ML19319B319

NRC-2018-000831 - Resp 2 - Interim (RES Workshop Presentations_Rif) Part 10 of 10

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Evaluating Structures, Systems & Components from Decommissioned/Decommissioning Nuclear Facilities in Canada Presented at the Nuclear Regulatory Commission Harvesting Workshop - March 7-8, 2017 Daniel Tello - CNSC Senior Research Officer Désiré Ndomba - CNSC Technical Specialist Karen Huynh - AECL Federal S&T Manager e-Docs #5196600

Outline

• Who we are Canadian Nuclear Safety Commission (CNSC)

Atomic Energy of Canada Limited (AECL)

• Canadian Harvesting Projects & Sources Nuclear Power Plants and Research Reactors Nuclear Power Demonstration (NPD) Generating Station Gentilly-2 Nuclear Generating Station Nuclear Research Universal (NRU) Reactor

• Summary 2

Canadian Nuclear Safety Commission Canadas nuclear regulator for over 70 years 3

Canadian Nuclear Safety Commission (CNSC):

Established on May 2000 under the Nuclear Safety Control Act (NSCA);

Replaced the Atomic Energy Control Board, which was established in 1946 under the Atomic Energy Control Act; CNSCs Mission:

Regulate the use of nuclear energy and materials to protect the health, safety and security of Canadians and the environment; Implement Canadas international commitments on the peaceful use of nuclear energy; Disseminate objective scientific, technical and regulatory information to the public;

Atomic Energy of Canada Limited 4

AECL is a federal Crown corporation responsible for managing Canada's radioactive waste liabilities and enabling nuclear science and technology AECL delivers their mandate through a contractual arrangement with Canadian National Energy Alliance (CNEA) for the management and operation of Canadian Nuclear Laboratories (CNL) under a Government-owned, Contractor-operated (GoCo) model AECL oversees the delivery of the Federal Nuclear Science and Technology Work Plan in order to support the Governments priorities and core responsibilities in areas such as nuclear safety, security, energy, health and the environment CNL is responsible for the management and operation of the Laboratories, and is the licensee with access rights to AECLs assets and Intellectual Property (IP)

Harvesting Materials in Canada Why is Harvesting Important?

The nuclear power plants (NPPs) that are currently in operation were generally designed and built with conservative principles, and in many cases have significant remaining safety margins. Typically, NPPs were designed with the intent of operating for up to 30 years. This is now changing to approximately 60 years.

Harvesting materials from decommissioned or decommissioning facilities is intended to assess the remaining safety margins for the physical condition of structures, systems and components (SSCs) in NPPs through testing to verify and/or validate the technical feasibility of Long Term Operation (LTO).

Canadian Harvesting Projects Canada currently has harvesting projects in 2 areas from different facilities Analysis of Degradation Mechanisms of Cables Understanding Degradation of Concrete 5

Nuclear Power Demonstration Plant (NPD)

• The 20 MW Nuclear Power Demonstration Plant (NPD) was Canadas first nuclear power reactor to supply electricity to Ontario Hydros electrical distribution grid

• The reactor permanently shutdown in 1988 after 25 years of service CNSC sponsored a research project with Ontario Hydro in 1991 on:

Cable insulation degradation of the 20 MW Nuclear Power Demonstration Plant AECL currently has a research project to analyze concrete samples from NPD 6

Understanding the Degradation of Concrete

Background

This project will address gaps in the domestic knowledge of concrete degradation in nuclear power plants and will support regulatory decisions for long-term reactor operations of domestic utilities and new reactor technologies, such as SMRs.

Project Objective To assess concrete core samples for degradation Status Year one of a three year project Received 7 concrete cores from Nuclear Power Demonstration (NPD) reactor Identified test techniques to assess for degradation Other opportunities Concrete from other decommissioned reactors in Canada such as Gentilly-2, Douglas Point and AECLs whiteshell reactor in Pinawa, Manitoba 7

Gentilly-2 Nuclear Power Plant

• Gentilly-2 (G2) Nuclear Power Plant (NPP) is a CANDU-6 675 Mwe nuclear reactor which was permanently shutdown in 2012 after 29 years of service CNSC & AECL/CNL are currently conducting a research project on the Analysis of Degradation Mechanisms of Cable Insulation due to Ageing in a Decommissioned Nuclear Power Plant 8

Cable Harvesting Project from G2

Background

Material properties of cables aged in real time and real operating conditions can be significantly different from the properties received by studying samples aged in laboratory and assumed in codes and standards.

Project Objective Assess current cable degradation resulting from thermal and radiation ageing Validate environmental qualification work Status Reviewed environmental conditions and selected cables to be harvested from Hydro Quebec/Gentilly-2 reactor CNSC & AECL/CNL staff have recently witnessed the removal of cable samples from the G-2 NPP Samples will be retrieved and tested to improve cable ageing test parameters used to assess cable condition 9

Cable Harvesting Project from G2 (contd) 10 Challenges There were several challenges associated with the cable harvesting project at G2:

removal of material samples from a decommissioned NPP is neither a compliance nor licensing activity for licensees; accessibility of analysis and testing records (data, samples, etc.)

inaccessibility or contamination of materials to be removed cost related to carry out research activity on these materials.

National Research Universal (NRU) Reactor NRU is a 135MWt nuclear research reactor built in the Chalk River Laboratories, Ontario with first criticality achieved on November 3, 1957.

The NRU reactor has three purposes

Supplier of industrial and medical radioisotopes used for the diagnosis and treatment of life-threatening diseases;

A major Canadian facility for neutron physics research; and

Research and development support for CANDU power reactors.

After 5 decades of service, the NRU reactor will shut down permanently in March 2018, after ~270k hours operation.

The NRU reactor contains a vast array of materials and components including

structural materials (such as steels and other nickel bearing alloys, zirconium alloys, aluminum, concrete) and welded joints

a thermal graphite column

equipment (including pumps)

graphite seals

electrical cables

thermocouples 11 304 SS, ~1.6 dpa, 35 oC,

~3.4x1026 n/m2 (E<0.625 eV)

Harvest Material from National Research Universal (NRU) Reactor Project Objective Create an inventory of irradiated materials which can be harvested from the decommissioned NRU reactor The inventory will be used to assess irradiation damage on the performance of in-core materials and components Advantages of Harvesting Materials from NRU Assess the effects of irradiation on the performance and degradation of a variety of materials;

wide range of temperature, flux and neutron spectrum

irradiation times on the order of power reactor lifetimes

the combination of operating conditions and exposure is not always easily or economically obtainable in test programs Collaborate with various partners throughout the international nuclear industry who also wish to characterize the effects of irradiation on materials Provide information to decommissioning groups interested in the radionuclide inventory of the decommissioned reactor.

