NESCC 13-027 - American National Standards Institute

Report
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
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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,
[email protected]
• Regulatory Guide Comment Portal
http://www.nrc.gov/reading-rm/doccollections/reg-guides/contactus.html
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