IR 05000491/1979016
| ML19256E365 | |
| Person / Time | |
|---|---|
| Site: | Cherokee  |
| Issue date: | 10/04/1979 |
| From: | Bryant J, Rausch J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19256E357 | List: |
| References | |
| 50-491-79-16, 50-492-79-16, 50-493-79-16, NUDOCS 7911020228 | |
| Download: ML19256E365 (3) | |
Text
{{#Wiki_filter:. . . / 'o,, UNITED STATES
NUCLL'AR REGULATORY COMMISSION o s - i-,' j REGION 11 ' o
101 MARIETTA ST., N.W., SUIT E 3100 N o ATLANTA, GEORGIA 30303
Report Nos. 50-491/79-16, 50-492/79-16, and 50-493/79-16 Licensee: Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 Facility Name: Cherokee Nuclear Plant Docket Nos. 50-491,50-492,and50)f-493 License Nos. CPPR-167, CPT-' w, and CPPR-169 Inspection at Che okee, 'te near Gaffney, South Carolina /#~ f-[[ Inspecto M e- . Rausch Date Signed Approved by: u m /p/f 9 . 'C.' Bryarft/, Section Chief, RC&ES Branch Dite' Signed SUMMARY Inspection on September 13 - 14, 1979 Areas Inspected This routine unannounced inspectran involved 12 inspector-hours onsite in the of QA progr m implementation, concrete plscement and containment plate areas assembly.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
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. b . . DETAILS 1.
Persons Contacted Licensee Employees
- J. W. Willis, Senior QA Engir.:er
- A. R. Hollins, Senior QC Enr,ineer
- K. W. Schmidt, OA Engineer
- H. L. Atkins, si Engineer, echanical Welding and NDE Other licensee employees contacted included technicians and office personnel.
- Attended exit interview
2.
Exit Interview The inspection scope and findings were summarized on September 14, 1979, with those persons indicated in Paragraph 1.
3.
Licensee Action On Previous Inspection Findinos Not inspected.
4.
Unresolved Items Unresolved itmes were not identified during this inspection.
5.
Quality Ass 'rance Manual And Procedure Review Procedure No. M-2 Rev. No. 16, titled " Inspection of Design Ccierete" was reviewed in conjunction with the inspection of testing of concrete for placement in the auxiliary building areas surrounding the containment.
Prepour inspections were being made and information recorded of Form 2A, Prepour Site Inspection. The testing of fresh concrete included the required cast cylinders, performance of air and slump tests and checking of the temperature. Results were being recorded on the licensees form M-2D.
Specification No. P 815-1109.00-00-0001 Rev. No. I titled " Specification for Concrete for Category i Structures" was reviewed in conjunction with the production, delivery, placing and finishing of the concrete.
_.
N;, items of deviation or noncompliance were identified.
6.
Construction Auditing A review of Duke's construction auditing program as established by the qual J assurace program was made. Duke surveillances consist of checking documents, records, concrete placement, welding, maintenance, and other types of construction activities.
Persons responsible for surveillance 1259 295
. -2- . - - develop and maintain senedules for periodic surveillances. They review each new QA and QC procedure upon issuance, documenting results of the review.
The inspector examined procedures, schedules and organization charts and discussed applicability with Duke Management.
No items of deviation or noncompliance were identified.
7.
Independent Inspection Effort The inspector examined various areas of Units 1, 2 and 3 observing construc-tion work and related activities in progress, the general state of cleanliness and housekeeping, and storage conditions of materi-Is. Preassembly of con-tainment plate pieces, located on the preassembly platform was observed. The containment plate sections had been cleaned and ground. Tack welding in preparation for welding was in process.
No items of noncompliance or deviations were identified.
8.
IE Bulletins a.
Closed: IEB 79-11 Faulty Overcurrent Trip Device in Circuit Breakers for Engineered Safety Systems.
Duke replied to this bulletin on July 19, 1979, advising that a review of the design of Cherokee Nuclear Satation revealed that no Westinghouse DB-50 or DB-75 circuit breakers are used or planned for use in safety related systems.
b.
Open: IEB 79-15, Deep Draft Pump Deficiencies. Duke responded to this bulletin on September 6, 1979. Duke identified the manufacturers, models, capacity, plant application quantity and overall dimensions.
Drawings, sectional assemblies and parts lis'. will be examined on a subsequent inspection at the Cherokee Nuclear Plant site.
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