HI-STORM UMAX: Holtec s Underground Dry Storage System

Similar documents
SONGS Dry Cask Storage System. Defense in Depth

Community Engagement Panel ISFSI Location and Technology Option Update July 17, For internal use only

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C SAFETY EVALUATION REPORT

Re: Holtec HI-STORM UMAX Canister Storage System Amendment 1 (CoC No. 1040)

Jayant Bondre AREVA TN

California s Nuclear Waste Problems and Solutions

Light years ahead! AREVA TN Americas 1/22/2015. Prakash Narayanan AREVA TN INMM Spent Fuel Management January 2015

SPENT NUCLEAR FUEL DRY STORAGE FACT SHEET

Dry storage systems and aging management

Letter with Enclosure

H.R relies on the NRC for all safety issues. However, the NRC provides limited safety evaluations.

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS WASHINGTON, DC

Nuclear Energy. Consolidated Interim Storage Facility Design Concepts In the United States. Nuclear Fuels Storage and Transportation Planning Project

The paper includes design and licensing status of the MAGNASTOR system, and prototyping development that NAC has performed to date.

The following considerations are taken into account for designing the NUHOMS MP197 packaging.

CHARACTERISTICS AND COMMON VULNERABILITIES INFRASTRUCTURE CATEGORY: NUCLEAR SPENT FUEL STORAGE FACILITIES

Interim Storage of Used Nuclear Fuel. The Nuclear Energy Institute

Investigations of Stress Corrosion Cracking of Spent Fuel Dry Storage Canisters Used for Long-Term Storage

Development of Chloride- Induced Stress Corrosion Cracking (CISCC) Aging Management Guidelines


SONGS ISFSI EXPANSION PROJECT SOUTHERN CALIFORNIA EDISON COASTAL DEVELOPMENT PERMIT APPLICATION PACKAGE ATTACHMENT A: PROJECT DESCRIPTION

Tip-Over Analysis of the HI-STORM Dry Storage Cask System

NDT AUDIT Z LLC. An EnergySoluitons Company. Audit Status. Interviewed 3 Finalist. Close to Awarding the Audit

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

Division of Spent Fuel Management Interim Staff Guidance 2, Revision 2. Fuel Retrievability in Spent Fuel Storage Applications

SPENT FUEL STORAGE IN BELGIUM

The Westinghouse Advanced Passive Pressurized Water Reactor, AP1000 TM. Roger Schène Director,Engineering Services

FIG. 1. Fort St. Vrain Nuclear Generation Station.

The CRP on Demonstrating Performance of Spent Fuel and Related Storage System Components during Very Long Term Storage (CRP T13014)

Spent Nuclear Fuel and Low Level Radioactive Waste: Current and Future Storage Options

Spent Fuel Transportation

Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life

Spanish Spent Fuel Transport

U.S. Department of Energy Office of Nuclear Energy, Response to IPC 1000 Independence Ave SW. Washington, DC

BEFORE THE PUBLIC UTILITIES COMMISSION OF THE STATE OF CALIFORNIA ) ) ) ) ) )

Reactor Technology: Materials, Fuel and Safety. Dr. Tony Williams

CURRENT STATUS ON THE SPENT FUEL DRY STORAGE MANAGEMENT IN TAIWAN

Demonstrative Drop Tests of Transport and Storage Full-Scale Canisters with High Corrosion-resistant

EPRI s CISCC R&D Roadmap and Development of CISCC Aging Management Guidelines. Shannon Marie Chu

Palo Verde Nuclear Generating Station. Asset to Arizona and the entire Southwest. Mark Fallon Director, Communications

PACKAGING AND TRANSPORTATION SYSTEM FOR THE K-BASIN SPENT FUEL - COMPONENT TESTING

SMR An Unconditionally Safe Source of Pollution-Free Nuclear Energy for the Post-Fukushima Age

Zion Project Overview S. Chris Baker VP EH&S

Collection and safekeeping of TRIGA Spent Nuclear Fuel

WM2012 Conference, February 26 - March 1, 2012, Phoenix, Arizona, USA

Power Reactor Decommissioning: U.S. Perspective on Regulatory Insights and Challenges

CONSTOR SPENT NUCLEAR FUEL STORAGE AND TRANSPORT CASK SYSTEM

Newsletter. Headlines. Number 23 - December 2014

7/15/2015 Federal Register, Volume 80 Issue 44 (Friday, March 6, 2015)

August 30, State Lands Commission ATTN: Cynthia Herzog

Demonstration Test Program for Long term Dry Storage of PWR Spent Fuel

Activities of the NRC s Division of Spent Fuel Management: An Overview

Journal of American Science 2014;10(2) Burn-up credit in criticality safety of PWR spent fuel.

