ML090890494

Exelon Presentation Slides for 03/31/2009 Meeting with the NRC Staff Concerning Proposed CO-60 Production at Clinton Station

ML090890494
Person / Time
Site:	Clinton
Issue date:	03/30/2009
From:	Bamford P J Plant Licensing Branch II
To:	Exelon Nuclear
Bamford, Peter J., NRR/DORL 415-2833
Shared Package
ML090890540	List: ML090890494
References
TAC ME0657
Download: ML090890494 (26)

Text

Bulk Isotope Generation Project Clinton Power StationNRC Meeting in Rockville, MDMarch 31, 2009 Presentation LayoutProprietary nature of the projectBackground -Non-Proprietary

• Bulk Isotope Generation process

• High level descrip tion of program 2Lead Test Assembly Program

-Non-Proprietary

• Specifics on Clinton Power Station activitiesProject Details -Proprietary

• Competitive technical information Background AgendaExelon / GE-Hitachi Partnership Cobalt Process Flow Se gmented Cobalt Tar g et Rods 3 ggIrradiation of Cobalt Targets Transportation Hot-Cell Work End Uses of Cobalt-60 Partnership -Exelon & GE-HitachiThe long-term global production capacity of radioactive isotopes used in nuclear medicine is a very

serious concernGE-Hitachi (GEH) proposed that EldGEHtith 4 E xe l on an d GEH par t ner i n th e bulk generation of Cobalt-60 Isotope TargetsThe 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 3 4 5 6 2Rods Irradiated in ReactorRods Shipped to CA Hot Cell Handling Cancer 5 Cobalt Target Rods 6 1 2 Handling CancerTreatments Food Sterilization Segmented Cobalt Target RodsSmall Cobalt-59 targets are placed in target holding cylinder

• Cobalt-59 is a naturally occurring metalTarget holding cylinders are held inside cobalt target rod segments

• 2layersofzirconiumcladding 6*2 layers of zirconium cladding*Each layer is seal-welded

• Ends of outer cladding have male and female fittings9 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 7Segmented rods previously used by GE Fuels

• Used for spacer capture in earliest GE fuel designs

• Testing of different fuel cladding materials in 1990'sCobalt 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 ReactorFuel Bundles with cobalt target rods shipped to the nuclear power station along with balance of new fuel bundles and placed in the spent fuel

poolNew fuel bundles are loaded into the reactorduringarefuelingoutage 8 reactor during a refueling outage*Approximately 300 new fuel bundles are loaded into a reactor every 2 yearsThe reactor is brought on-line for normal 2 year operating cycleCobalt-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 bundlesCobalt Target Rods Removed from Reactor 9 bundles*The fuel bundles are placed back into spent fuel pool with other used fuel bundlesCobalt 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 RodsRadioactive material shipping cask is loaded on a truck trailerTrailer is shipped to GE-Hitachi hot-cell facility in V allecitos , CA 1 REVISIONS 4 5 6 7 8 9 10 11 12 13 14 S H N O.K J I H G F E D K J I H G F E D C EIS IDENT:

1 SH NO.2 3 1 0 5 E 9 5 5 0 105E9550 1 TRAILER IDENTIFICATION NAME ITEM NO OVERPACK STND 2 1 ARRANGEMENT G01 GROUP NO AND QTY 1 3 TRANSPORT 1 STAND 4 TIE-DOWN 2 BRACKET 5 SHACKLE 2 6 127WIRE ROPE 48WIRE ROPE 8 9 RATCHET 4 TURNBUCKLE 10 RATCHET 4 TURNBUCKLE 11 OVERPACK 1 COVER 12 OVERPACK 1 BASE 13 7A CONTAINER 1 14 4 INCH STRAP SUPPLIED BY CARRIER 6 15 WIRE ROPE 4 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 SHACKLE SEE G.E. DRAWING 218B6106, PT NO. 1 SEE G.E. DRAWING 218B6106, PT NO. 2 TIE-DOWN BRACKET SEE G.E. DRAWING 183C8336, GROUP 2 DURBIN PT NO. DD-CJ 18.00 BARREL LENGTH X 1.25 DIA THREAD OR EQUIV

