View source for TXX-6427, Final Deficiency Rept CP-86-46 Re Design Change to Vendor Supplied Equipment Made W/O Formal Evaluation by Vendor. Initially Reported on 861021.Bolt Connection Voided & Original Design Requirements Reestablished

{{Adams
| number = ML20210A974
| issue date = 04/30/1987
| title = Final Deficiency Rept CP-86-46 Re Design Change to Vendor Supplied Equipment Made W/O Formal Evaluation by Vendor. Initially Reported on 861021.Bolt Connection Voided & Original Design Requirements Reestablished
| 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-86-46, TXX-6427, NUDOCS 8705050204
| document type = DEFICIENCY REPORTS (PER 10CFR50.55E &amp; PART 21), TEXT-SAFETY REPORT
| page count = 1
}}

=Text=
{{#Wiki_filter:M                                         Log # TXX-6427 FE File # 10110 908.3
                                                      =           =                             Ref: 10CFR50.55(e) 189 ELECTRIC
       .,, a.m                                                                                 April 30, 1987 Lsecutin he l'reudem 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 G0ULD BATTERY RACKS TRANSVERSE BRACING SDAR:  CP-86-46 (FINAL REPORT)
Gentlemen:
On October 21, 1986, we notified you by our letter, logged TXX-6052, of a deficiency involving a design change to vendor supplied equipment being made without formal evaluation by the vendor, which we deemed reportable under the provisions of 10CFR50.55(e). This is a final report submitted to status corrective action implemented to date.
In our most recent transmittal, our corrective actions were noted as follows:
a)      The design change which authorized the one (1) bolt connection has been voided and the original design requirements reestablished, thus reverting back to the original design of the two (2) bolt connection.
b)      TUGC0 Nuclear Engineering Procedure TNE-DC-8-1, " Engineering Review and Design Verification of Field Design Changes," (currently Rev.10) has been revised and now provides more detailed instructions and establishes a verifiable approval record of all design changes including calculations.
Con.pletion of the associated rework concerning both Units 1 and 2 is scheduled for August 31, 1987.
Very tr ly yours, Y
W. G. Counsil u
j     '
By:      . .-    <    -
G. S. Keeley             /,
Manager, Nuclea"r W1nsing RWH/mlh c - Mr. E. H. Johnson, Region IV                                                                       \/
Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV f
8705050204 870430                                                                                                 /
gDR    ADOCK 05000445' PDR                                       pali.n. lesas 7520 sorth oine street i..it. 81                                                   IQ}}