Letter Sequence Acceptance Review |
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EPID:L-2018-LLA-0008, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors (Approved, Closed) |
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MONTHYEAR05000324/LER-1916-006-01, Regarding Control Room Air Conditioning Units Inoperable Due to Corroded Supports2017-05-0303 May 2017 Regarding Control Room Air Conditioning Units Inoperable Due to Corroded Supports Project stage: Request BSEP 17-0098, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2018-01-10010 January 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors Project stage: Request ML18045A8492018-02-14014 February 2018 NRR E-mail Capture - Brunswick 50.69 - Risk Informed SSC Acceptance Review Project stage: Acceptance Review ML18130A0212018-05-0909 May 2018 NRR E-mail Capture - Brunswick - Adoption of 10 CFR 50.69 - Hwpra and Xfpra Audit Plan and Setup of Online Reference Portal Project stage: Other ML18180A4182018-07-0202 July 2018 Audit Plan for Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components Forr Nuclear Power Reactors (EPID L-2018-LLA-0008; L-2018-LLA-0034) Project stage: Other ML18220A7902018-08-0707 August 2018 NRR E-mail Capture - Brunswick - Adoption of 10 CFR 50.69 - Supplement to the Hwpra and Xfpra Audit Plan for BSEP Onsite Audit Project stage: Other ML18263A3042018-09-20020 September 2018 NRR E-mail Capture - Brunswick Draft RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: Draft RAI RA-18-0144, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Report2018-09-27027 September 2018 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Report Project stage: Request ML18282A1492018-10-0909 October 2018 NRR E-mail Capture - Brunswick RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: RAI RA-18-0178, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for .2018-11-0202 November 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for . Project stage: Response to RAI ML18282A2242018-11-14014 November 2018 Regulatory Audit Summary Regarding License Amendment Requests to Adopt 10 CFR 50.69 Project stage: Other ML18360A0352018-12-21021 December 2018 NRR E-mail Capture - Brunswick Draft 2nd Round RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: Draft RAI ML19015A0302019-01-14014 January 2019 NRR E-mail Capture - Brunswick 2nd Round RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: RAI RA-19-0010, Response to NRC RAI Re Application to Adapt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2019-02-13013 February 2019 Response to NRC RAI Re Application to Adapt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Project stage: Response to RAI ML19056A2212019-02-25025 February 2019 NRR E-mail Capture - Brunswick Draft 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: Draft RAI ML19067A2712019-03-0707 March 2019 NRR E-mail Capture - Brunswick 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: RAI RA-19-0152, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,Systems, and Components (Sscs) for Nuclear Power Reactors2019-04-0808 April 2019 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,Systems, and Components (Sscs) for Nuclear Power Reactors Project stage: Response to RAI ML19149A2102019-07-0101 July 2019 Regulatory Audit Summary, License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants Project stage: Other ML19149A4712019-09-17017 September 2019 Issuance of Amendment Nos. 292 and 320, Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Project stage: Approval 2018-08-07
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Text
1 NRR-DMPSPEm Resource From:
Hon, Andrew Sent:
Wednesday, February 14, 2018 4:07 PM To:
Zaremba, Arthur H.; Murray, William R. (Bill) (Bill.Murray@duke-energy.com)
(Bill.Murray@duke-energy.com)
Subject:
Brunswick 50.69 - Risk Informed SSC Acceptance Review (EPID: L-2018-LLA-0008)
Importance:
High By letter dated January 10, 2018 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML18010A344), Duke Energy Progress, LLC (Duke Energy, the licensee) submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant Unit Nos. 1 and 2. The proposed amendments would revise the licensing basis by adding a license condition to allow for the implementation of the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.69, "Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. The provisions of 10 CFR 50.69 allow adjustment of the scope of equipment subject to special treatment controls (e.g., quality assurance, testing, inspection, condition monitoring, assessment, and evaluation).
The purpose of this email is to provide the results of the NRC staffs acceptance review of the licensees request. The acceptance review is intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. The staff performed the acceptance review in accordance with Office Instruction LIC-109, Revision 2, "Acceptance Review Procedures" (ML16144A521) and concluded that it provides technical information in sufficient detail to enable the NRC staff to complete its technical review and make an assessment regarding the acceptability of the proposed request. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that affect the staffs ability to complete the detailed technical review are identified despite the completion of the acceptance review.
Our review will include the evaluation of the acceptability of Full-power Internal Events (FPIE), Internal Flooding, and Internal Fire PRA models as well as external hazard analyses such as: Seismic Margins Analysis (SMA) and external flooding probability for this application and the use of those models in the licensees 10 CFR 50.69 categorization program. The NRC staff estimates that the review of this request will take approximately 1,350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> to complete. We will use your request completion date of January 16, 2019 as a target date. However, because of the external hazards included in your request, additional time may be needed. These estimates are based on the staffs initial review of the application and they could change, due to several factors including requests for additional information, and unanticipated addition of scope to the review. If there are emergent complexities or challenges in the review that would cause changes to the initial forecasted completion dates or hours, the reasons for the changes, along with the new estimates, will be communicated to you.
Andy Hon, PE Project Manager (Brunswick Nuclear Plant 1 & 2, Sequoyah Nuclear Plant 1 & 2)
Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-8480 OWFN O8E06 Mail Stop O8B1A andrew.hon@nrc.gov
Hearing Identifier:
NRR_DMPS Email Number:
164 Mail Envelope Properties (Andrew.Hon@nrc.gov20180214160600)
Subject:
Brunswick 50.69 - Risk Informed SSC Acceptance Review (EPID:
L-2018-LLA-0008)
Sent Date:
2/14/2018 4:06:47 PM Received Date:
2/14/2018 4:06:00 PM From:
Hon, Andrew Created By:
Andrew.Hon@nrc.gov Recipients:
"Zaremba, Arthur H." <Arthur.Zaremba@duke-energy.com>
Tracking Status: None "Murray, William R. (Bill) (Bill.Murray@duke-energy.com) (Bill.Murray@duke-energy.com)"
<Bill.Murray@duke-energy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3149 2/14/2018 4:06:00 PM Options Priority:
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