ML18345A211

Letter from P. Noss/Orano Federal Services LLC Brr Package Amendment Request, Docket No. 71-9341 and EPID No. L-2018-LLA-0028 (Redacted)

ML18345A211
Person / Time
Site:	07109341
Issue date:	11/14/2018
From:	Noss P Orano Federal Services
To:	Michael Layton Spent Fuel Licensing Branch
Devaser N
References
EPID L-2-18-LLA-0028, FS-18-00289
Download: ML18345A211 (17)

Text

orano federal Way Office USA 505 S. 336th Street Suite 400

.Federal Way, WA 98003 Tel: (253) 552-1310

@orano_USA AT1N: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguard~

U.S. Nucleat Regulatory Commission

• Washington, be 20555:-0001 November 14, '2018 FS-18-00289

SUBJECT:

BRR Package Amendment Request,Docket No. 71-9341 and EPID No. L-2018-LLA-0028

Dear Mr. Devasei':

Qrano Federal Service~ LLC (Orano FS) hereby stip)llits Revision 14 of the Safety Analysis Report (SAR) for the BRR Package, which consists entirely of a col"rection to Note 13 on Sheet 1 of drawing 1910-01-01-SAR.

The note h~s been changed FROM:

Forged mateifal shall be ultrasonically artd liquid penetrant inspected in accordance with ASMECode, Section Ill, Division 1, Subsection NB, Atticle NB-2540, and Section V, Atticles 4 and 6.

TO:

• Forged Ihaterial shall *be ultrasonically and liquid pertetrant inspected in.

~ccordance with ASME Code,Section III, Divisipn.1, Subsection NB, Article NB-2540, and Section V; Atticles 5 and 6.

The only change is that Atticle 4 has been changed to Atticle 5. This.corrects a minor e1rnr in the inspection techniques. Article 4 of Section V refers to ultrasonic inspection of weids, whereas the c01Tect Articie for the inspection of forgi~gs is A1ticle 5. This e1rnr was identified during a NRC inspection of the facility cm1*ently fabricating BRR packagings during the week of 11/5/18.

In order that this con:ection can be supplied td the fabricator at the earliest possible date, it would be greatly appreciated if this change could be incorporated into the licensing action cmTently underway for the BRR package.

In addition, our DOE client has scheduled isotope shipments to occur shmtly ijfter the beginning of the new year. For these reasons, a Certificate of Compliance issue date as early as the end of November, or by mid-December at the latest, would be appreciated.

This chimge affects only Note 13 on sheet 1 of drawing 1910-01-01-SAR, which has been advanced to Revision 7. For completeness and t> comply with Orano's.

Page 1 bf 2

orano Federal Way Office USA 505 S. 336th Street S4ite.400 federal Way, WA 98003 Tel: {253) 552-1310

@orano_USA November 14, 2018

'FS-18-002$9 ptocedutes, all five sheets of dtawing 1910-01-01-SAR, the SAR cover sheet and binder spine, and the Table of Contents (six pages) are supplied as pait of this amendment request. Note, there are no changes to any other. drawings orto any SAR text.

Included with this letter is cme paper copy of the stated drawing and SAR update pages and one CD containing the PDF file "BRR SAR Complete Rev. 14.pdf' (35,910 kb, 777 pages). The CD.is labeled, "BRR Package SAR Revision 14, Docket 71-9341 EPID No. L-2018-LLA-0028".

To update a paper copy of the SAR, replace the cover sheet, Table of Contents, and drawing 1910-01-01-SAR (five sheets). Ah extra cover sheet and spine*

sheet are provided to update the binder.

Should you have any questions regarding this submittal, please contact me at (233) 552-1321 or via email (phil.noss@orano.group ).

Yours Truly,

1. U/Jj/l/0 Philip Noss Licensing Manager Oram) Federal Services LLC Copies:

Attention: Nishka Devaser, Project Manager (lncl. changed pages and CD)

U.S. Nuclear Regulatory Colllmission 11545 Rockville Pike Rockville, MD 20852 Donald Darrington, Idaho National Laboratory (ind, changed pages and CD)

Cada Dwight, Idaho National Laboratory (incl. changed pages and CD)

DL Ethan Balkin, DOE-SC Isotope Programs (incl. changed, pages and CD)

Richard J. Smith, Project Manager, Orano Federal Services LLC Tess Klatt, Contracts, Orano Federal Services LLC Page 2 of 2

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tD Safety 0Analysis Report Docket 71-9341 Revision 14 November 2018. /

DOCKET 71-9341 orono BEA Research Reactor*Package Safety Analysis Report Revision 14

