ML20198G067

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Forwards Request for Addl Info Re Util 750903 & 1107 Ltrs to Evaluate Models Used to Calculate Hydraulic Forcing Functions as Result of Postulated Loca.Info Required to Assess Reactor Vessel Supports Integrity
ML20198G067
Person / Time
Site: Washington Public Power Supply System
Issue date: 01/21/1976
From: Norian P
Office of Nuclear Reactor Regulation
To: Deyoung R
Office of Nuclear Reactor Regulation
References
CON-WNP-1104 NUDOCS 8605290219
Download: ML20198G067 (2)


Text

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R. C. DeYoung, Assistant Director for Light Water Reactors, PH THRU
Z. R. Rosatoczy, Chief, Analysis Branch, SS t

REACTOR VESSEL SUPPORTS AND REACIOR VESSEL INTERNALS (TAR 3217) i Plant Name: Nuclear Projects Nos.1 and 4 Docket Numbers: 50-460/ 0-513 Milestone No.: 01-l Licensing Stages Responsible Branch LWR-1 and Project Manager: T. H. Cox System Safety Branch Involved: Analysis Branch Description of Review: WPPSS letters from Noo. Strand to R. Boyd, G01-75-181 dated September 3, 1975 ada G01-75-264 dated Novem-ber 7,1975 Raquested Completion Date: January 30, 1976 Review Status: Request for additional infomation The Analysis Branch has been requested to review the above referenced letters to evaluate the models used to calculate the hydraulic forcing functions as a result of a postulated LOCA. This information is re-quired to assess the integrity of the reactor vessel supports and the reactor vessel internals. .1 The information presented in the letters is not sufficient to evaluate the hydraulic models. Additional information is therefore sequested N as outlined in the enclosure. \

P. E. Norian, Section Leader Analysis Branch Division of Systems Safety Office of Nuclear Reactor Regulation

Enclosure:

Additional Information Request cc:- S. Hanauer DISTRIBUTION:

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. ENCLOSURE Additional Information Required to Complete Review of WPPSS Letters G01-75-181 and C01-75-264 In 'the subject letters the Applicant concludes that an analysis performed with the CRAFT-2 code, to calculate the hydraulic forcing functions resulting from.a postulated LOCA, is acceptable for use in the design of .the reactor vessel supports and in assuring the integrity of the reactor vessel internals.

In ceder to evaluate the Applicant's conclusions it will be necessary to review the hydraulic code, CRAFT-2, as applied to this area of concern.

It is therefore requested that the following be provided to complete the revicw:

1. The CRAFT-2 computer code description r:

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2 .- The following should also be provided for the code:

(a), User notes on how to set up a model including input description, (b) noding sensitivity and justification for the noding .

scheme used, (c) time step sensitivity, (d) verification of code results, i.e., comparison with existing experimental data.

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