IR 05000528/1980014
| ML17296B035 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/15/1980 |
| From: | Haynes R, Vorderbrueggen NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17296B034 | List: |
| References | |
| 50-528-80-14, 50-529-80-14, 50-530-80-14, NUDOCS 8011050360 | |
| Download: ML17296B035 (8) | |
Text
50-528/80-14 50-529/80-14 Report No 50-530/80-14 Docket No.50-528/529/530 U. S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
License No.
CPPR-141,
-142, -143 Safeguards Group Licensee:
Arizona Public Service Company P.
0.
Box 21666 Phoenix Arizona 5036 Facility Name:
Inspection at:
Palo Verde Construction Si Inspection conduct d.
August 4-29, 1980 Inspectors:
r
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~ ~6 or eggen, ess en eac or nspector nd
80llh /Be Date Signed Date Signed Date Signed proved By:
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R b, d
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R by P
Rd inspector of construction activities including:
storage of Unit 1 containment tendons; Unit 1 auxiliary feedwater system piping welds; Unit 1 condensate storage tank, Unit 1 main steam piping, and Unit 2 containment dome-liner plate; installation of Unit 2 reactor pressure vessel; preservation of equipment in all three units; and general activities in progress at the site.
The inspection involved 67 inspector hours on-site by one NRC inspector.
Results:
No deviations or items of noncompliance were identified.
g oji>/8o.
R.
C. Haynes, ie, Reactor Projects Section Date Signed Reactor Construction 5 Engineering Support Branch summary:
In~s ection on Au ust 4-29, 1980 Re ort Nos. 50-528/80-14, 50-529/80-14 and 50-530/80-14 RV Form 719 (2)
DETAILS l.
Persons Contacted a.
Arizona Public Service Com an (APS
- E. E.
Van Brunt, Jr. Vice President, Nuclear Projects Management
- J. A. Roedel, Manager, Quality Assurance
- W. E. Ide, Site QA Supervisor
. *G. Pankonin, QA Engineer R.
D. Forrester, QA Engineer b.
Bechtel Power Cor oration Bechtel S.
M. Nickell, Construction Superintendent D.
R. Hawkinson, Project QA Supervisor R.
M. Grant, Project QC Engineer J.
L. Black, Resident Engineer R. Hoke, Quality Control Engineer L. Oscarson, Unit 2 Lead Field Welding Engineer Other persons contacted during the inspection period included construction craftsmen, inspectors and supervisory personnel.
- - Denotes management meeting participants 2.
Unit 1 - Containment Buildin Tendon Stora e
The tendons for Unit 1 containment building po'st-tensioning system are being delivered to the jobsite and are being stored outdoors in the Unit 1 area.
Each tendon is coated with a temporary corrosion protection material, coiled, and enclosed in a plastic bag prior to shipment from the manufacturer's plant.
The coiled tendons are shipped in racks.
Upon arrival at the jobsite, the coiled tendons are left in the shipping racks for storage.
The inspector examined the tendons (9) stored on the north side of the containment building.
The bagged tendons were adequately covered and enclosed to prevent the entrance of dirt and rainwater.
The governing specification is No.
13-CM-158, Furnishing and Installing Containment Building Post-Tensioning System.
No deviations or items of noncompliance were identifie.
Unit 1 - Auxiliar Feedwater S stem Pi in Melds Four completed welds in the auxiliary feedwater piping in the discharge of the motor driven pump in the turbine building were examined by the inspector.
These were the welds joining spool 001 to check valve V-012, spool 002 to check valve V-012 and gate valve V-013, and spool 003 to gate valve V-013, all as shown on Drawing 13-P-AFF-401, Turbine Building Isometric Auxiliary Feedwater System.
The specified welding procedure was No. P8-AT-Ag.
This system is a backup for the normal auxiliary feedwater system.
It is not classified as a safety-related system and is constructed to the requirements of ANSI B31.1, Code for Power Piping.
The welds appeared free of cracks and undercut, and displayed quality workmanship.
The welder's qualification was checked and found satisfactory.
- No items of concern were observed.
4.
Unit 1 - Condensate Stora e Tank Meldin The inspector visually examined several vertical seams and portions of one horizontal seam on the inside of the condensate storage tank.
The welds were completed welds joining the shop fabricated, 1/4-inch stainless steel panels which make up the liner plate for the reinforced concrete tank.
The welds displayed quality workmanship.
There was no evidence of undercut and weld crown was within the 3/32-inch allowance.
The specified welding procedure was P8-T-b-o and the governing specification was 13-CH-340, Field Erection of Stainless Steel Liner Plate.
5.
No deviations or items of noncompliance were identified.
