IR 05000413/1979001
| ML19284A689 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/14/1979 |
| From: | Blake J, Conlon T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19284A685 | List: |
| References | |
| 50-413-79-01, 50-413-79-1, 50-414-79-01, 50-414-79-1, NUDOCS 7903150202 | |
| Download: ML19284A689 (4) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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o R EGION ll
ak 101 M ARIETT A STR EET, N.W.
ATLANTA, GEORGI A 30303
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Report Nos..
50-413/79-01 and 50-414/79-01 Licensee: Duke Power Company Post Office Box 33189 Charlotte, North Carolina 28242 Facility Name:
Catawba Nuclear Power Station License Nos.-
CPPR-116 and CPPR-117 Clover, South Carolina Inspection at: '
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Inspector:
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J. J/ Blake Date Signed Approved by:c-Ig:>fr c# /d/
v T. E. Conlon, Section Chief,RC&ES Da'te Signed SUMMARY Inspection conducted on January 8-9, 1979 Areas Inspected This routine, unannounced inspection involved 14 inspector-hours on-site in the areas of welding of reactor coolant, pressure boundary and safety-related piping (Unit 1), installation of pressurizer lower support (Unit 1), and housekeeping (Units 1 and 2).
Results Of the areas J.nspected, no apparent items of noncompliance or deviations were identified.
790315 0 2 6 2
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DETAILS 1.
Persons Contacted Licensee Employees D. G. Beam, Project Manager
- R. A. Morgan, Senior QA Engineer
- R.
P. Ruth, QA Engineer
- S. W. Dressler, Senior Construction Engineer
- L. R. Davison, Senior QC Engineer Other licensee employees contacted included several construction craftsmen, QC technicians and QA personnel.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 9, 1979 with those persons indicated in Paragraph 1, above. There were no items of concern discussed in the exit meeting.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection The inspector conducted a walk through inspection of the Unit 1 and Unit 2 containment and auxiliary buildings to observe the status of construction and to determine if installed or stored in place safety-related equipment and materials were being adequately protected from damage from construction debris and trash.
There were no items of noncompliance or deviations within this area of inspection.
6.
Safety-Related Piping (Welding)-Observation of Work and Work Activities The inspector observed field welding of safety-related piping outside the reactor coolant pressure boundary at various stages of weld com-
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-2-pletion. The applicable code for safety-related pipe welding is ASME B&PV Code,Section III, 1974 Edition with Summer 1974 Addenda as imple-mented by Duke ASME QA Manual.
Observation of field welding activities included, where applicable, the following areas: weld identification and location, joint preparation and alignment, specified weld procedure, welder qualification, specified weld material, specified purge, specified temperature (pre-heat, inter-pass and post-weld heat treatment), welding iariables within limits, evidence of QC verification, physical appearance suitable for NDE and specified NDE being performed.
Pipe to Pipe (PP) and Pipe to Fitting (PF)
a.
Joint Number Type Isometric 1RN 223-3 PF CN-1RN-223 7.
Reactor Coolant Pressure Boundary (RCPB) Piping (Welding I)-Observation of Work and Work Activities The inspector observed field welding of safety-related piping outside the reactor coolant pressure boundary at various stages of weld com-pletion.
The applicable Code for safety-related pipe welding is ASME B&PV Code Section III, 1o74 Edition with Summer 1974 Addenda as implemented by Duke ASME s\\ Manual.
Observation of field welding activities included, where applicable, the following areas: weld identification and location, joint preparation and alignment, specified weld procedure, welder qualification, specified weld material, specified purge, specified temperature (pre-heat, interpass and post _ weld heat treatment), welding variables within limits, evidence of QC verification, physical appearance suitable for NDE and specified NDE being performed.
a.
Joint Fitup Joint Number Isometric System IND 38-4 CN-IND-38 RHR (12" Diameter)
IND 38-18 CN-IND-38 RHR (12" Diameter)
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Root Pass Only Joint Number Isometric System IND 38-18 CN-IND-38 RHR (12" Diameter)
c.
Welding Complete and Testing in Progress Joint Number Isometric System IND-38-20 CN-IND-38 RHR (12" Diameter)
8.
Containment (Structural Steel Welding) Observation of Work and Work Activities The pressurizer lower support for Unit I was being assembled and installed in accordance with Drawing No. CN-1070-4.
The inspector observed welding activities on the lower support including control of welding materials and documenting of welding and QC inspection activities.
There were no items of noncompliance or deviations in this area of inspection.
9.
Containment (Structural Steel Welding) Review of Quality Records The inspector reviewed the welding and inspection records for field welds PS-13 and PS-16 on the pressurizer lower support.
There were no items of noncompliance or deviations in this area of the inspection.