IR 05000528/1980018
| ML17296B155 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/01/1980 |
| From: | Haynes R, Vorderbrueggen NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17296B154 | List: |
| References | |
| 50-528-80-18, 50-529-80-18, 50-530-80-18, NUDOCS 8012310234 | |
| Download: ML17296B155 (8) | |
Text
U ~ S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
Licensee:
Arizona Public Service Company P.O.
Box 21666 Phoenix, Arizona 85036 50-528/80-18
REGION V
50-529/80-18 Report No.
50-528, 50-529, 50-530 Li No CPPR 141 142 Safeguards Group Facility Name:
Palo Verde Nu lear Generatin Station - Units
2 and
Inspect ion t Pa 1 o Verde Constructi on Si te, Winters burg, Arizona Inspection conducte
October 1-31, 1980 pectors:
or e en, esl en eactor nspec or
/ Z./I/Pe=
Date Signed Date Signed Approved By:
Surrmary:
Date Signed x"jr,.
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R. C~Ha es, Chief, Reactor Projects Section Date Signed Reactor Construction and Engineering Support Branch Ins ection on October 1-31, 1980 Re ort Nos.
50-528 80-18, 50-529 80-18, and 50-530/80-18
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id inspector of construction activities including:
protection of installed reactor vessels and Unit 1 reactor vessel internals, anchor bolt tensioning on Unit 2 reactor vessel support columns, Unit 1 refueling water storage tank foundation, and installation of reactor coolant pressure boundary and other safety related piping.
The inspection involved 55 inspector hours on-site by one NRC inspector.
Results:
No deviations or items of noncompliance were identified.
RV Form 719 (2)
sozsszo 2. 5f
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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
- D. B. Fasnacht, Site Construction Construction Manager
- R. J.
Kimmel, Field Engineering Supervisor 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'W.
A. Miller, Assistant Project Field Engineer
- R.
M. Grant, Project gC Engineer
- J.
E. Pfunder, gA Engineer A. Switanek, Welding Engineer - Unit
J.
Froschauer, Welding Engineer - Unit
0. Ostereich, Welding Engineer - Unit 2 R.
Hoke, guality Control Engineer H. Thompson, Civil Superintendent
- Unit
Other persons contacted during the inspection period included construction craftsmen, inspectors and supervisory personnel.
- - Denotes attendees at exit interviews.
2.
Protection of Installed Reactor Vessels Nozzle welding has been completed on Unit 1 reactor vessel, and the entry of authorized personnel, equipment, tools and materials to the reactor pool area is under guarded access control.
A suitable plastic protective cover is in place over the vessel flange to prevent the entry of foreign objects and debris into the vessels Nozzle welding operations are in progress on Unit 2 reactor vessel.
Nozzle openings not being worked are protected from construction damage.
Work platforms/ladders/scaffolds inside the vessel are metallic or of treated wood to minimize damage from accidental fires.
The top of the vessel is covered to prevent the accidental entry of foreign objects and debri The inspector found that the procedures for protection of the installed reactor vessels are adequate and were being followed.
3.
Unit 1 Reactor Vessel Internals
~
The internal components of the reactor vessel remained under storage conditions during this reporting period.
No work was performed on the components due to the labor stoppage by the boilermaker craft.
The inspector verified that the component supports and protective covers were adequate.
It appeared to the inspector that the procedures for protection of the vessel internals are adequate and were being followed.
Unit 2 Reactor Vessel Installation The inspector observed the tensioning of six of the ten anchor bolts in vessel support column 1A in order to verify that work and inspection procedures were being followed and that the specified bolt elongations were obtained.
The bolts observed were Nos.
1, 4, 5, 6, 9 and 10.
The requirements were specified in WPP/gCI No. 350.54-2, Special Construction Inspection Planning for NSSS Equipment.
The bolts were tensioned in the specified sequence and the operations were performed under the cognizance of the assigned gC inspector.
The inspector recorded the bolt elongation values achieved on the record sheet provided.
The inspector also checked the calibration status of the dial indicators being used to measure bolt elongation and the pressure gage on the hydraulic pumping unit.
No deviations or items of noncompliance were identified.
5.
Foundations
- Unit 1 Refuelin Water Stora e Tank The inspector examined the work activities associated with the installation of the mat type foundation for the refueling water storage tank.
The top of the."mud mat" was at the specified elevation to form the bottom surface of the 4-ft, 6-inch thick foundation.
The size, grade and spacing of the reinforcing steel were verified and preplacement cleanliness was observed to be satisfactory.
Formwork joints appeared to be leak-tight and securely supported.
