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MEMORANDUM TO:

FROM:

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION I

21OO RENAISSANCE BOULEVARD, SUITE 1OO

KING OF PRUSSIA, PENNSYLVANIA 1940G2713

Jul:y 9 , i0121

Those on Attached List

Eric J. Leeds, Director

Office of Nuclear Reactor

William M. Dean

Regional Adm inistratoq

Region I

SUBJECT: SEABROOK ALKALI-SILICA REACTION ISSUE TECHNICAL

TEAM CHARTER

The enclosed Seabrook Alkali-Silica Reaction (ASR) lssue Technical Team (SAITT)

charter defines the purpose and objectives of the assigned staff. Attachments to the Charter

provide background information and additional detail involving the teams' review of NextEra's

ASR investigation and resolution activities. litj

.;

Docket No. 50-443

Enclosure.

SAITT Charter and Attachment

CONTACT: Richard Conte, Region I/DRS

610-337-5183

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ADDRESSEES - Memorandum dated : 2

Reoion l(Rl)

David Lew, Deputy Administrator

Darrell Roberts, Director, Division of Reactor Projects (DRP)

Chris Miller, Director, Division of Reactor Safety (DRS)

James Clifford, Deputy Director, DRP

Arthur Burritt, Chief, Reactor Projects Branch No. 3 (RPB3), DRP

Richard Conte, Chief, Engineering Branch No. 1 (EB1), DRS

William Raymond, Senior Resident Inspector, Seabrook, DRP

William Cook, SRA, DRS

James Trapp, Chief, Projects Support Branch 1, DRS

Suresh Chaudhary, Reactor Inspector, DRS

Diane Screnci, Office of Public Affairs (OPA)

Neil Sheehan, OPA

Nancy McNamara, State Liaison Office (SLO)

Doug Tiffi, SLO

Office of Nuclear Reactor Reoulation (NRR)

Bruce Boger, Deputy Director for Reactor Safety Programs

Daniel Dorman, Deputy Director for Engineering and Corporate Support

Michele Evans, Director, Division of Operating Reactor Licensing (DORL)

Patrick Hiland, Director, Division of Engineering (DE)

Brian Holian, Director, Division of License Renewal (DLR)

Ho Nieh, Director, Division of lnspection and Regional Support, (DIRS)

Timothy McGinty, Director, Division of Policy and Rulemaking (DPR)

Sher Bahadur, Deputy Director, DPR

Mary Muessle, Deputy Director, DPR

John Lubinski, Deputy Director, DIRS

Melanie Galloway, Deputy Director, DLR

Louise Lund, Deputy Director, DORL

Michael Cheok, Deputy Director DE

Martin Murphy, Branch Chief, Mechanical & Civil Engineering Branch (EMCB), DE

George Thomas, Structural Engineer, EMCB, DE

Meena Khanna, Branch Chief, Plant Licensing Branch No. 1-2 (LPL1-2)

John Lamb, Sr. Project Manager, LPL 1-2

Dennis Morey, Branch Chief, Project Branch No. 1 (RPB1), DLR

Art Cunanan, License Renewal Project Manager, RPBl

Michael Marshall, Chief, Aging Management of Structures, Electrical and Systems Branch

(RASB), DLR

Abdul Sheikh, Sr. Structural Engineer, RSAB, DLR

Timothy Kobetz, Branch Chief, Reactor lnspection Branch (lRlB)' DIRS

Bill Cartwright, Engineer, lRlB, DIRS

Harold Chernoff, Branch Chief, Operating Experience Branch (IOEB), DIRS

David Pelton, Branch Chief, Generic Communication Branch (PGCB)' DPR

John Jolicoeur, Branch Chief, Licensing Processes Branch (PLPB), DPR

Holly Cruz, Project Manager, PLPB, DPR
SUBJECT:

The enclosed Seabrook Alkali-Silica Reaction (ASR) lssue Technical Team (SAITT)

charter defines the purpose and objectives of the assigned staff. Attachments to the Charter

provide background information and additional detail involving the teams' review and oversight

of NextEra's ASR investigation and resolution activities.

