IR 05000528/1981009
| ML17297A836 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/20/1981 |
| From: | Bishop T, Burdoin J, Eckhardt J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17297A835 | List: |
| References | |
| 50-528-81-09, 50-528-81-9, 50-529-81-09, 50-529-81-9, 50-530-81-09, 50-530-81-9, NUDOCS 8109180340 | |
| Download: ML17297A836 (14) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OffICE OF INSPECTION AND ENFORCEMENT REGION V
Report Nos.
50-528/81-09 50-529 81-09 50-530 81-09 Docket Nos.
50-528 50-529 50-530 Licensee:
Arizona Public Service Com an P. 0.
Box 21666 Phoenix Arizona 85036 License No.
Facility Name:
Palo Verde Nuclear Generatin Station - Units
2 and
5
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Inspection At:
Palo Verde Construction Site Wintersbur Arizona
Inspection Cond ted:
Jul 6-10 1981
Inspectors:
.
H.
kh rdt, eactor Inspector-lI-D e Signed ld
.
F.
B rdoin, Reactor Inspector D te ig ed
Approved By:
T.
W. Bis op, Chief, Reactor Projects Section
Da e S gned Summary:
Ins ection on Jul 6-10 1981 Re or t Nos. 50-528/81-09 50-529/81-09 and
~50-53 51-55 5~II d:
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of activities associated with: piping installation and welding; containment post-tensioning; instrumentation systems and components; and electrical systems and components.
The inspection involved 60 inspector hours on-site by two NRC inspectors.
Results:
No deviations or items of noncompliance were identified.
8109180340 810820 t
- DOCK 05000528
'. 6 PDR RV Form 219 (2)
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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, Corporate gA Manager
- W. E. Ide, Site gA Supervisor R. J.
Kimmel, Field Engineering Supervisor G. Pankonin, gA Engineer D.
E. Fowler, gA Engineer L. Souza, gA Engineer D. Wittas, gA Engineer b.
Bechtel Power Cor oration Bechtel
- R. L. Patterson, Division Manager, gA
- S.
H. Nickell,'roject Superintendent
- A. K. Priest, Project Field Engineer
- D.
R. Hawkinson, Project gA Supervisor
- C. J.
Dun, Assistant Project Field Engineer
- H. A. Hear, Assistant Project gC Engineer D. Gray, gC Engineer, Instrumentation R. Gallatin, Field Engineer, Electrical D. Madden, Lead Field Engineer, Electrical R. Gutierres, gC Engineer, Mechanical c.
Western Concrete Structures Inc.
WCS K. Guffey, Project Superintendent.
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2.
Pi in Installation and Weldin Units 2'and
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The following pipi'ng and pipe'welding acti.vities were examined to ascertain compliance with"applicabl'e construction speci'fications, work plan and gC inspection procedures,,'and the ASME corfe.
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a.
Unit 2 (1)
Completed, weld'001<on 6 inch'-.pressurizer relief line pipe spool RC 001-'BCAA.
(2)
Tack.wel'd W003 on 1'4.inch: safety--injection spool SI-E-207-BCAA.
This weld had been'>inspected by. the AI for cleanliness and fitup, and purging was in',piogress.
(3)
Preheating of weld W001 on 30 inch NSSS pipe RC 079 to reactor coolant pump 2A in.preparation for Dimetrics machine welding.
fl (4)
Completed weld W001 on 6'inch auxiliary feed pipe spool AF-A-006-DCBA, (5)
Rod room No. 4.
Examination of rod ovens and rod storag II U
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NSSS piping stored in containment.',,-Pipe ends capped, proper rigging",, and pipe on tempo'rary hangers.
J t3 Completed wel'd'015 on '4,,inch'afety iiijection pipe spool SI-A-100-r jf
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Completed w'eld W008,on 3,,inch-charging system pipe spool CH-N-284-HCCA.'ll Completed weld W001 (Rl, R2) on 10 inch safety injection pipe spool S I-A-078-FCBA.
(4)
Completed weld W007 on -10, inch safety injection pipe spool SI-A-087-FCBA.
(5)
Completed weld W001 on 3 inch safety injection pipe spool SI-A-106-CCBA.
(6)
Completed weld W001 on 4 inch safety injection pipe spool SI-A-100-CCBB.
(7)
Completed weld W001 on 10 inch safety injection pipe spool SI-B-147-FCBA.
(8)
Pipe storage in auxiliary building.
Pipe ends capped and pipe protected during structural steel welding.
(9)
Rod room No. 13.
Examination of rod ovens and rod storage.
(10)
36 inch flued head penetration No.
26 for 16 inch safety injection line SI-194.
Dimetrics machine set up, ready for preheating, and purging in progress, The field welding checklists and filler metal withdrawal forms were reviewed for the above in-process welds, In addition, the field welding checklists and nondestructive examination records were reviewed for the following welds, which have been qC accepted:
Unit 2 WOOl, W001C Unit 3 W015 W008 W001 W001 h
spool AF-A-006-DCBA spool AF-B-035-DCCA spool S I-A-100-CCBA spool CH-N-284-HCCA spool SI-'A-106-CCBA spool S I-A-100-CCBB No deviations or items of noncompliance were identifie II 0'
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Containment Post-tensionin Containment post-tensionin'g 'system ac'tiviti'es, were'xamined to ascertain compliance with appli'cable'CS,p'roc'edui es.'
portion of the tensioning of Unit 1 vertical tendon-" No.'-,90 'has', observed..." Also examined were the installed tendon sheaths in the Unit 2 cohtainment dome and the Unit 3 containment wall.
Particular items checkeP 'included vent valve covers, seam taping, condition of sheathing, and,,tiedown of sheathing.
