ML20148H892

Forwards Request for Addl Info Re Topical Rept 7270-RP-16A51,Buckling Criteria & Appl of Criteria to Preliminary Design of Containment Shell for the Floating Nuc Plant

ML20148H892
Person / Time
Site:	Atlantic Nuclear Power Plant
Issue date:	11/06/1978
From:	Baer R Office of Nuclear Reactor Regulation
To:	Zechella A OFFSHORE POWER SYSTEMS (SUBS. OF WESTINGHOUSE ELECTRI
References
NUDOCS 7811150035
Download: ML20148H892 (5)

Text

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t Dis tri bution NRC PDR RPDenise W

6 1978 Local PDR

, RHartfield

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Docket File v ' ELD LWR #2 File IE(3)

RSBoyd JRBuchanan 3

Docket No. STN 50-437 DFRoss

'TBAbernathy DBVassallo-ACRS(16)

FJWilliams RLBaer Mr. A. P. 2echella.

RABirkel President JLee' Offshore Power Systems-RJMattson P. O. Box 8000 VAMoore 8000 Arlington Expressway JKnight Jacksonville, Florida 32211 RTedesco RDeYoung

Dear Mr.'Zechella:

RHVol1mer

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SUBJECT:

CONTAINMENT SHELL BUCKLING CRITERIA REVIEW

-(Floating Nuclear Plants 1-8) l We have reviewed your topical report

o. 7270-RP-16A51, " Buckling Criteria and Application of Criteria to Preliminary Design of the Containment Shell for the Floating Nuclear Plant," and find that we-are in need of some additional information which is described in the Enclosure. We have I

discussed this, matter with members of your staff and have arranged to meet with them in Jacksonville on November 16 and 17,1978.

We request that your response be'provided either as ar) amendment to the PDR or a revision to the topical report.

t Sincerely, Ccp Z _ - ' b y.

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

Enclosure:

Request for Additional Informa tio.n i

ces w/ enclosure:

See next page 7811150o3I

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Mr. A. P. Zechella P resider 4-Offshore Power Systems P. O. Box 8000 8000 Arlington Expressway Jacksonville, Florida 32211 cc:

Vincent W. Campbell, Esq.

Vice President & General Counsel Offshore Power Systems P. O. Box 8000 8000 Arlington Expressway Jacksonville, Florida 32211 g

Thomas M. Daugherty, Esq.

Offshore Power Systems P. O. box 8000 8000 Arlington Expressway Jacksonville, Florida 32211 Barton Z. Cowan, Esq.

Eckert, Seamans, Cherin & Mellott 600 Grant Street, 42nd Floor Pittsburgh, Pennsylvania 15219 Franklin H. Berry, Jr., Esq.

County Counsel County of Ocean P. O. box 757 34 Washington Street Toms River, New Jersey 08753 Anthony Z. Roisman, Esq.

Natural Resources Defense Council 91715th Street, N. W.

Washington, D. C.

20005 Dr. Glenn L. Paulson Assi; tant Commissioner State of New Jersey Department of Environmental Protection Labor and Industry Building John Fitch Plaza Trenton, New Jersey 08625 R. William Potter, Esq.

Miriam it. Span, Esq.

. Assistant Deputy Public Advocates 520 East State Street Post Office Box 141 Trenton, New Jersey 08625 p

Mr. A. P. Zechella cc: Mark L. First, Esq.

New' Jersey State Deputy Attorney General State House Annex Trenton, New Jersey 08625 Carl Valore, Jr., Esq.

Valore, McAllister, DeBrier, Aron & Westmoreland Mainland Professional Plaza 535 Tilton Road P. O. Box 152 i

Northfield, New Jersey 08225 Mr. Harold P. Abrams 9100 Amherst Avenue Margate, New Jersey 08402 Dr. Willard W. Rosenberg 8 North Rumson Avenue Margate, New Jersey 08402 Mr. John Williamson 211 Forest Drive Linwood, New Jersey 08221 Mr. Kenneth B. Walton Brigantine Tutoring 309 Twenty-first Avenue, South Brigantine, New Jersey 08203 Harold P. Green, Esq.

Fried, Frank, Harris, Shriver and Kampelman Suite 1000,.The Watergate 600 600 New Hampshire Avenue, N. W.

Washington, D. C.

20037 Nuclear Coordinator Office of Merchant Marine Safety Commandant (GMMT-4)

U. S. Coast Guard Washington, D. C.

20590

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Mr. A. P. Zechella

.cc: Mr. Mitchell. Attalla 4028 Ponce DeLeon Avenue Jacksonville, Florida 32217 Mr. Reg Crowder Jacksonville Journal P. O. box 1949 Jacksonville, Florida 32201 Sheldon J. Wolfe, Esq., Chairman Atomic Safety and Licensing Board U. 5. Nuclear Regulatory Commission Washington,.D.' C.

20555 Dr. David R. Schink Department of Oceanography Texas A. & M. University College Station, Texas 77840 Mr. Lest'er Ko' nblith, J r.

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

20555 Richard S. Salzman,'Esq., C airman Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 i

Dr. John H.. Buck Atomic Safety,and Licensing Appeal Board-V. S. Nuclear Regulatory Commission Washington, D. C.

20555 Mr. Michael C. Farrar Atomic Safety and Licensing Apoeal Board

11. S. Nuclear Regulatory Commission Washington, D. C.. 20555 Chairman Joseph M. Hendrie-Commissioner Victor Gilinsky Commissioner Richard T. Kennedy Comissioner Peter A. Bradford Comissioner John F. Ahearne u.

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%M ENCLOSURE FLOATING NUCLEAR POWER plant STRUCTURAL ENGINEERING BRANCH REQUEST FOR INFORMATION

1) The. stress analysis assumes that cutout reinforcement as pre-scribed by the ASME Pressure Vessel Code is sufficient to al-leviate stress concentrations.

How certain is this assumption?

What studies have been made to substantiate this claim?

1

2) The buckling analysis replaces the two-dimensional stress distribution by uniform stress distributions. These corres-

. pond to combined axial, circumferential and shear stress. The stress components at every point in the shell are comoared to the critical uniform stress values. While the effectiveness of opening reinforcement can also be questioned, more questionable is the procedure of replacing the variable geometry shell by a shell having uniform oroperties. What is the justification for this method? Why is not the stress analysis model also used for buckling analysis?

3) Capacity reduction factors have been defined on the basis of Koiter's asymptotic-imperfection sensitivity studies and assumed deformation amplitudes.

In the present study, the deformation amplitudes are taken as the maximum out-of-roundness values aermissible under the ASME Pressure Vessel Code, the shell thickness. With such a large " imperfection" the method is conservative.

Tne choice of amplitude is rather arbitrary, however, and may be too severe.

Lesser amplitudes may yield unconservative results since it is not at all certain that the ASME tolerances control all of the imper-i fections which reduce buckling loads. Why isn't aerospace industry experience in the form of empirical buckling criteria, NASA SP-8007, 8032, for example, used?

4) Dynamic reduction factors are in ouestion since the literature indicates that for axial load, the dynamic buckling load is at least 70.9% of the static buckling load of the imperfect structure.

Why, then, is the capacity reduction factor eoual to unity when the dynamic stress is greater than 1.42 (1/.707) of the static stress?

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