Docket No. 50-443

Enclosure:

SAITT Charter and Attachment

MEMORANDUM TO:

FROM:

CONTACT: Richard Conte, Region I\DRS

610-337-5183

DISTRIBUTION:

Public

RidsN rrPMSeabrook Resource

RidsRgnl MailCenter Resource

LPWB Reading File

RidsNrrLAABaxter Resource

RidsOgcRp Resource

RidsN rrDorl Lpll -2 Resou rce

ADAMS Accession No. : MLl21250588

Those on Attached List

Eric J. Leeds. Director

Office of Nuclear Reactor Regulation (NRR)

William M. Dean

Regional Administrator

Region I

SEABROOK ALKALI-SI LI CA REACTION I SSU E TECHN ICAL

TEAM CHARTER

RidsNrrAdes Resource

RidsEdoMailCenter Resource

RidsNrrOd Resource

RidsNrrAdro Resource

RidsAcrsAcnw-MailCTR Resou rce

RidsNrrDorl Resource

S. Burnell, OPA

E. Dacus, OCA

RFGIr)N I SIINSI REVIEW: PUBLIC REV|EW bV RJG 6/7,12

OFFICE R1/DRS/BC R1/DRP/BC R1/DRP/D RI/DRS/DD DORL/DD DE/DD DIRS/DD

NAME RConte* ABurritt* DRoberts* CMiller* MEvans* PHiland* HNieh*

DATE 617112 617112 6t7t12 6t11112 6t22112 6126112 6126112

OFFICE DLR/DD DPR/DD R-I/RA NRR/D

NAME BHolian TMcGintv* WDean ELeeds

DATE 6t29112 6120t12 7109112 7t03112

concurence
CHARTER FOR THE

SEABROOK ALKALI-SILICA REACTION ISSUE TECHNICAL TEAM

Backqround:

The Alkali-Silica Reaction (ASR) adversely impacts the physical properties of cured concrete.

ASR is a slow chemical process in which the alkalis in the Portland cement react, in the

presence of water, with the susceptible silica contained in the concrete aggregate. This

process creates an alkali-silica gel that expands within the concrete conglomerate causing

micro cracks. The micro cracks may cause a weakening of the concrete (affecting the

compressive strength, tensile and shear strength and elasticity modulus) and potentially the

structural integrity of the safety related and important to safety concrete structures that house

and/or support safety related systems. ln addition to the engineering evaluations,

assessments, and operability determinations completed by NextEra Energy Seabrook, LLC

(NextEra) for the concrete structures observed to be impacted by ASR, NextEra has initiated

an interim monitoring program and an extensive research and testing project to assist in

better understanding the specific causes and effects of ASR at Seabrook Station. The

results of this project are envisioned to shape the long term resolution and corrective actions

of this issue at the station. NRC Confirmatory Action Letter (CAL) No. 1-2112'002, dated

May 16, 2012 (ADAMS Accession No. ML12125A172) confirms recent commitments by

NextEra in regard to planned actions to address ASR at Seabrook Station.

Purpose:

To provide coordination of the onsite inspections, in-office technical reviews, and other

associated evaluation and assessment activities involving NextEra's review and resolution

of the ASR issues at Seabrook Station'

Obiectives:

To review and assess the adequacy of the prompt operability determinations and

supporting engineering evaluation of Seabrook Station concrete structures currently

identified to be impacted by ASR.

To review and assess the adequacy of the interim monitoring program that is used to

help assess the current applicability of the latest operability determinations for the ASR

affected structures until the final operability determination and its bases are complete.

To assess the adequacy of NextEra's root cause evaluation and corrective actions, initial

building assessments, and associated integrated corrective action plan for the project.

To ensure adequacy of technical methods used by the licensee in determining adequate

margin (including testing, sampling).

e. To ensure that the licensee maintains compliance with its license as new information is

obtained that may indicate a need for change, and to ensure a coordinated review of

submittals made by the licensee regarding ASR.

a.

b.

d.
t.

2

To ensure a coordinated review and assessment of the adequacy of the final operability

determination and supporting engineering evaluation along with residual corrective

actions.

To coordinate the NRC staffs review of the adequacy of NextEra's completion of CAL

items.

To ensure coordination of long term aging management program issues related to the

ASR.

i. To ensure a coordinated review for all public and congressional inquiries related to ASR

at Seabrook.

j. Provide a recommendation for closure of CAL No. 1-2012-002.

