ML090890494

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Presentation Slides for 03/31/2009 Meeting with the NRC Staff Concerning Proposed CO-60 Production at Clinton Station
ML090890494
Person / Time
Site: Clinton Constellation icon.png
Issue date: 03/30/2009
From: Peter Bamford
Plant Licensing Branch II
To:
Exelon Nuclear
Bamford, Peter J., NRR/DORL 415-2833
Shared Package
ML090890540 List:
References
TAC ME0657
Download: ML090890494 (26)
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Text

Bulk Isotope Generation Project Clinton Power Station NRC Meeting in Rockville, MD March 31, 2009

Presentation Layout 9 Proprietary nature of the project 9 Background - Non-Proprietary

  • Bulk Isotope Generation process
  • High level description of program 9 Lead Test Assembly Program -

Non-Proprietary

  • Specifics on Clinton Power Station activities 9 Project Details - Proprietary
  • Competitive technical information 2

Background Agenda 9 Exelon / GE-Hitachi Partnership 9 Cobalt Process Flow g

9 Segmented Cobalt Target g Rods 9 Irradiation of Cobalt Targets 9 Transportation 9 Hot-Cell Work 9 End Uses of Cobalt-60 3

Partnership -

Exelon & GE-Hitachi 9 The long-term global production capacity of radioactive isotopes used in nuclear medicine is a very serious concern 9 GE-Hitachi (GEH) proposed that E l and Exelon d GEH partner t in i the th bulk generation of Cobalt-60 Isotope Targets 9 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 4

Cobalt Process Flow Rods Irradiated in Reactor Rods Shipped to CA 3 4 Rods in Fuel Bundles Hot Cell 5 6

2 Cancer Handling Treatments 6 Food 1 Sterilization Cobalt Target Rods 5

Segmented Cobalt Target Rods 9 Small Cobalt-59 targets are placed in target holding cylinder

  • Cobalt-59 is a naturally occurring metal 9 Target holding cylinders are held inside cobalt target rod segments
  • Each layer is seal-welded
  • Ends of outer cladding have male and female fittings 9 9 cobalt target rod segments are screwed together to match the size of a fuel rod 9 Small 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 6

Segmented Cobalt Target Rods 9 Segmented rods previously used by GE Fuels

  • Used for spacer capture in earliest GE fuel designs
  • Solid zirconium at spacers where debris may collect 7

Cobalt Target Rods Irradiated in Reactor 9 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 9 New fuel bundles are loaded into the reactor during a refueling outage

  • Approximately 300 new fuel bundles are loaded into a reactor every 2 years 9 The reactor is brought on-line for normal 2 year operating cycle 9 Cobalt-59 atoms absorb neutrons from nuclear fission process and become Cobalt-60 8

Cobalt Target Rods Removed from Reactor 9 The fuel bundles with cobalt target rods are removed from the reactor along with other used fuel bundles during refueling outage 9 After refueling outage the cobalt target rods are removed from fuel bundles

  • The fuel bundles are placed back into spent fuel pool with other used fuel bundles 9 Cobalt target rods are disassembled at splice points and rod segments are loaded into a rod segment canister 9 Rod segment canister is placed in NRC licensed shipping cask 9

Shipping Irradiated Cobalt Target Rods 14 13 12 11 10 9 8 7 6 5 4 3 EIS IDENT: 2 105E9550 SH NO.

1 GROUP NO GROUP NO REVISIONS AND QTY ITEM NAME IDENTIFICATION AND QTY ITEM NAME IDENTIFICATION PT G01 NO G01 NO 4 OR 5 OR 17 OR 18 SEE NOTE 2 8X 1 24 TORQ WRENCH SNAP-ON TOOLS P/N TQP250 OR EQUIV 1 1 TRAILER TRAILKING IND. MODEL NO. TK60MC-482 K .50 K NOTES: 1 25 HEX HD DRIVER SNAP-ON TOOLS P/N SA20A OR EQUIV OVERPACK STND 1 2 SEE G.E. DRAWING 101E8756, GROUP 1 1 26 BREAKER BAR 1/2 INCH DRIVE ARRANGEMENT

