ML18200A138
| ML18200A138 | |
| Person / Time | |
|---|---|
| Site: | 07109360 |
| Issue date: | 06/19/2018 |
| From: | Industrial Nuclear Co |
| To: | Division of Spent Fuel Management |
| Allen W | |
| Shared Package | |
| ML18200A137 | List: |
| References | |
| EPID L-2018-LRM-0134 | |
| Download: ML18200A138 (35) | |
Text
Industrial Nuclear Company, Inc.
Ten Hole Source Changer Model THSC Docket No. 71-9360 A Presentation to the US Nuclear Regulatory Commission June 19, 2018
> NRC #2, June 19, 2018 2
Agenda Introduction Description of THSC Package Materials of Construction THSC Payload Descriptions Certification Test Results Verification of Shield Integrity Submittal Schedule Summary
> NRC #2, June 19, 2018 3
Description of THSC Package Enclosed, Right Circular Cylinder 12-3/4 OD x 14-1/2 High Welded Stainless Steel Construction Depleted Uranium Gamma Shield Titanium Source Tubes/Hub Gross Weight: Approximately 330 lb
> NRC #2, June 19, 2018 4
Description of THSC Package (cont)
> NRC #2, June 19, 2018 5
Description of THSC Package (cont)
Shown without bottom support channels TOP DU SUPPORT PIPE LOCK BOX ASSEMBLY COPPER SHIM, TYP SIDE DU SUPPORT CHANNEL PLASTIC BURN-OUT PLUGS (3 PLACES) 3 8" CLOSURE LID BOLTS (8 PLACES)
UPPER DU SUPPORT RING 3 8" THK MOUNTING PLATE SOURCE TUBE ASSEMBLY (TITANIUM)
DEPLETED URANIUM (DU) SHIELD DU LOWER SUPPORT RING POLYURETHANE FOAM
> NRC #2, June 19, 2018 6
Materials of Construction Structural:
Type 304 stainless steel plate, bar, and pipe ASTM A320 L7 or L43 Closure Lid & Lock Box Bolts All welded construction encasing gamma shield Copper shims between DU and stainless steel contact points Polyurethane foam for insulation & impact mitigation 0.50 OD x 0.056 wall titanium source tubes Titanium hub Gamma Shielding Cast depleted uranium (DU)
All materials have previously been used in currently NRC licensed source changers and radiation cameras
> NRC #2, June 19, 2018 7
THSC Payload Description Contents Iridium 192 (Ir-192) capsules Selenium 75 (Se-75) capsules Licensed as Special Form Contents limits 1,500 Ci total limit Maximum 150 Ci per capsule Maximum of 10 capsules per package
> NRC #2, June 19, 2018 8
Regulatory Compliance Plan Structural evaluations:
NCT compression and free drop, HAC free & puncture drops, by test All other NCT and HAC load cases by analysis Thermal evaluation by comparison to IR-100 thermal test:
Thermal test not necessary since DU shield not exposed following all free and puncture drop tests IR-100 thermal test demonstrated no shielding degradation occurs provided DU shield remains protected by stainless steel body Shielding evaluation NCT and HAC dose rates by test
> NRC #2, June 19, 2018 9
Certification Test Results Test Objectives Demonstrate resistance to compressive force per
§71.71(c)(9)
Demonstrate no degradation in shielding capability of package occurs after a worst-case sequence of free and puncture drops Demonstrate retention of special form capsules within the gamma shield Free/Puncture drop tests performed at Oak Ridge National Laboratory, March 27-28, 2018
> NRC #2, June 19, 2018 10 Certification Test Results (cont)
Compression Test Test per 10 CFR §71.71(c)(9), greater of:
5 times weight of package (=1,650 lb) or Equivalent of 13 kPa (2 lb/in2) multiplied by vertical projected area of package (=255 lb)
Applied force: 1,652 lb Result: No deformation of package after 24 hrs
> NRC #2, June 19, 2018 11 Certification Test Results (cont)
Compression Test
> NRC #2, June 19, 2018 12 Certification Test Results (cont)
Free and Puncture Drops Two full-scale, prototypic CTUs Demonstration basis: radiation dose rates comply with §71.51(a)(2) radiation limits after series of free and puncture drops Use of actual radioactive source capsules Post-test readings versus pre-test readings Tests Performed per 10 CFR §71.73 Five Free Drops Two Puncture Drops
> NRC #2, June 19, 2018 13 Certification Test Results (cont)
Free and Puncture Drops Test Conditions For high-impact drops, DU temperature cold (~ -20 °F)
Bottom down orientation, NCT & HAC For maximum crush deformation and/or high-impact drops, temperature was at NCT hot condition (~140 °F)
Top down, CG-over-corner Top down Side All puncture drop tests were performed with CTUs at post-free drop test temperature condition
> NRC #2, June 19, 2018 14 Certification Test Results (cont)
Free and Puncture Drops One NCT, 4-ft free bottom down drop, Cold (CTU-1)
Four HAC 30-ft free drops Bottom down, Cold (CTU-1)
Top down, CG-over-corner, Hot (CTU-1)
Top down, Hot (CTU-2)
Side, Hot (CTU-2)
Two puncture drops Top down, CG-over-corner (CTU-1)
Side (CTU-2)
> NRC #2, June 19, 2018 15 Certification Test Results (cont)
