IR 05000528/1980013
| ML17296B009 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/09/1980 |
| From: | Dodds R, Vorderbrueggen NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17296B008 | List: |
| References | |
| 50-528-80-13, 50-529-80-13, 50-530-80-13, NUDOCS 8010170662 | |
| Download: ML17296B009 (7) | |
Text
Report No.
50-528/80-13 50-529/80-13 50-53 U ~
S ~
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Docket No. 50-528 529 License No. CPPR-141-142-143 Safeguards Group Licensee:
Arizona Public Service Com an Facility Name:
Palo Verde Nuclear Gen Inspection at, Palo Verde Construction Site, Mintersbur, Arizona Inspection conducted:
Jul 14-25, 1980 nd
Inspectors:
~
~
L.
E. Vor(evbrueggen, Resident Reactor Inspector Date Signed Date Signed Approved By:
~
~
R..
Dogds C ief, Engineering Support Section Reactor Construction
& Engineering Support Branch Date Signed r/<1~b Date Signed Suamary:
Ins ection on Jul 14-25, 1980 (Re ort Nos. 50-528/80-13, 50-529/80-13, and 50-530/80-13
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l, dl p
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p of construction activities including:
closure of Unit 1 containment building construction opening, piping and components inside Unit 1 Hain Steam Supply System support structure, reinforcing steel omission from containment building wall for all three units, erection of Unit 2 containment dome liner segments, Unit 2 reactor vessel installation, Unit 2 cooling tower erection, piping in Unit 3 auxiliary building, and general activities in progress at the site.
The inspection involved 25 inspector hours on-site by one NRC inspector, Results:
No deviations or items of noncompliance were identified.
RV Form 219 (2)
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 W. E. Ide, Site gA Supervisor G. Pankonin, gA Engineer R.
D. Forrester, gA Engineer L. Souza, gA Engineer b.
Bechtel Power Cor oration Bechtel)
W.
G.
Bingham, Project Engineering Manager S.
M. Nickell, Construction Superintendent D.
R. Hawkinson, Project gA Supervisor R.
M. Grant, Project gC Engineer J.
L. Black, Resident Engineer R.
Hoke, guality Control Engineer D. Jacks, guality Control Engineer C. Stalnaker, Unit 2 General Superintendent Other persons contacted during the inspection period included construction craftsmen, inspectors and supervisory personnel.
2.
Unit 1 - Containment Buildin Construction 0 enin Work activities associated with concrete placement No.
1C-125A for construction opening closure from elevation 118-ft. to elevation 140-ft. were observed by the inspector.
The governing specifications were Nos.
13-CM-375, Placing of Reinforcing Steel, and 13-CM-371, Installation of Post-Tensioning Trumplate Assemblies and Sheathing.
The reinforcing steel and the tendon sheaths had been previously spliced to complete the uninterrupted matrix for the entire opening.
Several cadwelds joining reinforcing steel segments were examined and sheathing tie-down spacing was checked.
Carpenters were in the process of placing and supporting the concrete formwork.
The concrete construction joint had been cleaned and was essentially ready to accept fresh concrete.
No deviations or items of noncompliance were identifie.
Unit 1 - Pi in and Com onents Inside NSSS Structure Installation activities were associated with the auxiliary feedwater and steam generator blowdown piping and the associated valves and supports were observed by the inspector.
Several completed welds were examined and were seen to display quality.
All pipe openings not being worked on were appropriately capped and weld filler metal appeared to be under proper control.
lleld No. W-031, joining spool 019 from Valve No. V-130 to check valve Y-642, was selected for documentation review.
This weld was originally "field fabricated" with schedule
material for spool 019; a subsequent design change specified schedule 120 thickness for the spool which established a nonconforming situation for the original weld.
A new valve was substituted for V-642 (new weld prep machining was required)
which required'eld 031 to be cut out and remade.
This condition was properly documented and dispositioned on NCR-PC-1081.
The Field Melding Check List (llR-5 form) was properly completed regarding specified procedures, materials, and inspection verification points.
The welder's qualification was checked and found to be satisfactory.
The final weld had not yet been radiographically examined.
The governing drawing is No. 13-P-SGF-145, t1SSS Isometric-Downcomer Feedwater and the governing specification is 13-Ptl-204, Field Fabrication and Installation of Nuclear Piping Systems.
