IR 05000328/1981030
| ML20010A660 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/17/1981 |
| From: | Burnett P, Fiedler R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20010A658 | List: |
| References | |
| 50-328-81-30, NUDOCS 8108110646 | |
| Download: ML20010A660 (3) | |
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NUCLEAR REGULATORY COMMISSION o
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E REGION 11 e[
101 MARIETTA ST N.W., SUITE 3100 o,
o ATLANTA. GEORGIA 3023 Report No. 50-328/81-30 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name:
Sequoyah Unit 2 Docket No. 50-328 License No. CPPR-73
Inspection at Sequoyah Site Chattanooga, Tennessee
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Inspector:
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R. L. Fiedle r Date Signed Approved by:
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. Burnett, feting Section Chief Date Sign id
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Engineering Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspection on June 12-17, 1981 f
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Areas Inspected This routine, announced inspection involved 42 inspector-hours onsite in the area of reviewing preoperational test results.
Results i
No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees J. M. Ballentine, Plant Superintencent
- J. M. McGriff, Assistant Plant Superintendent
- M. Halley, Pre-Op Supervisor 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 June 17, 1981 with those persons indicated in paragraph 1 above.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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Unit 2 Preoperational Testing Results Review The inspector examined the procedures used and the results obtained from the following preoperational tests:
W-1.28 Reactor Coolant System Heatup W-1.3 Reactor Coolant System at Temperature W-1.4 Reactor Coolant System Cooldown W-6.1D SIS - Safety Injection Pump and Related Injection System Performance Test W-6.1E SIS - Residual Heat Removal Pump and Related Injection System Performance Test W-8.1B Reactor Protection Time Response W-8.3 Engineered Safety Features Actuation Operational Test W-11.1 Nuclear Instrumentation System
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The above preoperational test results had not received final approval by
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TVA. Interim engineering design (EN DES) approval of the results for W-1.3, W-6.1D and W-6.1E had been obtained.
Test. deficiencies and exceptions remain open for_ all of the tests reviewed.
The results appeared satis-factory pending _ satisfactory resolution of the remaining deficiencies, exceptions and open items.
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During the. performance of W-1.3, Reactor Coolant System at Temperature, exception #13 was written for the requirement to monitor the differential pressure (DP)' across the reactor coolant ' system (RCS) full flow filter, which is attached to the lower core plate, at least once every 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-throughout the test. Apparently the instrumentation used to monitor the filter DP malfunctioned on April 12, 1981 since this was the date of the last entry on data sheet 5.1 of W-1.3.
There was full flow through the RCS until April 26, 1981. EN DES approved the exception stating that the filter DP was periodically recorded.
The inspector could not find any recorded values for the period following April 12, 1981. The precautions contained in W-1.3 state that "The lower internals baffle plates.may be damaged if. the maximum allowed pressure drop is exceeded."
If the DP across the filter was not monitored, then the resolution to the exception should address the possibility of. damage to'the lower internals. This item was discussed during the exit interview on June 17, 1981. This item will be inspected during. a future inspection (IFI 328/81-30-01).
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