ML20235N531
| ML20235N531 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/11/1989 |
| From: | Beck J TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CP-88-16, TXX-89063, NUDOCS 8903010270 | |
| Download: ML20235N531 (2) | |
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- TXX-89063' J
Log 4
File'#
10110 906.5
. TUELECTRIC -
Ref. # 10CFR50.55(e)
February 13,.1989 W.J.Cahm Executive Vice Presi&M l
U. S. Nuclear Regulatory Commission Attn: Document Ccntrol Desk Washington, D. C.
20555 COMAN'HE PEAK STEAM ELECTRIC STATION (CPSES)
SUBJECT:
C DOCKET NOS. 50-445 AND 50-446 CONTAINMENT SPRAY CHEMICAL ADDITIVE SYSTEM SDAR:
CP-88-16 (SUPPLEMENTAL REPORT)
Gentlemen:
On January 19, 1988, TV-Electric notified the NRC via final report logged-TXX-88116 of a deficiency involving the Containment Spray System chemical additive tank and associated piping which has been identified as being designed and fabricated from material that does not provide the specified design life. The latest report was logged TXX-88784, dated November 15, 1988.
The purpose of this report is to update the status of this item.
In TXX-88116, the potential corrosion rate for the containment spray chemical additive system tank / piping was stated as.020 inch / year based on National Association of Corrosion Engineers (NACE) publication, " Corrosion Data Survey," 5th Edition 1974.
Subsequent to TXX-88116, laboratory tests were conducted to more closely approximate the actual corrosion rate. Results of the tests indicate that the corrosion rate at CPSES would be substantially lower than the NACE value.
Based on these new results, the system piping and tank life expectancy will be significantly longer than previously estimated in TXX-88116.
s903olo270 890213 DR ADOCK 0500 t5 400 North Olive Street LB81 Dallas, Texas 75201 f
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')i TXX-89063 February 13, 1989 Page 2 of 2 This new information has impacted the schedule for development of the Unit 1 containment spray chemical additive system tank / piping corrosion monitoring program.
The program will quantify the actual corrosion rates occuring within the subject system components.
These results will dictate future actions, including adjustment of monitoring frequency or cessation of monitoring.
The estimated completion date for the Unit 1 program development is now March 31, 1989.
The results of the Unit 1 program are applicability to Unit 2 and any corrective action required for Unit 2 will be implemented prior to Unit 2 fuel load.
Sincerely, William J. Cahill, Jr.
By:
J. ks___
JgnW. Beck Vice President, Nuclear Engineering JLR/ddm c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) 1 1
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