Final Interim Staff Guidance DI&C-ISG-03: Probabilistic Risk Assessment Information To Support Design Certification and Combined License Applications, 22522 [2019-10314]

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3 to Section 19.0 of NUREG–0800, the staff has determined that DI&C–ISG–03 is no longer necessary and should be withdrawn.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

Agencies

[Federal Register Volume 84, Number 96 (Friday, May 17, 2019)]
[Notices]
[Page 22522]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-10314]


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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

AGENCY: Nuclear Regulatory Commission.

ACTION: Interim staff guidance; withdrawal.

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

SUMMARY: 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. 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: [email protected]. 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 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 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.

    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
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