ML110070231

NUREG/BR-0476, 2010 New Reactors Program.

ML110070231
Person / Time
Issue date:	12/31/2010
From:	Jasinki R Office of New Reactors
To:
Beltz G
References
NUREG/BR-0476
Download: ML110070231 (48)

Text

2010 NEW REACTOR PROGRAM Of"ce of New Reactors 2010 New Reactor Program l 1

Cover New reactor construction activity at the Vogtle site near Augusta, GA, with operating Units 1 and 2 in the background.

Photo courtesy of Southern Company

2010 NEW REACTOR PROGRAM Photo courtesy of Southern Company OFFICE OF NEW REACTORS

Table of Contents I. A Message from the Director 1 II. Overview 2 III. Activities and Accomplishments 6 New Reactor Licensing 7 Oversight 13 Advanced Reactor Program 21 International Cooperation 29 IV. A Look Ahead 30 V. At a Glance 32 2010 New Reactor Program l i

4 l 2010 New Reactor Program A Message from the Director In many ways, 2010 was a hallmark year for the New Reactor Program. It was a year characterized by significant activities and accomplishments in our core responsibility areas of new reactor licensing, vendor and construction inspections, the agencys Advanced Reactor Program, and our growing international cooperation. We were presented with a host of opportunities and met these challenges by maintaining our focus on teamwork, execution, and planning for and adapting to change.

This 2010 New Reactor Program annual review is designed to clearly convey the full array of activities completed and accom-plishments realized during the past year. While industry decisions required us to adjust some of our activities, the New Reactor Program moved in a timely and responsive way to appropriately balance its ever-increasing workload. The review is meant to provide our key stakeholders with accurate and useful information on our performance in 2010 and direction for the coming years.

The New Reactor Program continues to fulfill its mission to serve the public interest by enabling the safe, secure, and environmentally responsible use of nuclear power in meeting the Nations future energy needs. In fulfilling this mission, we recognize the importance of enhancing and facilitating openness and stakeholder involvement, as well as fostering an open and collaborative working environment.

During the past year, we continued to support and implement the U.S. Nuclear Regulatory Commissions goals for reactor standardization and enhanced safety. Our focus in 2010 and going forward is on conducting licensing reviews and construction oversight activities necessary to address industry plans for near-term construction and establishing the necessary regulatory framework and infrastructure for advanced reactor reviews. In addition, we will continue to leverage international insights and experience to enhance our design reviews and construction oversight program.

As we look forward to 2011 and beyond, mounting challenges and opportunities may further impact our workload, but our mission, vision of success, and top priority of safety will not change. We hope this annual review provides you with a thorough and thoughtful summary of the activities undertaken and the accomplishments achieved in the past year by the New Reactor Program, with the support of the agencys Region II Center for Construction Inspection, the Office of Nuclear Regulatory Research, the Office of Nuclear Security and Incident Response, the Office of Nuclear Reactor Regulation, and the Office of the General Counsel.

Michael R. Johnson Director Office of New Reactors 2010 New Reactor Program l 1

Overview Photo courtesy of Southern Company Top, Batch Plant #1 at the Vogtle site.

Above, NRO Senior Geologist Dr. Gerry Stirewalt, center, reviews the geologic features of the V.C. Summer Unit 2 nuclear island rock with South Carolina Electric and Gas geology consultants.

Right, NRO Director Mike Johnson, fourth from left, and other NRC staff members stand in front of the containment building at the con-struction site of the worlds first AP1000 reactor in Sanmen, China.

2 l 2010 New Reactor Program

The much-anticipated and often-written about world- In 2010, the staff continued to review design certifica-wide nuclear resurgence is underway. Throughout the tion applications for three new designs and two amend-year, the U.S. Nuclear Regulatory Commission (NRC) ments to previously certified designs. During the year, continued to serve as the Nations nuclear safety regu- the staff completed the technical reviews and prepared lator to meet the growing challenges generated by the the rulemaking packages for concurrence for the resurgence. Advanced Passive 1000 (AP1000) Design Certification Amendment application and the Economic Simplified Since its inception in 2006, the agencys Office of New Boiling-Water Reactor (ESBWR) Design Certification Reactors (NRO), located at the NRCs Headquarters application. By certifying nuclear reactor designs, the in Rockville, MD, has served the public interest by agency resolves the majority of safety review areas in enabling the safe, secure, and environmentally respon- a design certification rulemaking. When an applicant sible use of nuclear power in meeting the Nations submits an application for a new nuclear power plant future energy needs. Additionally, the agency estab- using one of the certified designs, the license applica-lished a dedicated construction inspection organization tion review can proceed more efficiently in a manner in its Region II office in Atlanta, GA, that carries out that ensures safety while minimizing unnecessary regu-construction inspection activities nationwide, including latory burden and delays.

both the day-to-day onsite inspections and the special-ized inspections as part of the agencys oversight of the Also during the past year, the NRC received two ap-construction of new nuclear power plants. The New plications for early site permits (ESPs), which address Reactor Program carries out its activities with sup- site safety, environmental impacts, and emergency port from the agencys Office of the General Counsel preparedness review areas and allows the holder to (OGC), the Office of Nuclear Security and Incident bank the site for a future plant.

Response (NSIR), the Office of Nuclear Regulatory Research (RES), the Office of Nuclear Reactor Regu- Oversight lation (NRR), the Office of Public Affairs (OPA), the In the Construction Oversight Subprogram, the Office of Congressional Affairs (OCA), and others. agency carefully monitored safety-related construc-tion that officially began at Vogtle Unit 3, near In 2010, NRO actively engaged in the review of Augusta, GA, with the start of engineered backfill numerous new reactor licensing applications and operations authorized under a limited work authori-continued to refine its construction inspection pro- zation (LWA) issued in March 2010. The NRC has gram. To date, the agency has received 18 applica- developed an inspection program and has put in tions to build and operate 28 new light-water reactor place the structure and procedures required to con-units. Of these, 12 applications for 20 units are under duct the new reactor construction oversight program active review by the NRC, while the remaining for ongoing and near-term construction activities.

applications have been suspended or deferred at the This includes inspection of an applicants activities request of the applicants. related to the inspections, tests, analyses, and ac-ceptance criteria (ITAAC). In addition, Region II Licensing has inspected portions of the Quality Assuance (QA)

All of the large, light-water reactor combined program, in accordance with the inspection proce-license (COL) applicants are using the one-step dures associated with LWA activities completed at licensing process specified in Title 10 of the Code the time of the inspection.

of Federal Regulations (10 CFR) Part 52, Licenses, Certifications, and Approvals for Nuclear Power The NRC staff continues to refine concepts for Plants, which is designed to provide more stability and ITAAC closure, as well as maintenance of closed predictability than the two-step process specified in ITAAC. It continues to hold regular public work-10 CFR Part 50, Domestic Licensing of Production shops to solicit input and to exchange views related and Utilization Facilities. This new licensing process to ITAAC completion, closure documentation, and resolves the safety and environmental review areas, as ITAAC maintenance. The staff is currently pursuing well as emergency preparedness and security review a proposed rulemaking to codify ITAAC mainte-areas, before a new nuclear power plant is constructed. nance-related requirements.

2010 New Reactor Program l 3

Overview Top, Reactor Operations Engineer Andrea Johnson answers an inquiry at a staff meeting.

Above, Division of Safety Systems & Risk Assessment (DSRA)

Deputy Director Mark Lombard discusses construction inspection at a Lunch & Learn seminar.

Right, Division of Construction Inspection & Operational Programs (DCIP) Director Glenn Tracy fields a question at a Commission meeting.

4 l 2010 New Reactor Program

Furthermore in 2010, NRO has continued to conduct technologies, the NRC and the Nuclear Energy Institute oversight of manufacturers and suppliers of safety-re- (NEI) have established and sponsored periodic work-lated components through the NRC Vendor Inspection shops to focus on the resolution of the generic issues Program. The staff conducted 11 vendor inspections, that face advanced reactor design.

6 QA implementation inspections, and 3 aircraft im-pact assessment inspections. International In addition to working on domestic issues for new reac-Advanced Reactors tor construction, the NRC has been a leader in cooper-During 2010, the NRC witnessed increased interest ating with other national nuclear regulatory authorities in the potential licensing of advanced reactor designs. to address new reactor design reviews and oversight of Although a wide range of these designs are being construction. The NRC is participating in an inter-discussed in the nuclear community, NROs Ad- national effort, the Multinational Design Evaluation vanced Reactor Program is focusing on preparing for Program (MDEP), to more effectively and efficiently the review of a high-temperature, gas-cooled reactor review new reactor designs. As part of this program, (HTGR) design in accordance with the Energy Policy NRC representatives communicate on a regular basis Act of 2005 (EPAct). Additionally, NRO is focused with the other members regarding the Evolutionary on the review of multiple integral pressurized-water Power Reactor (EPR) design review, the AP1000 design reactor (iPWR) designs. This focus will require signifi- review, vendor inspections, and specific regulatory and cant efforts on the part of the agency, NRO, and our technical review areas such as digital instrumentation external stakeholders. and controls.

