IR 05000327/1982001
| ML20050A374 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/01/1982 |
| From: | Fiedler R, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20050A371 | List: |
| References | |
| 50-327-82-01, 50-327-82-1, 50-328-82-01, 50-328-82-1, NUDOCS 8204010224 | |
| Download: ML20050A374 (3) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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E REGION 11 101 MARIETT A ST., N.W., SUITE 3100 o,
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ATLANTA, GEORGIA 30303
- eses Report Nos. 50-327/82-01 and 50-328/82-01 Liceasee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, TN 37401 Facility Name:
Sequoyah Docket Nos. 50-327 and 50-328 License Nos. DPR-77 and UPR-79 Inspection at Sequoyah site near Chattanooga, TN Inspector:
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Date Signed Approved by:
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Date' Signed Engineering Inspect 4<fn Brarich Engineering and Technical Inspection Division SUMMARY Inspection on January 25-27, 1982 Areas Inspected This routine, unannounced inspection involved 24 inspector-hours on site in the areas of review of power ascension ' test procedures, power ascension test wit-nessing and a tour of Unit 1.
Results Of the three areas inspected, no violations or deviations were identified.
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-C204010224 820300 PDR ADOC% 05000327 PDR
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REPORT DETAILS 1.
Persons Contacted Licensee Employees W. T. Cottle, Assistant Plant Superintendent
- J. M. McGriff, Assistant Plant Superintendent R. Fortenberry, Nuclear Engineer
- T. Howard, quality Engineering Supervisor
- A. Carver, Compliance Other licensee employees contacted included startup test personnel and several operators.
NRC Resident Inspector E. Ford, Senior Resident Inspector S. D. Butler, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 27, 1982, with those persons indicated in paragraph 1 above.
The findings were acknowl-edged without significant comment.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Review of Power Ascension Test Procedures The following power ascension test procedures were reviewed:
a.
50-1.1 rev. 3 Loss of Offsite Power b.
SU-1.2A rev. 3 Shutdown from Outside Control Room c.
SU-1.28 rev. 2 Cooldown from Outside Control Room d.
50-7.3.2 rev. 2 Nuclear Design Check Tests:
Low Power Flux Mapping l
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e.
50-8.1 rev. 7 Power Coefficient and Integral Power Defect Measurement f.
SU-8.3 rev. 7 Static kCCA Drop and RCCA Below Bank Position Measurement g.
SU-9.4A rev. 6 Plant Trip From 100*. Power h.
SU-9.4B rev. 6 100% Net Load Trip The procedures were reviewed to verify the following:
a.
That the testing commitments of FSAR Chapter 14 have been included.
b.
That the procedure had been properly reviewed and approved c.
That the procedure contained adequate prerequisites.
d.
That the test objectives are clearly stated.
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That acceptance criteria against which the test will be judged are clearly identified.
f.
That step-by-step instructions for the performance cf the procedure are complete to the extent necessary to assure that test objective are met.
The procedures appeared adequate.
6.
Power Ascension Test Witnessing The performance of SU-8.1 Power Coefficient and Integral Power Defect Measurement, at 30% power was witnessed by the inspector. The performance of the test appeared adequate.
7.
Tour of Unit 1 A tour of the accessible areas was conducted to determine by observation that plant conditions and activities were in accordance with applicable requirements.