ML20035A331

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Resubmittal of Prior Applications & Suppls for Approval to Transport MW-3000 Radioisotope Thermoelectric Generator as Type B Package
ML20035A331
Person / Time
Site: 07109030
Issue date: 11/30/1990
From:
TELEDYNE ENERGY SYSTEMS
To:
Shared Package
ML20035A328 List:
References
FOIA-92-470 TES-3233, TES-3233-01, TES-3233-1, NUDOCS 9303250155
Download: ML20035A331 (98)


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RESUBMITIAL OF PRIOR APPLICATIOts AND SUPPLDETIS FOR APPROTAL 'ID

'IRAIEPCRT THE PM-3000 RADICISOIDPE THERN.NC GENERATCR AS A TYPE B ( ) PACFJGS REPORT 10. TES-3233 i

I M asER 1990

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PREPACE By this suteission, Teledyne Energy Systems (TE.S) hereby requests approval for transport of its Md-3000 Radioisotope Thernoelectric Generator (RTG) as a Type B ( ) package.

The cost recent Certificate of Compliance, Certificate Nunber 9030, pertaining to the Ed-3000 RM was issued bf the U.S.

Nuclear Regulatory Cocnission as Revision Number 4 dated October 22, 1985.

Its expiration date is October 31, 1990.

This report consists of a cocpilation of the previously submitted information specific to the MW-3000 RTG and previously submitted inforration relevant to the units covered by the Certificate of Compliance.

The following drawing and references, cited in the Certificate 9030, are those applicable to the Md-3000 RM.

Drawing:

Martin Company 471A1000000

References:

(1) Martin Cmpany Application dated June 16,1%5.

(2) Martin Company Supplement dated July 22, 1966.

(3) Martin Company Supplement dated August 16, 1966.

The NA-3000 RTG was designed to produce three watts of electrical power over a ten year operational lifetime and was designed to operate undersea at depths up to 2000 feet.

Four Ed-3000 RTG's were fueled in August of 1966. One unit was tested and evaluated by the U.S. Navy for approxicately four years and disposed.

The remining three units are presently in storage at Nuclear Sources and Services, Inc. in Houston, Texas.

The Ed-3000 RM's were designed of the Martin-Marietta Corporation.

When this division was acquired by Teledyne, Inc. in 1968 the MW-3000 RTG was renamed as the Sentinel-3 RM (see Item 9).

However, no RTG's were fabricated under the new Sentinel-3 designation.

Each unit, veighing approximately 2800 lbs, is constructed with a forged 4130 steel housing, a tungsten alloy shield plug and a fuel capsule of Hastelloy C.

The fuel capsule contains about 25,000 curies of Strontium-90 in the titanate form.

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At the tire of the original subctittal, some of the submitted sterial l

vas considered by the Martin Company to be proprietary mterial. This is no i

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longer the case.

Regardless of proprietary stamps, all information provided in this report is considered to be non-proprietary and my be mde available 5

to the general public in accordance with current 130 policies.

i The applicable assembly Drawing 471A1000000 is also enclosed with this l

report.

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The original sutr.ittal for license application was Martin Company l

f Report ACC-486, " Proposed Amendment to Byproduct License No. 19-1398-34,"

dated June 16,1%6.

This sutxnittal has been included herein as Item No.1 (see Table of Contents).

Item 2 entitled " Addendum to Martin Marietta

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Corporation June 16, 1966 Application for Amendment of Bypro$uct License No.

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19-1398-34," includes three addenda including A.

Stress (includes both lifting and tie-down) and Impact Analysis, B. Fire Analysis, and C. Radiation l

Analysis.

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Martin Company Letter 6321 dated July 22, 1%6 (Item 3), provides

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j additional infotration concerning a four-foot drop, mximum temperature for w

i the tungsten shield and drawing co::ments.

I Martin Company NTD-50, " External Hydrostatic Pressure Qualification f

Test," April 25, 1966 (Item 4) and IDC, "N-3000 Vessel and Cover," August l

25, 1966 (Item 5) present the test specification and test report, respectively for the housing pressure qualification.

Martin Company Report MN-lC187, April 8,1%6 (Item 6) and an IDC dated 1

July 1,1966 (Item 7) are the specification and specification change notice for the encapsulated Strontium-90 heat source.

I Mattin Company Nuclear Test Directive, M-3000 Puel capsule, April 15, i

1966 (Item 8) is the fuel capsule hydrostatic test specification.

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TABLE OF CatfrfATS 1

l Item No.

Page Preface 11 Table of Contents iv 1

Martin Company Report ACC-486, Proposed 1

Amnd:nent to Byproduct License No. 19-1398-34, June 16, 1966 2

Addendum to Martin Marietta Corporation 26 June 16, 1966 Application for Amendment of Byproduct License No. 19-1398-34, Undated i

Addendum A Stress and Impact Analysis 27

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J Addendum B Fire Analysis 59 l

Addendum C Radiation Analysis 66 i

3 Martin Company Report 6321, Additional 74 Infornation - Martin Kd-3000 Thernoelectric l

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Generator - Byproduct License 19-1398-34, July 22,1966

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4 Martin Company Nuclear Test Directive hTO-50, 76 i

External Hydrostatic Pressure Oaalification Test (Ed-3030 Vessel and Cover), April 25,1%6

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5 Martin Company IDO, NW-3000 Vessel and Cover, 79 i

August 25, 1966 i

6 Martin Company Report 204-10187, Specification 84 for Strontium-90 Heat Source for the M4-3000 Generator, April 8,1966 7

Martin Company IDO, Change Notice to MN-10187, 89 July 1,1966 8

Martin Co w y Nuclear Test Directive, Proof 93 Pressure Test at Operating Pressure (Ed-3003 Fuel Capsule), April 15, 1966 9

Letter to R. B. Chitwood (AEC) from P. J. Faapp 96 (Teledyne), PJK:1210-018, December 19, 196B C

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suscs .} June 16,1966 Refer to: 3 ACC-486 i i U. S. Atomic Energy Commission j Division of Material Licensing Washington, D. C. Attention: Mr. W. H. Ray, Irradiated Fuels Branch

Subject:

Proposed Amendment to Byproduct License No. l 19-1398-34 i

Reference:

(1) Application dated May 16,1966 (ACC-480) (2) Application dated May 4,1966 (ACC-476) f (3) Application dated October 28,1965 ( ACC-437) (4) Application dated August 13, 1965 i

  • f (5) Title 10 Code of Federal Regulaticns, Chapter 1 Part 2, Rules of Practice, Section 2. 790 (6) AEC letter (DM/L-IFB:WHR) dated June 6,1966 from A. McBride to C. W. Keller i

Gentlemen: 1 'The Martin Marietta Corporation hereby requests that Byproduct License l No. 19 -1398-34 be amended to include the transportation, display, and demonstration of Martin thermoelectric generators designated MW-3000. Thank you for your effort.in issuing Amendment No. I to License No. 19-1398-34 which authorizes the possession and use of the MW-3000 at j our facilities at Middle River, Maryland. l This application is separated into nonproprietar'y and proprietary sections. The nonproprietary section is intended to be a general description of the MW-3000 generator and a summary of analysis results which conclusively i shows compliance with applicable regulations. The analyses ~which define I specific characteristics of the MW-3000 are Martin proprietary information l and must be withheld from the public document files. Dissemination of [ t .~ ~ 00G1 i ~ A DIVISION OT WMT mmer.x m-

$ June 16,1966 Mr. W. H. Ray t "= this information would greatly affect Martin's competitive position with considerable financial loss of Martin funds expended in our f development program. Since our nonproprietary section summarizes the analytical results, the detailed analyses are not needed in the public interest. Reference 6 included your concurrence with our i position to withhold a drawing of the,MW-3000 from the public document files. The proposed part 71 of title 10 of the Code of Federal Regulations i has formed the basis for our evaluation and we have included the results of our analyses to show compliance with these requirements. We have not, in most cases, redefined material properties or fabri-cation techniques and refer you to references 1, 2 and 3 since this information is commonly applicable to both the Martin LCG-?.5 and the l MW -3000. We appreciate your guidance in establishing a complete i format for this application. iis Very truly your s, ~ MARTIN MARIETTA CORPORATION MARTIN COMPANY, Baltimore Div. i l C. W. Keller Nuclear Materials & Licensing Representative i CWK: mal i h i I l -u 00G2

22 ~1 s l /. 2 ' 4 APPLICATION FOR AMENDilENT TO BY-FRODUCT License No. 19-1398-34 r?. "I.. Transport, Display, and Demonstration l of 11artin Thermoclectric Generator i 1:odel lih3000 t ? 4 t 00G3 i +4*

h.. ~ TABLE OF CONTENTS 1. General Discussion A. Introduction B. Safety Philosophy and Design Criteria II.

System Description

A. Generator Assembly B. Biological Shield -~s-Q, C. Heat Source D. Radioisotope Fuel E. Quality Control III. Har.ards Evaluation A. Licensing Regulations .., Accident Environments B. C. Radiation D. Tampering 1 i l L..... ~~ 00G4 l ~~ - - ....2

i i r e _i .~. r 4-f t ( t i I r e b r -I c e sV' GENERAL DISCUSSION 4 L r i N [ i 4 I k i i i f ( w' 00G5 t e g ,1 t p .m 3 - waea =+. +4 -4e 6 ,#y, f._. 4 f

.y_ ~. f t J ~ I. General Discussion A. INTRODUCTION This report presents a description and nuclear safety eva'luation of the llartin IPS 3000 tcdel of a lot. cost radioisotope thermoelectric generator w: ich can b,e used for terrestrin. L: navigational applications. The L?? 3000 generator is an inherently safe device and its' radioisotope $ cat source nay be considered as a sealed source which is uneffected by modifi-l cations in the energy conversion subsystera or in the quantity i 5 of fuel loading. ~~ (- D. S4Fi:TY Pi!ILO3(*P!1Y AND DESIGN CRITERI A I In the application of atomic energy the most important l ~l aspect of any safety philosophy is the protection of the gen-eral public from any undae hazards. To obtain this goal the most desirable approach is to achieve absolute containe.ent of the radioisotope fuel under all normal and accidents 1 shipping, j handling and operational conditions. ) Consistent with this approach, 'the IFT 3000 heat source ) has been designed as a sealed source that is highly resistant i to: a. mechanical loads and shocks, j 1 a b. elevated temperatures, l 7 c. tampering i 00GG 1 i -~ ^