Currently, the staff expects to receive its first design Progress in 2010 in each of these areasnew reactor certification application for an advanced reactor design licensing, oversight, advanced reactors, and interna-in the fiscal year (FY) 2012 timeframe. To fully engage tional cooperationare explored in more detail in the early in the review process of multiple nuclear reactor following pages of this publication.

Photo courtesy of Southern Company The construction of Vogtles Modular Assembly Building, located near Augusta in Burke County, GA., is underway.

2010 New Reactor Program l 5

Activities &

Accomplishments Top, General Engineer Eric Miller, hand raised, participates in a division meeting.

Above, from left to right, Justin Fuller, the senior resident inspector for Vogtle Units 3 and 4, Deputy Regional Administrator for Construc-tionRegion II, Loren Plisco, the agencys Executive Director for Operations, Bill Borchardt, and Tim Chandler, resident inspector for Vogtle Units 1 and 2, visit the site.

Right, Mike Johnson presents Electrical Engineer Tania Martinez-Navedo with the office Vision of Success Award.

6 l 2010 New Reactor Program

New Reactor Licensing

• Comanche Peak (TX)

• River Bend (LA)

One of NROs three subprograms or areas of major focus, the New Reactor Licensing Subprogram con-

• Nine Mile Point (NY) tinued to lead, manage, and facilitate design certifi-

• Bell Bend (PA) cation application reviews, ESP application reviews, COL application reviews and

• Turkey Point (FL) associated LWAs, and new reac- Activities under the New Applicants have withdrawn or tor preapplication activities. It also requested the agency suspend developed and maintained neces-Reactor Licensing Subprogram reviews of six applications: Grand sary technical and programmatic include planning and scheduling, Gulf, Victoria County Station, support for new reactor licensing Callaway, Nine Mile Point, River infrastructure development, activities, such as large-scale project Bend, and Bellefonte. The Victoria management tools, scheduling and environmental reviews, technical County Station COL application resource planning and tracking, safety reviews, and proper was withdrawn and submitted as and guidance development. The an ESP application in FY 2010.

New Reactor Licensing Subpro- management of new large, light-gram also had the lead for interac- water reactor activities in support The New Reactor Licensing tions with stakeholders on issues Subprogram expects to complete pertaining to new large, light-water of licensing and rulemaking to the technical review of the first reactors. include design certification few COL applications in the The NRC started to receive new application reviews, early site permit FY 2011 and FY 2012 timeframe.

In FY 2010, no COL applications large, light-water reactor license application reviews, combined were submitted.

applications in 2007. These appli- license application reviews, cations were submitted to the NRC To obtain information on the cur-under 10 CFR Part 52. As of the interaction with stakeholders, rent review schedule for new reac-end of 2010, the NRC had received and new reactor preapplication tor COL applications, access the a total of 18 COL applications to NRC public Web site at: http://

build and operate 28 new reactors activities. Staff conducts these www.nrc.gov/reactors/new-reac-at the following sites: activities in a manner that develops tors/col.html.

trust and is consistent with NRC

• Calvert Cliffs (MD) To date, the NRC has issued four organizational values. ESPs to the following applicants:

• South Texas Project (TX)

• Bellefonte (AL)

• System Energy Resources, Inc. (Entergy), for the Grand Gulf site in Mississippi

• North Anna (VA)

• Exelon Generation Company, LLC, for the Clinton

• William States Lee III (SC) site in Illinois

• Shearon Harris (NC)

• Dominion Nuclear North Anna, LLC, for the

• Grand Gulf (MS) North Anna site in Virginia

• Vogtle (GA)

• Southern Nuclear Operating Company, for the Vogtle site in Georgia (includes an LWA)

• V.C. Summer (SC)

In 2010, the NRC received ESP applications from

• Callaway (MO) Exelon Nuclear Texas Holdings (Exelon) for the

• Levy County (FL) Victoria County Station site, located in Victoria County, TX, and PSEG Power, LLC, and PSEG

• Victoria County Station (TX) Nuclear, LLC (PSEG) for the PSEG site (the Salem and Hope Creek Generating Stations site) located

• Fermi (MI) in Salem County, NJ. Both applications use the plant 2010 New Reactor Program l 7 Office of New Reactors l 7

Activities &

Accomplishments Top, NRO Materials Engineer Tim Steingass, seated, discusses the South Texas Project license application submittal with Mohammed Abid, a reactor engineer in Region III.

Above, NRO geologists and geotechnical engineers, along with Progress Energy Florida, Inc., consultants, examine core to ascertain the volume of cavities in the foundation rock at the Levy County site in Florida.

Right, members of the staff are recognized for their efforts on the issuance of the Vogtle Early Site Permit and Limited Work Authorization.

8 l 2010 New Reactor Program

parameter envelope approach (no design specified at

• Worked collaboratively across the agency toward this time) and were accepted for docketing. resolution of the technically challenging and highly visible issues related to the AP1000 shield building.

To obtain information on the current review schedule In addition, proactively employed a full range of for new reactor ESP applications, access the NRC regulatory tools including audits and public meet-public Web site at: http://www.nrc.gov/reactors/ ings to advance the review of technically complex new-reactors/esp.html. issues such as ESBWR hydrogen accumulation, sump strainer adequacy, and probabilistic risk To date, the NRC has issued design certifications assessment.

for four reactor designs that can be referenced in an

• Issued the final supplemental environmental impact application for a nuclear power plant. These designs statement for the North Anna COL application include the following: and the draft environmental impact statements for the South Texas Project, Calvert Cliffs, Comanche

• General Electric-Hitachi Nuclear Energys (GEHs)

Advanced Boiling-Water Reactor (ABWR) Peak, Levy, and V.C. Summer COL applications, and the supplemental environmental impact state-

• Westinghouses System 80+ ment for the Vogtle COL application.

• Westinghouses Advanced Passive 600 (AP600)

• Conducted environmental scoping meetings for

• Westinghouses AP1000 Turkey Point and Lee COL applications and Victoria County Station and PSEG ESP applications in accor-dance with the National Environmental Policy Act Currently, the NRC is reviewing the following design requirements outlined in 10 CFR Part 51, Environ-certification applications:

mental Protection Regulations for Domestic Licensing and Related Regulatory Functions.

• AREVAs U.S. Evolutionary Power Reactor (USEPR)

• Issued three license amendments, and associated

• Mitsubishi Heavy Industries U.S. Advanced environmental assessments and findings of no Pressurized Water Reactor (US-APWR) significant impact, for the Vogtle ESP and limited

• GEHs Economic Simplified Boiling-Water Reactor work authorization related to the limited scope (ESBWR) approvals for a subset of onsite locations for use of backfill material.

• Westinghouses AP1000 Design Certification Amendment

• Continued to develop and implement Enterprise

• South Texas Project Nuclear Operating Companys Project Management and developed schedule (STPNOC) ABWR design certification amendment improvement data quality initiative, including:

to address the aircraft impact rule (1) standardized project performance reporting; (2) centralized business intelligent database devel-The NRC did not receive any new large, light-water opment; and (3) provision of project management reactor design certification applications or new large, and earned value training to NRO staff, manage-light-water reactor design certification amendment ment, and project managers.

applications in FY 2010. To obtain information on the current review schedule for new reactor design

• Assessed the revised North Anna COL application certification and design certification amendment ap- that addressed the applicants change in reactor plications, access the NRC public Web site at: http:// technology from ESBWR to US-APWR tech-www.nrc.gov/reactors/new-reactors/design-cert. nology. The staff determined how it will proceed html. and began developing a new review schedule to accommodate the new technology for review of the In addition to continuing the review of 12 COL ap- North Anna COL application.

plications, three design certification applications, and

• Conducted various public meetings to maintain two design certification amendments, the New Reac- stakeholder awareness and technical understanding tor Licensing Subprogram accomplished the following of the status of new reactor technical activities in 2010: including meetings with Westinghouse on the AP1000 shield building review, with NEI on the aircraft impact assessment methodology, with 2010 New Reactor Program l 9

New Nuclear Power Plant Applications Updated December 20, 2010 Company (Project or Docket Numbers) Date of Design Date Site Under Consideration Number State Existing Status Application Accepted of Units Operating Plant New Nuclear Calendar Power Year Plant (CY) 2007 Applications Applications NRG Energy (52-012/013) 09/20/07 New ABWR Nuclear Updated Power December 11/29/07 Plant South Applications 20, Texas 2010Project 2 TX Y Accepted/Docketed Company (Project or Docket Numbers) Date of Design UpdatedDate December Under Site20, Consideration 2010 Number State Existing Status Company (Project or Docket Numbers) Application Date of Design Accepted Date Site Under Consideration of Units Number State Operating Existing Status UNISTAR (52-016) 07/13/07 (Envir.) EPR 01/25/08 Calvert Cliffs 1 MD Y Accepted/Docketed Application Accepted of Units Plant Operating 03/13/08 (Safety) Calendar 06/03/08 Year (CY) 2007 Applications Accepted/Docketed Plant NRG Energy Dominion (52-012/013)

(52-017) 09/20/07 11/27/07 ABWR ESBWR 11/29/07 Calendar 01/28/08 South North Year (CY) 2007 Texas Project Anna Applications 2 1 TX VA Y Accepted/Docketed 10 l 2010 New Reactor Program NRG Energy (52-012/013)

Duke (52-018/019) 09/20/07 12/13/07 ABWR AP1000 11/29/07 South 02/25/08 WilliamTexasLee Nuclear Project Station 2 TX SC Y N Accepted/Docketed UNISTAR (52-016) 07/13/07 (Envir.) EPR 2007 Total01/25/08 Number of Applications Calvert Cliffs= 4 1 MD Y Accepted/Docketed UNISTAR (52-016) 03/13/08 (Envir.)