• Orano Federal Services LLC November 201/8

DOCKET 71-9341 I

orono BEA Research Reactor Package

-~-

'Safety Analysis Report Revision 14 Orano Federal Services LLC November 2018

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BRR Package Safety Analysis Report TABLE OF CONTENTS Docket No. 71-9341 Rev. 14, November 2018 1.0

• GENERALINFORMATION.............................................................................. 1.1-1 1.1 Introduction................................................................................................. 1.1-1 1.2 Package Description......................,............................................................. 1.2-1 1.2.1 Packaging...................... :............................................................. 1.2-l 1.2.2 Contents....................................................................................... 1.2-6 1.2.3 Special Requirements for Plutonium......................................... 1.2-10 1.2.4 Operational Features................................................................. 1.2-11 1.3 Appendices.................................................................................................. 1.3-1 1.3.1 References................................................................................... 1.3-1 1.3.2 Glossary of Terms and Acronyms............................................... 1.3-2 1.3.3 Packaging General Arrangement Drawings................................ 1.3-4 2.0 STRUCTURAL EVALUATION........................................................................ 2.1-1 2.1 Structural Design........................................................................................ 2.1-1 2.1.1 Discussion........... ::~..................................................................... 2.1-1 2.1.2 Design Criteria............................................................................ 2.1-2 2.1.3 Weights and Centers of Gravity.................................................. 2.1-6 2.1.4 Identification of Codes and Standards for Package Design........ 2.1-6 2.2 Mater~als..................................................................................................... 2.2-1 2.2.1 Material Properties and Specifications........................................ 2.2-1 2.2~2 Chemical, Galvanic, or Other Reactions..................................... 2.2-1 2.2.3 Effects of Radiation on Materials................................................ 2.2-2 2.3 Fabrication and Examination...................................................................... 2.3-1 2.3.1 Fabrication................................................................................... 2.3-1 2.3.2 Examination................................................................................ 2.3-1 2.4 General Standards for All Packages........................................................... 2.4-1 2.4.1 Minimum Package Size............................................................... 2.4-1 2.4.2 Tamper-Indicating Feature.......................................................... 2.4-1 2.4.3 Positive Closure.............................................. ]_............................ 2.4-1 2.4.4 Valves.......................................................................................... 2.4-1 2.4.5 Package Design........................................................................... 2.4-1 2.4:6 External Temperatures................................................................ 2.4-1 2.4.7 Venting........................................................................................ 2.4-1 2.5 Lifting and Tie-down Standards for All Packages..................................... 2.5-1 2.5.1 Lifting Devices............................................................................ 2.5-1 2.5.2 Tie-down Devices....................................................................... 2.5-1 2.6 Normal Conditions of Transport................................................................. 2.6-1 2.6.1 Heat............................................................................................. 2.6-1 2.6.2, Cold..............................................................................,.............. 2.6-9 2.6.3 Reduced External Pressure........................................................ 2.6-11 2.6.4 Increased External Pressure...................................................... 2.6-11 2.6.5 Vibration.................................................................................... 2.6-12 2.6.6 Water Spray........................................................... *.................... 2.6-13 2.6.7 Free Drop....................................................... *............................ 2.6-13

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BRR Package Safety Analysis Report Docket No. 71-9341 Rev. 14, November 2018 2.6.8.

Corner Drop........................................................ :...................... 2.6-17 2.6.9 Compression.................................................................. ;........... 2.6-17 2.6.10 Penetration................................................................................. 2.6-17 2.7 Hypothetical Accident Conditions.............................................................. 2.7-1 2.7.1 Free Drop..................................................................................... 2.7-1 2.7.2 Crush......................................................................................... 2.7-21 2.7.3 Puncture..................................................................................... 2.7-21 2.7.4 Thermal..................... :............................................................... 2.7-23 2.7.5 Immersion-Fissile................................................................... 2.7-25 2.7.6 Immersion -All Packages......................................................... 2.7-25 2.7.7 Deep Water Immersion Test...................................................... 2.7-25 2.7.8 Summary of Damage................................................................. 2.7-26 2.8 Accident Conditions for Air Transport of Plutonium................................. 2.8-1 2.9 Accident Conditions for Fissile Material Packages for Air Transport....... 2.9-1 2.10 Special Form............................................................................................. 2.10-1 2.11 FuelRods..........................................,....................................................... 2.11-1 2.12 Appendices............................................................................ ::,*.................. 2.12-1 2.12.1 References.............................................................................. 2.12.1-1 2.12.2 Certification Test Plan............................................................ 2.12.2-1 2.12.3 Certification TestResults....................................................... 2.12.3-1 2.12.4 Stress Analysis Finite Element Models.................................. 2.12.4-1 2.12.5 Impact Limiter Performance Evaluation................................ 2.12.5-1 2.12.6 Analysis Software Descriptions............................................. 2.12.6-1 2.12.7 Seal Performance Tests.. :....................................................... 2.12.7-1 2.12.8 Basket Stress Analysis........................................................... 2.12.8-1 3.0 THERMAL EVALUATION............................................................................... 3.1-1 3.1 Description of Thermal Design................................................................... 3.1-1 3.1.1 Design Features........................................................................... 3.1-1 3.1.2 Content's Decay Heat.................................................................. 3.1-4 3.1.3 Summary Tables of Temperatures.............................................. 3.1-4 3.1.4 Summary Tables of Maximum Pressures.................................... 3.1-4 3.2 Material Properties and Component Specifications.................................... 3.2-1 3.2.1 Material Properties...................................................................... 3.2-1 3.2.2 Technical Specifications of Components.................................... 3.2-3 3.3 Thermal Evaluation for Normal Conditions of Transport.......................... 3.3-1 3.3.1 Heat and Cold.............................................................................. 3.3-1 3.3.2 Maximum Normal Operating Pressure....................................... 3.3-6 1