Functional Responsibilities :

a. Routinely update line executives and make periodic reports to the Region I Administrator

and NRR Office Director.

b. Establish and maintain an action item tracking system.

c. Review each assigned action item's associated closure documentation for adequacy and

completeness.

d. Convene team meetings, as necessary, to review licensee progress, staff review

activities, and to assign or close action items, as needed.

e. Prepare for and conduct public meetings with the licensee, as appropriate.

THIS CHARTER IS APPROVED FOR IMPLEMENTATION gP JUIY 9' .2912

Regional Administrator

Region I

g.

h.

Office of Nuclear Reactor Regulation
ATTACHMENT

Additional Backqround

f n August 2010, Seabrook confirmed the presence of Alkali-Silica Reaction (ASR)

degradation of concrete in below-grade walls of several Category 1 structures with

groundwater intrusion as a result of an investigation that started with license renewal

application. Seabrook is the first plant in the U.S. nuclear industry to exhibit ASR in

concrete structures on site. Initial testing of core samples indicated a reduction in

compressive strength and elastic modulus properties. The U.S. Nuclear Regulatory

Commission (NRC) issued Information Notice (lN) 2011-20,"Concrete Degradation by

Alkali-silica Reaction," on November 18, 2011, to provide the industry with information

related to the ASR identified at Seabrook.

The NRC staffs review of this issue to date has determined that there are no immediate

safety concerns due, in part, to existing safety margins, the localized nature of the ASR, and

ongoing crack monitoring. Key branch chiefs in Region I and NRR have been working

closely to ensure a coordinated effort to the review and share information when needed for

consistency. Cognizant branch staff members from the projects and technical branches of

Region l, NRR DORL, DE, and DLR have been communicating on developments and issues

as ihey occurred since October 2010. They have been instrumental in coordinating

recommendations and communications on this issue.

With the assistance of NRR DE and NRR DLR technical reviewers, Region I conducted

several inspections. In particular, the NRC inspection report, dated March 26,2012, called

for a management meeting on April 23,2012, in addition to documenting two NRC-identified

findings of very low significance (Green). As a result of the meeting, the licensee made

commitments in letters dated May 3, 2012 and May 10,2012 (ADAMS Accession Nos'

ML12125A022 and MLI 2131A479, respectively).

Executive discussions that occurred surrounding the management meeting, the commitment

letters, and the unique nature of this problem have resulted in the formation of the SAITT

and charter.

Recgmmended SAITT Organization and Structure

SAITT Membership

Chairman:

Alternate:

Vice Chairman:

Alternate:

Members:

James Trapp, Branch Chief, EB1, DRS, R1

Arthur Burritt, Branch Chief, RPB3, DRP, R1

Richard Conte, Team Leader, DRS, R1

William Cook, SRA, DRS R1

Martin Murphy, Branch Chief, EMCB, NRR

Meena Khanna, Branch Chief, DORL, NRR

Michael Marshall, Branch Chief, DLR, NRR

Tim Kobetz, Branch Chief, RlB, DIRS

Alternates: Kamal Manoly, Senior LevelAdvisor, DE, NRR
John G. Lamb, Senior Project Manager, DORL, NRRDennis Morey,

Branch Chief, RPB, DLR, NRR

Harold Chernoff, Branch Chief, OEB, DIRS, NRR

A quorum for meetings will consist of the Chairman and Vice Chairman and all other

members or their alternates from the applicable NRR Divisions. For informational meetings

such as the conduct of status meetings with the licensee, a quorum would be the Chairman

or Vice Chairman and two of the other members or their alternates. The desired output from

working group meetings is a level of consensus for actions and recommendations to be

taken by lead offices but tracked to completion by the working group. Alternate views

should be brought to the attention of lead office executives.

Other contributors to the Team may include:

Suresh Chaudhary, Senior Engineer, DRS, R-l

Abdul Sheikh, Senior Engineer, DLR, NRR

George Thomas, Senior Engineer, EMCB, NRR

Angela Buford, Structural Engineer, DLR, NRR

Alice Erickson, Engineer, DLR, NRR

William Raymond, Senior Resident Inspector

Other members or contributors may include staff from NRO, RES, and other offices, as

necessary, and other NRR and Region I support staff that may assist the SAITT in its

activities. Coordination with the Office of New Reactors (Vendor Inspection Branch) will be

the responsibility of the DIRS representative, and coordination with the Office of Nuclear

Regulatory Research (User Needs Assessments) will be the responsibility of the DE and/or

DLR representatives as needed for functionality or aging management. Coordination with

the Division of Policy and Rule Making (Generic Communications and Licensing Process

Reviews) will be the responsibility of the DORL representative.