07/13/07 (Safety) EPR 01/25/08 06/03/08 Calvert Total Number of Units =Cliffs 6 1 MD Y Accepted/Docketed Dominion (52-017) 03/13/08 (Safety) 11/27/07 ESBWR 06/03/08 Calendar 01/28/08 North Year (CY) 2008 Anna Applications 1 VA Y Accepted/Docketed Dominion Duke Progress (52-017)

(52-018/019)

Energy (52-022/023) 11/27/07 12/13/07 02/19/08 ESBWR AP1000 02/25/08 04/17/08 North Anna William 01/28/08 Harris Lee Nuclear Station 1 2 VA SC NC N Y Accepted/Docketed Duke (52-018/019)

Southern Nuclear Operating Co. (52-025/026) 12/13/07 03/31/08 AP1000 02/25/08 Number of Applications 2007 Total05/30/08 Vogtle Nuclear William Lee = 4 Station 2 SC GA N Y Accepted/Docketed South Carolina Electric & Gas (52-027/028) 03/31/08 2007 Total AP1000 Number Total Number 07/31/08 Applications of of Units = 6 = 4 Summer 2 SC Y Accepted/Docketed Progress Energy (52-029/030) 07/30/08 AP1000 Total Calendar Number Year 10/06/08 of (CY) 2008 Units Levy =6 Applications County 2 FL N Accepted/Docketed Progress Energy Detroit Edison (52-022/023)

(52-033) 02/19/08 09/18/08 AP1000 Calendar 04/17/08 ESBWR Harris Year (CY) 2008 11/25/08 Applications Fermi 2 1 NC MI Y Accepted/Docketed Progress Southern Nuclear LuminantEnergy (52-022/023)

Operating Co. (52-025/026)

Power (52-034/035) 02/19/08 03/31/08 09/19/08 AP1000 USAPWR 04/17/08 05/30/08 12/02/08 Harris Vogtle Comanche Peak 2 NC GA TX Y Accepted/Docketed Southern South Nuclear Carolina PPL Generation Operating Electric (52-039)& GasCo. (52-025/026)

(52-027/028) 03/31/08 10/10/08 AP1000 EPR 05/30/08 07/31/08 12/19/08 Vogtle Summer Bell Bend 2 1 GA SC PA Y Accepted/Docketed South Carolina Progress (52-029/030)

EnergyElectric & Gas (52-027/028) 03/31/08 07/30/08 AP1000 07/31/08 10/06/08 Summer Levy County 2 SC FL Y N Accepted/Docketed Detroit Energy ProgressEdison (52-029/030)

(52-033) 07/30/08 09/18/08 AP1000 ESBWR 10/06/08 11/25/08 Levy County Fermi 2 1 FL MI N Y Accepted/Docketed Detroit Edison Luminant Power(52-033)

(52-034/035) 09/18/08 09/19/08 ESBWR USAPWR 11/25/08 12/02/08 Fermi Comanche Peak 1 2 MI TX Y Accepted/Docketed Luminant PPL Generation (52-034/035)

Power(52-039) 09/19/08 10/10/08 USAPWR EPR 12/02/08 12/19/08 Comanche Bell Bend Peak 2 1 TX PA Y Accepted/Docketed PPL Generation (52-039) 10/10/08 EPR 2008 Total 12/19/08 Number of Applications Bell Bend = 7 1 PA Y Accepted/Docketed Total Number of Units = 12 Calendar Year (CY) 2009 Applications Florida Power and Light (763) 06/30/09 AP1000 09/04/09 Turkey Point 2 FL Y Accepted/Docketed 2008 2009Total TotalNumber Numberof ofApplications Applications==71 2008 Total Number Total TotalNumber Applications of of Number ofUnits Units==12 2 =7 Total Calendar Number Year of Units (CY) 2009 2010 = 12 Applications Florida Power and Light (763) 06/30/09 No Letters of Intent AP1000 have been receivedCalendar 09/04/09 from applicants Turkey 2009 Applications Year (CY)expressing their 2 Point plans to submit new COL applications Y FL in CY 2010 Accepted/Docketed Florida Power and Light (763) 06/30/09 AP1000 2009 Total09/04/09 2010 Number of Applications Turkey Point= 0 1 2 FL Y Accepted/Docketed 2009 Total Number Total Number Applications of of Units = 2 0 =1 Total Calendar YearNumber of Units 2010 (CY) 2011 =2 Applications Blue Castle Project No Letters of Intent have been received TBDfrom applicants Calendar Year (CY)expressing 2010 their plans to submit new COL applications Applications Utah 1 UT in CY 2010 N

Southern No Letters of Intent have been received 2010 TBD applicants fromTotal Numberexpressing of Applications TBD their=plans0 to submit new COL applications 1 in CY 2010 TBD Unnamed 2010 Total TBD Number Total Number Applications of of Units = 0 = 0 TBD 1 TBD Unnamed TBD Total Calendar YearNumber of (CY) 2011 Units =0 Applications TBD 1 TBD Blue Castle Project TBD Calendar 2011 TotalYear Utah (CY) 2011 Number Applications of Applications =4 1 UT N Blue Castle Project Southern TBD Total Number of Utah TBD Units = 4 1 UT N TBD Southern Unnamed 2007TBD

- 2011 Total Number ofTBD Applications = 21 1 TBD Unnamed TBD Total Number ofTBD Units = 30 1 TBD Unnamed TBD TBD 2011 Total Number of Applications =4 1 TBD 2011 Total Number Total Number Applications of of Units = 4 = 4

Mitsubishi Heavy Industries on digital instrumenta- alternating current power and ground water flow.

tion and control, and with AREVA on seismic design We also issued final interim staff guidance on issues. Also, the New Reactor Licensing Subprogram post-COL commitments, soil structure interac-staff conducted a meeting between the NRC and tion, and seismic margin analysis. Additionally, Westinghouse on the AP1000 shield building to the New Reactor Licensing Subprogram provided identify dates for specific tech- extensive technical expertise for nical meetings associated with the development and review of the testing and benchmarking technical guidance and rulemaking plans. NRO arranged a technical The New Reactor documents including: the Cyberse-meeting on test program setup curity Plan Template (NEI 08-09);

and criteria and analysis and Licensing Subprogram a draft NUREG/CR on seismic other followup meetings. tests of degraded piping; Regula-tory Guide (RG) 1.62, Manual

• Provided continued support to the also has lead for Initiation of Protective Actions; RG Advisory Committee on Reactor 1.65, Materials and Inspections for Safeguards. The staff proactively interactions with Reactor Vessel Closure Studs; and a employed a full range of regula-proposed rulemaking under 10 CFR tory tools to advance the review of technically complex issues stakeholders on issues 50.55a, Codes and Standards, to reflect changes in the American to assist the Commission with pertaining to new large, Society of Mechanical Engineers independent and timely technical (ASME) Code. We also issued RG advice on issues of public safety.

1.215, Guidance for Inspections, Staff participated in numerous light-water reactors. Tests, Analyses, and Acceptance audits and public meetings Criteria (ITAAC) Closure Under on topics including AP1000 10 CFR Part 52, for use in satisfying Generic Safety Issue (GSI)-191 the requirements for documenting and containment, USEPR realistic large-break the completion of ITAAC. In FY 2010, the New loss-of-coolant accidents and fuel design, ESBWR Reactor Licensing Subprogram finalized six interim hydrogen accumulation, US-APWR sump strainer, staff guidance documents and issued five interim ABWR spent fuel pool criticality and probabilistic staff guidance documents for comment.

risk assessment, and STPNOCs request to amend the ABWR design certification to comply with the

• Developed an approach to resolve alternate vendor aircraft impact assessment rule. Staff made consider- issues for ABWR Design Certification Rule rule-able progress on design certification and combined making issues and reach a resolution on how to treat license reviews and completed numerous safety the South Texas Project ABWR Aircraft Impact evaluation inputs and successful presentations to Assessment amendment (technical qualifications).

the Advisory Committee on Reactor Safeguards

• Developed and began implementation of a stream-on schedule to support published milestones. In lined approach for scheduling the ABWR aircraft FY 2010, the New Reactor Licensing Subprogram amendment rulemaking that targets a completion staff submitted 55 design certification safety evalu-date of August 2011. This will be the first rule-ation report chapters covering four design centers making prepared for a design certification amend-and 38 COL application chapters covering two ment project.

design centers to the applicants and to the Advisory Committee on Reactor Safeguards. The staff also

• Assembled rulemaking teams for AP1000 and presented 66 safety evaluation report chapters to the ESBWR design certifications and is in the process of Committee. preparing proposed rules for the design certification amendments and design certifications

• Issued interim staff guidance for comment on the in parallel with completion of the final safety design reliability assurance program, loss of large evaluation.

areas, gas accumulation, and standby emergency 2010 New Reactor Program l 11 Office of New Reactors l 21

Activities &

Accomplishments Top, employees participate in a simulated inspection at Vogtle as part of the ITAAC Closure and Verification Demonstration.

