ML20248B910
| ML20248B910 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/04/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CP-87-013, CP-87-13, TXX-89528, NUDOCS 8908090365 | |
| Download: ML20248B910 (2) | |
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!EEI5EE3 Log # TXX-89528
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C Fi1e # 10110 903.9 Ref. # 10CFR50.55(e)
N/ELECTR/C August 4, 1989 Wimam J. CahW. Jr.
Executive nce President U. S. Nuclear Regulatory Commission j
Attn: Document Control Desk i
Washington, D. C.
20555
SUBJECT:
CCMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 CLASS 1E SEPARATION VIOLATIONS SDAR:
CP-87-013 (SUPPLEMENTAL REPORT)
Gentlemen:
On January 11, 1988, the NRC was informed via report logged TXX-88059 of a reportatle deficiency involving Class IE separation violations resulting from the removal or modification of non-safety class cable tray covers after acceptance b) CPSES Quality Control. This report is to revise the preventive action and update the completion schedule for this issue previously described in TV Electric Reports TXX-88059 and TXX-88184, respectively.
Preventive action discussed in TXX-88059 included revision of Inspection Removal Notice (IRN) Procedure CP-CPM-6.10 to clearly state that the issuance of IRN's was required for the removal of all tray covers.
Subsequently, CP-CPH-6.10 has been superseded by a construction procedure which requires a traveler step for the removal of previousiy inspected items.
Additionally, construction personnel are required to prepare a package for QC inspection whenever a cover on a non-safety related cable tray is installed or removed.
8908090365 890804 PDR ADOCK 05000445 S
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-August 4, 1989 Page 2 of-2 I "
-Design Change Authorizations (DCA's) for locating and reinstalling the cable tray covers have been initiated. The DCA's will be implemented to support room and crea turnover and are scheduled to be completed prior to Unit 1 fuel load for. Unit I and prior to Unit 2 fuel load for Unit 2.
Supporting documentation for this issue is available for the NRC-inspector's review.
' Sincerely, Y
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)h William J. Cahill, Jr.
By:
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Roger"D. Walker Manager, Nuclear Licensing
.DAR/ddm-c - Mr; R. D. Martin, Region IV
- Resident Inspectors, CPSES (3) l' 1
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