IR 05000269/1988030
| ML16127A242 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Crane  |
| Issue date: | 10/07/1988 |
| From: | Blake J, Coley J, Glasman M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16127A241 | List: |
| References | |
| 50-269-88-30, 50-270-88-30, 50-287-88-30, 50-289-88-30, NUDOCS 8810250060 | |
| Download: ML16127A242 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., ATLANTA, GEORGIA 30323 Report Nos.:
50-269/88-30, 50-270/88-30, and 50-287/88-30 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-269, 50-270, License Nos.: DPR-38, DPR-47, and and 50-287 DPR-55 Facility Name: Oconee 1, 2, and 3 Inspection Conducted: August 29 -
September 2, 1988 Inspectors:
w.7 J. L. "Iey Date Signed manDate Signed Approved b JJBlake, Section Chief DtSigned n neering Branch
i ision of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection was in the areas of inservice inspection -
observation of work activities, review of data and evaluations, and Steam Generator 3B tube sleeving repair Results:
Duke Power Company (DPC) management was responsive to the inspector's questions and concerns and were actively involved in assuring qualit Rigorous training, and experienced vendor nondestructive examination personnel contribute significantly to the effectiveness of the licensee inservice inspection progra In the areas inspected, violations or deviations were not identifie S1011 PDR ADOCK 05000269 PDC
REPORT DETAILS 1. Persons Contacted Licensee Employees G. Baker, Supervisor, Eddy Current Acquisition
- T. Hildebrand, Supervisor, Eddy Current Analyst
- M. Hipps, Maintenance Engineer
- B. Hunt, Quality Assurance Engineer
- F. Owens, Regulatory Compliance
- M. Tuckman, Station Manager Other licensee employees contacted during this. inspection included craftsmen, engineers, technicians, and administrative personne Other Organizations Babcock and Wilcox (B&W) Special Products and Integrated Field Services H. Stoppelman, ISI Supervisor J. Walden, ISI Technician G. Nagy, Task Leader, Steam Generator Sleeving Operations D. Mezzano, Process Engineer NRC Resident Inspector
- P. Skinner, Senior Resident Inspector
- Attended exit interview 2. Inservice Inspection (ISI) Unit 3 (73052, 73753 and 73755)
The inspectors reviewed procedures, observed work activities, reviewed and evaluated recorded data, and observed code repair activities on Steam Generator 3B to determine whether the licensee's program pertaining to ISI and code repairs was being effectively implemented at the Oconee facilit The applicable code for the Unit 3.ISI is the ASME Boiler and Pressure Vessel (ASME B&PV)
Code,Section XI, 1980 Edition, with the Winter 1980 Addend a. Review of Procedures, Instructions and Drawings During the inspectors' observation of work activities, the proce dures, instructions and drawings listed below were reviewed to determine if the observed work was being performed in accordance with these procedures, instructions, or drawings and to determine whether the procedures had been approved by authorized licensee personnel and the authorized nuclear inservice inspector, where applicabl DPC Procedure N NDE-12, Revision 5, "General Radiographic Procedure for Preservice and Inservice Inspection" B&W Procedure N ISI-130, Revision 24, "Ultrasonic Examination of Vessel Welds and Nozzle Inside Radius Section"
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B&W Procedure No. ISI-418, Revision 4, "Technical Procedure for the Multifrequency Eddy Current Examination of OTSG Tubing in
[Model] 177 Steam Generators Using the MIZ-18"
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DPC Procedure N NDE-700, Revision 0, "Multifrequency Eddy Current Examination of OTSG Tubing in the [Model] 177 Steam Generator Using the MIZ-18
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B&W Procedure No. ISI-460, Revision 14, "Technical Procedure for the Evaluation of Eddy Current Data of Nuclear Grade Steam Generator Tubing"
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B&W Drawing 1154519A, Revision 8, "Tube/Sleeving Roll Expanding"
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B&W Drawing 1154519A, Revision 8, "Field Procedure for Once Through Steam Generator Tube Sleeving"
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B&W Drawing 1157633A, Revision 9, "Tool Operating Instruction:
The Lower Roll Expander OTSG Sleeving Using the SDLC Sleeving Control System" The above procedures were also reviewed to determine if the following information was included and adequate:
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Qualifications of examination personnel was specified
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Methods of examination, extent and technique was adequately described
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Methods of recording, evaluating, and dispositioning findings was established
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Reporting requirements were in compliance with applicable code requirements b. Observation of Work Activities The inspectors observed three different methods of examination of components which included the following:
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Volumetric examination of welds using the manual (A-Scan)
Ultrasonic Technique (Volumetric examination of nozzle to vessel weld and radiused section)
Volumetric examination of welds using the radiographic technique (Radiographic Film Reviewed)
