ML14014A378
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 February 19, 2014 MEMORANDUM TO: Those on Attached List FROM: Eric J. Leeds, Director /RA by Jennifer Uhle for/
Office of Nuclear Reactor Regulation (NRR)
William M. Dean /RA/
Regional Administrator Region I
SUBJECT:
SEABROOK ALKALI-SILICA REACTION ISSUE TECHNICAL TEAM CHARTER REVISION 1 The enclosed Revision 1 to the Seabrook Alkali-Silica Reaction (ASR) Issue Technical Team (SAITT) charter defines the purpose and objectives of the assigned staff. The SAITT charter is revised to remove completed objectives associated with NRC review of NextEras prompt operability determinations and supporting engineering evaluations, NextEras root cause evaluation and integrated corrective action plan to resolve the ASR issue at Seabrook, and NRC staff coordination and closure of CAL 1-2012-002. This revision also updates charter objectives to coordinate NRC staff review of NextEras ongoing structural monitoring and testing programs and the licensees assessment of new information and its operability determinations. Objectives related to NRC review of NextEras aging management program for ASR and agency communication activities remain unchanged. Functional responsibilities have been revised to delete reference to an action tracking system because normal regional and agency tracking processes are being used to track actions as necessary. Finally the attachment to the SAITT charter has been streamlined and revised to reflect personnel changes since initial charter development.
Docket No. 50-443
Enclosure:
SAITT Charter and Attachment CONTACT: William Cook, Region I/DRS 610-337-5074
ML14014A378 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRS RI/DRS RI/DRS DORL/DD DE/DD NAME WCook/WC MGray/MG RLorson/RL MEvans/ME PHiland/KB for DATE 01/02/2014 01/02/2014 01/06/2014 01/22/2014 01/17/2014 OFFICE DIRS/DD DLR/DD RI/RA NRR/D NAME HNieh/HN JLubinski/JL WDean/WD ELeeds/JU for DATE 01/28/2014 01/28/2014 02/04/2014 02/18/2014 2
ADDRESSEES:
Region I (RI)
David Lew, Deputy Regional Administrator Michael Scott, (Acting) Director, Division of Reactor Projects (DRP)
Ray Lorson, Director, Division of Reactor Safety (DRS)
James Trapp, Deputy Director, DRS Glenn Dentel, Chief, Reactor Projects Branch No. 3, DRP Paul Cataldo, Senior Resident Inspector, Seabrook, DRP Chris Newport, Resident Inspector, Seabrook, DRP William Cook, Senior Risk Analyst (SRA), DRS Mel Gray, Chief, Engineering Branch 1, DRS Suresh Chaudhary, Reactor Inspector, DRS Niklas, Floyd, Reactor Inspector, DRS Diane Screnci, Office of Public Affairs (OPA)
Neil Sheehan, OPA Nancy McNamara, State Liaison Office (SLO)
Doug Tifft, SLO Office of Nuclear Reactor Regulation (NRR)
Daniel Dorman, Deputy Director for Engineering and Corporate Support Timothy McGinty, Director, Division of Safety Systems (DSS)
Michele Evans, Director, Division of Operating Reactor Licensing (DORL)
Patrick Hiland, Director, Division of Engineering (DE)
John Lubinski, Director, Division of License Renewal (DLR)
Ho Nieh, Director, Division of Inspection and Regional Support, (DIRS)
Lawrence Kokajko, Director, Division of Policy and Rulemaking (DPR)
David Pelton, (Acting) Deputy Director, DSS Louise Lund, Deputy Director, DORL Brian Smith, (Acting) Deputy Director, DE Melanie Galloway, Deputy Director, DLR Allen Howe, Deputy Director, DIRS Sher Bahadur, Deputy Director, DPR Mirela Gavrilas, (Acting) Deputy Director, DPR Anthony McMurtray, Chief, Mechanical & Civil Engineering Branch (EMCB), DE Meena Khanna, Chief, Plant Licensing Branch No. 1-2 (LPL1-2), DORL John Lamb, Seabrook Project Manager, LPL 1-2, DORL Michael Marshall, Chief, Aging Management of Structures, Electrical and Systems Branch, DLR Dennis Morey, Chief, Aging Management of Reactor Systems Branch, DLR Chris Regan, Chief, Reactor Inspection Branch (IRIB), DIRS Bill Cartwright, Engineer, IRIB, DIRS Harold Chernoff, Chief Operating Experience Branch, DIRS Anthony Mendiola, Chief, Licensing Processes Branch (PLPB), DPR Holly Cruz, Project Manager, PLPB, DPR
CHARTER FOR THE SEABROOK ALKALI-SILICA REACTION ISSUE TECHNICAL TEAM
Background:
Alkali-silica reaction (ASR) adversely impacts the physical properties of hardened concrete.
