ML18164A110: Difference between revisions
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{{#Wiki_filter:/RA - A. Bradford for/}} | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 4, 2019 MEMORANDUM TO: Andrea Veil, Executive Director Advisory Committee on Reactor Safeguards FROM: Robert M. Taylor, Director /RA - A. Bradford for/ | ||
Division of Licensing, Siting, and Environmental Analysis Office of New Reactors | |||
==SUBJECT:== | |||
ADVANCED BOILING-WATER REACTOR DESIGN CERTIFICATION RENEWAL APPLICATION SAFETY EVALUATION WITH NO OPEN ITEMS FOR SUBSECTION 6.2.1.3, SHORT-TERM PRESSURE | |||
===RESPONSE=== | |||
By letter dated December 7, 2010, GE-Hitachi Nuclear Energy (GEH) submitted an application to the U.S. Nuclear Regulatory Commission (NRC) requesting renewal of the Advanced Boiling-Water Reactor (ABWR) design certification (DC). | |||
Based on our review of the application, the staff is providing the Advisory Committee on Reactor Safeguards (ACRS) its safety evaluation (SE) with no open items associated with Subsection 6.2.1.3, Short-Term Pressure Response, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18052A925). This SE supplements the final safety evaluation report for the ABWR DC that was documented in NUREG-1503, Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design, and NUREG-1503, Supplement 1. Unless otherwise stated in the SE, the staffs review was based on Revision 6 of the ABWR design control document. The SE is being provided to support a future meeting of the subcommittee of the ACRS. The ACRS full committee meeting will be held after the subcommittee meeting. | |||
CONTACT: Adrian Muniz, DSLE/LB3 301-415-4093 | |||
A. Veil The staff concludes that the SE does not contain any information exempt from public disclosure. | |||
However, the NRC will withhold the SE from public disclosure for 10 business days to allow GEH the opportunity to verify the staffs conclusion that the SE contains no such exempt information. Therefore, the staff requests that the ACRS withhold the SE from public disclosure until the information has been released publicly in ADAMS. | |||
The staff will inform the ACRS immediately if GEH requests that any of the information in the SE be withheld from public disclosure. | |||
Docket No.: 52-045 | |||
ML18052A922 - Package ML18164A110 - Memo ML18052A925 - Safety Evaluation NRO-002 OFFICE DLSE:LB3:PM DLSE:LB3:LA DLSE:LB3:BC(A) DLSE: D NAME AMuniz SGreen JRankin RTaylor (ABradford for) | |||
DATE 6/13/2018 6/13/2018 2/4/2019 2/4/2019}} |
Latest revision as of 23:25, 20 October 2019
ML18164A110 | |
Person / Time | |
---|---|
Site: | 05200045 |
Issue date: | 02/04/2019 |
From: | Renee Taylor NRC/NRO/DNRL |
To: | Andrea Veil Advisory Committee on Reactor Safeguards |
Muniz A | |
Shared Package | |
ML18052A922 | List: |
References | |
Download: ML18164A110 (2) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 4, 2019 MEMORANDUM TO: Andrea Veil, Executive Director Advisory Committee on Reactor Safeguards FROM: Robert M. Taylor, Director /RA - A. Bradford for/
Division of Licensing, Siting, and Environmental Analysis Office of New Reactors
SUBJECT:
ADVANCED BOILING-WATER REACTOR DESIGN CERTIFICATION RENEWAL APPLICATION SAFETY EVALUATION WITH NO OPEN ITEMS FOR SUBSECTION 6.2.1.3, SHORT-TERM PRESSURE
RESPONSE
By letter dated December 7, 2010, GE-Hitachi Nuclear Energy (GEH) submitted an application to the U.S. Nuclear Regulatory Commission (NRC) requesting renewal of the Advanced Boiling-Water Reactor (ABWR) design certification (DC).
Based on our review of the application, the staff is providing the Advisory Committee on Reactor Safeguards (ACRS) its safety evaluation (SE) with no open items associated with Subsection 6.2.1.3, Short-Term Pressure Response, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18052A925). This SE supplements the final safety evaluation report for the ABWR DC that was documented in NUREG-1503, Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design, and NUREG-1503, Supplement 1. Unless otherwise stated in the SE, the staffs review was based on Revision 6 of the ABWR design control document. The SE is being provided to support a future meeting of the subcommittee of the ACRS. The ACRS full committee meeting will be held after the subcommittee meeting.
CONTACT: Adrian Muniz, DSLE/LB3 301-415-4093
A. Veil The staff concludes that the SE does not contain any information exempt from public disclosure.
However, the NRC will withhold the SE from public disclosure for 10 business days to allow GEH the opportunity to verify the staffs conclusion that the SE contains no such exempt information. Therefore, the staff requests that the ACRS withhold the SE from public disclosure until the information has been released publicly in ADAMS.
The staff will inform the ACRS immediately if GEH requests that any of the information in the SE be withheld from public disclosure.
Docket No.: 52-045
ML18052A922 - Package ML18164A110 - Memo ML18052A925 - Safety Evaluation NRO-002 OFFICE DLSE:LB3:PM DLSE:LB3:LA DLSE:LB3:BC(A) DLSE: D NAME AMuniz SGreen JRankin RTaylor (ABradford for)
DATE 6/13/2018 6/13/2018 2/4/2019 2/4/2019