THE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY. Edwin Lyman Union of Concerned Scientists May 26, 2011

European Experience In Transport / Storage Cask for Vitrified Residues

New England Coalition VT. NH. ME. MA. RI. CT. NY - POST OFFICE BOX 545, BRATTLEBORO, VERMONT (802)

Fuel Reliability Guidelines. EPRI Fuel Reliability Program

Operational Challenges of Extended Dry Storage of Spent Nuclear Fuel 12550

Draft Report for Comment

Westinghouse AP1000 Nuclear Power Plant

NUCLEAR. Nuclear Reactor Pressure Vessel Seals

Technological Solutions of SF Storage in the World

Boiling Water Reactor Vessel and Internals (QA)

DISPOSITION OF ORNL S SPENT NUCLEAR FUEL*

Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation

Decommissioning of Dairyland Power s Lacrosse Boiling Water Reactor

AP1000 The PWR Revisited

Post Fukushima Safety Margins

Methodology for a Safety Case of a Dual Purpose Cask for Storage and Transport of Spent Fuel

Ensuring Spent Fuel Pool Safety

SPENT FUEL STORAGE MANAGEMENT IN INDONESIA. SUMARBAGIONO Radioactive Waste Technology Center, Indonesian National Nuclear Energy Agency (BATAN)

LINKING THEORY AND PRACTICE

Pressurized Water Reactor Materials Reliability Program

Effective Aging Management of Baffle-to-Former Bolts to Assure Long-Term Reliability of Reactor Vessel Internals

An optimized cask technology for conditioning, transportation and long term interim storage of «End of Life» nuclear waste


Boiling Water Reactor Vessel and Internals Project (QA)

Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant

Long-Term Interim Storage of Spent Nuclear Fuel and HAW in Dual Purpose Casks Perspectives and Challenges

AGING MECHANISMS INFLUENCE ON TRANSPORT SAFETY OF DUAL PURPOSE CASKS FOR SPENT NUCLEAR FUEL. Bernhard Droste, Frank Wille, Steffen Komann

Chloride-Induced Stress Corrosion Cracking Tests and Example Aging Management Program

Spent Fuel Management and Research Activities in Korea

A Liquidation Strategy of Fukushima Daiichi Nuclear Power Plant: A new In-Situ Entombment Plan proposed

Application of Selected Safety Requirements from IAEA SSR-2/1 in the EC6 Reactor Design

Boiling Water Reactor Vessel and Internals

Dominion North Anna Power Station Restart Readiness

SECTION I FLEXIBLE PIPE VS. RIGID PIPE (GENERAL)

Selection of Stainless Steels for Nuclear Applications

WM2016 Conference, March 6 10, 2016, Phoenix, Arizona, USA

Pressurized Water Reactor Materials Reliability Program (QA)

IAEA Spent Fuel Performance Assessment and Research Programmes (SPAR II and III) Ferenc Takáts

Integrity Assessment of CANDU Spent Fuel During Interim Dry Storage in MACSTOR

INDUSTRIAL PIPE FITTINGS, LLC

DESIGN EVALUATION OF A LARGE CONCRETE CASK TO MEET IP-2 REQUIREMENTS

Ensa Solutions for Interim Dry Spent Fuel Storage & Transportation

CASE STUDY: RH-TRU WASTE TRANSPORTATION FROM BATTELLE COLUMBUS LABORATORIES. James H. Eide Battelle Columbus Laboratories

RESUME of SCOTT ATWATER

Salem/Hope Creek License Renewal Presentation to the NRC March 16, 2009

RECOMMENDATION 2.3: SEISMIC. The U.S. Nuclear Regulatory Commission (NRC) is issuing this information request for the following purposes:

