TXX-6176, Interim Deficiency Rept CP-86-74 Re Internal Wiring Discrepancies & Rusty Close Nipples & Fittings in Terminal Boxes for Unit 2 Msivs.Initially Reported on 861021.Field Verification Underway.Next Rept Will Be Submitted by 870410

From kanterella
(Redirected from TXX-6176)
Jump to navigation Jump to search
Interim Deficiency Rept CP-86-74 Re Internal Wiring Discrepancies & Rusty Close Nipples & Fittings in Terminal Boxes for Unit 2 Msivs.Initially Reported on 861021.Field Verification Underway.Next Rept Will Be Submitted by 870410
ML20207C646
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 12/19/1986
From: Counsil W, Keeley G
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To: Johnson E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CP-86-74, TXX-6176, NUDOCS 8612300197
Download: ML20207C646 (1)


Text

Log # TXX-6176 File # 10110 908.3 TEXAS UTILITIES GENERATING COMPANY SRYWAY TOWER e 409 NORT,4 OLIVE STREET. L.B. 81. DALLAS. TEXAS 7MSR December 19, 1986 32@m0W3 %

.w.w.mL J

Mr. Eric H. Johnson, Director DEC I 91986 6

Division of Reactor Safety and Projects jJ U.' S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ROCKWELL-TERMINAL BOXES SDAR: CP-86-74 (INTERIM REPORT)

Dear Mr. Johnson:

On October 21, 1986, we verbally notified your Mr. Ian Barnes of a deficiency regarding internal wiring discrepancies and rusty close nipples and fittings in terminal boxes for Unit 2 main steam isolation valves supplied by Rockwell.

Our preliminary evaluation indicates this deficiency potentially effects Units 1 and 2.

This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-6084, dated November 17, 1986.

Currently, we are reviewing the applicable nonconformance reports and performing a field verification of the affected terminal boxes, conduit fittings and the internal wiring to ascertain the significance of this issue in the event the condition had remained undetected. Our assessment will be determined pending completion of the document review and field verification of affected hardware. These efforts are currently scheduled for completion on March 4, 1987.

We will submit our next report on this issue no later than April 10, 1987.

Very truly yours, L,

HJbf W. G. C,u.i 8612300197 861219 L

g PDR ADOCK 05000445 OY /

PDR G. S.'Keeley %

/

S Manager,Nucleapicensing WJH/amb c - Region IV (Original + 1 copy)

Director, Inspection and Enforcement (15 copies)

U. S. Nuclear Regulatory Commission Washington, D. C.

20555 1 Q p7l L Q A mm,m or nu, immre uren,c nmmv