bulk isotope generation project clinton power station
TRANSCRIPT
Bulk Isotope Generation ProjectClinton Power Station
NRC Meeting in Rockville, MDMarch 31, 2009
Presentation Layout
Proprietary nature of the project
Background – Non-Proprietary• Bulk Isotope Generation process
• High level description of program
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Lead Test Assembly Program –Non-Proprietary• Specifics on Clinton Power Station activities
Project Details – Proprietary• Competitive technical information
Background Agenda
Exelon / GE-Hitachi Partnership
Cobalt Process Flow
Segmented Cobalt Target Rods
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g g
Irradiation of Cobalt Targets
Transportation
Hot-Cell Work
End Uses of Cobalt-60
Partnership –Exelon & GE-Hitachi
The long-term global production capacity of radioactive isotopes used in nuclear medicine is a very serious concern
GE-Hitachi (GEH) proposed that E l d GEH t i th
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Exelon and GEH partner in the bulk generation of Cobalt-60 Isotope Targets
The irradiated Co-60 targets are used by the medical industry for use in cancer treatments and for irradiation sterilization of foods and medical devices
Cobalt Process Flow
Rods in Fuel Bundles
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Rods Irradiated in Reactor Rods Shipped to CA
Hot Cell HandlingCancer
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Cobalt Target Rods
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1
2 HandlingCancerTreatments
Food Sterilization
Segmented Cobalt Target Rods
Small Cobalt-59 targets are placed in target holding cylinder • Cobalt-59 is a naturally occurring metal
Target holding cylinders are held inside cobalt target rod segments• 2 layers of zirconium cladding
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• 2 layers of zirconium cladding
• Each layer is seal-welded
• Ends of outer cladding have male and female fittings
9 cobalt target rod segments are screwed together to match the size of a fuel rodSmall number cobalt target rods are placed in fuel bundles in lieu of fuel rods • 92 total rods in a GE14 fuel bundle• Segment splice points are under spacer positions
Segmented Cobalt Target Rods
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Segmented rods previously used by GE Fuels • Used for spacer capture in earliest GE fuel designs
• Testing of different fuel cladding materials in 1990’s
Cobalt target rods made from same zirconium material as UO2 fuel rods• 2 layers of zirconium cladding
• Solid zirconium at spacers where debris may collect
Cobalt Target RodsIrradiated in Reactor
Fuel Bundles with cobalt target rods shipped to the nuclear power station along with balance of new fuel bundles and placed in the spent fuel pool
New fuel bundles are loaded into the reactor during a refueling outage
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reactor during a refueling outage• Approximately 300 new fuel bundles
are loaded into a reactor every 2 years
The reactor is brought on-line for normal 2 year operating cycle
Cobalt-59 atoms absorb neutrons from nuclear fission process and become Cobalt-60
The fuel bundles with cobalt target rods are removed from the reactor along with other used fuel bundles during refueling outageAfter refueling outage the cobalt target rods are removed from fuel bundles
Cobalt Target Rods Removed from Reactor
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bundles• The fuel bundles are placed back
into spent fuel pool with other used fuel bundles
Cobalt target rods are disassembled at splice points and rod segments are loaded into a rod segment canister Rod segment canister is placed in NRC licensed shipping cask
Shipping Irradiated Cobalt Target Rods
Radioactive material shipping cask is loaded on a truck trailer
Trailer is shipped to GE-Hitachi hot-cell facility in Vallecitos, CA
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REVISIONS
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IDENTIFICATIONNAMEITEMNO
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GROUP NOAND QTY
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3TRANSPORT
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4TIE-DOWN
2BRACKET
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SHACKLE
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6127 WIRE ROPE48 WIRE ROPE8
9RATCHET
4TURNBUCKLE
10RATCHET
4TURNBUCKLE
11OVERPACK
1COVER
12OVERPACK
1BASE
13 7A CONTAINER114 4 INCH STRAP SUPPLIED BY CARRIER6
15 WIRE ROPE4
SEE G.E. DRAWING 101E8756, GROUP 1
SEE G.E. DRAWING 101E8761, GROUP 1
SEE G.E. DRAWING 183C8336, GROUP 1
1.38" SCREW PIN ANCHOR SHACKLESEE G.E. DRAWING 218B6106, PT NO. 1SEE G.E. DRAWING 218B6106, PT NO. 2
TIE-DOWNBRACKET
SEE G.E. DRAWING 183C8336, GROUP 2
DURBIN PT NO. DD-CJ 18.00 BARRELLENGTH X 1.25 DIA THREAD OR EQUIVDURBIN PT NO. DD-CJ 12.00 BARRELLENGTH X 1.25 DIA THREAD OR EQUIVSEE G.E. DRAWING 101E8749, GROUP 1OR G.E. DRAWING 955E219, GROUP 1SEE G.E. DRAWING 101E8749, GROUP 2OR G.E. DRAWING 955E219, GROUP 2
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SECTION B-B3
NOTES: 1. NORMAL LOCATION OF COMPONENTS ARE AS SHOWN. OPTION: THE 7A CONTAINER AND THE TRANSPORT STAND LOCATIONS MAY BE SWITCHED. 6.00
3.00(2.50)
OR4 5.50
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2. AFTER WELDING ITEMS 4, 5, 17, AND 18, TIE-DOWN BRACKETS, TO ITEM 1, TRAILER, PRIME AND PAINT WITH A GOOD ENAMEL PAINT.
