View source for TXX-6716, Interim Deficiency Rept CP-87-18 Re Errors Identified During Review of Struther-Wells Qualification Documentation for Component Cooling Water Hxs.Initially Reported on 870608. Evaluation Continuing.Next Rept Will Be Provided by 871106

{{Adams
| number = ML20238E999
| issue date = 09/11/1987
| title = Interim Deficiency Rept CP-87-18 Re Errors Identified During Review of Struther-Wells Qualification Documentation for Component Cooling Water Hxs.Initially Reported on 870608. Evaluation Continuing.Next Rept Will Be Provided by 871106
| author name = Counsil W, Keeley G
| author affiliation = TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000445, 05000446
| license number = 
| contact person = 
| document report number = CP-87-18, TXX-6716, NUDOCS 8709150330
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 2
}}

=Text=
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:ll:' =             Log # TXX-6716
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File # 10110 909.2
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U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555

==SUBJECT:==
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)                                                                                 l DOCKET NOS. 50-445 AND 50-446                                                                   '
3 COMPONENT COOLING WATER (CCW) HEAT EXCHANGER SEISMIC QUALIFICATION                                                                                     -
SDAR: CP-87-18 (INTERIM REPORT)                                                                          7       .
1 Gentlemen:                                                                                                             d     .1       I On June 8, 1987, we verbally notified your Mr. 1. Barnes of a defic b cy-involving errota identified during a review of the vendor (StrutherGliells) qualification documentation for the CCW heat exchangers that indicatbd the seismic and nozzle loading conditions exceed specification requirements and could be overstressed. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our most recent interim report, logged TXX-6607, was submitted on August 3, 1987.
We are continuing our evaluation of the impact of this issue on the safety of plant operations.
Our next report will be submitted no later than November 6, 1987.
Very tr ly ours, OM W. G. Counsil By:           .
72       6 G. S. Keeley Manager, Nuclea     L''en     ng MCP/lp c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3)                                                                                               ;
B709150330 s70911 S
PDR    ADDCK 05000445 PDR                                                                           / h;ff 400 North Olive Street LB 81 Dallas, Texas 75201                              {v

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