019. ADDRESSES: Please refer to Docket ID: NRC–2008–0089 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 Website: Go to https://www.regulations.gov and search for Docket ID NRC–2008–0089. Address questions about Docket IDs in Regulations.gov to Jennifer Borges; telephone: 301–287–9221; email: Jennifer.Borges@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 ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/ adams.html. To begin the search, 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 FURTHER INFORMATION CONTACT: Mr. George Wunder, Office of the New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC, 20555– 0001; telephone 301–415–1494 or email at George.Wunder@nrc.gov. SUPPLEMENTARY INFORMATION: On June 11, 2008, as noticed in the Federal PO 00000 Frm 00094 Fmt 4703 Sfmt 4703 22523 Register (73 FR 34347), the staff issued Final Interim Staff Guidance (ISG) DC/ COL–ISG–03, ‘‘Probabilistic Risk Assessment Information to Support Design Certification and Combined License Applications’’ (ADAMS Accession No. ML081430047). This document is being withdrawn because on January 21, 2016, the staff issued Revision 3 to Section 19.0 of NUREG– 0800 incorporating the guidance of DC/ COL–ISG–03 (ADAMS Accession No. ML15085A093) and, therefore, superseding it. Therefore, as of the date of this notice, DC/COL–ISG–03 is withdrawn. Dated at Rockville, Maryland, this 14th day of May 2019. For the Nuclear Regulatory Commission. Jennivine K. Rankin, Acting Branch Chief, Licensing Branch 3, Division of Licensing, Siting, and Environmental Analysis, Office of New Reactors. [FR Doc. 2019–10319 Filed 5–16–19; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 52–047; NRC–2016–0119] Tennessee Valley Authority; Clinch River Nuclear Site Nuclear Regulatory Commission. ACTION: Early site permit application; receipt. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is giving notice once each week for four consecutive weeks for an application from Tennessee Valley Authority (TVA), for an early site permit (ESP) for the Clinch River Nuclear Site located in Oak Ridge, Tennessee. SUMMARY: The ESP application was received on May 12, 2016 and supplemented with Revision 2 on January 18, 2019. ADDRESSES: Please refer to Docket ID NRC–2016–0119 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 website: Go to https://www.regulations.gov and search for Docket ID NRC–2016–0119. Address questions about NRC docket IDs in Regulations.gov to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individuals listed DATES: E:\FR\FM\17MYN1.SGM 17MYN1

Agencies

[Federal Register Volume 84, Number 96 (Friday, May 17, 2019)]
[Notices]
[Pages 22522-22523]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-10316]


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

NUCLEAR REGULATORY COMMISSION

[NRC-2009-0110]


Final Interim Staff Guidance DC/COL-ISG-10: Review of Evaluation 
To Address Adverse Flow Effects in Equipment Other Than Reactor 
Internals

AGENCY: Nuclear Regulatory Commission.

ACTION: Interim staff guidance; withdrawal.

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

SUMMARY: The Nuclear Regulatory Commission (NRC) is withdrawing its 
Final Interim Staff Guidance (ISG) DC/COL-ISG-10, ``Review of 
Evaluation to Address Adverse Flow Effects in Equipment Other than 
Reactor Internals.'' This ISG served to supplement the guidance 
provided to the staff in Sections 3.9.2, ``Dynamic Testing and Analysis 
of Systems, Structures, and Components,'' and 3.9.5, ``Reactor Pressure 
Vessel Internals,'' of NUREG-0800, ``Standard Review Plan for the 
Review of Safety Analysis Reports for Nuclear Power Plants: LWR 
Edition,'' concerning the review of probabilistic risk assessment 
information and severe accident assessment submitted to support design 
certification (DC) and combined license (COL) applications. The NRC 
staff issues ISG to facilitate timely implementation of current staff 
guidance and to facilitate activities associated with review of 
applications for DC and COLs by the Office of New Reactors. The NRC 
staff incorporated the approved DC/COL-ISG into Revision 4 to Sections 
3.9.2 and 3.9.5 of NUREG-0800 dated March 2017. With the issuance of 
Revision 4 to Sections 3.9.2 and 3.9.5 of NUREG-0800, the staff has 
determined that DC/COL-ISG-10 is no longer necessary and should be 
withdrawn.

DATES: The date of the withdrawal of Final Interim Staff Guidance DC/
COL-ISG-10 is May 17, 2019.

ADDRESSES: Please refer to Docket ID NRC-2009-0110 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 Website: Go to https://www.regulations.gov and search for Docket ID NRC-2009-0110. Address 
questions about Docket IDs in Regulations.gov to Jennifer Borges; 
telephone: 301-287-9127; email: [email protected]. For technical 
questions, contact the individuals listed in the FOR FURTHER 
INFORMATION CONTACT section of this document.

[[Page 22523]]

     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 ``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 [email protected].

FOR FURTHER INFORMATION CONTACT: Mr. George Wunder, Office of the New 
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone 301-415-1494 or email at [email protected].

SUPPLEMENTARY INFORMATION: On November 3, 2009, as noticed in the 
Federal Register (74 FR 58323), the staff issued its Final Interim 
Staff Guidance, DC/COL-ISG-10, ``Review of Evaluation to Address 
Adverse Flow Effects in Equipment Other than Reactor Internals'' (ADAMS 
Accession No. ML092890285). This document is being withdrawn because on 
March 6, 2017, the staff issued Revision 4 to Sections 3.9.2 and 3.9.5 
of NUREG-0800 (ADAMS Accession No. ML16133A418), incorporating the 
guidance of DC/COL-ISG-10 and, therefore, superseding it. Therefore, as 
of the date of this notice, DC/COL-ISG-10 is withdrawn.

    Dated at Rockville, Maryland, this 14th day of May 2019.

    For the Nuclear Regulatory Commission.
Jennivine K. Rankin,
Acting Chief, Licensing Branch 3, Division of Licensing, Siting, and 
Environmental Analysis, Office of New Reactors.
[FR Doc. 2019-10316 Filed 5-16-19; 8:45 am]
BILLING CODE 7590-01-P
This site is protected by reCAPTCHA and the Google Privacy Policy and Terms of Service apply.