View source for TXX-4701, Interim Deficiency Rept CP-86-05 Re Safety Class Pipe Supports Mounted to nonsafety-related Embedded Plates. Initially Reported on 860113.Piping Sys & Supports Analyzed & Remaining Support Removed.Next Rept by 860325

{{Adams
| number = ML20153F227
| issue date = 02/12/1986
| title = Interim Deficiency Rept CP-86-05 Re Safety Class Pipe Supports Mounted to nonsafety-related Embedded Plates. Initially Reported on 860113.Piping Sys & Supports Analyzed & Remaining Support Removed.Next Rept by 860325
| author name = Counsil W
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name = Johnson E
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION IV)
| docket = 05000445
| license number = 
| contact person = 
| document report number = CP-86-05, CP-86-5, TXX-4701, NUDOCS 8602250341
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 1
}}

=Text=
{{#Wiki_filter:Log i TXX-4701 F11o i 10110 903.8 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER
* 400 NORTH OLIVE ErrREET. L.H. al e DALLAS. TEXAS 78201 February 12, 1986 MM *ES
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1I-       FEB i 91966      h{     '
e:Mr." EifcTHT' Johnson',': Acting Director                                           jii Division of' Reactor Safety and Projects                                                                     l,;
U.S. Nuclear Regulatory Commission                                               -
611 Ryan Plaza Drive, Suite 1000 Arlington. TX 76012

==SUBJECT:==
COMANCHE PEAA STEAM ELECTRIC STATION D0CKET NO. 50-445 SAFETY CLASS PIPE SUPPORTS MOUNTED TO NNS EMBEDDED PLATE SDAR: CP-86-05

==Dear Mr. Johnson:==

On January 13, 1986, we verbally notified your Mr. T. Westerman of a defi-ciency involving four piping systems which have been identified as including safety class pipe supports mounted to non-safety related embedded plates. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Currently, with a single exception, all piping systems and supports have been analyzed without noting an adverse condition. The remaining support at issue will require removal of the sup-port and testing of the base plate.
We are continuing our evaluation and anticipate completion of our final report by March 25, 1986.
Very truly yours, W. G. Counsil l
JCH/ arm                                                                                                             l c - NRC Region IV (0 + 1 copy)                                                                                       l Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C. 20555
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         % /44                                   8602250341 860212 PDR         ADOCK 05000445 d~
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