= l o. Page 2 l L Specifically, the EM 3000 has been designed to provide the w-4 following safety and structurcl criteria: 1. Fuel compatibility with containment structure. l 2. Necessury and sufficient biologicn1 shiciding to com-l ply with present ICC and ACC shipping and handling regulations. 3. Negligib'le radiation effects on the structural integrity ) of the gencrutor Lutorials. 4. Negligibic chemical cud physical reactions between component materials. 5. System operation and fuel cor.tains..ent at sea depths t greater than 2000 feet. 6. Fuel containn.ent under the following sequence of accident environr.:ents without increasing the dose rate at one l 4 ructer frota the surface of the source by more. than a { l factor of 100: a. Free fall from a height of 30 feet onto a i rigid non-yielding surface b. Drop frou 40 inches onto a steel cylinder U ~ lNposure to an accident' fire of 1475 F for a c. period of 30 uinutes t d. Intersion in water for a 24 hour period l To assure the integrity of these safety design features, the strict quality control with regard to p.aterials - and v.ork-l manship during manufacturing and assen.bly will, as usual, be -l 4 c.aint ai n e d. ^ '.4 00G7 1 4 l 1 e ~ N

K e, Page 3 II. Sy s t er.: Description ~~~ 'The W 3000 (CG is an advanced model of the LCG -25A, ' -prototype'or a new line of radioisotope thermoelectric gener-ators designed by the Lartin Company for commercial terrestrial and undersea applications. Decause of its long hulf-1ife, avail- ~ ability, and relatively good cher.iical compatibility with con-tainuent r..aterials, strontion:-00 was chosen as the nuclear fuel for these syster.s. The LE 3000 gene'rator, ucighing around 2650 lb, is fueled with approximately 25,000 curies of strontium titanate compound, enou5h fuel to produce three electrical watts after a ten-year operational lifetime. As with the LCG-25A, the 3000 pr asse;.bly cos. prises a s '~- nuclear heat source, energy conversion unit, and biological shielding. The containraent of the strontium-90 fuel is such that even under the : echanical and thermal environments of a transportation accident the heat source will remain intact, thereby precluding any possible relense of the radioactive materful. A. GENERJsTOR AS3is.BLY The strontium titanate fuel is doubly contained in a ~ cylindrical Haste 11oy-C capsule and liner serving as the heut This capsule is surrounded by several layers of source. Johns-1;unv111e LIN-K insulation which, in addition to preventing substantial hoot losses, provides positioning support for the capsule. The structual strength and shiciding for the system m_a is attributed io a 2500 pound outer shell of forged steel. 00GS 9 s e n mm.

Page 4 O' Directly above the heat source is a 25 lb tungsten alloy f block, the purpose of which is to provide sufficient shielding . from radiation to allow removal of the outer steel. cover plate,- the inner lid, and the thermoelectrics. The thern.oelectric modules are spring loaded axially und are positioned between the steel hot plate and the aluminum heat sink. Thus, a positive et.nduction' heat path is provided to and from the thern.o-elec'trics. The heat frou the thermoelectric modules is rejected ~ through this aluminum inner lid by conduction to the steel case. . There is sufficient surfuce area on the EM 3000 generator to dissipate the heat from the thermoelectrics so that no fins are retuired for this design. The steel lid is bolted to the gen-t ci.A-crator case and "O" ring se'als are used at the lid-case interface s, to keep water out of the generator interior should it be immersed in unter. There is a water tight electrical connection on the lid to facilitate generator replacenent during maintenance t activities. An internal atmosphere (at 1 psig) around the modules is prevented from mixing with the air environment betueen the ihner and oufer lid by a second'"0" ring and betwee'n the inner lid and the generator ca,se. The Senerator norn. ally rests in the vertical position 7: during generator assembly and shipping. All lif ting of the j generator is accomplished by the four lifting lugs which are l l attached to the generator case. The positioning of the gener-ator during operation is not critical. l 1. Fuel Block Support The fuel block, which cons *ists of the heat source and ~ 00G9 ~* I ,,s

/c Page 5 I-inner shicid, is supported by the liIN-K insulation on the sides and bottom of the fuel block. The conbination of the steel hold [ a down ring around the top of the tungsten shield, the insulation, and the stee] ring on top of the-insulation'prever.ts the. fuel l from escaping from the generator once it is installed. Therefore, i' tne fuel capsule will reuuin in the generator case even if the i case should be in a horizontal position while the r..odule is being renoved. Tnis design also prevents the full weight j fuel block fror.. bearing down on the thers oclectric module.. of the 2. Insulation All thermal insulation is Johns-Manville 1.IN-K 1301. The insulation around the sides and bottom of the generator will be fabricated in layers from sheets. The insulation around the or nodules is a specially fabricated ' sheet of insulation. HICI.OGICAL.VIICLD D. 1. Internal Tunesten Shield Block The internal tungsten alloy shield is a solid right circular cylinder. The heat source is attached at one face by a machined threaded stud so that the two pieces form a heat block assembly. This shield is provided.to allow for assembly and disassembly of the thermoelectric modules into the generatur after the generator has been fueled. The steel hold down rings are so designed that the fuel block will remain positioned within the generator. Personnel will not he exposed to excessive radiation levels under any situation while the lids of the f generator are removed. 2. Wrought Steel Case The outer shell of the generator is wrought steel. It ~ OCP70 t

Page 6 [, has a right circular cylindrical shape with one face cachined out to accept the fuel block, modules, insulation, and other c'omponents of the system. The sides of the cylinder and the l I face that has not been machined provides sufficient thickness of steel to maintain the necessary biological shielding so that t once t: e fuel block is assembled into the generatur all external radiation is reduced to a IcVel consistent with ICC Regulations. C. U2.1T JOD!CE Tne containment of the strentium titanate fuel in tne 1:'N 3030 6enerator is provided by a cylindrical fuel capsule sim,ilar to the capsules of the LCG-25A. Double encapsultation is efforded the f.iel by a Maste11oy-C liner sealed within a i:astelloy-C outer capsule, the outer container providing structural support and the inner liner facilitatin; fuel loading and capsule decontamination. Approximately 25,000 curies of strontium titanate fuel will be loaded into the capsule to meet i the beginning-of-life pov.er requirement for use of t he 1"I 3000. FUEL CAPSULE DI.WMIGNS I Inside Diameter, in. 3.0 Outside Diameter, in 3.5 t'lall Thickness, in. O.250 l Overall Length, in. 4.5 Cylinder Length, in. 3.44 Liner ' fall Thickness, in. 0.060 Line'r Internal Volua.e, in /"15.6 f D x 0071 as,m e. m.e.a..m *eas..e re +ww w. e-- w

li Page 7 i Haste 11oy-C was selected as the fuel capsule material l r_. _ pricarily because of its high teuperature strength and com-patibility with str.ontium titanate. In addition, it exhibits-excellent corrosion resistance to cheuical reactants, i:articularly l sea water. Separate studies perforced by International Nickel Coupany and the llartin Company showed uverage corrosion rates of.0001 inches a year or 100 micro inches _a year and 3-1000 ~ micro inches a year, respectively. Reaction rates of ilustelloy-C as reported in Sendia Corporation's Aerospace Nuclear i safety Laterials Pronerties gandbook are sun.marized below. This compatibility integrity, along with a high melting point and tensile strength at generator operating teuperatures, assures of the strontium-90 fuel under'very stringent mechan-l c onte.i nr.ent l ical and thermal environments. a' TYPICAL ri:NETRaTION rat.;5 IN C0:r:031VE ! EDIA Temperature 150 F i kedia mils / year mils / year Acetic Acid O.2 0.2 l Chlorine Gus (wet) 0.1 ~ dhromic deid' 0.1 5 ~ Cupric Acid Nil Nil i Ferric Chluride Nil hil 1 Formic Acid 0.3 0.4 2 25

lydrochloric Acid 6

Hydroflouric Acid Nitric Acid 1 23 0.1 0.3 Phosphoric Acid i O.1 Seawater 0072 asser e e- .re>= w..

E Page 8 D. ndDIGIsnTOFC FUZL The choice of strontium-00 as the fuel for the ).K 3000 is 1 ~~-" attributed to its long half-life, availability, and the ability to be processed into the highly insoluble compound, SrTiO. 3 This fuel foru. will be step pressed in powder form into the liner and fuel capsule at the lartin processing facility at Quehanna, Tennsylvania, i Strontium titanate is a chemically stable compound effectively 9 insoluble in natural reagents. For a highly insolubic fuel forn. such as pelletized SrTiO, Zigman and associates have made a 3 careful study of the solubility rate in sea w'ater. They found that the solubility rate can be expressed according to the expression ^ ) R e 105 (t+6)~1 ugm/cm*-day where t is in days. For SrTiO in the powdered forr.., the 3 solubi;ity in sea water c.uy occur at a slightly higher rate.

Yhen the radioactive Sr-90 disintegrates, the daughters Yttrium-JO and Zirconium-90 are formed.

Since the valence of the cation increases, there is an oxygen deficiency and cense-quently yttrium and zirconium m.ay exist in the fuel in uncombined states. Tne effect of such composition variation on solubility l . rates cannot yet be established. Dos.ever, the overall solut.ili ty rate of strontiuu titanate, whether powder or pellet, is lou and this coupled along with the containment integrity of the j i generator system as a whole, precludes a breach of containn.ent of the fuel. E. (CaLITY CONTHCL u _. To insure containment integrity of the 1"r 3000 generator , unit, adherence will be made to rigid quality control procedures 0073 g o e

Page 9 ) l during and after asser.bly of the various components. Generally, <,uality control syster.. requirecel.ts as defined in !..ilitary Specification EIL-Q-9858a are followed as procedure guidelines. 1*artin quality control procedures applicabic to such i systens as tae 14 3000 LCG are as follows: 1. Periodically inspect ~and calibrute all gages and precision acusuring instrur..ents used in manufacturing. 2. liaterials are ordered as specified in the drawings. Alternate uaterials ure specified, when feasible, to reduce costs and iii. prove delivery schedales and all substitutions taast be approved by Engineering. All incouing unterials, parts, or units are checked for l dimensions, pt.ysical cin.forn.ity, norkmanship, and O[ shipping danage. 3. Visual and dirensional inspection as well as ches..ical and physical tests are performed winere 2:ecessary. Dye penetrant tests per process 1.IL-I-6566 and LIL-I-6868 l and radiograras are perforr..ec as restuired. Special consideration is given to welded asser.blies r'equiring absolute containuents and seul nelds are helium leak tested 'according to specifications. t 4. Quality Inspection Log Control is unintained to docuuent implant inspection steps during n.anufacturing, assembly, and tests. The specific quality control and assurcnce procedures defined for the fuel capsule and shield block are conducted according to specifications of the applicable drawings. j \\ 0074 i f I -.... ~

