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Attachment 3 - RES Staff Presentation Handout Materials NRC-RES/Doe/EPRI Coordination Meeting NRC Headquarters, Church Street Building Wednesday, May 26, 2010
	ML101740528
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Issue date:	05/26/2010
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	Hudson D, RES/DRA, 301-251-7919
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06/10/2010 1

NRC Long Term Research Plan

Long-term regulatory research is forward-looking regulatory research performed to provide fundamental insights and technical information, or address potential technical issues or identified gaps in support of issues or identified gaps in support of anticipated future (greater than 5 years)

NRC needs.

Long-term Research Process Developed through a variety of means:

- solicitation of research ideas from staff and solicitation of research ideas from staff and management from each of the program offices and RES

- review of existing topic-specific and program-specific research plans from both NRC and external organizations

- review of selected reports on NRC research activities

- inputs from external stakeholders including other government organizations, industry groups, and several of the national laboratories

Review Committee comprised of SLS RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 2

LTRP Review

Prioritize proposals using criteria and i hti f

t b l weighting factors below

- Leveraging resources (10%)

- Advancing state-of-the-art (30%)

- Providing independent tool (10%)

- Applying to more than one area (20%)

Applying to more than one area (20%)

- Addressing gaps created by technology (30%)

FY2012 Priorities

- Advanced Reprocessing S

t G id I t

NPP

- Smart Grid Impacts on NPPs

- Safety and Regulatory Issues of the Thorium Cycle RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

5/25/2010 1

Status Update: License Renewal Beyond 60 Proactive Management of Materials Degradation Stuart Richards, Deputy Director Division of Engineering 1

License Renewal Beyond 60

Tasked by NRRs Division of Component Integrity tasked to:

- hold recurrent NRC/industry workshops on status of operating y

p p

g experience and industry research activities to address aging management technical issues for subsequent license renewal period (Life Beyond 60, LB60)

- develop an expanded materials degradation assessment to verify aging assumptions for LB60

- assess results from implementation of license renewal aging management programs and recommend improvements for LB60

- continue to develop domestic and international partnerships to share expertise capabilities and resources related to aging share expertise, capabilities, and resources related to aging management research for long-term operation

- identify degradation scenarios not addressed in the currently available generic aging lessons learned (GALL) report

- summarize inspection and monitoring programs for highly likely degradation scenarios 2

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

5/25/2010 2

License Renewal Beyond 60 (contd)

Areas of collaboration

- EPRI MOU addendum (April 30, 2010)

cooperative aging management R&D program in NPP long-term operations in second, and subsequent, license renewal periods beyond 60 years ("Life Beyond 60")

- DOE MOU addendum (in concurrence)

cooperative aging management R&D program in NPP LTO in second, and subsequent, license renewal periods beyond 60 years ("Life Beyond 60 & LWR Sustainability Program)

- International collaborations te at o a co abo at o s

International Forum for Reactor Aging Management (IFRAM)

Timeline

- 2009 through 2013 3

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

5/25/2010 1

Status Update: Neutron Material Absorber Degradation Mirela Gavrilas Division of Engineering Neutron Absorbing Materials in Spent Fuel Pools

user need from NRRs Division of Component Integrity (presently in concurrence) create a knowledge base of neutron absorbing materials in

- create a knowledge base of neutron absorbing materials in spent fuel pools

- if necessary, confirmatory research on surveillance methodology effectiveness

- if necessary, confirmatory research on surveillance interval adequacy

areas of collaboration with EPRI

- industry data industry data

- technical expertise to address materials performance and surveillance issues

timeline

- now through 2012 RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

1 NeutronAbsorberDegradation-status

RES/DE has the lead on this issue, although RES/DSA is following RES/DEhastheleadonthisissue,althoughRES/DSAisfollowing theissuecloselyincaseneutronics issuessurface

MOUhasbeenestablishedbetweenRESandEPRItoshare information

Atthelastpublicmeeting(Category2on05.06.10inBaltimore, Maryland)NRRtooktheactiontoreviewEPRIresearcheffortsto minimize duplication of research efforts This analysis will feed minimizeduplicationofresearchefforts.Thisanalysiswillfeed intothefinalUserNeedtoRES NeutronAbsorberDegradation-status

NRC interest in how EPRI will handle the issue of limited SFP NRCinterestinhowEPRIwillhandletheissueoflimitedSFP couponsandextendedplantlifetimes

NRCalsointerestintheEPRIdatabasethatwillhousedetailed informationfromallutilitiesSFP.Detailssuchascoupon destructiveanalysisdatatothetypesofmaterialsinuse.

Industry(EPRI)hasfocusedtheirresearcheffortstoBORAL, howeverNRRinterestsaremorebroadandinclude Carborundum,Metamic,Boraflex,etc.

