IR 05000528/1982010
| ML20054N063 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/24/1982 |
| From: | Eckhardt J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20054N061 | List: |
| References | |
| 50-528-82-10, 50-529-82-05, 50-529-82-5, 50-530-82-05, 50-530-82-5, NUDOCS 8207150315 | |
| Download: ML20054N063 (8) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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50-528/82-10
REGION V
50-529/82-05 Report flo.
50-530/82-05 Docket ?!o. 50-528. 50-529. 50-530 License No. CPPR-141.142.143 Safeguards Group Licensee:
Arizona Public Service Company P. O. Box 21666 Phoenix. Arizona 85036 Facility Name:
Palo Verde Nuclear Generating Station - Units 1, 2, and 3 Inspection at:
Palo Verde Construction Site. Wintersburg. Ari7nna Inspection conducted: March 29 - Aoril 7. 19R?
Inspectors *
d /2/!<N J./1. EckhardE, Reacto'r Inspector
/ Date/Signen Date Signed
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Approved by:
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6/zg/82 J. fi. Eckhardt, Acting Chief
/ Date' Signed R actor Projects Section 1 Summary:
l Inspection on March 29 - April 2, 1982 (Report Nos. 50-528/82-10, 50-529/
82-05, and 50-530/82-05)
Areas Inspected:
Routine, unannounced inspection by regional based inspector of construction activities associated with Unit 1 and 2 electrical cable installation, Unit 2 safety-related component installation, and IE Bulletin and Circular follow-up. The inspection involved 27 inspector-hours on-site by one NRC inspector.
Results:
One item of noncompliance concerning removal of installed equipment without proper documentaticn (paragraph 4) was identified.
8207150315 820625 gDRADOCK 05000528 PDR RV Form 219 (2)
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DETAILS 1.
Persons Contacted a.
Arizona Public Service Company (APS)
- E. E. Van Brunt, Jr., Vice President, Nuclear Projects Management J. A. Roedel, Corporate QA Manager
- D. B. Fasnacht, Nuclear Construction Manager
- W. E. Ide, Site QA Supervisor
- R. J. Kimmel, Field Engineering Supervisor L. Souza, QA Engineer B. S. Kaplan, Quality Systems Supervisor W. Quinn, Licensing Engineer G. Duckworth, QA Engineer
- M. T. Sweigart, Operations QA Engineer b.
Bechtel Power Corporation (Bechtel)
- W. J. Stubblefield, Field Construction Manager
- A. K. Priest, Project Field Engineer
- R. M. Grant, Project QC Supervisor
- J. E. Pfunder, Site Project QA Engineer D. R. Hawkinson, Project QA Supervisor C. J. Dun, Assistant Project Field Engineer
- Denotes those attending exit meeting.
2.
Licensee Action on Previous Inspection Finding The licensee action pertaining to the following item was examined:
(Closed) Open Item (50-528/80-04/04) Edge protectors on cable trays Metal edge protectors are now being installed on straight sections of cable tray and flexible rubber edge protectors on curved sections of cable tray where required to protect cable where it enters the tray.
During this inspection, no instances of missing edge protectors were identified during an extensive examination of installed cable in Units 1 and 2.
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Tour of Unit 3 The inspector conducted a Unit 3 tour to assess general construction progress and techniques. Particular areas inspected included Unit 3
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auxiliary, control, fuel handling, and containment buildings. Also, the inspector toured the Unit 3 NSSS laydown area and examined storage
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of the Unit 3 reactor vessel, steam generators, and safety injection I
tanks. Movement of a Unit 3 emergency diesel generator to the Unit 3 diesel generator buildins, in preparation of moving the diesel generator into the building, was obs trwi.
No deviations or items of noncunpliance were identified.
Electrical Cable Installation (Units 1 and 2)
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Units 1 and 2 electrical cable installation was examined to ascertain compliance with Bechtel cable installation and raceway installation construction specifications. The examination was performed in the general areas of the Unit 1 auxiliary and control buildings and the
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Unit 2 auxiliary building and diesel generator exhaust fan area.
Particular attributes checked included cable tray cleanliness, protection of installed cable, raceway support welding, raceway support bolting, cable tray fill, cable tray edge protectors, raceway and cable identification, j
and separation.
l In addition, the inspector observed cable pulling of three " train A" l
(red) cables (2EH001ACIFA) from a Unit 2 diesel generator room exhaust l
fan to the exhaust fan switchgear (approximately 230 feet). Also, the cable pulling card and the cable pulling tension calculations for these cables were reviewed.
The cable pulling equipment was observed to have a current calibration sticker.
The inspector observed a Class IE conduit support in the Unit 2 charging pump room for charging pump 2MCHEP01 to be mounted to the concrete wall with four Hilti anchor bolts. The support was associated with Class 1E " train B" conduit 2EZAIDBRR17 and junction box 2EZAIDBKKJ05.