(C i l 1 .,..n IIAZARDS CONSIDERATIONS I 4 4 + b O 0071) 4 6 j

/. i [ i ~ III. HAZALDS CONSIDERATIONS f For the transport of the MW 3000 generator, and for its. storage and > l operation, it is necessary to assure compliance with existing regulatory j i requirements. This necessitates evaluation of the thermal, structural, and i containment integrity of the generator system when exposed to environments { J f typical of normal shipping and handling and of transport accidents. A. LICENSING REGULATIONS f 4 l t j Transport of the MW 3000 generator requires that an ICC shipping permit ~ 1 and an AEC license be obtained. Only the latter will be discussed here l t i although, in many cases, ICC restrictions are compatible. j An application for an AEC license must adhere to the following parts of i I Title 10 of the Code of Federal Regulations: t -~ l t Part 20 - Standards for Protection Against Radiation i Part 30 - Rules of General Applicability to Licensing of Byproduct Material 1 ? Part 71 - Transport of Licensed Material (Proposed) f Par't 100 - Reactor Site Criteria q .Of these regulations, subpart C of Part 71 sets forth the packaging standards i to be rnet. Those standards applicable to the MW 3000 and comments as to how j ~ these criteria are satisfied are given below: 73.31 General Standards for all pachaging f (a) No internal reactions - Discussed in II-A (b) Temperature resistant (-400F to + 1600F) - All critical compon-l ents of the generator are constructed of materials offering sound i i structural integrity well beyond these limits. l ~ 1 007G 111 Page 10 r

/. i (c) Positive fastening device - The generator outer cover plate j i ' ~ is fastened with 16 epoxy - sealed 3/4 inch monel bolts. I (d) Marked with model number and serial number - nameplate bolted f on top coverplate. (e) Primary coolant within shielding during transport - No liquid or gaseous coolant is used: heat rejection occurs by radiati'on' from the outer cover plate which serves as part of the shielding. i (f) Lifting devices (1) Support three times loaded weight of package-l (2) Support three times weight of lid. I 4 i j (3) Non-lifting attachments covered or locked. j 4 (4) Failure of lifting device would not cause package failure. Based upon a generator weight of 2600 lbs. and a support i 1 't requirement of 3 times the above weight, each lifting eyebolt is required to carry 2100 lbs. The allowable working load P A i and ultimate load capabilities of the four eyebolts are 2250 lbs. i i and 5750 lbs. respectively. (g) Tiedown devices { t (1) Withstand 2G vertical,10G longitudinal, SG horizontal forces. (2) Non-tiedown devices covered or locked. l (3) Failure of device would not cause package failure. I The tiedown devices consist of four steel lugs attached to the Eenerator base by 5/8" bolts. As a result of 2 g's vertical, i 10 g's longitudinal and 5 g's horizontal acting at the generator { t center-of gravity, factors of safety of 1. 24 and 1. 20 (based upon yield) were established for lug bending and bolt tension j 0077 re spe ctively. 111 Pa g e 11 l t

/t { i 7 1.32 Structural Standards for I.arge Quantity Packaging ~ (a) Load resistance: Support five times package weight as a simpic beam - Maximum stress approximates 2,8.5 pounds per square j 'in ch. (b) Internal pressure - 20 pounds per square inch gauge pressure. Internal argon pressure is 1 psig under normal operating j I conditions. t I (c) External pressure - the Fuel ca,psule will survive 2000 ft. sea i l i depth hydrostatic pressures. [ t (d) Pressure relief device - Not applicable to MW 3000. j 71.33 Temperature Standards for Large Quantity Packages l (a F1 b) Contents intact with luss of coolant in sunlight and 1000F j l p.. y Y tempe rature. -Loss of heat rejection is discussed in III-B. 71.34 Radiation Shielding Standards for all Packages ) i (a) For a package not being transported by exclusive use, the dose l rate shall not exceed: l l (1) 200 mr/hr at any point on the surface of the pt.ckage; or j i f ~(2) 10 mr/h'r a't a meter frEm the cenier. This is discussed l in 'the Radiation Analysis in III-C. j l-71.36 Standards for Normal Conditions of Transport for a Single Package j j (a) A package for a large quantity of fuel shall be so designed and l constructed and its contents so limited that under the normal-j i conditions of transport: -~, (1) No release of radioactive material from the containment ~~ 4 I vessel will occur. 007S 1 ~ Ill Page 12 l 1 . ~.

19 i (2) The effectiveness of the package will not be substantially 'p reduced. (3) No mixture of gases or vapors which could, through an increase of pressure or an explosion, reduce the effective-ness of the package. (4) Radioactive contamination of coolant will not exceed limits. (5) Internal pressure will not exceed 50% of design Eauge j pressure. Normal conditions of transport are defined as t 9 i follows: Heat - Direct sunlight at an ambient temperature of 1000F I j in still air, i l Cold - An ambient temperature of -400F in still air and shade. Z I J Pressure - 0. 5 times standard atmosphere pressure. I i Vibraticin - Vibration normally incident to transport. i Water Spray - All surfaces except bottom wet for 30 minutes. Free Droo - Within 21/2 hours after water spray, drop 4 l feet (or le s s). j Cover Drop '- Drop wood and fiberboard containers 1 foot 'onto corners. s Penetration - Drop 13 pound,1 1/4 inch steel cylinder 4 feet j i onto package, j Compression - Five times weight, or 2 psi Ioaded for 24 hours. i Items 1, 2, and 3 are all satisfied and are discussed either in II-A 8 or III-B. Items 4 and 5 do not apply to the MW 3000. v i i III Page 13 0073 l 4 I

e-71.37 Standards for Hypothetical Accident Conditions for a Single Package l I N (a) A package for a large quantity after the hypothetical accident f conditions will meet the following: (1) External dose rate increased less than by a factor of 100. I (2) Eadioactivity released will not exceed: (i) 0.17e of total contents (ii) Specified limits of the other isotopes. [ The hypothetical accident conditions are as given in III-B. Both of i these items are satisfied by design of the generator system. From the l results of III-B it can be concluded that there will be no release of activity and from III-C the maximum radiation dos e at one meter will be only 25 mrem /hr with the outer cover plate and modules removec. j /!. B. ACCIDENT ENVIRONMENTS i The MW 3000 has been designed to maintain its containment integrity and i provide sufficient shielding to satisfy the requirements of the AEC hypothetical f accident conditions, part 71. 37 of 10 CFR. Thus the generator will satisfactorily withstand the following sequence of conditions: J t 1. Flat Drop - A free drop through a distance-of 30 feet onto a flat essentially unyielding horizontal surface, striking the surface in l i such a position as to suffer maximum damage. l 2. Puncture - A free drop through a distance of 40 inches striking, in i such a position as to suffer maximum damage, the top end of a vertical j ~ cylindrical mild steel bar mounted on an essentially unyielding surface. The bar shall be 6 inches in diameter, with the top horizontal and its

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edge mounted to a radius of not more than one-quarter inch, and of I ~ 00SO n1 Page 14 l

g, i l f such a length as to cause maximurn damage to the package, but not less than 8 inches long. The long axis of the bar shall be normal to l the package surface. 3. Thermal - Exposure for 30 minutes within a source of radiant heat j i having a temperature of 14750F and an emissivity coefficient of 0.9 j \\ 4 or equivalent. For calculational purposes, it shall be assumed that i l the package has an absorption coefficient of 0.3. The package shall j not be cooled artificially until after the 30 minute test period his i l expired and the temperature at the center of the package has begun to fall. 1 4. Water immersion - Immersion in water for 24 hours to a depth of at least 3 feet. Subsequent to these conditions, the system must retain sufficient shielding i properties such that the radiation level at one meter from the center of the i generator will not exceed 1000 mr /hr. The MW 3000 system has been analytically evaluated for exposure to the f 4 6 above sequence of environments and has been found to exhibit, without question, l an integrity against cbnditions well beyond these potential ~ threats. The analytical ~ results of this evaluation are discussed in the following paragraphs. ~ i ] Structural: l i 1. Generator - Puncture Drop l t The most critical component of the MW 3000 if subjected to the 40 inch l puncture drop onto a 6 inch steel cylinder would be the steel outer cover plates, u or lid. An analysis was performed to determine the energy required to completely l 1 i a P Ill Page 15 00S1

2 l i i t penetrate this lid and it was found that, while it is designed with a total energy i } w capacity of over 400,000 ft-lb, only an energy of less than 9000 ft-Ib is available ~" from a drop of 40 inches. Thus, the cover plate will most certainly withstand this condition. f 2. Generator - Free Fall The structural integrity of-the generator was investigated for the free fall from 30 feet onto a non-yielding surface. The first analysis examined the propo-gation of stress waves in the steel casing. For thh, the critical impact { velocity at which the elastic regime of the casing material would be exceeded was calculated. This was found to occur near 440 ft/sec, but the actual impact j velocity of a 30 foot drop is only 44 ft/see, an order of magnitude lower. j A second method of evaluation of the 30 ft. drop found that, if the generator l O fell on its cover at the critical impact angle, the outer cover plate could be forced j r off due to shearing of the 16 monel bolts. However, in such an event, the inner i aluminum lid acts as a backup device and, although it might suffer some com-l i t t pressive deformation and its bolts appreciable bending, it would not completely t 6 shear off. Therefore, the interior of the generator - module, shield block, and 'f 1 heat source would all remain intact. c l ( 1 3. Fuel Capsule - External Pressure 1 The Haste 11oy-C fuel capsule, heat source for the MW 3000 Eenerator system, j l [ was examined to determine its structural integrity in 2000 feet of seawater. The analysis evaluated the capsule design for stresses in the end covers and cylindrical j wall for both stress and buckling. In all cases examined, a large margin of safety l r 4 was found and it has therefore been concluded that the present fuel capsule design f [ r i will survive the hydrostatic pressure of greater than a 2000 ft. head of water. j (~ dog *o III Page 16 ~ me