Status One year project that will start on April 1, 2017 12

Summary 13

• Understanding ageing degradation is an important aspect to ensure nuclear safety as nuclear power plants age

• R&D behind SSC material life management is needed to ensure the safe and reliable operation of NPPs

• Several nuclear facilities in Canada exist for potential harvesting of Structures, Systems & Components. Examples include:

Nuclear Power Demonstration (NPD) Facility Gentilly-2 (G2)

National Research Universal Reactor (NRU)

Douglas Point AECLs Whiteshell Reactor

Contacts 14 Daniel Tello Désiré Ndomba Senior Research Officer Technical Specialist E-mail: daniel.tello@canada.ca E-mail: desire.ndomba@canada.ca Karen Huynh Federal S&T Manager Email: khuynh@aecl.ca Gina Strati Lori Walters Director - Energy Sr Mechanical R&D Email: gina.strati@cnl.ca Email: lori.walters@cnl.ca

Questions 15 Thank you!

KHNP-CRI KHNP-Central Research Institute Kori-1 Harvesting Plan for Materials Aging Degradation Research Al Ahluwalia (EPRI) for Han-sub Chung (KHNP)

March 7-8, 2017

KHNP-CRI Contents

===1.

Background===

2.

Research planning using materials from retired Kori-1 3.

Future Plans

KHNP-CRI

1. BACKGROUND

KHNP-CRI

KHNP PWRs and Kori-1

Kori-1 is a Westinghouse two loop PWR

SG replaced in 1998, RV head replaced in 2015

Kori-1 will be shutdown on 2017.6.18 (30 year original design life + 10 year extended life)

Seven additional PWRs complete their original 40-year design lives beginning 2023, nearly one plant each year

KHNP intends to seek license renewals but it will be a challenging task due to public concern for safety

KHNP is planning a comprehensive research program on long-term materials aging degradation

KHNP-CRI

Schedule of decommissioning Kori-1 (tentative)

Submission of a KHNP decommissioning plan (2020.6.)

Approval procedures including public hearings

Final approval of the decommissioning plan (2022.6.)

Completion of the cutting and dismantling (2024.12.)

KHNP-CRI

2. RESEARCH PLANNING USING MATERIALS FROM RETIRED KORI-1

KHNP-CRI Planning sub committees (2016.1.~4.)

classification Chair/secretary Members Neutron irradiation embrittlement of RPV BS Lee(KAERI)/

JS Yang(CRI) 5~10 members each group from relevant organizations (KAERI, KPS, KEPCO-E&C, DHIC, KAIST, and a few universities)

Reactor internals SS Hwang(KAERI)/

JS Yang(CRI)

SCC of Alloy 600 weld nozzles and penetrations (CRDM, BMN, DMW)

HP Kim(KAERI)/

HD Kim(CRI)

Steam generators HP Kim(KAERI)/

HD Kim(CRI)

Thermal embrittlement CH Jang(KAIST)/

MW Kim(CRI)

FAC & buried pipes DJ Kim(KAERI)/

SK Park(CRI)

KHNP-CRI 12 tasks proposed at the subcommittees 1.

Irradiation Embrittlement of the Reactor Pressure Vessel Beltline Material 2.

Irradiation Embrittlement of RPV Nozzle steel 3.

Investigation of the IASCC mechanism 4.

Material properties of aged RVI components 5.

Residual stress and susceptibility to PWSCC of Alloy 600 welds and penetrations 6.

Residual stress and susceptibility to PWSCC of Alloy 690 CRDM penetration nozzles 7.

Degradations of steam generator 8.

Thermal embrittlement in cast and weld austenitic stainless steel 9.

FEM integrity assessment and actual test of a bend portion in an aged real plant pipe

10. Thermal embrittlement of low alloy steel and its weld exposed to PZR temperature

11. FAC and erosion in CS piping in the secondary system and BOP

12. Degradations in buried pipes and inspection performance demonstration

KHNP-CRI Course of test materials and specimens CRI Hot lab Non-Radioactive Materials (Piping, Structures)

Radioactive Materials (RV, Internals, Pipe)

CRI KHNP Maintenance Building at KORI Station (Decontamination and Machining)

Specimens

KAERI, colleges EPRI &

others KAERI Platform at KORI-1 (Cutting, Decontamination)

KHNP-CRI KHNP maintenance building in Kori station RCP maintenance facilities Separate rooms Old original Kori-1 RV head

KHNP-CRI Current Activities

Input of research plan to KHNP decommissioning plan by 2017.12

Planning of improving KHNP facilities for handling irradiated materials (2016.5.~2018.4.)

KHNP maintenance building in Kori station

CRI materials test building

Improvement of KAERI Irradiated Materials Evaluation Facility

KAERI IMEF is overcrowded

An EPRI project

Analytical assessment of residual stress in a few selected dissimilar metal nozzles in Kori-1

KHNP-CRI

3. FUTURE PLAN

KHNP-CRI Project Schedule (draft)

Phases Description Phase One (2020~2024)

Improvement of KHNP and KAERI facilities

Decontamination, movement, machining, and storage of test materials

Preliminary analytical studies

- irradiation dose, residual stress, and others Phase Two (2024~2030)

Test and evaluation Phase Three (2031~,

as needed)

Remaining tasks after completion of Phase Two

- additional irradiation test, international collaboration, and others

KHNP-CRI Others

Planning of specific projects among Korean organizations

Planning of international collaboration via EPRI

KHNP-CRI

© 2017 Electric Power Research Institute, Inc. All rights reserved.

Sherry Bernhoft Senior Program Manager NRC Ex-Plant Harvesting Workshop March 7 & 8, 2017 Ex-Plant Harvesting Workshop Session 1 EPRI Perspective

2

© 2017 Electric Power Research Institute, Inc. All rights reserved.

