ML19312D292

Forwards Ames Lab Presenting Estimate of Statistical Parameters for McGuire Containment Design Variables.Requests Addl Info on Reinforcement Thickness & Size & Penetrating Shell Thicknesses for Equipment

ML19312D292
Person / Time
Site:	McGuire, Mcguire
Issue date:	03/10/1980
From:	Baer R Office of Nuclear Reactor Regulation
To:	Parker W DUKE POWER CO.
References
NUDOCS 8003240148
Download: ML19312D292 (4)

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' UNITED STATES g

p, NUCLEAR REGULATORY COMMISSION

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WASHINGTO N, D. C. 20555 k*..../

MAR IO M

' Docket Nos. 50-369 and 50-370 Mr. William O. Parker, Jr..

Vice President, Steam Production

. Duke Power-Company P. O. Box.2178 422 South Church Street Charlotte, North Carolina 28242

SUBJECT:

REVIEW OF NUCLEAR PLANTS STRUCTURAL DESIGN (McGuire Nuclear Station, Units 1 and 2)

On November 15, 1979, Dr. Sai Chan, NRC Staff and representatives of our con-sultant, Ames Laboratory, visited the McGuire Station'to observe and discuss the McGuire containment structure and design. As a result of this visit and discussion, our consultant has prepared an estimate of the statistical parc-meters for the McGuire containment design variables. These are presented in the enclosed February 12, 1980 letter to us.from our consultant.

It is requested that you review and comment on our consultants e-timates.

In addition, we need some additional details on the penetration for the containment vessel, in particular, reinforcement thickness and size and penetrating shell thick-nesses for the equipment and personnel penetrations.. These matters were dis-cussed with your staff on February 28, 1980.

Although this review is being performed on a gr seric basis outside of our review of your application for an operating license, we.vould appreciate a prompt response in letter fonn.

~ Your continued cooperation in this matter is appreciated.

Sincerely, O.

N'l Robert L. Baer, Chief Light Water Reactors Branch No. 2 Division of Project Management

Enclosure:

Letter From Ames Laboratory Dated February 12,.1980 ccs w/ enclosure:

See next pages 800324014s v

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.i l Mr. William 0. Parker, Jr.

MAR 111980

.Vice President, Steam Production-

- Duke Power Company 1

P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242 cc: Mr. W. L. Porter Duke Power Company P. O. Box 2178 422 South Church Street '

Charlotte, North Carolina 28242 Mr. R. S. Howard Power Systems Division Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 1

Mr. E. J. Keith EDS Nuclear Incorporated 220 Montgomery Street San Francisco, California 94104 Mr. J. E. Houghtaling

'NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Mr. Jesse L. Riley, President.-

The Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 J. Michael McGarry, III, Esq.

Debevoise & Liberman 1200 Seventeenth Street, N. W.

Washington, D. C.

20036 Robert M. Lazo, Esq., Chairman Atomic Safety and Licensing Board U. S.~ Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Cadet H.' Hand, Jr., Director

' Bodega Marine Lab of California P.-0. Box 247 Bodega Bay, California 94923 G

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Mr. William 0.~ Parker,'Jr..

" a i 11980 Vice. President, Steam Production Duke Power Company P. 0. Box 2178

'422 South Church Street Charlotte, North Carolina 28242 cc:

Mr.-W. L. Porter Duke _ Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina Ec?42 Mr. R. S. Howard Power S" stems Division Westinghouse Electric Corporation P. O. Box 355

- Pittsburgh,- Pennsylvania 15230 Mr. E. J. Keith EDS Nuclear Incorporated 220 Montgomery Street San Francisco, California 94104 Mr. J. E. Houghtaling NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Mr. Jesse L. Riley, Presidcat The Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 J. Michael McGarry, III, Esq.

Debevoise & Liberman 1200 Seventeenth Street, N. W.

. Washington, D. C.

20036 Robert M. Lazo, Esq., Chairman Atomic: Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Emmeth A. Luebke.

Atomic' Safety and Licensing Board U. S. Nuclear-Regulatory Commission Washington, D. C.

20555 Dr. Cadet H. Hand, Jr., Director Bodega Marine Lab of California P. O. Box-247-Bodega Bay,' California 1 94923-w

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x TMr. William 0. Parker,fJr..

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cc :: ~0 avid Flesichaker.-Esq.

21735. Eye Street,~N.'W.,

Suite 709

- Washington, 0. C. (20006

-; Richard.P. Wilson, Esq.