Nuclear Regulatory Commission (NRC) Review of Reducing the Hazards from Stored Spent Power-Reactor Fuel in the United States 1

Transcription:

HI-STORM UMAX: Holtec s Underground Dry Storage System State-of-the-Art Solution for the Safety and Security of the People and Environment at SONGS A Presentation to Community Stakeholders By: Kris Singh, PhD, PE President & CEO, Holtec International October 14, 2014 San Juan Capistrano, California

Topical Outline 1) Overview of Holtec International and Holtec s HI-STORM UMAX System Design and Implementation 2) Defense-in-Depth, Maintenance, and Surveillance Requirements Performance Monitoring Program 3) Anticipated Aging Management Plan Canister Monitoring On-Going Developments 4) Mitigation of Degraded Canister Damaged Canister Storage Plan 2

Overview of Holtec International Holtec is a U.S. Owned Company with Four Operation Centers in Four States Holtec has a large international footprint in used fuel management with 67 nuclear units, including Chernobyl. Ringhals Forsmark Palisades Oskarshamn Clab Beznau Doel Tihange Chernobyl Holtec has the Most Transportable Dry Storage Systems Loaded Worldwide 3

Overview of Holtec International Examples of Holtec s Technology Leadership in Dry Storage Secured license for the first multi-purpose canisters in the U.S. (1998). Secured license of America's first dual-purpose cask, HI-STAR 100 (1998). Pioneered the certification of canning for storing vulnerable or damaged fuel in the welded canister; a large number have been successfully loaded around the world (Illinois, Oregon, California, and Spain). First to obtain the license to store high burnup fuel (2001). Licensed industry's first transport cask, HI-STAR 180 for high burnup and MOX fuel (2009). Holtec holds more Patents on Used Fuel Management Technologies than all World Suppliers Combined 4

Overview of Holtec International Holtec has Licensed a Fleet of Used Fuel Transport Casks Industry leader in obtaining transport cask licenses over the past 5 years. Certification effort for Holtec's universal transport cask (HI-STAR 190, proposed for SONGS) is underway; Expected to receive NRC license in 2015. HI-STAR 100 HI-STAR 180 HI-STAR 180D HI-STAR 60 HI-STAR 120 HI-STAR 190 5

Essential Features of Holtec s HI-STORM Dry Storage Systems Canisters are stored vertically. Reduced rate of solute deposition on vertical surfaces. Vertically oriented fuel rods provide significant selfshielding. Entire shell surface can be conveniently inspected. Biological shielding uses structural steel with enclosed concrete to prevent spalling of concrete due to aging. Steel structure is more resistant to incident missiles or crashing airplanes. HI-STORM UMAX Cavity 6

Introduction to Holtec s HI-STORM UMAX Underground Dry Storage System Reinforced Concrete Top Pad 24,000 lb. Steel/Concrete Closure Lid Corrosion-Resistant Stainless Steel Spent Fuel Canister Solid Concrete Monolith Corrosion-Resistant Stainless Steel Liner Reinforced Concrete Base Mat 7

Constituent Components of the HI-STORM UMAX System for SONGS Multi-Purpose Canister (MPC-37) Meets the most stringent ASME Code. HI-STORM UMAX Underground storage module designed for virtually zero dose, low profile, full protection from extreme environmental events. HI-TRAC VW On-Site Transfer Cask Assures safe movement of the MPC during on-site loading and transfer operations from the spent fuel pool to the HI-STORM UMAX. HI-STAR 190 Off-Site Transportation Cask Qualified to transport MPC-37 containing highburnup fuel. 8

Holtec s HI-STORM UMAX Multi-Purpose Canister Canister shell is made of 5/8- inch thick, high-quality, stainless steel type 316L, providing extreme corrosion resistance in marine environments. Canister lid (9.5-inches thick) is strength welded to the shell, and further protected by a redundant closure ring to ensure long service life. Canister is licensed for the storage of Damaged Fuel Containers ( cans ). HI-STORM UMAX Canister (MPC-37) 9