IDENTIFICATIONNAMEITEMNO
TORQ WRENCH2425 HEX HD DRIVER
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GROUP NOAND QTY
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19 JAM NUT820 JAM NUT 1.25-4 ACME THREAD, LEFT HAND821 TOOL CHEST122 WRENCH 2 INCH OPEN END2
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1RATCHET
SEE G.E. DRAWING 105E9547, GROUP 1
172BRACKET
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SEE G.E. DRAWING 183C8336, GROUP 3
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SEE G.E. DRAWING 183C8336, GROUP 4
1.25-4 ACME THREAD, RIGHT HAND
McMASTER P/N 6758A13 OR EQUIV
SEE G.E. DRAWING 166D8051 GROUP 1
1/2 INCH DRIVE11/2 INCH DRIVE11/2 INCH DRIVE 4 INCH LG1
112 INCH CRESENT17/16 OPEN / BOX END13/16 INCH THRU 3/8 INCH SET125 FT LG 110V GROUNDED3
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NUCLEAR GRADE LUBRICANT11.00 X 3 FEET, NYLON42.00 X 6 FEET, NYLON4
14 LEG, 1000 LB CAPACITY1
262728293031323334353637
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NUCLEAR GRADE MARKER, BLACK ONLY
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18 174
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SNAP-ON TOOLS P/N SA20A OR EQUIV
3. ITEMS 30 THRU 43 ARE CONVENIENCE ITEMS.
SEE NOTE 2 SEE NOTE 2
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SEE NOTE 2
SEE NOTE 2 SEE NOTE 2
45'-0 1/4" (540.25)
8'-6" (102.00)
4 OPTIONAL CONFIGURATION: THE OUTER ROPES MAY-BEUSED BY COMBINING PART NO. 7 & 8 AND REPLACINGTHEM WITH PART NO. 15. THIS WILL REDUCE THE QUANITYOF PART NO. 6 FROM 12 TO 8.
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SEE G.E. DRAWING 218B6106,PT NO. 34
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UNLESS OTHERWISE SPECIFIED
FRACTIONSANGLES
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3 PLACE DECIMALS 2 PLACE DECIMALSTOLERANCES ON :
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ISSUE DATE DWG NO. REV.
ALL SURF
FMF
TITLE
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MODEL 2000 CASK TRAILERARRANGEMENT
- MODEL 2000 TRANSPORT PACKAGING
28 11 9419 10 94
DRAWN
CHECKED
SIGNATURES
L. MEEKS. JAIN
THIS ITEM IS OR CONTAINS A SAFETY NUCLEAR SAFETY RELATED
RELATED ITEM NO YES YES NO
DAY YR MO
VNC, Pleasanton, CA
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SAFETY RELATED IEEE CLASS 1E
EQUIPMENT CLASS. CODE NA
10 19 206
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Cobalt-60 Targets Separated for Use
Separation and handling of cobalt from target rods to be performed at the GEH facility
Existing hot-cell at GEH Vallecitos CA facility well
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Vallecitos, CA facility well suited for handling Cobalt-60
Co-60 Gamma Knife
Non-Invasive brain surgeryNearly ½ million people treatedGE experienced in gamma knife sourcesNon-Invasive gamma cancer treatment
growing to other cancer fieldsHigh Specific Activity (HSA) cobalt-60
targets required (4 t 6 f i di ti d d)
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(4 to 6 years of irradiation needed)
Co-60 Sterilization
Eliminates harmful pathogensLengthens food shelf lifeGrowing public acceptanceAlso used in medical and blood sterilizationLow Specific Activity (LSA) cobalt-60 targets
required (2 years of irradiation needed)
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232 Gamma irradiators in use today25% Needs replenishing per yearE.Coli outbreaks increasing need
Clinton Power Station (CPS)Lead Test Assembly (LTA) Agenda
CPS LTA Project Description
Use of LTA framework
LTA Report
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LTA License Amendment Request
CPS LTA Design Schedule
GEH Technical Evaluation Report
Exelon’s Configuration Control Process
LTA Handling and Shipping
CPS GE14iLead Test Assembly (LTA) Project
LTA programs have been successful in the controlled introduction of new fuel designs
To use proven Global Nuclear Fuel (GNF) GE14 fuel bundles as host for cobalt target rods
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Bundles with cobalt target rods (designated GE14i) are inserted into operating reactor core to confirm expected operations
Purpose of the CPS LTA Program is to obtain data to verify the GE14i fuel bundles perform satisfactorily in service prior to use on a production basis
A separate project would be required to move forward with a Bulk (large scale) Isotope Generation program
Utilize Lead Test Assembly (LTA) Framework
GE14i fuel bundles with cobalt target rods are still fuel assemblies• Energy production is the primary purpose of the fuel
assemblies • Majority of the rods in the bundles contain UO2 (over 90%)• Physical geometry of the GE14 fuel bundles not affected
The analysis of the GE14i LTAs using approved
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The analysis of the GE14i LTAs using approved methods meets the approved criteriaThe number of GE14i LTAs used will be numerically small• Less than 2% of the core• If an LTA failure occurs the amount of cobalt is restricted and
easily handled by the normal plant operating systems
The GE14i LTAs will be placed in non-limiting core locations
CPS GE14i LTA Report
The report provides the NRC with information on the GE14i LTAs per the approved LTA guidelines
Non-Proprietary and Proprietary versions to be provided with CPS License Amendment Request
Describes and displays new segmented target rod d i f t
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design features • Cobalt targets, target holding cylinders, target rod end
caps, etc.