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

2 NeutronAbsorberDegradation-status

The RES User Guide in development is foreseen to consist of 4 TheRESUserGuideindevelopmentisforeseentoconsistof4 parts:Aliterarysearch,confirmatoryresearchonsurveillance methodology,confirmatoryresearchonsurveillanceintervaland livingknowledgebaseforthepreviousareas RESUserNeedisexpectedtobeinplacebyJuly10 RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

SFST/RES Quaterly Meeting 1

Burnup credit-status Extension of Technical Basis for BUC in PWR SNF Casks [NMSS 2005-003] Fission Products Credit NMSS/RES/NRR/NRO offices to coordinate ORNL work that will yield a consistent approach to spent fuel criticality safety analysis

- Evaluation of the French FP critical experiments (received from AREVA in August 2009)

- Develop the technical basis revision to ISG-8 Rev. 2 to include FP credit Burnup credit-status Extension of Technical Basis for BUC in SNF Casks [NMSS 2005 ExtensionofTechnicalBasisforBUCinSNFCasks[NMSS2005 003] - ConfirmationofSpentFuelBurnup Values{poolside measurementsrequirement}

- NUREG/CR6998,ReviewofInformationforSpentFuelBurnup Confirmation,ML100210543(PublishedinJanuary2010)

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

SFST/RES Quaterly Meeting 2

Burnup credit-status ExtensionofTechnicalBasisforBUCinSNFCasks[NMSS 2005003] FissionProductsCredit FissionProductsConsidered:

- Rh103,Cs133,NdNat,Sm149,Sm152,andGd155

- Provide~20%oftotalBUC PubliclyavailableFPdata:Sm149andRh103 Basisforuncertaintypropagationmethod Frenchdatatobeusedfor internal method confirmationonly.

Burnup credit-status ExtensionofTechnicalBasisforBUCinSNFCasks[NMSS2005 003] Fission Products Credit 003]FissionProductsCredit

- Developanopenapproachthatdeterminesbiasesandbias uncertaintiesbasedonpropagationofnucleardata uncertaintiesusingpubliclyavailabledata[inadditionto thefullactinideBUC]andpublishtheresults Use the French proprietary data to support or qualify the

- UsetheFrenchproprietarydatatosupportorqualifythe openapproach(toprovideaddedconfidencetoNRConthe openapproach)

- IssueISG8Rev.3forfullBUCforPWR (byendof2010)

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

5/25/2010 1

Status Update: Extended Dry Storage Stuart Richards, Deputy Director Division of Engineering 1

Extended Dry Storage In February, 2010, the Commission directed the staff to review the regulatory programs for spent fuel storage and transportation to evaluate their adequacy for ensuring safe and secure storage and transportation beyond 120 years.

The staffs review should identify risk-informed, performance-based enhancements that will bring increased predictability and efficiency to the regulatory processes.

The staff should develop a project plan for Commission approval.

The staff is currently working on the project plan.

The staff is participating on the EPRI/DOE dry storage working The staff is participating on the EPRI/DOE dry storage working group Present research includes casks in a marine environment; modeling of cask drop tests; testing of high burnup fuel for material properties; and fuel burnup credit for storage.

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 1

Integral Pressurized Water Reactors (iPWRs)

In U.S. NRC Pre-application Review Reactor Primary Circulation NuScale IRIS mPower Current Pre-application activities

Supporting NRO in review of available vendor information - identify knowledge gaps, need for PIRTs, information identify knowledge gaps, need for PIRTs, inhouse code/model dev. needs

TRACE generic iPWR model developed

Evaluation of iPWR Design Issues that could affect TRACE model

MELCOR generic iPWR model under development MELCOR generic iPWR model under development

Reviewing currently available vendor information to identify transient analyses of interest.

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 2

TRACE Model for a Generic iPWR Nodalization of generic iPWR Nominally based on NuScale Examples of technical issues to be addressed

Steam Generator Performance (ht. transfer performance, flow stability, ECC function)

- Helical steam generator Helical steam generator

Fuel and cladding performance for 2, 4, or greater years of operations - pressure build up in cladding, power

Spargers, valves, and core to containment venting

I&C and In-Service Inspection of components integrated internal to reactor vessel g

Natural circulation and passive core cooling capability and performance RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 3

Potential Experimental Facilities for testing and obtaining experimental data

Proposed Integrated System Test Facility (B&W)

M lti A li ti S

ll Li ht W t R

t

Multi-Application Small Light-Water Reactor facility (MASLWR) at Oregon State University

Proposed SPES3 Experimental Facility for IRIS (1:100 scale)

When will proposed facilities be operational?

Availability for licensing and regulatory data needs?

Future efforts in preapplication phase (thermal-hydraulic and neutronics)

Continue review of vendor preapplication information and technical specifications as provided and technical specifications as provided.