ASR is a slow chemical process in which the alkalis in the cement react, in the presence of water, with the susceptible silica contained in the concrete aggregate. The chemical reaction results in an alkali-silica gel that expands within the concrete conglomerate causing micro cracks. As the gel absorbs water, the micro cracks expand and cause a weakening of the concrete (affecting the compressive strength, tensile and shear strength, and elasticity modulus) and potentially the structural integrity of the reinforced concrete structures that house and support safety-related systems.
The NRC issued a Confirmatory Action Letter (CAL) Number 1-2012-002, dated May 16, 2012 (ADAMS Accession No. ML12125A172), which confirmed commitments by NextEra in regards to actions taken and planned to address the non-conforming ASR issue at Seabrook Station. The results of the NRC inspections to verify that NextEra had satisfactorily completed each CAL commitment are documented in NRC Inspection Reports 05000443/2012009, dated December 3, 2012 (ML12338A283), and 05000443/201210, dated August 9, 2013 (ML13221A172). The NRC closed the CAL in a letter to NextEra dated October 9, 2013 (ML13274A670).
NextEra initiated a large specimen testing program to determine the impact of ASR on concrete structures that is currently in progress at the University of Texas Ferguson Structural Engineering Laboratory (FSEL). Additionally, a Structures Monitoring and Assessment Program is being conducted at Seabrook Station to track the progression of ASR in affected reinforced concrete structures. The testing program was developed, in part, to support resolution of the open ASR-affected structures final operability determinations.
The NRC Seabrook ASR Issue Technical Team (SAITT) was established to provide coordinated agency oversight of NextEras activities to address this non-conforming condition.
Purpose:
To provide oversight and coordination of the NRC onsite inspections, in-office technical reviews, and other associated evaluation and assessment activities involving NextEras actions to resolve the ASR issues at Seabrook Station.
Objectives:
- a. To review and assess the results of the onsite ASR monitoring of ASR-affected reinforced concrete structures.
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- b. To monitor activities involving anchor, shear and lap splice test specimens at the FSEL and assess the results of remediation testing, if required.
- c. To ensure NextEra maintains compliance with its license as new information is gathered from the Structures Monitoring and Assessment Program or FSEL testing program.
- d. To ensure a coordinated review of any associated reports or licensing submittals made by NextEra regarding ASR-affected safety-related or important to safety structures.
- e. To ensure a coordinated review and assessment of the final operability determination and supporting engineering evaluation, including review of any associated corrective actions.
- f. To support agency review of the structures aging management program related to ASR.
- g. To support a coordinated review for all public and congressional inquiries related to ASR at Seabrook.
Functional Responsibilities:
- a. Provide updates to the Region I Administrator and NRR Office Director after key milestones are completed, and as requested.
- b. Convene team meetings, as necessary, to review licensee progress, assess key test results and structural monitoring program observations.
- c. Ensure documentation of significant SAITT findings, observations, and decisions in NRC Inspection Reports, as appropriate.
- d. Prepare for and conduct public outreach activities, as appropriate. Maintain the Seabrook Concrete ASR Degradation public webpage up-to-date:
http://www.nrc.gov/info-finder/reactor/seabrook/concrete-degradation.html.
- e. Make recommendation to the Regional Administrator (RI) and Director (NRR) to dissolve the SAITT upon satisfactory completion of the above stated objectives.
THIS CHARTER IS APPROVED FOR IMPLEMENTATION ON February 18, 2014
/RA/ /RA by Jennife Uhle for/
William M. Dean Eric J. Leeds Regional Administrator Director Region I Office of Nuclear Reactor Regulation
ATTACHMENT SAITT Membership Chairman: Mel Gray, Branch Chief, DRS, RI Vice Chairman: William Cook, SRA, DRS, RI Members: Anthony McMurtray, Branch Chief, DE, NRR Meena Khanna, Branch Chief, DORL, NRR Michael Marshall, Branch Chief, DLR, NRR Chris Regan, Branch Chief, DIRS, NRR Glenn Dentel, Chief, Projects Branch 3, DRP, RI Additional Guidance A quorum for acceptance of recommendations or actions developed by lead offices or branches in primary support for the project will consist of the Chairman or Vice Chairman and all other members or their designated alternates from the applicable Division. Other participants may include staff from NRO, RES, and other offices, as necessary.
Region I Division of Reactor Safety has the responsibility for the team leadership, as assigned by the Regional Administrator. A meeting summary email will capture significant team activities, discussions, and accomplishments. Informational management briefings should be conducted, as needed, or upon request.
The SAITT shall communicate licensing and technical issues to external stakeholders via public outreach activities, the NRC external website, or through the use of direct communication plans for documents being issued and for significant inquiries made through the use of other established correspondence avenues (e.g., email, facsimile, telecon, etc).
When an office is in a support role, the SAITT will ensure coordination of activities in order to provide the timely completion of due dates for the lead office.
The SAITT will review the results of activities of the lead office 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 documentation.
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