  • m e

De = 4 I

25 l b The rmal: i Analyses were performed to determine the integrity of the MW 3000 in the. i t j hypothetical 14750F accident fire for 30 minutes. Conservative results indicate j i that the rnean surface temperature of the generator will not exceed 6000F due to i the large heat capacity of the system and, if the module and cover plates remain i structurally intact, the fuel capsule will experience only a minor temperature rise. If the module is damaged structurally to a point at which the heat rejection path is destroyed, however, the hottest point.on the fuel capsule will still be well l below the melting point of the Hastelloy-C material. If the outer cover plate were to be knocked off in the 30 ft. free fall, it would require much more heat than is available in a 30 minute fire to melt the inner aluminum lid and destroy the normal heat conduction path. Thus, the fuel ( l t P, capsule will remain intact. va Immersion. t a I j The excellent corrosion resistance of the MW 3000 system has been previously l l discussed. As shown in the structural analyses, the fuel capsule has been designed ] to withstand hydrostatic pressurss of ocean burial at depths of 2000 feet and ] greater at operating temperatures. Although the structural properties would be lower if the fuel capsule temperature were to reach, say 20000F, it can readily be shown that the capsule will still possess sufficient strength to withstand external f pressures much greater than that correspondi,ng to a three foot water immersion over a 24 hour period. j i The integrity of the generator when subjected to the normal and accidental i t I transport conditions has been established on a very conservative basis. It may .a.... i therefore be concluded that no chain of events within the limits set by the hypo. 00$3 III Page 17 J 1

{ thetical accident conditions will present any threat to the containment integrity of the system. Furthermore, since there will be no loss of shielding, save for f t the possible loss of the outer cover plate, any increase in dose rate will be weli j ~ i below the prescribed accident done of 100 times the originally permitted level, [ L or 1 rem /hr. I C. RADIATION A radiation analysis was performed to determine the thicknesses of materials j t required to keep the MW 3000 generator within prescribed ICC and AEC shipping limits. The thickness of steel outer casing necessary to attenuate radiation [ down to 200 mr/hr at the generator surface and 10 mr/hr at one meter from the center of the source was found to be around eight inches on the side and slightly more than this below the fuel capsule, f In addition to meeting the above radiation levels, the thickness of the tungsten [ i shield block was sized to lower the dose rate on the top surface of the block to a point low enough to allow a man to change modules in the field. The maximum l t i dose rate in this case, with the module and cover plates removed, was found to j l , be under 700 mr/hr at the shield block surface. l t TA MP.ERING D. i" Since the MW 3000 is designed for commercial applications, it may not always ) -be possible to impose restricted entry within its operational confines and, even f i if this were possible, controlled access is ineffective to the meddler, vandal, or j i s aboteur. Possible destruction by sabotage must be acknowledged. However. [ t for the layman spurred on by curiosity or mischief, danger from radiatinn ~ exposure to himself or others is practically nil. A i t i III Page 18 0084 i i

. _ =.. 2j. ~ i If he were couipped with all the proper tools to facilitate removal of the t' heavy cover plates and module, and were able to work without overexposure l to the radiant heat from the hot generator surface, attempts to get further than i this and on to the fuel block itself would be futile. Only by burning through the ~ ~ r hold down rings or the shield block could the heat source be reached. To l i t i carry the deed to such an extent, however, would require motives much l. 1 greater than mischief or curiosity. The radiation at the top surface of the tungsten shield block is only { f 600 mr/hr. Thus, for one to receive the maximum permissible normal i i quarterly dose of 18.75 rem for the hands would require direct contact with I the hot surface of the block for more than 30 hours. r F .a i 4 r t t i 4 a i L i ? i i 1 l f l. II

(

s, l I III Page 19 2 00SS i 3 h j

l /TDd No Y. l Q- ^ s... <m .u .. i.,,,. e n ,u i.o.,.u.n..i. ,4. ....~,,. r . t o, i. .or-- ,usi .r-ior i.,..,- i.ii . s ..i.r ..n ..,i,, n.... o, c . w....... sm.,...=.... .s.....,r.,.....w., u .s...,.< ., i.i> w - me. ..,.. a e.. no.. w f .f h 6 3 ~ I i ADDENDUM TO MARTIN MARIETTA CORPORATION JUNE 16,1966 APPLICATION FOR AMENDMENT OF BYPRODUCT LICENSE NO. 19 -1398-34 i 4

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~ EE From the general packasin5 requirenants for nucles.r O"; generators as. set forth by the AE0 the followins structural 5 requirements are evaluated for liftin5 and tie -dorn: 1. Liftin5 Devices - must support three tines the loaded package weight. t 2. Tie-down Devices - will not yield with 2 E s vertical, 10 5's longitudinal and 5 g:s horizontal. The fo11owin5 calculations are enclosed to provide en analysis of structural integrity per the lon6.s specificd above. In addition, a large quantity package requirement states that the generator must support five tinc ite This Intter. case weight when treated as a sinple bec=. seens most critical when assuning the generator supportcd w horizontally and supported at each end. Due to the raccive cross-section of 4130 steel, the enrirun stress ras found to be 28 5 psi, a ne51151ble quantity. (A :. v

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    • W'*")1. (.r. 7u)(. as) - (-4.cc1)(-tr.frJ),

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. -^,.e,. m.,.. s4.. n i,,.. $..,.,...,.-....

i...., u., g o,,...< m..m.n...

.u... .,..o......,.....,........... ............ m,..,. ..i n... . i.w. ...n -m.- i.. a.,i..,< .,.m .. e,,,,- ww....., w i,4 $.......orope .~ i. ..u. ..w.....u.,..........,.. .,un,,,,,,,,,,,...... -,...u., ...u..,......,i..... _7"- '.% Is.w van.a i r g, ADDD WJM B A J ry ~ - Ite nr~,_q. ..~u E {- FIRE AW. LYSIS C? }M-3DO3 GDC/.TO3 i 5 An inresti ;ntion has been nade to detertine the effect of experirg a 10-3003 generater to n 1475'F fire for half an bour. UnSer the vorst 1 condition the fuel espmule temperature vill not ereced 2100*F st any cpot on the capsule. Sin:c the celting temperature of the Eantelloy-C fuel 4 caps.ule is 2300*I', there is no danger of an accident fire retrulting in 1 1 a releue of fuel. Tnere vere two apptccches ende durind the invectisation. First: 1 l it vas necuted that beat van tran::mitted frcs the fire to tbc Cencratcr surface and the Effects -vere itrediately (influite thercal conductivity) ~ felt throasbout the vbole generater. The beat input to the centrator oc-curred thron(,h tbc sidce an5 top cf the generator by radiction cs fc11cas: S h 4 m T3) q cre A (T y a vhere: Effective eminsivity of generntor and fire, 0.82 I ' E e Constnnt, 0.171h x 10' Bto/hr-ft

  • F i

f 2 Surface crea of generator, 1h.0 ft A = Tecperntu-e of fire,1935* R' T = y Te:perature of generatcr surface, $70* R at t tart of fire T e. J 1 -g Ecat input to cecerator, Btu /br q .= 4 The thercal ecpacity of the centrator var determined by the follow 1us reintion-- ebip, and the results tabulated below. = C V4T q p. g 1 0118 ---==-----2

v t Iv' Ill Wheef f**ery regiate s.F *=sethwl Upr..I ?.t stro mesy r.ws e g.ves sad ti.d se-a ,'semlehed unitet (Inits d ikatee ta'e'en'est

      • er'by et I.or te rmorecessit. eloret sla-tork e in ti.e y, te. ef av.-

d.,Jo. .+ see sener.clbe. L -,. < U- +4.sti mot Ase F ahn 6.t 8..t e

  • either resemoed smote sJe the gesweenenent, w lscon e.r girnawas6 tonterried as not oths re a f a.

eseed. suplacated, or dist 6.=td se elote or en ts.o.a.atdy asank.6,le to es Lle sana n3 pet. %r tin..s u b s-port lov sia%factere DF treesteens ed, oath-forssaaree of the o erk er t at release se, 5 e, re g. . : a. een ersitem persnaassan et teenapes, lac,. 4orenga ge=ernmernt. as the ariterests of t . +, ^- - y.,,', e ~ vbere: x 4% Grecific hent. Etu/lb '? C = t P .....y, 4. Ucicht. Ib W = Temperature cbouge. *F T

== j ~ Ecat chno;;e. Btu q 4 i Pateric1 C W CU P P Geners.tcr b130 sn, o.n 2s03.0 272 58 cree Ecat sint Aluninus 0.23 19 4.37 shadcishield Ter:pten o.03b 37 5 le27 1 Fac1 Capsule Tactoney 0.09 39 35 t Wo celution of thten equttiona is ebc. n in Ficure 1. The ccan surfnec te=psrcture of the generater trill not cnceed 603*F; to the cle=inun heat cint vill not celt. The curren of the fuel carcule 'te:.Tereture-vill al T.ys I l be lereer then those shown in Fiscre 1 since the therr1 cerductivity of thebiccuthtelluricecodulesisabout1Etu/br-ft*P(instendofinfinity), anG the stcol ce.se vill he.re a tt.:penture &calent with the cool cide t in custcet with the in::ulation cod the c 5ules. his does, hovever, repre-esnt a n~! :u: te=rerature envelepe,vbich indictics that the biccutb tellu-ride with a =oiting tezperature of apprezientely 1100*F vin not celt. _t Thereferc, c boat conduction path for the generator thercal invento: y vill j re r.ain inte.ct cnd tbc generetc: vin pnanally cool dove. The corimu: I .-tempraturo cf the fuel block vi n not eneced 1350*F. [ . Le cecend cyproach to the analy:in csou:,eG that the Een0rc. tor fell in en inverteki positica co tbc.t the thercoeicetric eleoanta vere crushed, reculting in aufficient interfaces to ccctroy the best co:.unctios Icth t i ecrccc the cc5ule. A cubrecucnt fire vould tben heat the generctor eurfeco I e 0119 2 I

r.,....,2,r..n..,,,,......,~......., om. s,.....,~.., ~.....r.o., i.o.J.~, t,, ~,3. 9.. $, 7.,1.. ; - ~ ~ ' WC.. e,,,,,, m.,, e. ..m., ....n - i u. ., e....... k.. ..... e-....n...... w. . n..~.,,... a.m. i.3.. A 4 ey,.... o., % n, .m. 2 1.. ........,.. m e. p,,s'eg... 4 n..,,. A. x un,,,-r.n.,,,...m...,,..... tpa.,.. ; se...g. g e nn.ot. as tw e t.: nirsi p. r mt...a or i..so; e s. sm. i.L., "o.. Ev ~

- ::, - s

. ~ r g' q. gt- ~ ..- 'N,c rcg - r to 600'f. 'fbe futi capsule, under tbc influccee of the generatcr

u investo y, vould grc$tn11y beat-up until the cic ent: bad r.elt:4. Eceever, in the liquid fc: u e bent conductica Ictb would cgain be estabMcbe5 sicee, if the liquid fler. red frce the ecdule, the bent vould be discipated throush the bolco in the inculntion left by the eclted clencetc. 'Ite fuel block in;ernturc required to radinte the 110 vetto c,f bect (lhO vait theresi inventary ler.c 30 vatte throu;h the inculntion) vae detercined fc-no c ic-P sivity of 0 5 and ou nrta of 0.03o2 ft~ ac3, fcr there valuer the top surfc.ce of tbt: fuel blech vns found to be 17h5*F. Sitea the tecperntt:re ca the botto: of the capsule vill be bisher than that c the top. the botto of -the fuel espsule vill rench 2110*F nt a corresponCinS Generatcr surface tctperntta e of 600'F.

