TXX-6981, Final Deficiency Rept CP-87-27 Re Galvanic Corrosion in Svc Water Sys.Initially Reported on 870629.Resultant Corrosion Will Advance to Saturation Level,Where Further Corrosion Will Be at Very Slow Rate

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Final Deficiency Rept CP-87-27 Re Galvanic Corrosion in Svc Water Sys.Initially Reported on 870629.Resultant Corrosion Will Advance to Saturation Level,Where Further Corrosion Will Be at Very Slow Rate
ML20236T039
Person / Time
Site: Comanche Peak  
Issue date: 11/24/1987
From: Beck J, Counsil W
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CP-87-27, TXX-6981, NUDOCS 8711300249
Download: ML20236T039 (1)


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  1. TXX-6981 Fi e # 10110 r

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909.2 M# ELECTRIC Ref. # 10CFR50.55(e) wimam c. counsa November 24, 1987 Executive Vke Ptrsideart V. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 GALVANIC CORROSION IN SERVICE WATER SYSTEM SDAR:

CP-87-27 (FINAL REPORT)

Gentlemen:

On June 29, 1987, we verbally notified your Mr. H. S. Phillips of a potentially reportable deficiency' involving galvanic corrosion in the Service Water (SW) system. Our latest interim report logged was TXX-6663, dated August 20, 1987.

Af ter further evaluation, we have determined that this issue is not reportable pursuant to 10CFR50.55(e).

Design validation of specification 2323-MS-624A, "Annubar Flow Elements,"

identified flow elements installed in the Service Water System that are constructed of monel material, while the associated piping mating flanges are carbon steel.

The mating of the dissimilar metals would cause galvanic Corrosion.

We have completed our evaluation and have concluded that the resultant corrosion products will advance to a saturation level, where further corrosion will be at a very slow rate.

This corrosion, even should minor leakage occur, would not adversely affect the Service Water System or flow element operation.

Therefore, were this condition to remain uncorrected, no condition adverse to safe plant operations would exist.

Supporting documentation is available onsite for your inspector's review.

Very truly yours, ld. G. c.

W. G. Counsil (j,/k 8711300249 g7112 By:

PDR ADOCK 0 % DR Johv H. Beck S

Vice President, Nuclear Engineering MCP/grr c - Mr. R. D. Martin, Region IV p7 i

Resident Inspectors, CPSES (3) 400 North Olive Street LB 8I Dallas, Texas 73:01