IR 05000528/1980019
| ML17296B245 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/22/1981 |
| From: | Dodds R, Vorderbrueggen NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17296B244 | List: |
| References | |
| 50-528-80-19, 50-529-80-19, 50-530-80-19, NUDOCS 8103050379 | |
| Download: ML17296B245 (12) | |
Text
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- -<,'i.-",Report No.
50-528/80-19 50-529/80-19 50-530/80-19 S
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NL'CL KR P'" CULKTORY CO.
fZSS IO O".""."':C."; O'=
'5'.<SP:-CTTON A".iD ""NFORCE!~'.iT
- -:"=CTON V Docket No.
s Licensee:
50-528/529/530 License No. CPPR>> 41'-142'>>143 Sazeguards Grouo Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036
@;~,;;-.p<<i1it> Na~Palo Verde Nuclear Generating Station - Units 1, 2 and
Tnspection at. Palo Verde Construction Site, Mintersburg, Arizona
'ath. Signed Date Signed D te Signed Results:
No deviations or items of noncompIi'ance were identified.
Inspection conducted.Novemoer 3-21.. 1980
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Inspectors: ~
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, Yorderbrueggen, Resident Reactor Inspector
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Date Signed
',. '" Approved By:
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-/gz-p-R. T. Oodds, Chief, Engineering Support Section Reactor Construction t'ai Engineering Support Branch
~~p"-Sutaatary
'nspection on November 3-21, 1980 Re ort Nos. 50-528/80-19 50-529 80-19 an o0-
80-1 Areas Ins ected:
Routine, unannounced inspection by the resident inspector o
construct on activities including: protection oj installed reactor vessels and Unit 1 reactor vessel iriternals, insta11ation of reactor coolant pressure boundary and other safety related piping, concrete placement activities for the Unit 1 refueling water tank foundation, containment structural concrete, electrical components and systems, care and preservation of equipment, and general activities in progress at the site.
The inspection involved 55 inspector hours on-site by'one NRC inspector.
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BETAILS 1.
Persons Contacted a.
An1zona Pab1<c Service Com an~APS).
- E. E.
Van Brunt, Jr., Vice President, Nuclear Projects Management
- J. A. Roedel, Manager, Quality Assurance
"D. B. Fasnaght, Nuclear Construction Manager
- J. fl. Allen, Nuclear Engineering Manager
~A. C. Rogers, Nuclear Engineering Manager
- B. S. Kaplan, Quality Systems Supervisor b.
Bechtel Power Cor oration Bechtel)
W. J.
- D. R.
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M.
J.
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Stubblefield, Field Construction Manager Hawkinson, Project, QA Supervisor Grant, Project QC Engineer Pfunder, QA Engineer 2.
Other persons contacted during the =inspection period included construction craftsmen, inspectors and supervisory personnel.
Denotes attendees at exit interviews.
r Protection of Installed Reactor Vessels 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.
A plastic protective cover is kept in place over the vessel flange to prevent the entry of foreign objects and debris into the vessel.
Nozzle welding operations continued on Unit 2 reactor vessel.
Nozzle openings not being worked are covered for protection from adjacent construction activities.
Mork platforms and ladders inside the vessel are metallic or of treated wood so as to minimize fire hazards.
The top of the vessel is covered to prevent the accidental entry of 'foreign objects and debris.
The inspector found that the procedures for protection of the installed reactor vessels were being implemente :0
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3.
Unit 1 Reactor Vessel Internals During this reporting period the internal components remained under storage conditions in the refueling pool area.
No wor k was performed on the components because of the labor stoppage by the boilermaker craft.
The inspector. verified that the protective covers for components were in place.
It appeared to the inspector that the procedures for protection of the vessel internals are adequate and were being followed.
4.
Reactor Coolant Pressure Boundar and Safet Related Pi in Installation l,
7l a.
Component Installation Activities The inspector observed various installation work activities associated with portions of the chemical and volume control system in the Unit 2 auxiliary building at the 40 and 70 foot elevations.
Particular attention was given io the handling and supporting of system components, correctness of configuration, control of welding records in the work area, use of specified materials, control of weld filler metal, absence or defects on component surfaces, and inspection performance by qualified personnel.
The applicable requirements are specified in MPP/gCI 202.0, Piping System Installation, and Specification 13-PN-2104, Field Fabrication and Installation of Nuclear Piping Systems.
No items of noncompliance or deviations were identified.
b.
In-rocess Meldin Activities The inspector examined four welds in Units
8 2 to ascertain compliance with requirements of the applicable specifications, codes, standards, and procedures.
The welds were:
No. M-017 joining spools 16 and 17 in suction line CH-N-284-3" to reactor drain pump No.