The WT4 x 6.5 embeds to serve as backing plates for subsequent welding of the stainless steel liner plate were securely fastened in place.
The 3-inch stainless steel drain line for the tank was in place and adequately capped to prevent the entry of concrete or other forei gn material.
The initial portion of the concrete placement was observed and the specified design mix and concrete slump value were verified.
Records of measurements for slump loss in the concrete pump line were examined and found adequate.
The governing specifications were 13-CH-375, Placing of Reinforcing Steel and 13-CM-365, Placing, Finishing and Curing of Concrete.
The applicable drawing was 13-C-ZYS-706, Refueling Water Tank Concrete - Plans, Sections and Details.
No deviations or items of noncompliance were identifie.
Reactor Coolant Pressure Boundar and, Safet Related Pi in Installation a.
Com onent Installation Activities The inspector observed various installation work activities associated with the following items:
Unit
Pres suri zer Rel ief Va1 ves, Hiscellaneous 1-and 2-inch stainless steel assemblies in the pipe fabrication shop.
Particular attention was given to the handling and supporting of the connecting piping spools, correctness of confi guration, control of welding records in the work area, use of specified materials, control of weld filler material, absence of defects on component surfaces, and inspection performance by qualified personnel.
The applicable requi rements are specified in WPP/gCI'02.0, Piping System Installation; Specification 13-PH-204, Field Fabrication and Installation of Nuclear Piping Systems.
Drawing 13-P-RCF-114, Reactor Cooling System - Pressurizer Relief Lines was specifically applicable to the pressurizer relief valve.
No items of noncompliance or deviations were identified.
b.
Examination of Com leted Pi e
Runs The inspector examined two essentially completed piping runs to ascertain if the installations were in accordance with the latest approved drawings -and the construction specifications.
They were:
- 12-inch Pressurizer Surge line in Unit 1 between steam generator No.
1 hot leg to the bottom of the pressurizer surge tank - Line No. 1-RC-028.
The applicable drawing is No. 13-P-RCF-101, Rev. 6, Reactor Coolant Isometric Pressurizer Surge Line.
- 20-inch fuel pool outlet line (No. 1-PC-E-016)
to the suction inlet of both Unit 1 Spent Fuel Pool Cooling Pumps.
The applicable drawing is No.
13-P-PCF-501, Rev.
7, Fuel Building - Spent Fuel Pool Cooling and Cleanup System Isometric.
For both items, the applicable specification and WPP/gCI are as identified in the paragraph above.
No deviations from the requirements were observe C.
In-rocess Weldin Activities In-process welding of two welds in the reactor coolant system for Unit 2 was observed by the inspector to ascertain if the requirements of applicable specifications, codes, standards, and procedures were being met.
The welds were:
the reactor hot leg outlet nozzle to 42-inch I.D. pipe spool S-001 (Line No. 2-RC-063),
reactor coolant pump No.
2B outlet nozzle to 30-inch I.D. pipe spool S-001 (line No. 2-RC-093)
Both welds were being made by the simultaneous use of two independently operated automatic welding machines utilizing welding procedure Pl(G2)-T-I-o-(ITP).
A properly filled out Field Welding Check List (WR-5 Form) was present at the work location of each weld with hold points and NDE call-outs specified.
The inspector observed the arc, weld puddle, and electrode motion on one of the passes.
The machine settings for voltage, current, travel speed, filler metal wire feed speed,'scillation frequency and amplitude were verified to be within the ranges listed on the welding procedure specification.
The weld identification, material specifications, shielding gas flow rate, and i nterpass temperature were in accordance with the requirements specified on the WR-5 Form.
The inspector verified that the WR-5 provi sions were in accordance with the requi rements of the ASNE Code,Section III, 1974 edition.
Interpass cleaning was being performed with wire brushes.
Filler metal issue slips and the qualification records of two welders involved were examined and found to be acceptable.
The inspector observed that quality control inspection and supervisory surveillance were being performed to an appropriate degree.
Drawing No.
13-P-PCG-103, Rev.
3, Containment Building-Reactor Coolant Loops governed both welds, and the applicable specification was 13-PN-204, Field Fabrication and Installation of Nuclear Piping Systems.
WPP/gCI 101.0, Welding Control, and WPP/gCI 202.0, Piping System Installation were the controlling work plan and inspection documents for both wel ds.
No deviations or items of noncompliance were identified.
7.
Exit Interviews On October 10 and 30, 1980, the inspector met with the licensee representatives identified in Paragraph 1 to summarize the scope of the inspection activi ties and review the inspection findings as described in this repor r