ML20132G221

Summary of 850905-06 Meetings W/Nuclear Structures,Inc, Mitsubishi,Lll & Lowenberg Assoc,Inc in Livermore,Ca Re Mitsubishi Revised Rept on Dry Spent Fuel Storage Cask Design.Meeting Attendees,Agenda & Viewgraphs Encl

ML20132G221
Person / Time
Issue date:	09/20/1985
From:	Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
REF-PROJ-M-36 NUDOCS 8510010501
Download: ML20132G221 (34)

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r FC Central File j~ Project M-36 NMSS r/f PDR FCAF r/f LCRouse JPRoberts FBrown M-36 SEP 20 ISS5 FSturz JSchneider JSpraul

?iEMORANDU!! FOR: Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety FR0ft:

John P. Roberts Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety SU3 JECT:

f tEETING WITH MITSUSIStil HEAVY INDUSTRIES, LTD. (fili)

DATE A1D TIME:

September 5-6, 1935; 3:30 a.m.

LOCATION:

Lawrence Livemore National Laboratory Livemore, California ATTENDEES:

See Enclosure 1 PURPOSE:

To discuss firtI's submittal of a revised topical safety analysis report for the design of its MSF IV dry spent fuel storage cask (fomally the REA 2023 cask) for the storage of :; pent pressurized water reactor (PWR) fuel in ar. at reactor site independent spent fuel storage installation (ISFSI) (See Enclosure 2, agenda).

DISCUSSION:

In general, the discussion followed the agenda. After introduction of MHI (see Enclosure 3 and 4), cuality assurance was briefly discussed.

It was discussed in dstail in a subsequent meeting with the'Qcality Assurance Branch on Septenber 10, 1935.

Design changes have been nade to the REA 2023 PWR original design which will be incorporated in the MSF IV. Previous flRC staff cor.rients (letter to Ridihalgh, Eggers and Associates dated Ilovember 4,1933) on the original REA 2023 PUR cask design were reviewed, fill is preparing a revised topical report in response to NRC staff coments for submittal in early 1986.

0510010501 850920 PW

$D-6 John P. Roberts Advanced Fuel and Spent Fuel Licensing Branch

Enclosures:

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Agenda for Meeting Between MITSUBISHI HEAVY INDUSTRIES, LTD.

and NRC on September 5 and 6, 1985 September 5, 1985 1.

Opening remarks and presentation of MHI organization and communications chart - H. Lowenberg (5 minutes) 2.

Introduction of MHI-NSI technical team and MHI interest in NEC approval of MSF-IV for storage - H. Nakamoto (15 minutes) 3.

Presentation of MHI capabilities and resources Video tape and movie - (45 minutes)

Documents - (5 minutes) 4 Brief presentation of MHI CA Program / Plan for MSF-IV -

M. Kudoh (10 minutes) 5.

Discussion of principal design criteria - H. Lowenberg and MHI-NSI technical team - (30 minutes) 6.

Discussions on design corditions, i.e.

radiation protecticn, site conditions, installation, etc. - H. Lowenberg and MHI-NSI technical team -

(1 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) 7.

Lunch Break - (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 8.

Discussion of key NRC questions and MHI approach to providing responses for accident analyses - H. Lowenberg and MHI-NSI' technical team - (1 - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)

============================================================

September 6,1985 9

Review of discussion on September 5, 1985 - further clarification H. Lowenberg and MHI-NSI technical team - (

• o 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) 10.

Review of docket M-36 project - H. Lowenberg (1-hour)

MHI's schedule for submittal of revised TSAR NEC projection for review and approval Availability of data from DOE demonstration and tests NRC comments 11.

Plans for next meeting with NRC (15 minutes)

Cuality Assurance TSAR 12.

Closing remarks from MHI - H. Nakamoto (5 minutes)

Video tape - (20 minutes)

Organizational Structure and Communication Chart for Mitsubishi Hearf Industries, Ltd. (MHI)

Docket Files M-36 and M-33 Nuclear Regulatory Commission-Mitsubishi International Corp.

