ML19257A862

Suppl Cask Drop Analysis for 15-Ton Cobalt & 7.5-Ton Treat-II Casks

ML19257A862
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	04/21/1977
From:	BECHTEL GROUP, INC.
To:
Shared Package
ML19257A861	List: ML19257A860 ML19257A862
References
NUDOCS 8001090250
Download: ML19257A862 (17)

Text

{{#Wiki_filter:-- ,l 3 I.e t g j.: e } BIG ROCK POINT NUCLEAR PLANT ';jk [ (-f SUPPLEMENT CASK DROP ANALYSIS l ef FOR [ 15 TON COBALT AND 7% TON TREAT-Il CASKS I @(N f c& l i f f. b{ rr t ? 94 t h E. i f FOR WORg>avse;M OMj ~ ~ M l { BECHTEL ASSOCIATES PROFESSIONAL CORPORATION ..n{ ANN ARBOR, MICHIGAN l APRIL 21,1977 E g$ 1706 341 ii ?r 3[. MO b 8001000 r: t

e t l TABLE OF CONTENTS SECTION DESCRIPTION Sl.0 U1TRODUCTION S2.0

SUMMARY

S3.0 CASK DROP ACCIDENTS 9 S4.0 EFFECTS ON STRUCTURAL INTEGRITY a S

5.0 REFERENCES

i i APPENDIXES A HANDLING PROCEDURES ?> Ir LIST OF FIGURES I f S3-1 CASK ROUTING AREA, PLAN + 4 S3-2 SECTION A-A S3-3 SECTION 3-B p S3-4 SECTION C-C e M ?) S3-5 SECTION D-D " [j J t .s' g; i ,g I a. 'i. t . ). t-l V. \\ -I O 'o ~5 [ ?)- ,r 7p f, + r; 4 1706 342 S-1 [ s [ u

a r l I Sl.0 INTRODUCTION This report is a supplement to the report " Big

• Rock Point Nuclear Plant, Evaluation of Postulated Cask Drop Accidents; May, 1974",

i which was made by Bechtel Power Corporation, San Francisco, [ California. ( \\ The May 1974 report made the analysis for the postulated drop of the i i following casks: 2 ) YW i I D . g% I 1) 60 ton spent fuel shipping cask <f (4)

• s' I

r e 2) 24 ton spent fuel transfer cask (.MM f t gV* l 3) 15 con cobalt shipping cask h 4) 7 ton treat-II cask t- ?- The results and proposed equipment modifications were largely con-trolled by the 60 ton spent fuel shipping cask. E e W This report discusses, in particular, the postulated drop of the 15 5-D ton cobalt shipping cask and 7h ton treat-II cask. In evaluating i the cask drop accidents, the present handling system and current i F handling procedures are used. The present cask handling route is g; 1706 343 Sl-1

C. f, g'c shown in Figure S3-1, and Appendix A contains the current handling 1. 'd proc edur es. It is assumed that the handling procedures would con- '. t ! L, servatively control the cask route and its postulated height of

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drop. f This report includes the effects of the postulated cask drops on y_. the integrity of impacted structures such as an evaluation of the capability of floors subje.it to cask drop to protect the safety related equipment and systems located beneath the floors. The l consequences of damage to safety related eqitipment and potential radiological effects are not within the scope of this report. I j This report utilizes the findings of the May 1974 report as applicable to the 15 ton cobalt and 715 ton treat-II casks. l k ute[3 .yObl OAjl v h 1706 344 Sl-2 1

4

c S2.0 SIMfARY

?:4 'l The postulated cask drops would cause the following failures: I' 's

7..:.4 a) 15 ton cobalt cask: The 30 inch floor slab at elevation t

if, 621'-0" (decontamination room) and 45 inch slab at eleva- ,] tion 599'-5" (just southeast of equipment lock) would be 2 ,f penetrated. -f Y ? y[ b) 7 ton treat-II cask: The 30 inch floor slab at elevation

• 3 621'-0" (decontamination room) would be penetrated.

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3 ? J S3.0 CASK DROP ACCIDENTS -5 c ' i To determine the postulated cask drop locations and the casks' mode -Q of drop, the current handling procedures and route of travel for 5 0, a the 15 ton cobalt and 7h ton creat-II casks have been used. } Appendix A contains the handling procedures while Figures S3-1 . ? through S3-5 show the cask route, 4 T. 3 0 2 The 15 ton cobalt cask and 7 ton treat-II casks are handled by b - 3 the Containment Single Leg Cantry Crane - 75 ton capacity. The - 7 m 1 minimum factor of safety for such an operation is 20. This factor I of safety and strict supervisory controls, while moving the casks j within the containment, make cask drop accidents a very reaote p + .C2 7 probability. Factor of safety for the yoke is not available at %a ! '[ this time. cs g 1 srp _r gen y Nevertheless, consistent with the mode of handling the casks, the on 'n following cask drop accidents are postulated. d,.m p.o a - g + { n f "N P I 1 L Between the equipment lock area and the decontamination area at i fj! El. 632'-6" (as defined in the handling procedures - Appendix A), I I l the casks are moved horizontally, with longitudinal axis in the c 2 East-West direc tion. I Two types of cask drop accidents may be D j postulated in this area. First is that the casks drop sidewise i 1: h L [u with their axis in the east-west direction. The second is that O { one end of the four pronged yoke could fail or that the casks v Ny s I 1706 346 i5 y tip off a structure and the wire rope at the pulley block breaks, 4 y ft in which case the casks fall endwise. ~ $ 53-1 y

1 X t

n Between the decontamination area (a t El. 632'-6") and the cask

?g' loading area (in the southwest corner of the Spent ruel Storage If t

A Tank), the casks are handled in the vertical position. Endwise cask drop accident along with tipping on the fuel racks may be

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postulated in this case. /(* 'l. 3

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.,-m t I t ls T S4.0 EFFECTS ON STRUCTURAL INTEGRITY P } E i Structural integrity of the different elements has been checked (' F for the cask route shown in Appendix A. Cobalt and the treat-II casks travel the same route. i ). b' 'I Casks have been postulated to drop at seven different location s 4 h along their travel path. As discussed in Section S3.0, the casks t

j j.