USED FUEL AND HIGH-LEVEL WASTE MANAGEMENT Nuclear Sector Research Areas NONDESTRUCTIVE EVALUATION RISK AND SAFETY LONG-TERM OPERATIONS EQUIPMENT RELIABILITY CHEMISTRY AND RADIATION SAFETY FUEL RELIABILITY ADVANCED NUCLEAR TECHNOLOGY MATERIAL DEGRADATION

3

© 2017 Electric Power Research Institute, Inc. All rights reserved.

EPRIs Global Membership

>320reactors worldwide GLOBAL PARTICIPANTS GLOBAL BREADTH & DEPTH Participants Encompass Most Nuclear Reactor Designs

>75% of the worlds commercial nuclear units

4

© 2017 Electric Power Research Institute, Inc. All rights reserved.

EPRI Collaborative Model Basic Research and Development National Laboratories, Universities Nuclear Utilities Collaborative Technology Development, Integration, and Application EPRI Suppliers, Vendors Inputs Solutions

5

© 2017 Electric Power Research Institute, Inc. All rights reserved.

LTO Research Focus is on Aging Management

1. Reactor pressure vessel

2. Primary system metals, welds, and piping

3. Electrical cables

4. Concrete and containment structures Priority High

6

© 2017 Electric Power Research Institute, Inc. All rights reserved.

Experience With Harvesting Takes longer and cost more than anticipated Incomplete knowledge on the pedigree of the harvested materials Roles and responsibilities not well defined Contracting is complicated Logistics, i.e. transportation and storage are challenging You can spend a lot of money and not get any value

7

© 2017 Electric Power Research Institute, Inc. All rights reserved.

EPRIs Criteria for Harvesting Needs to be of value for our members Is prioritized as a need by our members Fills a knowledge gap that can not otherwise be filled Needs to start with a well developed project plan including:

- Funding

- Risk Management plan

- Exit Ramps

- Clear roles and responsibilities

8

© 2017 Electric Power Research Institute, Inc. All rights reserved.

TogetherShaping the Future of Electricity

Plants in Decommissioning in Germany Uwe Jendrich, GRS March 7, 2017 Ex-Plant Materials Harvesting Workshop US NRC Headquarter, Rockville/MD, USA

Basic Requirements for Decommissioning NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany Regulation of decommissioning in Germany 2

Final shut down of the facility Granting of 1st decommissioning license Power Operation Post operation transition period Operation Decommissioning phase/

Direct dismantling or Safe enclosure Decommissioning

The German Regulatory System NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany Basic requirements

• For a nuclear facility the atomic energy act allows either to immediate dismantle or to dismantle after a safe enclosure Note: no entombment (near surface disposal) is allowed

• The operator of a nuclear facility is fully responsible for the decommissioning and dismantling of a nuclear facility.

• There are 4 operators of commercial nuclear reactors in Germany:

1. PreussenElektra1)

(KKS, KKI, KKU, KWG, KKG, KBR, KKE)

2. EnBW2)

(KWO, GKN, KKP)

3. RWE (KMK, KRB, KWB)

4. Vattenvall (KKB, KKK) 3 For any requests on materials: Contact the operator!

1) until recently known as E.ON Kernkraft 2)

Energie Baden-Württemberg

Overview on Decommissioning Projects in Gemany NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany Past and current decommissioning projects of Prototype or Commercial Reactors 4

Name Abbrev.

Reactor type Power MWe Decom.

started Strategy Rheinsberg KKR WWER 70 1995 UC Compact Natrium Cooled Reactor KKN SNR 21 1993 UC Multipurpose Research R.

MZFR PWR/D2O 57 1987 UC Obrigheim KWO PWR 357 2008 UC Neckarwestheim 1 GKN-1 PWR 840 2017 UC Isar-1 KKI-1 BWR 912 2017 UC Gundremmingen-A KRB-A BWR 250 1983 RCA KRB-II Greifswald 1-5 KGR 1-5 WWER 440 1995 UC Lingen KWL BWR 268 1985 UC after SE UC: unconditional clearance RCA: radiation controlled area, new license SE: safe enclosure

Overview on Decommissioning Projects in Gemany NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany Past and current decommissioning projects of Prototype or Commercial Reactors 5

Name Abbrev.

Reactor type Power MWe Decom.

started Strategy Stade KKS PWR 672 2005 UC Research Reactor Jülich AVR HTR 15 1994 UC Thorium High-Temperature-Reaktor THTR-300 HTR 308 1993 SE since 1997 Würgassen KWW BWR 670 1997 UC Mülheim-Krlich KMK PWR 1302 2004 UC Hot-Steam Reactor Grosswelzheim HDR HDR 25 1983 UC since 1998 Niederaichbach KKN DRR/D2O 106 1975 UC since 1994 Test-Reactor Kahl VAK BWR 16 1988 UC since 2010 UC: unconditional clearance SE: safe enclosure

NPPs Preparing for Decommissioning in Gemany NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany 6

Name Abbrev.

Reactor type Power MWe Date of application Philippsburg-1 KKP-1 BWR 926 2013 / 2014 Grafenrheinfeld KKG PWR 1345 2014 Biblis-A KWB-A PWR 1225 2012 Biblis-B KWB-B PWR 1300 2012 Unterweser KKU BWR 1410 2012 / 2013 Brunsbüttel KKB BWR 806 2012 / 2014 Krümmel KKK BWR 1402 2015 Shut down Commercial Reactors

• that have no decommissioning license granted yet RPV design fluence after 40 years

< 5

• 1018 n/cm²

NPPs Preparing for Decommissioning in Gemany NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany 7

Name Abbrev.