Lowenberg Associates, Inc.

MHI, Tokyo Headquarters l

l' MHI Takasago i

i Institute MHI, Kobe Mitsubishi Atomic Power Industries i

I Nuclear Structures, Inc.

Organization Function MIC-Washington Liaison LA (Lowenberg Associates)-

Agent MHI head office Official Capacity for application (Nuclear Waste Management Eng. Sec.)

MHI Kobe (Kobe Shipyard & Engine Works)

Overall responsibility for MSF-IV Cask Nuclear Plant Equipment Designing Sec.

Engineering

- Nuclear Plant QA sec.

Quality Assurance MHI Takasago Institute Technical Advisor MAPI (Mitsubishi Atomic Power Ind.)

Vendor NSI (Nuclear Structures Inc.)

Analysis g.

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~u CAPABILITIES OF DESIGNING AND MANUFACTURING OF SHIPPING CASK IN MITSUBISHI HEAVY INDUSTRIES (MHl) l 1

MITSUBISHI HEAVY INDUSTRIES, LTD.

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CONTENT i

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- i Page

' O SPENT FUEL SHIPPING CASK -- -

--- 2

- - - - ~ ~ -

i OSPECIAL TESTING AND DEVELOPING PROGRAM CARRIED OUT BY MHI ----- ---- 9 t

h O MHi CASK DEVELOPMENT VIEW --- --

- -- ~ ~ --- 1 2 O EXAMPLE OF DESIGN AND MANt9FACTURE J

---~~-~~-----~~1S I.

O ORGANIZATION CHART OF SHIPPING CASK FABRICATION 2S O LIST OF MAJOR FACILITIES ON HEAVY COMPONENT SHOP --

-27 IN KOBE SHIPYARD & ENGINE WORKS l.

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OUR EXPERIENCE IN THE SHIPPING CASK FIELD From the first half of 1960's, we, Mitsubishi Heavy industries, Ltd., have been involved in the development of designing and manufacturing in the cask, toget!ier with the safety licensing application service.

Up to the present, we have manufactured and constructed numerous nuclear facilities including nuclear power plants and the nuclear fuels, and with this accumulated technology as a basis, we are now aiming to design and manufacture the shipping cask that coordinates nuclear power plant and nuclear fuel.

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SAFETY ANALYSIS As for safety analysis of the shipping cask, overall correspondence in broad fields is required, such as structural, thermal, sealing, shielding and critical analysis together with l

its manufacturing and inspection.

Safety analysis is now carried out based on abundant, high-level technology that was experienced in the designing of nuclear power plants.

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TESTING AND RESEARCH-To evaluate the safety of the shipping cask, it is necessary to carry out its analysis and i

various demonstration tests, model tests and basic researches in material and welding, etc.

At our company, these tests are carried out at Takasago Technical Institute which is our main laboratory for research relating to nuclear energy.

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P MANUFACTURE 1

As the shipping cask contains spent fuels or radioactive materials, it is necessary i

that the technology of manufacturing and quality control should be highly reliable.

For years, we have been manufacturing not only heavy components for nuclear power plants, but also numerous vessels and core internals for reactors at our factory l

I exclusively for nuclear energy.

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Also, our broad experiences based on technology acquired from manufacturing and i

j quality control is applied to the manufacturing of these shipping casks.

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. SUPPLY LIST 4

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Japea Alemar (aergy Reserch Deegneng & Menutecturerig of spent f eet Shopeg I-E. IM

gagg, Ceek for JRR2 Coneept Des f

4...p.at.sa of 100 Tea & So.e.en Ctese C-e - ;~~ -

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.e.op, C.e Dem.a.traw

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I Dernenetteten Test of $heggerg Coe ter Demonese 1

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teen Transportemg Serve 40eage Cape,as ter psucteer glu) len house wel 1

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Desceng and Menufacturing of Depag Coe for fan howe vel Tenaceries steem Generator tepectea f te l

g, M4msees Moevy fadweeroe, Ltd IW*4 *e'l M*weec hehg ef 5hdevine Cat for g

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fea have vei feene.orice Survoitience Cepen,ie ser esweiser menctor.