Above, DCIP Deputy Director John Tappert, right, and Branch Chief Juan Peralta lead a vendor inspection at a manufacturing facility in South Korea.

12 l 2010 New Reactor Program

Oversight additional inspections of operational programs to provide assurance that these activities and programs Construction Inspection Program are in compliance with program requirements.

The NRC conducts inspections of nuclear power The agency has put in place the structure and proce-plant construction activities to verify compliance dures required to conduct necessary oversight for on-with the agencys regulations and to ensure that the going and near-term construction activities. The pro-new plants are constructed in a way that protects cess for oversight of new reactor construction has been public health and safety and the environment. The documented in inspection manual chapters (IMCs)

NRC anticipated that future applicants of a nuclear and inspection procedures. All inspection procedures power plant will apply for a combined license under that are required to implement inspections of licensee 10 CFR Part 52 and has devel- activities related to ITAAC have been oped an inspection program for approved and issued for use. The NRC continues to make significant progress the construction activities of The NRC conducts in the development and improvement these plants. The new inspec-of programs and procedures to support tion program incorporates the oversight activities to ensure inspection of activities occurring later elements in 10 CFR Part 52, such as ITAAC, incorporates in construction. These include proce-lessons learned from the in- that a plant is constructed dures such as those required for inspec-spection program used in the tion of licensee operational readiness.

previous construction era (1970- in accordance with These remaining procedures are in 1980) for plants licensed under development and their planned com-10 CFR Part 50, and considers approved design and safety pletion in FY 2011 will fully support the inspection requirements for those modular construction at remote locations. applicants with the earliest construction regulations, to determine schedules.

The NRC inspection program provides for inspectors to track plant readiness for The NRC has begun executing con-and inspect construction activities struction inspection activities associated at the site. Most of the activities operations, and to ensure an with the Vogtle LWA. In March 2010, will be conducted by resident in- safety-related construction officially began at Vogtle Unit 3 with the start of spectors and supplemented with effective transition to engineered backfill operations authorized regional inspectors. It is expected that the peak resident staffing under the LWA. Safety-related activities will be around five inspectors at the Operating Reactor have also begun on Unit 4. NRC Region sites with one unit and seven at II construction inspectors were present to construction sites with two units. Oversight Program. view the initial activities and to begin the During construction, inspec- first onsite ITAAC inspection. Addition-tors sample the spectrum of the ally, Region II has selected the construc-applicants activities related to the ITAAC in the tion senior resident inspector and resident inspector for design-basis document to confirm that the applicant Vogtle and opened the resident office in the summer of is adhering to quality and program requirements. 2010.

The NRC staff will review all ITAAC closure letters to verify completion by the licensee, and will verify The NRC staff continues to refine concepts for ITAAC successful ITAAC completion on a sampling basis. closure and maintenance of closed ITAAC. The NRC NRC inspection results, together with the informa- staff conducted numerous public meetings over the past tion submitted by the licensee will be the foundation year to provide a forum for stakeholders to participate of the staff s recommendation to the Commission in in and comment on NRC staff proposals for ITAAC support of its finding on whether all ITAAC in the closure, ITAAC maintenance, and other construc-combined license have been met. The NRC will pub- tion inspection program issues. The NRC staff issued lish notices in the Federal Register of those ITAACs that RG 1.215 in October 2009. This guide endorses the have been completed. Inspectors will also perform industry guidance for ITAAC closure as documented in NEI 08-01, Revision 3, Industry Guideline for the 2010 New Reactor Program l 13 Office of New Reactors l 23

Photo courtesy of Southern Company Activities &

Accomplishments Top, Mechanical Engineer Yuken Wong and Pat Sekerak, a senior mechanical engineer, attend an All Hands Meeting for NROs Division of Engineering.

Above, construction work continues at Vogtle.

Right, NRO staff member, Chuck Rosselle, a management analyst, discusses coordination for the scheduling of multiple projects with Project Manager Mike Canova.

14 l 2010 New Reactor Program

ITAAC Closure Process Under 10 CFR Part 52, issued Vendor Inspection Program January 2009.

The NRC conducts oversight of manufacturers and The staff continues to hold regular public workshops suppliers of safety-related components through the NRC to solicit input and exchange views on issues related vendor inspection programs, which inspect compliance to ITAAC completion, closure documentation, and with QA and defect reporting requirements. Vendor ITAAC maintenance. The NEI, industry representa- inspections are conducted at manufacturers and suppli-tives, and other external stakeholders participate in ers shops principally to examine their compliance with these public workshops. Through these workshops, Appendix B, Quality Assurance Criteria for Nuclear the NRC staff has developed an enhanced approach Power Plants, to 10 CFR Part 50, of the Code of Federal to address ITAAC maintenance. The NRC staff is Regulations (10 CFR Part 50), as required by procurement currently pursuing a proposed rulemaking to codify contracts with licensees. Notices of Nonconformances ITAAC maintenance-related requirements and plans or Notices of Violations are issued to manufacturers and to issue a proposed revision to RG 1.215, shortly after suppliers for failures to meet quality commitments or the publication of the proposed rule. requirements of 10 CFR Part 21, Reporting of Defects and Noncompliance, respectively. In addition, the NRC Construction Reactor Oversight observes licensees oversight of manufacturers and sup-Process pliers. However, the primary responsibility for oversight rests with licensees, who typically perform their oversight A construction assessment process has been established audits through participation in the Nuclear Procurement and is in place as described in IMC 2505, Periodic Issues Committee.

Assessment of Construction Inspection Program Results, issued December 2009. This process was first As a result of the development of the enhanced implemented in July 2010 to assess licensee perfor- vendor inspection program in 2007, and within the mance related to construction activities at the Vogtle framework of IMC 2507, Construction Inspection site. The first assessment period will cover the time Program: Vendor Inspections, the NRO staff cur-between July 1, 2010, and June 30, 2011. rently conducts a minimum of 10 routine and reac-tive vendor inspections annually. Furthermore, the The Construction Reactor Oversight Process (cROP) staff plans for further expansion of the oversight of Working Group was formed in December 2009 to manufacturers and suppliers, based on the potential respond to Commission direction to develop construc- increase of activities within the nuclear industry as-tion assessment program options for its consideration. sociated with the construction of new plants. During Development efforts have been focused on the inclu- FY 2010, 11 vendor inspections, 6 QA implementa-sion in the Reactor Oversight Process (ROP) of objec- tion inspections, and 3 aircraft impact assessment tive elements such as construction program perfor- inspections were conducted.

mance indicators (PIs) and significance determination processes (SDPs) analogous to those used in the ROP. Vendor Inspections:

To date, the working group has developed a regulato-ry framework, including strategic performance areas October 14, 2010 and cornerstones, comprising objectives, attributes, Black and Veatch (B&V), Overland Park, KS and areas to measure. The working group continued Inspection of selected portions of B&Vs QA program to meet periodically with stakeholders during Category and 10 CFR Part 21 program.

II and III public meetings to solicit their input. It de-veloped a paper with assessment program options for September 29, 2010 Commission consideration. The assessment program Mangiarotti S.p.A., Sedegliano(UD) ItalyInspection will be updated based on Commission direction. of selected portions of Mangiarottis QA program and 10 CFR Part 21 program.

July 15, 2010 Sandvik Materials Technology (SMT), Sandviken, SwedenInspection of selected portions of SMTs QA program and 10 CFR Part 21 program.

2010 New Reactor Program l 15

Activities &

Accomplishments Top, employees enjoy discussion during a quarterly division meeting.

Above, NRO Deputy Director Gary Holahan, right, shares a laugh during a weekly program meeting.

Right, Branch Chief Terry Jackson, left, and his team perform an audit at CS Innovations in Phoenix, AZ.

16 l 2010 New Reactor Program

July 8, 2010 was technically qualified to engage in the proposed International Quality Consultants, Inc.(IQC), Butler, activities related to the amendment of the ABWR PAInspection of selected portions of IQCs QA design certification rule in accordance with the regu-program and 10 CFR Part 21 program. lations in 10 CFR 52.47, Contents of Applications; Technical Information.

