IR 05000327/1979051
| ML19210D283 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/12/1979 |
| From: | Cantrell F, Gouge M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19210D276 | List: |
| References | |
| 50-327-79-51, 50-328-79-27, NUDOCS 7911260227 | |
| Download: ML19210D283 (5) | |
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%*****o ATLANTA, G EORGIA 30303 OCT 121979 Report Nos. 50-327/79-51 and 50-328/79-27 Licensee: Tennessee Valley Authority 500A, Chestnut Street Tower II Chattanooga, Tennessee 37401 Facility Name: Sequoyah Nuclear Plant, Units 1 and 2 License Nos. CPPR-72 and CPPR-73 Inspection at Sequoyah site near Daisy, Tennessee
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/ I Inspected by:
we M. J. Gouge
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Date Signed Approved by:
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F. S. Cantrell, Section Chief &G6ES Branch Dat'e Sif,ned y
Date of Inspection: September 18-20, 1979 Areas Inspected This routine, unannounced inspection involved 23 inspector-hours onsite in the areas of licensee action on previous inspection findings (Unit 2), inspector followup items (Unit 1), and 10 CFR 50.55(e) items.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted Licensee Employees
- J. E. Wilkens, Construction Engineer
- R. W. Olson, Assistant Construction Engineer
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- D. W. Mack, Assistant Construction Engineer
- J. L. Smith, Assistant Construction Engineer
- J. M. Munns, Supervisor, Construction QA Unit W. E. Andrews, Supervisor, QA Staff, Sequoyah Nuclear Station
- R. L. Hamilton, QA Engineer, Sequoyah Nuclear Station
- R. W. Farrell, Supervisor, QC hecords Unit L. W. Jones, Supervisor, Welding Inspection Unit
- M. A. McBurnett, Nuclear Engineer, Regulatory Staff
- E. C. Pendergrass, Engineer, QC Records Unit J. A. Hauerter, Welding Inspection Unit J. A. Thompson, Assistant Supervisor, Unit 1 Coordination Unit J. Bajreszewski, Mechanical Engineering Unit J. H. Rinne, Unit 1 Coordination Unit B. Edwards, Unit 1 Coordination Unit Other licensee employees contacted included various construction craftsmen, technicians and office personnel.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on September 20, 1979, with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings (Closed) Infraction 50-328/79-24-06:
Inadequate Welder Qualification. The licensee's corrective action is specified in the response letter dated September 21, 1979. Region II has reviewed this response which describes acceptable measures to correct the ncncompliance and to prevent recurrence of simila r problems. TVA has reworked welds 2CVC-163, 164, and 165 with welders q.alified to the weld procedure specified. Weld 2CVC-166 was conducted by two welders neither of which exceeded the wall thickness they were qualified to weld and no corrective action was necessary for this weld. The licensee has reviewed completed weld records and determined that, as of September 18, 1979, about 109 welds had been conducted by welders not qualified to the particular wall thickness of pipe welded.
This problem has been documented by site originated nonconformance reports (NCR's) 1848 and 1849. The licensee will accept the welds based on non-1701 323
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destructive examination and by previous or post qualification of welders as appropriate. Welding foremen and inspectors have been instructed on the importance of ensuring that welders are qualified fully to the weld proce-dure specified.
4.
Unresolved Items Unresolved ' items were not identified during this inspection.
5.
Inspector Followup Items (Unit 1)
a.
(Closed) IFI 50-327/79-06-01: Disposition of UT Indication for Weld RER-S119. The licensee conducted a repair on the subject shop weld to remove the linear indication found by ultrasonic testing (UT). The final repair passed visual testing, dye penetrant testing, radiographic testing and ultrasonic testing, b.
(Closed) IFI 50-327/79-19-02: Reactor Vessel Closure Head Weld Indi-cation. The licensee has conducted a fractare mechanics analysis as discussed in IE Inspection Report 50-327/79-23. The results of this analysis have been forwarded to Region II and NRR by the licensee as required by paragraph IWB-3600 of ASME Section XI. The Materials Engineering Branch (NRR) reviewed the analysis report submitted by TVA entitled " Analytical Evaluation of a Flaw Indication in the Unit 1 Reactor Vessel Closure Head".
The Materials Engineering Branch con-cluded in a memorandum from S. S. Pawlicki to L. Rubenstein dated September 6, 1979, that "...the flawed component has adequate safety margin and is acceptable for service."
6.
Licensee Idnetified Items (Units 1 and 2)
TVA has reported a number of items to Region II as reportable events in compliance with 10 CFR 50.55(e). The inspector reviewed the items listed below and the supporting documentation, and discussed the items with re-sponsible licensee staff during the inspection.
a.
(Closed) Item 50-328/78-27-04: Safety Injection Rate into Reactor Coolant System. This item was closed for Unit 1 in IE Inspection Report 50-327/79-44.
Corrective action for Unit 2 is identical to that described for Unit 1.
The licensee's letter of March 9, 1979, and the above Unit I report document required corrective action.
b.
(Closed) Item 50-328/79-11-01: Accumulator Level Transmitter Lines.
The inspector reviewed the TVA final report dated March 30, 1979, closed NCR SWP 79-S-4 and closed ECN 2250. All required work has been completed with the exception of final inspection. The final inspec-tion will be documented on the four open work packages for this ECN.
c.
(Closed) Item 50-328/79-11-02:
Overheating of Bearings in Motor Driven AFW Pumps. The inspector reviewed the TVA final report dated April 7,1979, the closed NCR MEB 79-11 and the revised vendor drawings 1zo1 T24
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2AFD-156 R1 and 2AFD-157 R1 that incorporate the design modification to correct the bearing overheating problem. Work package F137M003-014
'as been issued to control this modification. The work package and a
revised drawings will ensare that the required corrective action is accomplished for Unit 2.
The work will be done prior to Unit 2 fuel loading.
d.
(Closed) Item 50-327/79-36-04 end 50-328/79-21-04: Class IE Junction Boxes in Containment Not Environmentally Qualified. The inspector reviewed the final TVA report dated July 12, 1979, the closed NCR EEB 79-7, and the closed ECN's 2498 and 2522.
The corrective action discussed in the final report is in progress in Unit 1 in accordance with work plan 3360. This item is on the outstanding work items list (0WIL) and is required to be completed prior to fuel loading of each respective unit. Work on Unit 2 has not commenced but will be conducted in accordance with work package F243E074-007 (and others) and the drawings revised by the above ECN's.
e.
(Closed) Item 50-327/79-36-06 and 50-328/79-21-06: Pipe Restraint Structural Strand Temperature. The inspector reviewed the TVA final report dated June 18, 1979, the closed NCR MEB 79-18 and Unit I work plan 1889. Work is nearing completion on Unit I and is being accom-plished in accordance with work plan 1889 and revised vendor drawings.
The status on this item is indicated on the OWIL. All required work will be done prior to fuel loading of each respective unit. Work on Unit 2 will be accomplished in accordance with a work package and revised vendor drawings.
f.
(Closed) Item 50-327/79-36-07 and 50-328/79-21-07: Pipe Support Deflection Summation. The inspector reviewed the TVA final report dated September 7, 1979, the closed NCR SWP 79-S-7 and the closed ECN 2416. Work is nearing completion on Unit I and is being accomplished in accordance with work plans 4715, 4717 and others. The status of this item is indicated on the OWIL. The licensee stated in the final report that all corrective action will be accomplished prior to attain-ing 1% power on the respective units.
The project inspector stated during the exit meeting that this item must be completed prior to fuel loading. Work on Unit 2 will be conducted in accordance with the drawings as revised by ECN 2416.
g.
(Closed) Item 50-327/79-34-14:
Corrosion of Terminal Blocks in Junction Boxes. The inspector reviewed the TVA final report dated August 31, 1979, the closed NCR 9P, and the closed ECN's 2520 and 2521. Work on Unit 1 is being conducted in accordance with Special Maintenance Instructions (SMI) 360-1 and 360-2.
Work will be com-pleted prior to fuel loading of Unit 1.
This item remains open for Unit 2 (item 50-328/79-24-05).
h.
(Closed) Item 50-327/79-36-15: Flexible Bellows Penetration Mis-alignment. The inspector reviewed the TVA final report dated September 11, 1979, the closed NCR 1666 and work plans 4133 and 1701 325
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4133A. Discussions with the responsible engineer indicated that work on this item has been completed and the work plans will be closed after final inspection of the completed work.
i.
(Closed) Item 50-327/79-43-04 and 50-328/79-24-04: Electrical Conduit Qualification. The inspector reviewed the TVA final report dated August 16, 1979. The final report stated that analysis by the licen-see's design group of this item, NCR CDB 79-4, indicated that the structural design of the six conduit handholes was adequate for all design basis events.
j.
(Open) Item 50-327/79-51-01 and 50-328/79-27-01: Excessive Output Fluctuations of Foxboro Instrumentation. On August 28, 1979, TVA informed Region II of this reportable item identified as NCR SWP 79-S-5.
A 30 day written report is due September 27, 1979.
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