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• P P"ri't b P6"ci'*t F"'i Demeremeten Test of TPig t2t f ree Shapetag 6^

Coe ter treaepertes Fresh Fue of Jveve.

W De=coomeat Cerpeetoa 4

Demmetreten feet of 90 fea Ctes koseg Ca.

Centres sence lanemste of 7.

fleces Pe*er andwetry

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Ceaves meneeren saevieuw et Meaufersure et to ten Cies Depeng Coe for i

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Demeaseem tem tascoe Pe=er taewury I

i Ceawm Aeee th tasteve of Dee.pseg of 100 Yea Class Cask fe Demoncrenaea 8

lieese Deaer tadweery f eet for teensportes Lam teres *we 1

Cenes menerch tassevis of Demonenstea f eet of to Ten Clee Depeg Coe J

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Eleces Pe=or sadverv (Pesegureneestence f eet 3pw /em )

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fae, itsceasel WS-I free lhopeg Cee.

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Jacan Nc eso $mp Concept Dea gn of Spen 2D Nsaarca and De.esooment

'M4 Fw $Nomag Casa for Age 9c y Nuclear $J%p 'M/su' Technical Evatwanon et PEA Cews: 4 search est<tute Type Transoortame Srcrage or E ecinc Po.er inewstry Casa in Dry $1orage et B. %

Spene Fues 22l of E ectnc Power indvstry f

Tochtwesi Eve:vation of Dry l

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SPECIAL TESTING AND DEVELOPMENT PROGRAM CARRIED OUT BY MHI

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1. Basse Studies (1) F,. -" Characteristic Test of Various Shock Absortmie Materials for Shock Absorber Both statical and k sostic cssmpsession cheracteristics of the enam wooden maeoreal and plastic, etc., were obtained.

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(2) Wehleeg Studies of Copper Fins 6

A study was neede of tese usolding cordetsons when weideng copper fins to stainless steel or carbon stool.

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(3) High Temperature Strengeh Test of Lead i

A test was sumade useder hash temperature to obtain the tenssie strength of lead and the -,. - _" strength of lead I

when ceased inonde the can ased the castfacsont of friction.

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(4) Heat Transfer Per6ormance Test of the Inner Fiss A test was sumade regardang heat trans8er performance of the iriner fin for host transfer installed inesde of the high l

n.-s_..si

,s (5) E-

.t of a Highly Effectsve Neutron Shasiding j

Selecon rubber, a sieutron shameding maeorial with outstanding thermal rosastance and fere resistance was '--

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.i (6) Evahneeseen et Besniene Behaveor of Hegh eGolaciale Isoveren Sheeldung tentorial An asialysis senethod of hagli esielecaste suistorial Elled ineede colted weseel in Ere s es h.sh.d l'

(7) Evahnamen of Heat Trane8er Perloneiance in Spent Fuel Assembly under a Dry Horizontal j

and Verhcal Poestsen.

Pregoctag ene estableshment of an analyses senested of a mesesseessui rod tossiperatuse ter 1

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, deerifig a dry eterage.

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2. Stud.es for Practical Use (1) Demonstration test of MS 1 Type Shippeng Cask (2) Demonstraten test of Steam Generator Entraction Tube Shipping Cask (3) Fue Test of MSF-f Type Shipping Cask by a sectonal nxmfet (4) Conceptual desegn and detailed design of MSF-l Type Shipping Cask (5) Conceptualdesign of new type Shipping Cask for high burnup spent fuels (6) Study to irnprove fabricating process of leaf ring (Under study)

(7) tsodel test of kBSF-1 Type Shipping Cask (8) Denionstrahon test of New Type PWR fresh fuel Shipping Cask

3. Development of Analyses Code (1) CASH 11 CODE A shock absorber performance evaluatson cr* for the cask shock absorber based on the Unianial Displacement Method (2) FINPAC CODE An unpact characterestic evaluaten code of the circular fan.

