NRC Plans for NESCC Concrete Specifications, Codes & Standards (SCS) Endorsement NESCC Meeting March 28, 2013 Richard Jervey USNRC Office of Regulatory Research, Department of Engineering, Regulatory Guide Branch 1 NRC’s Policies on Consensus Codes and Standards • Consensus codes and standards have been integral to the regulatory process for 3 decades • Codes and standards promote safe operation of nuclear power plants, improve effectiveness and efficiency of regulatory oversight • Federal law requires Government staff to use consensus standards where possible 2 NRC ‘Endorsement’ Processes Supported with a Legal basis • Rules / Regulations (10 CFR) • Regulatory Guides (RGs) Indeterminate legal standing (other than precedent) • • • • • • • Licenses (FSARs and DCDs)- licensee specific Safety Evaluation Reports (SERs)- licensee specific Inspection Procedures – NRC use Standard Review Plans (SRPs) – NRC use Generic Communications, RIS, IN, etc. Technical Reports (NUREGs) Letters & Memoranda 3 Regulatory Guides & SRPs • Regulatory Guides – Guidance to applicants - describes methods that the staff considers acceptable for use in implementing regulations – Large percentage of standards cited by NRC in RGs – Best repository of the current staff positions & standards • SRPs – Guidance to NRC staff (not an endorsement, per se) – Only updated intermittently, as determined by NRC offices needs 4 How to get NRC to review your SCS? • One process – Send a letter to the NRC Standards Executive (Mike Case); Reg Guide branch coordinates response across NRC offices – Issues: Reviewing is separate from endorsing; based on review, need NRC technical lead to initiate RG update; SRP only updated intermittently • Better process – Get an NRC representative to participate in developing the standard – Get an informal commitment from the NRC representative to consider the standard in a RG or SRP – Send a letter to the NRC Standards Executive – Issue: More likely to get NRC tech lead to initiate RG update 5 Generic Plan for Guidance Development Identify Regulatory Issue Receive SCS for Review Identify and Review Current Guidance No Further Action No Gaps found? Yes Determine appropriate Guidance and develop 6 NRC SCS Review Priorities • NRC believes the NESCC recommendations are worthy of support for each SDO. American Concrete Institute- ACI American Society of Mechanical Engineers-ASME American Institute of Steel Construction- AISC American National Standards Institute –ANSI National Fire Protection Association – NFPA American Society of Civil Engineers –ASCE • NESCC Concrete / NRC alignment -NRC Top ‘4’ ACI 349-12 -Code Requirements for Nuclear Safety-related Structures ACI 359-10 - Code for Concrete Containments ANSI/AISC N690-12 -Specification for Safety-Related Steel Structures for Nuclear Facilities ASCE 4.xx - Seismic Analysis of Safety Related Structures 7 NRC Work to support NESCC - Concrete • SCS related to Concrete is the first area NRC looked at for potential collaboration within NESCC project • Staff from the Reg. Guide Branch reviewed NIST/ANSI Concrete report recommendations – Reviewed the Identified Documents and where they stand in NRC plans – Discussed with NRC/RES management • Identified key reviews and schedule 8 Planned Reviews of Concrete SCS • Goal is to consider needs as identified in the NESCC report for collaborative opportunities • Timeline for ACI 349-2012 review, – (includes 51 ASTM Docs) • AISC N690-201X with draft Appendix N9 review, – (includes 84 SCS) and • Specifications, codes and standards referenced within each 9 American Concrete Institute ACI 349 • ACI 349, Code Requirements for Nuclear Safety-Related Concrete Structures • NRC currently endorses ACI 349-1997 (with exceptions) in RG 1.142, R2, dated 11/2001 • Current ACI 349 is 2006 issue with commentary including significant changes worthy of review. • Plan is to review/endorse the proposed ACI 349-2012 and ASTM standards in RG: 1.142 R3 10 RG 1.142 Plans • NRC participating in development – Currently in process • DG to go through internal NRC review – Following 349-12 publishing. (1QFY14?) • Publish DG with 60 day comment period – Likely 6 months following publishing • Incorporation of comments and ACRS review – Typically 2-6 months following end of public comment period • Issue final RG – Total time approximately 1 year following publishing the guide 11 AISC N690-2006 and Appendix N9 • NUREG-0800 is the SRP for Nuclear Power Plants, DCD for the AP1000 as well, currently refers to:N6901994 including Supplement 2 (2004), • Current N690-2006 (and 2011) has ANSI/AISC 360-10, Specification for Structural Steel Buildings, as the baseline document (instead of standalone document) • Use of LRFD approach (with ASD as an alternative) which is consistent with the code for concrete structures (ACI-349) • Planned Standard for Modular Composite Construction (SC) (Appendix N9) – A concurrent review of Appendix N9, Standard for Modular Composite Construction (SC) is ongoing – Also comparing with International standards – Plan to issue a new RG 1.225 “Safety-Related Steel and SteelConcrete Composite Structures (Other than reactor vessels and containments)” would like it to include App. N9 12 RG 1.225 Rev. 0 Plans • Ongoing NRC participation in development, and concurrent review • 3rd party review complete by – 4QFY13 • DG-1304 to go through internal NRC review – (incorporate draft App. N9) – 1QFY14 • Publish DG-1304 with 30-60 day comment period – 1QFY14 • Incorporation of comments and ACRS review – (variable) • Issue final RG – 2Q-3QFY14 13 NRC SCS Review Normal Review Process • NRC reviews the Reg. Guide library in a 5 year cycle. 3 outcomes: – Acceptable-As-Is – Revise, or – Withdraw • Upcoming reviews include guides which reference numerous SRS 14 Related Seismic Regulatory Guides and SCS • 1.122- Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components (1978) 10CFR50, App. A Criteria 2; Peak response spectra analysis • 1.132-Site Investigation for Foundations of Nuclear Power Plants (2003) 10CFR100, Subpart B Reactor Site Criteria; RG covers Detailed site investigations; borings; rocks and soils etc. RG references ASTM, ASCE US Army COE • 1.198 -Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites (2003) 10CFR100.23 Analysis of soli liquefaction • 1.199-Anchoring Components and Structural Supports in Concrete (2003) ASCE Army COE, Etc. 15 Questions? • ??? • Contact Rick Jervey @ 301-251-7404, or, richard.jervey@nrc.gov • Regulatory Guide Comment Portal http://www.nrc.gov/reading-rm/doccollections/reg-guides/contactus.html 16