ML20069A339

Comments on Seismic Analysis of Reactor Internals, Matl Supplied in Rept Useful in Defining Mass & Stiffness Characteristics of Vessel Internals & Supports But Does Not Answer Design Question in NUREG/CR-0891

ML20069A339
Person / Time
Site:	05000000, Dresden
Issue date:	03/25/1980
From:	Stevenson T WOODWARD-CLYDE CONSULTANTS, INC.
To:	Jabbour K Office of Nuclear Reactor Regulation
Shared Package
ML20069A188	List: ML20069A186 ML20069A195 ML20069A208 ML20069A210 ML20069A231 ML20069A235 ML20069A252 ML20069A259 ML20069A276 ML20069A303 ML20069A339 ML20069A353 ML20069A367 ML20069A370 ML20069A540 ML20069A648 ML20069B580 ML20069B602 ML20069B633 ML20069C380 ML20069C424
References
FOIA-82-399, TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8004010318
Download: ML20069A339 (1)

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Woodward Clyde Consultants k

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March 25, 19d0 i

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Jabbour g

SEP Equiprnent and Piping Systematte Evaluation Progran Brinch s

Division of Operating Reactors Office of Nuclear Peactor Regulation fl. 9.

Nuclear Re gulatory Commission Washington, D.C. 20555,

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Dear Dr. Jabbour:

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I ha've reviewed the " Seismic Analysis of Peactor Interna'Is for Dresden II" dated December 24, 1968 whien was transmitted by Mr. Janecek's letter dated 20 February 1980.

While the re;,rt into considerable detail conc ~ernino the dynamic analysis goes 4

procedures and assumptions used in analyzino the reactor vessel

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internals an'd supports, the only selsmic input to the analysis

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3 ts N-S El, Centro 1940 time history normalized to 0.19 zero pericd l

ground acceleration.

In addition, while the trodel seems to indicate that the bu 1 ding structure-reactor vessel interaction was considered, no mass coefficient for the building structure g

was defined in the input properties o the analysis.

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The vessel skirt moment of 12,800 F-ft. and shear of '28 Kips determined in the subject report compare to the values of 25, 200 K-ft. and 821 Kip determined in a John A.

Blume report date<: februa ry 2, 1966 which was used by BlW in their Stress I

Analysis evaluation of the Support Skirt.

Of particular interest

n the further review of the design adequacy of the reactor vessel internals and support would be John alume's report where the L.'sia for the 25,800 K-ft. and 821 Kip loads used in tho stress analysis co:ld be evaluated.

Unfortunately, the mater:al suppited :n *he sub)cet report while useful in definina the ass and stiffness characteristics of the vessel internals and supports does lit?!c to answer the design adequacy quest: ens ra:st ! :n the curront f.L' REG /CR-0891 Section 6. 3.1. 8 report.

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