U-600342, Responds to Request to Evaluate Effects of Flexibility of Valve 1C11F011 on Piping Stress Analysis.Dynamic Response Spectrum Analysis on Drain Line Subsystem,W/Both Rigid & Flexible Valve Models,Performed

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Responds to Request to Evaluate Effects of Flexibility of Valve 1C11F011 on Piping Stress Analysis.Dynamic Response Spectrum Analysis on Drain Line Subsystem,W/Both Rigid & Flexible Valve Models,Performed
ML20137S234
Person / Time
Site: Clinton Constellation icon.png
Issue date: 12/04/1985
From: Spangenburg F
ILLINOIS POWER CO.
To: Butler W
Office of Nuclear Reactor Regulation
References
U-600342, NUDOCS 8512060194
Download: ML20137S234 (9)


Text

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U-600342 L30- 85 (12-04)-L 1***

  • ILLINDIS POWER 00MPANY IP CLINToN power STATION, P.o. Box 678, CLINToN. ILLINOIS 61727 December 4, 1985 Docket No. 50-461 Director of Nuclear Reactor Regulation Attn: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U. S. Regulatory Commission Washington, DC 20555

Subject:

Clinton Power Station Effects of Valve Flexibility in Dynamic Piping Analysis

Dear Mr. Butler:

In response to an NRC request to evaluate the most flexible valve listed in Table 1 of the Illinois Power letter dated August 26, 1985 to the NRC, valves 1C11F010 and IC11F011 (both having a natural frequetay of 10.6 Hz) were investigated. These valves are in the Control Rod Drive (CRD) system; 1C11F010 is a one inch valve in the CRD scram vent line, and IC11F011 is a two inch valve in the CRD scram drain line. The piping analyses for these lines were performed by Reactor Controls, Inc.

(RCI) and included rigid modelling for each of these valees. The design of the vent line subsystem included a seismic restraint attached directly to valve IC11F010, effectively increasing its natural frequency. Therefore, valve IC11F011 was chosen for evaluation.

Sargent & Lundy evaluated the effects of the flexibility of valve IC11F011 on the piping stress analysii by performing a dynamic response spectrum analysis on the drain line subsystem with both rigid and flexible valve models. The enclosed exhibits 1 through 3 document a comparison of the flexible and rigid valve analysis results. The results of this comparison are consistent with the conclusion documented in Illinois Power's August 26, 1985 letter referenced above 1. e., the flexible valve modelling has no significant impact on the overall  ;

subsystem behavior when compared to the rigid valve analysis.

Differences in pipe stresses and support loads are minor and are similar to variations which would be expected due to changes in other system modelling parameters.

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L30-85(12-04)-L  !

1A.120 Please contact us should you have any questions regarding this matter.

Sinenrel yours, b

F. A. S ngen gerg l Manager-Licenling and Safety DW/bjg Enclosura ec: B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety

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