Free and Puncture Drops Data collected Surface temperature of DU shield Photographs Normal & high speed video Measurements Crush distance, puncture damage (if any)
Radiation Dose Rates Pre-and post-test No reduction in shielding capability recorded
> NRC #2, June 19, 2018 16 Certification Test Results (cont)
CTU-1 NCT 4-ft Bottom Down Drop, DU Surface -19 °F
> NRC #2, June 19, 2018 17 Certification Test Results (cont)
CTU-1 HAC 30-ft Bottom Down Drop, DU Surface < -7 °F
> NRC #2, June 19, 2018 18 Certification Test Results (cont)
CTU-1 HAC 30-ft CG-Over-Top Corner Drop, CTU Temp 156 °F
> NRC #2, June 19, 2018 19 Certification Test Results (cont)
CTU-1 HAC 40-inch Puncture on CG-Over-Top Corner Damage, CTU Temp 70 °F
> NRC #2, June 19, 2018 20 Certification Test Results (cont)
CTU-2 HAC 30-ft Top Down Drop, DU Surface 153 °F
> NRC #2, June 19, 2018 21 Certification Test Results (cont)
CTU-2 HAC 30-ft Side Drop, DU Surface >120 °F
> NRC #2, June 19, 2018 22 Certification Test Results (cont)
CTU-2 HAC 40-inch Puncture on Side Damage, CTU Temp 85 °F
> NRC #2, June 19, 2018 23 Certification Test Results (cont)
CTU-1 Post-Test Results Inspection of the mounting plate/lock boxes experienced no damage from NCT or HAC drop tests Brass dust caps dislodged (not lock wired for test)
> NRC #2, June 19, 2018 24 Certification Test Results (cont)
CTU-2 Post-Test Results Inspection of the mounting plate/lock boxes revealed mounting plate was bowed inward from HAC side drop impact:
0.380 inch at Tube 6 (adjacent to side impact) 0.233 inch at Tube 10 (180° from side impact)
Deformed mounting plate slightly moved lock box/source pigtail from the designed stored position in DU shield Brass dust caps dislodged (not locked wired in test)
> NRC #2, June 19, 2018 25 Certification Test Results (cont)
CTU-2 Post-Test Results (cont)
> NRC #2, June 19, 2018 26 Certification Test Results (cont)
CTU-2 Post-Test Results (cont)
View of Tube 6 (left) and Tube 10 (right) illustrating post-test mounting plate deformation
> NRC #2, June 19, 2018 27 Certification Test Results (cont)
Details of DU Shield DU shields procured from Aerojet Ordnance TN CTU-1 Shield (2012):
Shield Weight: 235 lb One source tube damaged during casting, only (9) source tubes useable Gross package weight: 328 lb CTU-2 Shield (2014):
Weight: 225 lb During casting, upper mold broke, which resulted in a 2-step casting process All (10) source tubes useable Gross package weight: 319 lb
> NRC #2, June 19, 2018 28 Certification Test Results (cont)
Radiation Surveys Both pre-test and post-test surveys were performed using actual Ir-192 special form capsules:
Pre-Test: 110 Ci/capsule (total of 1,110 Ci max)
Post-Test: 105 Ci/capsule (total of 1,050 Ci max)
During CTU-2 post-test survey, it was discovered that a trap plate was inadvertently installed in lock boxes on CTUs Plate utilized for the IR-50 Source Changer Prevented source capsules from being positioned in designed stored position near/against titanium hub Effect was to increase measured surface dose rates
> NRC #2, June 19, 2018 29 Certification Test Results (cont)
Radiation Surveys (cont)
CTU-1 measured dose rates Trap plate installed for both pre-test & post-test surveys
> NRC #2, June 19, 2018 30 Certification Test Results (cont)
Radiation Surveys (cont)
CTU-2 measured dose rates Trap plate installed for both pre-test & post-test surveys
> NRC #2, June 19, 2018 31 Certification Test Results (cont)
Radiation Surveys (cont)
CTU-2 measured dose rates Maximum surface dose rate comparison with & without trap plate installed
> NRC #2, June 19, 2018 32 Certification Test Results (cont)
Summary Regulatory Compliance Minimal damage to package from free and puncture drops IAW 10 CFR §71.71 and §71.73 No dislodgement of source capsules Pre-test and post-test radiation dose rates comply with 10 CFR §71.47(a) [NCT] and §71.51(a)(2) [HAC],
respectively
> NRC #2, June 19, 2018 33 Verification of Shield Integrity Based on certification testing of two separate DU shields, acceptance tests in application for shield integrity will include:
Ultrasonic examination at suppliers facility Shielding test upon receipt at INC facility Dimensional inspection DU shields not passing all acceptance tests will not be utilized in a THSC package
> NRC #2, June 19, 2018 34 Submittal Schedule Certification testing - Completed Compression Test - September 2017 Free and Puncture Drops - March 2018 Radiation Survey Tests - March (Pre-) & May (Post-) 2018 Anticipate submittal of application to NRC for Type B(U)-96 certification - 4th Quarter 2018 Planning on approximately 5 months to first round RAIs
> NRC #2, June 19, 2018 35 IR-THSC Package Summary