IR 05000395/1979032
| ML19256G455 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/16/1979 |
| From: | Conlon T, Ruff A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19256G451 | List: |
| References | |
| 50-395-79-32, NUDOCS 7912310331 | |
| Download: ML19256G455 (3) | |
Text
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o UNITED STATES
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g NUCLEAR REGULATORY COMMISSION
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ATLANTA, GEORGIA 30303 Report No. 50-395/79-32 Licensee: South Carolina Electric and Gas Company Columbia, South Carolina 29218 Facility Name:
V. C. Summer Nuclear Station Docket No. 50-395 License No. CPPR-94 Inspection at V. C. Summer Site near Columbia, South Carolina Inspector b
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A. B. Ruff ~
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- Accompanying Personnel: Norman Merriweather Approved b
// -/ d-7 9 T. E. Conlon, Section Chief, RC&ES Branch Date Signed SUMMARY Inspection on October 30-31, and November 1-2, 1979 Areas Inspected This routine, unannounced inspection involved 26 inspector-hours onsite in the areas of safety-related electrical cable ir.stallation and Quality Control (QC:
records, and safety-related instrumentation installation and QC records.
m Results Of the areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- J. F. Algar, Site Manager
- M. B. Jones, Construction Manager
- A.
A. Smith, Site QA Coordinator
- E. Evans, QA Engineer D. Dawkin, QC Electrical Inspector Other Organizations Daniel Construction Keith Deistel, Instrument ai Control Engineer NRC Resident Inspector
- J. L. Skolds
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on November 2, 1979, with those persons indicated in Paragraph 1 above.
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 in the reactor building, Auxiliary Building, intermediate building, and control building.
During this inspection safety-related cables and cable tray installations were observed.
Several 7.2 KV safety-related cables, CCM 33A,12A,11A, and 17A, were selected as part of this examination. Those items and associated records were examined in areas of nonconformance control, receipt inspec-tion, installation, identification, termination (at switchgear end only)
and grounding. The procedures used in this examination were FQCP-2.1.4,
"Nonconformance Control and Procedure", FQCP -3.1.0, " Receiving Inspection",
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s-2-FQCP-7.1.1, " Cable Pulling", FQCP-7.1.2, " Cable Termination", and Drawing S-200-912, including Field Change Request A 335E to this drawing, " Electrical Construction Guide for Cable Installation". Within the areas examined no items of noncompliance or deviations were identified.
6.
Instrumentation (Components and System I) - Observation of Work,' Work Activities and Review of Quality Records
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Two flow transmitters (FT 425 & 436) in the Reactor Coolant System were examined in the areas of installation including location and mounting, receipt inspection, storage inspection, handling and identification.
Procedures used in this examination were FQCP-3.1.0, " Receiving Inspec-tion", FQCP-3.2.0, " Storage, Handling and Issuing", FQCP-3.3.0, "Identi-fication and Status Control", and QCP-VIl-09, " Pipe Installation Inspection".
During the infield examination, it was noted that the cable connection box part of the transmitter had manufacturer's supplied mounting brackets that were not being used.
The licensee has agreed to determine if the internal connections between the transmitter housing and the cable connection box portion are adequate supports for the cable connection box. This is an Inspector Follow-up Item identified as 50-395/79-32-01, " Manufacturer's Connection Box Support Brackets on Flow Transmitters".
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