ML19211C511
| ML19211C511 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/20/1979 |
| From: | Janecek R COMMONWEALTH EDISON CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19211C512 | List: |
| References | |
| NUDOCS 8001110553 | |
| Download: ML19211C511 (1) | |
Text
Commonwealth Edison one Fast Nat:onal Plaza Chicago. Imnois Address Rep!y to Post Office Box 767 Chicago. I!hnois 60690 December 20, 1979 Mr. D.L. Ziemann, Chief Operating Reactors-Branch 2 Division of Operating Reactors U.S. Nuclear Regulatory Comission Washington, D.C.
20555 Subjec t: Dresden Station Unit 1 Core Spray Distribution Modification NRC Docket N0. 50-10
Reference:
(a)
M.S. Turbak letter to D.L. Ziemann dated December 28, 1978.
(b) 0.L. Ziemann letter to C. Reed dated February 1, 1979.
(c) CECO /GE meeting with NRC Staff on September 20, 1979.
Dear Mr. Ziemann:
Reference (a) transmitted the General Electric Report NED0-24164 titled " Evaluation of the Dresden 1 Core Spray Sparger Performance in a Steam Environment" to th: NRC Staff. Your transmittal, Reference (b), re-quested additional information to permit continued staff review.
Our review of your concerns identified several areas that would require additional extensive analysis and testing to bring to a satisf actory conclusion. We have, therefore, pursued another approach which modifies the existing core spray distribution design. A meeting was held with the Staff, Reference (c), to discuss a new " grid" distribution design. The result of that meeting plus continued engineering is a completed core spray " grid" design. The enclosed report, "Dresden-1 Core Spray Program Update" NED0-24228, Class I, December, 1979 describes the nm design, engineering considerations and test program.
This transmittal is being made to permit an early NRC review of the new core spray distribution design in order to provide us with assurance that the new design satisfies all NRC concerns.
Reference (b) questions are no longer applicable because of the new grid design and proposed testing program.
Please contact this office if you have any questions regarding this transmi ttal.
One (1) original and thirty-nine (39) copies of this letter and enclosure are provided for your use.
Very truly yours, 1742 009 Mlwn Robert F. Janecek Nuclear Licensing Administrator Boiling Water Reactor
Enclosures:
As Stated 80011yo6 M