The nuts on the two lower anchor bolts for this support were observed to be only finger tight; they were backed off from the support plate approximately one to two turns.
The nuts appeared to have been tightened at one time based on indications in the paint on the support and nuts.
The plate and nuts appeared to have been painted after proper installation of the nuts and prior to loosening of the nuts. Also_, the upper two nuts appeared to have been tampered with as evidenced by indications in the paint. The raceway inspection record ("racewa.i card") indicated that the support had been inspected and accepted on Jane 26, 1981.
The inspector found no evidence that the support was rot properly
installed at the time of the inspection; it appears that the nuts on the Hilti bolts were loosened at a later time. There was no documentation that these nuts had been loosened as required by Bechtel Procedure WPP/QCI-251.0, " Raceway Installation," paragraph 9.10 which states:
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"9.10 In the event a design change from Project Engineering, or any authorized rework occurs after a raceway has been installed and accepted, or partially accepted, the following criteria shall apply:
9.10.1 Issue a new control and tracking systems raceway card with appropriate rework instructions to the field.
Upon completion of raceway rework or design field change, the installer or responsible designee shall record the date of the rework, or design field change, signature and badge number.
9.10.2 The AFE shall note in the remarks section of the new card the document (s) authorizing the rework. The AFE/
QCE shall initial, stamp, and date respectively completion of rework. The AFE shall indicate completion acceptance with his signature and date (lower right hand corner)
" Raceway, Inspection Record."
The lack of documentation for loosening of the conduit support nuts is considered an item of noncompliance (50-529/80-05/01).
5.
Mechanical Equipment Installation (Unit 2)
The inspector examined the following installed Unit 2 mechanical equipment:
pressurizer, pressurizer relief valves (four), electric driver auxiliary feed pump, turbine driven auxiliary feed pump, and charging pumps i
(three). The purpose of the examination was to ascertain compliance with the construction specifications for equipment installation and j
maintenance of installed equipment. Attributes checked included equipment location and orientation, supports, mouriting, and equipment protection and cleanliness. The inspector noted that the housekeeping conditions
in the area below the pressurizer had deteriorated to an unsatisfactory level.
Immediate action was taken by the licensee to remedy this situation.
No deviations or items of noncompliance were identified.
6.
Licensee Action on IE Bulletins and Circulars The inspector reviewed the licensee's response to IE Bulletins and i
Circulars issued during 1976, 1977, and 1978. The purpose of the l
review was to evaluate the licensee's response to the issues addressed in the Bulletins and Circulars, and to verify that the proposed action
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had been accomplished, where applicable.
In addition to the Bulletins l
and Circulars, the licensee's files contained letters from the licensee to Bechtel and/or Combustion Engineering regarding the issues, responses
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l to the letters from Bechtel and/or Combastion Engineering, and letters from APS engineering to the appropriate organization reauesting that
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I the recommendations be acted upon. The following is a list of the individual Bulletins and Circulars examined.
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Circulars The following Circulars required the licensee to submit a written response to the NRC:
76-01 Crane Hoise Control-Circuit Modification, issued July 28, 1976. The Circular required the licensee to respond to the NRC within 90 days. The licensee's response dated December 22, 1976, indicated that the purchase specification for both the polar crane and cask handling crane adequately covered the issue.
76-02 Westinghouse BF (ac) and BFD (dc) Relays, issued August 18, 1976. The Circular required the licensee to respond to the NRC within 90 days. The licensee's responie dated December 16, 1976, in.'icated that none of the defective relays are incorporated into the design.
76-05 Hydraulic Shock and Sway Suppressors (ITT Grinnell),
issued October 8,1976. The Circular required the licensee to respond to the NRC within 90 days. The licensee's resp:nse dated November 2,1976, indicated that none of the subject su; pressors are incorporated into the design.
The following Circulars were issued fo: information only and no written response to the NRC was required:
77-01 Malfunction of Limitorg;e Valve Operators, January 3, 1977.
77-03 Fire Inside a Motor Control Center, March 3, 1977.
77-05 Liquid Entrapment in Valve Bonnets, March 29, 1977.
77-06 Effects of Hydraulic Fluid on Electrical Cables, April 6, 1977.
77-14 Separation of Contaminated Water System from Non-contaminated Plant Systems, November 22, 197._____
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78-02 Proper Lubricating 011 for Terry Turbines, April 20,
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78-04 InstaliaUnn Errors t' it could Prevent Closing of Fire Doors, May 18, 1978.
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78-05 Inadvertent Safety Injection During Cooldown, May 23, i
1978.
l 78-06 Potential Connon Mode Flooding of ECCS Equipment, May 25, 1978 l
78-07 Damaged Components of a Bergen-Patterson Series 25000
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Hydraulic Test Stand, May 31, 1978.
l 78-08 Environmental Qualification of Safety Related Electrical Equipment, May 31, 1978.
