FACILITY: Seabrook Station, Unit No. 1 

SUBJECT: SUMMARY OF JUNE 15, 2016, PRESUBMITTAL MEETING WITH NEXTERA 

ENERGY REGARDING PROPOSED LICENSE AMENDMENT REQUEST ON 

ALKALI SILICA REACTION (CAC NO. MF7996) 

On June 15, 2016, a Category 1 public meeting was held between the U.S. Nuclear Regulatory 

Commission (NRC) and representatives of NextEra Energy (NextEra, the licensee) at NRC 

Headquarters, Three White Flint North, 11601 Landsdown Street, Rockville, Maryland. The 

purpose of the meeting was to discuss NextEra's planned license amendment request (LAR) to 

include the impacts of alkali silica reaction (ASR) into the licensing basis at the Seabrook 

Station, Unit No. 1 (Seabrook). The meeting notice and agenda, dated May 31, 2016, are 

available in the Agencywide Documents Access and Management System (ADAMS) at 

Accession No. ML 16153A279. A list of attendees is enclosed. The licensee's presentation is 

available in ADAMS at Accession No. ML 16168A412. 

The licensee presented its plans to submit an LAR by July 31, 2016, to propose a change in the 

Updated Final Safety Analysis Report methodology to address ASR concrete degradation at 

Seabrook. The current licensing basis for Seabrook is ACI 318-71 for all seismic Category I 

structures other than containment and American Society of Mechanical Engineers Boiler & 

Pressure Vessel Code (ASME Code), Section Ill, for containment. Neither of these codes takes 

into account the loads and stresses associated with ASR. The licensee stated that the LAR will 

show how the acceptance criteria for ACI 318-71 and ASME Code, Section Ill, will still be met 

after adding the loads and stresses associated with ASR for Seabrook. 

The licensee went on to describe the testing programs it developed to investigate the structural 

impact of ASR on reinforced concrete. The NRC staff questioned whether the basis for the 

licensee's conclusions would be included as part of the submittal, and NextEra indicated it 

would be included. The NRC staff also asked whether an explanation as to how the test 

methods and results are applicable to Seabrook would be included in the submittal, and 

NextEra said that they would be included. 

The next portion of the licensee's presentation focused on its proposed methodology to evaluate 

structural deformation due to ASR at Seabrook. The licensee indicated that the LAR would 

describe a progressive approach for evaluating structures with deformation. The approach will 

have three stages (1 - Screening, 2 - Analytical, and 3 - Detailed), and each stage has a 

progressively more complex evaluation to ensure adequate margin exists to either the 

ACI 318-71 or ASME Code, Section Ill, limits. As an example, if the Stage 1 evaluation for a 

building showed there was adequate margin, then a Stage 2 or Stage 3 evaluation was not 

required. Since the evaluations are done for each applicable building, each evaluation also 

defines the threshold for monitoring that specific building. 
- 2 -

The NRC staff had a number of questions on the modeling techniques NextEra would be using 

to refine its calculations for the different stages. The NRC staff stated that this would be an 

important portion of its review. NextEra acknowledged the NRC staff's concerns. 

The licensee then went on to describe its ASR monitoring program. NextEra stated that the 

monitoring program will ensure that the expansion seen at the plant is bounded by the limits 

established from the test program. The licensee will update its Structural Monitoring Program 

(SMP) with new monitoring requirements. NextEra then described the tiered approach of this 

program, including actions taken and proposed criteria (slide 27 of the licensee's presentation). 

The NRC staffed asked whether the SMP, or at least this new monitoring criteria for ASR, would 

be included in the submittal. NextEra said that was not its intention but would take this into 

consideration. 

During the meeting, the NRC staff asked if the submittal would address the effect of ASR on 

concrete material properties and whether the information would be included as part of the 

submittal. The NRC staff also asked questions related to NextEra implementing its 

methodology for addressing deformation (i.e., have any evaluations been completed for any of 

the structures, what is the timeline for completing all of the evaluations, and will any evaluations 

be included as part of the submittal, or at least completed prior to the submittal). NextEra 

acknowledged the NRC staff concerns and will consider them in preparing the final document. 

Members of the public were in attendance but no comments were made. Public Meeting 

Feedback forms were not received. 

Please direct any inquiries to me at 301-415-2048 or._.~XAe-mail t2_o Justin.Poole@nrc.gov . .... •' 

,.~·· / 

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( ~'/ ~-- '--"" . 

