ML19345C166

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Ack Receipt of Providing Results of Bergen- Patterson Steam Generator Snubber Testing.Provides List of Comments.More Detail Should Be Provided for Stiff Spring Mod Which Altered Original Valve Block Design
ML19345C166
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 11/20/1980
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Reed C
COMMONWEALTH EDISON CO.
Shared Package
ML19345C167 List:
References
NUDOCS 8012040057
Download: ML19345C166 (2)


Text

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~4 UNITED STATES NUCLEAR REGULATORY COMMISSION

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REGION ll1 e

'8 799 ROOSEVELT ROAD Y

8 GLEN ELLYN, ILLINOIS 60137 g*...+

o liOV 2 01980 7

r5 Docket No. 50-295

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<S Docket No. 50-304 0-0,3 m-

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na Commonwealth Edison Company nt 005 ATTN:

Mr. Cordell Reed EhN T

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Vice President d

M Post Office Box 767 Fi N

"d Chicago, IL 60690 C

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o Gentlemen:

Thank you for your letter dated October 15, 1980, providing us the results of the testing of Bergen-Paterson steam generator snubbers installed at the Zion Station. We reviewed this report and have the following comments:

1.

The report content is considered factual; however, more detail should be provided for the stiff spring modification which completely altered the original valve block design.

2.

The matters listed below that were previously included in our Inspection Reports 50-295/80-08 and 50-304/80-08 were not discussed in your report:

Improper function of the bleed valve pressure compensator unit that a.

required hardware modification by replacing the positioning spring with a stiffer spring should be further evaluated to assess whether or not a long term system improvement is warranted.

b.

During and subsequent to the extended LOCA steam test, fluid was observed boiling out of the reservoir; the flange seal was observed leaking fluid, and corrosion was found in the bleed valve areas within the control valve lock. The cause of these problems and a system evaluation that takes into consideration actual design con-siderations should be undertaken by CECO.

c.

Particles in the fluid were found in the control valve block.

These particles caused plugging of the bleed orifice. Filtering of the-fluid internally and externally should be considered in conjunction with Item a. above. With the stiffer positioning spring, the need for the pressure compensator has most likely been removed, and the bleed rate is now obtained mainly by the pressure stepdown fluid passage ports and the bleed orifice.

8012040 N

4

~ Commonwealth Edison Company NOV ' 2 01980 -

Your prompt response to these matters'is needed to support our concurrence with the. Zion Unit ;l repair program.

Sincerely, D

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J mes G. Kepp r Director cc:

Mr.

J.- S. Abel,' Director of Nuclear Licensing Mr. K. L. Graesser, Station Superintendent i

cc w/1tr dtd-10/15/80:

Central Files

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Reproduction Unit NRC 20b AE0D Resident Inspectors, RIII PDR Local PDR' NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General 1

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