ML19263D730

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Forwards ECCS Evaluation of Dresden-1 Using Exxon Nuclear Co Wrem Non-Jet Pump Evaluation Model,Large Break Example Problem in Response to NRC 780512 Request for Addl Info
ML19263D730
Person / Time
Site: Dresden 
Issue date: 04/04/1979
From: Vanecek R
COMMONWEALTH EDISON CO.
To: Ziemann D
Office of Nuclear Reactor Regulation
Shared Package
ML19263D731 List:
References
NUDOCS 7904130199
Download: ML19263D730 (2)


Text

,1.

4 Commonwealth Edison One Fast Nabonal Plaza, Chicago. Ilknois Address Reply to: Post Ottice Box 767 Chicago, lihnois 60690 April 4, 1979 Mr. D.L.

Ziemann, Chief Operating Reactors - Branch 2 Division of Operating Reactors U.S.

Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Dresden Station Unit 1 10CFR50 Appendix K - Sample Problem NRC Docket No. 50-10 References (a) :

Byron Lee, Jr. letter to B.C. Rusche dated October 16, 1975 (b) :

M.S. Turbak letter to D.L.

Ziemann dated March 14, 1978 (c) :

D.L.

Zicmann letter to Cordell Reed dated May 12, 1978 (d) :

M.S. Turbak letter to D.L. Ziemann dated September 19, 1978

Dear Mr. Ziemann:

Reference (b) was transmitted to the NRC staff to revise and updato the Dresden 1 ECCS Design Report transmitted by Reference (a).

As part of the staff's review we received a request for ad-ditional information (Reference (c)).

Our partial response (Reference (d)) indicated that in answer to Question 1 Exxon Nuclear Company would perform "ECCS Performance" calculations.

Prior to the performance of these 10CFR50 Appendix K calculations a "Large Break Example Problem" has been performed.

This example problem entitled "ECCS Evaluation of Dresden-1 Using the Exxon Nuclear Company WREM Non-Jet Pump Evaluation Model--Large Break Example Problem", XN-NF-79-24 is enclosed.

This document is being transmitted to present the application of the ENC Non-Jet-Pump BWR WREM-Based ECCS model for Dncsden 1.

The basic system blow-down model uses an NRC approved computer code.

Included is the system nodalization utilized in the analysis.

This report is submitted to the staff so a review of the technique and method to be utilized in the Appendix K calculations may be made.

If there are any questions regarding applicability of 0

7904130t1j p.

NRC Docket No. 50-10 l

Dear Mr. Ziemann:

April 4, 1979 the previously approved model or nodalization of the plant we request prompt notification.

To insure an early agreement of this approach we recommend a meeting in the very near future to discuss any staff questions.

We also request the staff to not review the specific results but rather the technique used in the analysis.

If you have any questions regarding this transmittal please contact this office.

One (1) original and thirty-nine (39) copies of this letter and enclosure are provided for your use.

Very truly yours, fh R.

F.

Janecek Nuclear Licensing Administrator Boiling Water Reactors