IR 05000321/1980015
| ML19323J113 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/29/1980 |
| From: | Conlon T, Hardwick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19323J108 | List: |
| References | |
| 50-321-80-15, 50-366-80-15, IEB-79-01B, NUDOCS 8006170784 | |
| Download: ML19323J113 (4) | |
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,U UNITED STATES
NUCLEAR REGULATORY COMMISSION o
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REGION 11
101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 30303 APR 3 01980 Report Nos. 50-321/80-15 and 50-366/80-15 Licensee: Georgf.a Power Company 270 Peachtree Street Atlanta, GA 30303 I
Facility Name:
E. I. Hatch Nuclear Plant Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NFP-5 Inspection at Hatch site near Baxley, Georgia Inspector:
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f-29-pa R. J. @ardwick, Jr.
Date Signed
Approved by
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. E. Conlon,~Section Chief, RCES Branch Date Signed SUMMARY Inspection on April 2-4, 1980 Areas Inspected This special, announced inspection involved 17 inspector-hours on site in the area of installed equipment review with respect to the IE Bulletin 79-01B response.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
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s DETAILS 1.
Persons Contacted Licensee Employees
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M. Hanry, Plant Manager
- T. V. Greene, Assistant Plant Manager
- C. R. Locke, Engineering Supervisor C. L. Coggin, Superintendent of Engineering Services
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- P. E. Fornel, Senior QA Field Representative
- W. B. Thigpen, QA Field Representative
- J. T. Hadden, Senior QC Specialist NRC Resident Inspector R. Rogers
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on April 4, 1980 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations. New unresolved items identified during this inspection are discussed in paragraph 5.
5.
IE Bulletin 79-01B, Unit 2
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An examination was made of instrumentation and compento s asscciated with the Residual Heat Removal (Ell) and Nuclear Boiler (821) systems. The
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-2-s equipment that was examined is located inside the drywell. The environ-mental qualification documentation review for this equipment will be per-formed during a future inspection. The specific equipment examined is listed below.
Residual Heat Removal System (RHR)
Motor / Air Operated Valve No.
Cable No.
Electrical Penetration No.
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2E11-F009 AAE717C03 2T52X102A
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EAE702C02 2T52X102A EAE702C25 2T52X102A AAE317M02 2T52X105A 2E11-F022 AAE720C03 2T52X102A AAE320M02 2T52X105A
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2E11-F050A EAE736C03 2T52X102A 2E11-F050B EAE860C03 2T52X103A Nuclear Boiler System Air Operated Valve No.
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2B21-F022B 2B21-F022D During the examination of the installed equipment it was observed that the side covers of electrical penctration assemblies (EPA) T52X102A and T52X105A were not installed. After questioning several licensee personnel and a cursory review by the licensee of the authorized on going work, the reason for EPA cover removal or the point in time of their removal was not deter-mined. The licensee has agreed to further investigate the cause for the EPA cover removal. This item is identified as Unresolved Item 366/80-15-01, Electrical penetration T52X102A and T52X105A covers not installed.
In reviewing the RHR system section drawings for valve numbers 2E11-F050A and 2E11-F009 it was noted that the drawings indicated a valve operator orientation that was different from the actual field installation. The field installation of valve operator orientation on valve number 2E11-F050B could not be determined due to valve disassembly for current outage work.
Discussions with the licensee indicated that a detailed review of the valve installation work packages would be required to assure that the installed valve operator orientation is correct. The licensee has agreed to review the vaive installation work packages. This item is identified as Unresolved Item 366/80-15-02, Valve operator orientation on valve numbers 2E11-F009 and 2E11-F050A.
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After reviewing the name plate data for the Main Steam Isolation Valve (MSIV) 2B21-F022D limit switches, it was noted that an unqualified limit
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switch was installed. The installed limit switch, catalog No. EA7008610, was previously identified as unqualified by IE Bulletin 79-01.
The inspec-tor notified the licensee of the unqualified component and a Licensee Event Report (LER) has been requested.
Within the areas examined, there were no items of noncompliance or deviations
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