DURBIN PT NO. DD-CJ 12.00 BARREL

LENGTH X 1.25 DIA THREAD OR EQUIV SEE G.E. DRAWING 101E8749, GROUP 1 OR G.E. DRAWING 955E219, GROUP 1

SEE G.E. DRAWING 101E8749, GROUP 2

OR G.E. DRAWING 955E219, GROUP 2 11 6 8 SECTION B-B 3 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)OR 4 5.50 8X A DETAIL A TYPICAL SEE NOTE 2 TRAILKING IND. MODEL NO. TK60MC-482

2. AFTER WELDING ITEMS 4, 5, 17, AND 18, TIE-DOWN BRACKETS, TO ITEM 1, TRAILER, PRIME AND PAINT WITH A GOOD ENAMEL PAINT.

IDENTIFICATION NAME ITEM NO TORQ WRENCH 24 25 HEX HD DRIVER G01 GROUP NO AND QTY 1 1 16 TIE-DOWN 19 JAM NUT 8 20JAM NUT1.25-4 ACME THREAD, LEFT HAND 8 21 TOOL CHEST 122WRENCH 2 INCH OPEN END 2 23 TURNBUCKLE 1 RATCHET SEE G.E. DRAWING 105E9547, GROUP 1 17 2 BRACKET 18 2 SEE G.E. DRAWING 183C8336, GROUP 3 TIE-DOWN BRACKET 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 DRIVE 1 1/2 INCH DRIVE 1 1/2 INCH DRIVE 4 INCH LG 1 1 12 INCH CRESENT 1 7/16 OPEN / BOX END 1 3/16 INCH THRU 3/8 INCH SET 1 25 FT LG 110V GROUNDED 3 1 1 NUCLEAR GRADE LUBRICANT 1 1.00 X 3 FEET, NYLON 4 2.00 X 6 FEET, NYLON 4 1 4 LEG, 1000 LB CAPACITY 1 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 BREAKER BAR

RATCHET EXTENSION SOCKET WRENCH WRENCH ALLEN WRENCH EXT CORD THREAD LOCK

TAPE LUBRICANT SLING SLING MARKER SLING SNAP-ON TOOLS P/N TQP250 OR EQUIV 1/2 INCH DRIVE 3/4 INCH 6 POINT

ND INDUSTRIES P/N VC-3 "VIBRA-TITE" NUCLEAR GRADE TAPE NUCLEAR GRADE MARKER, BLACK ONLY 14 13 21 40 THRU 5 4 18 17 4 5 18 17OROR 17 18 PT SNAP-ON TOOLS P/N SA20A OR EQUIV

3. ITEMS 30 THRU 43 ARE CONVENIENCE ITEMS.

SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 SEE NOTE 2 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-BE USED BY COMBINING PART NO. 7 & 8 AND REPLACING THEM WITH PART NO. 15. THIS WILL REDUCE THE QUANITY OF PART NO. 6 FROM 12 TO 8.

4 15 SEE G.E. DRAWING 218B6106, PT NO. 3 4 14 C 2 9 19 20 12 6 SEE NOTE 2 8 5 7 91920 10 , DIST TO VC-E9550001 114.00 78.00 B B E1413 A 12 114.001110 8 9 G01 B 78.00765 SEE NOTE 2 UNLESS OTHERWISE SPECIFIED FRACTIONS ANGLES 3 3 PLACE DECIMALS

2 PLACE DECIMALS

TOLERANCES ON :

+-+-.12 NA 4 DFTG ENGRG APPLIED PRACTICES Y1010A3 R.PEREZ S. JAIN 1 2 1 ERM NO. COMPL STAT SH NO. CONT ON +-+-0 F C 105E9550 NA 1\ ISSUE DATE DWG NO.

