IR 05000327/1978040
| ML19263B623 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/14/1978 |
| From: | Donat T, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19263B622 | List: |
| References | |
| 50-327-78-40, NUDOCS 7901220244 | |
| Download: ML19263B623 (4) | |
Text
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Report No.: 50-327/78-40 Docket No.:
50-327 License No.: CPPR-72 Licensee: Tennessee Valley Authority
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830 Power Building Chattanooga, Tennessee 37401 Facility Name: Sequoyah Unit 1 Inspection at: Sequoyah Site, Daisy, Tennessee Inspection conducted: December 4-6, 1978 Inspector:
T. J. Donat Accompanying Personnel:
S. Vajgel (CNEN Inspector)
R. Colosimo (CNEN Inspector)
Approved by:
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R. D. M'artin, Chief Date'
Nuclear Support Section No. 1 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on December 4-6, 1978:
(Report No. 50-327/78-40)
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Areas Inspected:
Routine, announced inspection of preoperational tehi'ng, observation of post RCS hydrostatic test plant restoration, and f acility tour. The inspection involved twenty-one inspector hours onsite by one NRC inspector.
Results: Of the three areas inspected, no item of noncompliance or deviations were identified.
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RII Report No. 50-327/78-40 I-1 s
DETAILS I Prepared by:
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m T.J.'Donat,ReactorIngpector Fat (
Nuclear Support Section No.
Reactor Operations and Nuclear Support Branch Dates of Inspection; ecember 4-6, 197,8
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Reviewed by:
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R. D/ $artin, Chief Hatef Nuclear Support Section No.1 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted
- J. Ballentine, Plant Superintendent
- W. Andrews, Plant QA Staff Supervisor
- E. Condon, Pre-Operational Test Section Supervisor
- J.
W. McGrill, Plant Results Supervisor
- W. Diegel, Construction Coordination Supervisor W. Guin, Operations Supervisor E. H. Bell, Instrumentation Engineer J. Rinne, Construction Coordination Shift Test Engineer J. Richardson, Work Plan Coordinator A. Lehr, Senior Instrument Mechanics Foreman B. Patterson, Instrumentation Engineer
- Denotes those present at the exit interview.
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2.
Licensee Action on Previous Inspection Findings
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Not applicable 3.
Unresolved Items None 4.
Exit Interview The inspectors met with Mr. J. Ballentine and his staff as identified above at the conclusion of the inspection on December 6,1978.
The inspectors summarized, as reported in the following paragraphs the purpose and findings of the inspection.
Within the three areas inspected no items of noncompliance or deviations were identifie.
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RII Report No. 50-327/78-40 I-2 5.
Pre-Operational Test Procedure Review Test Procedure TVA-2C, " Containment Vessel Pressure and Leak Test-Containment Isolation Valve Leak Rate Test" was previously reviewed for conformance to the requirements stated in sections 6.2.1.2, 6.2.1.4, and Table 14.1 of the Sequoyah FSAR and also those presented in ANSI-N45.4-1972. No deficiencies were noted during this preliminary review.
The procedure will be reviewed in greater detail by the regional
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specialist who inspects containment testing progra'ms.
6.
Preoperational Test Witnessing Two preoperational tests were scheduled to be in progress during the inspection interval, " Control System Test of Turbine Runback" (W-8.4)
and " Upper Containment Ventilation System Test" (TVA-4).
The prerequisite section of the Turbine Runback Test, W-8.4, was reviewed to determine if each prerequisite was either signed or provided for by a test exception or an approved change notice. The two change notices which had been issued for the test procedure were checked for proper signatures by the initiating Test Director and the appropriate supervisory signatures depending on whether it was a safety or non-safety related change. Five test instruments being used to establish test conditions, were checked to see if they had current calibration stickers and a review of their most recent calibration data was made.
The test consisted of two parts. The first was a check of the two out of four logic and the associated control room interlocks and annunciations. The second was a timing of the closure of the high speed turbine governor valves. The verification of the two out of four combinational logic for both the "Over Power - Delta T runback /out motion rod stop" and the "Over Temperature - Delta T runback /out motion rod stop" was witnessed by the inspector. 7fh'e inspector witnessed preparations for the turbine governor valvs closure timing including chart recorder calibration and operation of the turbine's governor and intercept valves. The timing of the gov ru r valves closure was not accomplished while the inspector was on-site due to the lack of a suitable signal generator. The inspector had no comments on the areas inspected of W-8.4, Control System Test of Turbine Rurback.
The Upper Containment Ventilation System Test, TVA-4, was originally scheduled to start during this inspection. The inspector performed a review of the test prerequisites including checking that all of the original test drawings had been reviewed and signed by representatives of Engineering Design, Construction, and Power Production signifying that the drawings represented the as built configuration of the system.
The review also checked that there were no outstanding design changes
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RII Report No. 50-327/78-40 I-3 to the system which would affect the test, and that the system was considered operational for testing purposes. Also reviewed were the two procedure changes which had been approved and incorporated into the procedure, and the test exception taken to those prerequisites on the availability of ERCW to the fan air coolers. The test was subse-quently delayed by work in the containment.
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Facility Inspection
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The inspector toured the Unit I containment including each loop cubicle, the pressurizer space and the safety injection system accumulators; the upper head injection rooms; the bottom of the reactor vessel; the main stream isolation valve / safety valve rooms; the auxiliary equipment building; and the control building. The inspector noted that progress had been made in removal of temporary services and scaffolding, and that installation of mirror insulation on reactor coolant systems had begun. Housekeeping and general plant cleanliness were observed and no discrepancies were identified.
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