ML20204F867

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Summary of 860722-23 Meetings W/Nuclear Assurance Corp (NAC) at Lll Re NAC Responses to NRC Initial Safety Review Comments on Proposed Topical Rept Covering NAC S-T Dry Spent Fuel Storage Cask Design
ML20204F867
Person / Time
Issue date: 07/31/1986
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-40 NUDOCS 8608060202
Download: ML20204F867 (9)


Text

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JUL 31 Ed6 Project M-40 MEMORANDUM FOR: Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety FROM:

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

SUBJECT:

MEETING WITH NUCLEAR ASSURANCE CORPORATION (NAC)

Date and Time:

July 22-23, 1986, 9:00 am.

Location:

Lawrence Livermore National Laboratory (LLNL).

Attendees:

See Enclosure 1

Purpose:

To discuss NAC responses to NRC staff initial safety review comments on NAC's submitted topical report (TR) covering the NAC S-T dry spent fuel storage cask design.

Summary:

For the two days of meetings NRC staff (including headquarters and LLNL personnel) reviewed with NAC staff the detailed responses NAC had made to NRC comments (by letter dated July 1, 1986 docketed under Project No. M-40).

These were supplemente'd by additional information (see Enclosure 2).

Proposed NAC changes to the cask design were discussed. A different cask basket design is to oa submitted in NAC's revised TR.

It will accommodate 26 pressurized water reactor spent fuel assemblies without reliance on burnup credit with respect to fuel basket criticality design.

Changes with respect to impact limiter design and shielding material use are being considered.

8608060202 860731 PDR PROJ PDR M-40

JUL 31 NE6 Leland C. Rouse 2

l There are no issues outstanding, precluding submittal of a revised NAC TR. A revised TR is expected in late calendar 1986.

omem47. swom E John P. Roberts Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and Material Safety

Enclosures:

1.

Attendance list 2.

Supplemental Responses DISTRIBUTION:

?,.. Project.M 40.s PDR NMSS r/f FCAF r/f JPRoberts FBrown Beveridge/ Cornell JSchneider I

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ENCLOSURE 1 ATTENDEES John P. Roberts NRC/NMSS Monika Witte LLNL Larry Fischer LLNL Ernest E. Hill Hill Associates Mark Mount LLNL John Genser NAC Bill Lloyd LLNL James Schneider NRC/NMSS Jerry Counts NRC/IE Alan Wells NAC Bo Woodhall NAC Tom Thompson NAC Martin W. Schwartz LLNL C. K. Chou LLNL l

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i ENCLOSURE 2 Project No. M-40 NUCLEAR ASSURANCE CORPORATION 07/01/86 4.8.1.3.2 Finite Element Model Description (Continued)

Question b.

More detail would be helpful in the description of the finite element model of the separate components.

For example, the bolts are said to be modeled with beam elements.

These elements should be identified in Figure 4.8-8.

Also, describe in detail how the interfaces is handled between these elements and the closure lid, and the cask body.

Also explain how the axisymmetric model deals with the bolt loads.

Response

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Project No. M-40 NUCLEAR ASSURANCE CORPORATION 07/01/86 4.8.1.3.2 Finite Element Model Description (Continued)

Question Explain how the " gap elements" describe the interface between c.

the lead and the inner and outer shells.

Response

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8.2.10 RESPONSE:

Tip Over Analysis

" Cask Vertical" For Case 5,

the applied seismic loads and subsequent calculations were incorrect.

More appropriately in accordance with Reg. Guide 1.60 the applied vertical ground acceleration is 2/3 of the.25g horizontal ground acceleration so that.179 is the vertical acceleration to the cask.

Correcting for these accelerations and re-analyzing; the free body diagram and calculations are as shown below:

A For Static Equilibrium:

J

.355GW(b)

(RM) Resisting Moment > (TM) Tipping Moment g

I RM = 39.72 W Jgy qu TM = 91 (.3536W) + 39.72 (.17W) = 38.93 W Sgg,

Y Since 39.72 W > 38.93W 353EL/ ;b RM > TM 3q,7g n W.th/

Since RM > TM the cask will not tip over for the combination of seismic loads as statically applied in Case 5.

.3536 W = ((.25W)2 + (.25W)2)1/2

= Resultant maximum horizontal ground acceleration load

e..

8.2.10 RESPONSE:

Roll Over Analysis

" Cask Horizontal" For Case 5,

the applied seismic loads and subsequent calculations were incorrect.

The resultant maximum horizontal ground acceleration is.35369 (vectorial sum of two normal horizontal ground accelerations of.259 each).

More appropriately in accordance with Reg. Guide 1.60 the applied vertical ground acceleration is 2/3 of the.25g horizontal ground acceleration so> that

.179 is the vertical ground acceleration to the cask.

Correcting for these accelerations and re-analyzing; the free body diagram and calculation are as shown below:

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,ggg_

For Statg)fquilibrium:

A

___.._. _(RM) Res@ ng Moment > (ROM) Roll Over Moment W

A

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RM=,fgg}

kW

/

75.2 6"

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._ _ __RM > ROM,r4 y

W.IiW

. _ H0y.i

_ g.,

=._. _.

Since RM > ROM the-cask-will not th foVe'rOfor the combination of seismic loads as statically ap' plied ine e..

.