Volumetric examination of Steam Generator (SG) tube using the eddy current technique Examinations of the following welds/tube were observed by the inspectors:
Method of Inspection Item Examined Weld/Tube N Review of Radiographic Film C05.021.308 3-03-29-WG91-H Review of Radiographic Film C05.021.368 3-OIA-13-19 Review of Radiographic Film C05.021.379 3-O1A3MG-16A-A Review of Radiographic Film C05.022.016 3-O1A3MG-16A-AL Review of Radiographic Film C05.021.387 3-01A-10-19 Review of Radiographic Film C05.021.381 3-O1AMG-23A-A Review of Radiographic Film C05.021.362 3-01A-13-16 Review of Radiographic Film C05.022.011 3-O1A-13-16L Manual Ultrasonic Examination C02.021.002 3SGA-WG23-2 (Weld)
Manual Ultrasonic Examination C02.022.002 3SGA-WG23-2 (Radiued Section)
Eddy Current Data Acquisition SG-B Row 98 Column 88 Eddy Current Data Acquisition SG-B Row 98 Column 101 Eddy Current Data Acquisition SG-B Row 98 Column 109 Eddy Current Data Acquisition SG-B Row 98 Column 110 Eddy Current Data Acquisition SG-B Row 98 Column III Eddy Current Data Acquisition SG-B Row 98 Column 112 Eddy Current Data Acquisition SG-B Row 98 Column 113 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 26 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 25 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 24 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 22 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 21 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 20 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)-
Row 127 Column 19 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 18 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 17 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 11 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 16
Method of Inspection Item Examined Weld/Tube N (cont'd)
Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 15 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 14 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 13 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 12 Secondary Eddy Current Data Analysis SG-A (Bobbin Coil)
Row 127 Column 10 Eddy Current Data Analysis SG-B (Sleeved Tubes)
Row. 77 Column 27 Eddy Current Data Analysis SG-B (Sleeved Tubes)
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Row 77 Column 26 Eddy Current Data Analysis SG-B (Sleeved Tubes)
Row 77 Column 6 Eddy Current Data Analysis SG-B (Sleeved Tubes)
Row 78 Column 7 Eddy Current Data Analysis SG-B (Sleeved Tubes)
Row 78 Column 5 Eddy Current Data Analysis SG-B (Sleeved Tubes)
Row 77 Column 22 Eddy Current Data Analysis SG-B (Sleeved Tubes)
Row 77 Column 8 Eddy Current Data Analysis SG-B (Sleeved Tubes)
Row 77 Column 6 Eddy Current Data Analysis SG-B (Sleeved Tubes)
Row 78 Column 12 Eddy Current Data Analysis SG-B (Sleeved Tubes)
Row 78 Column 11 For each of the methods of examination observed above, the inspectors verified that the following requirements were met:
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Approved procedures are available, are being followed, and specified Nondestructive Examination (NDE)
equipment was being use Examination personnel are knowledgeable of examination method and operation of test equipmen Examination personnel with proper level of qualification and certification are performing the various examination activities, including designation of examination method/technique to be used, equipment calibration, examination, and interpretation/
evaluation/acceptance of test result Examination results, evaluation of results, and any corrective actions/repairs/replacements are being recorded as specified in the ISI program and NDE procedure Certification/Qualification records were reviewed for the examination personnel listed below:
Name Method/Level Company M. Brown ET, L-IIA DPC T. Hildebrand ET, L-IIA DPC R. Neyman ET, L-IIA Flour Daniel M. Klatt ET, L-IIA B&W E. Lopez ET, L-IIA Allen Nuclear Associates V. Lynn ET, L-IIA Allen Nuclear Associates D. Robinson UT, L-II DPC W. Robinson RT, L-II DPC J. Rogers RT, L-I DPC J. Donald RT, L-II DPC H. Stoppleman UT, L-II B&W T. Walden UT, L-II B&W The inspectors also observed the following Steam Generator 3B sleeving repair/modification work activitie This sleeving operation was performed on the upper 80 inches of tubing from the upper tube sheet and extending below the 15th support plat (1) Calibration check of sleeve rolling equipment:
The calibration observed by the inspectors was for expansion rolling of the sleeves below the 15th support plate. The intent of the calibration was to determine the extension of the roll expansion tooling and to assure a constant degree of expansion during the life of the roll expansion too The roll expansio tool that is in contact with the sleeving consists of four roller Rollers are changed after 50 roll expansion operation The observed calibration was satisfactory. Listed below are the sleeve expansion tools and calibration blocks involved in the calibration observed by the inspectors:
o Roll expander, Serial No. 80-38 o
Flexpander, Serial No. 80-28 o
Tool Head, Serial No. 4 o
Calibration Block, Serial No. CB-4 o
Calibration Block, Serial No. CB-2
(2) Sleeving operation observed:
Row Column
2 Data Review and Evaluation During the present refueling outage, the licensee had performed the second consecutive examination of the upper head to tube sheet weld (3SGB-WG58-1).