Reactor type Power MWe Anticipated date of final shutdown Gundremmingen-B KRB-II-B BWR 1344 31.12.2017 Philippsburg-2 KKP-2 PWR 1468 31.12.2019 Gundremmingen-C KRB-II-C BWR 1344 31.12.2021 Grohnde KWG PWR 1430 31.12.2021 Brokdorf KBR PWR 1480 31.12.2021 Emsland KKE PWR 1406 31.12.2022 Isar-2 KKI-2 PWR 1485 31.12.2022 Neckarwestheim-2 GKN-2 PWR 1400 31.12.2022 Commercial Reactors in operation

Overview on Decommissioning Projects in Gemany NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany Past and current decommissioning projects of Research Reactors

• Total: 35

• Removed: 29

• Final Shut down / under dismantling: 4

• Safe

Enclosure:

2

• Variety of types of Research Reactors Argonaut type Critical assembly Educational reactors Liquid homogenous reactor Propulsion reactor Pool reactor (incl. TRIGA type)

Heavy Water reactor (incl. DIDO type)

Nuclear Ship Otto Hahn during operation

© Babcock Noell GmbH Rad. transport of dismantled pressure vessel 8

Overview on Decommissioning Projects in Gemany NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany Past and current decommissioning projects of Prototype or Commercial Reactors

• Total: 21

• Removed: 3

• Final shut down / under dismantling: 17

• Safe enclosure: 1

• Reactor types:

PWR BWR Fast Breeder High Temperature Gas Cooled Heavy Water Gas Cooled 9

© Forschungszentrum Karlsruhe HDR Growelzheim

Thank you for your attention!

Role of GRS in Decommissioning and LTO Uwe Jendrich, GRS March 7, 2017 Ex-Plant Materials Harvesting Workshop US NRC Headquarter, Rockville/MD, USA

Introduction NRC Harvesting Workshop, Rockville, March 2017, Role of GRS 2

GRS with its staff of about 430 is Main Technical Support Organization (TSO) in nuclear safety for the German federal government

• BMUB (Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety),

• BMBF (Federal Ministry of Education and Research),

• BMWi (Federal Ministry of Economic Affairs and Energy) and

• AA (Federal Ministry of Foreign Affairs) and GRS participates in international activities of

• IAEA, OECD, EU (DG Energy, DG RTD, DG DevCo),

Services of GRS in Decommissioning of Nuclear Installations Advice and assessment concrete technical and legal issues strategy and planning of decommissioning projects

• Project management, progress monitoring and documentation of decommissioning projects

• Support in the drafting of regulations taking into account national specifics

• Know-how transfer individually tailored seminars and coaching elaborations on specific issues NRC Harvesting Workshop, Rockville, March 2017, Role of GRS 3

GRS Customers and References in Decommissioning BMUB:

• Various projects (since 1998):

technical and organizational requirements analysis of technical aspects, assessment of application and licensing documents BMBF:

• Project management (since 2013):

• Decommissioning, dismantling and waste management projects relating to nuclear test facilities IAEA:

• Decommissioning and Remediation of Damaged Nuclear Facilities (DAROD) (since 2015)

• Decommissioning Risk Management (DiRiMa) (since 2012)

• Constraints to implementing decommissioning and environmental remediation programs (CIDER) (2013-2015)

EBRD:

• Assistance to Bulgaria Nuclear Regulatory Agency (BNRA) decommissioning of Kozloduy NPP units 1-4 (since 2008)

NRC Harvesting Workshop, Rockville, March 2017, Role of GRS 4

GRS Activities in Ageing Management and Long Term Operation BMUB:

• Evaluation of nat. & internat. operating experience

• Nat. & internat. Regulations and Guidelines on AM EU:

• Several INSC projects on Regulatory aspects of LTO, Specific technical aspects

• JRC Database EMAR (R&D results on ageing of materials)

IAEA:

• International IGALL OECD/NEA:

• Database projects CODAP (components), CADAK (cable)

• WG IAGE, NUGENIA ANVS (NL):

• Assessment of licensing documents for LTO of Borssele NRC Harvesting Workshop, Rockville, March 2017, Role of GRS 5

Y G

R OLUTIONS E

N E

S Future Harvesting Opportunities at Decommissioning Power Plants Gerry van Noordennen March 7, 2017

E Y

G R

E N

S I

T U

L O

ONS Successful Harvesting Opportunities Require Clear Scope and Schedule

• Plant View

- There is no financial incentive to support harvesting

- The research agency must be willing to pay for the costs to surgically remove components

- The research agency must provide a clear scope and schedule at the beginning of the active decommissioning period (DECON)

- Delays in federal approvals mean lost opportunities 2

E Y

G R

E N

S I

T U

L O

ONS Flexibility is Key

• Flexibility in the removal schedule is key

- Schedule changes result in components becoming available on short notice

- The research agency must have the funds set aside from one year to the next or miss out on harvesting opportunities 3

E Y

G R

E N

S I

T U

L O

ONS Future Opportunities

• Reactor vessel surveillance coupons

- Best removed when work begins on cutting up reactor internals

• Reactor vessel weld specimens

- Only applicable for large vessels

- Smaller vessels like SONGS 1 and Ft. Calhoun shipped intact to disposal facility 4

Reactor Vessel Cutting Head

E Y

G R

E N

S I

T U

L O

ONS Future Opportunities

• Spent fuel rack coupons

- Best removed before or after spent fuel transferred to the ISFSI

- Cannot not interfere with fuel characterization or fuel transfer

• Spent fuel rack

- Removed after pool completely empty including GTCC waste

• Cabling from Harsh Environments

- Some can be harvested at any time

- High rad environment requires timing of harvest to mesh with source term removal schedule in each area 5

E Y

G R

E N

S I

T U

L O

ONS Future Opportunities

• Switchgear, Bus Ducts, Control Panels, Breakers

- Some can be harvested at any time

- Specify cable lengths needed

- High rad environment requires timing of harvest to mesh with source term removal in area

• Concrete Cores

- Cores best taken consistent with site characterization needs for License Termination Plan 6

E Y

G R

E N

S I

T U

L O

ONS Harvesting Plans Needed Now

• Plants that are entering DECON in the next 2 years need to know now if the NRC or DOE are interested in harvesting materials at these sites:

- San Onofre 2 & 3 (January 2018)

- Vermont Yankee (2019)

• Plants potentially entering DECON in the next 2 years should be contacted now:

- Kewaunee

- Crystal River

- Ft. Calhoun 7

Y G

R OLUTIONS E

N E

S Zion Harvesting Experience and Lessons Learned Gerry van Noordennen March 8, 2017

Z N

O I

S I

T U

L O

ONS An EnergySoluitons Company LLC Zion Nuclear Power Station 2

Z N

O I

S I

T U

L O

ONS An EnergySoluitons Company LLC Two 4-Loop Westinghouse PWR 3250MWt (1085 MWe)

• Construction permit December 1968

• Operating Licenses April 1973 (Unit1)

November 1973 (Unit 2)