[. may drop endwise or sidewise. Where endwise drop is possible, i 3 the structure is analyzed for this drop and the horizontal drop

3 of the cask is omitted. The sidewise drop of the cask will always be less etitical as conpared to the endwise drop due to the additional area of contact during impact. Figures S3-1 y

.' l thru S3-5 show the various locations and modes of the postulated A s!i J h vs-> h E cask drops, while Tables S4-1 and S4-2 summarize the structural ,g response for those drops. h !' f [ .re ' j.,[ s f d @' )' Y-Table S4-1 categorizes the structural capability to withstand ) the postulated drops of the 15 ton cobalt cask. The floor slab at itjj l( elevation 621'-0" of decontamination room (drop nunber 4) would I-r be inadequate in shear and bending, and the cask would penetrate }ff g the slab. The slab at elevation 599'-5" between equipment hatch k. e T> and the decontamination room wall would be inadeque.te in shear ,4 'i If while the supporting wall below does not have sufficient bearing ( 'I capacity to stay within the allowable ductility limit. t The cask y would also penetrate the slab. i

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3 o 3 q. i 1706 348 y S4-1 [ 65 8 fd I. L

L ! ( F Table S4-2 sucrnarizes the structural integrity results for the {' postulated drops of 711 tc, treat-II cask. Floor slabs at elevation 621'-0" of decontamination room (drop number 4) would f fail in the similar mode as is discussed for the cobalt cask. io i. In addition to the structural failures that are noted in ( "M t Tables S4-1 and S4-2, the following local effects are common C { to the postulated drops of cobalt and treat-II casks. k i mern [ e> ob l a,rq a) The drop of the cask would violate the integrity of the Q l liner plate in spent fuel storage tank, however, water b f p s J sakage would be limited to seepage through the concrete. M P = 4 anci ) I b) The 4" $ redundant core spray line could be damaged by the I, drop of either cask. Postulated drop number 7 would have negligible effect on the structure. m ~ r &s l c 7". i 4 I Uhile making the evaluation of the postulated cask drops, only the I first most evident point of impact on the structure is analyzed. t i l The chain effects af ter the structural failure or the rolling of f k the casks to other points of inpact have been omitted. The most p evident failure in such a case vculd be that of the hatch in the i, floor slab at elevation 599'-5", junt southeast of equipnent lock. 6 If the cask drops from the operating floor (elevation 632'-6"), I ) 6 it would penetrate the hatch. i h The tipping of the casks onto the fuel racks has been discussed A r in Section 6.0 of May,1974 report en the subject. 1706 349 .i s4-2 )

b 7 f7 T A V 4 lI g SS.O REFERENCES 4 k 9 e f h[ 1. BC-TOP-9A, Revision 2, Bechtel Topical Report, Design of ?' h Structures for Missiles Impact, September, 1974 k b } K 2. J. V. Rotz, Results of Missile Impact Tests in Reinforced Concrete Panels, Second ASCE Specialty Conference on a ? Structural Design of Nuclear Plant Facilities,1975. I h. f [ 3. Norris, C. H., et al, Structural Design for Dynamic Loads, 5 t

• I' McGraw Hill Book Company, Inc., New York, New York,1959.
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/ l 4 .I Timoshenko and Goodier, Theory of Elasticity, McGraw Hill N h Book Company, Inc., New York, New York,1951. .c I $ 1 5. T-2 Cask, General Electric Drawing No. 919D755. 3 1 N y' ' 6. Cobalt 60, Shipping Cask, O. G. Kelley & Co., Inc., Boston, Massachusetts, Drawing No. 67-0442-1. .? ' 4 4 F t. I! L L. u. .f e?:)=$* ' d g a

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• ALLOWABLE DUCTILITY CABLE CASK WEIGIIT CASK DROP HEIGIIT IN VELOCITY DUCTILITY RATIO RATIO STRUCTURE C DROP (k)

AIR WATER TOTAL AT IMPACT RATIO ATTAINED (4 s FAILURE O NO. (ft) (ft) (ft) (ft/sec) f( a , (( s (. c. a 1 15 3.0 28.4 31.4 39.0 1.3 (1.0 (1.0 No 2 15 1.0 1.0 8.02 1.3 (1.0 (1.0 No 3 15 1.0 1.0 8.02 1.3 (1.0 (1.0 No 4 15 6.67 6.67 20.7 26.3 27.3 1.04 Yes 5 15 17.5 17.5 33.6 1.3 (1.0 (1.0 No 6 15 8.58 8.58 23.5 20.0 10.6 0.53 No 7 15 No structure failure, damage to 4"O redundant core spray line. For the mode of cask drop and the structure impacted, see Figures S3-1 to S3-5. i l i $m.,l,l b a niu:M,n n m p".d ry }p""Y 2 n e r.m ? l U/ i; U L ~4 2 h*

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