The leadership of the team rests currently with Region I DRS, as assigned by the RA, and

this includes the formation of a team dedicated to the follow-up of the CAL actions in

accordance with lnspection Procedure (lP) 92702. This may change in the future if the

primary focus shifts to licensing or license renewal issues.

Meeting minutes will capture significant team activities, discussions, and accomplishments,

and provide an updated Action ltem List for staff and management reference.

Informational management briefings should be conducted, as needed, or requested. Team

members are expected to keep their supervision informed and be available to provide

additional details to the published team meeting minutes.

Additional Recommended Functional Details

The SAITT shall coordinate the review of action items developed by the lead office or as

suggested by those branches in support of the project (see attachments 1 and 2). The lead

office for coordination is responsible to ensure the actions items are developed and

consolidated with the following aspects: 1) unique numbering; 2) action to be taken; 3) due

date consistent with licensee action completion dates; 4) lead branch; 5) primary support

branch, if needed; 6) other needed support branches; and, 7) Open or Closed Status with

reference to how the action or technical question was addressed. A lead office not requiring

A-2

Attachment
coordination with other divisional organizations defined in this charter will follow its normal

work practice but keep this organization informed at periodic meetings if the action is related

to the ASR problem (e.9., schedule for license renewal).

The SAITT shall use and schedule resources consistent with the budget process. The lead

offices will be responsible to ensure changes to the budget are appropriately processed.

The SAITT shall work with the responsible organization to develop new guidance, as

needed, related to the operability reviews, licensing reviews, aging management reviews or

inspection instructions related to the ASR issue (Temporary Instructions, Branch Technical

Position, or lnterim Staff Guidance) related to short or longer term monitoring of the problem.

The SAITT shall coordinate the communication of licensing and technical issues to NRC

management, and internal stakeholders, as appropriate and ensure that the technical

resolution of questions raised are appropriately documented by the lead office in the forum

that it would normally use, such as an inspection report or license amendment.

The SAITT shall coordinate the communication of licensing and technical issues to external

stakeholders with the conduct of public meetings and through the use of communication

plans for documents being issued and for inquiries made through the use of

correspondence.

When an office is in a support role, the SAITT will ensure coordination of activities in order to

support timely completion of due dates for the lead offices.

The SAITT will review the results of activities of the lead offices so as to not impact the

timely processing of the associated documentation by the lead office including the review of

any associated communication plans for that document.

Reportino

The SAITT will communicate the results of its coordinated efforts to the Region I Regional

Administrator and Director of NRR on a periodic basis as needed (quarterly to start).

CONTACTS

610-337-51 28

610-337-5229

610-337-5186

61 0-337-5069

610-337-5183

610-337-5074

603-474-3589

610-337-5335

301-415-1453

301-415-3298

301-415-1 183

301-415-1004

301-415-2150

301-415-3969

Christopher Miller, Director DRS, R1

Darrell Roberts, Director, DRP, R1

James Trapp, Chief EBl, DRS, R1

Arthur Burritt, Chief RPB3, DRP, R1

Richard Conte, Team Leader, DRS, R1

William Cook, SRA, DRS R1

William Raymond, Senior Resident Inspector

Suresh Chaudhary, Senior Engineer, DRS, R1

Louise Lund, Deputy Director, DORL, NRR

Michael Cheok, Deputy Director, DE, NRR

Melanie Galloway, Deputy Director, DLR, NRR

Ho Nieh, Director DIRS, NRR

Meena Khanna, Branch Chief, DORL, NRR

Martin Murphy, Branch Chief, EMCB, NRR

A-3

Attachment
301-415-2871 Michael Marshall, Branch Chief, DLR, NRR

301-415-1932 Tim Kobetz, Branch Chief, RlB, DIRS

301-415-2765 Kamal Manoly, Senior LevelAdvisor, DE, NRR

301-415-3100 John G. Lamb, Senior Project Manager, DORL, NRR

301-415-6852 Dennis Morey, Branch Chief, RPB, DLR, NRR

301-415-6584 Harold Chernoff, Branch Chief, OEB, DIRS, NRR

301-415-6004 Abdul Sheikh, Senior Structural Engineer, DLR, NRR

301-415-6181 George Thomas, Structural Engineer, EMCB, NRR

301-415-1933 Alice Erickson, Engineer, DLR, NRR

301-415-3166 Angela Buford, Structural Engineer, DLR, NRR

REGULATORY FRAMEWORK

The regulatory requirements, applicable for the duration of the current 4O-year operating