• Shutdown (unexpected)

February 1998

• Permanently Defueled March 1998

• License transferred to EnergySolutions September 2010

• All Spent Fuel in Dry Storage January 2015

• Expected Completion April 2019 3

Z N

O I

S I

T U

L O

ONS An EnergySoluitons Company LLC Decommissioning Progress

• Plant Decommissioning is on schedule and on budget

• Currently demolishing Auxiliary Building

• Containment buildings ready for open air demolition in May 2017

• Complete building demolition by early 2018

• Show demolition video 4

E Y

G R

E N

S I

T U

L O

ONS Scope

• Zion Harvesting Program Experience

- Extensive harvesting conducted from 2011 to 2016

- Senior management supportive of program

- Reassignment of plant personnel to support harvesting program

- Demolition organization generally not supportive but tolerated surgical removal of components

- Demolition did not stop for harvesting

- Harvested items only have scrap value 5

E Y

G R

E N

S I

T U

L O

ONS Items Harvested

• Reactor Vessel Material Surveillance Capsules

- Capsules were removed during reactor internals cutting and stored on the reactor cavity floor

- Capsule designators were very hard to read

- Only one capsule had research value (X)

- Zion attempt to identify capsule markings failed

- Capsule X ended up being disposed of by the time contract issues were worked out with Westinghouse to retrieve capsule

- Result: All capsules disposed as radwaste 6

E Y

G R

E N

S I

T U

L O

ONS Reactor Vessel Weld

• Reactor vessel beltline weld

- Reactor vessels cannot be rotated in cutting machine

- Vessel cutting plan looked like it would work for vessel specimen harvesting plan

- Unit 2 beltline weld was too close to cut line so torch could have affected metal properties

- Unit 1 cut line was far enough away from weld to obtain a successful specimen 7

E Y

G R

E N

S I

T U

L O

ONS Safety-Related Cabling Cabling harvested from Unit 1 (11 Tasks)

1. East Valve House near Steam Tunnel

2. Instrument cabling inside missile barrier

3. Loop Isolation Valve cabling

4. Accumulator discharge valve MOV cabling

5. Instrument Rack cabling in containment

6. Air-operated valve cabling

7. Electrical penetrations assembly and cables

8. Electrical penetration cabling in Aux Bldg.

9. Pressurizer heater cables

10. Cables in steam tunnel

11. Submerged cable in Turbine Bldg. to Crib House 8

E Y

G R

E N

S I

T U

L O

ONS Safety-Related Cabling Experience

• Only some of the cables harvested.

- Changing priorities

- Demolition crew not cognizant of research needs

• Cable lengths of 30 feet were difficult to obtain in some instances. Could only get 10 feet.

• Cable type, age and environment were generally available from plant records 9

E Y

G R

E N

S I

T U

L O

ONS Fire Testing Program

• Bus bar section ( 8 feet) removed along with any remaining support hardware and isolators

• 480-volt distribution center removed

• 480-volt motor control center removed

• Control Room Control Panel removed

• Instrument Rack removed in Aux. Bldg..

• 4KV Switchgear, Relays and Breakers removed

• ISO-Phase Bus Duct removed 10

E Y

G R

E N

S I

T U

L O

ONS Concrete Core Bores

• Planned to take core bores in containment and under spent fuel pool liner

• Task cancelled by ORNL 11

E Y

G R

E N

S I

T U

L O

ONS Spent Fuel Pool Storage Racks

• Spent Fuel Pool Testing completed for boron degradation

• Remaining coupons retrieved

• Storage rack piece cut and shipped

• Good onsite coordination with EPRI and NRC

• Most work completed during weekend 12

E Y

G R

E N

S I

T U

L O

ONS Lessons Learned

• Changing scope leads to frustration on both sides

• Delays in paper work for each task authorization lead to lost opportunities

• Plan early

• Obtain senior plant management support

• Have someone on site when harvesting takes place

• Be able to deal with changing plant support personnel 13

US Nuclear Science User Facilities (NSUF)

Overview J. Rory Kennedy, Ph.D.

Director, NSUF Idaho National Laboratory March, 2017

2 NSUF General Established 2007 as DOE Office of Nuclear Energy first and only user facility Idaho National Laboratory is lead institution Irradiation effects in nuclear fuels and materials Provide access to capabilities and expertise at no cost to user Support design, fabrication, transport, irradiation, PIE, disposition Link intellectual capital with nuclear research infrastructure to fulfill mission of DOE-NE Generally select projects through open competitive proposal processes Consolidated Innovative Nuclear Research (CINR FOA, 1 call/year)

Irradiation + PIE ($1.0M - $4.0M, up to 7 years)

PIE only (~$500K, up to 3 years)

Irradiation only ($500K - $3.5M)

Beamlines at other user facilities Rapid Turnaround Experiments (RTE, 3 calls/year, limited $$, executed within 9 months)

Proposals welcome from University, National Laboratory, Industry, Small Business, Intl researchers 2

3 NSUF - A consortium A group formed to undertake an enterprise beyond the resources of any one member Partner Facilities to date

8 Universities + 3 Universities in CAES (3 currently expressed interest)

4 National Laboratories (4 expressed interest)

1 Industrial Expanded capabilities

Need for additional capabilities outside INL recognized early

Partner facilities program established in 2008

4 NSUF General Capabilities Neutron Irradiations ATR (loop, rabbit), ATRC, HFIR (rabbit), MITR (loop), PULSTAR, NRAD (Future: BR2 - SCK-CEN Belgium), Halden - Norway ?)

Ion Irradiations Tandem Accelerator Ion Beam (U. Wisc), Michigan Ion Beam Lab (U. Mich), IVEM (ANL)

(Future: TAMU, SNL, LANL)

Hot Cells INL(HFEF, FCF, AL, IASCC), ORNL (IFEL, IMET, REDC), PNNL (RPL), U. Mich (IMC),

Westinghouse (MCOE)

High radiation level measurements/instrumentation Neutron radiography, elemental & isotopic analyses, gas sampling and analyses, profilometry, gamma scanning, mechanical testing, electron and optical microscopy, thermal analyses, eddy current, IASCC, EPMA, AES, XPS, SIMS, focused ion beam (FIB)

Low radiation level measurements/instrumentation SEM, TEM, APT, FIB, hardness, micro- & nano-indentation, tensile, thermal analyses, XRD, XPS, AES, SIMS, NMR, PAS Beamlines X-ray (ANL APS: MRCAT, IIT; BNL NSLS-II: XPD, NST Dept)

Neutron, positron (PULSTAR, NCSU)

High Performance Computing FALCON machine Moose-Bison-Marmot Visit nsuf.inl.gov under Research Capabilities tab for details at individual facilities

5 NSUF and GAIN Gateway for Accelerated Innovation in Nuclear (GAIN)

Technology Readiness Levels (TRL) 10 100 1000 Investment Levels ($M)

R&D TEST BED Rapid and cost-effective advancement of scientific underpinning and retirement of technical and licensing risk for innovative technologies.

