IR 05000269/1992021
| ML16148A687 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/14/1992 |
| From: | Blake J, Coley J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16148A686 | List: |
| References | |
| 50-269-92-21, 50-270-92-21, 50-287-92-21, NUDOCS 9209290087 | |
| Download: ML16148A687 (12) | |
Text
\\ 8 RE3o UNITED STATES o
NUCLEAR REGULATORY COMMISSION REGION 11 101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report Nos.:
50-269/92-21, 50-270/92-21, and 50-287/92-21 Licensee:
Duke Power Company P.O. Box 1007 Charlotte, N.C. 28201-1007 Docket Nos.:
50-269, 50-270,
-License Nos.:
DPR-38, DPR-47, and 50-287 and DPR-55 Facility Name:
Oconee Units 1, 2, and 3 Inspection Conducted:
August 24-28, 1992 Inspector: ColeyDate Signed Approved by:
. Blake, Chief Date Signed Werials and Processes Section Engineering Branch Division of Reactor Safety SUMMARY Scope:
This routine, announced inspection was conducted onsite in the areas of Inservice Inspection (ISI) -
observation of work activities and review of completed record In addition, radiographic film packages for replacement piping welds and plant modification welds were examine Results:
In each of the areas examined the inspector discovered that nondestructive test (NDE) examiners were conducting effective examinations in accordance with the appropriate test procedur Supervisors, engineers, and NDE examiners contacted during this inspection were very knowledgeable in their responsible area One non-cited violation was identified: "Failure of Radiographic Technique to Discern Penetrameter Image", paragraph 3. During routine inspections on the 28" main steam system piping located on the auxiliary building roof for Unit 3, the inspector observed that 12 fasteners, which support the structural platform above the main steam piping and the safety relief valves, were 9209290087 920922 PDR ADOCK 05000269 PDR
misaligned and lacked full thread engagement into the embedded anchors. Duke's design engineering was notified of the fastener/anchor discrepancies and a Problem Investigation Report was issued by Duke to analyze the problem and to determine what subsequent actions would be required, paragraph.
Persons Contacted Licensee Employees
- G. Bibb, UT Examiner
- T. Coleman, ISI Coordinator/Compliance Engineer
- C. Freeman, NDE Supervisor
- R. Harris, ONS Regulatory Compliance
- J. McArdle, NDE Level III Examiner
- 0. Kohler, ONS Regulatory Compliance
- B. Peele, ONS Engineering
- S. Perry, Regulatory Compliance
- R. Pettit, ISI Outage Support
- M. Salim, ONS Component Engineering
- J. Weir, ONS Component Engineering Supervisor Other licensee employees contacted included technicians, operators, mechanics, security force members, and office-personne NRC Resident Inspectors P. Harmon
- B. Desai K. Poertner
- Attended exit intervie Acronyms and initialisms used throughout this report are listed in the last paragrap.
Inservice Inspection (ISI)
The inspector reviewed documents and records, and observed activities, as indicated below, to determine whether ISI was being conducted in accordance with applicable procedures, regulatory requirements, and licensee commitment The applicable code for ISI, for Unit 1, Unit 2, and Unit 3, is the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME B&PV) Code,Section XI, 1980 Edition with Addenda through Winter 1980 (80W80)., Unit 1 is operating, in the fourteenth fuel cycle, or the third 40 month period, of the second ten year ISI interval (P3,I2).
Unit 1 received its operating license on February 6, 1973 and commenced commercial operations on July 15, 197 Unit 2 is operating, in the thirteenth fuel cycle, or the third 40 month period, of the second ten year ISI interval (P3,I2).
Unit 2 received its operating license October 6, 1973 and commenced commercial operations on September 9, 197 Unit 3 has completed the thirteenth fuel cycle, and is in the second outage of the third 40 month period, of the second ten year ISI interval (P3,I2).
Unit 3 received its
operating license July 19, 1974 and commenced commercial operations on December 16, 1974. The licensee's nondestructive examination personnel are performing the liquid penetrant (PT), magnetic particle (MT), ultrasonic (UT) and radiographic (RT) examinations under the umbrella of the Duke Power Company (DPC) Quality Assurance (QA)
program. Babcock and Wilcox (B&W) is performing steam generator tube plugging repair activities, under the umbrella of the B&W QA program. Program and procedure review and eddy current examination activities normally examined during an outage were examined by inspectors in a previous inspection and reported in Region II, Inspection Report 50-269,270, and 287/92-1 Observation of Work and Work Activities, Unit 1 (73753)
The inspector observed work activities, reviewed certification records of NDE equipment and materials, and reviewed NDE personnel qualifications for personnel utilized in the ISI examinations during this outag The observations conducted by the inspector are documented belo *l Activities Observed Liquid Penetrant Examination (PT)
The inspector observed PT examinations of piping welds listed below to determine whether the examinations were conducted in accordance with the licensee's approved procedure NDE-35, Rev.1 The inspector also performed an independent evaluation of the indications obtained to confirm the NDE examiner's evaluatio Liquid Penetrant Examinations Observed Item No Weld N System C05.011.11 High Pressure Injection C05.011.014
High Pressure Injection The examinations were performed and indications evaluated satisfactoril.