3.3.3 Cask Draining and Vacuum Drying Operations......................... 3.3-8 3.3.4 Cask Cavity Backfill with Helium Gas..................................... 3.3-10 3.4 Thermal Evaluation for Hypothetical Accident Conditions....................... 3.4-1 3.4.1 Initial Conditions................... '...................................................... 3.4-1 3.4.2 Fire Test Conditions.................................................................... 3.4-2 3.4.3 Maximum Temperatures and Pressure........................................ 3.4-2 3.4.4 Maximum Thermal Stresses........................................................ 3.4-3 3.5 Appendices.................................................................................................. 3.5-1 3.5.1 References................................................................................... 3.5-2 ii

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BRR Package Safety Analysis Report Docket No. 71-9341 Rev. 14, November 2018 3.5.2 Computer Analysis Results......................................................... 3.5-5 3.5.3 Analytical Thermal Model........ :................................................. 3.5-5 3.5.4

'Last-A-Foam' Response under HAC Conditions.................... 3.5-36 3.6 Thermal Evaluation oflsotope Production Target Payloads...................... 3.6-1 3.6.1 Description of Thermal Design................................................... 3.6-1 3.6.2 Material Properties and Component Specifications.................... 3.6-7 3.6.3 Thermal Evaluation for Normal Conditions of Transport........... 3.6-9 3.6.4 Thermal Evaluation for Hypothetical Accident Conditions...... 3.6:-22 3.6.5 Appendices for Isotope Target Payloads................................... 3.6-29 4.0 CONTAINMENT................................................................................................ 4.1-1 4.1 Description of the Containment System..................................................... 4.1-1 4.1.1 Containment Boundary................................ ::............................. 4.1-1 4.1.2 Containment Penetrations........................................................... 4.1-1 4.1.3 Seals............................................................................................ 4.1-1 4.1.4 Welds........................................................................................... 4.1-2 4.1.5 Closure........................................................................................ 4.1-2 4.2 Containment Under Normal Conditions of Transport................................ 4.2-1 4.3 Containment Under Hypothetical Accident Conditions............................. 4.3-1 4.4 Leakage Rate Tests for Type B Packages................................................... 4.4-1 4.4.1 Fabrication Leakage Rate Tests.................................................. 4.4-1 4.4.2 Maintenance/Periodic Leakage Rate Tests................................. 4.4-1 4.4.3 Preshipment Leakage Rate Tests................................................. 4.4-1 4.5 Appendix..................................................................................................... 4.5-1 4.5.1 References................................................................................... 4.5-1 5.0 SHIELDING EVALUATION............................................................................. 5.1-l 5.1 Description of Shielding Design................................................................. 5.1-1 5.1.1 Design Features........................................................................... 5.1-1 5.1.2 Summary Table of Maximum Radiation Levels......................... 5.1-1 5.2 Source Specification................................................................................... 5.2-1 5.2.1 Gamma Source.... ;........................................................................ 5.2-1 5.2.2, Neutron Source............................................................................. 5.2-9 5.2.3 Irradiation Gas Generation........................................................ 5.2-10 5.3 Shielding Model.......................................................................................... 5.3-1 5.3.1 Configuration of Source and Shielding....................................... 5.3-1 5.3.2 Material Properties...................................................................... 5.3-3 5.4 Shielding Evaluation................................................................................... 5.4-1 5.4.1 Methods....................................................................................... 5.4-1 5.4.2 Input and Output Data................................................................. 5.4-1 5.4.3 Flux-to-Dose Rate Conversion.................................................... 5.4-2 5.4.4 External Radiation Levels........................................................... 5.4-2 5.5 Appendices.................................................................................................. 5.5-1 5.5.1 References.................................................................................. '. 5.5-1 5.5.2 Detailed TRIGA Results............................................................. 5.5-1 5.5.3 Sample Input Files................................................................. _...... 5.5-8 lll