2 (Unit 2).
No.
M-038 joining spools 32 and 33 in line CH-N-305-3" between the reactor drain pump discharge filter and the heat recovery exchanger in the CVCS gas stripper (Unit 2).
Nos.
M-OAC and W-OAD which connect spool N006 in charging line CH-E-005-3" where it enters the reactor vessel cold leg (line RC-E-079-30") (Unit 1).
-3-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 weld identification, material specifications, and interpass temperature were in accordance with the requirements specified on the MR-5 Form.
The MR-5 provisions were in accordance with the requirements of the ASME Code,Section III, 1974 edition.
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 surveil.lance were being performed as required.
WPP/gCI 101.0 Welding Control, along with the two documents identified in paragraph 4.a.
above, contained the applicable work and inspection requirements.
for all welds.
No deviations or items of noncompliance were identified.
c.
Examination of Completed Pi e Runs
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1.1.
The inspector examined two essentially completed piping runs to ascertain if the installations were in accordance with the latest approved drawings and construction specifications.
They were:
Unit 1
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The safety injection line SI-E-159-14" including check valve V-215 and motor operated valve UV-614 from safety injection tank 2A to reactor vessel cold leg-line RC-E-079-30".
The applicable drawing is No. 13-P-SIF-136, Rev. 9, Containment Building Isometric - Safety Injection System - HP and LP Lines, Loops 2A and 2B.
Unit 2 - The 2-inch suction and discharge piping in the reactor drain pump room, including check and globe valves, for both reactor drain pumps.
The applicable drawing is 13-P-CHF-224, Rev. 7, Auxiliary Building Isometric - Chemical and Volume Control System - Containment to Reactor Drain Filter.
For both runs, the applicable specification is No. 13-Pt)-204, Field Fabrication and Installation of Nuclear Piping Systems.
No items of noncompliance or deviations were identified.
5.
Foundations - Unit I Refuelin Mater Tank 0'oncrete placement for'
portion of the foundation for the refueling water tank was observed by the inspector.
Cleanliness and preplacement preparation were satisfactory and the crew size appeared to be adequate.
Concrete consolidation by the vibrator personnel appeared adequate and quality control inspection personnel were present and exercising appropriate surveillance.
The quality control records were later
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examined.
The applicable drawing was 13-C-ZYS-706, Refueling Mater Tank Concrete - Plans, Sections, and Details.
The governing specification was No. 13-CM-365, Placing, Finishing, and Curing of Concrete.
The inspection and documentation requirements weve specified by MPP/gCI Nos. 52.0, 53.0, and 54.0, respectively titled Concrete Pre-placement, Concrete Placement, and Concrete Post Placement.
No deviations or items of noncompliance were identified.
Unit 3 Containment - Structural Concrete The inspector examined work activities associated with preparations for placement of the first concrete lift (el. 77-ft. 3-in, to el. 85-ft.
1)-3/4-in.} for the containment exterior she'l.
A section from azimuth
to approximate azimuth 270" had formwork in place and had been cleaned and made ready to receive concrete.
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 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 sufficient to prevent the entrance of mortar. It was verified that the reinforcing steel Cadwelds had been inspected and found acceptable.
The governing specifications are 13-Ci~<-371, Post-Tensioning Trumplate Assemblies and Sheathing, and 13-CN-375, Placing of Reinforcing Steel.
The applicable drawings are 13-C-ZCS-ll4 through -119, Containment Building-Wall Reinforcing-Sections and Details.
No deviations or items of noncompliance were identified.
'Electrical Com onents and S stems During tours of Unit 1 and Unit 2 safety-related electrical equipment items, both installed and in storage areas, were observed to ascertain that protective requirements were being met.
Particular attention was given to energization of space heaters, lubrication and rotation of motor shafts, storage position and presence of dunnage, identification, cleanliness, and adequacy of protective cover,
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-5-The protection of installed cable and raceways in several areas of the Unit 1 auxiliary and containment buildings was also observed.
Cables appeared to be properly supported and tied down, and coiled cable ends appeared to be appropriately sealed.
Trays and junction boxes appeared'o be protected from adjacent construction activities and were not being used as ladders, walkways, or otherwise abused.
No deviations or items of noncompliance were identified.
8.
Plant Tours 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 the handling of heavy pipe spools and valves during welding fit-up, presence of covers over installed equipment for protection from adjacent work activities, adequate caps, over pipe openings not being worked on, and adequacy of dunnage undet stored valves, pipe spools and other components.
No welding electrode stubs were found lying around the various work areas.
No deviations or items of noncompliance were identified.
9.
Nana ement f<eeiin s On I'november 14 and December 5, 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 I (y'