IR 05000269/1980018
| ML19320B765 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/28/1980 |
| From: | Conlon T, Harris J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19320B760 | List: |
| References | |
| 50-269-80-18, 50-270-80-13, 50-287-80-12, NUDOCS 8007150021 | |
| Download: ML19320B765 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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If REGION 11
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101 MARIETTA sT., N.W., sulTE 3100
ATLANTA, GEORGIA 3o303
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MAY 2 91980 Report Nos. 50-269/80-18, 50-270/80-13 and 50-287/80-12 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: Oconee Nuclear Station Docket Nos. 50-269, 50-270 and 50-287 License Nos. DPR-38, DPR-47 and DPR-55 Inspection at Oconee site near Seneca, South Carolina Inspector:
iD hM, f/)f/cFu J. R. Hapis
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/Date' Signed Approved by: o 6p;#
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O T. E. Conlon, Section Chief, RCES Branch
'Date' Signed SUMMARY Inspection on May 13-15, 1980 Areas Inspected This routine, unannounced inspection involved 20 inspector-hours on site in the areas of structural concrete for the standby shutdown facility.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee' Employees J. E. Smith, Station Manager
- R. J. Brackett, Station Senior QA Engineer
- R. T. Bond, Licensing Project Engineer G. Sheperd, Site Civil Engineer
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- G. Vaughn, Assistant Manager
- R. Calhoun, Licensing Project Engineer
- T. C. Matthews, Licensing Technical Specialist NRC Resident Inspector F. Jape
- Attended exit interview 2.
Exit Interview i
The inspection scope and findings were summarized on May 15, 1980 with those persons indicated in Paragraph I above.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items
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Unresolved items were not identified during this inspection.
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Independent Inspection The inspector examined procedures, specifications, drawings, records and results of work on structural concrete for the Standby Shutdown Facility.
This facility is being constructed to augment existing shutdown capabilities and will provide an afternate means to achieve and maintain a hot shutdown condition. The facility is designed to meet a remote shutdown capability relative to the fire program, the modified amended security plan, and turbine building flooding. Acceptance criteria examined by the inspector
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appear in the NRC letter dated December 29, 1979, from Robert Reid, Chief, Operating Reactors Branch #4, to Mr. Willia a 0. Parker, Jr., Vice President Steam Production, Duke Power Company, and tetion 17 of Topical Report, Duke - 1A. procedures, specifications and arawings examined by the inspector vere:
Procedure Qr'-1, Inspection of Safety Related Concrete.
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Procedure QCG-1, Receipt Inspection and Control of Materials, Parts and Components Important to Nuclear Safety.
Specification OS-160-1, Concrete for Nuclear Safety Related Structures.
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Specification OS-160-2, Receiving and Placing Concrete for Safety Related structures.
Drawing numbers 0-320-A t'o 0320-G, Standby Shutdown Facility Plans.
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Drawing number 0-3LO-J6K, Miscellaneous Steel.
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Drawing number 0-320-S, Reinforcing Steel.
Records examined by the inspector incluu;; batch tickets, test cylinder data, results of in process testing and certification, and test data on concrete materials.
Examination of the batch plant and discussions with responsible engineers disclosed that concrete operations have been temporarily suspended pending adjustments for hot weather operations.
No deviations or items of noncompliance were disclosed.
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