If the Eencrater lid vere tscured to be knocked off duries en acci-s x dedtal generator arc,p, it in necersnry to detert.ine if the expxed aluminus inrr lid vill r.elt du-i 3 the fi e. It has c3 ready becn found that the averce terperr.ture c' the GCCcrEtCT cace vill not be eufficient to telt tbc altniens (Figre 1), but let it be escute5 th t the curfn=e terprature cf the citric = 6c's r:ceb 119ff'. Tre use of equetica (1) vith c etr face a:En cf the clurinc cf 1.23 f t cives a total bent input to the lid of 3 7 0 : 10 Etu in a 30 tinute fire. Thic but vill be diosipated by best. 'connuetico, te p rature increue of the clusinua cud.eltins of the r.lcrior Tcc latter tuo ite:z cre defited by the folic:<itig relatienchir: Q..= C W A '1' + b U (3) p f e 0120 3

~... - -. ....n...,u.,.,,......,.,~,..e.c i T iu.. .,e, ua....W,.i o, o,nt.. : >,..L..,.:,_m 4c ..,..,o.,a.,s....... ...,......,.......,4...,....... ..,.,,i.m- ...i-. ..a.uu. ..<..,,,4.., ........u..<o.. se.. - ..,, i......., u.. i.., i..... us....w. i,.~i. i, e.n -., i..m s, o,...u. .... e. t

.o......

.,...,...a. ..e...., ....,.......4...- . e i.... i.. .. w....me i........e. ri. Since the cajority of the icuer lid top curfcce vill be closer to tbc ctec1 i ca::e than indicated by this reintionship, the cetual therr.sl conductit*; ccpacity of the lid is greater then that ebe.n. This given a total bett 3 diccipation ability fcr the lid of 119 x 10 Etu if the lid celts en5 3 91 x 10 Etu if the lid doesn't celt. sicee the beat input is only 7 0 x,18 But the' lid vin not be totany destroyea no that the norra1 bet.t concuction pnth fer the icotopic heat vill re:.sia intact efter tbc I fire. E I n w _lSOTOPE.S ? 1 _. ~, Y ' I 6 PrM ~ - ve:, ' "~ s.:,. w,.,,".. ~ '8'" W"= h

    • A

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    • 8'%

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  • *.ere e%c e,t,#

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  • w.

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,. ~. n % De g s._,. .,. *s n Ae'. ' ' ' ' "'1 4,' l RADIATION AIRLYU1S v, ' g,,.,, ,~ n' r,,b B;- ou e y' A radictica c.calycic van cade of the IG-3000 cenerator in which

  • R j

the inner chield is to be cc::: posed of a tungsten alley cf density equim-i ~ i lentto17c=/ccandtheoutershieldin4130 steel. i The heat source is 150 thermal vatts of 'strentium titncate which iE loaded into E BiUO e cap 3ule. DC CO.paule ic cSde of Eastelloy-C cud ) l I i.c apprcrimtely 1[4" thick. l The thietneca of 4130 steci required to cret the.ICC chipping regula-tions of 200 r3/hr at the Eencrate" murfcce and 10 r3/hr ct one ceter frce the conter of the cource vere fonod to be 6" on the cide and 8.1" belou t the fuel ecysule (figures 1 ana 2). Tbc thickness of the inner tungsten elloy chield var cir.e5 so cs to (1) cect the preriously stated r: diction 7 levels above the fuc1 capsule sud (2) to lower the deze rate on the top surfaeo of the inner chicla to a leml which' vould n11cu the thercoalectrie v cedule to be chacssa in the field., 1 Dose rates were deterniced at various points arouna both en cocecbled l I generat71 c.nd c generat= vith the tcp pinte off and thercealectric cc5ulo rencersa. The ocae point locations cre choen on figures 3 oca 4 while the dose print cearainater and 6cac rate et cach point is given in te. bloc 1 i l eL6 2. e ? b h I e E ~:. e om 1 6

e.orms.ted ess.ser t?mited States to.ernment - encerat f.r. Ien ess.cet.er. y eerair er ert 1 Us.terC KL.tes m y erer tre, s e. W F ' * ' 2 7 en.H*et08 een by er for et.r p.erimient, e here.t. esthet a..e ein r tc. or, e-e, g..+ 43,,n e ateace be.1 " ' stern er 3. rut *.e coaterm.'J 3. Dret plher 4ee $s.(If ere le Stef ph all 14 geb7419. ty f.,se. esther rolesses a.ste etc ths g srs nient or o.ed desdecated. 4e es.cle,ed en.selv er te esasor.thly availeNe se erubic senicis pa r-geeig 4 aateu.. This le gen.

l..la e, part for snan t.cluse or proterernent.
  • 6th-f.rsesance of tre. ori-or tasi re.le.se s. a sna r me

- reg 4 ed.cteuri nice,1 e...t a,- out e ritten g+ramassism of isotapas, Inc., sareign goveranernt, as tam-Antere.t. of tre a 44:. {*~~s Yone~s 9,,l u.., ^ s, ,. ~,,, ry.ny: 1 3 i....,.. D IE nic s roa /.ssn a n'a cE:Ent.wa . - J..N,. o u, Dozs Pone D03E Rts gym I (.uaus) Z '(n cHEs) DaLum!/Ecm) 1 0.0 9 27 23 8 2 1.6 9 27 19 8 3 2.0 9 27 18.o 4 25 9 27 15.4 5 30 9 27 17 2 .6 4.0 9 27 30.6 7' 50 9 27 55 3 8 6.0 9 27 65 7 r. 9 70 9.?T 68.6 s.. 10 0.0 9 27 h6.b n n.75 0.0 n3 12 0.0 -n.34 les 13 -o.0 39 37 1.2B l i 14 n.25 3'7 72 1.oB 15 20.17 33 81 .5.BB i L' 16 22 71 32.16 5 60 ~ 17 25 24 30.21 3.87 I 18 39 37 O.o 10.0 19 o.o -39 37 10.0 l i ams'- 012G l 'I

r.,,,,i.e.. 3...*..:.,.. n -. =, -..,r.,wa .y-mer.c.u....-..-.i.n..... .,u '...... i.. u r, _ _.....,.. a .a u.. ..,,,.c.....,an...+........ui...so.. u.. *., s.a m...,. ..., s., ..~.i.. n,., c i. ,ao.. i., n o, u.. i, ,,,, :./3 .i .m .,-ii......a. s t.. .. i. -....g,.......u .u -,... e ' 0 OP ~g f +

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  • /

I DCG5 EffB D EC 701D2 ymm I (Tramp),

7. (Ec?rsl O'IngE'.!/ijer:).

1 o.o 4.09 660 8 2 c.o 7 97 2ho 3 1.0 7 97 222 4 1.6 7 97 196 5 2.0 7 97 175 6 25 7 97 142 i 7' 30 7 97 110 '6 h.0 7 97 254 = i 9 s.o 7 97 31). v 10 6.0 7 97 391. 11 70 7 97 209 12 6.0 7 97 160 13 O.o 37 3'I 9.hD i 14 11.26 37 72 6 51 15 20.17 33.D1 23 1 ~. ' 16 22.*ll '32.16 23 0 17 E5 24 30.21 10.2 ~ l p e, 1 01:37 1 /.t/.i];ll /L'.(:!ETTA CG.?i3/.11; I Precrk!:.tv ' bfarr M..n j j -._.,.,.;.._...,~.---, w

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.i i. .m,~,,.., ....,........no .. y E FIGUBE 3 Dose Po/NT LocA7/oA'.5 fcg AS557;gjgp ggs ggpyog e e y, l i h F .zL 13 j I g. I 1 IS~ lb g 17 i ,i h e I 22 1 7 ? W to 4/30 STEEL i l AtosuwvM t v fYffh$ $ g .T' 30 All OY 2.u" ~ ~ MC ll X f i 4/30 STEEL tJ IS l --HI S TELLDY-C Y B" MD = t.4p/-x 4 t l si ~ 81 c e i .g t t l' ISOTOPES ._.,........nu_ ,,,_.m... _... ~ _--e .,,O' ~~ rvv - - O .. - -wwwVie:LW. v. e,, g, g. n=r pr I l ".;,m n.., ,a,--%...e r y ,.,et ...sj _ n.r-J v. w. v. .6.a h..s r un 4 Da Die. I a -...,. wi d. o G L/#asif.A F 6.. 4 r wse

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i ,.,...,,,.m.,,...ni.. on. im. r... i. r...... ....s.. r s FIGURE '? P055 Polt/71.0 CAT /0lJS WITH 1DP PL A TE ( T.E. MCDULE/?E/iF/E. f f - p ~ :. 7I rs i w -e14 Is" f i. N's. /4 N,N 17 { \\ ~. i i \\. s i \\ \\ \\ i 1,, w s-' p R 19 11 I? k o ee v4 \\ t o \\ f

  • I i

YCd 3.ts' 711+15{p Y l At 4 2.:s* + ~ y. X i SA 6 .q13 0 S 7 C C l- ) ~~ ~~ \\ -H/ STEL.l Cf-C \\ SI L.ycip 5 i i = Mid-!f l i i l e B.I ' i i I e i e I 4 g ISOTOPES 8 l T n v r'is L a n n i I. n o hi.;a s.0.", i i TKC **_..;..o.: ~ ~ ' ' ' * *N F C30 E 4 o.. t v *'OT BE %:o ; a Ta r " tm ; g prwc; ry:EPT i i b'u'"'~.~.~.~--~~'"1.'.' j ~ 0131 4 1

h /WAY 5.) f l l July 22,1966 Retyped for clarity October 17, 1990 Refer to: 6321 Internal Mail No. 865 U.S. Atomic Energy Cornission Division of Material Licensing l Washington, D.C. Attention: A.C. Aikens, Jr. j Chief, Irradiated Fuels Branch

Subject:

Additional Information - Martin 54-3000 Thermoelectric Generator - Byproduct License 19-1398-34

Reference:

(a) AEC Letter dated July 16, 1966 from A.C. Aikens to C.W. Keller (DML:IFB:JCG) Gentlemen: This application supplies the additional infernation requested in the referenced letter with regard to a proposed ameninent to byproduct License 19-1398-34 to authorize and transport, display and demonstration of the 5i-3000 therroelectric generator. Four-feet Drop-We consider the effective package for the 59-3000 a. to be the generator housire closed by the inner lid. The outer top lid of the 54-3000 is nerely a protective cover for the unit and an additional radiation barrier. It facilitates the ease of utilization of the 54-3000 in a ntraber of varied applications. All shipments vill be made with the outer lid properly in place to assure compliance with ICC radiation requirements. The outer lid serves in the same capacity as the protective container for the LCG-25 and should be considered in this light. In our previously s'lxnitted analysis of the M4-3000 no structural credit is taken for the outer lid and our review indicates that these analyses are still valid. b. Maximtrn Temperature-The naxinun temperature which we have established for the wolfram shi^1d during nornal operation is 900 F. We do not anticipate that the temperature vill ever reach this value without application of heat from an external source. We have previously proven the safety of the device during the standard fire conditions. The satisfactory norral performance of the heat source and insulation system is established during initial generator checkout at our Middle River Facility prior to any shipment. Should any abnornal condition exist, it vill become apparent during the test period and an analysis of the problem vill be made under controlled conditions at that tine. Since the fuel, insulation and module was subjected to extensive testing and inspection, m

o i Page 2 ve cannot envision any problem existing after our final check out of all systems at our Martin facilities. Specific procedures to be followed in i the very unlikely event of any malfunction of the N-3000 vill, in large measure, depend on the nature of the problem. i Detailed Drawings-We have included a top drawing for the W-3000 c. generator (Partin Drawing 471A1000000) and the detailed drawing for the lifting devices (Partin Drawing 471A1300003) to assist you in completing your review of our previous application. These drawings are Partin proprietary information and must not be released to the public document room for reasons which we have previously established. The lifting devices have been changed and are now incorporated in the i side of the N-3000 instead of on the top outer lid as previously defined to you. We are also including a drawing which details the tie-down devices to be used in the shipments of the M-3000. Our previous analysis indicated 6/8 inch lugs. Please note that the finalized design will incorporate i even stronger one-inch lugs. The thermocouple readout mechanism is presently under development, but in no way will affect the integrity of the defined package and merely serves, as does the top lid, to f acilitate application of the over-all i ~~ generator. d. Proprietary Information-We have included with this application a l revised analysis for the lifting devices as well as the original pages which discussed the tie-down aspects for the N-3000. You may consider these pages as replacements for those specific pages to our prior submission which were at that time defined as Martin proprietary information. It is presently planned that we vill be making a shipment of a fueled i M-3000 generator duing the first week of August 1966 and will appreciate your granting of an amendment to byproduct 19-1398-34 for the transportation, display, and demonstration of the N-3000 no later than f August 1, 1%6. 'Ihank you for your usual expeditious review of this application. Very truly yours, f PARTIN-PARIETTA CORPOMTION PARTIN COMPANY, Baltirnere Div. C.W. Keller Nuclear Accountability and ( Licensing Representative w w - h

/7EM /Vo. 4-7. A ril 25, 1966 P Dah NIFCLEAR TEST DIRECTIVE Page1of 3 o Accour_t Nc.

c. O.D. No.

d.Tect Diractive No.

c. Eng. Approvd 4991-802-A 11500 4991 hTD-50 ggg.3 TestItemPart Numbcr g.TestItzm Name h.TestItem Serini No/Nas or Quan 471A1300003 and

&m5000 Vessel and 471A1300001 Cover . Tert Type J. Test Description

k. Test Group L TestIo:.

}** U D External Ilydrostatic WO MO Pressure qualification Test l n.Dssirad Schedule

2. Objectivo Start l Ocmp.

The purpose of this test is to prove the capability of the in'.3000 Pressure

o. Bepor;Rg'a Containment to trithstand its design en-At Completion vironment.

v. J. Gereral Esgr.tremento The tert procedure prepsred in rerg:re to this dtrective will be reviewed r.nd approved by (a) Profect Engineer-ing (b) PsWhmty E::sicaer!rg (c) Qur.lity. Quality will verify that all test equipment is in calibration at the i=itiation of testi::g and that data la recorded 2. in secordance with the test procedure. ?. AI! fciluzes as dedntd in 11NQ-CB-001, Satfect: Corrective Action Systen and Section 2. Test Requirementa, co-currl=g during test will be repcrted on M ARR Form MN.IOM and a copy included in the test log, G. S. Stivers 9130 IttmedInte notiacation w!Il be given to the Project Engineicr g fall es snd to the Project Ba%hmty Ecpresentative F. LicGinty z 854 5 when n iations to this directive vill be authorized on a Test Directive Change Sheet and distributed in e.ecordance with ev the distribution !!st at tbs end of this dL@.

3. A copy of the Snal test report /rsports resulting frcm this directive will be furnished to Project cnd Rellsbility Engiretring.

A144

7 '. i Page 2 of 3 Test Directive tsumder NUCLEAR TEST DI:1ECTIVE NTD-50 q. Test Roquirements I. Para =eters to be measured. A. Hydrostatic Pressuro External to Test Vessel O to 1500 psig. II. Tests to be performed. A. General The test vessel will be icmersed in a pressure chamber whose unter has been stained with a dye. The chamber will then be pressurized to the specified prcesurec for the specified times. Upon completion of these pressuriza-tions the test vessel will be removed, opened and examined for leakage. ~ B. Test Description. 1. Place the assembled vessel (Martin Drawing Ji 471A1000006) in the test chamber. 2. Add approximately 1 lb. of water soluble dye (A679) to the test chanber. 3. Close the test chamber and fill it with water. Purge the chamber of all gases. 4. Increase chamber pressure to 500 psig at a rate not greater than 50 psig per minute and hold for 10 minutes at 500 psig. O b-serve chamber pressure for pressure loss during the hold period. Any pressure loss not attributable to temperature variations shall be cause for depressuri-zation and examination of Jie test vessel for leakage. 5. Follon the procedure in step 4 for raising the pressure to 1000 psig. 6. After the bold at 1500 psig, reduce the chamber pressure to O psig at a rato not exceeding 1000 psig per minute. -w/

M l 3 of 3 NUCLEAE TEST DIRECTATE Pege ~ Test Directive No. NTD-50 7tst Eequhuntnte (Continued). 7. Cycle the test vessel between 0 and 1500 psig twice more. The rate of pressure ' increase shall not exceed 500 psig per minute and tbc rate of pressure decreases shall not exceed 1000 psig per minute. 8. Increase the pressure to 1500 psig and secure the pumps. Ilold a pressure of 1500 psig for 24 hours ninimum. 9. After bolding the chamber pressure at 1500 psig for I 24 hours, reduce the pressure to O psig. 10. Remove the test vessel from the pressure chamber and thoroughly dry all surfaces and interface joints with compressed air. 11. Open the test vessel and make a thorough examination for water leakage into the test vessel through the electric feedthrough, the main flango seals and weeping through the walls. II. Miscellaneous Inforcation. A. Measure =ent Accuracy. ,4 uw 2' l. Pressure: + 20 psig l . Report Ecquirectsts A summary report will be uritten at the completion of the test. The report will include any unusual events occurring during the test and the results of the vessel inspection made at the completion of the test. Distribution

t. Originator Project Engineering G. S.

Stivers Ret Engineering F. McGinty Test Engineering G. S. Stivers Quality E. Oeinkam Paject Wr.nn.=snt T. R. Barker Phone 9130 mad No. 812 ~ Other A. Streb Dets April 24, 1906 S. Furman l K. Dufrano R. Nolan (2)

/)chyiva.l} ~. rit, i ? M f 196D IRII.L-del'S121 C01.Eli1CKIICI: ${f I .aagus t 25, 1906 To: C. Stiverc l E. E. Eaxford, J. W. McCrew, L.Peturn, T. Barker, R. McGtrriglo, i cc N. Ross, K. Dufranc, C. Emiley, H. Laios (N.E.L.) f Subj WW3000 veccal and Cover ...ae .........aa.............-.e...... Enclosed is the report on the extcrnal bydmststic proccure qualification test of an Er.>0C0 veccel cau cover ubich wec perfomed et the Naval Research 14beratorios. I i f .W. ~ gJ.S.Greewell;fr. { JMams Encl. i 1 L b [ I l t i ) I I t h i w= l

. lirl ~

  • ~.'

L W3000 VESSEL *D COVER BYDEOST.CIC PRESSURE QUALIFICATION TEST MM SPFL No. Submitted byr 2 / e [ JT S. Gdsenwell, Jr2 i Tect Engineer ?, i Approved by: t.: I i ~ E. E./nirford Group Leader, Small Powr Plant Lab. ]l$1k.- . W. Edrew Supervisor. T/E Development Section l i i ~ I i

8 1.0 Intred:e tipa 1.1 on July 25 and 26, an external, hydrostatic pressure qualificatfee test was performed on an W3000 vestal and cover at the Eydrostatic Prezeure Tacility of the Naval Eesearch Laboratories. he tect was conducted in accord. ance with NID-50. 1.2 he W3000 is part of the Wellbsad Centrol Systams Program. 20 5gac~.r tw No observable leako or weeping were found in tiit W3000 af ter it had been pressure-cycled twice betvsea apprer.imetely 0 psig and aplsrexiestely 1500 psig and maintained at approximstely 1500 psi.g for 16 hours. 3.0 Escuniqq 3.1 Test Set-Up 3.1.1 ne test set-up, as shotx2 in Tisure No.1, censists basically of a cylindrical test chmber, a water pus: ping station, and a prcreure gage, na pressure sage reads pressura at the base of the prescure seal and a 11,700 pound, threaded clorure nut e.aintains the pressure within the test chamber. 3.1.2 he Fressure sage was referenced to +40 peig; that is 1510 peig on the gege is actually 1550 psis. We pressuret mentioned in Section 3.2 of this report are the preseures as read frte the eart, (readability: 10 peig). Watsr soluble, fluorescent dye wee added to the water en the initial 3.1.3 pressurization as an aid in determining any trate of water which would enter the W3000 Arring the test. 3.2 Test Eistory 3.2.1 Initial Pressariaation he pressure was increased to 600 peig, blod to 250 psis to remove the air pocket within the test chamber, and increzsed to.600 psig he pressure was held for 10 minutet. De pressure was then in-again. creased to 1000 psig and held for 1 minute, and iners.ased to 1510 psig and

m e. bold f:r 9 minutos. During all of ths chers Shelde," no pressero 1:ss was observed in the test chamber indicating ne large leahs in the NW3000. ~'-~ 3.2.2 Cycling the pressure The pressure was then cycled twice from 1510 psig to o pcis to 1500 t Psig, and from 1500 psig to 50 psig to 1512 pais he_ rate of in-t crease was less than 500 psig per minute at all times and the rate of decresca l 1 h was less than 1000 psig per minute at all times. 3.2.3 Enerrance Esa i N pressure was mest held for 16 hours, the initial and final readiess l being 1512 psig and 1500 psig, respectively. Nre were several 3g,1112, ressoas for this 12 psig difference: error in reading the gage (readd.ility ( .i i of 10 psig), stabilisation of the water temperature, and sac 11 leaks or i I weeping in the ter3000, I 3.2.4 Post-test Inspection i -- i 3.2.&.1 m 25r3000 was remuod from the test chambar, dried with an air i r-s hose, and opened. 3.2.4.2 he vessel sad cover were black-lighted to illuminate any fluorescent j dye. No Isaks er weeping were observed. l l f i I l I i l t f s i i l I i

l-9. ) 1 Figura No. 1 t Test Set-UP (Schematic) i k 8 water pumpirs i station i t 1 i pressure gege l i sgg 11700 pound

h...-1 eleeure out e

.,.g f, threeds E:.'E . b. i

7. >:

3 { k Y-

  1. 'l ~

G f~ pressure sssi j ~ i 1 b E 0 sad dye 2 i ~ 12' i i t i 6 l l ] f W 3000 + V t C 4' ) a A w- .r,.. 1 .]

f!, f, f7j(jl' 's ~ /7"E$ hh. b l t, M'.?T.T UE1 C%'t t t i ? i I i-t' t l EFCITICAt20N -l PCS SwM!ms. 03 ElAT EU2:E KB TF1 Ye:50%A gel:EYKW i i i i i a MX-101E', i I April C, 1955 t 4 .l Prepared by: h Y/ G. S. dtivers eh l

f. r

~ Approved by: Project Ibgineer I M 2. (W. 8.4 I Des!gr/ Unit I =- W 5eleksed ty: f Centract Techn'cC; } Requirements l

r v. l i, t S Pi.7: C A*~~.E F.h BTPO."r10'-W EU.T STEF Ti? 0FI W OO3'. GI'J5aICC ) i l I 3. S 0TE - 'Ihic specificciien estitlishes the requirements for a Strcttiu-P3 hee.t source (fuel capsule} for t're MI 300^t redtf sct p thercoele:trie s Eenerator. t & r-dificatione er devicti:ns frcn either thir spe:fliet.- 1.1 Cete ral tier or refeiiEed de trente ebil be allcved u-less tuthorised ty Engireerin.r in writing. j .i 2. APEEAME IC/F)ES ' ins foMwing so:ve:estr ic2r L Fort cf thir epecifi.stien to the e;:re:.t rpecified here n. i 2.1 Martin Spee5 ficaticm j EJ-lOl37 restancy c. Pu:1 ccprule W.M 2.2 2.0.L hrift 2 - Isacerou: Arti lec j i f ,= m k Ccr2n ic; Eer$r'4.ir$ Sctel 2 3 AF.E-32 6 I i Ancy Stect, Ccrrerfea asd Eut T aziste.' i AMS-5530 RI;07.D'.E'CS 7 3 The Str::.tiu: -W fuel eb:.M ta it.+ the ?m:r te Tc air.. l 31 Srt;O Fuel i J 32 Source 'n'erar_.2 Read re-ente - ) 3 2.1 At ti=e of Freaprulatien At the tice: of fue'. encaprulatic.u, the themal inventory in the fuel capsule rhn11 te cet lest than 10 watte t;r ne:v .l the.n lLO vatts. t

a Per the determinstion of Sr-E9 3 2.2 At five Yasrs froc
Encapsulatien content limitaticcs, the themel inventory five f Si years arter encapsulation l

ehall te not less the ne. Exterior radioactive extaminaticn 33 Capsule Surfece Contse:iratiot of the completed fuel capsule, se measured by wipe tert, shan v.t exceed 0.05 l microcuries per one hundred (100) square centimters. l i Folleving the loadirs of the 34 Shippint Cer^Ainer Conte niestion fuel capsule inte the shipping c:ntainer (either e generetor or a Eenerater i body with a shipping lid), the radictetive centamir.atien of the extericr sur-I faces shall not exceed those specified in the Interstate Cceraeree Cons:nissien ~~' Regulations for shipping radioactive enterials. (I,C A hriff 2). i -,,,,.y- -,m -.-w w --w -n

17. . ovv Fuel cr.pruit linero es7 be ure6 et the dis-3 5 Pue~ Carn ~(e literr cret.ica cf ti e fuGirt fr.cility to si6 in the fut". prccer s'n; ctd the fuelirg of th E 3 COO heat scurce. If su:3 '.iness an, ured, they thc.n bs fahricatt.i frce 1316 321 stainless steel or Eastellcy C (155-5530;. fil fuel et.pnule cuter veldr chall acet 3 6 Cepsule Veld Recuire=erts the nquirc ents of M.b1013".. l 3 7 Capsule Materia? Certificctict A certified 2sberetory analytic r.hr.H te cttcir.ed fer an r. terielt used in the fatr*caticn of capsule ecurponents and test specisent except the fuel. The a slyrcr chall be cttsited frat the Supplier of the sateriale cr alterm.tely

  • y cle :ict.i and/cr spectrc;;raphic eralysis perfersed bv the Fart.in Crnpry.

Ar" dn39. tic.r. freu gevernin;;; speaii5-oc.tions specified by procuresent documts. and/or encinecring dravings shmil be cause for rejection. The Pac 1 Capsde thsn to 38 Fuci Capsule Owrttir.c Envircr-cr.t decigned with the c?;iective cf opersti:3 ir. either of the fc11ovirs enviro =tente for the time cpecified without brec. chics of the fuel esprule. uten t;te ful ecpsule it instclied in the 3.S:1 re m.1 Invirerzet.t Eenerator the environmental perarcters am: i Terpsrature - Nel :apsule surface lh00 t 1600*T. n Pres;ure - 1.0 to 1,5 atreephers Atr.osphere - 95% A gen, hitnce F : Op CCp. 2 Time - 300 years As an alterr. ate te tha envirctment of 3 8.2 b ergerev E vire x : paragraph 3 6.1, the capsule may crperience t' e fellevirte envirce. tent l 3 8.2.1 rire Terperature - 2000*T en fuel esprule surfact Pressure - 1 ste.rphere i 1 Atnosphere - Air and hydrocarbos cecbustica producte j Time - The abcre conditiers vin exirt for a wrW: of one hcur. I Felleming the fire, the capsule vin te subject to 300 years exposure to salt sir at 125'F vith the capsule surface texperature at 1000}T. The capsule any te sulzterEed in ses vater at c 3 8.2.2 Submergence depth of 30C0 ft. (1500 psi) for 300 years. I I i l

All beat ecurces and test pieces c.han be assigned 30 Identificatien an identifying n.:r.hr a. ' shan be chesrly marked with tlat nuder 'cy c pertnnert e'ep in any ccnveniert loes.ti r. Fuel es.pr4es shu te rr.rhc in the fellowing unnne.. Lide: A permanent stan str.E be cade et thc lifLin;; knot. This identificatier. stan he tb fae'_ eapsule identifying syttel ? fer the capsule of whici. the lid ferns a ar.rh. i 1odies: The bodice she.E rr.t te earhed *ey starpin, crccVitE cr any i other mechnical recr21.0 shi.n h cathed with a pcreanent die that vin met rub cff vith nennl hnnolins 'ihe die shall be red, yenev. or vhit<- r.::' eb:.11 h epp'.ied after the ft:1 l i capsule final ma-Mnim. l t L k. QT.I.T* AFSEGfE A ryste: cf qrtiity ecntrol and k.1 Inspectice System Fesuireme %r inspecticn stan te cet up to verify ec:sforrate with the require =.ents cf thic specificaticn. A co;rplete quality ca cre.+. reecra sta*.1 te asir.,tained and onc copy of cn required documents chi 1~ b: ti"Mtted to the Hartin Ccep:ny. l The reecrds shal.1 include as a cinit :2 int nct be lirited to the fonevin- [ iters ~ A certified ehemical analyris k 1.1 Capsule Fcterisis Certifiettiz L of all raterisis used in the tuci esprule rz.d fuel capr;le linct, e:: cept its j fuel. Qualifiestion tect data and equipeent log bocht and 4.1.2 Fuel individual run test data to de::cestrate the centerrn=e to parrgraph 31 of l this specifiestion. i Qvalifi:sticn test data, ve'.d l-k.13 Seal Veld process Certificatio3 photo r.icrographs and equ.iyaent 1cg bocks t.td quality ecntrol test data to desonstrate eenformance with paragraphs 3 6 and 4.2 of this specification l (that is, as required in Ms-lo13D. l Test De.tc denonstrating cenfort:r.ce f h.1.k Radioecntsminatien Vice hrts to paragraphs 3 3, 3 4 and 4 3 of this specification for et.ch heat scurce. Tert data de=cestrating conformance with f k.15 calorisietry Tests paragraph 3 2 and 4.4 of this specificatica for each heat source. l k.1.6 Part Identifice. tion Yach heat source and test piece shall be I assigned an identifying actbar and aban be clesrly marked with that nur.ber in accordance with the requirements of paragraph 3 9 This. identification j shall be recorded with all identifyin6 quality centrr,1 and test reecrds. j t An espsule velds chan be tested k.2 Weld Quality Verifiestien accordir.g to the tests and inspections required in psxagraph 3 6 of this i specifiention (that is as required in MK-lol37). e

.h. l 7 Radiocent=.ine. tion Vipe Tests eht11 be pertorised on. f f,ca, 4 3 wire Teste the fuel capsule exterier after the final deccuta=ination m:d en tbc shipping enck or generator exterier after heat scuree installatier.. In either case. zodiesetive contamination eel not exceed 0.05 microcuries per 100 square centimeters. If contninntion excecis this level, the deccLtarirstion pro:ecs vill be repeated until the above level is reached. If the specified levei ir not obtained, the espsule or generater vill be rejectc6. -l I t-Tbc fuel ecprule follovird the k.4 Caleriseter Check cf Ec t Sepee_ firA3 seal we d and decon+2,'nntien, stall te tested by cct:s of a. calerineter for conferrance to partgrnph 3 2.1. If the fuel capsule themel inventory ' exceeds lhd vatts or is less th n 133 sx.tts the ecrsuie cla:1 te rejected.. This acceptatic bana chel include the necurney cf the ccicri:2ter. 4 i e i i i ~$ 7 I i I a j i ) r k -l i I I i J J l

