IR 05000566/1982001
| ML20054D891 | |
| Person / Time | |
|---|---|
| Site: | Yellow Creek  |
| Issue date: | 03/29/1982 |
| From: | Conlon T, Harris J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20054D884 | List: |
| References | |
| 50-566-82-01, 50-566-82-1, 50-567-82-01, 50-567-82-1, NUDOCS 8204230478 | |
| Download: ML20054D891 (4) | |
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~q UNITED STATES
NUCLEAR REGULATORY COMMISSION'
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REGION 11
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101 MARIETTA ST., N.W., SUITE 3100 o,
C ATLANTA, f,EORGIA 30303 g**ss*
Report Nos. 50-566/82-01 and 50-567/82-01 Licensee:
Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Yellow Creek Docket Nos. 50-566 and 50-567 License Nos. CPPR-172 and CPPR-173 Inspection at Yellow Creek site near luka, MS Inspector:
i)Mhrt4h 3/2 7/& 2-J. R/Ffarris
'Date' Signed
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_p 42 7-PA Approved by
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ection Chief Date Signed E. Conlon, Engineering Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on March 10-12, 1982 Areas Inspected This routine, unannounced inspection involved 20 inspector-hours on site in the areas of extended construction delay program, structural cencrete and previously identified items.
Results
Of the three areas inspected, no violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- L. S. Cox, Project Manager
- D. J. Ward, Supervisor, QA Unit
- R. B. Whitaker, Supervisor, Materials Services Unit
- R. G. Delay, Supervisor, Materials and Civil QC Unit
- C. E. Hale, Assistant Construction Engineer
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- G. French, Supervisor, Mechanical QC Unit Other licensee employees contacted included five construction craftsmen, four technicians, two security force members, and three of fice personnel.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 12, 1982, with those persons indicated in paragraph 1 above.
3.
Licensee /ction on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Independent Inspection The inspector examined ongoing work in the Unit 1 power block, the concrete soils and testing laboratory and backfill operations around the west side of the Unit I reactor building. No violations or deviations were identified.
6.
Extended Construction Delay - Review of Quality Assurance Implementing Procedures, Units 1 and 2 The inspector discussed manpower needs and proposed QA/QC controls for the deferred construction program that was announced by TVA on February 25, 1982, and status of safety related activities.
Discussions with responsible management indicated that the number of trades and labor personnel will be reduced from 1700 to 325 by July 1, 1982 and that the number of annual personnel would be reduced from 325 to 80 by October 1982. Ongoing QA/QC activities will continue to be covered by the existing QA/QC program. The existing QA/QC program will be modified to meet the requirements of the deferred construction program. Modifications are
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currently being developed by management and will be implemented when approved and as needed.
During the construction delay program, ongoing QA/QC activities will consist mainly of receiving inspection, and storage and preservation of safety related materials. Controlling procedures examined by the NRC inspector for receiving inspection, storage and preservation of material, components and systems, and the preventative maintenance program are:
a.
CEP 13.02, Storage and Preservation of Materials, Components and Systems b.
CEP 13.03, Warehouse Storage Area Inspection c.
CEP 7.02, Receiving Inspection d.
S0P 24, Warehouse Receiving e.
50P 25, Field Storage f.
S0P 27, Storage Facility Location Index Guide g.
50P 29, Warehouse Issue of Material h.
50P 48, Inplace Storage i.
S0P 49, Preventative Maintenance Program Four safety related concrete pours consisting of a total of 457 cubic yards remained to be completed as of March 12, 1982. No safety related, welding, electrical, or mechanical activities other than those associated with preparation for the concrete pours was planned or taking place. Observa-tions of ongoing concrete pours indicated activities were being controlled in accordance with the following acceptance criteria:
a.
Section 3.8 of the PSAR b.
TVA Specification G-2, Plain and Reinforced Concrete c.
Procedure QCI C-201, C-202, C-208, and C-12.
No violations or deviations were identified.
7.
Licensee Identified Item 10 CFR 50.55(e)
a.
(Closed) Item 50-566/81-04 and 50-567/81-03:
Unverified Seismic Analysis. During review of design drawings, it was discovered that the final design had been completed and construction drawings issued based on a preliminary seismic analysis for the ERCW pumping station, the equipment hatch access platform, and the waste management building.
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l The inspector examined the licensee's final response dated October 23, l
1981. TVA has completed the final seismic analysis for the structures l
in question. Evaluation of the final seismic loads on the structures
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showed that no changes are required to the final design.
Other TVA nuclear plants are not affected. The requirement of having i
final seismic analysis before completion of construction drawings has been reemphasized to engineers and designers.
This item is closed.
b.
(0 pen) Item 50-566/81-05-02 and 50-567/81-05-02: Tornado Depressuriza-tion Design Deficiency.
Drawings for the intake and ERCW pumping station structures do not provide sufficient vents for adequate
depressurization during tornado conditions.
L This item remains open pending NRC review of the licensee's final response to be submitted to NRC by October 1982.
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