TXX-6436, Interim Deficiency Rept CP-87-07 Re Procurement of safety- Related Components w/Q-code C Instead of Q-code A.Initially Reported on 870406.Spare Parts Review Program Implemented. Next Rept Will Be Submitted by 880219
| ML20215M223 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/06/1987 |
| From: | Counsil W, Keeley G TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-87-07, CP-87-7, TXX-6436, NUDOCS 8705130130 | |
| Download: ML20215M223 (2) | |
Text
, . o M Log # TXX-6436 FE File # 10110
__ .-- 917.1
= r Ref: 10CFR50.55(e)
TilELECTRIC w au. c. c""""' May 6* 1987 Eneastow he hesident U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC -20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 ITEMS PROCURED TO IMPROPER CODE CLASS SDAPs: CP-87-07 (INTERIM REPORT)
Gentlemen:
On April 6,1987, we verbally notified your Mr. C. Hale of a deficiency involving spare parts for safety related components. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).
Specifically, these components were procured with a Q-code "C" instead of a Q-code "A" as required. The documentation requirements imposed in these instances may not have been sufficient to assure that the quality of the item purchased was equivalent to the quality of the item as provided under the original equipment specification, or as required to maintain equipment qualification.
The Spare Parts Review Program has been implemented to identify and resolve individual problems resulting from a generic deficiency in the procurement engineering review process as identified in Corrective Action Request 86-002.
The safety implications of the individual deficiencies (documented by site NCRs) are considered in addition to the availability of required documentation, installation status, and hardware replacement cost.
- The Spare Parts Review Program is currently scheduled for completion by December 31, 1987. The results of this program are required to determine the impact of this issue upon the safety of plant operations.
8705130130 870506 5 DR ADOCK 0500 l
i 40 North Olise Street I..H. 81 Dallas, 'lexas 75201 g7 t MO
TXX-6436 May 6,*1987' Page 2 We will submit our next report on this issue no later than February 19, 1988.
Very truly yours, ndY W. G. ounsil By: . . .
/
G. S. Keeley Manager,' Nuclear Li sing DAR/mlh c - Mr. E. H. Johnson, Region IV 1 Mr. D. L. Kelley, RI - Region IV Mr. H. S..Phillips, RI - Region IV E