Holtec s HI-STORM UMAX System Design and Implementation Decommissioning Benefits of Vertical Storage and MPC-37 MPC-37 stores 37 used fuel assemblies High storage capacity of MPC-37 requires fewer storage system and fewer off-site transports. Enables expedited defueling of the spent fuel pools. Enables prompt decommissioning of the site. High heat rejection capacity of MPC-37 (47kW) ensures low fuel cladding temperature in service. Keeps fuel in the orientation (vertical) for which it is designed. No risk of creep-induced deformation in long-term storage. MPC-37 stands on solid ground. MPC-37 Canister 10

Holtec s HI-STORM UMAX System Design and Implementation Installing the loaded canister in HI-STORM UMAX is a simple, low dose operation that relies only on gravity. Canister is vertically stored underground in a clean, dry cavity. HI-STORM UMAX MPC-37 being Installed in the Underground Cavity 11

Holtec s HI-STORM UMAX System Design and Implementation Holtec s HI-STORM UMAX will have 73 dry storage cavities to defuel the spent fuel pools compact footprint. 12

Holtec s HI-STORM UMAX System Design and Implementation High Seismic Canister Storage in California In California, Holtec deployed the first anchored aboveground dry storage system at Diablo Canyon and later deployed underground dry storage systems at Humboldt Bay. Underground Vertical Dry Storage Systems at Humboldt Bay (2006) Anchored Vertical HI-STORM Systems at Diablo Canyon (2003) 13

Holtec s HI-STORM UMAX and MPC-37 System Design and Implementation HI-STORM UMAX Excels in Dose Attenuation, Seismic Resistance, and Security Extreme Seismic Resistance Capability: exceeds SONGS specified earthquake criteria HI-STORM UMAX underground storage cavities are encased by a 25 feet thick concrete monolith. Dose: Indistinguishable from background radiation at the boundary fence Aesthetics and Security: Visually inconspicuous HI-STORM UMAX ISFSI 14

Holtec s HI-STORM UMAX System Design and Implementation HI-STORM UMAX Cavity is Invulnerable to Ground Water Ingress, Fire, Flood, and Tsunami There is no path for ground water to intrude into the HI-STORM UMAX cavity. Flooding of any severity will not challenge HI-STORM UMAX's performance. Any fire in the HI-STORM UMAX cavity will self-extinguish. HI-STORM UMAX is designed to withstand beyond design basis tsunami impact. Provides convenient removal features for water, mud, and debris. HI-STORM UMAX Cross-Section 15

HI-STORM UMAX is Fortified to Withstand Beyond Design Basis Threats HI-STORM UMAX was designed in the wake of 9/11. The cylindrical surfaces of the stored canisters are inaccessible to any missile or projectile. The only access to the MPC-37 is guarded by a 36-inch thick stainless steel and concrete lid. Below the Closure Lid, the canister is protected by a 9.5-inch thick solid stainless steel lid. All Design Basis and Beyond Design Basis Threats cannot cause loss of confinement of the stored canister. 9.5-inch Thick Stainless Steel Plate (Lid) 24,000 lb. Steel/Concrete Closure Lid 16

Defense-in-Depth, Maintenance, and Surveillance Requirements Defense-in-Depth in Manufacturing Integrated design and manufacturing under NRC, ASME, and ISOapproved Quality Assurance Program. HI-STORM UMAX Steel Components Fabricated at the U.S. Holtec Manufacturing Division 17

Defense-in-Depth, Maintenance, and Surveillance Requirements Defense-in-Depth by Design Canister oriented vertically to minimize salt deposits from accumulating on the canister s shell surface. MPC-37 The warm surface of the canister discourages dissolved salts in the air from condensing. The vertical orientation allows for complete access to the shell surface for inspection. Vertical orientation ensures that there are no crevices on the canister shell where contaminants can collect and Thermo-siphon Action in the concentrate. MPC-37 HI-STORM UMAX 18

Defense-in-Depth, Maintenance, and Surveillance Requirements Defense-in-Depth during Canister Loading The Forced Helium Dehydrator (FHD), invented and licensed by Holtec in 2002 provides additional protection to used fuel during drying by maintaining low fuel cladding temperatures. FHD is currently in use at 30 reactor units to protect used fuel from failure during canister drying operations. Holtec s Patented Forced Helium Dehydration System 19