BRR Package Safety Analysis Report Docket No. 71-9341 Rev. 14, November 2018 5.6 Shielding and Heating Evaluation oflsotope Production Target Payloads...................................................................................................... :5.6-1 5.6.1 Description of Shielding Design................................................. 5.6-1 5.6.2 Source Specification.................................................................... 5.6-3 5.6.3 Shielding Model.......................................................................... 5.6-4 5.6.4 Shielding Evaluation................................................................. 5.6-16 5.6.5 Heating Evaluation.................................................................... 5.6-19 5.6.6 Appendices for Isotope Production Target Payloads................ 5.6-24

6.0 CRITICALITY EVALUATION

......................................................................... 6.1-1 6.1 Description of Criticality Design................................................................ 6.1-1 6.1.1 Design Features........................................................................... 6.1-1 6.1.2 Summary Table of Criticality Evaluation................................... 6.1-1 6.1.3 Criticality Safety Index............................................................... 6.1-2 6.2 Fissile Material Contents............................................................................ 6.2-1 6.2.1 MURR Fuel Element................................................................... 6.2-1 6.2.2 MITR-II Fuel Element................................................................ 6.2-2 6.2.3

• ATR Fuel Element............................................................. :.*.:*..... 6.2-3 6.2.4 TRI GA Fuel Element.................................................................. 6.2-5 6.2.5 PULS TAR Fuel Element............................................................. 6.2-6 6.2.6 Square Plate Fuels....................................................................... 6.2-6 6.3 General Considerations............................................................................... 6.3-1 6.3.1 Model Configuration................................................................... 6.3-1 6.3.2 Material Properties...................................................................... 6.3-2 6.3.3 Computer Codes and Cross-Section Libraries............................ 6.3-2 6.3.4 Demonstration of Maximum Reactivity...................................... 6.3-3 6.4 Single Package Evaluation.......................................................................... 6.4-1.

6.4.1 Configuration.............................................................................. 6.4-1 6.4.2 Results....................................................................................... 6.4-10 6.5 Evaluation of Package Arrays under Normal Conditions of Transport...... 6.5-1 6.5.1 Configuration.............................................................................. 6.5-1 6.5.2 Results......................................................................................... 6.5-1 6.6 Package Arrays under Hypothetical Accident Conditions.......................... 6.6-1 6.6.1 Configuration.............................................................................. 6.6-1 6.6.2 Results......................................................................................... 6.6-3

6. 7 Fissile Material Packages for Air Transport............................................... 6. 7-1

• 6.8 Benchmark Evaluations.............................................................................. 6.8-1 6.8.1 Applicability of Benchmark Experiments................................... 6.8-1 6.8.2, Bias Determination....................................................... :.............. 6.8-3 6.9 Appendices........................................... *....................................................... 6.9-1 6.9.1 References................................................................................... 6.9-1 6.9.2 Parametric Evaluations to Determine the Most Reactive Fuel Geometries.................................................................................. 6.9-1 6.9.3 Sample Input Files..................................................................... 6.9-12 7.0 PACKAGE OPERATIONS................................................................................. 7.1-1 7.1 Procedures for Loading the Package........................................................... 7.1-1 7.1.1 Preparation for Loading.............................................................. 7.1-1 IV

BRR Package Safety Analysis Report Docket No. 71-9341 Rev. 14, November 2018 7.1.2 Loading of Contents.................................................................... 7.1-1 7;1.3 Preparation oflsotope Targets for Loading into the BRR Cask. 7.1-8 7.1.4 Preparation for Transport............................................................ 7.1-9 7.2 Procedures for Unloading the Package....................................................... 7.2-1 7.2.1 Receipt of Package from Carrier................................................. 7.2-1 7.2.2 Removal of Contents................................................................... 7.2-1 7.3 Pr~paration of an Empty Package for Transport...................... '................... 7.3-1 7.4 Appendix...................................................................................................... 7.4-1 7.4.1 References................................... :............................................... 7.4-1 8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM.......................... 8.1-1 8.1 Acceptance Tests.................... :................................................................... 8.1-1 8.1.1 Visual Inspection and Measurements.......................................... 8.1-1 8.1.2 Weld Examinations..................................................................... 8.1-1 8.1.3 Structural and Pressure Tests...................................................... 8.1-1 8.1.4 Fabrication Leakage Rate Tests.................................................. 8.1-2 8.1.5 Component and Material Tests................................................... 8.1-5 8.1.6 Shielding Integrity Tests............................... ;~:......................... 8.1-12 8.1.7 Thermal Tests............................................................................ 8.1-13 8.2 Maintenance Program................................................................................. 8.2-1 8.2.1 Structural and Pressure Tests...................................................... 8.2-1 8.2.2 Maintenance/Periodic Leakage Rate Tests............ ~.................... 8.2-1 8.2.3 Component and Material Tests................................................... 8.2-3 8.2.4 Thermal Tests.............................................................................. 8.2-4 8.3 Appendix..................................................................................................... 8.3-1 8.3.1 References................................................................................... 8.3-1 V

