ML20050C780

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Assessment Rept,Spent Fuel Storage Rack
ML20050C780
Person / Time
Site: Zimmer
Issue date: 04/07/1982
From: Chew G, Javid A, Voutyras M
NUTECH ENGINEERS, INC.
To:
Shared Package
ML20050C776 List:
References
CGE-03-218, CGE-03-218-R0, CGE-3-218, CGE-3-218-R, NUDOCS 8204090349
Download: ML20050C780 (11)
v • d • e


Text

_________ _________

s NUTECH CONTROLLED CGE-03-218 00Pi' NO.

I 33 803 0952 Revision 0 ss so EXHIBIT G 1

i Assessment Report Spent Fuel Storage Rack For Wm. H. Zimmer Nuclear Power Station Prepared by:

NUTECH San Jose, CA Prepared by:

Approved by:

Mad N G. P. Chew Mark Voutyras Engineering Analyst Engineering Manager Checked by:

Issued by:

/

V V

f A. Javid V. J. Brocato, P.E.

Project Engineer Project Manager I

8204090349 820407 n ed PDR ADOCK 05000358 A

PDR

s Introduction Sciemic analysis of the Spent Fuel Storage Rack was performed The two NRC concerns for the purpose of SQRT requalification.that the overturning moments in the that the seismic restraints were not considered in the waro 1)

In addition to these concerns, NUTECH has 2) original analysis.cico addressed the effect of added hydrodynamic mass of the water surrounding the racks.

i Mnthod of Analysis i

Annlysis of Spent Fuel Storage Rsck was composed of two parts.

The modal In the first part a dynamic analysis was performed.

cuperposition method using acceleration response spectra, was j

utilized and the dynamic loads on the system (shears and j

were calculated using the computer program STARDYNE.

moments) the calculated loads were utilized to In the second phase, obtain the stresses at the critical parts of the assembly.

c The rack was modeled as a finite element model as shown in The simple components of the rack justified the use of only a beam element with six static degrees of freedom Figure 1.

and three dynamic degrees (translations only).

A sufficient number of nodes was included in the model to obtain an accurate j

representation of the system and to extract all applicableSeismic su j

frequencies.

The effect of the surrounding water appropriate nodal point.and other racks was simulated by adding a uniformly dist I

This added mass was con-mass in both horizontal directions.

corvatively estimated by assuming that only one rack is free In dynamically while all surrounding racks remain stationary. act l

j multi-member arrangement.

i Results and Conclusions R3sults from the modal extraction, along with the response j

cpectrum used in the dynamic analysis, are shown in Appendix Resulting dynamic loads (also Appendix A) were used to calculate stresses in five critical areas, as summarized in A.

The only critically stressed area was found to be It is shown to be 1.6%

Table 1.

the bolt pad of the base supports..However, it is considered acceptable because e'

over stressed.

of the amount of conservatisu that was used in calculating the water mass which is directly proportional to this stress.

An additional stress calculation was made on the cross bracing numbers to validate the assumption that the vertical columns act together, enabling the rack to be modeled using a simple This stress is shown to be well within the stick model.

allowable.

nutech

By using a six degree of freedom model and the appropriate restraints NUTECH has considered both NRC concerns mentioned above.

In addition, NUTECH has considered additional loading due to the hydrodynamic mass of water surrounding the racks.

Dynamic analysis was performed using the appropriate response spectrum.

All stresses were calculated to be within accept -

able limits.

This analysis demonstrates that the Spent Fuel Storage' Racks for the Zimmer Nuclear Power Station will main-tain their functional integrity if subjected to seismic events.

O nutech

~

Table 1.

Summary of Stresses

-Maximum Allowable Component (Stress Type)

Stress (PSI)

Stress (PSI 1

Column and End Channel qHFp (Combined Bending & Axial) 3179 31000 (Shear )

256 31000 Column-base Weld (Combined Bending) 6438 20000 1

(Shear )

767 20000 i

c, y

Column-divider Weld E-W (Combined Bending) 4141 20000 (Shear) 875 20000 b-N-S Bolt Pad (Bearing) 16262 16000 Base (Compression) 5354 21000 Figure 1.

Finite Element Model 3C GO 3-

Appendix A 1

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... :. : 6 nutech

't EXHIBIT "H" Response to Zimmer SQRT Audit Specific Open Item Part A (b).

A list of Non Essential Devices on the Reactor Core Cooling Benchboard (H13-P601) are as Follows:

NAME MANUFACTURER IDENTIFICATION (PPD #) MODEL #

Fuse Cartridge Bussman 145C3039 M/N-1,2,3,5,10,15,20,25,30 Register 145C3232 Switch General Electric 145C3040 CR-2940 Meter Panel General Electric 157C4545 &

Type 180 Vertical (Ammeter, Voltmeter) 163C1746 Edgewise Meter Recorder Bailey 193B1484 732232BBAAlWAB Resistor Ohmite 234A9775 0777 Controller Bailey 248A9393 701002AAAAl The Non-Essentiality of These Devices Were Established by the Non-Essential Classification Shown in GE Electrical Device List (EDL) for Reactor Core Cooling System Benchboard (H13-P601)

(Document No. 328X227TU Rev. 24) for Zimmer.

  • To Meet Military Standard ZPL-18546-25 By Various Manufacturers.

T 1

J 1

i EXHIBIT "I" Justification of Reduction Ratio The magnification factor of the rack (Q ) is conservatively R

estimated as a single degree of freedom system with center of gravity at the rear, see reference. The Alarm is mounted within the rack, and has a center of gravity (C.G.) more toward the front. Thus, conservatively estimating the alarm center of gravity (C.G.) at one third (1/3) the depth of the rack, means that the alarm experiences a factor of three less mag-nification of acceleration.

RACK X

9CG " D 9R D

ALARM A

CG

//////

Reference:

Nutech Calculation, Bailey Alarm (745) in Rack (7610)

Acceleration dated 6-11-81

A IACHVENT I

(

l

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