ML20235F958

Forwards Request for Addl Info on Pda Module 7 of RESAR SP/90 Application in Order to Complete Review of Structural Aspects of Design.Response Requested within 90 Days

ML20235F958
Person / Time
Site:	05000601
Issue date:	09/22/1987
From:	Kenyon T Office of Nuclear Reactor Regulation
To:	Johnson W WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 8709290382
Download: ML20235F958 (5)

Text

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1 Docket No.'50-601 September 22, 1987 Mr. W. J. Johnson Nuclear Safety Department Westinghouse Electric Corporation Water Reactor Division Box 355

, Pittsburgh, Pennsylvania 15230

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON RESAR SP/90 As a result of our ongoing review of PDA Module 7 of the RESAR SP/90 application, we require additional information in order to complete our review of the structural aspects.of the design. Enclosed are review questions Q 220.1-220.9.

Please respond to this request within 90 days of the date of this letter. If you have any questions regarding this matter, call me at (301) 492-8206.

Sincerely,

/S/

Thomas J. Kenyon, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

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Docket No. 50-601 Mr. W. J. Johnson Nuclear Safety Department Westinghouse Electric Corporation Water Reactor Division )

Box 355 '

Pittsburgh, Pennsylvania 15230

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON RESAR SP/90

_ As a result of our ongoing review of PDA Module 7 of the RESAR SP/90 C application, we require additional information in order to complete our review l of the structural aspects of the design. Enclosed are review questions  !

. Q 220.1-220.9.  !

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• 1 Please respond to this request within 90 days of the date of this letter. If j you have any questions regarding this matter, call me at (301) 492-8206. <

Sincerely,

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Tho s J. K M , Project Manager Standardization and Non-Power Reactor Project Directorate 4 Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

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RESAR SP/90 REQUEST FOR ADDITIONAL INFORMATION DOCKET No. 50-601 220.1 (3.3.2) The design parameters applicable to the design basis tornado do not cover the entire area of contiguous United States, acc.ording to the guidelines stated in Regulatory Guide 1.76. The maximum wind speed of 320 mph is above the requirement of Tornado Intensity Region II (300 mph), but is below that of Tornado Intensity Region I (360 mph). The atmospheric pressure drop of 1.96 psi is less than the requirement of Tornado Intensity Region II (2.25 psi). If the plant site selection is

[ fntended to cover the entire contiguous United States, the design F parameters should be in compliance with the requirements stipulated in l Regulatory Guide 1.76. Otherwise, provide a map indicating the areas and L borders within which the plant sites will be located and the bases of their design parameters.

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k 220.2 (3.5.3) Provide bases and references for the missile penetration formulas used for design of barriers. For each formula, describe the f condition as well as the limitation of applicability and the basic 9

< assumptions or theories involved. Does the heading " Steel (Standard l

Fomula)" mean " Stanford Fomula"? Please clarify.

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220.3 (3.7.1.2) Provide in detail the design time history generated for seismic design and analysis of Category I structures. Descriptions ,

should include time durations of rise, strong motion and decay stages of l L the time history. A plot of the design time history (in the free field 6

and at the foundation level of structure) is required. The assumption L

of a total duration of 10 seconds is significantly less than that ,

typically assumed (approximately 30 seconds) in post licensing reviews. I Justify your assumption. Also, provide a plot showing the power spectral l L> density of the devyn time history, so that a verification of the uniformity of the spectral energy through the frequency range of interest can be made.

l 220.4 (3.7.2.11) Provide in detail the method used to account for torsional effects on structures in the seismic analysis. To account for accidental torsion, an eccentricity of 5% of the maximum building dimension at the level under consideration shall be assumed. The accidental torsional effect shall be additional to the effect due to variation of underlying i soil properties of a site specific configuration.

t 220.5 '(3.7.2.15) The staff has not reviewed, and therefore has not approved

- the ASCE nonproportional damping modeling approach of the draft report j

" Standard for the Seismic Analysis of Safety-Related Nuclear Structures" i by ASCE Seismic Analysis Standard Comittee, May 1984. Provide details i

of this approach including its basic assumptions, theories, experimental

! verifications, method of analysis, and limitation of appifcability.

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2-220.6 (3.7.3.1) Provide detailed description of the Westinghouse computer program DEBLINZ. Give details of theories, assumptions, algorithm, and verification of accuracy and limitations of the program.

220.7 (3.8.2.4) Provide detailed description of the verification of Westinghouse computer programs WECAN and ASHSD.

! 220.8 (3.8.2.5)' The structural acceptance criteria for buckling (instability) have not been clearly addressed. The ASME Boiler and Pressure Vessel

Code,Section III, Subsection NE and the ASME Code Case N-284 did not contain adequate guidance and explanation on the subject. Provide design criteria for various structural members and shells on buckling, including knock down factors and safety factors for different loading conditions.

Also provide theoretical and experimental bases and justifications for these factors.

220.9 (3.8.4.3) In Table 3.8-3 " Load Combinations and Load Factors for Category I Concrete Structures," the factor for accident pressure Pa of

load combination no. 7 deviates from that of SRP 3.8.4,(1.15 instead of .

1.25). Provide basis and justification for such deviations or change to comply with SRP.

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