IR 05000528/1980007
| ML17296A900 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/10/1980 |
| From: | Dodds R, Vorderbrueggen NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17296A898 | List: |
| References | |
| 50-528-80-07, 50-528-80-7, 50-529-80-07, 50-529-80-7, 50-530-80-07, 50-530-80-7, NUDOCS 8008070492 | |
| Download: ML17296A900 (10) | |
Text
50-528/80-07 50-529/80-07 Report No.
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NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Docket No.
50-528 50-529 50-53 License No.
Arizona Public Service Company P. 0.
Box 21666 Phoenix Arizona 85036 Safeguards Group Facility Name:
Palo Verde Nu lear Gene d 3 Inspection at:
Inspection conducte A ri 1 1-30 1980 Inspectors'.
E. Vorderbr en Resident Reactor Inspector Date Signed Date Signed roved By:
Date Signed c
8c Date Signed R. T. Dodds, Chs
,
. Support Section Reactor Construction 8 Engineering Support Branch Ins ection on A ril 1-30, 1980 Re ort Nos. 50-528/80-07, 50-529/80-07, 50-530/80-07
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by the Resident Inspector including:
Unit 1 spray pond piping installation and reactor internals storage, Unit 2 reactor vessel/steam generator storage and steam generator support installation, Unit 3 reinforcing steel cadwelding and containment liner welding, review of licensee evaluation of polar crane support girder fabrication deficiency, and miscellaneous work in progress.
The inspection involved 60 inspector hours on-site by one NRC inspector.
Results:
Ho deviations or items of noncompliance were identified.
RV Form 219 ('2)
soosovo /P DETAILS 1.
Persons Contacted a.
Arizona Public Service Com an APS
- E. E.
Van Brunt, Jr., Vice President, Nuclear Projects Management
//*J. A. Roedel, Manager, guality Assurance n*W. E. Ide, Site gA Supervisor
- S. Kesler, Supervising Engineer
- R. D. Forrester, gA Engineer G. Pankonin, gA Engineer b.
Bechtel Power Cor oration Bechtel
- W. J. Stubblefield, Field Construction Manager D.
R. Hawkinson, Project gA Supervisor
- C. E. Gaither, Assistant Project Field Engineer
- R. M. Grant, Project gC Engineer B. Leuniz, Boilermaker Superintendent
- D. T. Krisha, gA Supervisor
- J.
E. Pfunder, gA Engineer B
Campo, Nuclear Field Engineer E. Stone, Welding Engineer D. Jacks, gC Engineer J.
McDermott, gC Engineer Other persons contacted included construction craftsmen, inspectors, and craft supervisory personnel.
- - Attendees a't management meeting on April 18, 1980
Attendees at management meeting on April 30, 1980 2.
Unit
S ra Pond Pi in Work activities associated with installation of the stainless steel piping in the spray pond were examined by the inspector.
The general area appeared orderly, piping was properly supported on wooden blocks or adjustable pipe tripods, and pipe openings not being worked on were capped.
Welders were exercising proper care of welding electrodes and discarding their stubs into stub buckets.
The tack welds joining spools 006 and 007 in spray header 1-SP-022, and spools 001 and 002 in header 1-SP-021 had been completed and were examined by the inspector.
Both weld joints had a properly filled out Field Welding Check List (WR-5 form).
The piping material was the specified 14-inch schedule 20, ASTM SA312-316L stainless steel.
The applicable drawing was 13-P-ZYA-069, and the welding procedure specified on the WR-5 forms was PB-AT-Ag.
The welder's qualification record was subsequently examined and found acceptable.
No deviations or items of noncompliance were identifie Unit 1 Reactor Vessel and Internals Several times during this report period while making general tours of the Unit 1 containment building, the inspector examined the storage conditions associated with the reactor vessel and the vessel internals.
The core barrel, the core support structure and the upper guide structure are separately wrapped and stored at the two ends of the reactor pool area, and appeared to be adequately protected.
The reactor vessel, though accessible for interior work, appeared to be reasonably clean of construction materials and debris, and appeared to be adequately protected.
Unit 2 Reactor Vessel and Steam Generator Stora e
The reactor vessel and the one steam generator that has arrived onsite are stored in the large component outdoor storage yard north of Unit
Both components are still fastened. to their steel transport carriages and are supported on steel bar beams and wood cribbing.
The inspector observed that a positive nitrogen pressure was present in the primary and secondary sides of the steam generator and its exterior strippable coating was in good condition.
The reactor vessel was fitted with an interior humidity indicator.
All openings in both vessels were properly covered and sealed.
The storage area was free of debris and was appropriately enclosed with a rope to restrict personnel and vehicle access.
No deviations or items of noncompliance were identified.
Unit 2 Steam Generator Su orts Due to differential movement between the shims in the "shim stacks" under the sliding bases supporting the Unit 1 steam generators, Bechtel modified the shim design for the Unit 2 and 3 steam generators.
(Reference:
Inspection Reports 50-528/79-05 and 79-11).
Each of the redesigned
"shim stacks" consist of two approximately 3-inch thick steel plates which are doweled together to prevent differential movement.
The lower plate is welded to the embedded steel in the support structure using a 1/2-inch fillet weld along two sides of the plate.
Difficulties were encountered when the lower shim plates for steam generator No.
1 were welded in place.
On the generator east-west center-line (the first shim plates to be welded) the embed plates are 4-inches thick and the fillet welds to these embeds were satisfactory.
On the generator north-south center-line, however, the embeds are 12-inch thick forgings and the shim plates fillet welds cracked soon after completion.
The weld cracking was due to the fast cool down rate resulting from the large heat sink presented by the massive forging The cracked welds were removed by grinding in accordance with the approved weld repair procedure.
The inspector observed the NDE techniciah perform the required magnetic particle examination of the ground forging surface.
The surface was free of crack indications.
The examination technique used by the NDE examiner was in accordance with the approved procedure.
On the following day the inspector observed the fillet welds being redone.
This time the welding was performed after overnight preheating of the embedded forgings using electric blankets, followed by the use of localized heating with acetylene torches immediately prior to welding.
The preheat tempera-ture specified was 450'F minimum, and this was checked by the use of a contact pyrometer.
The maximum temperature limitation was 500'F which was the allowable limit of the surrounding concrete.
The
'nspector examined the completed welds after the materials had returned to ambient temperature.
The welds appeared to be sound and there was no evidence of any deleterious effects on the adjacent concrete.
The inspector also observed the subsequent placement of concrete for the sliding support base for steam generator No.
1.
Prior examination of the graphite-buttoned slide plates (which rest on the aforementioned shim plates)
was made by the inspector.
He also reviewed the constructor's Construction Inspection Plan (CIP) No. 350.39-2.
The placement appeared well organized and was in accordance with the procedure.
No deviations or items of noncompliance were identified.
Unit 3 Containment Liner Heldin Activities associated with liner plate erection, fitup and welding were observed by the inspector.
The vertical seam welds are being made with an automatic machine using the flux-core process.
Several vertical seams were visually examined and appeared to be high quality welds.
Attempts were made to use the automatic machine for horizontal welds but the results have not yet been satisfactory, The inspector watched one horizontal seam segment being welded with the automatic machine.
The resulting weld was laden with surface porosity and had to be removed.
Subsequently the seam was rewelded using the standard manual SHAH process.
The Bechtel superintendent expressed confidence that the automatic machine would work satisfactorily after some refinements were made in the control settings.
The inspector also observed vacuum box testing of the welds joining floor segments 3B-48 and -49, and 3B-48 and thickened floor segment P-72 at about azimuth 55-degrees near the outer containment periphery.
The weld seams displayed no leakage under an applied vacuum of 10 psig for a period of 20 seconds.
The vacuum gage was noted to have a current calibration.sticker attached.
The test procedure followed is outlined in specification No. 13-Ct5-370,
"Erecting the Containment Building Liner Plate System."
No deviation or items of noncompliance were identifie.
Unit 3 Containment Shield Wall Cadweldin The inspector observed the preparation and firing of 4 B-series cadwelds at about the 180-degree azimuth in the south shield wall inside containment.
In addition, the inspector examined 10 adjacent B-series cadwelds in the shield wall made by the same two welders.
The governing specification was No. 13-CM-375, "Placing of Reinforcing Steel."
The qualification records of the two workmen were subsequently checked and the overall system for tracking cadwelder qualification was reviewed.
No deviations or items of noncompliance were identified.
8.
Plant Tours The construction site was toured by the inspector at various times each week during this reporting period.
Particular attention was directed to work in progress, presence of supervision at the work locations, care and preservation of equipment, general housekeeping conditions, and routine implementation of quality assurance program requirements.
9.
Mana ement Meetin s
t On April 18 and 30, 1980, the inspector met with the project personnel denoted in Paragraph No.
and summarized the scope of the inspection activities and the inspection findings as described i,n this report,
t