license pursuant to 10 CFR Part 50, and guidance applicable to addressing the ASRdegradation of concrete in Other Seismic Category 1, structures at Seabrook, which

includes the "B" Electrical Tunnel, can be found in the following regulations and regulatory

documents.

(1) 10 CFR 50.65, Maintenance Rule, as it relates to monitoring the performance and

condition of structures, systems, or components (SSC) in a manner sufficient to

provide reasonable assurance that these SSCs are capable of fulfilling their intended

functions. When the performance or condition of an SSC does not meet established

goals, appropriate conective action shall be taken'

(2) 1O CFR Part 50, Appendix B, as it relates to the quality assurance criteria for nuclear

power plants.

(3) Criterion Xl, "Test Control," as it relates to establishing a test program to assure that all

testing required to demonstrate that structures, systems, and components will perform

satisfactorily in service is identified and performed in accordance with written test

procedures which incorporate the requirements and acceptance limits contained in

applicable design documents; and test results are documented and evaluated to

assure that test requirements have been satisfied'

(4) Criterion XVl, "Corrective Action," of 10 CFR Part 50, Appendix B, as it relates to

implementing a corrective action program to assure that conditions/significant

conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations,

defective material and equipment, and non-conformances are promptly identified,

cause addressed, and corrected. (5) 10 CFR Part 50, Appendix A, GDC 1, as it relates to structures, systems, and

components being designed, fabricated, erected, and tested to quality standards

commensurate with the importance of the safety function to be performed. Where

generally recognized codes and standards are used, they shall be evaluated to

determine applicability, adequacy, and sufficiency and shall be supplemented or

modified as necessary to assure a quality product in keeping with the required safety

function. (6) 10 CFR Part 50, Appendix A, GDC 2, as it relates to the design of the safety-related

structures being able to withstand the most severe natural phenomena such as wind,

tornadoes, floods, and earthquakes and the appropriate combination of all loads.

(7) 10 CFR Part 50, Appendix A, GDC 4, as it relates to safety-related structures being

appropriately protected against environmental and dynamic effects, including the

effects of missiles, pipe whipping, and discharging fluids, that may result from

equipment failures and from events and conditions outside the nuclear power unit.

A-4

Attachment
(8) 10 CFR 50.59, as it relates to changes, tests, and experiments.

(9) NUREG-0800, Standard Review Plan, Section 3.8.4 - Other Seismic Category 1

Structures

(10) Regulatory Guide 1.160, Revision 2 (March 1997), Monitoring the Effectiveness of

Maintenance at Nuclear Power Plants

PAST INSPECTION REPORTS ANd OTHER DOCUMENTS

(1) Seabrook Report No.0500044312010004, dated November 1,2010 (ADAMS

Accession No. ML1 03050447) (2) Seabrook Report No. 0500044312011002, dated May 12,2011(ADAMS Accession No.

M1111330689) .

(3) Seabrook Report No. 0500044312011003, dated August 12,2011 (ADAMS Accession

No. ML1 12241543) (4) NRC Integrated Inspection Report05000443/2011005, dated February 14,2012

(ADAMS Accession No. ML12045A544) (5) NRC Integrated Inspection Report 05000443/2011007, dated May 23,2011 (ADAMS

Accession No. ML111360432) related to License Renewal lP 71002

(6) NRC Inspection Report 0500044312011010 Related to Alkali-Silica Reaction lssue in

Safety-Related Structures, dated March 26,2012 (ADAMS Accession No.

M1120480066) (T) Confirmatory Action Letter No. 2012-002, dated May 16, 2012,Information Related to

Concrete Degradation lssues (ADAMS Accession No. M112125A172)

A-5

Attachment