IR 05000327/1979061
| ML19260C286 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/15/1979 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19260C282 | List: |
| References | |
| 50-327-79-61, NUDOCS 7912260151 | |
| Download: ML19260C286 (3) | |
Text
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
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E REGION 11
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101 MARIETTA ST., N.W., SUITE 3100 o,
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ATLANTA, GEORGIA 30303
NOV 161973 Report No. 50-327/79-61 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name:
Sequoyah Nuclear Plant Docket No. 50-327 License No. CPPR-72 Inspection at Sequoyah site near Chattanooga, Tennessee Inspector: b.f uv%
ll 5 ?fi B.~R. Crowley Dite Signed Approved by:
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A. R. Herdt, Section Chief, RC&ES Branch D' te Signed a
SUMMARY Inspection on October 25, 1979 Areas Inspected This special, announced inspection involved 6 inspector-hours onsite in the area of steam generator feedwater line inspection (Bulletin 79-13).
Results No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- J. E. Wilkins, Construction Engineer D. W. Mack, Assistant Construction Engineer C. R. Brimer, Outage Director C. R. Byrant, Mechanical Engineer K. G. Galloway, Level II Examiner L. W. Jones, Supervisor - Mechanical and Welding Inspection NRC Resident Inspector W. T. Cottle
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 25, 1979 with the person indicated in Paragraph I above. The licensee was advised that no items of noncompliance or deviations were identified during the inspection.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
IE Bulletins (IEB)
(0 pen) IEB 79-13, Cracking in Feedwater System Piping, Unit 1.
As follow-up to IEB 79-13, the inspector performed the following inspections:
a.
RT Film Review RT film for the welds and adjacent base material indicated below were re-reviewed after further review by TVA (see IE-RII Report 50-327/79-54).
The applicable code for evaluation is Article NC 5000 of the 1977 Edition of Section III of the ASME Boiler and Pressure Vessel Code, except that a 2T sensitivity was used.
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-2-t Welds IFD - 10 IFD - 11 IFD - 21 IFD - 22 IFD - 130 IFD - 131 IFD - 140 IFD - 141 During this review the inspector noted a questionable area in view 2-3 of weld 1FD-131
" Nozzle". Tha area appears to be small surface irregularities caused by removal of a lug on the outside surface of the nozzle. However, an inspection of the surface is necessary to verify the exact nature of the indications. The licensee agreed to evaluate the questionable area by surface inspection.
b.
Inspections of Supports and Snubbers The licensee has completed an inspection of supports and snubbers as required by paragraph 1.c of the Bulletin and is in the process of reporting the results to NRC. The inspection was conducted in accor-dance Special Maintenance Instruction SMI-1-3-1, revision 0.
The inspector reviewed the inspection " Data Sheets" for the following hangers:
1-FDH-322; Dwg. 1-H4-322 1-FDH-200; Dwg. 1-H4-200 1-FDH-284; Dwg. 1-FDH-284 1-FDH-209; Dwg. 1-H4-209 1-FDH-203; Dwg. 1-H4-203 1-FDH-330; Dwg. 1-H4-330 Within the areas inspected, no items of noncompliance or deviation were identified.
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