ML20009D201

Addendum to ICP-1077 SAR for Packaging (Sarp) Krypton Shipping Container USA/5958/BL(DOE-ID)

ML20009D201
Person / Time
Site:	07105958
Issue date:	01/31/1981
From:	Mortimer S, Olsen W SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:
Shared Package
ML20009D196	List: ML20009D195 ML20009D197 ML20009D200 ML20009D201
References
ENICO-1069, NUDOCS 8107230276
Download: ML20009D201 (21)

Text

{{#Wiki_filter:_ _ _ _ ENICO-1069 ADDENDUM TO ICP-1077 SAFETV ANALYSIS REPORT FOR PACKAGING (SARP) KRYPTON SHIPPING CONTAINER USA / 5958 / BL (DOE-ID) JANUARY 1981 Idaho Falls, Idaho 83401 l E@N NUCLEAR IDAHO COh;PANY, Inc. DEPART bb b ENERGY IDAHO OPERATIONS OFFICE UNDER CONTRACT DE-AC07-79lD0'.9 ,s $$A7$S8EE.6$i2335* 0 C PDR

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t I cf I. i l- + i. l I' ~ ADDENDUM T0 ICP-1077 SAFETY ANALYSIS REPORT FOR PACKAGING (SARP) 2-L KRYPTON SHIPPING CONTAINER l USA /5958/BL(DOE-ID) c i r i- ~ Prepared By: l 'S. R..Mortimer [ W. C. Olsen l till> 3 January 1981 !~ r l' Exxon Nuclear Idaho Company, Inc. b P.O. Box 2800 l s-1955 Fremont Avenue Idaho Falls, Idaho 83401 h 8 e f O I

SUMMARY

fi This report is an addendum to the Safety Analysis Report for Packaging C/ (SARP) for the Krypton Shipping Container, USA /5958/BL (EF DA-ID), issued by Allied Chemical Corporation as Report Number ICP-1077;l it has been prepared to incorporate: (1) Use of the D0T Specification 3AA compressed gas cylinder cs a primary containment vessel (49 CFR 178),2 (2) an - alternate closure valve for use with the primary containment vessel, (3) - a preloading helium leak test procedure to verify ieak tightness of the primary containment and a preliminary Kr-85 leak test, and (4) updated procedures concerning preparation of the package for shipment. This Safety Analysis Report for Packaging Addendum is pre,nared under the jurisdication of Exxon Nuclear ' Idaho Company, Inc. (ENICO,, who assumed the contract for operation of the Idaho Chemical Processing Plant from Allied Chemical Corporation (ACC), Idaho Chemical Programs (ICP). Ac-cordingly, all references to Allied Chemical Corporation (ACC) and/or Idaho Chemical Programs (ICP) as included in the original report (ICP-1077) have been changed to Exxon Nuclear Idaho Company, Inc. Similarly, all references to AECM Appendix 0529 should be construed to refer to the current document in use 'ERDAM Appendix 0529). This addendum's organization is the same as used in the original report civ.h it allows for direct correspondence between the re-(ICP-10775-as port

eco, sections, thereby clarifying what changes have been 2e changes affect the report's substance.

made c h Addeadum to the Safety Analysis Report for Packaging (SARP) Krypton Ship- "/ ping Container, identified as USA /5958/BL (DOE-ID), prepared as Allied Chemical Report ICP-1077. e o iii )

I. Intrcduction {} Nri Change Required. II. Authorized Contents Ne Change Required. O III. Description of Protective Packaging Section A, Compressed Gas Cylinders: Include'as a condition. .(1) The 00T 5pecification 3AA-2015 Cylinder may be substituted for the 3A-2015 cylinder. (2) Nupro bellows valve, Series T (#SS-6 TAW-TSW or #SS-6 TAG-TSW), may be used as an alternate for the Kerotest valve (see Figure A-1). This valve wa tested at various temperature and pressure (see Appendix Ag) and proved to be leak tight under all conditions tested. The Nupro bellows valve has positive stem retraction, safety back seat sealing, and is 100 percent Helium leak tested by the manufacturer. The valve body is constructed of Type 316 stainless steel and has a pressure and temperature rating of 2,000 psi (max.) Q at 6000F. All other parts of the valve are constructed of \\ / steel, except the valve actuator handle (aluminum). A one (1) ' inch joining nut connects the valve bonnet to the valve body (#SS-6 TAG-TSW) and should be torqued to at least 450 in. lbs but not to exceed 550 in, lbs prior to use. The valve bonnet is welded to the body for "T" ser as