BRR Package Safety Analysis Report This page left intentionally blank.

vi Docket No. 71-9341 Rev. 14, November 2018

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lpWGNIJ 1910;01~01-SAR IREV 7 1sr11 I 1

LIST OF MATERIAL$

NOTES; U~Ll::SS OTHERWISE SPECif 11:D:

ITEMNO PART NO DESGRiPTION SPECIFICATION A4 A3. A2 A1 1-.

INTERPRET DRAWING PERASMEY14.5.M.

• INTERPRET WELDS PER ANSlfAVVSA?.4.

I BRR f>ACKA9E. AS~EMBL v

?,

THREAD$ PERAl\\!SI B1.1; D<

A1

3.

THE-PACKAGE SHALL BE IDENTIFIED IN ACCOROAJIICE WITH THE REQLJIREMENTS.QF 10 CFR71,8ti(r;) U.SING IX 1 A2 BRR CASK ASSEMBL. Y A STAINLESS STEEL JIJAMEPLATE;....

~

1 A3 SHIELD PLUG D

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4, ALL WELDING PROCEDURES AND PERSONNEL SHALL BE OllALiFIED JN*ACCORDANCE WITH AslViE SECTION IX;

5.

ALL WELIJS SHALL BE VISl,IALL Y E>v)tvJINEO. IN I\\CCORDAJIIC.E WITH AWS D1.6.

IX 1

A4 PERSdNNEL BARRIER ASSEMBLY IT:)* INDiCATEDWELDS SHALL BE LIQUID PENETro>.NJINSPECTED ON THE FINAL PASS INACCQRDANCE WITHASME CODI;,

SECTION 11,;DIVISION 1, SUBSECTION NB; ARTICLE NB-500Q; ANO. SECTJC>NV, ARTICLE 6: **

t 1

. 1910-01-0Z1AR~~i utPER IMPACT UM1TER;AS$~MBLY CE) INDICATED WE:LDS SHALL BERADIOGRAPH INSPECTED IN ACCORDANCEWITH.ASMECODE, SECTION Iii, DIVISION 1, 1

2 191.0,01-92~SAR-A2 LO\\fVER IM~A~,: LIIVl!TER AS.SEMBLY SUB~ECTIOfll NB, ARTICLE NB~oo.o; Al'lP SEGTION v. ARTJ(;L.E 2.

(() iNDICATED WELDS SHALL BE UL TRASONiCALLY INSPECTED IN ACCORDANCE WITH ASME CODE, SECTION Iii, DiVISION 1, Hf 3

C.b16~~LPT 13ALl,LOCKPiN.. 1 DiA, STAINLE:SS~TEEL dAR~LANE,OR.t::Q(!tv

• • SUBSECTION NB~ ARTICLE NB~5000,AND SECTION V; ARTICLE 4; CID 1

4 O-RING, 1'1.88 +/~ 1% 10 X:;375 +i-.Olfr BVTXL, AAINiERRIJBBER R040.S.:10

9.

ALL ITEMS MADE FROM SHEET MATERIAL MAY EiE MADEFROM TWO OR MORE PIECES; AND JOINED WITH COMPLETE (i.;RING, 20.125 +/~ 1% IDX.315 +/ *. 007

. BUTY( RAINIERR1JBBERR040!i4Q -

PEt-lETRATION VVELDS, IN$PECTECJ IN AQCORDANCE: VVITHGlN.?8, DD 1

5 fo.

