ML18045A849: Difference between revisions

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| document type = E-Mail
| document type = E-Mail
| page count = 2
| page count = 2
| project = EPID:L-2018-LLA-0008
| stage = Acceptance Review
}}
=Text=
{{#Wiki_filter:1NRR-DMPSPEm ResourceFrom:Hon, AndrewSent:Wednesday, February 14, 2018 4:07 PMTo: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:HighBy 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 staff's acceptance review of the licensee's 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 staff's 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 licensee's 10 CFR 50.69 categorization program. The NRC staff estimates that the review of this request will take approximately 1,350 hours 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 staff's 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:    High  Return Notification:    No  Reply Requested:    No  Sensitivity:    Normal  Expiration Date:      Recipients Received:       
}}
}}

Revision as of 23:14, 29 March 2018

2018/02/14 NRR E-mail Capture - Brunswick 50.69 - Risk Informed SSC Acceptance Review (EPID: L-2018-LLA-0008)
ML18045A849
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 02/14/2018
From: Hon A L
Plant Licensing Branch II
To: Zaremba A H
Duke Energy Carolinas
References
L-2018-LLA-0008
Download: ML18045A849 (2)


Text

1NRR-DMPSPEm ResourceFrom:Hon, AndrewSent:Wednesday, February 14, 2018 4:07 PMTo: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:HighBy 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 staff's acceptance review of the licensee's 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 staff's 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 licensee's 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 staff's 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: High Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: