IR 05000528/1980012
| ML17296B006 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/03/1980 |
| From: | Dodds R, Eckhardt J, Wagner W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17296B005 | List: |
| References | |
| 50-528-80-12, 50-529-80-12, 50-530-80-12, NUDOCS 8010170428 | |
| Download: ML17296B006 (14) | |
Text
50-528/80-12 50-529/80-12 Report No
'0-530/80-12 U. S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEHENT
REGION V
Docket No.
Licensee:
50" 528/529/530 License No CPPR-141,-142,-143 gage uards Grou Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 Facility Name:
Inspection at:
Palo Verde Nuclear Generating Station - Units 1, 2, and
Palo Verde Construction Site, Wintersburg,.-hri.zona Inspection conducted:
July 28-August 1, 1980 Inspectors:
.
H. Eckhardt, Reactor Inspector ate Signed
.
Wagner Reactor Inspector Date Signed Approved By:
i i/
- r R. T.
Oodds, Chief, Engineering Support Section Reactor Construction and Engineering Support Branch Date Signed
~ 3f~s D t Signed Summary:
Ins ection on Jul 28-Au ust
1980 Re ort Nos.
50-528 80-12 50-529 80-12 and 50-530/80-12
.
Areas Ins ected:
Routine, unannounced inspection by the regional based inspectors o
activities relating to reactor coolant pressure boundary welding and other safety-related pipe welding activities, Unit 2 dome liner plate installation, electrical cables and terminations, licensee action on previous inspection findings, and general construction and housekeeping activities.
The inspection involved 60 inspection-hours onsite by two NRC inspectors.
Results:
No items of noncompliance or deviations were identified.
RV Form 219 (2)
I li (\\i
DETAILS 1..
Persons Contacted a.
Arizona Public Service Com an APS
- E. E.
Van Brunt, Jr., Yice President, Nuclear Projects
- W.
E. Ide, Site qA Supervisor
- R. J.
Kimmel, Field Engineering Supervisor
- D. B. Fasnacht, Site Construction Manager
- J. A. Roedel, (}uality A'ssurance Manager G. Pankonin, gA Engineer R.
D. Forrester, gA Engineer L. Souza, gA Engineer D.
E. Fowler, gA Engineer b.
Bechtel Power Cor oration Bechtel
"A. K. Priest, Project Field Engineer
- R. M. Grant, Project gC Supervisor
- J.
E. Pfunder, Project gA Engineer
- H. L. Claxton, Construction Specialist D.
R. Hawkinson, Project gA Supervisor T. Todd, gC Inspection J.
Froschauer, Field Welding Engineer R. Peters, Civil Resident Engineer A. Sahli, Area Field Engineer J.
Crawford, gC Inspector H. Keanini, gC Inspector R.
Hoak, gC Inspector W.
S.
Cummings, Lead Discipline Engineer (Instrumentation)
- Denotes those attending exit interview.
2.
Construction Status Licensee representatives reported that as of June 30, 1980, construction of Unit I was 68.3%, Unit 2 was 32.7% and Unit 3 was 10.8% complete.
The inspectors toured the site to observe construction activities and noted the following major progress:
the Unit 2 dome liner plate had been partially installed, the Unit 2 reactor vessel and steam generators are in place, and construction on the Unit 3 containment liner plates is up to Ring 6.
3.
Licensee Action on Previous Ins ection Findin s a.
Closed Noncom liance 50-528/80-01/01
Document control of superseded drawings and FCR/DCN revisions.
The corrective actions identified in the licensee's response, dated March 26, 1980, were reviewed.
The inspector verified that all remedial actions and actions taken to avoid further violation in this area were accomplished.
In addition, the
-2-e inspector verified that these actions were effective by examining over 40 drawings and related DCN's at the "Maintained Station" and at various stick file locations in Units I, 2 and 3 work areas.
This item is closed.
b.
Closed Noncom liance 50-528 79-09
Missing temporary cleanliness covers on piping.
During general plant tours, no instances of missing temporary cleanliness caps were identified.
The licensee's action to correct this problem appears to have. been effective and this item is considered closed.
c.
Closed Noncom liance 50-528 80-01/06
Improper control of weld electrodes.
During general plant'tours and inspection of welding, no instances of improper control of weld electrodes or stubs were observed.
The licensee's corrective action concerning this problem appears effective and this item is considered closed.
4.
Safet -Related Pi e Heldin a ~
Observation of Heldin Activities In-process welding on safety-related components was examined for compliance with applicable procedures and standards.
The specific components inspected and their location are as follows:
(1)
Unit I - Reactor Coolant Loop (NSSS)
Pipe Welding.
- Machine welding of a 30-inch diameter pipe fitting to the reactor coolant pump (2B) nozzle (system RC 084, FH-2)
was observed.
Welding was being performed simultaneously by two independently operated welding machines.
The inspector observed the arc, weld puddle and transverse oscillation (weave) of the electrode.
The welding parameters such as amps, volts, wire and travel speed, indicated on the power-supply consoles, were inspected for performance within the specified limits of the welding procedure specification.
Calibration frequency of the electrode circuitry was also examined.
(2)
Unit I - Safety-Related (non-NSSS)
Pipe Welding.
Manual welding was observed on two safety-related systems.
The first system, RC-028, was a
12 inch diameter stainless steel pipe-to-pipe weld with an argon gas purge.
The second, SI 223 was a fourteen inch diameter pipe-to-valve weld; both materials being stainless stee (3)
Unit 2 - Safety-Related (non-NSSS)
Pipe rlelding.
