ML19210A448
| ML19210A448 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/09/1971 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | John Miller METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7910300458 | |
| Download: ML19210A448 (2) | |
Text
b JUI. 9 5 71 Docket no. 50-289 Metropolitan Edison Company AITd: IIr. John G. tiiller Vice President & Chief Engineer P. O. Box 542 Reading, Pennsylvania 19603 Gentlemen:
Un June 19, 1971 the AEC adopted interim acceptance criteria for the performance of emergency core cooling systems (ECCS) in light-water nuclear power plants. A copy of che Commission's interim policy state-ment on this matter is enclosed for your information. In accordance with Section IV.E. of the interim policy statement, before we can complete our evaluation of the ECCS for the Three Mile Island Nuclear Station Unit 1 we need information to show that the system meets the general criteria of Section IV.A. using a suitable evaluation model.
We are continuing discussions with representatives of the Sabcock &
Wilcox Company (B&W) that are directed toward establishing a suitable evaluation model using B&W computer codes for evaluation of plants incorporating a nuclear steam suppgy system designed by B&W.
The information that we need regarding analyses performed with a suitable evaluation model is:
(1) For the break size range, location and type mentioned in Appendix A, Part 1, of the interim policy statement, provide inforuttion per-taining to (a) the systc= pressure, (b) hhe hot-spot clad tenper-ature, local mass velocity, fluid temperature, and heat transfer coefficient, (c) the core precsure drop, quality, and mass velocity, (d) the heat flux distribution in the hot channel, (e) the flow rates in the upper and lower plenums, (f) the flow rates in the broken and intact cold-leg piping, (g) the flow rate e se of the break, and (h) percr.at clad metal-water reactio2.
(2) Provide a detailed discussion of the calculation used to prediet heat transfer during the reflood portion of the transient.
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netropolitan Edison Company (3) Discuss in detail any deviations in the evaluation codel used in the foregoing studies from that described in Appendix A, Part 1 of the interim policy statement 7 j M, W, u tx',
In addition, you should submit for our review any changes to the Technical Specifications for the plant that may be required on the basis of the results of your analyses.
When you have obtained the required information, please submit,
it as an amendment to your application.
Sincerely, Origimt Signed by Pect A. Mc*ris Peter A. Morris, Director Division of Reactor Licensing
Enclosure:
DISTRIBUTION:
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AEC PDR cc: Jersey Central Power & Light Company Local PDR ATTN: ;ir. Robert H. Sims PWR-2 Reading Vice President DR Reading Mr. John R. Thorpe, Manager DRL Reading Safety & Licensing CKBeck 260 Cherry Hill Road MDiann Parsippany, New Jersey 07054 SHanauer FSchroeder Pennsylvania Electric Company RSBoyd ATTN: fir. Paul L. Limmitzer RCDeYoung Vice President, Technical DJSkovholt 1001 Broad Street TRWilson Johnstown, Pennsylvania 15907 EGCase RR! 'cary RI
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