ML19205A393

NRC045 - Memorandum from Eric J. Leeds, NRR, and William M. Dean, Region 1, Seabrook Alkali-Silica Reaction Issue Technical Team Charter (July 9, 2012)

ML19205A393
Person / Time
Site:	Seabrook
Issue date:	07/24/2019
From:	NRC/OGC
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
50-443-LA-2, ASLBP 17-953-02-LA-BD01, RAS 55107
Download: ML19205A393 (11)

Text

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD In the Matter of Docket No. 50-443-LA-2 NEXTERA ENERGY SEABROOK, LLC ASLBP No. 17-953-02-LA-BD01 (Seabrook Station, Unit 1)

Hearing Exhibit Exhibit Number: NRC045 Exhibit

Title:

Memorandum from Eric J. Leeds, NRR, and William M. Dean, Region 1, Seabrook Alkali-Silica Reaction Issue Technical Team Charter (July 9, 2012)

UNITED STATES NUCLEAR REGULATORY COMMISSION

't:ffi REGION I 21OO RENAISSANCE BOULEVARD, SUITE KING OF PRUSSIA, PENNSYLVANIA 1940G2713 1OO Jul:y 9 , i0121 MEMORANDUM TO: Those on Attached List FROM: 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

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Enclosure.  ; ",- -* rfl SAITT Charter and Attachment F@

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c3 CONTACT: Richard Conte, Region I/DRS 610-337-5183

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

MEMORANDUM TO: Those on Attached List FROM: Eric J. Leeds. Director Office of Nuclear Reactor Regulation (NRR)

William M. Dean Regional Administrator Region I

SUBJECT:

SEABROOK ALKALI-SI LI CA REACTION I SSU E TECHN ICAL 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 and oversight of NextEra's ASR investigation and resolution activities.

Docket No. 50-443

Enclosure:

SAITT Charter and Attachment CONTACT: Richard Conte, Region I\DRS 610-337-5183 DISTRIBUTION: RidsNrrAdes Resource Public RidsEdoMailCenter Resource RidsN rrPMSeabrook Resource RidsNrrOd Resource RidsRgnl MailCenter Resource RidsNrrAdro Resource LPWB Reading File RidsAcrsAcnw-MailCTR Resou rce RidsNrrLAABaxter Resource RidsNrrDorl Resource RidsOgcRp Resource S. Burnell, OPA RidsN rrDorl Lpll -2 Resou rce E. Dacus, OCA ADAMS Accession No. : MLl21250588 RFGIr)N I SIINSI REVIEW: PUBLIC REVlEW bV RJG 6/7,12 RI/DRS/DD DORL/DD DE/DD DIRS/DD OFFICE R1/DRS/BC R1/DRP/BC R1/DRP/D RConte* ABurritt* DRoberts* CMiller* MEvans* PHiland* HNieh*

NAME 617112 6t7t12 6t11112 6t22112 6126112 6126112 DATE 617112 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:

a. 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.

b. 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.

d. 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.

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t. To ensure a coordinated review and assessment of the adequacy of the final operability determination and supporting engineering evaluation along with residual corrective actions.

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

h. 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 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: James Trapp, Branch Chief, EB1, DRS, R1 Alternate: Arthur Burritt, Branch Chief, RPB3, DRP, R1 Vice Chairman: Richard Conte, Team Leader, DRS, R1 Alternate: William Cook, SRA, DRS R1 Members: 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 Christopher Miller, Director DRS, R1 610-337-5229 Darrell Roberts, Director, DRP, R1 610-337-5186 James Trapp, Chief EBl, DRS, R1 61 0-337-5069 Arthur Burritt, Chief RPB3, DRP, R1 610-337-5183 Richard Conte, Team Leader, DRS, R1 610-337-5074 William Cook, SRA, DRS R1 603-474-3589 William Raymond, Senior Resident Inspector 610-337-5335 Suresh Chaudhary, Senior Engineer, DRS, R1 301-415-1453 Louise Lund, Deputy Director, DORL, NRR 301-415-3298 Michael Cheok, Deputy Director, DE, NRR 301-415-1 183 Melanie Galloway, Deputy Director, DLR, NRR 301-415-1004 Ho Nieh, Director DIRS, NRR 301-415-2150 Meena Khanna, Branch Chief, DORL, NRR 301-415-3969 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 ASR-degradation 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) 10 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. ML103050447)

(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. ML112241543)

(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