IR 05000528/1981003
| ML17297A433 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/16/1981 |
| From: | Dodds R, Vorderbrueggen NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17297A430 | List: |
| References | |
| 50-528-81-03, 50-528-81-3, 50-529-81-03, 50-529-81-3, 50-530-81-03, 50-530-81-3, NUDOCS 8105220043 | |
| Download: ML17297A433 (12) | |
Text
ort No.
Docket No.
Licensee:
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-528/81-03 REGION V
50-529/81-03 50-530/81-03 50-528, 50-529, 50-5/0.
R CPPR-141, CPPR-142~
P icense No.
'Safeguards Group CPPR-
Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 Facility Name:
Palo Verde Nuclear Gener atin Station - Units 1, 2, and
Inspection at:
Palo Verde Construction Site, Wintersbur
, Arizona Inspection conducted:
Februar 9-27, 1981 Inspectors:
L. E. Vorderbrueg n
Resident Reactor Inspector ate Signed Date Signed Reactor Construction Project Section
Date Signed fr~ P/
at Signed Summary:
Inspection on Februar 9-23, 1981 Re ort Nos. 50-528/81-03 50-529/81-03 and 50-529/81-03 y'~ld:
d d, d
d d
by b
dd of construction activities including:
containment structural concrete; structural foundations; reactor coolant pressure boundary piping; protection of installed reactor vessels; Unit 1 reactor vessel internals installation; care and preservation of equipment; and general activities in progress at the plant site.
The inspection involved 39 inspector hours on-site by one NRC inspector.
Results:
No deviations or items of noncompliance were identified.
8 zosmso 043 RV Form 219 (2)
DETAILS 1.
Persons Contacted a.
Arizona Public Service Company (APS)
- E. E.
Van Brunt, Jr. Vice President, Nuclear Projects Management
- J. A. Roedel, Manager, guality Assurance
- W. E. Ide, Site WA Supervisor G. Pankonin, gA Engineer R.
D. Forrester, gA Engineer
- R. J.
Vimmel, Field Engineering Supervisor b.
Bechtel Power Cor oration Bechtel
- D. R. Hawkinson, Project QA Supervisor R.
M. Grant, Project gC Engineer 0. Ostereich, Welding Engineer - Unit 2 H. Greco, gC Engineer W. Miller, Civil Superintendent
- Unit 3 c.
Combustion En ineerin CE S.
Maser, Site Manager P.
DeGreef, Internals Installation Superintendent Other persons contacted during the inspection period included construction craftsmen, inspectors and supervisory personnel.
- Denotes management meeting participants.
2.
Containment Structural Concrete Work activities associated with preparations for the following concrete placements were examined:
a.
No.
2C114 - The first seqment of the Unit 2 containment dome, from El. 210 ft. (3 ft. 6 in. below springline) to El. 217 ft.
b.
No.
3C103 - The fourth lift of the Unit 3 containment exterior wall, from El.
106 ft. to El.
116 ft.
e For placement 2C114, formwork closure segments were being fastened in place and final cleanup of the construction joint was in progress.
For placement 3C103, cleaning oper ations had been completed and concrete placement (700 cubic yards estimated)
was ready to begin.
For both placements, the size, grade and spacing of the reinforcing steel was as specified and appeared free of any surface materials that would adversely affect the concrete bond.
The forms were anchored to preclude movement during concrete placement, joints were tight, and the specified cover for the reinforcing steel would be obtained.
Embeds were adequately fastened in place, and tendon sheaths
'1
were clean, free of damage, and securely fastened in the specified locations.
The junctions of the trumpet extensions and the tendon sheaths appeared to be covered sufficiently to prevent the entrance of mortar.
It was verified that the reinforcing steel Cadwelds had been inspected and found acceptable.
Trumplate openings in the buttresses were plugged to prevent the inadvertent entry of concrete.
The governing specifications are 13-CM-371, Post-Tensioning Trumplate Assemblies and Sheathing, and 13-CM-375, Placing of Reinforcing Steel.
Applicable drawings are 13-C-FCS-108 through -123, Containment Building
'Hall and Oome Reinforcing, and 13-C-FCS-175 through -181, Containment Building Prestressing Requirements.
Inspection and documentation require-ments were observed to be in accord with WPP/gCI 52.0, Concrete Preplacement.
I No deviations or items of noncompliance were identified.
3.
Structural Foundations Installation" activites involved with formwork, reinforcing steel, embeds and anchor bolts for the Unit 3 main steam support structure foundation were observed.
The placement was identified as 3M001, El. 71'ft.'B.in. to El. 81.ft;"0 in
. and was'stimated.to contain 195'cubic yards".of";cohcrete.
Reinforcing steel's spacing size and grade were as specified, and the steel was free of rust or other surface materials that would interfere with the concrete bond.
Formwork joints were tight, and the forms were clean and well anchored to prevent movement during concrete placement.
Embeds and anchor bolts were of the proper size and type, and were firmly fastened in their specified locations.
Just prior to the scheduled concrete place-ment, the area was seen to be free of debris and ready to accept concrete.
The preplacement check list required by WPP/gCI 52.0 was observed to be properly signed,off.