May 3, 2010 Sulzer Pumps (US) Inc., Chattanooga, TN July 2010 Inspection of selected portions of Sulzers QA Westinghouse Electric Company - Purdue University program and 10 CFR Part 21 program. in West Lafayette, INInspection of the Westing-house Electric Company oversight and dedication of April 22, 2010 the testing conducted at Purdue University related to Shaw Nuclear Services, Charlotte, NC the design of the AP1000 shield building in accor-Inspection of selected portions of Shaws QA dance with the requirements of 10 CFR Part 21 and program and 10 CFR Part 21 program.

Appendix B to 10 CFR Part 50.

February 22, 2010 July 2010 DuBose National Energy Services, Inc., Clinton, Tennessee Valley Authority (TVA), Bellefonte Units NCInspection of DuBoses 10 CFR Part 21 3 and 4 COL applicationInspection of the imple-program.

mentation of the QA program and followup of the December 23, 2009 2008 NRC limited-scope inspection on the Simu-Namco Controls Corporation, Elizabethtown, NC lated Open Channel Hydraulic code to support the Followup inspection of selected portions of Namcos Bellefonte Units 3 and 4 COL application in ac-QA program and 10 CFR Part 21 program. cordance with the requirements of Appendix B to December 8, 2009 10 CFR Part 50 and 10 CFR Part 21 at the TVA Energy Steel and Supply Company, Lapeer, MI facilities in Chattanooga, TN.

Followup inspection of selected portions of Energy June 2010 Steels QA program and 10 CFR Part 21 program. Westinghouse Electric Company facility in Cranberry December 4, 2009 Township, PAAssessment of quality activities imple-Curtiss Wright Flow Control Company, Electro- mented to control use of a macro code used in the Mechanical Division (Curtiss Wright-EMD), Ches- design of nuclear island structures of AP1000 design.

wick, PAInspection of selected portions of Curtiss June 2010 Wright-EMDs QA program and 10 CFR Part 21 Progress Energy, Inc., Harris Units 2 and 3 COL program. applicationInspection of the implementation of November 16, 2009 the QA program to support the Harris Units 2 and Sumitomo Metal Industries, Ltd., Higashi-Mukojima 3 COL application in accordance with the require-Amagasaki, JapanInspection of selected portions ments of Appendix B to 10 CFR Part 50 and of Sumitomos QA program and 10 CFR Part 21 10 CFR Part 21 at the Progress Energy facilities in program. Raleigh, NC.

June 2010 Progress Energy, Inc., Levy County Units 1 and 2 Quality Assurance Inspections: COL applicationInspection of the implementa-tion of the QA program to support the Levy County Units 1 and 2 COL application in accordance with July 2010 the requirements of Appendix B to 10 CFR Part 50 STPNOC amendment application to the design and 10 CFR Part 21 at the Progress Energy facilities certification rule for the ABWRInspection of the in Raleigh, NC.

implementation of the QA program to support STP-NOCs amendment application in accordance with the requirements of Appendix B to 10 CFR Part 50 and 10 CFR Part 21 at the STPNOC facilities in Bay City, TX. An additional purpose of the QA imple-mentation inspection was to determine if STPNOC 2010 New Reactor Program l 17

Activities &

Accomplishments Top, with a new steam generator in the background, NRO and Region II employees, along with Japanese regulators, participate in a vendor inspection at a manufacturing plant in Kobe, Japan.

Above, Division of Site and Environmental Reviews (DSER)

Acting Deputy Division Director Rebecca Karas discusses career development with Luissette Candelario, a geotechnical engineer.

Right, NRO and Region II staff members gather at the V.C. Summer Unit 2 excavation site.

18 l 2010 New Reactor Program

On June 17, 2010, NRO hosted the 2nd NRC Work-shop on Vendor Oversight for New Reactor Construc-tion in New Orleans, LA. The workshop was widely attended and included discussions on such issues as vendor oversight for new reactors; the ASME nuclear survey process; the NRC enforcement policy as it ap-plies to vendors; counterfeit, fraudulent, or suspect items; and vendor insights on third-party oversight.

The workshop was attended by about 550 individu-als, representing companies and organizations from 11 countries. They included 233 vendors, 3 industry groups, 10 Government regulatory agencies, and 45 foreign and domestic utilities, including NRC license applicants (for design certification, COLs, and fuel cycle facility licenses).

Engineering Inspections:

The NRC staff is developing an effective and viable design acceptance criteria (DAC) inspection process, in-Photos courtesy of Southern Company cluding process framework and DAC inspection proce-dures. These criteria are defined as a set of prescribed limits, parameters, procedures, and attributes on which the agency relies, in a limited number of technical areas, to make a final safety determination to support a design certification. They are objective and must be verified as part of the ITAAC performed to demon-strate that the as-built facility conforms to the certified design. The staff expects to complete the inspection procedure by the end of 2010. It conducted the first inspection of the South Texas Project (STP) Units 3 and 4 Digital Instrumentation and Control DAC in May 2010. Concurrent with ongoing initiatives, an integration plan is under development to expand the working group charter beyond the STP effort, incorpo-rate elements of the STP initiative into a generic DAC inspection methodology, and set the stage for revisions to RG 1.215.

New reactor construction specialists complete tasks at the Vogtle site.

2010 New Reactor Program l 19

Activities &

Illustration courtesy of GE Hitachi Accomplishments Illustration courtesy of GE Hitachi Top, Project Manager Samina Shaikh presents an overview of the advanced reactor program at an office meeting.

Above, Power Reactor Innovative Small Module (PRISM) representation.

Right, Next Generation Nuclear Plant (NGNP) illustration.

20 l 2010 New Reactor Program

Advanced Reactor Program struction, and operation of advanced reactors. This includes the following:

The development of advanced reactor designs in the United States and abroad has been supported

• Building a knowledgeable and capable organiza-by various Government efforts such as the Genera- tion, through a combination of hiring, training, and tion IV International Forum, as well as by private contractor support, ready to conduct reviews of companies and governments seeking to introduce an advanced reactor designs.

alternative to large, light-water reactors. The NRC has had experience in the area of advanced reactors

• Developing the regulatory framework to support in the pastPeach Bottom 1 in Pennsylvania and efficient and timely licensing reviews of advanced Fort St. Vrain in Coloradobut the programs were reactor designs.

not pursued because of changes in Government policies or private sector initiatives. The existing

• Engaging DOE, designers, and potential licensees in new reactor licensing program has benefited from meaningful preapplication interactions and coor-previous advanced reactor programs that led to the dinating activities with internal and external stake-certification of the AP600 passive design and preap- holders.

plication reviews of gas-cooled and sodium-cooled reactors. A range of different technologies are being discussed with the NRC staff. Currently the staff is implement-The current increased interest in advanced reactors ing a structured approach in preparing for the review resulted from a number of developments such as the of these various designs. Specifically, the staff has inclusion of a requirement in the EPAct for the NRC to been focusing on preparation activities for the review license an HTGR as part of the U.S. of an HTGR design in accordance Department of Energys (DOEs) with the EPAct of 2005, as well as Next Generation Nuclear Plant The staff is focused on for the review of iPWR designs.

(NGNP) project; the introduction The staff is also maintaining an awareness of other designs and of small modular reactors (SMRs) ensuring that the agency is technologies but is not investing for domestic and foreign markets; and the possible use of fast reactors significant resources in these activi-prepared to address the ties so that it can focus on NGNP as part of a solution to close the nuclear fuel cycle. The Advanced and iPWRs. This structured ap-Reactor Program (ARP) was created multiple new technologies proach is consistent with the time-within NRO in January 2009 to pro- lines for the various technologies vide a focused project management being proposed. discussed by DOE representatives.

function for technologies beyond large, light-water reactors. The current regulatory framework is primarily geared towards large, light-water reac-A clear indication of the interest in the development tors. To facilitate efficient and timely licensing reviews and deployment of advanced reactors designs is a of other technologies, such as SMRs, the staff has host of several draft legislative proposals directing embarked on an initiative to develop a regulatory DOE and NRC to coordinate the licensing of an framework for these new classes of reactors. The SMR. In light of this congressional interest in SMRs, NRC expects to receive its first SMR application in on December 15, 2009, the Director of NRO provid- FY 2012. To support development of a regulatory ed testimony to the Senate Committee on Energy and framework for iPWRs and HTGRs, and ultimately Natural Resources on the status of the staff s prepara- to be ready to conduct licensing reviews during this tion activities. In addition, NRO staff and managers timeframe, it is essential that major policy, technical, have participated in SMR-related conferences spon- and licensing issues be identified and progress made sored by DOE, NEI, the American Nuclear Society, on their resolution prior to receiving applications.

and numerous other companies and organizations. The staff, with support from the national laboratories, is identifying technical issues for the various advanced The staff is focusing its efforts on preparing the NRC reactor technologies (e.g., different fuel forms, cool-for reviews of applications related to the design, con- ants, and materials) and preparing revised guidance 2010 New Reactor Program l 21 Office of New Reactors l 27

Schematic courtesy of Babcock & Wilcox Nuclear Energy Inc. Illustration courtesy of Babcock & Wilcox Nuclear Energy Inc.

