IR 05000528/1996019
| ML17312A996 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/09/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17312A995 | List: |
| References | |
| 50-528-96-19, 50-529-96-19, 50-530-96-19, NUDOCS 9610110247 | |
| Download: ML17312A996 (12) | |
Text
ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket Nos.:
License Nos.:
Report No.:
Licensee:
Facility:
Location:
Dates:
Inspector:
Approved By:
50-528 50-529 50-530 NPF-41 NPF-51 NPF-74 50-528/96-1 9 50-529/96-1 9 50-530/96-1 9 Arizona Public Service Company Palo Verde Nuclear Generating Station, Units 1, 2, and 3 5951 S. Wintersburg Road Tonopah, Arizona September 23-27, 1996 W. M. McNeill, Reactor Inspector, Maintenance Branch Division of Reactor Safety Dr. Dale A. Powers, Chief, Maintenance Branch Division of Reactor Safety Attachment:
Partial List of Persons Contacted List of Inspection Procedures Used List of Items Opened List of Documents Reviewed 96iOli0247 961009 PDR ADOCK 05000528
-2-EXECUTIVE SUMMARY Palo Verde Nuclear Generating Station, Units 1, 2, and 3 NRC Inspection Report 50-528/96-19; 50-529/96-19; 50-530/96-19 Maintenance
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The Inservice Inspection Program continued to be implemented well (Section M1.1).
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An inspection followup item was identified regarding use of calibration blocks (Section M1
~ 1)
-3-Re ort Details Summar of Plant Status Units 2 and 3 were operating at 100 percent power and Unit 1 was in its sixth refueling outage (U1R06) scheduled from September 21 through November 1, 1996.
II. Maintenance M1 Conduct of Maintenance M1.1 General Comments a.
Ins ection Sco e
73753 The inspector observed the following inservice inspection activities of welds and supports that were identified in the licensee's program:
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Ultrasonic Examination - Pipe Welds (ASME Item 521):
Nos.
1 on Line SG-13-14 and 15 on Line SG-2-14 in Zone 54;
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Magnetic Particle Examination - Pipe Welds (ASME Item 521):
Nos.
1 on Line SG-13-14 and 15 on Line SG-2-14 in Zone 54; 41-44 on Line SG-2-16 and 41-45 on Line SG-13-16 in Zone 41;
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Liquid Penetrant Examination - Pipe Welds (ASME Item 540):
Nos. 2 and 7 on Line RC-18-4; 5 on Line RC-7-6 and 13 Line RC-3-6 in Zone 31; and
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Visual Examination - Pipe supports (ASME Item 64): Nos. 9, 18, 21, 22, 24, and 25 on Line SG-039 in Zone 64.
b.
Observations and Findin s The inspector found the work was performed in accordance with the program, procedures, and ASME Code requirements.
Rejectable conditions on hangers (loose nuts) were identified and reported.
The authorized nuclear inservice inspector accompanied the NRC inspector during this inspection and appeared to be witnessing a majority of inservice inspection activities.
The inspector found that the ultrasonic examinations of Welds 41-44 and 41-45 were not performed because of confusion on which calibration block to use for the examination.
The inspector found the "zone drawing summary" identified calibration block Nos. 29 and 72 to be used for these welds.
The "outage inservice plan table" identified block Nos. 29 and 75 to be used for these welds.
The ASME
Code IWA-2232(c)(4)(a)(3) requires the material to be of the same material specification as that inspected.
A calibration block assures the system obtains a proper response from a minimum sized reflector or flaw.
The inspector found the materials for the calibration blocks were SA 533 Group B for No. 29, SA 106 Group C for No. 72 and SA 333 Group 6 for No. 75.
The pipe to be inspected was SA 508 Class 2.
During preservice inspection in 1981 for Unit 1 calibration block No. 29 was used.
A subsequent examination in Unit 1 of the companion steam generator (No. 2)
performed in 1989 of similar welds (42-44 and 42-45) used both calibration blocks 72 and 75.
In Unit 2 calibration block No. 75 was used for examination in 1990 of similar welds (42-43 and 42-44) in No. 2 steam generator and in 1996 for examination of both steam generator's welds (41-43, 41-44, 42-43 and 42-43).