(3) CAFAD CODE A cask kanetic response evaksaten code when an earthquake occurs at the time of stored en upright possten (4) CAPUC CODE (Under development)

I A penetration rewstance performance evaluaten code at the twne of cask penetration test (Drop Test II) 11 a

MHI CASK DEVELOPMENT VIEW 12

j MH1's cask has been developing with high technology experienced in PWR power i

'l plants.

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MHI recognizes casks are devices to link fuelcycle facilities each together. MHl can 1

design well-matched casks to these facilities with high technology experienced in nuclear l

l industries field.

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MHi will develop casks to meet new requirements from these facilities.

o High enriched fresh fuel shipping cask o

High burnup spent fuel shipping cask o

High level waste shipping cask 1

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MHI SITUATION OF CASK DEVELOPMENT i

OBJECTS SERVICES OBJECTS CASK TYPE MHI SITUATION I

I RAW FUEL UFs TIGER TYPE O

MATERIALS TRANSPOR-

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TATION RU,PU,MOX MHITYPE O

TRANSPOR-CONVENTIONAL FF RCC TYPE 9

FRESH FUEL TATION HIGH ENRICHED FF MFC-1 TYPE O

l CONVENTIONAL SF EXL.TN TYPE 1

i SPENT FUEL fPOR-SPECIAL USE MSF-I TYPE e

TRANSPOR-HIGH BURNUP SF MSF-I TYPE O

TATION-STORAGE HIGH BURNUP SF MSF-I TYPE O

TRANSPOR.

CONVENTIONAL SF MSF-y TYPE O

HIGH LEVEL TATION I

VITRIFIED WASTE MHITYPE O

STORAGE WASTE l

(RETURNED WASTE)-

LOW LEVEL TRANSPOR-VARIOUS MHITYPE 0

WASTE TATION WASTES i

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9: DEVELOPED O: DEVELOPING Q: INTERESTED i

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o DESIGN (1) MSF-I Type Shipping Cask MSF-l type shipping cask will be used to transport a leaker fuel, and a high burnup fuel assembly.

Detail design was carried out and Safety Analysis Report (SAR) has been completed.'

SAR has been approved by Japanese Competent Authority (2) MSF-il Type Shipping Cask MSF-Il type shipping cask will be used to transport new type high burnup fuel

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assemblies. Conceptual design was carried out.

l (3) MSF-I Type Transportable Storage Cask.

MSF-N type cask will be used to transport and storage high burnup fuel assemblies. Conceptual design was carried out.

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DESIGN AND MANUFACTURE (1) 100-Ton Class Spent Fuel Shipping Cask l

This was designed and manufactured in order to test and demonstrate the reliability of this cask, HZ-Type and EXL-Type now in commercial use.

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MSF-1 TYPE SHIPPING CASK SPECIFICATION (1) Package Type

B(M) Type Fissile Class I Package (2) Max. Weight

Abt. 45 Ton (3) Max. Length

6220 mm (4) Max. Width

1800 mm (5) Max. Outer Diameter of Main Body: Abt.1410mm (6) Cavity Diameter

Abt. 410 mm l

(7) Cavity Length

4800 mm (8) Burnup Condition (For PWR Spent Fuel)

(a)

Burnup

45000* MWD /MTU (b) Enrichment

Max. 4.2 wt%

(c) Specific Power

Max. 43 MW/MTU (d) Cooling Time

Min. 360 Days (9) Number of Units Housed : PWR: 1 Assembly

BWR: 2 Assemblies (10) Max. Decay Heat Power : Max.10.0 KW (11) Cavity Condition

Wet Type i

• This cask also has capability to contain more high-burnup fuel assembly (max. 56000 MWD /MTU).