1. NORMAL LOCATION OF COMPONENTS ARE AS 1 27 RATCHET 1/2 INCH DRIVE TRANSPORT SHOWN. OPTION: THE 7A CONTAINER AND THE 3.00 1 3 SEE G.E. DRAWING 101E8761, GROUP 1 (2.50) 1 28 EXTENSION 1/2 INCH DRIVE 4 INCH LG STAND TRANSPORT STAND LOCATIONS MAY BE SWITCHED. 6.00 1 29 SOCKET 1/2 INCH DRIVE 3/4 INCH 6 POINT TIE-DOWN 2 4 SEE G.E. DRAWING 183C8336, GROUP 1
2. AFTER WELDING ITEMS 4, 5, 17, AND 18, TIE-DOWN 1 30 WRENCH 12 INCH CRESENT BRACKET BRACKETS, TO ITEM 1, TRAILER, PRIME AND PAINT 1 31 WRENCH 7/16 OPEN / BOX END TIE-DOWN 2 5 SEE G.E. DRAWING 183C8336, GROUP 2 WITH A GOOD ENAMEL PAINT. 1 32 ALLEN WRENCH 3/16 INCH THRU 3/8 INCH SET BRACKET
3. ITEMS 30 THRU 43 ARE CONVENIENCE ITEMS. 3 33 EXT CORD 25 FT LG 110V GROUNDED 12 6 SHACKLE 1.38" SCREW PIN ANCHOR SHACKLE J 1 34 THREAD LOCK ND INDUSTRIES P/N VC-3 "VIBRA-TITE" 4 7 WIRE ROPE SEE G.E. DRAWING 218B6106, PT NO. 1 J 4 OPTIONAL CONFIGURATION: THE OUTER ROPES MAY-BE DETAIL A 1 35 TAPE NUCLEAR GRADE TAPE 8 8 WIRE ROPE SEE G.E. DRAWING 218B6106, PT NO. 2 USED BY COMBINING PART NO. 7 & 8 AND REPLACING TYPICAL THEM WITH PART NO. 15. THIS WILL REDUCE THE QUANITY 1 36 LUBRICANT NUCLEAR GRADE LUBRICANT RATCHET DURBIN PT NO. DD-CJ 18.00 BARREL 4 9 OF PART NO. 6 FROM 12 TO 8. 4 37 SLING 1.00 X 3 FEET, NYLON TURNBUCKLE LENGTH X 1.25 DIA THREAD OR EQUIV 4 38 SLING 2.00 X 6 FEET, NYLON RATCHET DURBIN PT NO. DD-CJ 12.00 BARREL 4 10 1 39 MARKER NUCLEAR GRADE MARKER, BLACK ONLY TURNBUCKLE LENGTH X 1.25 DIA THREAD OR EQUIV 1 40 SLING 4 LEG, 1000 LB CAPACITY OVERPACK SEE G.E. DRAWING 101E8749, GROUP 1 1 11 9 Radioactive material COVER OR G.E. DRAWING 955E219, GROUP 1 OVERPACK SEE G.E. DRAWING 101E8749, GROUP 2 1 12 BASE OR G.E. DRAWING 955E219, GROUP 2 I 1 13 7A CONTAINER SEE G.E. DRAWING 105E9547, GROUP 1 I

6 14 4 INCH STRAP SUPPLIED BY CARRIER SEE G.E. DRAWING 218B6106, 4 4 15 WIRE ROPE PT NO. 3 16 TIE-DOWN 2 17 SEE G.E. DRAWING 183C8336, GROUP 3 BRACKET TIE-DOWN 2 18 SEE G.E. DRAWING 183C8336, GROUP 4 shipping cask is loaded on BRACKET 8 19 JAM NUT 1.25-4 ACME THREAD, RIGHT HAND H 8 20 JAM NUT 1.25-4 ACME THREAD, LEFT HAND H 3 1 21 TOOL CHEST McMASTER P/N 6758A13 OR EQUIV 2 22 WRENCH 2 INCH OPEN END SECTION B-B SEE NOTE 2 5 SEE NOTE 2 TURNBUCKLE 1 23 SEE G.E. DRAWING 166D8051 GROUP 1 RATCHET A 4 SEE NOTE 2 18 17 SEE NOTE 2 G G a truck trailer F 8'-6" (102.00)

SH NO.

1 F

9 Trailer is shipped to GE-105E9550 SEE NOTE 2 17 18 SEE NOTE 2 SEE NOTE 2 5 4 SEE NOTE 2 E E 45'-0 1/4" (540.25) 11 Hitachi hot-cell facility in D 4 15 6

8 9 19 20 21 THRU 40 14 13 D

Vallecitos,, CA C 2

14 20 19 9 12 6

8 10 19 20 7

5 6

SEE NOTE 2 4

C B B SEE NOTE 2 EQUIPMENT CLASS. CODE NA SAFETY RELATED IEEE CLASS 1E THIS ITEM IS OR CONTAINS A SAFETY NUCLEAR SAFETY RELATED B SIGNATURES DAY RELATED ITEM MO YR YES X NO YES X NO 78.00 78.00 DRAWN L. MEEK 19 10 94 VNC, Pleasanton, CA CHECKED S. JAIN 28 11 94 114.00 114.00 DFTG R.PEREZ 28 11 94 TITLE ENGRG S. JAIN 19 10 94 MODEL 2000 CASK TRAILER A APPLIED PRACTICES Y1010A3 ALL SURF ARRANGEMENT G01 UNLESS OTHERWISE SPECIFIED XXX FMF ISSUE DATE

- MODEL 2000 TRANSPORT PACKAGING DWG NO. REV.

TOLERANCES ON :

2 PLACE DECIMALS + .12 FRACTIONS + NA 105E9550 0 DIST

- - ERM NO.

