IR 05000445/1980028
| ML20002C368 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 11/18/1980 |
| From: | Crossman W, Gilbert L, Randy Hall NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20002C365 | List: |
| References | |
| 50-445-80-28, NUDOCS 8101100178 | |
| Download: ML20002C368 (3) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION h
0FFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-445/80-28; 50-446/80-28 Docket No. 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 Site, Glen Rose, Texas Inspection Conducted:
Ncvember 3-6, 1980 h!// fu Inspector: A
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,p.O. Gilbert,ReactorInspector, engineering Date'
Support Section O
Approved:
W. A. Crossman, Chief, Projects Section Date '
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N / FD R. E. Hall, Ch-Af, Engineering Support Section
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Insoection Summary:
Insoection on November 3-6, 1980 (Report No. 50-445/80-28; 50-446/80-28)
Areas Insoected:
Routine, unannounced inspection of construction activities including a site tour and observation of work and review of records for Reactor Coolant Pressure Boundary piping in Unit 1.
The inspection involved twenty-eight inspector-hours by one NRC inspector.
Results:
No items of noncompliance were identified.
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810110017g *
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DETAILS 1.
Persons Contacted
.o incioal Licensee Personnel r
- R. G. Tolson, Site QA Supervisor, TUGC0 Other Personnel J. V. Hawkins, Project QA Manager, Brown & Root (B&R)
W. Baker, Project Welding Engineer, B3R D. Doyle, QC Inspector, B&R The IE inspector also interviewed other licensee and contractor employees during the course of the inspection.
- Denotes those attending the exit interview.
2.
Site Tour The IE inspector toured the Units 1 and 2 Reactor Buildings and Auxiliary Building to observe construction in progress and to inspect housekeeping.
No items of noncompliance were identified.
3.
Reactor Coolant Pressure Boundary Piping - Unit 1 a.
Observation of Work The IE inspector observed the welding of two butt welds in the Safety Injection System.
The two welds were identified as field weld FW-1 in Line No. 10" - SI-1-180-2501R-1 on Isometric Drawing BRP-SI-1-RB-059 and field weld FW-4 in Line No. 6" - SI-1-172-2501R-1 on Isometric Drawing BRP-SI-1-RB-013.
In the areas inspected, no discrepancies were noted concerning welder qualification, weld procedure compliance and material control.
The IE inspector noted that the column on the FW-4 weld data card (WDC)
for designation of QC hold points had been incorrectly marked as not applicable (NA) for each operation.
When the QC inspector was questioned about the NA markings, he immediately recognized the error and took the WDC to the WDC center far correction.
Since the QC inspector had already inspected the first three operations (cleanliness, fit up and preheat) even though the QC hold points were incorrectly marked NA and work had not progressed past any other hold point required by Procedure CP-CPM-6.9G, Revision 1; this item will be considered unresolved pending a thorough WDC review by the licensee to determine if any QC hold points were by passed bccause they were incorrectly marked NA.
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Review of Records
b The IE inspector reviewed the ten most recent nonconformance reports
that had been completed and were relative to safety related piping of which two were for Class 1 piping.
The following nonconformance reports were reviewed and determined to be complete, legible, retrievable and properly closed out:
NCR 2495, 2479, 2457, 2454, 2448, 2446, 2434, 2423, 2413 and 2402.
The B&R Airdit Report No. CP-17 of September 1980 was reviewed and
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found s.
itent with the audit requirements of the B&R QA Manual.
No items of noncompliance were identified.
4.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items,of noncompliance, or deviations.
One unresolved item related to the designation of QC hold points on weld data cards is discussed in paragraph 3.a.
5.
Exit Interview The IE inspector met with a licensee representative (denoted in paragraph 1)
and R. G. Taylor (NRC Resident Reactor Inspector) on November 6, 1980, and summarized the purpose, scope and findings of the inspection.
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