Activities &

Accomplishments Above, Babcock & Wilcox Companys mPower schematic.

Top right, fuel element design for a high-temperature, gas-cooled reactor.

22 l 2010 New Reactor Program

to support applicants and the NRC staff. Some issues

• U.S. Environmental Protection Agency regarding have the potential to influence design decisions and process heat applications, jurisdictional issues for leaving them unaddressed prior to receipt of the collocated nuclear and chemical facilities, and intro-applications would greatly complicate the licensing duction of tritium into commercial products (e.g.,

process, reduce the efficiency of the staff, and likely hydrogen).

extend the review schedules.

Continued interactions also will be needed for agen-To ensure early communication with internal and cies such as the U.S. Department of State, U.S.

external stakeholders, the staff held two well-attended Department of Commerce, and other agencies (e.g.,

public workshops (February 3, 2010, and Octo- Army Corps of Engineers, U.S. Geological Survey).

ber 8, 2010) focusing on the identified potential policy, technical, and licensing issues. These issues were To ensure close coordination between the NRC and summarized in an information paper to the Com- its stakeholders, and timely resolution of the issues, mission, SECY-10-0034, Potential Policy, Licensing, the ARP and the NEI have established routine public and Key Technical Issues for Small Modular Nuclear meetings to discuss generic approaches to resolv-Reactor Designs, issued on March ing the policy, licensing, and key 28, 2010, and were also the subject technical issues for the spectrum of a Commission meeting held on of advanced reactor technologies.

April 6, 2010. The staff has devel- We will actively seek These meetings were kicked off on oped plans to address these major July 22, 2010, and will continue to policy issues (e.g., financial and information from vendors so occur approximately every 6 weeks.

insurance requirements, control room staffing and human factors The interest in advanced reactor requirements, emergency prepared-that potential policy issues designs also has led to increased ness requirements, and security re- international activities by organi-quirements) by evaluating possible can be addressed, and review zations such as the International changes in regulatory positions and Atomic Energy Agency (IAEA),

recommending courses of action guidance can be developed to Organization for Economic Co-for Commission consideration. The operation and Development, and implementation of these plans will support future reviews. Generation IV International Fo-require significant coordination rum. NRO participated in several from both internal and external conferences and meetings to ensure stakeholders to support proposed the NRC remained cognizant application schedules. For example, in addition to of advanced reactor development and deployment industry stakeholders, the NRC will need to com- around the world and to share NRC insights with the municate and coordinate with the following Federal regulators in other countries. ARP staff and manage-agencies: ment provided information at IAEA conferences, bilateral and multilateral meetings, and infrastructure

• DOE and its programs related to the NGNP, SMRs, development meetings organized by DOE.

fuel cycle research and development, and technology development. Other interactions will be required As noted previously, the NRC is focusing on prepara-for matters such as possible revisions to the Price tion activities for both the NGNP and expected iPWR Anderson Act and evaluations of proliferation resis- applications. A summary of the designs being pro-tance and physical protection. posed and ongoing preapplication activities follows:

• U.S. Department of Homeland Security and espe-cially the Federal Emergency Management Agency regarding proposed changes to requirements related to emergency management.

2010 New Reactor Program l 23

Activities &

Accomplishments Containment Reactor Control Rod Pressure Devices Vessel Reactor Vent Valves Pressurizer Control Rods Steam SG Holder Image courtesy of NuScale Power, Inc.

Annulus Steam Cold Leg Generator Feed Tubes Hosser Hot Leg Riser Sump Recir Downcomer Valves Core Shreud Top, employees attend a U.S. Department of Energy-sponsored training seminar on high-temperature, gas-cooled reactor technology.

Above, NuScale Small Modular Reactor design.

Right, fuel element design for Pebble Bed Modular Reactor.

Diagram courtesy of Idaho National Laboratory.

24 l 2010 New Reactor Program

Integral Pressurized-Water Reactors submit 12 topical reports between now and submittal of its design certification application, expected in late NuScale Power, Inc. FY 2012. The NRC staff has received four topical reports and is establishing review schedules for these

• The NuScale modular reactor is a 160 megawatt reports. Recent submittals include QA program de-thermal (MWt) (45 megawatt electric (MWe)), scription, design description, critical heat flux testing natural circulation pressurized-water reactor design plan, and integrated system testing plan. Additional that consists of an integrated reactor vessel assembly reports are expected through FY 2012.

which includes the reactor core, pressurizer, control rods, and two helical steam generators, all located within the reactor vessel. Next Generation Nuclear Plant

• NuScale is proposing that each plant be designed to The NGNP project was established in accordance accommodate up to 12 totally independent modules with Subtitle C of the EPAct. As defined by the (reactor vessel and containment) for a total plant EPAct, the NGNP will be a full-scale prototype plant electrical capacity of up to 540 MWe. that will be reliable, safe, proliferation resistant, and economical and will demonstrate the commercial NuScale is currently in the preapplication review potential of the design and associated technologies.

phase with the NRC and is scheduled to file its formal The mission of the NGNP includes providing high-request for design certification in early 2012. In temperature process heat for the chemical industry, advance of its design certification application, refining petroleum, extracting oil from shale and tar NuScale informed the NRC of its intent to submit deposits as an alternative to natural gas, producing 15 licensing topical reports. The NRC has received hydrogen, and serving as a central electric power sta-two topical reports and is establishing review sched- tion. To meet this mission, DOE has concluded that ules for these reports. the NGNP should be a gas-cooled, very-high-temper-ature reactor.

Babcock and Wilcox mPower TM DOE is conducting the NGNP project in two phases.

Phase 1 includes selecting and validating the appro-

• The Babcock and Wilcox (B&W) mPower reactor is a priate technology and supporting research and devel-400 MWt (125 MWe) light-water reactor that consists opment activities. It is expected that DOE will select a of a self-contained module with the reactor core, re- specific design for further development in early 2011.

actor coolant pumps, and steam generator located in Phase 2 covers development of a final design for the a common reactor vessel installed in an underground NGNP prototype, application for a combined license containment. The module uses a conventional core to construct and operate the nuclear reactor from with standard light-water reactor fuel and no exter- NRC, and construction and startup operations. Pres-nal pressurizer. Systems rely on existing light-water ently, a COL application is expected in FY 2014.

reactor technology and off-the-shelf components.

The modules would be manufactured at a single DOEs contractor for NGNP, Idaho National centralized B&W facility in the United States and Laboratory, has submitted several white papers transported by rail, road, and or ship. Each module addressing aspects of HTGR technology for NRC has a proposed 48-month refueling cycle. review. Recent submittals include papers addressing defense-in-depth for the reactor design, high-NRO has been engaged in preapplication activities temperature materials, mechanistic radiation source with B&W since mid-2009 following receipt of the term, fuel qualification, modular plant licensing, companys letter of intent to submit an application for and QA. Additional submittals are expected through design certification for the B&W mPowerTM commer- FY 2011.

cial advanced light-water reactor. In July 2010, B&W provided a letter to the NRC that detailed its plans to 2010 New Reactor Program l 25

Activities &

Accomplishments Illustration courtesy of Toshiba Top, Advanced Reactor Program Branch Chief Stewart Magruder briefs the staff on the latest developments in the program.

Above, Super-Safe, Small and Simple (4S) Reactor by Toshiba.

Right, General Engineer Wes Held makes a point about advanced reactor designs at a staff meeting.

26 l 2010 New Reactor Program

Other Advanced Reactor Designs Other reactor designs being developed include the following:

The NRC staff is aware of various efforts that could lead to other reactor technologies and designs coming

• Several Generation IV designs such as the molten forward for technical review, certification, or licensing. salt reactor, supercritical-water-cooled reactor, lead-The staff is currently participating in limited preap- cooled fast reactors, and gas-cooled fast reactors.

plication activities with the designers of four fast reac-tor designs: GEH PRISM; the Toshiba Corporation

• Several fission reactor designs not included in Gen-(Toshiba) Super-Safe, Small and Simple (4S) Reactor; eration IV but developed for defense, space propul-the Advanced Reactor Concepts, LLC ARC-100 sion, or other programs that may be deployed for Reactor, and the Hyperion Power Generation, Inc., commercial applications.

Hyperion Power Module design.

• Fission-Fusion hybrid reactors (e.g., Laser Inertial Additional designs are being considered within the in- Fusion Engine).

dustry. For example, the staff is aware that companies are currently engaged in design work for an advanced

• Fusion energy devices (e.g., ITER-derived machines, recycling reactor, the traveling wave reactor, and the inertial confinement systems, and TriAlpha plasma Sandia National Laboratory-initiated right-sized electric generator).

reactor.

The Evolution of Nuclear Power Generation I Generation II Commercial Power Generation III Early Prototype Reactors Reactors Generation III*

Advanced Generation IV LWRs

-Generations III

-Highly Evolutionary Economical Designs Offering

-Enhanced Improved

-shipping port Safety Economics

-Dresden, Fermi I -Minimize Image courtesy of Westinghouse, Inc.