Docket No. 50-443 

Enclosure: 

List of Attendees 

cc w/enclosure: Distribution via Listserv 

Justin C. Poole, Project Manager 

Plant Licensing Branch 1-2 

Division of Operating Reactor Licensing 

Office of Nuclear Reactor Regulation 
LIST OF ATTENDEES 

JUNE 15. 2016. MEETING WITH NEXTERA ENERGY 

PRESUBMITTAL MEETING ON PROPOSED ALKALI SILICA REACTION LICENSE 

AMENDMENT FOR SEABROOK STATION. UNIT NO. 1 

NRC Participants: 

• Doug Broaddus, Branch Chief, Office of Nuclear Reactor Regulation (NRR)/Division of 

Operating Reactor Licensing (DORL), LPL 1-2 

• Justin Poole, Project Manager, NRR/DORL 

• Yong Li, Acting Branch Chief, NRR/Division of Engineering (DE), Mechanical and Civil 

Engineering Branch 

• Kamal Manely, Senior Technical Advisor, NRR/DE 

• Farhad Farzam, Senior Structural Engineer, NRR/DE 

• Bryce Lehman, Technical Reviewer, NRR/DE 

• Brian Wittick, Branch Chief, NRR/Division of License Renewal (DLR), Aging Management of 

Structures, Electrical and Systems Branch 

• George Thomas, Senior Structural Engineer, NRR/DLR 

• Tam Tran, Project Manager, NRR/DLR 

• Fred Bower, Branch Chief, Region 1, Division of Reactor Projects, Branch 3 

• Bill Cook, Senior Reactor Analyst, Region 1 

NextEra Participants: 

• Larry Nicholson, Licensing Director 

• Ken Browne, ASR Project Manager 

• Brian Brown, Principal Engineer 

• Steven Hamrick, Attorney 

• Said Bolourchi, Senior Principal, SGH 

• John Simons, General Manager, MPR 

• Amanda Card, Engineer, MPR 

• James Moroney, Project Manager, MPR 

• Phil Rush, Engineer, MPR 

Public: 

• Jana Bergman, Technical Writer, Curtiss-Wright/Scientech 

Enclosure 
- 2 -

The NRC staff had a number of questions on the modeling techniques NextEra would be using 

to refine its calculations for the different stages. The NRC staff stated that this would be an 

important portion of its review. NextEra acknowledged the NRC staff's concerns. 

The licensee then went on to describe its ASR monitoring program. NextEra stated that the 

monitoring program will ensure that the expansion seen at the plant is bounded by the limits 

established from the test program. The licensee will update its Structural Monitoring Program 

(SMP) with new monitoring requirements. NextEra then described the tiered approach of this 

program, including actions taken and proposed criteria (slide 27 of the licensee's presentation). 

The NRC staffed asked whether the SMP, or at least this new monitoring criteria for ASR, would 

be included in the submittal. NextEra said that was not its intention but would take this into 

consideration. 

During the meeting, the NRC staff asked if the submittal would address the effect of ASR on 

concrete material properties and whether the information would be included as part of the 

submittal. The NRC staff also asked questions related to NextEra implementing its 

methodology for addressing deformation (i.e., have any evaluations been completed for any of 

the structures, what is the timeline for completing all of the evaluations, and will any evaluations 

be included as part of the submittal, or at least completed prior to the submittal). NextEra 

acknowledged the NRC staff concerns and will consider them in preparing the final document. 

Members of the public were in attendance but no comments were made. Public Meeting 

Feedback forms were not received. 

Please direct any inquiries to me at 301-415-2048 or by e-mail to Justin.Poole@nrc.gov. 

Docket No. 50-443 

Enclosure: 

List of Attendees 

IRA/ 

Justin C. Poole, Project Manager 

Plant Licensing Branch 1-2 

Division of Operating Reactor Licensing 

Office of Nuclear Reactor Regulation 

cc w/enclosure: Distribution via Listserv 

DISTRIBUTION: 

PUBLIC 

RidsACRS_MailCTR Resource 

RidsN rrDorl Lpl 1-2 Resource 

RidsNrrPMSeabrook Resource 

RidsNrrLALRonewicz Resource 

RidsRgn 1 MailCenter Resource 

LPL 1-2 R/F 

TWertz, NRR 

RidsNrrDeEmcb Resource 

KManoly, NRR 

FFarzam, NRR 

BLehman, NRR 

RidsNrrDlrRasb Resource 

GThomas, NRR 

TTran, NRR 

FBower, RI 

BCook, RI 

JBowen, OEDO 

ADAMS Accession No.: ML 16204A 261 M ee r mQ N o r ice: ML 16153A279 H d an outs: ML 16168A412 

OFFICE NRR/DORL/LPL 1-2/PM NRR/DORL/LPL 1-2/LA NRR/DORL/LPL 1-2/BC NRR/DORL/LPL 1-2/PM 

NAME JPoole LRonewicz DBroaddus (REnnis for) JPoole 

DATE 7/26/2016 7/25/2016 7/29/2016 7/29/2016 

OFFICIAL RECORD COPY