ML17254A752
| ML17254A752 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/06/2017 |
| From: | Dan Dorman, Brian Holian Office of Nuclear Reactor Regulation, Region 1 Administrator |
| To: | Office of Public Affairs, Division Reactor Projects I, Division of Reactor Safety I, Region 1 Administrator |
| Gray M | |
| References | |
| Download: ML17254A752 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD.
KING OF PRUSSIA, PA 19406-2713 September 6, 2017 MEMORANDUM TO: Those on the Attached List FROM: Brian E. Holian, Acting Director /RA/
Office of Nuclear Reactor Regulation (NRR)
Daniel H. Dorman, Regional Administrator /RA/
Region I
SUBJECT:
SEABROOK ALKALI-SILICA REACTION ISSUE TECHNICAL TEAM CHARTER REVISION 2 The enclosed Revision 2 to the Seabrook Alkali-Silica Reaction (ASR) Issue Technical Team (SAITT) charter defines the purpose and objectives of the team. The background section of the charter has been revised to reflect (1) NextEras completion of large-scale concrete specimen tests at the Ferguson Structural Engineering Laboratory (FSEL) at the University of Texas -
Austin, (2) NextEras submittal and NRC acceptance for review of a license amendment request (LAR) (ML16216A240) to address ASR affected structures and the current licensing basis, and (3) NextEras submittal of revised license renewal application (LRA) sections for aging management programs (AMPs) including structures monitoring, ASR and building deformation (ML16362A283). The LAR and LRA submittals are under review by the NRC staff. Region I inspectors continue to perform baseline inspections to assess NextEras performance to ensure the capability of Seabrook structures affected by ASR.
The SAITT charter objectives have also been updated. Objective (b) associated with NRC monitoring of testing at FSEL has been marked complete because this objective was fulfilled and the results of NRC monitoring were documented in NRC inspection and audit reports.
Objectives (d) and (f) related to staff review of ASR related documents were combined and updated to specifically reference coordination of both NRC inspections and staff reviews of the ASR specific LAR and LRA submittals. Finally objective (e) was retained (and renumbered) related to review and assessment of operability determinations as was objective (f) involving coordination of stakeholder communications.
No changes were made to SAITT functional responsibilities. SAITT membership was updated to reflect staff changes in these positions. Additionally, guidance on quorums and decisions was removed to reflect the SAITT coordination role now that both the LAR and LRA regulatory review processes are in progress for this issue.
Docket No. 50-443
Enclosure:
SAITT Charter CONTACT: Mel Gray, Region I/DRS 610-337-5209
ML17254A752 Non-Sensitive Publicly Available SUNSI Review Sensitive Non-Publicly Available OFFICE RI/DRS RI/DRS RI/DRP RI/DRS DORL/DD NAME WCook MGray FBower RLorson/JTY for ABoland*
DATE 03/16/2017 03/20/2017 03/22/2017 04/11/2017 05/24/2017 OFFICE DE/DD DIRS/DD DLR/DD RI/RA NRR/D NAME JLubinski* CMiller* GWilson* DDorman BHolian*
DATE 05/25/2017 07/05/2017 06/09/2017 08/11/2017 09/06/2017
- = Concurrence via email Memorandum to Those on the Attached List dated September 6, 2017
SUBJECT:
SEABROOK ALKALI-SILICA REACTION ISSUE TECHNICAL TEAM CHARTER REVISION 2 ADDRESSEES:
Region I (RI)
Daniel Dorman, Regional Administrator David Lew, Deputy Regional Administrator Ray Lorson, Director, Division of Reactor Projects (DRP)
Jimi Yerokun, Director, Division of Reactor Safety (DRS)
Blake Welling, Deputy Director, DRS Fred Bower, Chief, Reactor Projects Branch 3, DRP Paul Cataldo, Senior Resident Inspector, Seabrook, DRP Peter Meier, Resident Inspector, Seabrook, DRP William Cook, Senior Reactor Analyst (SRA), DRS Mel Gray, Chief, Engineering Branch 1, DRS Niklas, Floyd, Reactor Inspector, DRS Diane Screnci, Office of Public Affairs (OPA)
Neil Sheehan, OPA Jonathan Greives, State Liaison Office (SLO)
Doug Tifft, SLO Office of Nuclear Reactor Regulation (NRR)
Brian McDermott, Dep. Director for Engineering, NRR Mirela Gavrilas, Director, Division of Safety Systems (DSS)
Anne Boland, Director, Division of Operating Reactor Licensing (DORL)
John Lubinski, Director, Division of Engineering (DE)
George Wilson, Director, Division of License Renewal (DLR)
Chris Miller, Director, Division of Inspection & Regional Support (DIRS)
Louis Lund, Director, Division of Policy and Rulemaking (DPR)
Brian Wittick, Chief, Structural Engineering Branch (ESEB), DE James Danna, Chief, Plant Licensing Branch No. 1 (PL-I), DORL Justin Poole, Seabrook Project Manager, PL-I, DORL Sheldon Stuchell, Chief, License Renewal Projects Branch, DLR Shaun Anderson, Acting Chief, Reactor Inspection Branch (IRIB), DIRS Harold Chernoff, Chief, Operating Experience Branch, DIRS
1 CHARTER FOR THE SEABROOK ALKALI-SILICA REACTION ISSUE TECHNICAL TEAM (Revision 2)
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 in 2013 to determine the impact of ASR on concrete structures at the University of Texas Ferguson Structural Engineering Laboratory (FSEL). This testing and associated test reports (ML16216A241 and ML16216A242) were completed in July 2016 and were used in support of amendments to the Seabrook license renewal application (LRA), and for development of an ASR license amendment request (LAR) to support resolution of the open ASR-affected structures final operability determinations.