In addition, the physical and chemical properties test records of the sheathing filler material (Visconorust 2090P-4) for lot Nos.
1626, 103, 1022, and 02084 were examined for. compliance to the applicable ASTM requirements.
No deviations or items of noncompliance were identified.
4.
Instrumentation Unit 1 The inspector examined the Unit 1 plant protection systems, plant control system and selected instrument components described in detail below, to ascertain compliance with the FSAR and the following work plan procedures/g.C.
instructions; WPP/gCI 302, Mechanical Instrumentation Installation.
WPP/gCI 258.9, Electrical Instrument Installation.
a.
Plant Protection S stem The reactor trip system (RTS) and the engineered safety features actuation system (ESFAS) were examined.
Two process variables for each system (high containment and high steam generator pressure for the RTS, and low refueling water tank level and low steam generator level for the ESFAS)
were inspected from the transmitter located near the NSSS parameter taps
- to the instrumentation in the control room.
The installation of the plant protection system components were examined for:
(1)
Identification and location - proper type of instrument component with proper range, rating, and location.
(2)
Supports and protection physical protection from missiles and high energy line breaks.
(3)
Independence
- physical separation between redundant instrument components at sensors and actuating device in control panels.
(4)
Testing - calibration of indicating instruments in the control room, and pressure and level transmitters (sensors).
(5)
g.
C. inspection
-. including generation of inspection records during inspection activities by gC personne ik~...
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The task of installing and terminating instrumentation cables was in its early stages so these portions of the plant protection systems were not inspected.
No deviations or items of noncompliance were identified.
Plant Control S stem Two plant control system process variables (nuclear cooling water flow to reactor coolant pump 2B and main feed pump A discharge pressure)
were inspected from the parameter taps or sensor to the instrumentation in the control room for:
(1)
Identification and location - proper type of instrument component with proper range, rating and proper location.
(2)
Supports and protection - physical protection from missiles and high energy line breaks.
(3)
Independence
- physical separation between redundant instrument components at sensors and actuating device in control panels.
(4)
Testing - calibration of indicating instruments in the control room, and pressure and level transmitters (sensors).
(5)
g.
C. inspection - including generation of inspection records during inspection activities by gC personnel.
The task of installing and terminating instrumentation cables was in its early stages so this portion of,the system was not inspected.
It was found that the pressure tap coupling for the feed pump A discharge pressure was in contact with the piping hanger.
Novement of the pipe caused by thermal expansion would tend to shear off the pressure tap coupling.
The licensee s piping engineer investigated this deficiency and prepared a non-conformance report.
This issue will be examined during a subsequent inspection (50-,528/81-09/02).
i No deviations or items of noncompliance',were identified.
,
Instrument Com onent Record Generation and";Handlin
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The inspector review'ed the construction records for four thermometer wells, 1-J-PCA-TW-13
15 and 1-J'-PCB-TW-14 5 16; and'two panels:
IJZJAE-Ol and IJZJCE-Ol of the plant remote shutdown station.
I These records included the plan'/s'tat'4s of'install'ation'for the components, certification of welds, status of g,C. inspectjon and disposition of nonconformance reports.
No items of noncompliance 'or deviations were identifie I I>
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Electrical Com onent
S stems Unit'
The inspector examined, the Unit 1 direct current electrical power system and selected electrical components as described in detail below to ascertain compliance with the FSAR and applicable construction specifications.
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D.C.
Power S stem The 125 volt batteries A and D, the 125 volt main bus/load center M-44(d),
and 125 volt distribution panel E-PDK-D24 of Unit 1 DC power system were reviewed by the inspector for:
(1)
Construction installation in accordance with:
(a)
WPP/gCI - 258.3.-Battery System Installation.
(b)
WPP/gCI - 258.3-Power Distribution Equipment, Lighting and Control Panel Installation.
b.
(2)
Construction installation control and g.
C. inspection records (form 258.1).
(3)
Maintenance of batteries and distribution load centers, WPP/gCI-28.0-Maintenance of Materials and Equipment.
(4)
Receipt inspection, storage,. handling, and identification requirements.
(5)
Handling and documentation relative to nonconforming components and equipment.
(6)
Missile protection and separation requirements.
While examining partially completed work and/or completed work in the battery rooms, the inspector observed that the lighting fixtures supports appear to be non-seismic.
Some of the fixtures were located directly over the batteries.
The licensee committed to review the seismic design of the battery room lighting and supports to determine if the seismic design and classification is adequate for the area.
The licensee has a "Hazards Walkdown Procedure" to provide a systematic approach for identifying and resolving conditions in which hazards may affect safety-related systems, This procedure was reviewed by the inspector.
At the time of this inspection, thet hazards,walkdowns had not been initiated on any system.
This issue, will,be, reviewed during a subsequent inspection (50-528/81-09.01).
No deviations or items of noncompliance were identified.
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IJ Electrical Com'onents<.,
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The following electr'ical'coyponentst w'ere examined:
I (1)
Essential chilled water, circulating p'ump.motor (20 HP) 13-E-ECB-003.
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HPSI long term cooling valve motor (1.8 HP) J-SID-HV-331.
'3)
Diesel-generator Train A serial number 7184.
These components were inspected for:
(1)
Receipt inspection/acceptance requirements.
(2)
Storage identification and related record keeping.
(3)
Construction installation control and g.
C. inspection (form 580).
(4)
Maintenance of electric motors, motor operated control valves, and diesel generators; WPP/gCI 28.0-Maintenance of Materials and Equipment.
No deviations or items of noncompliance were identified.
6. ~iM On July 10, 1981, the inspectors met with the licensee representatives-identified in Paragraph 1 and summarized the scope and findings of the inspection as discussed in this report.
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