No deviations or items of noncompliance were identified.
4.
Units 1,
and 3 - Omitted Reinforcin Steel in Containment Buildin Mall The inspector reviewed the condition described in Bechtel Deficiency Report No. 80-19 pertaining to the omission of reinforcing steel in certain localized segments of the circumferential joint between the containment exterior wall and the basemat.
This situation was discovered by Bechtel during design review and comparison of drawings with the supporting design calculations.
The segments affected are those which have mechanical penetrations located approximately 10 to 15 feet above the joint.
This constitutes a region of approximately 110-degrees of the circumference spread over a 150-degree section adjacent to the auxiliary building.
In these segments, the construction drawings did not show reinforcing steel continuing up from the dowels in the basemat to the trim reinforcement around the penetrations, thereby improperly anchoring the trim reinforcement to the basemat.
The condition raises the concern that these local regions, under certain loading conditions identified in the design criteria, may exceed the allowable stress values established for those condition The inspector was informed that this matter had been reported by the licensee to the NRC as a potential 50.55(e)
item.
Unit 2 containment is also affected.
Bechtel issued Stop Work Notice No.
80-SW-4 on June 30, 1980 stopping all installation activities within a 6-ft.
annulus around the containment shell of Units 1 and 2 at the 77-ft.
elevation for the concerned locations.
It was also decided not to start placement of shell concrete for Unit 3 until the design drawings are appropriately revised.
Bechtel has initiated a program which will reanalyze the loading stresses based upon the actual measured strengths of the containment structure components and then determine if any additions to the structures are necessary.
5.
Unit 2 - Containment Dome Liner The initial fit-up of the prefabricated 30-degree liner segments was examined after the segments (12) were lifted into place.
The fit appeared satisfactory around the periphery of the cylindrical section except at some of the vertical prefabricated seam welds.
Some localized distortion (up to as much as 2-inches)
had occurred at the end of these seams, probably due to weld shrinkage.
Only one of the 12 vertical seams where the segments come together for welding displayed an overlap conditions This condition is expected to be corrected as the final fit-up for welding is accomplished, No deviations or items of noncompliance were identified.
6.
Unit 2 - Reactor Vessel Installation The vessel was set in position on its support columns on July 2, 1980, in full accordance with the approved procedures as documented on Construction Inspection Plan No.
WPP/gCI 350.54-2, Addendum 2.
A delay was encountered in bolting the vessel in place, however, due to thread tolerance questions pertaining to the tensioning nuts furnished by Combustion Engineering.
A precision thread measuring program was undertaken by Bechtel to measure the threads of a represen-tative number of nuts in order to determine if any remachining was necessary.
The precision measurements were complicated by the high amoient temperatures prevailing at the job-site.
Bolting of the vessel will continue to be followed by the inspector and will be covered in a subsequent report (50-529/80-13/01).
7.
Unit 2 - Coolin Towers The inspector examined some of the work in progress on cooling towers 8 and C.
This included prefabrication of reinforcement matrices for the fan deck support columns, installation and removal of the reusable steel forms for the concrete columns, cosmetic type repairs to concrete surfaces following form removal, and erection of prefabricated, interlocking tower segments.
Since the cooling towers are not safety related structures, the inspector did not attempt to ascertain compliance with established'requirements.
The towers are, however, essential for plant operation and the workmanship associated with their construction is important.
The inspector verified that the Bechtel guality Control group was exercising surveillance over the Marley Company work activities.
The inspector observed that the finished concrete work was of good quality, care was being exercised in the work operations, particularly in the handling of the prefabricated components, and an adequate amount of supervision was present at the work locations.
No items of concern for notification to the licensee were identified.
8.
Unit 3 Auxiliar Buildin Pi in During a tour of the auxiliary building, the inspector made general observations pertaining to the handling and preservation of piping, and overall housekeeping conditions.
Pipe spools were being properly handled and supported, and pipe openings that were not in a work process, were properly capped.
No weld electrode stubs were seen lying around the areas where welding was in progress.
Good workmanship was in evidence on completed welds and general cleanliness in the various rooms was good.
No deviations or items of noncompliance were identified.
9.
Mana ement Heetin On July 25, 1980, the inspector met with Mr. ll. E. Ide, Site gA Supervisor, to summarize the scope of the inspection activities and review the inspection findings as described in this repor (')