ML20086C535
| ML20086C535 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/01/1973 |
| From: | Betz J Public Service Enterprise Group |
| To: | Knuth D US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20086C534 | List: |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8311280111 | |
| Download: ML20086C535 (2) | |
Text
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John F.Betz Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/622-7000 Vece-President in Charge of Electric Operation August 1, 1973 U.S. Atomic Energy Commission Directorate of Regulatory Operations 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention of Mr. Donald F. Kr.uth Director g
7, Gentlemen:
3/[
I CVCS LETDOWN HEAT EXCHANGER - MODIFICATION NO. 1 AND 2 UNITS SALEM NUCLEAR GENERATING STATION In compliance with AEC Regulation 10CFR50.55(e), a i
verbal report was submitted on June 26, 1973 to the Region 1 Directorate of Regulatory Operations concerning the modifica-l tion of the No. 1 and 2 Units CVCS Letdown Heat Exchangers.
A review of.the design of the Letdown Heat Exchangers by Westinghouse Electric Corporation and our own engineers revealed that flow induced tube vibration may occur in the U-bend section of the tube bundles during certain modes 3
1 of operation.
The vibration can occur as a result of either vortex shedding excitation or fluidelastic excitation when-the shell side. flow rate exceeds the nominal design value.
In addition, it was determined that1high fluid velocities may occur at the shell inlet.
The Letdown Heat Exchangers will be returned to the manufacturer to have the U-tube-portion of the tube bundles banded to reduce vibration and to have a flow. distributor installed in the shell inlet to reduce fluid-velocities.
Procedures for the removal.and rework of the heat exchangers will be developed and approved by-Public Service Electric.and Gas Company before any work is performed.
The rework.affects
-only the 'shell side and will be in-accordance with the :ASME ~
Code Section1VIII, 196 5 edition to which. it was originally -
constructed.
Quality assurance requirements will be implemented.
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Atomic Energy 8-1-73 Commission The schedule for carrying out this work has not yet been established; however, when it is completed, the quality records, procedures, etc., will be available for your inspection at the construction site.
If you have any further questions on this su b j e c t,
we will be pleased to discuss them with you.
Very truly yours,
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s/
CC Mr. James P. O'Reilly King of Prussia, Pa.