ML20070E633
| ML20070E633 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/10/1982 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8212170326 | |
| Download: ML20070E633 (2) | |
Text
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- lHsconsin Becinc meacouesur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 December 10, 1982 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr.
R. A. Clark, Chief Operating Reactors Branch 3 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 SPECIFIC TREATMENT OF UPPER PLENUM INJECTION IN EMERGENCY CORE COOLING SYSTEM ANALYSIS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In Mr. Clark's letter of November 8, 1982 you requested the submittal on our dockets of the Emergency Core Cooling System (ECCS) evaluation model which specifically treats upper plenum injection (UPI) on Westinghouse two-loop plants.
In this regard, we reference the description of the ECCS evaluation model discussed in letter No. NS-TMA-2172 dated December 6, 1979 from Mr. T. M. Anderson of Westinghouse Electric Corporation to Mr. D. G. Eisenhut of the NRC staff regarding " Modifications to the W ECCS Evaluation Model (February 1978 version) for 2 Loop Upper Plenum Injection Plants".
The code modifications described in the Westinghouse letter which explicitly model upper plenum injection also apply directly to the 1981 version of the Westinghouse Large Break ECCS Evaluation Model which was recently approved by an NRC Safety Evaluation Report.
The sample calculations requested in your letter will be performed using the 1981 version of the Westinghouse ECCS Evaluation Model for a generic two-loop plant both with and without the UPI modifications.
Calculations will be performed for the worst-case large break for two-loop plants.
In addition, sensitivity studies will be performed to determine the affect on Peak Clad Temperature of different percentages of core cross-sectional area covered by upper plenum injection water.
It is our intention to provide you the results of the above calculations and analyses no later than February 25, 1983.
fool 8212170326 821210
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1 Mr. H. R. Denton December 10, 1982 c.
We would be pleased to answer any questions you may have regarding this matter.
l Very truly yours,', *
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Assistant Vice President C. W. Fay Copy to NRC Resident Inspector
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