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78-09 Arcing of GE Company Size 2 Contractors, June 5, 1978.
78-13 Inoperability of Service Water Pumps, June 10, 1978.
78-15 Failure of Tilting Disc Check Valves to Close with l
Gravity in Vertical Position, July 20, 1978.
78-16 Limitorque Valve Actuators, July 26, 1978.
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78-18 UL Fire Test, November 6, 1978.
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78-19 Manual Override of Safety System Actuation Signals, I
December 29, 1978.
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Bulletins l
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'The following Bulletins (except where noted) required the licensee to submit a written response to the NRC:
76-06 Diaphram Failures in Air Operated Auxiliary Actuators for Safety / Relief Valves, issued July 21, 1976. A response to the NRC concerning this Bulletin was required
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only by those licensees holding an OL.
l 77-01 Pneumatic Time Relay Setpoint Drif t (ITE), issued i
April 29, 1977. Licensee required to respond to NRC within
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60 days. The licensee's response dated June 14, 1977, indicated that the Palo Verde design does not use the
i subject ITE relays.
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-6-77-02 Potential Failure Mechanism in Certain Westingh;use AR Relays with Latch Attachments, issued Septen.ber 12, 1977. Licensee required to respond to the NRC within 60 days. The licensee's resp: se dated November 3, 1977, indicated that the AR latch type relays are not used at Palo Verde.
77-04 Calculational Error Affecting the Design Performance of a System for Controlling pH of Containment Sump Water Following a LOCA, issued November 4, 1977. Licensee required to respond to the NRC within 60 days. The licensee's response dated December 13, 1977, indicated that the required information would be presented in the FSAR.
77-05 Electrical Connector Assemblies; issued November 8 and and November 15, 1977. Licensee required to respond 77-05A to NRC within 60 days. The licensee's responses dated January 3 and January 5, 1978, indicated that no Class 1E connectors of the type specified are used in the areas spec ified.
77-07 Containment Electrical Penetration Assemblies, issued December 19, 1977. Licensee required to respond to the NRC within 30 days. The licensee's response deted January 9, 1977, indicated that the penetration type specified are not used at Palo Verde.
77-08 Assurance of Safety and Safeguards During an Emergency, issued December 28, 1977. Licensee required to respond to the NRC within 60 days. The licensee's resporse dated February 14, 1978, indicated that Palo Verde would be in full conforman;e with the requirements noted in the bulletin.
78-01 Flammable Contact Arm Retainers in GE CR120A Relays, issued January 16, 1978, Licensee required to respond to the NRC within 60 days. The licensee's response dated February 28, 1978, indicated that the subject relays were excluded from use at Palo Verde.
78-02 Terminal Block Qualification, issued January 30, 1978, required a 30-day response, dated February 24, 1978.
78-04 Environmental Qualification of Certain Stem Mounted Limit Switches Inside Reactor Compartment, issued February 21, 1978, required a 60-day response, dated March 31, 197 _
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I 78-05 Malfunction of Circuit Breaker Auxiliary Contact Mechanism-GE Model CR105X, issued April 14, 1978, required a 60-day response, dated June 1, 1978.
78-06 Defective Cutler-Hammer, Type M Relays with DC Coils,
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issued May 31, 1978, required a 60-day response, dated July 17, 1978.
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78-10 Bergen-Paterson Hydraulic Shock Suppressor Accumulator Spring Coils, issued June 27, 1978, required a 60-day response, dated August 21, 1978.
78-12 Atypical Weld Material in Reactor Pressure Vessel Welds,
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issued September 26, 1978, required a 60-day response, dated November 21, 1978.78-12A Atypical Weld Material in Reactor Pressure Vessel Welds, issued November 24, 1978, required a 120-day response, dated December 7,1978.78-12B Atypical Weld Material in Reactor Pressure Vessel Welds, issued March 19, 1979. The licensee responded April 25 and June 26, 1979, and Combustion Engineering responded i
June 8, 1"79, with the reque:ted information.
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78-14 Deterioration of Buna-N Components in ASCO Solenoids, issued December 19, 1978, for information only.
Based on supporting evidence in the licensee's files, the inspector considers all of the required licensee's written responses (listed j
above) to be adequate. Also, evidence exists in the files that those Bulletins and Circulars listed above which did not require written
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responses were adequately considered and that the recommendations were transmitted to the appropriate organization. However, the inspector did not find evidence that the licensee had followed up to ensure that the recommended actions had been implemented or completed. This particular point was discussed with the licensee who indicated that their QA organization would perform an audit to ensure that the actions are complete. The inspector will continue to review the licensee's work in this area and will field check, during future inspections, selected Bulletins and Circulars to verify that the recommendations have been implemented.
7.
Exit Meeting On April 2, 1982, the inspector met with the licensee representatives (identified in paragraph 1) and summarized the scope of the inspection activities and reviewed the inspection findings, as described in this report.
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