Identify important transient analyses

Phenomena Identification and ranking Table (PIRT) analysis and/or gap assessment

Review in-house codes (e.g. TRACE & PARCS) code applicability assessement code applicability assessement

Develop and assess generic models and features necessary for iPWR analysis RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

1 Status Update on Seismic Methods Projects Dr. Annie Kammerer Division of Engineering CEUS SSC

Central and Eastern US Seismic Source Characterization for Nuclear Facilities developing a replacement for 20 year old EPRI-SOG seismic source database

Participation by NRC, DOE, EPRI and USGS. DNFSB and ACRS staff are also on the peer review panel.

Draft final project source model and report to be reviewed by agencies in August 2010, and finalized December 2010 2

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

2 NGA-East

Next Generation Attenuation Relationships for Eastern North America developing ground motion prediction North America developing ground motion prediction equations (GMPEs predict ground motions for an earthquake at a given magnitude and distance)

Participation by NRC, DOE, EPRI, and USGS. Multiple other groups are interested in also contributing (Army Corps GEM project Canadian Geologic Survey etc)

Corps, GEM project, Canadian Geologic Survey, etc)

Full project initiated in 2009 and will be finished in 2014 3

Ongoing Cooperation

NRC and EPRI staff have been discussing the lessons learned from Kashiwazaki.

- Analyzing the equipment in the KKNPP for incorporation into the Analyzing the equipment in the KKNPP for incorporation into the seismic experience database

- Structural response and SSI

- Restart criteria, Site Response, Instrumentation, etc.

NRC and EPRI staff have identified areas of mutual interest for future research based on the ANS Seismic PRA pilot for future research based on the ANS Seismic PRA pilot study

- Guidance on seismic fragility in Seismic PRA

- Joint probabilities of failure of similar equipment

- About 12 topical areas over all 4

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

1 1

GI-199 Status Update Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States on Existing Plants Christiana Lui Director, Division of Risk Analysis 2

Current Status

Safety/Risk Assessment Panel has met.

Report (with recommendations) is expected to be issued in June.

Preparing for high stakeholder interest.

A public meeting will be held after report issuance.

Efforts will continue.

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

2 Path Forward - Approach to Resolution

Obtain additional information in order to prioritize plants for evaluation of potential plant-specific backfits.

Develop a method to assess potential backfits for Seismic Margins Analysis (SMA) plants.

Perform plant-specific backfit analyses, as applicable.

Long term, establish a mechanism to routinely assess implications of any new seismic hazard estimates or other seismic information.

3 RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 1

NRC Systems Analysis Capability RES develops T/H &

Neutronics codes (TRACE, RELAP5, SNAP &

PARCS)

Conducts T/H Conducts T/H experimental programs to support code development Analyses used in regulatory decision-making TRACE Introduction TRACE/PARCS is the consolidated TH systems analysis code with 3D kinetics SNAP helps with input preparation and post processing TRACE use at the NRC:

New reactor licensing ESBWR, EPR, APWR, ABWR, AP1000 Operating reactor power licensing actions Power uprates Support of GSI resolution Support of GSI resolution Sump strainer blockage issue TRACE use outside NRC:

CAMP Program provides independent assessment and validation Domestic User Group RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 2

TRACE Applications

TRACE (and other T/H codes) are assessed and considered valid only over specific ranges and specific applications

TRACE is applicable to:

- Conventional PWRs (W 3-,4-loop, CE, B&W)

- Conventional BWRs

- ESBWR, ABWR, EPR, US-APWR, AP-1000

For scenarios involving:

For scenarios involving:

- LBLOCA

- SBLOCA

- Transients (AOO, ATWS)

- BWR Stability Future TRACE Development TRACE development and validation is driven by application needs:

application needs:

Physical Models

- Droplet Field to improve reflood and spray modeling

- Grid spacer models to predict heat transfer enhancement for reflood

- Interfacial Area Transport Numerical methods improvements

- Implicit numerical methods Validation of TRACE for new applications

- New reactor types, new accident scenarios Support for calculation of uncertainties RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 3

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 4

Ringhals Fundamental Stability Mode BWR Stability RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

1 1

Status Update on NRC/RES-EPRI Fire Risk Addendum Tasks Christiana Lui Director, Division of Risk Analysis Joint NRC/RES-EPRI Projects

Fire Events Database

Fire PRA Method Development &

Training

DC Circuit Hot Short Fire Testing Program

Fire Model Application Guide

Fire Events Human Reliability Analysis

Incipient Fire Detection Systems 2

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

2 3

Fire Events Database Status & Milestones

NPP fire event data last updated in 2000

RES initiated discussion with EPRI and NEI 2 years ago on obtaining updated data

Expect to start evaluating the latest data jointly late Summer or early Fall 2010 Fire PRA Methods Development &