The governing specification is 13-CM-375, Placing of Reinforcing Steel, and the applicable drawings are 13-C-FCS-700, MSSS:con-crete Plans and -705, Pump Pad and Anchor Bolt Locations.
No 'deviations or items of noncompliance were identified.
4.
Reactor Coolant Pressure Boundar Pi in a ~
Com onent Installation Activities The inspector observed various work activities associated with piping installation in Unit 2 containment building.
The observations included
.
the handling and supporting of spool Ho.
001 in line RC-034 during its fit-up to the reactor vessel inlet nozzle.
Particular attention was directed to prevention and absence of damage on component surfaces, correctness of configuration, adequacy of temporary component supports, use of specified materials, control of weld filler material and weld-ing records in work areas, and inspection performance by qualified personnel.
The applicable requirements are specified in WPP/OCI 202.0, Piping System Installation, and Specification 13-PM-204, Field Fabrica-
-3-tion and Installation of Nuclear Piping Systems.
No deviations or items of noncompliance were identified.
In-rocess Weldin Activities In-process welding of two welds in the reactor coolant system for Unit 2 was observed to ascertain if the requirements of'pplicable specifications, codes, standards, and procedures were being met.
The welds were:
4<
(1)
30 inch I.D. spool No.
001 to reactor inlet nozzle from pump IB (Line 2 -
RC - 031).
(2)
30 inch I. D. spool No. 001 to reactor inlet nozzle from pump
(Line 2 -
RC - 093).
Both welds were being made by the simultaneous use of two independently operated automatic we'Iding machines utilizing welding procedure PI (62)-
T-I-0-(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 machine settings for voltage, current, travel speed, filler metal wire feed speed, oscillation frequency and amplitude were verified to be within the r anges listed on the welding procedure specification.
The weld identification, material specification, shield-ing gas flow rate, and interpass temperature were in accordance with the requirements specified on the WR-5 Form.
The inspector verified that the WR-5 provisions were in accordance with the requirements of the ASNE Code,Section III, 1974 edition.
Interpass cleaning was being performed with stainless wire brushes.
Filler metal issue slips and the qualification records of the 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 de-gree.
Drawing NO. 13-P-ZCG-103, Rev. 3, Containment Building - Reactor Coolant Loops governed both welds, and the applicable specification was 13-PM-204, Field Fabrication and Installation of Nuclear Piping Systems.
WPP/gCI 101.0, Welding Control, and WPP/gCI 202.0, Piping System In-stallation were the controlling work plan and inspection documents for both welds.
No deviations or items of noncompliance were identified.
5.
Protection of Installed Reactor Vessels e
Guarded access control to the Unit 1 reactor pool area continues to limit the entry of personnel, equipment, tools and materials to those which are authorized.
When there is no work activity inside the vessel, a plastic protection cover is kept in place over the vessel flange to prevent entry of foreign objects and debri On the Unit 2 reactor vessel, nozzle welding operations were in progress.
Openings not being worked were covered for protection from adjacent con-struction activities.
Work platforms and ladders inside the vessel were metallic or of treated wood so as to minimize fire hazards.
The top of the vessel was covered to prevent the accidental entry of foreign objects and debris.
The inspector verified that the procedures for protection of the installed reactor vessels were being implemented.
Unit 1 Reactor Vessel Internals In process welding of the lower support structure-core shroud assembly to the core support barrel flexure flange was observed for compliance with Section 6.5 of the approved CE Nuclear Power Systems-Internals Instruction Manual No.
IG-14273-RCE-400.
Weld pass No. 8 was in progress and the CE Superintendent estimated that the weld was approximately 70/ complete.
Workmanship appeared excellent.
The qualifications of the four individuals making the weld were examined and found satisfactory.
The optical instru-ments set up inside the upper region of the core support barrel to monitor relative movement of the two components and to guide the welding location sequence was also observed.
A heavy plastic cover was in place over the top of the assembly to prevent the entry of 'dust and debris.
Clean room procedures were in effect in the work areas.
It appeared to the inspector that the procedures for installation and protection of the interna1 com-ponents were being followed.
Ins ection Tours of Plant Site At various times during this inspection period, the inspector toured the
,
plant site in order to observe general housekeeping conditions, care and preservation of equipment, handling of heavy components, tagging and iden-tification of materials, adequacy of caps over pipe openings not being worked on, and presence of cribbing under stored pipe spools, valves and other components.
No welding electrode stubs were observed lying around the various work areas.
During one of the tours of Unit 2 containment building, the inspector ob-served that on the steam generator No.
2 steam blowdown lines (2-59-048-6"),
one of two dummy pipe support lugs had been removed from each line which were intended for supporting the lines from the vertical shield wall.
From the other prevailing conditions at that location, it appeared obvious to the inspector that the support members (hangers no.5)
had been removed in error.
Further review of the matter disclosed that a misunderstanding had developed because of the misfit of an attaching sway-strut clamp and the craftsman erroneously ground off the support members.
The condition had been properly documented on NCR Nos.P-C-2137 and P-C-2138 and FCR No.15172 P
had been issued to replace the support members.
The inspector was satisfied that the item had been properly identified and proper corrective action initiate P
No deviations or items of noncompliance were identified.
8.
Mana ement Meetin s
On February 27, 1981 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 report.