1. SS-6 TAW-TSW valves.

Da Nupro bellows valve is adapted for this use by: (1) cutting off the valve stem (valve in closed position) 3/8-inch above the bonnet and cutting a 1/8-inch deep by 0.094-inch wide slot in the stem; and (2) attaching a 3/4-inch 14NPT fitting to the valve inlet and a 0.825-14NG0 L.H. Ext. CGA 350 fitting to the valve outlet (see Figure A-2). These changes do not affect the operability of the valve. Section B, Shielding Coatainer: Include as a condition. (1) The use of the Nupro bellows valve will require slight modi-fications to the shield container plug. As shown in Figure A-3, the existing cask plug design will be modified by remov-ing the extended portion of the 3/8-inch shaft collar. Re-p) moval of material shall be accomplished so that the lead ( will not be exposed. u 1 l I

O 1 e 1 2.? 4" = e aw Axxxxxx j j, l ,.x m xxxxxx l l 1 1 6-1/8 Open i 6-5/8 Open 92 1:h 6-33/64 Closed 51/32 Open i 1 4 A re :s s W nw q j y iN $ 3 kI_ I !Ht,: A '[- Outlet M T/ i .Y _ _~~i - _ \\ \\b \\ \\ ga -i i t -3/4 Tube Bell b /2 Tube Socket Weld 1 3/8 1 -7/ 8" = ICPP-A-5763 Figure A-1. Nupro Bellows Valve, As Purchased. O 6 2

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The modification will not affect the shielding integrity of f3 - the container, the-Kerotest valve compatibility, or pose any -( )- problems with the container plug / body connections. v e Section C,-Thermal Insulating Container:

Include as a condition.

(1) The' Thermal Insulating Container will be conscruc*.ed of car-bon steel or other equivalent material. IV. Control Methods and Procedures Section A, Administrative Procedures: . Include as an addendum the following leak test item. This test shall be -used with the modified cylinders as described in this . addendum: (1) Testing a. Package Containment Testing - Testing of the Krypton Shipping Container is divided into two (2) parts: 1) Helium Leak Testing and 2) Kr Leak Testing. b. Leak Testing Leak tests on the cylinder / valve assembly shall be con- '(a) ducted prior to loading and prior to shipping. A Helium N_) (He) leak test of the crimary containment (cylinder / valve assembly) is performed before it is loaded with krypton product. This test is required: (a) for new assemblies (i.e., prior - to first use), (b) af ter every third use, or (c).if twelve months have elapsed since the preceding use. The test is to determine that the leak rate from the primary containment vessel is less than 1 x 10-7 atm-cm3 sec (leak tight).3 l. / l-A Kr leak test is also performed on the cylinder assembly i prior to shipping; this second test assures the leak rate is less than 0.278 pCi/sec at normal operating conditions.3 1. Helium Leak Testing - The He leak testing will be conducted in a specially designed leak test chamber (shown i, Figure A-4). The apparatus was designed for the leak test methods suggested in ASTM Stan-l dard E4!r9 (1973).4 The leak test method used on our cylinder / valve assembly is Method B.4 In conducting the He leak tests, the cylinder and -attached valve are first evacuated to a maximum absolute pressure of 10 pascals (75 microns Hg); (n they are then filled with high purity helium gas to 1 d one atmosphere. The loaded cylinder is placed in the test chamber and the chamber evacuated to 5

