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: Difference between revisions
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{{#Wiki_filter:M | {{#Wiki_filter:M Log # TXX-6427 FE File # 10110 908.3 | ||
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Ref: 10CFR50.55(e) 189 ELECTRIC April 30, 1987 | |||
.,, a.m Lsecutin he l'reudem U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 | |||
==SUBJECT:== | ==SUBJECT:== | ||
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) | COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) | ||
DOCKET NOS. 50-445 AND 50-446 G0ULD BATTERY RACKS TRANSVERSE BRACING SDAR: | DOCKET NOS. 50-445 AND 50-446 G0ULD BATTERY RACKS TRANSVERSE BRACING SDAR: | ||
CP-86-46 (FINAL REPORT) | |||
Gentlemen: | 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. | 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: | In our most recent transmittal, our corrective actions were noted as follows: | ||
a) | a) | ||
b) | 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. | Con.pletion of the associated rework concerning both Units 1 and 2 is scheduled for August 31, 1987. | ||
Very tr ly yours, Y | Very tr ly yours, Y | ||
W. G. Counsil | u W. G. Counsil j | ||
j | By: | ||
By: | G. S. Keeley | ||
G. S. Keeley | /, | ||
Manager, Nuclea"r W1nsing RWH/mlh c - Mr. E. H. Johnson, Region IV | Manager, Nuclea"r W1nsing RWH/mlh | ||
Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV f | \\/ | ||
8705050204 870430 | c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV f | ||
gDR | 8705050204 870430 | ||
/ | |||
gDR ADOCK 05000445' PDR sorth oine street i..it. 81 pali.n. lesas 7520 IQ}} | |||
Latest revision as of 18:08, 6 December 2024
| ML20210A974 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/30/1987 |
| From: | Counsil W, Keeley G TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| CP-86-46, TXX-6427, NUDOCS 8705050204 | |
| Download: ML20210A974 (1) | |
Text
M Log # TXX-6427 FE File # 10110 908.3
=
=
Ref: 10CFR50.55(e) 189 ELECTRIC April 30, 1987
.,, a.m 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
u W. G. Counsil 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 sorth oine street i..it. 81 pali.n. lesas 7520 IQ