Describes the licensing analyses that are being performed or are being completed with the CPS cycle 13 reload licensing activities
Outlines the post-irradiation LTA measurements
CPS GE14i LTA License Amendment Request
Scope of LTA License Amendment Request (LAR)• Revise and add operating license conditions to clarify how
byproduct materials are handled at CPS− Allows for the intentional production and transfer of byproduct
material in accordance with 10 CFR 30− Clarifies how the mechanical disassembly of items or
components containing byproduct material is not considered
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components containing byproduct material is not considered separation of the byproduct material
• Change to Technical Specification Design Features section to describe the LTAs being used
LAR was reviewed by PORC and approved by NSRBLicense Amendment Request and LTA Report are ready to be submitted following this meeting
LTA Design Schedule Overview
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GEH Technical Evaluation Report (TER)
TER for GE14i LTAs to qualitatively and quantitatively address the following:• Abnormal operational transient events
− Reactor pressure changes
− Reactor temperature changes
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p g
− Reactor water level changes
− Reactor water flow changes
− Positive reactivity events
• Design basis accident events
• System and program evaluation requirements
TER Revision 0 to be issued in May 2009
TER Revision 1 to be issued after CPS cycle 13 licensing activities are completed, Fall 2009
Exelon Configuration Control Process for GE14i LTAs
Evaluate GE14i LTA bundles with a Design Change Package (DCP – Exelon’s plant modification engineering package)• Ensures LTA performance of design basis functions• Ensures LTA compliance with plant licensing basis
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• Evaluates LTA affects on other structures, systems and components
• Utilize GEH/GNF’s Technical Evaluation Report as basis of design change
• Exelon system and program owners to evaluate impacts of the LTAs
• 10 CFR 50.59 evaluation to address impacts to SAR –referencing the License Amendment Request
Exelon Configuration Control Process for GE14i LTAs
Evaluate the utilization of the GE14i LTA bundles in the reload core with the CPS Cycle 13 Fuel Change Package (FCP – Exelon’s core reload engineering package)• Ensures reload core performance of design basis functions
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• Ensures reload core compliance with plant licensing basis• Evaluates reload core affects to other structures, systems and
components• Exelon system and program owners to evaluate impacts of
the reload• 10 CFR 50.59 evaluation to address impacts to SAR –
referencing the License Amendment Report• Use of LTA bundles in future cycles to be evaluated in
subsequent reload FCPs
LTA Safe Handling ProcessesGE14i LTA bundles to be received using normal receipt procedures
Post-Irradiation Handling• Staged spent fuel pool locations for interim storage
• Segmented rod handling to have Exelon technical
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evaluations and mock-up tests prior to use
• GNF fuel handlers to perform work under Exelon Outage Services supervision
• Fuel bundle disassembly similar to fuel inspections
• Rod segment basket and shipping cask loading by detailed Level 1 procedure
• NRC licensed shipping cask loaded on trailer for cross-country transport
Safeguard Shipping per NRC regulations handled by GEH
Utilize NRC licensed shipping cask
Cobalt target rod ownership will transfer from Exelon to GEH at CPS protected area
t
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gate
Shipments will qualify as Type B Shipment of Class 7 (radioactive) hazardous material• Shipments will be a highway route controlled
quantities
CPS GE14i LTA Shipping Schedule
Remove and ship 1 cobalt target rod after 2 years of irradiation• Remove cobalt target rod from an LTA bundle during 2012
scheduled refueling outage
• Perform inspections and measurements as part of the Lead Test Assembly process
• Remove cobalt target rod and ship to Vallecitos, CA
• Cobalt targets would be available for sterilization processes
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• Cobalt targets would be available for sterilization processes
Remove and ship balance of cobalt target rods after 4 or 6 years of irradiation • Remove cobalt target rods from LTA bundles during 2014 and 2016
scheduled refueling outages
• Perform inspections and measurements as part of the Lead Test Assembly process
• Remove cobalt target rods and ship to Vallecitos, CA
• Cobalt targets would be available for medical treatment processes
Questions
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