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MSF-1 TYPE SHIPPING CASK (For Leaker Spent Fuel and High Burnup Spent Fuel)

Approved pac'Kage design by Japanese competent authority.

LOWER SHOCK ABSOR8ER

[(SS./Fw Plywood)

REINFORC_ED RING GAMMA SHIELDING NEUTRON SHIELDIN_G-EMBLY CANISTER (S.S.)

(C.1) 7 [(Leadi (Selecon Rubber)

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MSF-Il TYPE SHIPPING CASK SPECIFICATION (1) Package Type

B(M) Type Fissile Class 1 Package (2) Max. Weight

Abt.110 Ton (3) Max. Length

63OOmm (4) Max. Width

2500mm (5) Max. Outer Diameter of Main Body: Abt. 2SOOmm (6) Cavity Diameter

1240mm (7) Cavity Length

43OOmm l

(8) Bumup Condition l (a) Bumup

51000 MWD /MTU (b) Cooling Time

1 years (9) Number of Units Housed : 12 Assemblies (PWR)

(10) Max. Decay Heat Power : Abt.100KW/ Package (11) Cavity Condition

Dry Type (He Filler) 19

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i MSF-H TYPE _ SHIPPING _CAS_K_ (For New Type High Burnup Spent Fuel) T' LOWER SHOCK , ABSORBER NEUTRON SH:ELDING f2 / LID m Kn j UPPER SHOCK 1 '_' '~ J k~ l ABSORBER 'M- -~ $ j,, jf f h ~ ? ? gf$ s,,,,wiin&x /- v

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MSF-5iTPE TRANSPORTABLE STORAGE CASK SPECIFICATION (1) Package Type

B(M) Type Fissile Class I Package (2) Max. Weight

Abt.1 iO~ 120 Ton (3) Max. Length

5400mm (4) Max. Outer Diameter of Main Body: Abt. 2SOOmm (5) Cavity Diameter

1500mm (6) Cavity Length

42OOmm (7) Bornup Condition (a) Burnup

51000 MWD /MTU i

(b) Cooling Time

SYears (8) Number of Units Housed: 17-21 Assemblies (PWR)

(9) Max. Decay Heat Power : Abt.30KW/ Package (10) Cavity Condition

Dry Type (He Filler) i I

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[ t MSF E TYPE TRANSPORTABLE STORAGE CASK TRUNNION SECONDARY LID ( PRIMARY LID _ %.'O,,,R,l]/% b Q SEUSEbl0M '/ s y / h / r, t ,1NNER SHELL_ c NXUTRON SHiggg j f l l l r . OUTER SHELL / f 's m_A s N: i N - 9 \\sas2E2 %))' g; y 'jy auss/ v e

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100-Ton CLASS SHIPPING CASK SPECIFICATION (1) Package Type B(M) Type Fissile Class II Package (2) Max. Weight

Abt.105 Ton (3) Max. Length

6180 mm (4) Max. Width

3000 mm (5) Max. Outside Diameter of Main Body: 2500 mm (6) Cavity Diameter

1240 mm (7) Cavity Length

4590 mm (8) Burnup Condition i

(a) Fuel type PWR 15 x 15 PWR 17 x 17 BWR8x8 (b) Burnup, (MWD /t) 33000 36000 27500 (c) Enrichment, (%) 3.4 3.4 2.7 (d) Specific Power, (MW/t) 35 40 24 (e) Cooling Time, (day) 360 420 360 (9) Number of Units Housed

Max.12 PWR Assemblies (10) Max. Decay Heat Power 1

56 KW/ Package (11) Cavity Condition

Wet Type I

100-Ton CLASS SHIPPING CASK FUEL BASKET (PWR) ISSJdoral Plate)_ LEAD _

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BASE SHOCK ABSORBER PWR FUEL ASSEMBLY 's Y c'(S.SjFir Plywood) ~~ ~ ,y h'e#* N \\ VENT VALVE x BOTTOM PLATE _uo iSsi \\ / .q:s t (Ssi LID SHOCK AdSOR_BER g N (SSJFar Ptywood) I'3 TRUNNION -g-- y - i

