ML17359A014
| ML17359A014 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/24/2017 |
| From: | NRC |
| To: | |
| References | |
| 17-953-02-LA-BD01 | |
| Download: ML17359A014 (16) | |
Text
1 SeabrookLANPEm Resource From:
Poole, Justin Sent:
Thursday, August 24, 2017 7:43 AM To:
'Deborah Grinnell'
Subject:
RE: Re: NextEra meeting with NRC Attachments:
2017_08_24_NEE_PublicMeeting.pdf
- Debbie, Here are NextEra's slides for the public meeting.
Justin C. Poole Project Manager NRR/DORL/LPL I U.S. Nuclear Regulatory Commission (301)415-2048
Original Message-----
From: Poole, Justin Sent: Tuesday, August 22, 2017 4:22 PM To: 'Deborah Grinnell' <grinnelldebbie2@gmail.com>
Subject:
RE: Re: NextEra meeting with NRC
- Debbie, Here are the staff's slides that we'll present at the public meeting and below is the conference line information. The meeting focus is on their stage 3 building evaluations.
Participant passcode: 46681#
Toll Free Number: 1-888-790-7136 Justin C. Poole Project Manager NRR/DORL/LPL I U.S. Nuclear Regulatory Commission (301)415-2048
Original Message-----
From: Deborah Grinnell [1]
Sent: Tuesday, August 22, 2017 4:18 PM To: Poole, Justin <Justin.Poole@nrc.gov>
Subject:
[External_Sender] Re: NextEra meeting with NRC
- Justin, What is the content of your meetin with NextEra g..the outline of your questions.
Thank you,
2 Debbie
> On Aug 22, 2017, at 4:12 PM, Deborah Grinnell <grinnelldebbie2@gmail.com> wrote:
> Hello Justin
> I will listen, follow, and may speak with C-10 on the Aug 24th 2017 meeting you will have with NextEra on August 24 at 1-3PM.
> Debbe Grinnell
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Subject:
RE: Re: NextEra meeting with NRC Sent Date:
8/24/2017 7:42:31 AM Received Date:
8/24/2017 7:42:27 AM From:
Poole, Justin Created By:
Justin.Poole@nrc.gov Recipients:
"'Deborah Grinnell'" <grinnelldebbie2@gmail.com>
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HQPWMSMRS01.nrc.gov Files Size Date & Time MESSAGE 1329 8/24/2017 7:42:27 AM 2017_08_24_NEE_PublicMeeting.pdf 387865 Options Priority:
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Seabrook Station License Amendment Request 16-03 ASR Structural Evaluation Methodology Ken Browne, Mike Collins 24 August 2017
2 NextEra Energys nuclear fleet is 4th largest in MW generation and number of reactors in the U.S.
Turkey Point (Florida) 1,600 MWe Turkey Point (Florida) 1,600 MWe NextEra Energys nuclear plants represent approximately 27 percent of our generation Acquired: 2007 Point Beach (Wisconsin) 1,193 MWe Acquired: 2007 Point Beach (Wisconsin) 1,193 MWe St. Lucie (Florida) 2,000 MWe St. Lucie (Florida) 2,000 MWe Acquired: 2002 Seabrook (New Hampshire) 1,245 MWe Acquired: 2002 Seabrook (New Hampshire) 1,245 MWe Acquired: 2006 Duane Arnold (Iowa) 615MWe Acquired: 2006 Duane Arnold (Iowa) 615MWe
3 The foundation for everything we do are the Values and Core Principles of our Nuclear Excellence Model
4 Objective Understand staff expectations for methodology Address comments on LAR Stage 3 methodology Discuss methodology document Show consistency of applied methodology Schedule & path forward
5 Overview of ASR Evaluation Process License Amendment Request Methodology Document Structural Analysis &
Evaluation Threshold Limits Stage 1, 2, and 3 analyses Material properties Repeatable process for stage 1, 2, and 3 Decision points for analysis Demand calculations Compliant to ACI 318-71, ASME and UFSAR acceptance criteria Establish design margin Structures Monitoring Program Threshold limits ASR expansion limits Administrative limits
6 Overview of Methodology Document Overview Codes and Standards Materials Load and load combinations Analysis
- Stage One and Stage Two
- Stage Three Correlation of model to field conditions Decision points Acceptance Criteria ASR Threshold Limits and Monitoring
7 FEA Model Field observations &
measurements Distress &
Deformation Sustained Loads Cracking Is cracking observed?
Is cracking limit exceeded?
Concrete Backfill Pressure Is backfill confined?
Is there softening in the confinement?
Is scaling needed to match field condition?
Moment Redistribution Is there a self-relieving condition?
Is there a localized moment exceedance?
Does structural configuration conform to ACI 318-71 Section 8.6?