DEMO PLATFORM Reduce the commercialization cost and associated risk by minimizing one-time costs. Reduce the cost uncertainty for commercial units.

9 1

3 5

8 2

7 4

6 Proof-of-Concept Proof-of-Performance Proof-of-Operations for 1st time cost

6 High Impact Nuclear R&D Project portfolio spans a variety of research objectives that are ultimately focused on both near and long-term technology development goals Understanding atomic level phenomena in fuels that affect thermal transport, elemental migration/diffusion, interface interaction, etc. as complex microstructures develop under irradiation

• ceramic, metallic, TRISO, ATF Understanding fundamental defect evolution in irradiated structural materials across multiple length scales as they affect mechanical properties.

• RPV, austenitic, F/M, Zr alloys, ATF Development of innovative radiation resistant materials for advanced reactor systems Development of radiation resistant sensors for collecting high fidelity on-line irradiation test data Development of materials from advanced manufacturing techniques Providing fundamental actinide nuclear data that can help inform advanced reactor and fuel cycle modeling and simulation campaign. J. Cole contributed to content of slide

7 Infrastructure Management Program Used for analyses to identify needs, redundancies, efficiencies, distributions, etc., to best understand the utility of DOE-NEs available infrastructure, inform the content of infrastructure calls, and provide information to NSUF users.

Infrastructure information collected can be combined with information on R&D needs as part of infrastructure gap analysis NSUF created a searchable and interactive database of all pertinent infrastructure supported by, or related to, the DOE Office of Nuclear Energy (DOE-NE).

Database known as the Nuclear Energy Infrastructure Database (NEID) and is located at nsuf-infrastructure.inl.gov (public launch Nov 2015)

8 Nuclear Fuels and Materials Library (NFML)

INL Legacy materials Volunteered materials from outside the INL Supporting documentation related to samples Provides irradiated samples for users to access for experimentation through one of the competitively reviewed proposal processes.

Critical to reducing costs and taking advantage of new ideas and future analysis techniques and equipment.

The library includes over 3500 specimens as part of the NSUF awarded research. 6K - 7K additional specimens by year end.

Most materials in NFML neutron irradiated with small number ion irradiated.

SAM irradiation series to stock library moving forward Effort to consolidate materials into easily accessible locations to reduce costs of retrieval.

Web-based searchable database through nsuf.inl.gov (public launch Sept 14, 2016).

Interest in collaboration on international efforts.

Materials Include:

Steels Other alloys Ceramics Pure materials Actinides Fission products

9 SAMPLE LIBRARY Temperature Dose (DPA)

Flux [x1014 ]

Fluence [x1020]

Environment PLANNED Temperature Actual Dose (DPA)

Flux [x1014 ]

Fluence [x1020]

Environment AS RUN PROJECT NAME Storage FACILITY Notes

1. of Samples Samples Remaining Specimen Availability Certification Certification Code Availability Date Capsule Packet Material Name Material Description Dimensions KGT #

Sample ID Code Material Code Specimen Type REACTOR REACTOR POSITION Project ID CINR #

RTE #

NSUF Call Award Date Start Date End Date PI Name Tech Lead Facility Tech Lead Collaborators Related Documents Project Type INSTITUTION FACILITY Research Area Material Type Proposal PROJECT DATABASE PROJECT NAME REACTOR REACTOR POSITION FACILITY INSTITUTION NEID DATABASE SME DATABASE INSTITUTION PI Name Subject Matter Databases Design

10

Kewaunee Power Station Insights on Material Harvesting 1

Kewaunee Power Station 2

Kewaunee Power Station 3

Kewaunee Power Station 2-Loop Westinghouse PWR (590MWe)

Construction permit August 1968 Operating license December 1973 Initial operating license expiration December 2013 Renewed Operating License Issued February 2011 Shutdown decision (unexpected)

October 2012 Permanently Shutdown May 2013 ERO offsite response eliminated November 2014 All nuclear fuel in dry storage July 2017 4

Kewaunee Perspective Top priority for decommissioning plants is preserving and good stewardship of the decommissioning trust fund Highest fund drain is staffing Station electrical use also expensive Initial decommissioning actions focus on safety and cost reduction.

Use initial required large staff to prepare plant for long term dormancy and decommissioning Abandon or downsize equipment to reduce ongoing costs.

Then reduce staff commensurate with reduction in risk 5

Kewaunee Power Station 6

630 300 163 147 50 0

100 200 300 400 500 600 700 4/1/2012 8/14/2013 12/27/2014 5/10/2016 9/22/2017 2/4/2019 Kewaunee Decommissioning Staffing Reductions

Kewaunee Perspective Timing is everything!

Perhaps best discussed via an example:

Reactor vessel surveillance capsules Two remain in the vessel Logistical considerations:

7

Kewaunee Perspective Circulating Water pumps were high energy consumers Therefore we wanted to retire them as soon as possible Circulating Water pumps were high capacity, low head, very good at dilution for meeting ODCM requirement for radiological discharges Without CW pumps, much smaller capacity service water pumps will be used in the future for dilution..

8

Kewaunee Perspective Therefore - prior to retiring CW pumps, we processed as much radioactive water as possible This included draining the RCS RCS at Kewaunee has no loop isolation valves RCS today is drained to the bottom of the cold legs, about 7 feet below the RV flange RV internals are installed, RV head is on the vessel, flux thimbles are installed in the vessel 9

Kewaunee Perspective So if we wanted to remove surveillance capsules today we would face unique challenges that would not have been present at initial plant shutdown:

Shielding - need to refill the RV (and cavity?)

