IR 05000482/1993007
| ML20035F315 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/12/1993 |
| From: | Powers D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20035F312 | List: |
| References | |
| 50-482-93-07, 50-482-93-7, NUDOCS 9304210143 | |
| Download: ML20035F315 (8) | |
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APPENDIX i
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION IV
Inspection Report:
50-482/93-07 Operating License: NPF-42
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Licensee:
Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839 Facility Name: Wolf Creek Generating Station (WCGS)
Inspection At:
Burlington, Kansas Inspection Conducted: March 29, through April 2, 1993
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Inspector:
L. D. Gilbert, Reactor Inspector, Maintenance Section Division of Reactor Safety Approved:
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( /2/f8 Dr. Dale A. Powers, Chief, Maintenance Section Date _
Division of Reactor Safety Inspection Summary Areas Inspected:
Routine, announced inspection of inservice inspection and repair / replacement programs.
Result s:
The inservice inspection program was effectively implemented, with
records of nondestructive examinations observed to be excellent (Section 2.1.1).
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The repair and replacement program was effectively implemented and well i
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documented, with performance of work activities observed to be good
(Section 2.1.2).
I The contract personnel used for the steam generator tube inspections and
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other inservice inspections were well qualified for the special processes (paragraph 2.2).
Summary of Inspection Find..as:
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No inspection findings were opened or closed.
- 9304210143 930414 PDR ADOCK 05000482 G
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Attachments:
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Attachment 1 - Persons Contacted and Exit Meeting
Attachment 2 - Documents Reviewed
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DETAILS 1 PLANT STATUS During this inspection period, the plant was in a re '. ) outage.
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2 INSERVICE INSPECTION - OBSERVATION OF WORK AND WORK ACTIVfTIES (73753)
The objectives of this inspection were to ascertain whether performance of inservice examinations, repair, and replacement of Class 1, 2, and 3 pressure retaining components were performed in accordance with the Technical Specifications, the applicable ASME Code, correspondance between NRR and the licensee concerning relief requests, and requirements imposed by NRC and
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industry initiatives.
2.1 Discussion 2.1.1 Inservice Inspection Activities The inspector observed steam generator tube inspection and plugging activities.
For the inspaction activity, the inspector observed the motorized rotating pancake coil probe passing through the calibratbn standard following examination of Tube 7 -122, which was the final operation for completing the eddy current test'.ng of Steam Generator B.
For the tube plugging activity, l
the inspector observed the mechanical plugging of Tubes 56-59, 54-59, 12-95, 47-99, and 45-101.
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The steam generator inspection and tube plugging activities were performed using Surveillance Test Procedure STS PE-022, " Steam Generator Tube Inspection," Revision 5.
The steam generator inspection consisted of a bobbin coil examination full length of all unplugged tubes in Steam Generator B.
The motorized rotating pancake coil probe was used on a sho-t segment of 62 tubes for further evaluation of certain indications identified during the bobbin coil data analysis as directed by Procedure ENG 06-350, " Steam Generator Data Analysis Guidelines," Revision 0.
The bobbin coil and rotating pancake coil examinations were performed using Procedure MRS2.4.2 GEN-35, " Eddy Current Inspection of Preservice and Inservice Heat-Exchanger Tubing," Revision 1.
The inspector verified that the tube plugging operations were performed in accordance with the requirements specified in Procedure MRS2.3.2 GEN-13,
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" Mechanical Plugging of Steam Generator Tubes," Revision 15.
The inspector i
i also verified that the material used for plugs was documented on the Bill of isterials in Work Orders 645-93 and 2331-92 and traceable to a certified i
material test report. The inspector reviewed the results of the eddy current
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testing for all the tubes in Steam Generator B.
The inspector determined that the inspection far exceeded the technical specification requirement to inspect at least 12 percent of the tubes in a steam generator and plugging of the five additional steam generator tubes met the surveillance requirements for Category C-2 as specified in Technical Specification 3/4.4.5.
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The inspector was informed that the inservice inspection examinations, scheduled for the current outage, had been completed with the exception of some piping system pressure testing scheduled for later in the outage. Since the inservice inspection activities had been completed ahead of schedule, two volumetric and two surface examinations were selected for records review from the list of inservice inspection examinations completed during the current outage. The inspector reviewed the first ten year Program Plan, WCRE-07, "lSI Program Plan Document," Revision 1 and verified that the examinations were included in the program document for the current inspection period (i.e.,
Period 3).
The two volumetric examinations reviewed were documented on Ultrasonic Data Sheets 2417-93-37 and 2417-93-45. The Ultrasonic Data Sheet 2417-93-37 l
documented the volumetric examination (Exam 1-BB-04-F001) of a reactor coolant
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system Code Class 1 pipe weld that connected a 4-inch pipe to the pressurizer
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spray nozzle safe-end. The Ultrasonic Data Sheet 2417-93-45 documented the volumetric examination (Exam 1-EJ-04-FW906A) of a residual heat removal system
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l Code Class 1 pipe weld that connected a 12-inch pipe to an elbow.
For each
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volumetric examination, the inspector verified from the records reviewed that the equipment used was calibrated, the system calibration was performed, the temperature difference between the component and calibration block was within the limits specified, and the applicable examination techniques recorded were consistent with the ultrasonic examination Procedure 83A2417, " Procedure for the Ultrasonic Examination of Piping System," Revision 3.
The two surface examinations reviewed were documented on Liquid Penetrant Data Sheets 1721-93-43 and 1721-93-50. The Liquid Penetrant Data Sheets 1721-93-43 and 1721-93-50 documented tha surface examination of the Code Class I welds described above as volumetric examinations,1-BB-04-F001 and 1-EJ-04-FW906A, respectively.