In Unit 3 calibration block No. 75 was used for a similar weld (42-38) in 1991 and calibration block No. 72 was used for another similar weld (42-39) in 1994.
The licensee initiated Condition Report/Disposition Request 961054, which identified that calibration blocks of the same material were not being used.
The closeout of this nonconformance report is an inspection followup item (50-528/-529/-530/9619-01)so that the it may be verified there is not a technical problem or a generic problem on the use of calibration blocks.
c.
Conclusions The Inservice Inspection Program continued to be well implemented.
The confusion.
on the use of calibration blocks, at this time, did not appear to be a technical problem, but an administrative problem.
The resolution of the inspection followup item on the nonconformance report should resolve any questions on the generic impact and if any technical issue has been overlooked.
M3 Maintenance Procedures and Documentation The inspector reviewed the records of comparable testing performed in Units 2 and 3.
The records were in accordance with the program, procedures, and ASME Code requirements.
M4 Maintenance Staff Knowledge and Performance The inspectors noted the knowledge and performance of the contractor staff and licensee staff was goo h I
-5-M7 Quality Assurance in Maintenance Activities a.
Ins ection Sco e 73753 The inspectors reviewed the licensee's quality assurance audits and evaluations of inservice inspection activities.
b.
Observations and Findin s The inspector noted that the licensee concentrated its audit and evaluation efforts on eddy current testing of steam generator tubing.
Only limited auditing and evaluations were performed on the rest of inservice inspection activities.
The licensee is considering performing some evaluations of the rest of inservice inspection activities in the near future.
C.
Conclusion The licensee's quality assurance audits and evaluations of inservice inspection activities were adequate III. En ineerin E2 Engineering Support of Facilities and Equipment E2.3 Review of Final Safet Anal sis Re ort Commitments A recent discovery of a licensee operating their facility in a manner contrary to the Final Safety Analysis Report (FSAR) description highlighted the need for a special focused review that compares plant practices, procedures, and/or parameters to the FSAR descriptions.
While performing the inspection discussed in this report, the inspector reviewed sections of the FSAR associated with the Inservice Inspection Program.
The inspector did not identify any discrepancies between the FSAR and the Inservice Inspection Program.
V. Mana ement Meetin s
X1 Exit Meeting Summary The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on September 27, 1996. The licensee acknowledged the findings presented.
The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary.
No proprietary information was identifie ATTACHMENT PARTIALLIST OF PERSONS CONTACTED Licensee W. Ahlstrom, Engineer T. Cannon, Department Leader, Specialty Engineering B. Eklund, Consultant, Nuclear Regulatory Affairs A. Krainik, Department Leader, Nuclear Regulatory Affairs D. Marks, Section Leader, Nuclear Regulatory Affairs A. Morrow, Section Leader, Inservice Inspection F. Poteet, Senior Engineer R. Stroud, Consultant, Nuclear Regulatory Affairs R. Younger, Department Leader, Engineering Assurance Lambert MacGill Thomas Inc.
J. Harry, Inspector Level II E. Thomas, Inspector Level III W. Thomas, Inspector Level II Hartford Steam Boiler Ins ection and Insurance Com an R. Hogstrom, Authorized Nuclear Inservice Inspector NRC D. Garcia, Resident Inspector INSPECTION PROCEDURES USED IP 73753
'nservice Inspection
~Oened 50-528;529;530 IFI
/961 9-01 ITEMS OPENED Correct UT Calibration Blocks (Section M1.1.c)
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-2-LIST OF DOCUMENTS REVIEWED Program No. ISI-1, lnservice Inspection Program Summary Manual, Revision
Nuclear Administrative and Technical Manual:
Procedure 73AC-OXI01, ASME Section XI Inservice Inspection, Revision 01.04 Procedure 73DP-9EE02, Inservice Inspection Examination Activities, Revision 00.03 Procedure 73TI-9ZZ18, Visual Examination of Support Components, Revision 6 Procedure 73TI-9ZZ09, Ultrasonic Examination of Pipe Welds, Revision 7 Procedure 73TI-9ZZ07, Liquid Penetrant Examination, Revision 5 Procedure 73TI-9ZZ05, Dry Magnetic Particle Examination, Revision 6