Canister Integrity Monitoring Program Defense-in-Depth, Maintenance, and Surveillance Requirements Canister Integrity Monitoring Program Provides early detection of potential threats to confinement integrity. Prediction of Flaw Initiation Material coupons are placed in the HI- STORM UMAX to serve as a pre-cursor of potential canister degradation. Coupons bound the worst-case conditions of canister temperature, stress, and air flow conditions. Periodic Surface Sampling for the presence of contaminants. Typical Damage Predictive Coupon *Pre-stressed to induce early stress corrosion cracking 20

Canister Integrity Monitoring Program Defense-in-Depth, Maintenance, and Surveillance Requirements Flaw and Failure Detection Surface Visual Examination Full-length, 360-degree visual canister and HI-STORM UMAX visual examination. Lighting and cameras can focus on any part of the canister shell or vertical HI-STORM UMAX structure and measure the geometry of an indication. Removal of the canister into the HI-TRAC Transfer Cask for an Integrated Helium Leakage Test Integrated Helium Leakage Test is quick, easy, absolute, and will find microscopic flaws undetectable by other means. Monitoring Periodic inspection of the canisters to monitor changes in any previously-found indications and identification of any new indications. 21

Canister Integrity Monitoring Program Defense-in-Depth, Maintenance, and Surveillance Requirements As shown at Hope Creek below, Holtec s Canister Integrity Monitoring Program Detects and Tracks indications long before they become a threat. Holtec s Surface Sampling Inspection Tool In-Use at PSEG 22

Canister Integrity Monitoring Program Defense-in-Depth, Maintenance, and Surveillance Requirements Holtec s Surface Sampling Inspection Tool previously used to take samples from canisters stored in marine environments at Diablo Canyon and Hope Creek as part of the EPRI study. Average Deposition in mg/m 2 (Threshold is 500) Canister Location 9.5-inch Thick SS Top Lid (Horizontal) Salem/Hope Creek Diablo Canyon 25 180 Side Wall (Vertical) 5 5 Years in Use 5 2 Visual Surface Condition Shiny Shiny Holtec Developed Surface Sampling Inspection Tool 23

Canister Monitoring Ongoing Advances in Aging Management Plan Advanced Inspection Techniques Made Easy by the Vertically-Oriented Canister Precise volumetric measurement method for indications Currently under development in conjunction with Rolls Royce and Electricity De France for use at Sizewell. Rotating sensors located in the Mating Device scan the entire canister shell surface. Continuous Lid Temperature Monitoring (Being Developed for Chernobyl) A sudden change in the temperature may indicate a deviation in canister conditions. MPC is Raised into HI- TRAC as Sensors Scan Entire MPC Shell Surface 24

Damaged Canister Storage Plan Mitigation of Degraded Canister Using HI-TRAC VW SONGS will have two HI-TRAC VW Transfer Casks ready to serve as confinement provider to a damaged canister. Separate, stand-alone, oversized HI- STORM UMAX cavity will eliminate the need to maintain the spent fuel pool or hot cell. The loaded HI-TRAC VW will be stored vertically in the specially designed spare HI-STORM UMAX cavity. HI-TRAC VW will provide radionuclide confinement for an extended period. HI-TRAC with Leak-Tight Lid 25

Damaged Canister Storage Plan Alternative Method for Mitigation of Degraded Canister Using HI-STAR 190 In the unlikely event of a threat of loss of confinement integrity is indicated, as an alternate approach: Canister is placed into the HI-STAR 190 Transportation Cask, located in the oversized HI- STORM UMAX cavity. Lid is sealed and leak tested. Cask provides radionuclide confinement. Casks are temporarily stored vertically in a HI-STORM UMAX cavity. The loaded HI-STAR 190 is readily transportable off-site. Canister Installed in HI-STAR 190 Transportation Cask (left); HI-STAR 190 Transportation Cask Ready for Off-Site Shipment (right) 26

Concluding Remarks HI-STORM UMAX is designed to withstand the California Coastal Commission earthquake with large margins. HI-STORM UMAX is designed to withstand severe environmental threats, such as flood, tsunami, fire, without threat to the system s confinement integrity. HI-STORM UMAX is designed to provide a long, trouble-free service life. HI-STORM UMAX s Canister Integrity Monitoring Program provides a comprehensive approach to prevention, detection, monitoring, and remediation. HI-STORM UMAX provides ultimate safety and security for public health and safety. 27