This weld was discovered to have rejectable indica tions when evaluated to the ASME Code acceptance standards for indications detected by ultrasonics during the sixth refueling outag The ASME Code (Section XI), however, allows fracture mechanics to be used to determine acceptance of indication based on the remaining through-wal When fracture mechanics is used for acceptance, the Code also requires the licensee to monitor the indications for three subsequent outages to determine if the indications were growing in through-wall depth The licensee had intended to have the weld examined this outage using an advance automated ultrasonic system to establish an accurate base line of recorded data for future examination However, the vendor chosen by the licensee to perform the examination did not have an acceptable QA program when audited by DPC and their services could not be utilized this outag As a result, the licensee used the manual method of ultrasonics and the vendor who had discovered the indications and that had performed the first re-examination in the seventh refueling outage. The inspectors reviewed the completed examination data and evaluations for the initial examination and the first re-examinatio The inspectors also reviewed the preliminary ultrasonic data taken this outage to determine if the indications were growing and if the examination equipment was performing within acceptable parameters of the initial examination. Calibration sheets, transducer beam profile and recorded indications were compared. The inspectors noted that the ultrasonic data taken during the seventh refueling outage had revealed three indica tions were slightly smaller than recorded during the sixth refueling outage and 16 indications were slightly large None of the differences noted in the seventh outage impacted the fracture mechanics evaluation performed on the indications during the initial examinatio Examination data taken this outage had not been reviewed by B&W to determine indication growth or acceptance. The inspectors noted that the licensee had used the same transducers for all three examinations performed to dat Beam profiles taken of the transducers on a calibration block remained comparabl The inspectors did note,
however, that different ultrasonic instruments were used during each outage; a Krautkramer USM-2 was used during the sixth refueling outage, a Krautkramer USIP-11 was used during the seventh refueling outage, and Krautkramer USD-10 and USK-7 instruments were used during the present outage. Final data taken during this outage will be further reviewed by the inspectors when received in the licensee 90 day repor In addition, the licensee's Quality Assurance Engineer for ISI was requested and agreed to notify the inspectors when the third examination of weld 3SGB-WG58-1 will be performed so that the advance automated examination can be observed by NRC and the recorded data of all four examinations compare Within the areas examined, violations or deviations were not observe. Action on Previous Inspection Findings (92701, 92702)
(Closed)
Inspector Followup Item 269, 270, 287/86-23-01, Verify Adequacy of UT Scanning Speed for Manual Examination of the Reactor Vessel Flange Clad Surfac DPC had contracted B&W to make the scanning speed evalua tions of the calibration block using the clad.surface similar to that on the reactor vessel flang B&W found that the six inches per second scanning speed allowed by code was adequate to reveal the reflectors at an amplitude that would require investigation and recording if determined relevan. Exit Interview The inspection scope and results were summarized on September 2, 1988, with those persons indicated in paragraph 1. The inspectors described the areas inspected and discussed in detail the inspection results. Although reviewed during this inspection, proprietary information is not contained in this report. Dissenting comments were not received from the licensee.