/7EA4 M. 7 '~ o! O DfIER.DEPARDE!!T COICMJICATIFJ July 1, 1966 To: Messrs. T. R. Barker II, W. Beutel, K. Dufrane, R. Euirch, S. Furmn, E. Kelly, L. Putnan, G. S. Stivers (2), A. Streb, W. Vogele, E. West Fran: D. O. Rhoads Mail Eo. 807 Ext. 313 Schj: 83 (1 to }Ci-10187 Specification for Strontitm-90 Eeat Source for the IW-300^J. Generator " i The subject specificttion chtage notice ic released and distributed hereby. 7 e D. O. Rhoads l Configuration & Data Mana. gem =t /1x 4 W t W i

-. ~. 7' .i .T THE MARTIN.MARIETTA CORPORATION SHEET 1 OF 3 BALTIMORE, MARYLAND 21203 ,, ~ ~ (Insert opp. page 1 .) .z. SPECIFICATION CH ANGE NOTICE .i f ~ - N O. 1 j DATE 1 July 1966 e SPEC.NO. -MN-10187 C.C.P. 'F/A i t t DATED April 8, 1966 PROJECT M1111vatt Generator CONTRACT NA SUBJECT OF CHANGE t Referenced specificai;1.ons r NATURE OF CHANGE: ~ e i In paragraph 2.1, delete *EN-10137" and replace with *MN-10191" f i t l REASON FOR CHANGE d h d I a b . To apply the latest and most appropriate veld specification i i.,. ! W. 1 3 :., j !?: ~ 'A -

REFERENCE:

~ MARTIN APPROVAL M 7EIN AUTHORIEATION: / h g, s, stivers .~ IM* kur II I \\ ' TH15 SCN AFFECTS P' AGES CDM Rhlease /).(A / . 7///g g i D. O. Rhoads 1, 2, 3 Manuf acturer's Code 3B597 y,.,.,. t 4.r,.,. i s. Ns 141.

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e f +

6 t THE MARTIN.MARIETTA CORPOR TION SHEET 2 OF 3 i BALT1MORE, MARYLAND 21203 (Insert opp. page 2 ) Spec. No. Mi-10187 =, SPECIFICATION CH ANGE NOTICE NO. 1 DATE 1 July lo66 In paragraph 3 6, delete "Mi-lOl37" and replace with "mi-lo191" t b 9 e I i 4 ~.., s B 0 's

  • s 9

' AUTHORIZATION SEE SHEET I THIS SCN AFFECTS PAGES 1, 2, 3 ~ . No1&E + ~..-- ?

y ( a t THE MARTIN-MARIETTi CORPORATION SHEET 3 OF 3' f l . BALTis0RE, MARYLAND 21203 (Insert opp. page 3 ) i i i

v Spec. No. 10187

{ ^ { SPECIFICATION CH ANGE NOTICE [ NO. 1 ~ D A T E _ i Juiv iM6 In paragraph 4.13, delete *MN-10137" and replace with "MN-10191" t In paragraph k.2, delete *MN-10137" and replace with "HK-10191" ( t t I .i I a. I a l l ^ l i q 2 i ) i T I i I f 4 t 1 .r ~ l t AUTHORIZATION SEE SHEET 1 r THIS SCN AFFECTS PAGES ('- 1, 2, 3 p .c .Neldt { ~* ) M* g .t

Dr:a r: v D:tc April 14, 196G n. NUrLTMR TEST DIRECuVU Pcge 1 of _ 't

i. Account No.
c. O.D. No.

d.T:st Directive No.

c. Ibs. Approrai

/d/////f/44 M 91-802-11500 4991 Prclininary f.TestItemPsrt Number

s. Test Iten Nr.m2
h. Test Itc n Suhl Ne/Nes er Ques 471 Allo 0001 Ei3000 Fuel Capsulo S/N-1
1. Test Typs
j. Tert D2:cription h.Ttst Grcup 1.TcztLee.

D Pr f Pressuro Test at O 10 Operating Te=perature

n. Desircd Echedulo rn. Objoetire StcrB6/24/66 I C:sp. 7/1/G6 The objective of this test is to decon~

ctrate the ability of the test part to curvive the hydrostatic pressures for which c.EcportR(d it was desigacG at the c:mected operating At cocipletion of test tesperatures. t

p. GenerelRequiremseta
1. The test procedure prepared in respense to this directive wiH be reviewed and approved by (r.) Projed Esgre r.

ing (b) Reliab5ity Enginearkg (c) Quality. 2. Q:Elity wIll verify that all test equipment is in en% tion nt the initiation of testing and that ds.ta is reccrdsf in accordanca with the test procederc.

8. Au fr.ilures as defined in MNQ.CB-001, Bubject: Corrective Action System and Stetian 2. Test Eequirmest oe.

enrring during test will be reported on ID ES Form MN-1024 and a copy indaded in the test log. 9130 en 33 G. S. Stiverm x

4. Immrdiste notification win be given to the Project EngineF-MeGin+y x

mum when ter' failures and to the Projoet E,%hmty Representative artidea fail. Deviations to this directive win be nuthtrhed on a Test Directive Change Sheet and distributed in accordanes wit: " the distrIbstionlirt at tha eni af this directive.

6. A copy of tbc final tset report / reports resniting fe:m this directive wEl be furn!shed to Project and Ec1!thilit-En&ds N-144
9. '

~ APRIL 14, 1966 PAGE 2 NUCLEAR TEST DIRDCTIVE NTD - Preliminary p:- q. Test Requirements I. Parameters to be measured. A. Hydrostatic Pressure external to test pieco 0 - 1000 psig D. Temperature of fluid surrounding test piece 1 100 to 1000*F II. Tests to be performed. A. General The test piece will be placed in the test fixture. The temperature and pressure of the test fixture fluid will be raised to 1000 psi and 1000*F and then cycled. Upon ecapletion of tbc test, Martin vill cut open the test picco to examine it for any evidences of ~ Icakage. D. Test Description 1. Place the test piece (Martin Draring 471A1100001) into the test fixture. 2. Close the chamber and fill it with water. Purge the chamber of all gases. 3. Increase the chamber pressure at the maximum possible rate, up to 1000 psig. 4. Bring the chamber temperature up to lOOO'F as rapidly as possible. 5. Hold at 1000 psig and 1000*F for 15 minutes. 6, Redupe pressure and temperature to O psig and 100* as fast as possible. 7, Following steps 4, 5, and 6, cycle the pressure and tecperature twice more. Then bring the test 1 piece back up to 1000*F and 1000 psig. Ok

NUCLEAR TEST DIEECTITE Pr.ra 3 of_ 8 L Test Dire:tirc Ko. Prelininn: y Test Eequir=cr.ts (Continued) t ~ i 8. 8. Iloid at 1000*F and 1000 psig for 24 hours. 9. Reduce pressure and temperature to O paig and room 4 temperature and recove test piece from chamber. 10. Inspect visually for cracks, leaks, etc. III. Miscellaneous Information A. Measurement Accuracy 1. Pressurc: + 20 psig 2. Temperature: + 25'F i I . '? t m tp I

r. Report Bequirements A summary report shall be written at the completion of the test.

The report will include any unusual events occurring during the test and results of the preliminary inspection.

t. Oristrator
s. DhdrIbstion Proje:L Engineering G. S. Stivers /

Pel. Errineering F. McGinty Test Er.gir.eerirs G. 5. Stivers Qaslity E. treinkam l ~ Projcet Mn.vege:ncnt T. R. Darker Phone 9130 EnB No. 835 Other x' '- A. Streb Date April 14, 1966 S. Farman (2) H. Kelly N-145

'~ /7E~)V7 /VO. 'f} l J-t 5 Cc.gh ' M biQg.W (klf 19 December 19'2 i Refer to: OJ705-12-19-63 PJK:1210-Ol8 To: U. S. Atomic Energy Co=issics inshington, D. C. 205L5 /,ttentics : iir. P.

3. Chitd, Chief Irridnted Fuels Branch

Subject:

AIC Byproduct Enterial I.icense 19-1396-34, Endicisotope Therr.oelectric Generator Nr>=encleture Gentiexa: Isotopes has decided to use nee designrtions for its ri.dicisatope ther=1 generatore ranufactured after Decesber 9, l?66. Tne tr.ble below sets forth nomencinutre dec1gnations for all radioisctope ther.ml generatoro ecvered by License 19 1333-34. r n Desigantion fcr Unite Alteracte Equivalent Unique Ikoigantions lunufactured Prior to Desicantion fcr Units for Units Minufactered December 9,192 Manufactured Prior to after Deced>cr 9, 1909 December 9, 196S 1EG-25A Sentinel 25A Gentinel 25A ICG-25B Sentinel 25B Sentinel 253 ICG-250 Sentinel 25C Sentinel 25C MW-37)3 Sentinel 3 Sentinel 3 Sentinel 8 If neccesary, plerse e.-and our license to reflect this ::ethei of designaticn. It is presently planned to continue using the Sentinel desi tetion on generators in.m:factured in the future, 6 t Sincerely yours, Peter J. Knapp Licensing & Accountebi.lity Representative 0332 pgt .e e n

g ~ 9PTELEDYNE C 'i. ENERGY SYSTEMS 110 W. TIMONIUM RD. T4MONIUM, MD 21093-3163 PHONE: (301) 2524220 [ TELEX: B 7780 (TDYENER TIMO) DDD: (301) 252-7926 (TDYEN ER TIMO) l CABLE: TELISES. 1 February.1991 Refer to: SEN-FAS-677 -United States Nuclear Regulatory Commission Transportation Branch Div. of Safeguards and I Transportation, NMSS Washington, D.C. 20555 t Attention: Mr. Charles E. MacDonald, Chief j

Dear Mr. MacDonald:

'With reference to your letter of December 31,1990 (SGTB:BHW 71-9030) I am enclosing copies of the text for Teledyne Reports TES-3231 and TES-3233 to I support renewal of Certificate No. 9030 for the Model Nos. MW-3000 and i Sentinel-8 packages. The reports enclosed are revised to comply with your recuirements as cited in the referenced letter. Revisions include the supplement dated August 16, 1966 (TES-3233, page i 97), and page number 18 from the supplement of November 5,1%8 (TES-3231, page 25A). The revisions also address compliance with 10 CFR Part 71 Subpart G. l t t If there are questions, please call me at (301) 252-8220. Sincerely, 29 f/ j a F. A. Schu:rann r ew Enclosures I I Il I i ? / a WA

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