Unit 1 - Hain Steam Pi in Meldin The inspector examined weld No.
M-001 joining steam generator No.
2 outlet nozzle to 31 1/2-inch OD by 28-inch OD concentric reducer (line 1-SG-042-28").
The weld had been completed and the configuration and appearance were satisfactory.
The work traveler (MR-5 form) was properly completed and specified the welding procedure
[Pl-AT-LH(CVN)] that was identified for the piping class and size on the Bechtel Form 84, Welding and NDE Requirements for Field Erected Piping.
The welder qualifications were checked and found to be valid for the specified procedure.
The governing specification was No. 13-PH-204, Field Fabrication and Installation of Nuclear Piping Systems.
No deviations or items of noncompliance were identifie Unit 2 - Containment Dome Liner The Unit 2 Dome Melding Sequence Plan, dated August 5, 1980, was reviewed by the inspector and discussed with the licensee's welding quality assurance engineer.
The plan specified alternate seam welding progression and back-stopping of welds, and appeared to be a satisfactory approach.
In addition,'eoment fit-up from the cylindrical "spring line" up to the 45-degree point had been essentially completed commencing the welding.
.This was examined in representative locations on the 12 vertical seams.
The fit-up appeared satisfactory.
In the horizontal seam at the spring-line, however, the inspector identified two azimuth locations (166'nd 266') where local'ized distortion at the ends of prefabricated vertical seams resulted in a fit-up concavity over a distance of approximately 18-inches.
The maximum "bulge" depth was measured and was two inches.
The inspector expressed concern about setting up excessive residual stresses in the liner plate when the bulge was forced out for final welding.
,This matter was discussed with the Bechtel Resident Engineer who had also noticed the condition previously and had studied the situation.
He expressed firm confidence that fitting up efforts would not unduly stress the liner plate because the mismatch was well within the tolerances established in the erection specification (No.
13-CM-370, Erecting The Containment Building Liner Plate System).
Upon the inspector's request, the Resident Engineer committed to notify the inspector in time for him to observe the fit-up of the first of the bulges to be'orked out.
This activity will continue to be followed and will be covered in a subsequent report.
(50-529/80-14/01).
Unit 2 - Reactor Vessel Installation The'inspector observed the placement of grout under vessel support column No.
2B.
The column base was adequately formed to contain the grouting material and the work appeared to proceed in accordance with the requirements of specification No.
13-CM-'365, Forming, Placing, Finishing and Curing of Concrete.
Additionally, the inspector reviewed the results of the thread measurement program for the vessel holdown nuts that was identified previously (50-529/80-13/01).
Fifty-six (56)
3 1/2-inch studs and nuts were furnished by Combustion Engineering (CE) for bolting the reactor vessel pads to the four support columns.
A total of 40 bolts were required for the installation, but only 35 nuts were found to have the j;bread pitch diameter within the CE specified tolerance of 3.435
'$() inches.
The others measured as much as
.004-inch greater than the maximum allowable dimension of 3.441.
The condition and
~
~
associated measurements are documented on NCR No. N-C-154.
CE agreed with the Bechtel resolution of selecting the 5 smallest oversized nuts to meet the 40 required and recording the pad location where the are installed.
Then, during the pretensioning of the studs, any abnormally short elongation measurements on these 5 stud-nut combinations when compared with the others having acceptable threads would indicate thread failure.
The inspector reviewed the elongation measurements for all 40 studs as recorded on the Construction Inspection Plan for WPP/gCI No. 350.54-2.
The elongation for all 5 suspect units were seen to be within the specified range of 0.038 to 0.0435-inch that was established for all studs in the vessel support pads.
The inspector had nor further questions on this matter.
No deviations or items of noncompliance were identified.
8.
Units 1, 2 5 3 Handlin
, Care and Preservation of E ui ment Several times during this reporting period the inspector toured the plant site to observe general housekeeping conditions and the care, handling and preservation of equipment.
Particular attention was given to work in progress on the handling of Unit 2 reactor.
coolant system hot leg spools for welding fit-up, presence of covers over installed equipment in all three-units for protection from adjacent work activities, adequate caps over pipe openings not being worked on, and adequacy of dunnage under stored values and pipe spools.
Installed electrical panels and control centers were observed for adequacy of covers and energized heaters to'revent damage from dust and moisture condensation.
Welding electrode control was seen to be under proper storage conditions and no electrode stubs were seen lying around the various work areas.
No deviations or items of noncompliance were identified.
9.
Mana ement Heetin s
On August 20 and 29, 1980, the inspector met with the licensee representatives identified in Paragraph 1 to summarize the scope of the inspection activities and review the inspection findings as described in this repor ~
~