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establish a pressure differential and remove any contaminant gas that would contaminate any leaking .( s\\ He. Leaking He is withdrawn from the chamber by a N._,/ vacuum - pump through a Helium Mass Spectrometer. (The leak rate shall not exceed 1x10-7 atm-cm /sec.) 3 )~ The Helium Mass Spectrometer shall be calibrated with a standard "He laak" prior to conducting the test. ii. Kr Leak Testing - After loading with Kr, each cy-linder/ valve connection is Kr leak tested with a Constant Air Monitor (CAM) equipped with a sniffer hose. At this point, the primary containment vessel must have a leak rate of less than 0.278 pCi/sec. This test is done with the cylinder inside the shielding container. (2). Cask Loading Description As a condition of closure on the Nupro valves, the following shall apply: CAUTION: Torque appiied to close the Nupro bellows valve should be limited to 100 in.-lbs however, greater torque may - be required to prevent leakage. A torque of approximately 450 in.-lbs broke one side from the slot in the valve stem (no visible damage to valve intervals). kj (3) Cask Unloading Description 3 NOTE: The tool supplied with containers using the Nupro bellows valve -- a blade (screwdriver) designed to fit the slot machined into the valve stem -- is secured in the shield with 3 set screw. This screw must be loosened to allow the tool to be positioned. (4) ~ Standard Operating Procedures References to the following SOPS are no longer applicable: S0P 1.6.7.11, " Radioactive Shipment Tiedowns," S0P 1.6.7.12, " Radioactive Shipments," and S0P 1.6.7.13, " Inspection and Maintenance Program for Radioactive Material Shipping Casks and Containers."- Rather, applicable procedures are included in the Exxon Nuclear Idaho Company, Inc., Manual, " Packaging,

Shipping, Receiving, and Transportation of Radioactive Materials."

~ In addiMon, S0P 4.2.9.4 " Product Distillation, loading, ' Sampling nd Shipping," has been replaced by S0P 4.3.29.4, " Gas Prr <t Distillation, Loading, and Sampling." Add references to S0P 4.3.29.8, " Product Container Leak f3 Test" and S0P 6.3.19, "Kr-85 Leak Test of Shipping Cylinder." b 7 L_

Section B, Radiation and Contamination Control: No change required. Section C, Preventive Maintenance: Standard Operating Procedure (S0P) 1.6.7.13 has been incorporated in the ENICO " Packaging, Shipping, Receivirg, and Transportation of Radioactive Materials" Manual. Section D, Quality Assurance: To satisfy requirements of ERDA Appendix 5201, Part V, ENICO has established and implemented a Quality Assurance Program. The Quality Assurance Program is administered through the ENIC0 Qual-ity Assurance Program Manual. The program is used during the design, procurement, fabrication / modification, maintenance, and testing of the Krypton Shipping Container. The ENICO QA Manager is responsible for Quality Assurance functions associated with this program. Using ENIC0's graded approach to Quality Assurance, the shipping container has been given a QA classification of "QA Level A," the highest Quality Assurance classification for safety-related items. Accordingly, all requirements specified in ENICO CS0P 1.1.4 for QA Level A classification apply. Quality Assurance requirements associated with the design, pro-curement, fabrication / modification, maintenance and testing of the Krypton Shipping Container include: (1) Design and Development: Design changes are controlled as specified in the ENICO S0P's. Review and approval of design changes are comensurate with that of the original design. (2) Procurement: Procurements documents are reviewed by ENIC0 Quality Engineering and Inspection to assure that all Quality Assurance requirements are specified and material is pur-chased from approved suppliers. (3) Fabrication / Modification: Maintenance Job Requests (MJR's) are used to request fabrication / modification changes. De-tailed inspection pla,oing incorporated into the MJR provides a means for documerting and verifying conformance to proce-dures, instructions and drawings. Calibration of measurino and test equipment is performed by EG&G Idaho, Inc. at the calibration laboratory. Non-conformances are handled by issuance of Non-Conformance Reports (NCR's) in accordance with ENICO S0P's. (4) Certification of Personnel and Equipment: Welding required for fabrication, modification or maintenance is performed by personnel qualified to the INEL Weld Procedures Specification Manual. All Non-Destructive Examinations are performed by 8 )