Lifting the RV head and internals - polar crane is in place, but maintenance has been discontinued Qualified staff - Crane operators, RP technicians, maintenance, operators Rad monitors (many have been abandoned)

Ventilation and atmosphere control, lighting 10

Kewaunee Perspective What generic issues could be resolved or simplified by harvesting and additional testing?

GALL aging management program examples Electrical cables and connections - test power cables taken from adverse localized environments SG divider plates; autogenous welds Buried piping; Inaccessible power cables (buried; underground) 11

Additional Considerations Who will pay?

Why is the material needed?

Whats in it for me?

Are we solving an industry problem? (example -

SFP neutron absorbing material GL 2016-01)

Objectively needing more information to determine if we have a new problem?

Whats the plan? What is done with the information gathered? Is there a driver to review impact on existing programs?

12

Additional Considerations Need to think ahead, plan ahead Some harvesting is very plant condition specific, others maybe not What plants will be entering decommissioning in the future?

Have you reached out to them?

Scope, Schedule, Budget 13

Kewaunee Perspective 14

© 2017 SCK*CEN Review of Past Reactor Pressure Vessels Test Programs and Perspective for Long Term Operation Rachid Chaouadi 1, François Henry 2, and Guy Roussel 3 1 SCK*CEN Mol, 2 FANC/AFCN Brussels, 3 Bel-V Brussels (Belgium)

Ex-Plant Materials Harvesting Workshop USNRC, Washington, March 7-8, 2017 federaal agentschap voor nucleaire controle agence fédérale de contrle nucléaire 1

© 2017 SCK*CEN Outline Part I : Past test programs analysis Focus on RPV materials (excl. stainless steel cladding, internals, vessel concrete containment, )

Literature survey of test programs on decommissioned RPVs 2 PWRs + 2 VVER-440 + 1 PWR and 1 Magnox gas-cooled reactor Brief description of main outcome and limitations Part II : Discussion (assuming that we are convinced of the benefits of such a test program via vessel sampling)

Approach / criteria for selection Potential issues of interest Organizational and financial aspects Perspective for the future 2

© 2017 SCK*CEN Overview of Investigated RPVs reactor location type (electrical power) start shutdown sampling/

testing BR3 (YR)

Belgium PWR (11 MWe) 1963 1987

~1995-1999 Chooz-A France PWR (305 MWe) 1967 1991

~1995-1999 Greifswald-1 to 4 Germany VVER-440 (408 MWe) 1974

-1979 1990

~2004-2012 Novovoronesh-1 Russia VVER-440 (408 MWe) 1964 1984

~1993-2000 Gundremmingen-A Germany BWR (237 MWe) 1966 1977

~1988-1992 Trawsfynydd UK Magnox (195 MWe) 1965 1991

~1996-2002 PWR (BR3 and Chooz-A)

VVER-440 (Greifswald and Novovoronesh)

BWR (Gundremmingen)

Magnox gas-cooled (Trawsfynydd) 3

© 2017 SCK*CEN Overview of Investigated RPVs reactor condition Tirrad

(°C) materials max (1019 n/cm²,

E>1MeV) composition Cu/Ni/P (%)

data sets BR3 (PWR)

IAR 260 Ni-mod A302B 4

0.2/0.6/0.02 single Chooz-A (PWR)

I 255-265 1.2MD07 (A336) 2 0.1/0.6/0.02 multiple through thickness Greifswald-1 to 4*

(VVER-440)

I, IA, IAR, IARA 255 10KhMFT 2

0.15/0.3/0.04 multiple through thickness Novovoronesh-1 (VVER-440)

I, IA 250 (228) 15Kh2MFA 1.4 0.15/0.1/0.03 single Gundremmingen-A (BWR)

I 284-288 20NiMoCr26 (A 336) 0.3 0.2/0.5/0.01 multiple through thickness Trawsfynydd (Magnox-gas cooled)

I 190 manual SA weld 0.2 0.26/0.1/0.04 mixture Legend : I = as-irradiated ; IA = I + annealing ; IAR = IA + re-irradiation ; IARA = IAR + annealing

• No relation between units 1 to 4 and I, IA, IAR, IARA 4

© 2017 SCK*CEN Overview of Investigated RPVs All low Ni / medium Cu / medium to high P Modern steels : low Cu and low P reactor Cu Ni P

test (T, CVN, FT)

BR3 (YR)

BM 0.19 0.56 0.02 T, CVN, FT Weld Chooz-A BM 0.08-0.10 0.59-0.61 0.010-0.015 T, CVN, FT Weld 0.08-0.09 0.13-0.21 0.010-0.016 FT Greifswald-1 to 4 BM 0.13 0.18 0.01 CVN, FT Weld 0.12-0.18 0.19-0.29 0.032-0.036 CVN, FT Novovoronesh-1 BM 0.15 0.13 0.015 Weld 0.12 0.12 0.033 CVN Gundremmingen-A BM 0.16 0.74 0.013 T, CVN Weld 0.24 0.11 0.009 CVN Trawsfynydd BM Weld 0.24-0.27 0.10-0.11 0.034-0.038 FT T = tensile CVN = Charpy impact FT = fracture toughness 5

© 2017 SCK*CEN BR3 (PWR)

Conservative regulatory RPV integrity assessment due to Ni-content, temperature and grain size.

Actual embrittlement conditions are less than predicted after comparison with other surrogate materials and direct measurements of fracture toughness on the vessel material.

6

© 2017 SCK*CEN Chooz-A (PWR)

Demonstration of the validity of the surveillance program for the base metal.

Fracture toughness data on the weld metal were all well bounded by the fracture toughness lower bound curve established in the unirradiated condition (KIc based on RTNDT).

Chooz-A Weld unirradiated KIc Source :

ASTM STP 1405 (2001) 28-41.

7

© 2017 SCK*CEN Greifswald (VVER-440)

Charpy impact T47J Master curve Master curve IAR-condition IAR-condition I-condition IA-condition 8

© 2017 SCK*CEN Novovoronech-1 (VVER-440)

Non-uniform through wall distribution of P-content in the weld.

Large scatter in embrittlement based on Charpy impact transition temperature T47J.

Less scatter when master curve T0 is used.

No comparison to surveillance data.

9

© 2017 SCK*CEN Gundremmingen-A (BWR)

Significant effect of specimen orientation (T-L versus L-T) on T41J and USE.