As'rM A240; A276 OR A479 ARE OPTIONAL MATERIAL FORMS THAT MAY.BE SlJEiSTlT\\./TED FOR ANY ASTMA240; /1,276 I

CID 2

6 NAS1523C6N SEALING WASHER;.3S 10.

BU1YL, RAiNIERRUBBl:R R~4d5-io I

0RA479, TYPE 304 STAINLESS STEEL...**

OD OPTION: LEAD M.AY BE PER FEPERAL SPECIFICATION QQ,L*171E; GRADE A OR 0, CID 1

7 NAS1523CtON SEACING WASHER,,63 ID BUTYL; RAINIER RUBBER R0405~70 WASHER, J7tAKX1:()6 fDX 1.6 OD ASTM A564, GRADE 630, CdNO H1025 CJD CAST MATERIAL SHALL BE RADiOGRAPH AND LIQUID PENETRANT INSPECTED IN ACCORDANCE WITH ASNIE CQDE.

z 8

SECTION II!; DIVISIOl'J 1, SUBSECTION )IIB; ARTICLE NB~2570; AND SECTION V, ARTICL!=S2 AND 6.

1

.9 DUST COVER,. BODY

• ASTM 016 UNS 036000, HQ2 TEMPER FORGED MATERIAL SHALL BE ULTRASOi'iJICALL Y At-ID LIQUID PENETRANT INSPECTED j~CORIJANCE: \\il/lTH ASME CODE,

.. *.,.-=.,.

13.

2:

10 DUST COVER, LID ASJ M B16. ONS,C36000, H02 TEMP.ER.

SECTION Ill; QIVISIQN h SUBSECTl!;>N NB.ARTICLE NB-2540, AND SECTIONV; ARTICLES. 5_ ND 6.

C OD WHEN.MATERIAL OPTION AstM A 18.2. GRAC)E F304 is usED, INSPECT.PER c,1N 13, 1

11 ALl$NIVIENT PIN,.75 DIA ASTM /.i27!>,lJNS s21 soq C

[][) Wl:IEN MATERIAL OPTION ASTM A 182, GRADE F3041S USED; INSPECT PER GiN 13 *. WHEN MATERIAL OPTION

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~2 tt SHCS, 1-BUNC-2A X 2.5 LG I

ASTM}\\320, TYPE L43

• ASTM A451, GRADE CPF8A IS USED; INSPECT PER F/N 12. * *

• 1 13

$HCS, 5/8~11UNC-?A AS,TNI B16 UI\\JS C3600Q,.H02J"EMPER 16, WELDMENTOF END CASTINGS fJ!N 15 AND.1/N 16~TO INNER AND OUTER SHELLS (1/N 17 AND UN 18~SHALL COMPLY WITH i

sHcs. 3/S-16VN<>2/\\

AS.TM B16 lJNS C36000, H02 TEMPER TOLE~l\\lCl=REQl;)IREMENTS O ASMECQDI;, S CTIQN !II, DI\\/ISION 1, SUBSECTIQN NE,.ARTICLE E:4220.

2 1.4 I.

cAs'nNG, yt>P~R Boov ASTM A351, GR CFBA 0RASTMA182,

!JD 0-RING MATERiAL, ACCEPTANCE TESTS, AND ACCEPTABLE DEVIATIONS IN PROPERTIES ARE PER SECTION 8.1.5.2 QF THE

[IDIJD

,1 15

. _ GRADE F304 SAFETY ANALYSIS REPORT;

[IDIJP 16 CASTING, LOWER BODY ASTM A351, GR CF8A ORASTM A 182, 1

.. GRADE F304.

[ID ~Efi!~6J~~L~b1tz\\b}t.T~Ws'i'oW}9~~~~ ?;'d;'B'i 6~010 INCHES. IN ACCORDANCE WITH SAE-AMS 2404, REVISION F.

(]!)OD 17 CASTING, INNER SHELL ASTM A451, GR CPFBA ORASTM A182,

• 1 GRADEF304

~ [ID PRIOR Tb ASSEMBLY, OPTIONALLY COAT EACH 0-RING WITH A THIN COAT bFVAC.UUM G.REASE.

ASTM A240; TYPE.304 OR;ASTM f\\182 ~

[ID[ID 1

18 PLATE, OUTER SHELL, 2.0 THK GRADE F304. ORASTM A451; GRADE

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TIGHTEN CLOSURE BOLTS TO A TORQUE OF 200-240 FT-LB,.USING A CROSSING PATTERN

• COAT lHREAOSWITH A LOW-CPF8A HALOGEN; NICK.EL BASED Nl,ICLEAR GRAl)E LUBRfc;ANT PRIOR TO ASSEMBLY.

1 19

,O.NGLE; 1 X 1)( 1/8 ASTM f>,'l.76, TYPE 304 rn::> TIGHTEN PORT PLUG BOLT Tb 8-10 FT-LB TORQUE.

DD AR 20 Ll:AD, POURED ASTMB?9

[ID TIGHTEN DRAIN PLUG BOLT TO 18~22 FT-LB TORQUE.