Manual welding was observed on systems NC B 087 and CH N 590.
The former is a ten inch diameter carbon steel pipe, the latter is a three inch diameter stainless steel pipe.
In all of the above welding locations, the in-process welding was observed and inspected in order -to determine that filler material, base metal, weld identification, cleanliness, gas purge, preheat, weld rod use, inspector qualification, weld joint geome'try, and proper use of a ".traveler", were in accordance with contractor's quality assurance and work procedures.
In addition, the inspector talked to the welders performing these welds about these items, especially interpass temperature control and gas purging.
During these discussions, it was determined that the welders received adequate instructions about the weld joint and welding procedure to be used, prior to welding.
No items of noncompliance or deviations were identified.
b.
Visual Examination of Helds The inspector visually examined seven completed welds in the Unit I containment and eight completed welds in the Unit 2 auxiliary building.
Characteristics examined were weld location, size, shape, finish, weld reinforcement height and absence of surface defects exceeding requirements.
Only safety-related welds outside the reactor coolant pressure boundary were examined.
No items of noncompliance or deviations were identified.
5.
Electrical Cable Installation and Terminations a.
Observation of llork Activities Installation of the following Unit 1 group A control cables was observed:
IESI29ACIRC 2/C 14AWG
~Lh, F.
344 From Aux. Bldg.
A2A To ESFAS Aux.
relay cabinet IESI27ACIRC 2/C 14AMG IESI10ACRB 9/C 14AWG IES I49ACZRC 4/C 14Ai'IG 344 344 Aux. relay cabinet Containment Class IE Pen.
IECH14AC IRC 4/C 14AlrlG I ES I49ACIRC 4/C 14AHG 444 444
The installation appeared to meet the requirements of lJPP/gCI-254
"Electrical Cable Installation".
In addition, a
gC inspector was observed inspecting completed terminations IESA03BCIRHZ and IESA03BCIRblZ for 3C 14ANG cables, IESA03BCIRN and IESA03BCIRW respectively.
The gC inspector was questioned concerning the inspection procedure and what attributes he was inspecting to.
He appeared knowledgeable of all applicable requirements.
Also, the cable pulling and termination records associated with the above work were reviewed.
No deviations or items of noncompliance were identified.
b.
Tension Calculations for Power Assisted Cable Pulls The actual measured cable tensions during cable installation were compared with the expected (calculated)
tensions for twelve previously installed cables in Unit l.
In all cases the actual measured values were greater than the expected values; almost double the expected values in some cases.
However, the actual tensions were less than the maximum allowable in all cases.
This nonconservative difference between measured and expected tensions was discussed with the Field Engineers who indicated they had also noted this difference.
They produced Specification Change Notice (SCN)
2113 to Specification 13-Et1-301 that they had initiated to correct this difference.
The SCN requires that the tension recorded for a cable pull being monitored should be the tension observed after the pulling line and cable attachment device has cleared the last section of raceway involved in the pull.
This SCN was discussed with the licensee, and the inspector noted that it was possible for the measured tension to exceed the maximum allowable tension with the attachment device still in the raceway and no record made of this tension.
The inspector noted that, should the cable be "hung up", the actual tension in the cable could exceed the maximum allowable.
The licensee acknowledged this concern and indicated that this matter would be evaluated.
This is considered a followup item.
(50-528/80-12/01)
6.
Unit 2 -Com onent Installation The partially installed Unit 2 reactor vessel and steam generators were examined to ascertain compliance with blPP/gCI 350.54-2 and HPP/gCI-350.36-2.
These procedures appeared to have been followed correctly.
In addition, tensioning of reactor vessel holddown studs 5 and 12 for reactor vessel support IB was observe No deviations or items of noncompliance were observed.
~
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7.
Calibration of Measurin and Test E ui ment Calibration records of the following measuring and test equipment associated with construction activities discussed in Paragraphs
and 6 were examined:
Electrical crimping tool JEB 0659 Go/no-go gage JEB 0078 Go/no-go gage JEB 199 Hydraulic wrench system Jt1A 0025 Telescopic transit square JAB 15 Optical transit JAB 16 See-through vertical spindle JAB 17 Automatic level Jl!A 0042 This review revealed a number of administrative errors and inconsistencies with the records such as:
Calibration control log specifying 30 day and 1 year calibration intervals for similar equipment.
Test and recalibration date on calibration control log not consistent with the test records.
Equipment check out log not up to date.
Cross outs on records not initialled.
Dates on calibration certificates which were not defined.
Confusion as to the purpose of the various types of
"calibration labels" used.
After review of all of the calibration records associated with this equipment, the inspector considers that the equipment was within calibration when used.
The administrative problems identified were discussed with the licensee who indicated prompt action would be taken to improve the administrative controls and record keeping in this area.
This item will be examined further during a future inspection.
(50-528/80-12/02).
8.
Unit 2 Containment Dome Liner The Unit 2 dome liner was get in place on the containment and alignment of the twelve 30 segments was in progress.
The inspectors observed significant mismatch and overlap of the segments in the top area where the dollar plate will be insta'lied; however, the segments in this area were not yet at their final elevation.
Melding of segments had not yet started, and the licensee committed
to have a formal welding sequence identified prior to start of
~
~
welding.
No deviations or items of noncompliance were identified.
9.
The inspectors met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on August 1, 1980.
The scope and findings of the inspection as noted in this report were discusse C