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'{ N ^ 4.' ~ y THERMAL BARRIER Jy' TRANSPORT FRAn4E (C.S.) U,-\\ BOPPER FIN (Copper) ,~ '\\lNSULATION (Firie Flex) f ' TRUNNION NEUTRON SHIELDING \\l./ (Selecon Ruboer) gS,gg I I 24 i l l

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LIST OF MAJOR FACILITIES ON HEAVY COMPONENT SHOP IN KOBE SHIPYARD & ENGINE WORKS l \\ i i 4 I

2 LIST OF MAJOR FACILITIES ON HEAV'l COMPONENT SHOP (1/2) l Equipment l Description O'ty Item 2

1. Shop Aree 45,000 m

2. Lifting Overhead Crane Capacity 450 ton 1

200 ton 2 120 ton 4 Others many

3. Forming (1) Press Capacity 6,000 ton 1

1,500 ton 1 Others 4 (2) Bending Roller Max. thickness 115 mm 1 Max. width 4,000 mm

4. Machining

' (1) Horizontal Boring Mill Spindie Dia. 225 mmd 3 Vertical Travel 5,500 mm Max. (2) Vertical Boring Mill Men. Work Dia. 11,000 mmd 3 Max. Height 6,000 mm Max. Work Weight 150 ton (3) Deep Hole Drilling 2-Spindle Hole Die. 25.4mmd 3 Machine (Gun Drill) Hole Depth 915 mm 3-Spindle Hole Die. 25.4 mmd 1 Hole Depth 800 mm (4) Planomatic Mill Width 6,000 mm (Longi. Edge Preparation) Height 3.475 mm 1 Length 8,500 mm

5. Heat (1) Fumace o 8mW x 8mH x 16mL 1

Treatment Load: 600 ton, Max. Temp.: 1200*C o 6mW x 6mH x 16mL 1 Load: 250 ton, Max. Temp.: 800*C o 6mW x 3mH x 10mL 1 Load: 120 ton, Max. Temp.: 1200*C o Others 4 3 (2) Quenching Bath 7mW x SmL x 6mD,6.7m /nr 1 (3) Induction Hester Capacity 160 KVA 15 m a==== 2 LIST OF MAJOR FACILITIES ON HEAVY COMPONENT SHOP'(2/2) l Equipment Description Q*ty Item

6. Automatic (1) Submerged Arc Welding Tandem Wire 1

Weiding Machine Welding Current AC 1,000A (With Manipulator & Max. Dia. 8,000 mmd Side Beem) Max. Thickness 500 mm Max. Length of Longi-Weld 9,000 mm (2) Nonle Welding Machine Max.Dia. 2,000 mmd 4 Min. Dia. 200 mmd Max.Thicknees - 300 mmd (3) Overley Weiding Machine Strip & Series Wire 10 Process Welding Current 1,200A (4) Electron Beem Weiding o Capacity 1,400mmdx9,000mmL 1 Machine Vacuum Max.10-4 Torr Power 7.5kW o Capacity 1 5,500mmW x 6,700mmD x 7,600 mmh Vacuum Max.10-8 Torr Power 45 kW (5) Hot Tig Welding Machine Max. Work Dia. 5,000 mmd 1 Max. Work Length 7,300 mm (6) Positioner 50 - 120 ton 5

7. Inspection (1) Radiographic Apparatus Source 120 Mov Linac (X Ray) 2 2,000 R/m/ min, Thickness Max.450 mm Others (Source X-Ray Co60, tr192) many (2) Ultrasonic Apperatus 9

(3) Magnetic Apparatus 13 (4) Testing Machine Universe' Testing Machine 5 Impact Testing Machine 2 Herdness Tester 4 - ~.,, ~}}