,\\R 21 StiEET!.10HA~ (12 GA)

ASTM A240, TYPE :304 23, THE DESIGN PRESSURE IS. 25 PSIG. THE CONTAINMENT BOUNDARY SHALL BE PRESSURE TESTED TO A MINiMUM OF 125%

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AR AR 22 LEA'D;SHEET ASTMB29 OF THE DESIGN PRESSURE AS REQUIRED BY SECTION a; 1.3.2 OF THE SAFETY ANALYSIS REPORT.

1 AR 23 Pi.ATE, to THK ASTM A240, TYPE 304.

24.

THE CONTAINMENT BOUNDARY SHALL BE LEAKAGE RATE TESTED TO DEMONSTRATEA LEAKAGE RATE NOTTO EXCEED..

11?

24 KNH1ij08JMX~SY. HEAVY DVTY INSERT~ 1.SUNC;-?B X 1.4 LG.

KE!:NSERT OR EQUIV 8

1.0E-7 REFERENCE CUBIC CENTIMETERS PER_SECOND,AIRiPER ANSI N14.5; AS REQUIRED BY SECTION B:1.4 OF THESAfETY 8

ANA" Y$1S REPORT; (CONTINUED ON SHEET 3)

CT[) A Sl:IIELDING INTEGRITY TEST SHALL BE PE:RFORME:D. PER ~E:CTION 8,1.~ OF TH.E SAFETY ANALYSIS REPORT.

(1[). LABEL TO BE MACHINED ENGRAVE, IMPRESSION STAMP, OR EQUIVALENT, CHARACTERS 3/8-INCH HIGH MINiMUM, I

[]D AN ANNULAR REGION OF LEAD UP TO 112. INCH SQUARE MAY BE REMOVED ADJACENT TO THE WELDTOPREVENT LEAD 7

SEEECNN0.1910-0t-01,SARR6~E1

.* CONTAMINATION. *sPACE fylAY BE FIL~ED)NITH CERAMIC ROPE QR EQUIVALENT. fl.WELD BACKING.BAR MAY BE USED.

e 28, EXCEPT AS iN016ATED,ANO EXCLUDING SEAL, TACK, -AND INTERMITTENT V\\/ELDt AND ASSEMBLY: A4, ALL VI/ELD$ SHALL BE 6

S.EE ECfll NO: 191q:1J1~01-SARR5.J:1, E2 & E~

LIQUID PENETRANT INSPECTED ON THE FINAL PASS IN ACCORDANCE WITHASM CODE;.SECTION Ill, DIVISION 1,.

5

.SEE ECN NO;.191o.;01~01'-$ARR4°E1 & E2 SUBSECTION NF. ARTICLE NF-5000, AND SECTION V. ARTICLE 6, 4

SEEECNN0.1910::01"l>1-8ARR3,.I;1.

llD LEAD SHEETS.SHALL BE ULTRAsONICALLY INSPECTED TO ENSURE NO VOIDS GREATER THAN 10%0F SHEET THICKNESS.*

Orano Federal Services 3

SEE ECN.N0.1910:01-0:1,.$ARR2,-E1 SHEETS SHALL FILLTHE.CAVITY AND BE TIGHTLY FIT AND FORCEFULLY INSTALLED'. ALL.REMAINING GAPS SHALL BE NOV 14 2018 i

SEE ECN NO, 1910~01-01..SARRhE:'1 PACKED.WITH FITTED LEADSCRAPS0RC0MPR£:SSEO LEAPWQOL.

[]Q:) THREADIN$EJUSARE OPTIONAL.

Records Management f

.SEE ECN N0.<1!i10~01,-01~ARRO-E1 REV I

DESCRIPTION QD INSTAL.L ITEM 3i (Pi!:'~) AFTER FINAL CU::5$1,JRE: ~LD OF SHIELD PLUG C:OMPLETED.

. REVISION HISTORY

32.

FOR UNDIMENSIONED FILLET WELDS, Ti-IE MINIMUM FILLET WELD.LEG $1ZE IS EQUAL TO THE THICKNESS OF THE THINNER NAMEiSIGNATURE

. DATE

Q; Orano i=Jderal ServicesLtc BASE METAL BEING JOINED.

. *. Packwng Projeqts...

[ID SPACERS, MADE FROM 12-GAUGESHEET METALJIIN 2~, ARE LOCATED.AS REQUIRED AROUND OUTER SHELL OD TO Ol"(lilQ feq~r:c\\l. ~Yi WA 98003 MAINTAIN.GAP BETWEEN THERMAL SHIELD.AND ASK ODY. SPACERS MAY BE ATTACHED USiNG CONTINUOUS OR 6

A INTERMITTEN! FILLET WELDS.