REV. ALL SURF FMF TITLE XXX MODEL 2000 CASK TRAILER ARRANGEMENT - MODEL 2000 TRANSPORT PACKAGING 28 11 94 19 10 94 DRAWN CHECKED SIGNATURES L. MEEK S. JAIN THIS ITEM IS OR CONTAINS A SAFETYNUCLEAR SAFETY RELATED RELATED ITEM NO YES YES NO DAY YR MO VNC, Pleasanton, CA X 19 10 94 X 28 11 94 SAFETY RELATED IEEE CLASS 1E EQUIPMENT CLASS. CODE NA 101920 6 4 Cobalt-60 Targets Separated for UseSeparation and handling of cobalt from target rods to be

performed at the GEH facilityExisting hot-cell at GEH VallecitosCAfacilitywell 11 Vallecitos , CA facility well suited for handling Cobalt-60 Co-60 Gamma KnifeNon-Invasive brain surgeryNearly 1/2 million people treatedGE experienced in gamma knife sourcesNon-Invasive gamma cancer treatment growing to other cancer fields High Specific Activity (HSA) cobalt-60 targets required (4t6fiditidd) 12 (4 t o 6 years o f i rra di a tion nee d e d)

Co-60 SterilizationEliminates 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) 13232 Gamma irradiators in use today25% Needs replenishing per yearE.Coli outbreaks increasing need Clinton Power Station (CPS)Lead Test Assembly (LTA) AgendaCPS LTA Project DescriptionUse of LTA frameworkLTA Re p ort 14 pLTA License Amendment RequestCPS LTA Design ScheduleGEH Technical Evaluation Report Exelon's Configuration Control ProcessLTA Handling and Shipping CPS GE14iLead Test Assembly (LTA) ProjectLTA programs have been successful in the controlled introduction of new fuel designsTo use proven Global Nuclear Fuel (GNF) GE14 fuel bundles as host for cobalt target rods 15Bundles with cobalt target rods (designated GE14i) are inserted into operating reactor core to confirm expected operationsPurpose 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 basisA separate project would be required to move forward with a Bulk (large scale) Isotope Generation program Utilize Lead Test Assembly (LTA) FrameworkGE14i 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 UO 2(over 90%)

• Physical geometry of the GE14 fuel bundles not affectedTheanalysisoftheGE14iLTAsusingapproved 16 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 ReportThe report provides the NRC with information on the GE14i LTAs per the approved LTA guidelinesNon-Proprietary and Proprietary versions to be provided with CPS License Amendment RequestDescribes and displays new segmented target rod dift 17 d es i gn f ea t ures *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 activitiesOutlines the post-irradiation LTA measurements CPS GE14i LTA License Amendment RequestScope 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 componentscontainingbyproductmaterialisnotconsidered 18components 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 19 GEH Technical Evaluation Report (TER)TER for GE14i LTAs to qualitatively and quantitatively address the following:

• Abnormal operational transient events Reactor pressure changes Reactor tem perature chan g es 20 pgReactor water level changes Reactor water flow changes Positive reactivity events

• Design basis accident events

• System and program evaluation requirementsTER Revision 0 to be issued in May 2009TER Revision 1 to be issued after CPS cycle 13 licensing activities are completed, Fall 2009 Exelon Configuration Control Process for GE14i LTAsEvaluate 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 21*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 LTAsEvaluate 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 22*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 23evaluations 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 GEHUtilize NRC licensed shipping cask Cobalt target rod ownership will transfer from Exelon to GEH at CPS protected area t 24 ga t eShipments will qualify as Type B Shipment of Class 7 (radioactive) hazardous material

• Shipments will be a highway route controlled quantities CPS GE14i LTA Shipping ScheduleRemove 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

• Cobalttargetswouldbeavailableforsterilizationprocesses 25*Cobalt targets would be available for sterilization processesRemove 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 26