Effect of specimen orientation.

Significant effect of specimen location in the base metal.

Uniform through wall chemical composition of the weld.

10

© 2017 SCK*CEN Trawsfynydd (Magnox)

Uniform chemical composition (through wall)

Good agreement with surveillance data Allowed the demonstration of the safety integrity approach followed for this type of reactors.

11

© 2017 SCK*CEN Outcome reactor outcome BR3 (PWR)

Conservative regulatory RPV integrity assessment due to Ni-content, temperature and grain size. Actual embrittlement conditions are less than predicted after comparison with other surrogate materials and measurements of fracture toughness on the vessel material.

Chooz-A (PWR)

Demonstration of the validity of the surveillance program of the base metal. Fracture toughness data on the weld metal were all bounded by the fracture toughness lower bound established in the unirradiated condition.

Greifswald-1 to 4 (VVER-440)

Uniform chemical composition of the weld through the wall thickness except at the weld root but large scatter in the transition temperatures without correlation to the neutron exposure. Scatter attributed to local microstructure (coarse versus fine). Annealing at 475°C/152h allows an effective recovery. No comparison to surveillance data.

Novovoronesh-1 (VVER-440)

Non-uniform through wall distribution of P-content in the weld. Large scatter in embrittlement based on Charpy impact transition temperature T47J. Less scatter when master curve T0 is used. No comparison to surveillance data. Post-irradiation annealing was also investigated and showed that 600°C/2h leads to an effective recovery.

Gundremmingen-A (BWR)

Significant effect of specimen orientation (T-L versus L-T) on the transition temperature T41J and upper shelf energy. Effect of specimen orientation complicated the comparison to surveillance data. A significant effect of specimen location was observed for the base metal. Uniform through wall chemical composition of the weld.

Trawsfynydd (Magnox-gas cooled)

Good agreement with surveillance data. Allowed the demonstration of the safety integrity approach followed for this type of reactors.

12

© 2017 SCK*CEN Limitations Materials Gen-I materials (BR3 + Chooz-A), VVER-440 welds (high P >0,03%)

Limited to small areas of the reactor vessels Many of these vessels were annealed BR3 (ineffective : 343°C/168h),

Greifswald-1, -2 and -3 (effective : 475°C/152h)

Material variability (VVER-Welds, Gundremmingen base metal)

Systematic absence of archive materials (except Gundremmingen)

Environment Majority irradiated at low temperature : 190 to 265°C except Gundremmingen (~288°C)

Change of temperature during operation : Chooz-A (265 255°C) and Novovoronesh (250 228°C)

Poor and/or unreliable surveillance program (except Chooz-A)

Poor and/or unreliable dosimetry 13

© 2017 SCK*CEN Discussion 14

© 2017 SCK*CEN Approach Vessel selection Do we have a choice ?

If yes, what are the selection criteria ? There are many :

Materials composition and damage levels Operation history (neutron fluence, irradiation temperature)

Availability of reliable surveillance data Availability of archive materials Other aspects : material variability, presence of segregated zones, Choice dependent on the targeted objectives What are the priorities International participation There is no ideal choice (except if infinite available budget)

Consensus 15

© 2017 SCK*CEN Selection Criteria Materials Preferably representative of modern reactors (LTO)

More systematic examination using many parts of the vessel (axial and azimuthal)

Available archive materials Irradiation environment LTO-representative fluence levels (> 1019 n/cm², E>1MeV)

Irradiation temperature ~290°C (majority of operating reactors)

Operation history and monitoring Well documented operation history Reliable temperature monitoring Reliable dosimetry Reliable surveillance program 16

© 2017 SCK*CEN Material Variability Material variability scatter Complicates the interpretation of the test results Increase the number of tests and use statistics Important details might be shadowed by the large scatter If the vessels are really inhomogeneous This should be taken into account in safety integrity assessment Check the adequacy of the surveillance program with respect to representativity of the whole vessel What should we favor and at which cost ?

For better understanding and validation of procedures with a minimum of tests (least scatter) or Application (real components) to check whether such material variability is covered by the available safety margins Alternative : availability of multiple locally homogeneous areas 17

© 2017 SCK*CEN Issues Materials (at multiple locations)

Homogeneity of chemical composition Homogeneity of mechanical properties Identification of segregated area and further analysis Identification of LTO-relevant areas and further analysis Neutron exposure Verification of the neutron calculations dosimetry measurements Through-wall fluence attenuation Vessel versus surveillance program Mechanical properties : vessel versus surveillance Verification of master curve shape at high KJc Thermal ageing assessment Neutron flux/spectrum effects Assessment of regulatory procedures 18

© 2017 SCK*CEN Organizational Aspects International participation As large as possible In-kind contributions Agreement on the project contents Main topics Vessel selection and sampling Materials transportation Work share and distribution Timeline Start date : 2017 4-5 yr project (benefit of operating reactors) 19

© 2017 SCK*CEN Financial Aspects Vessel trepanning If the vessel will be anyway cut in small pieces for final storage, the costs will be limited additional work mainly If the vessel was planned to be buried as a whole, then we will have to pay very much all costs SCK*CEN experience BR3 sampling : several trepans taken from the inner side of the vessel ~0,4 M ( of 1995) by PCI Energy Services, Illinois US BR3 dismantling team : several large trepans ~100 k ( of 1995)

Possible more accurate evaluation Westinghouse Belgium : Mr Joseph Boucau 20

© 2017 SCK*CEN Closing Remarks To be effective, need of international program (work sharing)

Focus on most critical issues (prioritization)

Discussion : What do we want to do ?

Which reactor vessel ? Materials compositions ? Irradiation conditions (temperature, fluence) ?

Specifications and requirements ?

Technical issues to be addressed ?

Work sharing ?

Financial aspects ? Vessel sampling costs : depend on decommissioning strategy Materials management and transportation Planning

Thanks for your attention 21

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SCK*CEN Studiecentrum voor Kernenergie Centre d'Etude de l'Energie Nucléaire Belgian Nuclear Research Centre Stichting van Openbaar Nut Fondation d'Utilité Publique Foundation of Public Utility Registered Office: Avenue Herrmann-Debrouxlaan 40 - BE-1160 BRUSSELS Operational Office: Boeretang 200 - BE-2400 MOL 22