IR 05000321/1978041
| ML19263B462 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/15/1978 |
| From: | Earnestine Clay, Gerald Williams NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19263B455 | List: |
| References | |
| 50-321-78-41, 50-366-78-50, NUDOCS 7901180276 | |
| Download: ML19263B462 (2) | |
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NUCLEAR REGULATORY COMMISSION
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Report No.: 50-321/78-41 and 50-366/78-50 Docket No.: 50-321 and 50-366 License Nos.: DPR-57 and CPPR-90
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Safeguards Group:
IV Licensee: Georgia Power Company 270 Peachtree Street, N.W.
Atltnta, Georgia 30303 Facility Name:
Hatch Nuclear Generating Plant Inspection at: Hatch Nuclear Plant Site Inspection Conducted:
November 20-21, 1978, and December 5, 1978 E. L.-il y J
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Inspector:
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/E Reviewed by: _' 7 / / /
N '~ n e <_
GT H Willia'ms, ]Chie f
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Date Material Contrpi and Accqv6tability Section Safeguards Branch Inspection Summary Inspection on November 20-21, 1978, and December 5, 1978 (Report Nos. 50-321/78-41, and 50-366/78-501 Areas Inspected:
Measurement and controls.
The inspection involved 18 inspector hours onsite by one inspector.
Results: No items of noncompliance were identified.
7901.16 D2 7f,
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RII Report Nos. 50-321/78-41 and 50-366/78-50-1-DETAILS Prepar by:
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f 3/7 j E. L. Clay, Safeguards Engineer Oatd Materials Control and Accountability Section Safeguards Branch Dates of Inspecti
'ovember 20-21 and December 5,1978
/>//3/7S Reviewed by:
w G. H. Williams, Chief ITa te'
Materials Control and Accountability Section Safeguards Branch 1.
Persons Contacted
- Max Manry, Plant Manager
- Harvey Nix, Assistant Plant Manager
- Steve Curtis, Reactor Engineering Supervisor
- Curtiss L. Coggins, Reactor Systems Supervisor Todd A. Cooper, Reactor Engineer Charles Lawrence, Computer Engineer Earl Spell, Jr., QA Supervisor
- John M. Watson, Quality Assurance
- Bill Widner, Manager Power Generation
- Tom Greene, Superintendent of Plant Engineering Services
- Denotes those present at the exit interview.
2.
Measurement and Controls Our inspection consisted of a review of burnup and depletion procedures and practices used by the licensee, and an examination of related records and reports.
It was noted during this inspection that burnup and depletion values for Unit #1 fuel assemblies were being determined one way during cycle opera-tion and by a different way at the end of a cycle. This raised a question which may be generic on burnup and depletion values reported to the NRC on the licensee's Material Status Reports, Form NRC-742.
3.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on December 5, 1978. The inspector summarized the purpose, scope and findings of the inspection.