View source for TXX-6235, Interim Deficiency Rept CP-86-19 Re Installation of Steam Svc Pressure Transmitters.Initially Reported on 860321.Scope of Item Expanded to Include Corrective Actions for CP-86-77, CP-86-70 & CP-86-16.Next Rept Expected by 870320

{{Adams
| number = ML20212J539
| issue date = 01/21/1987
| title = Interim Deficiency Rept CP-86-19 Re Installation of Steam Svc Pressure Transmitters.Initially Reported on 860321.Scope of Item Expanded to Include Corrective Actions for CP-86-77, CP-86-70 & CP-86-16.Next Rept Expected by 870320
| 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, 05000446
| license number = 
| contact person = 
| document report number = CP-86-19, TXX-6235, NUDOCS 8701280228
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 1
}}

=Text=
{{#Wiki_filter:Log # TXX-6235 File # 10110 910.3 TEXAS UTILITIES GENERATING COMPANY SKYWAY TOWER 4ES NORTH OLIVE STREEF, LB. 88 . DALLAS, TEXA8 78301 January 21, 1987 l
 .T!#".hff.WJi Mr. Eric H. Johnson, Director                                                                            4   n Division of Reactor Safety and Projects                                            ' L ',   JAN 2 31987      r.
                                                                                                                   ;h U. S. Nuclear Regulatory Commission                    '
gj                   i 611 Ryan Plaza Drive, Suite 1000                                                                       -'
Arlington, TX 76011

==SUBJECT:==
COMANCHE PEAX STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 INSTRUMENTATION INSTALLATIONS SDAR:    CP-86-19 (INTERIM REPORT)

==Dear Mr. Johnson:==

On March 21, 1986, we notified you of a reportable item involving the installation of steam service pressure transmitters (see TXX-4824). This is a follow-up interim report to status the corrective actions for a reportable item under the provisions of 10CFR50.55(e). Our last interim report was logged TXX-5045, dated September 26, 1986.
The scope of this item has been expanded to include corrective action implementation for SDAR(s) CP-86-77, " Instrument Tubing Minimum Wall Thickness," CP-86-70, " Elevated Temperature Effects on Instrument Supports and Tubing," and CP-86-16, " Fire Effects on Instrumentation Tubing," all of which have been reported under the provisions of 10CFR50.55(e). Corrective action for these deficiencies will be identified and 16plemented after a comprehensive evaluation is performed of instrument installations.
We will submit our next report no later than March 20, 1987.
Very truly yours, M&
W. G. Counsil GLB/gj c - NRC Region IV (0 + 1 copy)
Director, Inspection & Enforcement (15 copies)
U. S. Nuclear Regulatory Commission Washington, D.C. 20555 8701280228 DR               870121 ADOCK 05000445 PDR A Dl%NON OF 7'EX4% LTILITIF5 ELFCTRIC C0%tr.AW Pd                      -                                  .-              .                              --   Mh}}