Assistant Attorney General State of South Carolina 2600 Bull Street

- Columbia, South Carolina. 29201-h-

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e~w lowa State University Arnes. Iowa 50011 11111eS laherator Energy G Mineral AesourcesyAesearch insnrure February 12, 1980 g

9 Or. Sal Chen Structural Engineering Branch Division of System Safety Office of Nuclear Reactor Regulation

. Nuclear Regulatory Com,lssion Washington, DC 20555

SUBJECT:

AMES 1.ABORATORY TECHNICAL ASSISTANCE TO THE DIVISION OF SYSTEMS SAFETY, NRR -

"A REVIEW OF NUCLEAR PLANTS STRUCTURAL DESIGN" (FIN NO. A-4131). STATISTICAL PARAMETERS OF DESIGN VARIABLES

Dear Or. Chan:

Enclosed please find our estimates of tre statistical parameters for the design variables for the Sequoyah and McGuire Nuclear Power Plants. Unless there is an objection, we intend to use these values in our best estimate and uncertainty analysis of the two plants. Please review these. Also, please send them to the appropriate officials of the two plants for their review and cwenent.

Please ask Duke Power personnel for more details on the penetra-tiens for the McGuire containment vessel, in particular, we need i

reinforcement thickness and size and penetrating shall thickness for the equipment and personnel penetrations.

Please send me copies of letters you send to TVA and Duke.

If you have any questions, please contact me.

Sincerely,

~

tw owell Greimann 1

Project Engineer Enclosures I

cc:, Delwyn Bluhm, Head, Project Engineering F. P. Schauer, Chief, Structural Engineering Branch l

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.c.a STATISTICAL PARAMETERS FOR DES IGN VARIABLES McGulRE NUCLEAR PLANT44 Standard Oesign-Variable Nominal Mean Toterance Deviaeion Raference Plate Thickness 3/4" 0.768

[*ff" 0.0092 1,2

[0.0k0 0.0085 11/16 0.703 l

0.0075 1/2 0.513 Ring Plate Length 1A 1A

+ 1/4" 0.083" 3

ancs Width Containment Plate 3

1

+ 1/8" 0.042" 4

Length Containment Pla te

~ Ib b

b - 1/8 0.042" 4

Width

+0 Containment Radius 690" 690" 1.5" 0.5" 4

Material Yield 32 ksi 35.2 ksi

-0 ksi 3.8 ksi 5

Material Ul timate 60 ks!

66.0 ksi si 7.2 ksi 6

0

References:

'(1) ASTM Standards,1979, Specification A20, " Standard Specification for General Requirements for Steel Plates for Pressure Vessels". Table 1.

(2) Telephone Conversation with Product Specialist - Plate Sales, Bethlehem Steel, stated plate overweights: ranged from 3 to 5 percent, on average.

(3) Same'as Reference (1) Table 6.

(4) Drawings and informaticn supplied by Duka Power.

(5) Galambos, T. V. and Ravindra, M. K., " Properties of S teel for use in f.RFD".

Journal of the Structural Divisien, ASCE, v. 104, No. ST9, Sept. 1978,_pp'lL55-Ik68.

.(6) Ravindra, M. K. and Galambos, T.

V., " Load and Resistance Factor Design of Steel".

Journal of the structural Division ASCE, v.

104, No. ST9, Sep t.

1978, pp 1337-1353.

_G 1

( e STATISTICAL PARAMETER FOR DESIGN VARIABLES c

9 SEQUOYAH NUCLEAR PLANT k

Desi gn variable Nominal-fean_

Tolerance on Reference Plate' Thickness 1"

1.277"

[*

0.012" 1,2

-0.0 1 3/16 1.212 0.012 j'3 0.011 1 1/16 1.08 4 j,'

O.01 I

l.02 3/4

, 0.768

~0'0$

0.0092

[,0 0.0085 11/16 0.703

j'y 0.008 5/8 0.639 1/2 0.Si3

[O$

0.0075 n

Plate length t' 1, b 1, b g 1/4

v.083" 3

1380" 1380" g 6.9" 2.3" 4

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Material Yield 32 ksi 35.2 kst

-0 ksi 3.8 ksi 5

Material Ultimate 60 ksi 66.0 ksi 0

7.2 ksi 6

Refarences:

(1) ' ASTM Standards,1979, Specification A20, " Standard Specification for ' General Requirements for Steel Places for Pressure Vessel's',', Table 1.

(2)

Telephone Conversation with Product Specialist - Place Sales, Sethlehem Steel, stated plate overweights ranged from 3 to 5 percent, en average.

(3)

Same _ as Reference (1), Table 6.

(4) - Orawings suppl led by TVA.

for use in tRF0".1459-l'+6o,.

.(5)

Galambos f the Structural Division, ASCE, v.T. V.'

and Ravinda.

M'.

K., "propert ies of s teel 1978, pp Journal o 104, No. ST9, Sep t.

(6) ;Ravindra, M. K. and Galambos T.

V., " Load and Resistance Factor Design of Steel".

Journal of the Structural Division ASCE, v.

104, No. STS, Sept.- 1978, pp 1337-1353.

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