For each surface examination, the inspector verified that the materials used were appropriately certified and the applicable examination techniques recorded were consistent with requirements of Procedure 83A1721, " Liquid Penetrant Examination Procedure," Revision 5, Changes FCN-01 and FCN-02.
The volumetric and surface examinations were well documented and the examinations were performed consistent with the inservice inspection program requirements.
The inspector noted that the legibility of the examination data sheets was excellent.
The inspsctor also reviewed the qualifications and certifications of all nondestructive examination personnel involved in the performance, evaluation, and supervision of the steam generator inspection and other inservice inspection activities reviewed during the inspection. The inspector was provided satisfactory personnel certifications for the appropriate level of qualification for each method of nondestructive examination used. The certifications also documented a satisfactory annual visual acuity and color test for each of the nondestructive examination personnel.
The certifications were found to be current and consistent with the requirements of the applicable contractor procedure for qualification and certification of nondestructive examination personnel.
The certifications of contractor personnel for performing nonde:tructive examinations were well documented and
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-5-t included the approval of quality assurance and the ASME Authorized Nuclear Inservice Inspector.
2.1 -. 2 Section XI Repair and Replacement
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The inspector reviewed repair and replacement activities associated with a modification to the reactor coolant system piping for the reactor coolant pump thermal barrier, the replacement of leaking valves in the nuclear sampling system piping, and the repair of a socket weld in the steam generator bowl drain line.
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The modifications to the Code Class 3 portions of the reactor coolant piping l
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documented in Work Requests 01058-91, 01064-91, and 05909-92 and ASME
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Section XI Repair / Replacement Plans93-047 and 93-048. The replacement of the
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leaking Code Class 2 valves in the nuclear sampling system piping was r
l documented in Work Requests 955-91 and 956-91 and ASME Section XI Repair / Replacement Plans93-058 and 93-059. The inspector observed the piping i
installation activities and veritied that the piping installations were consistent with the five work request packages. The documentation in the work
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request packages included work instructions, plant modification package, bill
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of materials, weld data sheets, quality control inspections, nondestructive
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examinations, and post-installation testing. The workers interviewed that were performing the work in the plant were knowledgeable of the work t
instructions and the status of the work was consistent with the documentation in the applicable work request package.
The repair of the Code Class 2 piping socket weld in the steam generator bowl drain line was documented in Work Request 01797-93.
The inspector reviewed
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the work request package, which included the engineering disposition for i
repairing the linear indications identified in the socket weld. The work l
request package included instructions to remove and reweld the socket weld, documentation of the welding and quality control inspections, and records of nondestructive examinations, and instructions for post-maintenance testing.
l The repair and replacement activities were well documented and included notification of the Authorized Nuclear Inservice Inspector as required by Procedure ADM 01-036, "ASME Section XI Repair and Replacement Program,"
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2.2 Conclusiuns
The inservice inspection and repair and replacement programs were effectively
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implemented, with performance of work activities observed to be good.
The steam generator tube inspections and most of the other inservice inspection l
nondestructive examinations were performed by contract personnel that were
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well qualified for the special processes.
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ATTACHMENT 1
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PERSONS CONTACTED
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1.1 Licensee Personnel
- T. Anselmi, inservice Inspection Engineer
- C. DeLong, Supervisor, Quality Plant Support
- B. Grieves, Supervisor, Engineering
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- J. Lutz, Licensing Engineer
- 0. Maynard, Vice President, Plant Operations i
- G. Pendergrass, Supervisor, Results Engineering i
- G. Seier, Inservice Inspection Engineer S. Sprague, Welding Engineer
- M. Williams, Manager, Plant Support j
- J. Winkel, Authorized Nuclear Inservice Inspector l
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1.2 NRC Personnel G. Pick, Senior Resident Inspector i
In addition to the personnel listed above, the inspector contacted other personnel during this inspection period.
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- Denotes personnel that attended the exit meeting.
2 EXIT MEETING An exit meeting was conducted on April 1, 1993.
During this meeting, the inspector reviewed the scope and findings of the report. The licensee was notified that the inspection effort would continue through April 2, 1993.
The additional inspection effort did not result in a change to the inspection
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findings expressed at the exit meeting.
The licensee did not identify as proprietary any information provided to, or reviewed by, the inspector.
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ATTACHMENT 2
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DOCUMENTS REVIEWED ENG 06-350, " Steam Generator Data Analysis Guidelines," Revision 0
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ADM 05-'300, " Implementation of ISI Program Plan Scheduled Exams," Revision 1 WCRE-07, "ISI Program Plan Document," Revision 1, Change 030 ADM 05-119, "ISI Program Plan Document," Revision 1 STS PE-300, " Inservice Inspection Examinations," Revision 2, Change MI93-0295 STS PE-022, " Steam Generator Tube Inspection," Revision 5
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MRS2.4.2 GEN-35, " Eddy Current Inspection of Preservice and Inservice Heat-Exchanger Tubing," Revision 1 MRS2.3.2 GEN-13, " Mechanical Plugging of Steam Generator Tubes," Revision 15
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83A1721, " Liquid Penetrant Examination Procedure," Revision 5, Changes FCN-01 and FCN-02 83A2417, " Procedure for the Ultrasonic Examination of Piping Systems,"
Revision 3
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KGP-1265, " Inservice Inspection Program," Revision 1, Change PCN-1 ADM 08-300, " Control of Welding Operations," Revision 6 QA SURVEILLANCE TE: 53359 S-2021, " Steam Generator B Eddy Current Testing,"
dated March 31, 1993 i
ADM 01-036, "ASME Section XI Repair and Replacement Program," Revision 8 l
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