-LWR, PWR, BWR -ABWR Wastes

-Magnox

-CANDU -SYSTEM 80+ -Proliferation

-VVERBMK -AP600 Resistant

-AGR -EPR Gen I Gen II Gen III Gen III + Gen IV 1950 1960 1970 1980 1990 2000 2010 2020 2030 2010 New Reactor Program l 27

Activities &

Accomplishments Top, NRC staff visit the Sandvik Materials Technology facility in Sweden to inspect steam generator tubes.

Above, DCIP employees inspect a reactor vessel head at Japan Steel Works in Muroran, Japan.

Right, the Digital Instrumentation and Controls Working Group of the Multinational Design Evaluation Program meet in Paris, France.

28 l 2010 New Reactor Program

International Cooperation Meanwhile, the MDEP continues to develop innova-tive approaches to leverage the resources and knowl-Since its inception, NRO has been an active and robust edge of mature, experienced national regulatory participant in the worldwide nuclear regulatory com- authorities who are, or will shortly be, undertaking munity. Prime examples are recent NRO staff and the review of new reactor power plant designs. NRO management participation in multilateral and bilat- plays a leading role in the program, which includes eral exchanges of information, attendance at and the the regulatory authorities of nine other countries:

presentation of information at global conferences, and Canada, China, Finland, France, Japan, Korea, support of cooperative and assistance activities orga- Russian Federation, South Africa, and the United nized by the IAEA. Kingdom.

Multilateral exchanges were conducted as part of In 2010, significant progress was evidenced in fulfill-MDEP, Nuclear Energy Agency (NEA), and IAEA ing the overall MDEP goals of increased cooperation committees and working groups, and established and enhanced convergence of requirements and conferences. practices. NRO stood at the crossroads of that prog-ress, as it witnessed particularly note-Throughout 2010, NRO and the worthy accomplishments including:

NRCs Center for Construction NRC will partner with the completion of 13 vendor inspec-Inspection in Region II engaged in tions with multinational cooperation; several bilateral exchanges with the the international development of common positions in Chinese nuclear regulator, who is the area of digital instrumentation and overseeing the worlds first construc- community and incorporate controls; agreements with standards tion of an AP1000 reactor. As part of development organizations regarding the effort, an NRC regional inspector construction experience cooperation in pursuing convergence; spent 6 weeks inspecting and ob- and the completion of a comparison serving construction activities at the gained from around of the Korean, Japanese, and French AP1000 construction site at Sanmen codes for Class I pressure vessels (see page 2). This provided a unique the world into our against the ASME Code.

opportunity to test NRCs construc-knowledge base. NRO staff members shared informa-tion inspection procedures. The NRC also hosted six staff members from tion with their regulatory counterparts the Chinese regulator who were per- on design reviews through participation forming short-term exchange assignments. An NRO in MDEP design-specific working groups for the EPR inspector also spent a year with the French nuclear and the AP1000. In addition, the NRO staff partici-regulator performing vendor inspection activities. pated in an IAEA-sponsored siting training program for countries that are interested in developing a The staff conducted a number of vendor inspections nuclear program.

worldwide, including in Japan, France, Germany, Italy, and Sweden. Because the supply stream for NRO can point to several accomplishments to date nuclear components is global in nature, the NRC that provide confidence that the MDEP structure conducts many inspections of foreign component and process is an effective method of accomplishing manufacturers. One of our highest priorities and increased cooperation in regulatory design reviews.

biggest challenges is to instill nuclear-grade QA and Additional information on MDEP, including the an-a strong safety culture in suppliers, particularly those nual report, can be found at the NEA Web site:

that are new to the nuclear field. These inspections www.oecd-nea.org.

focus on vendors QA programs and the reporting of defects, as well as noncompliance programs. NRO also plays a leading role in the recently formed Working Group on the Regulation of New Reac-In 2010, NRO supported bilateral international tors, made up of the members of NEAs Committee exchanges on technical specifications and operator on Nuclear Regulatory Activities who are interested licensing with the French nuclear regulator and on air- in sharing information on new reactor licensing and craft impact assessment with the Canadian regulator. construction oversight.

2010 New Reactor Program l 29

A Look Ahead Photos courtesy of Southern Company 30 l 2010 New Reactor Program

For the New Reactor Program, 2011 and beyond will Meanwhile, construction activities will increase and be pivotal years. Within the next 2 years, we expect we will aggressively implement our construction to issue design certifications for evolutionary, passive inspection activities for the first new reactors. We reactor designs; issue the first combined licenses, and will continue to enhance our oversight program, continue to oversee the first new reactor construction with enhancements including additional guidance on in this country in decades. ITAAC maintenance; additional guidance on DAC closure; improving information technology infra-Guided by an unwavering commitment to safety, the structure; and the continued recruitment, training, New Reactor Program continues to meet the chal- and qualification of new inspectors. In fact, resident lenging goals posed by its primary program areas inspectors will begin to be placed at new reactor sites of licensing, oversight of vendor and construction under construction.

inspection, and advanced reactors. In doing so, it is contributing substantially to the fulfillment of the Elsewhere, vendor inspection activities to verify the agencys mandate to protect the public health and integrity of the supply chain, internationally as well safety, the environment, and to promote the common as domestically, will increase. We will continue to defense and security. partner with the international com-munity and incorporate construction As we look forward, it is clear experience gained worldwide into that NRO is strategically posi- While we anticipate our knowledge base.

tioned to successfully complete our increasing and changing Our Advanced Reactor Subprogram workload in a timely and respon-mounting challenges and will continue its preparation to meet sive manner. While we anticipate the rapidly growing interest in design mounting challenges and oppor- opportunities, we are poised and possible licensing applications tunities, we are poised to achieve for these advanced reactor designs.

significant accomplishments in to achieve significant In light of our mandate from Con-terms of volume, overall scope, gress, we will fulfill our obligations and quality of work. accomplishments in terms to complete a licensing review of an HTGR as part of DOEs next gen-In the area of licensing, the eration nuclear plant.

New Reactor Subprogram of volume, overall scope, will continue to sustain steady Furthermore, we are ready to review progress as our comprehensive and quality of work. the applications submitted for the review process serves us well. multiple new technologies now being Part 52 and the design-centered proposed. Accordingly, NRO will review approach will enable us continue to develop plans for policy to achieve COL standardization around selected and key technical issues associated with various reac-designs while maintaining both a strong safety focus tor technologies and designs.

and resource savings. We will continue to be flexible and responsive to the challenges presented by the NRO will continue to actively seek information to evolving needs of designers and COL applicants. keep informed of industry activities and plans so In addition, we will continue to evaluate plans and we can budget and prepare for them, as well as seek schedules of ongoing reviews based on an applicants information from vendors so that potential policy construction and commercial building plans as well issues can be addressed and review guidance can be as its support for issue resolution. We expect to com- developed to support future reviews.

plete our reviews of the majority of docketed COL applications in 2011 and 2012 and expect to receive As we move forward, our top priority is safetya two additional COL aplications by the end of 2012. priority that will remain steadfast as new applications We also received design certification renewal applica- are submitted and reviewed and nuclear reactor tions for the ABWR from GEH and Toshiba before technologies emerge.

the end of 2010.

2010 New Reactor Program l 31

At a Glance Top, DCIP Director Glenn Tracy addresses the audience at NRCs Workshop on Vendor Oversight for New Reactor Construction in New Orleans, LA.

Above, Division of Engineering Director Tom Bergman speaks at a division meeting.

Right, attendees listen intently at a quarterly accomplishments review session.

32 l 2010 New Reactor Program

NRO is responsible for licensing and oversight of construction of the NRCs nuclear reactor safety Key Participants mission for licensed new reactor facilities. As such, NRO is responsible for regulatory activities in the Office of primary program areas of siting, licensing, and Office of Nuclear the General Security and oversight for new commercial nuclear power reac- Counsel Incident

Response

tors to protect the public health, safety, and the environment and to promote the common defense Region II Office of and security. NRO works with other NRC offices Center for Nuclear to accomplish that mission. Construction Regulatory Inspection New Research Reactor For example, NRO works closely with the Cen- Program ter for Construction Inspection in NRCs Region II, located in Atlanta, GA. The centers mission 1

is to provide assurance in the safety of future and resource planning and tracking; and issuance of operations at new nuclear facilities by ensuring design approvals, design certifications, manufacturing that licensees construct the facilities according to licenses, and combined licenses. The division serves as approved designs, using appropriate practices and the lead organization for interactions with quality materials.

Government agencies pertaining to SMRs.