1'. %' 1: 3 : ; ..n ; W :. .?: 2.y, _ ! * :=...s. w,.;,, s. my personnel qualified to meet the requirements of SNT-TC-IA in accordance with the ENIC0 Non-Destructive Examination Proce-dure Manual. (5) Operations-Maintenance: An auditable Preventive Maintenance (PM) Program keeps the shipping container in satisfactory condition. Inspection frequency and maintenance requirements are programmed into the PM computer. This program is in accordance with Exxon Nuclear Idaho Company, Inc., Manual, o " Packaging, Shipping, Receiving, and Transportation of Radio-active Materials." (6) Records: Quality Assurance Records related to the shipping container are classified as Life-Time Records for retention by ENICO. V. Safety Analysis No Change Required. Section A, Fire and Explosion No Change Required. Section B, Nuclear Criticality No Change Required. Section C, Direct Radiation No Change Required. Section D, Temperature Rise From Decay Heat No Change Required. Section E, Maximum Credible Accident No Change Required. VI. Conclusion No Change Required. 9

SARP REFERENCES 1. No Change Required. 2. No Change Required. 3. (Delete; replace with): Quality Assurance Program Manual, ENI-127, Exxon Nuclear Idaho Company, Inc. 4. Delete. 5. h' Change Required. 6. No Change Required. 7. No Change Required. 8. No Change Required. 9. No Change Required. Appendix A, Structural Analysis for Krypton Shipping Container No Change Required. Appendix B, Thermal Analysis for Krypton Shipping Container No Change Required. Appendix C, Thermal Analysis Supplement for Krypton Shipping Container No Change Required. O 10

ADDENDUM REFERENCES } 1. C. W.' Nielsen, Safety Analysis Report for Packaging Krypton Shipping V Container USA /595'/B1 (ERDA-ID), ICP-1077. I a l -2. 40 CFR 178 (1979 edition) Subpart C, " Specifications for Cylinders," paragraph 178.36, Item 1 through 22 (178.37 for D0T Specification g -3AA cylinders). 3. ANSI Standard N14.5 (1977), "American National Standard for Leakage Test on Packages for Shipment of Radioactive Materials."

4., ASTM Standard E499 (1973), " Standard Methods of Testing for Leaks Using the Mass Spectrometer Leak Detector in the Detector Probe Mode."

i e L i l l J L O l 11

APPEND:X Al 1. NL;PR0 BELLOWS VALVE TEST ~

Purpose:

Test the "T" series Nupro Bellows Valve under various conditions of temperature and pressure to demonstrate the integrity of the valve when subjected to simulated conditions of normal operation, e The maximum allowable, helium leak rate through the valve shall cm /secl at all temperatures, pressures 3 not exceed 1 x 10-' and combinations thereof under which the valve is tested. Test Apparatus: A helium mass spectrometer leak detet - (Dupont Company Model

1. 141430 or equivalent) was used to measure che leak rate from the valve seat.

Prior to each test the mass spectrometer was checked using a calibrated helium leak source supplied by E. I. DuPont de Nemours and Company and identified as Serial #4045. This source 3 provided a known helium leak rate of 4.037 x 10-8 atm-cm /sec. All test results were compared to this known helium leak rate. High purity helium was used as the test gas. TEST 1: The test valve was subjected to an internal pressure of approxi-mately 55 atms at ambient temperature. Procedure: The valve was attached to a cylinder filled with helium (through the valve outlet) and pressurized to about 55 atms. The valve was closed with the blade tool (screwdriver) and torque wrench, using 100 in.-lbs of torque. The helium supply was re-moved from the valve and the valve outlet then con-nected to the helium mass spectrometer for measure-ment of any leakage. Results: Valve # Cylinder Pressure Leak rate (cm3 sec) / V-4 830 psig 6.7 x 10-9 i Valve tested performed satisfactorily, TEST 2: Three test valves were subjected to temperatures ranging from ambient to 2000C and a one (1) atm pressure differential. Procedure: The valves were attached to cylinders, pressurized to approximately one (1) atm, closed using about 50 in.-lbs torque, and connected to the helium mass spectrometer as in test #1. A thermocouple was attached to the valve body to record temperature and the valve was wrapped with a heat tape. The 12