Flexural cracking limited to ACI 318-71 Axial tension and shear cracking stiffness limits Limit to overburden pressure Limit to strength of confinement Limit to field observations Limit to ACI 318-71 8.6 for conforming structures Confirm with alternative analysis Factored Loads Demand-to-capacity ratio Acceptance Criteria Limits of use Decisions Evaluation Stage Three Evaluation Process
8 Consistency of Methodology CEB Make-up Air Intake RHR FSB Control & Diesel Mech. Pen. & MSFW-W Cooling Tower Electrical Manholes Condensate Storage Tank Equipment Hatch Containment Steam Gen. Blowdown CEVA Electrical Tunnel Containment Internals Stage 3
3 3
3 3
3 3
3,2,1 2
1 1
1 1
1 1
LOADS AND LOAD COMBINATIONS Load Combinations 9
9 9
9 9
9 9
9 9
9 9
9 9
9 9
Containment NA NA NA NA NA NA NA NA NA NA 9
NA NA NA NA Containment Internal Structures NA NA NA NA NA NA NA NA NA NA NA NA NA NA 9
Other Seismic Category I Structures 9
9 9
9 9
9 9
9 9
9 NA 9
9 9
NA ANALYSIS Selection of Starting Stage 9
9 9
9 9
9 9
9 9
9 9
9 9
9 9
Stage One Analyses NA NA NA NA NA NA NA 9
NA 9
9 9
9 9
9 Stage Two Analyses NA NA NA NA NA NA NA 9
9 NA NA NA NA NA NA Stage Three Analyses 9
9 9
9 9
9 9
9 NA NA NA NA NA NA NA Field Observations to Support Stage Three Analyses 9
9 9
9 9
9 9
9 NA NA NA NA NA NA NA Non-ASR Demands for Stage Three Analyses 9
9 9
9 9
9 9
9 NA NA NA NA NA NA NA ASR Demands for Stage Three Analyses 9
9 9
9 9
9 9
9 NA NA NA NA NA NA NA ASR Expansion of Structural Components 9
9 9
9 9
9 9
9 NA NA NA NA NA NA NA ASR Expansion of Concrete Backfill 9
NA 9
9 9
9 NA NA NA NA NA NA NA NA NA Correlation of Model with Field Conditions 9
9 9
9 9
9 9
9 NA NA NA NA NA NA NA Refined Analytical Methods 9
9 9
9 9
9 9
9 NA NA NA NA NA NA NA Use of Cracked Section Properties in Stage Three Analyses NR 9
9 9
9 9
9 9
NA NA NA NA NA NA NA Use of Moment Redistribution in Stage Three Analyses 9
NR 9*
NR NR NR NR 9*
NA NA NA NA NA NA NA Factored Load Calculation 9
9 9
9 9
9 9
9 NA NA NA NA NA NA NA ACCEPTANCE CRITERIA Acceptance Criteria for Containment NA NA NA NA NA NA NA NA NA NA 9
NA NA NA NA Acceptance Criteria for Other Seismic Category 1 Structures 9
9 9
9 9
9 9
9 9
9 NA 9
9 9
9 Impact of ASR on Code of Record Acceptance Criteria 9
9 9
9 9
9 9
9 9
9 9
9 9
9 9
Acceptance Criteria for Isolation Gaps 9
NA 9
9 9
9 NA NA NA 9
9 9
9 9
NA Acceptance Criteria for Foundations 9
9 9
9 9
9 9
9 9
9 9
9 9
9 NA Acceptance Criteria for Stability 9
9 9
9 9
9 9
9 9
9 9
9 9
9 NA ASR THRESHOLD LIMITS AND MONITORING Methodology to Account for Potential Future ASR Expansion 9
9 9
9 9
9 9
9 9
9 9
9 9
9 9
ASR Threshold Limits and Monitoring for Stage One Structures NA NA NA NA NA NA NA NA NA 1.5 1.8 3.5 3.0 3.0 9
ASR Threshold Limits and Monitoring for Stage Two Structures NA NA NA NA NA NA NA NA 1.6 NA NA NA NA NA NA ASR Threshold Limits and Monitoring for Stage Three Structures 1.2 1.4 1.2 9
9 9
9 9
NA NA NA NA NA NA NA
9 Threshold Monitoring Perform monitoring.
Is threshold limit approached?
Methodology Yes No Structural Evaluation Identify minimum threshold factor Consider Structural Modification Further analysis Re-evaluate using same methodology, Identify new threshold factor Continue Monitoring Yes
10 Building Deformation Analyses (1 of 2)
Structure Schedule Percent Complete Condensate water storage tank Complete 100%
Containment enclosure building Complete 100%
Containment enclosure ventilation area Complete 100%
Containment structure Complete 100%
Equipment hatch missile shield Complete 100%
Steam generator recovery blowdown bldg.
Complete 100%
Control room make-up air intake Complete 100%
Electrical cable tunnels Complete 100%
Pre-action valve building 3Q2017 80%
RHR equipment vault Complete 100%
Containment internal structures 3Q2017 80%
Main steam and feed water east pipe chase 3Q2017 50%
Hydrogen recombiner structure Safety-related electrical duct banks and manholes 1Q2018 40%
Emergency feedwater pump building 3Q2017 10%
Fuel storage building 3Q2017 60%
Structures that are/expected to be Stage 3
11 Building Deformation Analyses (2 of 2)
Structure Schedule Percent Complete Control Building Diesel Generator Building 4Q2017 10%
Mechanical Penetration Personnel hatch area Main steam and feed water west pipe chase 4Q2017 30%
Primary auxiliary building 4Q2017 10%
Service water cooling tower incl. switchgear rooms 1Q2018 Service water access (inspection) vault 1Q2018 Circulating water pumphouse (below el. 21')
Service water pumphouse 2Q2018 Piping (RCA) Tunnels 2Q2018 Tank farm area 2Q2018 Waste processing building 2Q2018 Structures that are/expected to be Stage 3
12 Discussion with NRC Staff
13 Wrap Up The importance to establish a repeatable methodology with limits is understood A consistent methodology is being applied in the structural evaluations A methodology document will be submitted Next Steps Submit methodology document Respond to issued RAIs Maintain communications with NRC staff