3 PLACE DECIMALS +- NA ANGLES -+ 1\ COMPL STAT C SH NO. 1 CONT ON F TO E 14 13 12 11 10 9 8 7 6 5 4 3 2 1 VC-E9550001 10

Cobalt-60 Targets Separated for Use 9 Separation and handling of cobalt from target rods to be performed at the GEH facility 9 Existing hot-cell at GEH Vallecitos CA facility well Vallecitos, suited for handling Cobalt-60 11

Co-60 Gamma Knife 9 Non-Invasive brain surgery 9 Nearly 1/2 million people treated 9 GE experienced in gamma knife sources 9Non-Invasive gamma cancer treatment growing to other cancer fields 9 High Specific Activity (HSA) cobalt-60 targets required (4 to t 6 years off irradiation i di ti needed) d d) 12

Co-60 Sterilization 9 Eliminates harmful pathogens 9 Lengthens food shelf life 9 Growing public acceptance 9 Also used in medical and blood sterilization 9 Low Specific Activity (LSA) cobalt-60 targets required (2 years of irradiation needed) 9 232 Gamma irradiators in use today 9 25% Needs replenishing per year 9 E.Coli outbreaks increasing need 13

Clinton Power Station (CPS)

Lead Test Assembly (LTA) Agenda 9 CPS LTA Project Description 9 Use of LTA framework p

9 LTA Report 9 LTA License Amendment Request 9 CPS LTA Design Schedule 9 GEH Technical Evaluation Report 9 Exelons Configuration Control Process 9 LTA Handling and Shipping 14

CPS GE14i Lead Test Assembly (LTA) Project 9 LTA programs have been successful in the controlled introduction of new fuel designs 9 To use proven Global Nuclear Fuel (GNF) GE14 fuel bundles as host for cobalt target rods 9 Bundles with cobalt target rods (designated GE14i) are inserted into operating reactor core to confirm expected operations 9 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 9 A separate project would be required to move forward with a Bulk (large scale) Isotope Generation program 15

Utilize Lead Test Assembly (LTA) Framework 9 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 9 The analysis of the GE14i LTAs using approved methods meets the approved criteria 9 The 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 9 The GE14i LTAs will be placed in non-limiting core locations 16

CPS GE14i LTA Report 9 The report provides the NRC with information on the GE14i LTAs per the approved LTA guidelines 9 Non-Proprietary and Proprietary versions to be provided with CPS License Amendment Request 9 Describes and displays new segmented target rod d i features design f t

  • Cobalt targets, target holding cylinders, target rod end caps, etc.

9 Describes the licensing analyses that are being performed or are being completed with the CPS cycle 13 reload licensing activities 9 Outlines the post-irradiation LTA measurements 17

CPS GE14i LTA License Amendment Request 9 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 separation of the byproduct material
  • Change to Technical Specification Design Features section to describe the LTAs being used 9 LAR was reviewed by PORC and approved by NSRB 9 License Amendment Request and LTA Report are ready to be submitted following this meeting 18

LTA Design Schedule Overview 19

GEH Technical Evaluation Report (TER) 9 TER for GE14i LTAs to qualitatively and quantitatively address the following:

Reactor temperature changes g

Reactor water level changes Reactor water flow changes Positive reactivity events

  • Design basis accident events
  • System and program evaluation requirements 9 TER Revision 0 to be issued in May 2009 9 TER Revision 1 to be issued after CPS cycle 13 licensing activities are completed, Fall 2009 20

Exelon Configuration Control Process for GE14i LTAs 9 Evaluate GE14i LTA bundles with a Design Change Package (DCP - Exelons plant modification engineering package)

  • Ensures LTA performance of design basis functions
  • Ensures LTA compliance with plant licensing basis
  • Evaluates LTA affects on other structures, systems and components
  • Utilize GEH/GNFs Technical Evaluation Report as basis of design change
  • Exelon system and program owners to evaluate impacts of the LTAs

referencing the License Amendment Request 21

Exelon Configuration Control Process for GE14i LTAs 9 Evaluate the utilization of the GE14i LTA bundles in the reload core with the CPS Cycle 13 Fuel Change Package (FCP - Exelons core reload engineering package)

  • Ensures reload core performance of design basis functions
  • 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

referencing the License Amendment Report

  • Use of LTA bundles in future cycles to be evaluated in subsequent reload FCPs 22

LTA Safe Handling Processes 9 GE14i LTA bundles to be received using normal receipt procedures 9 Post-Irradiation Handling

  • Staged spent fuel pool locations for interim storage
  • Segmented rod handling to have Exelon technical 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 23

Safeguard Shipping per NRC regulations handled by GEH 9 Utilize NRC licensed shipping cask 9 Cobalt target rod ownership will transfer from Exelon to GEH at CPS protected area gate t

9 Shipments will qualify as Type B Shipment of Class 7 (radioactive) hazardous material

  • Shipments will be a highway route controlled quantities 24

CPS GE14i LTA Shipping Schedule 9 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 9 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 25

Questions 26

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