IR 05000491/1980001
| ML19294B867 | |
| Person / Time | |
|---|---|
| Site: | Cherokee  |
| Issue date: | 02/06/1980 |
| From: | Hunt M, Rausch J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19294B853 | List: |
| References | |
| 50-491-80-01, 50-491-80-1, 50-492-80-01, 50-492-80-1, 50-493-80-01, NUDOCS 8003060225 | |
| Download: ML19294B867 (4) | |
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~,j NUCLEAR REGULATORY COMMISSION
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o ATLANTA, G EORGI A 30303 FEB 61950 Report Nos. 50-491/80-01, 50-492/80-01 and 50-493/80-01 Licensee: Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 Facility Name: Cherokee Nuclear Plant Docket Nos. 50-491, 50-492 and 50-493 License Nos. CPPR-167, CPPR-168 and CPPR-169
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Inspection at Cherokee site near Gaffney, South Carolina Inspector:
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J. K. Rausch
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D' ate / Signed Approved by:
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M. D. H'unt, A'ciing Section Chief, RCES Branch D6te# Signed
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SUMriARY Inspection on January 9-11, 1980 Areas Inspected This routine, unannounced inspection involved 21 inspector-hours onsite in the areas of QA program implementation, containment and other safety related steel structures and supports.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
Licensee Employees
- C. B. Aycock, Project Engineer
- J. W. Willis, Senior QA Engineer
- A. R. Hollins, Senior QC Engineer
- K. W. Schmidt, QA Engineer Other licensee employees contacted included technicians, and office personnel, e
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 11, 1980 with those persons indicated in Paragraph 1 above.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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Independent Inspection The inspector examined various areas of Units 1, 2 and 3 inclusive of the containment and auxiliary building areas of Unit I to observed construction activities in progress.
Installatioa of the spherical containment pieces was in progress. In addition workmen were building forms for containment walls. The inspector examined the common areas of Units 1, 2, and 3 inclusive of the pump structure and auxiliary dams throughout the site.
Various other areas of the site were examined observing construction work and related activities in progress, the general state of housekeeping and storage conditions of materials.
No items of noncompliance or deviations were identified.
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QA Implementation Procedures
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The inspector reviewed the quality assurance, implementing procedures used by the onsite QA & QC personnel to inst re quality relative to containment and other safety related steel structures and supports. The procedures
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identified below are those utilized by QA/QC to inspect and follow specific activities.
These procedures (exclusive of welding) were reviewed in part by the inspector.
Procedure M-7 " Containment and Tank Plate Erection Inspection, Rev. 3
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(non-nuclear safety related).
Procedure M-18, " Inspection of Structural Steel Erection" Rev. 5 Procedure M-71, " Process Control and Inspection of Containment Systems and Liner Plate" Rev. 1 Construction Procedure F-1A " Containment Plate Erection", Rev. 6
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Construction Procedure Form F-1A " Install; tion, Welding and Inspection of the Annulus Extension System for the Spherical Containment Building", Rev.
- Construction Procedure Form F-1A, " Installation and Welding Procedure for Containment Vessel", Rev. 6 Conctruction Procedure Form F-1A, " Nondestructive Testing Requirements for Reactor Building Containment Plate (ASME Seccion III, Subsection NE)
Construction Procedure, Form F-1A, " Containment Plate Erections" Rev. 6 No items of noncompliance or deviations were identified.
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IE Bulletin Status Closed IEB 79-25, Failures of Westinghouse BFD Relays in Safety Related Systems.
Duke Power replied on January 4,1980 that a review of the Cherokee Nuclear Station design has revealed that none of the Westinghouse BFD/N13FD relays specifie/- in the subject bulletin are used or planned for use in the safety-related systems at Cherokee.
Closed IEB 79-23, Potential Failure of Emergency Diesel Generator Field Exciter Transformer. Duke Power replied on November 2, 1979 that a review of the Cherokee Nuclear Station design has confirmed that connections have not been made between low KVA rated transformers and high KVA emergency diesel generators without adequate limitations on the flow of circulatory currents at these stations. The diesel generator factory test for Cherokee is expected to be complete April 1, 1983.
Open IEB 79-14 Seismic Analyses for As-built Safety Related Piping Systems.
Duke Power replied on October 30, 1979 that erection of systems at therokee Nuclear Station has not progressed to the point that significant comparisons between design documents and as-built configuration are possible. Duke plans to make the comparison identified in the subject bulletin during their normal inspection progra.
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3-Open IEB 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts.
Licensee response to the subject bulletin are under review by RII.
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