LD-83-051, Summarizes 830425 Meeting W/Nrc Re Natural Circulation Cooldown Analysis for CESSAR-F.Reanalysis to Be Submitted by 830729

From kanterella
Revision as of 09:14, 26 May 2025 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Summarizes 830425 Meeting W/Nrc Re Natural Circulation Cooldown Analysis for CESSAR-F.Reanalysis to Be Submitted by 830729
ML20072B420
Person / Time
Site: 05000470
Issue date: 06/07/1983
From: Scherer A
ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
LD-83-051, LD-83-51, NUDOCS 8306130428
Download: ML20072B420 (1)


Text

-

C-E Power Systems Tel. 203/688 1911 Cornbustion Engineenng, Inc.

Telex 99297 1000 Prospect mil Road Windsor, Connecticut 06095 M SYSTEMS POWER Docket No.:

STN 50-470F June 7,1983 i

LD-83-051 Mr. Darrell G. Eisenhut, Director Division of Licensing

[

U.S. Nuclear Regulatory Commission i

Washington, D.C.

20555 Subject :

Natural Circulation Cooldown Analysis for CESSAR-F

References:

(A) Letter LD-82-078, A. E. Scherer to D. C. Eisenhut, dated September 8, 1982 (B) Letter LD-83-025, A. E. Scherer to D. G. Eisenhut, dated March 28, 1983

Dear Mr. Eisenhut:

On April 25, 1983, a meeting was held between Combustion Engineering (C-E) and the NRC on the natural circulation cooldown analysis for CESSAR-F. The purpose ofthemeetingwastodiscussStaffconcernswiththeinforgtionsubmitted (References (A) and (B)) on the capability of the System 80 NSSS to achieve cold shutdown with a Reactor Vessel Upper Head (RVUH) steam void.

Specifically, the Staff noted that the analysis provided did not adequately demonstrate the capability to cooldown to Shutdown Cooling System entry conditions using only safety grade systems.

C-E proposed the following analysis to address the Staff's concerns.

We would re-analyze the cooldown assuming (1) no letdown available, (2) the Reactor Coolant Cas Vent System is available to help reduce the void in the RVUH, (3) boration and, hence, reactor coolant system inventory shall be predicated on the shutdown margin requirements with all rods inserted, and (4) conservative mixing and condensation in the RVUH.

Reactor Systems Branch has expressed confidence that an analysis, as described above, would satisfy their concerns with the analytical part of the issue.

Staff requirements for demonstration of this capability on the prototype System 80 plant will be addressed by the startup test program at the Palo Verde, Nuclear Cencrating Station 1.

The specifics of the testing will be resolved by Arizona Public Service with the Staff.

C-E intends to provide the re-analysis of the natural circulation cooldown by July 29, 1983. If you have any questions on the scope or schedule, please feel free to contact me or Mr. G. A. Davis of my staff at (203) 688-1911, ext. 5207.

Very truly yours, 63 8

COMBUSTION E INEERING, INC.

A. E. Scherer Director Nuclear Licensing AES:las cc: C. Meyer (Project Manager / USNRC) f

_