NRO also coordinates activities with OGC; NSIR, which works to prevent nuclear security incidents Branches Advanced Reactors Branch 1 (ARB1) and prepare for and respond to safety and security Advanced Reactors Branch 2 (ARB2) events; and RES. The mission of RES furthers the regulatory mission of the NRC by providing technical advice, technical tools, and information Program Management, Policy for identifying and resolving safety issues, and pro- Development, & Analysis Staff (PMDA) mulgating rules and guidance. RES also conducts independent experiments and analyses, develops PMDA provides administrative and management technical bases for supporting realistic safety deci- support for the New Reactor Program budgeting sions by the agency, and prepares the NRC for the through the planning, budgeting, and performance future by evaluating safety issues involving current management process; resource allocation through the and new designs and technologies. RES develops staffing plan; analysis of office performance through its program with consideration of Commission di- coordination of the operating plan; and internal con-rection and input from program offices, including trols of office activities. It also provides and enhances NRO, and other stakeholders. communication to internal and external stakeholders.

PMDA provides oversight and support of informa-NRO consists of the following divisions: tion management and technology and administrative and management support in areas including human Advanced Reactor Program (ARP) resource management, knowledge management, tracking and coordination of correspondence and ac-ARP leads, manages, and facilitates advanced reactor tion items, space management, training coordination, activities including: preapplication activities, design and Freedom of Information Act coordination. In approval application reviews, design certification addition, PMDA facilitates continuous organizational application reviews, manufacturing license applica- improvement by developing and improving office tion reviews, COL application reviews, and ESP instructions, represents the office in special projects in application reviews. ARP also develops and maintains areas of responsibility, and completes special projects the necessary technical and programmatic support assigned by office-level management.

for advanced reactor licensing activities; guidance development; interaction with stakeholders on issues Branches pertaining to advanced reactors; implementation Financial and Performance Management Branch of large-scale project management tools; schedule (FPMB) 2010 New Reactor Program l 33

At a Glance Top, NROs Donna Williams, far left, participates in an agency emergency exercise.

Above, Office Director Mike Johnson and Commissioner Kristine Svinicki during an NRO All Hands Meeting.

Right, members of PMDAs Human Capital Management Branch review the offices strategic workforce planning initiative.

34 l 2010 New Reactor Program

Human Capital Management Branch (HCMB) Division of Safety Systems &

Information and Infrastructure Management Branch Risk Assessment (DSRA)

(IIMB)

Information Technology Management Branch DSRA performs systems-related safety evaluations of (ITMB) applications for new facilities or designs and provides technical support and expertise for special projects, Division of New Reactor Licensing programs, and policy activities and reviews and evalu-(DNRL) ates design-basis and severe accident issues as they relate to advanced plant designs and combined licenses. It DNRL leads, manages, and facilitates design also develops and implements policies and guidance for certification application reviews, ESP application the use of probabilistic risk assessments and associated reviews, COL application reviews, and new reac- analyses in regulatory decisionmaking for new reactors.

tor preapplication activities. It also develops and In addition, it applies risk-informed methods to support maintains the necessary technical and programmatic resolution of regulatory issues and reviews probabilistic support for new reactor licensing activities, guidance risk assessment submittals and severe accident design development, interaction with stakeholders on issues features related to the certification and licensing of pertaining to new reactors, large-scale project man- advanced designs. Furthermore, DSRA provides risk agement tools, schedule and resource planning and assessment support in areas of plant security and utility tracking, and issuance of design certifications and actions to reduce potential vulnerabilities.

COLs. Based on the DNRL reorganization of August 6, 2007, the division was divided into the Branches licensing operations and the infrastructure and policy Balance of Plant Branch 1 (SBPA) organizations. Branches that fall within these two Balance of Plant Branch 2 (SBPB) organizations are listed below: Containment and Ventilation Branch 1 (SPCV)

Containment and Ventilation Branch 2 (SBCV)

Branches PRA and Severe Accidents Branch (SPRA)

Licensing Operations Reactor System, Nuclear Performance, and Code AP1000 Projects Branch 1 (NWE1) Review (SRSB)

AP1000 Projects Branch 2 (NWE2)

BWR Projects Branch 1 (NGE1) Division of Construction Inspection BWR Projects Branch 2 (NGE2)

EPR Projects Branch (NARP) & Operational Programs (DCIP)

USAPWR Projects Branch (NMIP)

DCIP develops policy and provides overall program Infrastructure and Policy management and planning for the construction inspec-Planning and Scheduling Projects Branch (NPLS) tion program for new commercial nuclear power plants.

Contract Planning and Management Branch (NCPM) It also coordinates with Region II, the Office of Nuclear Organizational Effectiveness and Productivity Branch Reactor Regulation (NRR), and other offices on pro-(NOEP) gram implementation, including licensee performance Rulemaking, Guidance and Development Branch assessment, allegations, and enforcement activities. It (NRCA) implements programs and procedures to systematically assess and coordinate the followup of construction-related issues, and recommends corrective plant-specific and generic actions. DCIP also reviews the quality assurance programs at vendors, fabricators, applicants, and construction licensees, and develops and implements the quality assurance and vendor inspection programs.

Additionally, DCIP reviews applicant radiation protec-tion programs and develops and oversees the radiation protection inspection programs. The division reviews li-censee submittals and develops programs and guidelines 2010 New Reactor Program l 35

At a Glance Top, employees visit the Westinghouse AP1000 simulator in Cranberry Township, PA.

Above, NRO and NRR staffers join forces at a Balance of Plant Counterparts Meeting.

Right, NRO Geologist Meralis Plaza-Toledo examines rocks at the V.C. Summer Unit 2 excavation site in Fairfield County, SC.

36 l 2010 New Reactor Program

for technical specifications and provides interpretations reactor preapplication activities. It provides technical of technical specification requirements. It develops poli- expertise to support regional activities, special proj-cies and guidance and implements the national program ects, programs, and policy activities. DE reviews may for the licensing of new nuclear reactor operators. DCIP be performed in support of topical reports, consensus develops programs and conducts reviews to ensure the standard changes, or new reactor designs.

effective consideration of human factors engineering in new nuclear power plant design and operation. In addi- Branches tion, it assesses the adequacy of facility personnel train- Component Integrity, Performance, & Testing ing programs and emergency operating procedures. Branch 1 (AP1000/EPR Projects) (CIB1)

Component Integrity, Performance, & Testing Branches Branch 2 (ESBWR/ABWR Projects) (CIB2)

Construction Assessment, Enforcement, and Electrical Engineering Branch (AP1000/EPR/

Allegations Branch (CAEB) ESBWR/ABWR Projects) (EEB)

Health Physics Branch (CHPB) Engineering Mechanics Branch 1 Construction Inspection Program Branch (CIPB) (AP1000/EPR Projects) (EMB1)

Operator Licensing & Human Performance Branch Engineering Mechanics Branch 2 (COLP) (ESBWR/ABWR Projects) (EMB2)

Quality & Vendor Branch 1 (AP1000/EPR Projects) Instrumentation, Controls & Electrical Engineering 1 (CQVA) (AP1000/EPR Projects) (ICE1)

Quality & Vendor Branch 2 (ESBWR/ABWR) Instrumentation, Controls & Electrical Engineering 2 (CQVB) (ESBWR/ABWR Projects) (ICE2)

Technical Specifications & ITAAC Branch (CTSB) Structural Engineering Branch 1 (AP1000/EPR Projects) (SEB1)

Division of Site & Environmental Structural Engineering Branch 2 (ESBWR/ABWR Projects) (SEB2)

Reviews (DSER)

DSER is responsible for the project management and Region II - Center for Construction assessment of the environmental impacts and the Inspection (CCI) technical evaluation of the site safety portions of de-sign certification, ESP, and COL application reviews. Major responsibilities for CCI include: serve as the It also develops and maintains the environmental and agency center of excellence for nuclear facility con-site safety regulatory infrastructure necessary to sup- struction inspection activities; manage the construc-port issuance of DCs, ESPs and COLs. The division tion inspection program; develop infrastructure for is also responsible for interactions with internal and construction inspection program and staff; carry out external stakeholders on issues related to siting and construction inspections at new facilities and associat-environmental review activities. ed vendors; evaluate performance of applicants; and provide regulatory bases for agency decisions.

Branches Environment Projects Branch 1 (RAP1) Divisions and Branches Environment Projects Branch 2 (RAP2) Division of Construction Inspection (DCI)

Environment Projects Branch 3 (RAP3) Inspection Branch 1 Environmental Technical Support Branch (RENV) Inspection Branch 2 Geosciences & Geotechnical Engineering Branch 1 Inspection Branch 3 (RGS1)

Geosciences & Geotechnical Engineering Branch 2 Division of Construction Projects (DCP)

(RGS2) Projects Branch 1 Hydrologic Engineering Branch (RHEB) Projects Branch 2 Siting & Accident Consequences Branch (RSAC) Projects Branch 3 Projects Branch 4 Division of Engineering (DE)

DE performs engineering-related safety reviews of applications for design certification, COLs, and new 2010 New Reactor Program l 37

38 l 2010 New Reactor Program 2010 2010 New New Reactor Reactor Program l 39 Program l 39

2010 NEW REACTOR PROGRAM OFFICE OF NEW REACTORS 40 l 2010 New Reactor Program

U. S. Nuclear Regulatory Commission NUREG/BR-0476 December 2010