EM hf.

• fJ'If.'f,n;.*,,fD.' Mia;,."' ll/f'oue DWGTni.E BRR PACKAGE ASSEMBLY A

[ID PLATE THICKNESS GREATER.THAN THOSE SPECIFIED IN THE l:.IST OF MATERIAL MAY BE USED IN ORDER TO ENSURE RE

~ " Ve,.i'S /Y/.u"':/':,1/.MA. il/ls/lK THE MINIMUM MILL PLATE THl<;;KNESS AFTER MAC:f!INING, I

. TECHCHK I~,,,,.:ss.,f"'a};/_j'/~ tl/,'i/1.f SARDRAWING.

,NA NA D.FTGCl:{I(

...... u,,.,;,..:r.r.~ ttA~/t'T

35.

WEATHER.SEAL MAY BE.INSTALLED BETWEEN THE BRR CASK ASSEMBLY,(ITEM A2) AND'THE LOWER IMPACT LIMITER SCALE: NOTED Im,-:, LBS ASSEMBLY(ITEM 2);

NEXTASSY FINALASSY* DRAWN Q.tE

11/121201 B

~NE!Ol fflANCE§;

REV:

1.

!SHEET 1 OFS THIRD ANGLE PROJECTION

!l!lt!!ll§ OTHERWJS11 seii!EJ1,0c FRACTION ~ 11,i 2 PLACE OECIMAl tJ)6 (CONTINUED ON SHEET 3)

ANGLES t 2'

• I PLACE DECIIMI. £.2 DWG DWGNO.

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. $1!.. TOLEMNCES PER ASME Yl4.e:-7.cl09 l!'llil,Q.! FIJR~IEQ TQbERAN¢§~;

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I f

I I

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. IIJWG, JOOIZ75*007 8

7 6

5 4

3 2

1

8 C

B A -

8 7

6 5

ASSEMBLY SCALE:1/8

~

7 6

5 4

4 3

3 DWGNO 1910-01-01-SAR R7 SH 2 REV: 7 SHEET 2 OF 5 DWGNO.

1910-01-01-SAR 2

D C

B A

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8 7

6 7

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[ID SCALE: 1/1 4

A4 A3 A2 A1 32 1

3 1

AR AR 16 8

32 64 8

8 16 8

8 4

ITEM NO 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 3

DWGNO 1910-01-01-SAR R8/7 SH 3 1

LIST OF MATERIALS (CONTINUED)

PART NO DESCRIPTION SPECIFICATION PLATE, 1/2 THK ASTM A240, TYPE 304 PLATE, 2.0 THK ASTM A240, TYPE 304 KNH813J HEAVY DUTY INSERT; 1/2-13UNC-2B X.7 LG KEENSERT OR EQUIV PLATE, 1 1/2 THK ASTM A240, TYPE 304 PLATE, 3/8 THK ASTM A240, TYPE 304 BAR, RD, 1.5 DIA ASTM A276, TYPE 304 PIPE, 3/4 SCH 40S ASTM A312 OR A376, GR TP304 EXPANDED SHEET, 3/4 #13 ASTM F1267, TYPE I OR TYPE II CLASS 3 SHEET,.135 (10 GA)

ASTM A240, TYPE 304 SEAMLESS TUBE, 01 OD X.25 WALL ASTM A511 GR MT304 ANGLE, 1 X 1 X 1/8 THK ASTM A276, TYPE 304 PLASTIC PAD ACETAL FLAT HEAD SCREW, 1/4-20 UNC-2A STAINLESS STEEL PAD,.5THK FOAM RUBBER SHCS, 3/8-16 UNC-2A STAINLESS STEEL FLAT WASHER, 03/8 NOM.

STAINLESS STEEL LOCK WASHER, 03/8 NOM.

STAINLESS STEEL HEX NUT, 3/8-16 UNC STAINLESS STEEL XPANDED METAL.

CE OF ITEM HAS SIVE DESIGNED PE TARGETS ONLY.

D TO EDGE STRIPS REV: 7 SHEET 3 OF 5 DWGNO.

1910-01-01-SAR 3

2 D

C B

A

C B

A e

8 8

7 7

6 6

5 5

-.z----.4 4

3 3

2 DWG NO SHEET 4 OF 5 1910--01-01-SAR D

B A

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4 3

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1910-01-01-SAR 7

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SECTION F-F REV: 7 SHEET 5 OF 5 SCALE: 1/2 DWG NO.

1910-01-01-SAR 8

7 6

5 4

3 2