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. valve - was : heated slowly -(about 100C/ min) ~ and the helium: leak te measured at temperature increases O of~ approximately 250C. .-This procedure. was-repeated for each valve tested. -j. ci

Resuits:

Valve i-.Tenperature OC . Elapsed time (min) He Leak Rate (cm3 sec) / j V-3 20.8 0 1.5x10-9. 46~ 10.8 '7.62x10-10 75 ~ 24.3 *. -7.62x10-10 -100 30.8 7.62x10-10 -9 ~125 36.0 1.5x10 150 43.0 1.5x10-9 175. 47.0 7.62x10-10 ~ 193 52.3 0* 200-55.3 0 215 75.0 0 V-4 20.4 0-9.4x10-10 50 6.5 9.4x10-10 75' 13.3 9.4x10-10 ~ 98 23.0 2.8x10-9 100 27.0 1.9x10-9 102 32.0 1.9x10-9 125 35.5 1.9x10-9 150 41.0 1.9x10-9 .175 46.0 1.9x10-9 200 50.0 1.9x10-9 200 60.0 9.4x10-10 200 65.0 0* a. V-6 19.4 0 9.0x10-10 25 2.0 0* 50 9.0 0 75 13.2 0 8 100 21.0 0 I i il 13 L. i

Valve # Temperature OC Elapsed time (min) He Leak Rate (cm3 sec) / V-6 125 27.5 0 150 33.2 0 175 38.0 0 200 47.7 0 200 58.0 0

• 0 indicates the leak rate was less than detection limits (9.0x10-10 cm'/sec).
  • Valve being tested showed signs of leakage.

Valve was retorqued (about 50 in.-lbs) and test continued. All valves tes ted performed satisfactorily. TEST 3: The test valve was subjected to an internal pressure of approxi-mately 55 atm and temperatures ranging from ambient to 2000C. Procedure: The valve was pressurized to approximately 55 atm internal as in test #1 and heated from ambient temperature to 2000C as in test #2. Results: Valve # Temperature OC Elapsed time (min) He Leak Rate (cm3 sec) / V-4 26.4 0 6.7x10-9 50 10.1 5.8x10-9** 75 17.1 6.7x10-9** 100 22.8 9.2x10-9** 200 3.1x10-8 Temperature was maintained at 1020C for approximately 25 minutes before continuing to 2000C.

• • Baseline leak rate t xcluding spiking, largest spikes approximately 10 s in duration and represented leak rates greater than 1x10 qcondg/sec.

' ce In this test also, leak rates were well below prescribed limits.

== Conclusion:== The "T" series Nupro Bellows Valve has t een tested successful'y under various conditions cf tempera- ~ ture and pressure. The integrity of the valves tested was sufficient to prevent helium leakage greater than 1x10-7 cm3 sec at pressure of 55 / atms and temperatures up to 2000C. 14

II. HELIUM LEAK TEST OF PRIMARY CGNTAINMENT VESSEL [

Purpose:

tV Assure the primary containment vessel of the ICPP Krypton Shipping Container USA /5968/BL(D0E-ID) is ". leak tight" (as defined in ANSI Standard N.14.5)I rior to loading with Kr-85. p O Test Apparatus: A helium mass spectrometer ' leak detector (DuPont Company Model

1. 141430 or equivalent) shall be used in conjunction with the he-lium leak test chamber pictured in Figure A-4 of the Addendum.

Prior to each test the mass spectrometer shall be calibrated using a known helium leak source. High purity helium shall be used as the test gas. Procedure: The primary containment vessel (cylinder / valve) shall be filled with helium, by connecting the valve outlet to the helium supply, and then pressurized to one (1) atm. The valve is to be closed with the blade tool and a torque wrench using approximately 50 in.-lbs of torque (greater torque may be required to prevent leak-age). The valve is then disconnected from the helium supply and placed in the test chamber, which is then closed and evacuated (0.2 microns) to remove any contaminate gas, and to establish a fG pressure differential. The mass spectrometer is used to measure )- the helium leak rate from the vessel. Results: Only those vessels which are " leak tight" shall be approved for Kr-85 loading. Those not passing the test shall be tagged as failing. III. Constant Air Monitor Kr-85 Test