In 2014, the NRC documented findings involving discrete, horizontal cracking in an internal wall of the Residual Heat Removal (RHR) vault and displacements and cracking associated with the Fuel Storage Building. In 2015, the NRC documented findings that identified global bulk expansion of the containment enclosure building. The staff concluded these findings were of very low safety significance because the safety function of these structures was not affected.
As part of the LRA process, the NRC requested additional information from NextEra to assess whether the effects of aging involving building deformation and discrete cracks will be adequately managed so that intended functions are maintained consistent with the current licensing basis during the period of extended operation. NextEra's response was received by the NRC on Aug. 9, 2016, and is currently under review. The response described that NextEra is conducting a Structures Monitoring and Assessment Program at Seabrook Station to track the progression of ASR in affected reinforced concrete structures.
On August 1, 2016, NextEra submitted a License Amendment Request (ML16216A240) to revise the Seabrook Updated Final Safety Analysis Report (UFSAR) to include methods for analyzing seismic Category I structures with concrete affected by ASR.
The NRC Seabrook ASR Issue Technical Team (SAITT) was established to provide coordinated agency oversight of NextEras activities to address this non-conforming condition.
2
Purpose:
To facilitate 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 support review and assess the results of the onsite ASR monitoring of ASR-affected reinforced concrete structures.
- b. To monitor activities involving anchor, shear and lap splice test specimens at the FSEL and assess the results of remediation testing, if required. Completed - July 2016.
- c. To ensure NextEra maintains compliance with its license as new information is gathered from the Structures Monitoring and Assessment Program.
- d. To support region based inspections and NRC staff review of NextEras LAR (ML16216A240) dated August 1, 2016, along with LAR supporting documents (ML16216A250), and LRA submittals associated with ASR-related aging management programs described in a submittal dated December 23, 2016 (ML16362A283).
- e. To ensure a coordinated review and assessment of the operability determinations and supporting engineering evaluations, including review of any associated corrective actions.
- f. To support a coordinated review for all public and congressional inquiries related to ASR at Seabrook.
Functional Responsibilities:
- a. Provide updates to Divisional management, 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 and assess structural monitoring program observations.
- c. Ensure documentation of significant SAITT findings, observations, and decisions in NRC Audit and 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 a recommendation to the Regional Administrator (RI) and Director (NRR) to dissolve the SAITT upon satisfactory completion of the above stated objectives.
3 SAITT Membership: (As of issuance of this Charter, Revision 2)*
Chairman: Branch Chief, EB1, DRS, RI (Mel Gray)
Vice Chairman: Senior Reactor Analyst, DRS, RI (William Cook)
Member Positions: Branch Chief, DE, NRR (Brian Wittick)
Branch Chief, DORL, NRR (James Danna)
Branch Chief, DLR, NRR (Sheldon Stuchell)
Branch Chief, DIRS/IRIB, NRR (Shaun Anderson)
Branch Chief, Projects Branch 3, DRP, RI (Fred Bower)
- Note: Membership is incumbent upon position, not specific individuals THIS CHARTER IS APPROVED FOR IMPLEMENTATION ON September 6, 2017
/RA/ /RA/
Daniel H. Dorman Brian E. Holian Regional Administrator Acting Director Region I Office of Nuclear Reactor Regulation