Training

Joint publication of NUREG/CR-6850 (2005)

- Supplemental guidance based on FAQs (2009)

- Revision as the state-of-the-art advances

Continued joint training sessions

- Use of best experts available

- Alternate years hosting the sessions 4

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

3 5

DC Circuit Fire Testing

Invited EPRI to join test program

- EPRI made significant hardware and expertise contributions to project

Testing complete

EPRI will participate in

- Fire Effects on Cables PIRT

- Hot Shorting Expert Elicitation

- Scheduled for Fall 2010 6

Fire Model Application Guide

Joint RES-EPRI Report

- Draft NUREG-1934 issued for public comment in 2009

- Team is evaluating comments

- Expect significant revision to the report

- RES and EPRI added additional resources

- Expect new revision to be issued for public comment in Fall 2010 RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

4 7

Fire Events HRA

Joint RES-EPRI Report

- Draft NUREG-1921 issued for public comment in 2009

- Team is evaluating comments

- Expect team to resolve all comments and issue final joint report in 2010

- Fire HRA track will be added to Fire PRA Training program this year 8

Incipient Fire Detection

New Project

- FAQ developed during NFPA 805 pilots

- New use of technology

- Proposing a joint RES-EPRI team to perform the project RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

5/25/2010 1

Status Update: Extremely Low Probability of Failure (xLPR)

Dave Rudland Division of Engineering 1

Extremely Low Probability of Failure (xLPR)

Objectives:

- Develop a probabilistic assessment tool to assess compliance with the requirements of 10 CFR 50 Appendix A GDC-4.

with the requirements of 10 CFR 50 Appendix A GDC 4.

- Develop, verify, and validate a modular probabilistic computer code that explicitly models environmental degradation to evaluate primary piping system leakage, LOCA, and rupture probabilities.

Approach:

- Model environmental degradation such as stress corrosion cracking with current management strategies; e.g. NRC approved in-service inspection protocols and mitigation technologies.

NRC/EPRI MOU Addendum:

- Existing xLPR addendum valid through December 31, 2012

- Allows cooperative development of the xLPR probabilistic software tool benefiting both NRC and industry.

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

5/25/2010 2

xLPR: Bottom Line

%)

Primary Water SCC in Dissimilar metal welds obability Density (%

Pro Failure Frequency (Year -1) xLPR: Bottom Line

%)

Primary Water SCC in Dissimilar metal welds Primary Water SCC MitigationTechnologies obability Density (%

Change in risk Change in risk Pro Failure Frequency (Year -1)

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 1

Loss-of-Coolant Accident Research

Studsvik (NRC sponsored)

- Mechanical testing of ballooned and burst high burnup cladding.

ANL (NRC sponsored)

- Mechanical testing of ballooned and burst fresh and hydrided cladding.

Halden (Multilateral)

- In-reactor testing of high burnup fuel under LOCA conditions.

Reactivity-Initiated Accident Research

CABRI (Multilateral)

Ne CABRI Water Loop ill q alif the effects

- New CABRI Water Loop will qualify the effects of coolant temperature during RIA events.

NSRR (International)

- Continuing investigation into fuel behavior under narrow pulse width RIA conditions PNNL (NRC sponsored)

PNNL (NRC sponsored)

- Analytical models used to complement empirical limits in Appendix B of SRP-4.2 RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 2

Spent Fuel Research

ANL (NRC sponsored)

- Mechanical testing of high burnup and hydrided cladding.

ORNL (NRC sponsored)

- Mechanical testing of high burnup fuel and Mechanical testing of high burnup fuel and cladding materials.

Background

Staff identified need for contemporary cancer epidemiology information for responding to recurrent t k h ld stakeholder concerns

- The sentinel 1990 National Cancer Institute (NCI) report Cancer in Populations Living Near Nuclear Facilities

- Demographic changes in the last 20 years

- Limited cancer incidence information

- Does not include facilities operated after 1982

- Staff desire to reduce the county size study unit to something smaller 2

Selected National Academy of Sciences (NAS) to perform the study RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

06/10/2010 2

Study Objectives

Provide an up-to-date review of cancer incidence and mortality risk for populations living near past, present, and mortality risk for populations living near past, present, and proposed NRC-licensed nuclear facilities

The study is to be performed in two phases to start in summer 2010

Provide opportunities for stakeholder input during the study process NAS will establish a committee to develop a stand alone

NAS will establish a committee to develop a stand alone document recommending a study design and approach 3

RES STAFF PRESENTATION HANDOUT MATERIALS NRC-RES/DOE/EPRI COORDINATION MEETING NRC HEADQUARTERS, CHURCH STREET BUILDING WEDNESDAY, MAY 26, 2010 ATTACHMENT 3

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