Purpose:

Determine if the Constant Air Monitor, CAM (Nuclear Measurement Corporation Model AM-2D) can be used to measure the leak rate of Kr-85 from the ICPP Krypton Shipping Container USA /5958/BL(DOE-ID). The maximum allowable leak rate of Kr-85 from the container is 0.278 N.14.5.pCi/sec as determined by he use of ANSI Standard { Test Aoparatus: A Constant Air Monitor (CAM) is used to measure Kr-85 which may be leaking from the container. The CAM is equipped with a 'snif-(] fer" hose for remote monitoring. A known Kr-85 source was used ' (v) to evaluate the CAM response. i 15 L

Procedure: A known quantity of Kr-85 was released into the CAM at a rate of 7.2x10-3 pCi/sec with the CAM filter removed (flow r9e of 2.5cfm). Results: The CAM showed an increase of 100 c/m when the Kr-85 was released to the detector. The CAM sensitivity was calculated as being equal to 1.4x104 [ec. CAM Response is plotted in Figure Al -1.

== Conclusion:== l The graph (Figure A -1) reveals that the suggested Kr-85 leck rate of 0.278 pCi/sec is.tithin the detection limits of the CAM and would result 5 an approximate increase of 3800 counts / minutes. IV. Allowable Kr-85 Leak Rate

Purpose:

Determine the dose rate that could be directly attributed to Kr-85 leaking at a rate of 0.278 pCi/sec. Assumptions: The container will be shipped in a closed trailer 34 f t. x 7 f t. x 7.5 ft. having a wall thickness of 0.64 cm of aluminum. There will be no leakage of material from the trailer. The dose rate at the outer surf ace of the trailer was calculated to be 0.35 mrem /hr/C1. Results: Shielding Calculations were made using the QAD-P5A computer code.4 Calculations showed that a continuous leak of Kr-85 at a rate of 0.278 pCi/sec would result in an increase in exposure of 0.06 mrem /hr with an accumulation of Kr-85 over a seven (7) day peri-od. Dose rate increase is plottea in figure Al-2.

== Conclusion:== l The graph (figure A -2) reveals that the suggested leak rate of 0.278 pCi/sec would not add significantly to the exposure of personnel associated directly or indirectly with the shipment. O 16

u-o (! CAM RESPONSE-vs Kr-85 LEAKAGE 5 10 i i i i i iii; i i i iiii; i i .i i i i i,_ C CAM - AM2D NO FILTER O FLOWRAT' = 2.5 SCFM U N 3 S I M l 3 N O. 278 JJCI/SEC R /' I / E 3 __ j j 10 O N ./ i / I C / 3 A / l l M i i l i te r ,,,i ,,,,i -3 -2 -1 10 10 gg 3 Kr-85 LEAKAGE CMICROCURIES/SEC) FIGURE A -1 i i

O s g --- D i 0 i S KR-85 LEAKAGE INTO A TRUCK FROM CASK 4 E l LEAK RATE = 0.278 MICR0 CI / SEC ~ i R .06 l 4 A T i m, i i pt I !.04! l O l L l m 1 l f l R .02 ! P E l l R I _l t R . 00 - l--- - --{-- -t 4l- -t l 5 1 2 3 4 5 6 7 ~ LEAKAGE TIME (DAYS) FIGURE A -2 18

- - ~. . ~ Ir; i _ (

Reference:

b 1. ANSI Standa,d N.14.5 (1977), "American Natinnai Standard for ~ Leakage Test on Packages for. Shipment of Radioactive Material." i i o-2.- Ibid. j;, 3.: Ibid. 4.. E...Solomito and J. Stockton, " Modifications of the Point-Kernerl Code QAS-P5A: Conversicn to the IBM-360 Computer and Incorpo- -ration of Additional Geometry Routines," July, 1968, ORNL-4181. r i I i k h f f. l t s s ' ) e. 19 l}}