IR 05000445/1981017
| ML20038B831 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/19/1981 |
| From: | Gilbert L, Randy Hall NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20038B824 | List: |
| References | |
| 50-445-81-17, 50-446-81-17, NUDOCS 8112090137 | |
| Download: ML20038B831 (3) | |
Text
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APPENDIX A U.S. NUCLEAR REGULATORY COPWISSION
REGION IV
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Report:
50-445/81-17; 50-446/81-17 Docket:
50-445; 50-446 Category A2
Licensee:
Texas Utilities Generating Company
2001 Bryan Tower Dallas, Texas 75201 Facility Name:
Comanche Peak, Units 1 and 2 Inspection at:
Comanche Peak Steam Electric Station Inspection conducted:
November 2-6, 1981 Inspector:
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// 9 j p D. Gilbert, Reactor Inspector, Engineering and Dater
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W Materials Section i
Approved:
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R. E. Hall, Acting Chief, Engineering and Materials Date'
l Section Inspection Summary:
Inspection During November 2-6, 1981 (Report 50-445/81-17; 50-446/81-17)
Areas inspected:
Routine, unannounced inspection of construction activities j
including site tour; observation of work and review of records for weldtc; of the Unit 1 Reactor Containment Building liner; and observation of work and review of records for safety-related pipe welding in Unit 2.
The inspec-tion involved 34 inspector-hours by one NRC inspector.
Results:
No violations or deviations were identified.
8112090137 811120'
PDR ADOCK 05000445 G
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DETAILS 1.
Persons Contacted Principal Licensee Personnel
- R. G. Tolson, Site QA Supervisor, TUGC0
- J. T. Merritt, Manager, Engineering and Construction, TUSI Other Personnel
W. E. Baker, Senior Project Welding Engineer, Brown & Root (B&R)
G. Willis, QC Mechanical Senior Superintendent, B&R G. Bennetzen, QC Supervisor, B&R D. Williams, Welding /QA Supervisor, Chicago Bridge & Iron (CB&I)
The NRC inspector also interviewed other licensee and contractor employees during the course of the inspection.
- Denotes those attending the exit interview.
2.
Site Tour The NRC inspector toured the Reactor Building, Auxiliary Building, and Fuel Handling Building for Units 1 and 2 to observe construction in progress and to inspect housekeeping.
No violations or deviations were identified.
3.
Reactor Building Containment Welding - Unit 1 The NRC inspector inspected the CB&I welding activities related to closing of the construction opening in the Reactor Containment Building liner.
In the areas inspected, welding and spot radiography were con-sistent with Welding Procedure Specification WPS-E8018-C1, Revision 4; Radiography Procedure RTP-74-2427/8, Revision 7; and CB&I Quality Assurance Manual for Steel Portions of Concrete Containment Vessels Issue No. 6.
i No violations or deviations were identified.
4.
Safety-Related Pipe Welding Activities - Unit 2 The NRC inspector observed the repair welding of two butt welds which (
were identified as follows:
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FW-1 in Containment Spray Line 16" CT-2-140-151R-2 on Isometric Drawing CT-2-RB-092
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FW-1 in Safety Injection Line 16" SI-2-073-151R-2 on Isometric Drawing SI-2-RB-088 In the areas inspected, no discrepancies were noted concerning compliance with B&R Welding Procedure Specification WPS 11020.
The NRC inspector selected ten field welds for visual examination and found the final weld surface condition to be consistent with the require-ments of B&R Procedure QI-QAP-10.2-7, Revision 1 for visual examination of weldments and ASME B&PV Code Section III,1974 Edition, including Summer 1974 Addenda for Class 1 and 2 piping.
The Class 1 field welds were identified as FW-2, FW-4, FW-10, FW-12, FW-18, FW-20, and FW-29 on Isometric Drawing RC-2-520-1 for the Reactor Coolant Loop Piping System.
The Class 2 field welds for the Safety Injection Piping System were identified as FW-2 and 3 on Isometric Drawing SI-2-RB-081 and W3-3A on Isometric Drawing SI-2-RB-46.
The NRC inspector also reviewed the postweld heat treatment records for four field welds in the Feed Water Piping System, FW-8, FW-9, FW-14, and FW-15 on Isometric Drawing FW-2-SB-001A.
The postweld heat treatments were found to be consistent with B&R Procedure CP-CMP-6.9D and ASME B&PV Code,Section III, 1974 Edition, including Summer 1974 Addenda for Class 2 pipe welds.
No violations or deviations were identified.
5.
Exit Interview The NRC inspector met with licensee representatives (denoted in paragraph 1) and P G. Taylor (NRC Resident Reactor Inspector) on November 6, 1981, and summarized the scope and findings of the inspection.
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