Magnetic Particle (MT) Examination The inspector observed the MT examination of the welds for the items listed below to determine whether the examinations were performed in accordance with the licensee's approved procedure NDE-25, Rev. 1 The inspector also performed an independent evaluation of the indications obtained to confirm the NDE examiner's evaluatio Magnetic Particle Examinations Observed Item No System C05.031.005 Main Steam C05.031.006 Main Steam C05.040.019 Main Steam The inspector reviewed the certification documentation for gray MT powder Batch No.89DO81 and 88-DOO50, yoke#
OC-QA-205, and field indicator OC-QA--FI-1. The inspector also reviewed the certification, qualification, and visual acuity documentation for MT level II examiner T. The examinations were satisfactorily performed in accordance with the approved examination procedur However, during the MT examinations of two 28" Di main steam welds above the auxiliary building roof on Unit 3, the inspector noted that the structural steel platform, located above the main steam relief valves, had 12 embedded anchors that were misaligned. This resulted in fastener.misalignment and, in the worst case, incomplete thread engagement of approximately 3/4".
The licensee's design engineering was notified and after performing a visual examination of the reported fastener/anchor discrepancies, issued Problem Investigation Report No.3-092-0406 to handle the concern. Licensee actions regarding this issue will be verified during a subsequent inspectio II
Ultrasonic Examination (UT)
The inspector observed examiners perform equipment calibrations and ultrasonic examinations for the welds listed below. The examinations were observed to determine whether approved procedures were being followed, if examination personnel were knowledgeable of the examination method and operation of the test equipment, whether welds were properly scanned, and whether examination results and evaluations of the results were recorded, plotted, and dispositioned correctl The applicable procedure for the examinations was NDE-600, Revision 1. Personnel and equipment certifications were verified by the inspector The following ISI examinations were observed by the inspector:
Ultrasonic Examinations Observed Weld Number Item Number Size 53.18-6 B09.011.201 10" DIA x 1.0" 53.18-8 B09.011.328 10" DIA x 1.0" The above calibrations and examinations were conducted in accordance with the approved procedure and evaluation of indications appeared to be satisfactor Radiographic (RT) Examination The inspector reviewed the radiographic film for the welds listed below to determine if the radiographic quality and the evaluation of the examination results were in accordance with the requirements of the approved radiographic procedure (NDE-12 Rev.8).,
ISI Item N Weld N Size C05.021.386 3-01A-10-16 12"Dia.x.562" Th C05.021.308 3-03-29-WG91-H 14"Dia.x.750" Th C05.021.361 3-01A-13-13 36"Dia.x 1.164" Th C05.022.010 3-01A-13-13L Longitudinal Seam
The review of the above film revealed that Duke's radiographic examiners are obtaining high quality radiographs and that evaluation of discontinuities were within Code requirement Code Repairs The inspector reviewed procedures, observed work activities, and reviewed selected quality records associated with the plugging of the A and B Steam Generator tubes which had been rejected during eddy current examinations conducted this outage. The repair activities were controlled by the B&W QA program. As a result of inspections this outage, 74 tubes in A Steam Generator and 52 tubes in B Steam Generator had to have roll plugs installed. The following procedures were reviewed by the inspector to insure.they had been properly approved and that the subject material properly controlled the repair activitie Document N Title 1154835A Rev.26 Roll Plugging & Flex, Segmented or Hybrid Stabilization Field Procedure 1183514A Field Procedure/operating Instruction for Preparing a Sleeved OTSG Tube for Installation of a Rolled Plug 1169879A Re Field Procedure for Manual and Remote Marking of Tube Locations in a OTSG In addition to the above review, the inspector observed mockup training for manual insertion of tube plugs and stabilizers, observed the staging of the computer operated equipment fixtures and observed the plugging operations for the following tube Row N Tube N SG Tube Sheet 139
B Upper 130
B Upper 140
B Upper
52 A
Lower
128 A
Lower 101
A Upper
8 A
Upper
10 A
Upper
3 A
Upper
5 A
Upper
3 A
Upper
4 A
Upper
2 A
Upper
3 A
Upper
4 A
Upper
11 A
Upper
8 A
Upper
40 A
Upper
45 A
Upper The above plugging activities were performed in accordance with the approved procedures and appeared to be satisfactor Data Review and Evaluation, Unit 3 (73755)
The inspector reviewed completed ultrasonic data and evaluations of welds where recordable indications had been detected to determine if indications were properly interpreted and dispositioned. The inspector also reviewed previously recorded data for welds that were in service base on a fracture mechanics analysi.Records for the following welds were reviewed:
Examination Records Examined Weld ID Number Item Number Component 3-53A-15.2-64 C05.021.002 Pipe to Pipe 3-53A-17-17 C05.021.003 Pipe to Pipe 3-SGA-WG58-1 B02.040.001 Upper Head to Tube sheet 3-SGB-WG58-1 B02.040.003 Upper Head to Tube Sheet 3-53A-61-43C E07.001.002 Pipe to Pipe 3-53A-18-08 B09.011.202 Elbow to Pipe 3-53A-18-06 B09.011.201 Elbow to Pipe 3-SGA-WG8-4 C01.010.004 Shell to Shell
Review of Completed Data -
Continuation 3-SGA-WG8-1 C01.010.001 Shell to Shell 3-SGA-WG8-2 C01.010.002 Shell to Nozzle Belt 3-SGA-WG50-1 B03.130.00 Outlet Nozzle Y-Z Axis 3-SGA-WG25 B03.130.005 3A Inlet Nozzle Pc.70 to Pc 08 3SGB-WG25 B03.130.006 3B Inlet Nozzle Pc 70 to PC 08 3-PIB1-7 B05.050.005 B1 Suction,Pump S/E to Pipe 3-PDBl-2 B05.050.006 B1 Discharge, S/E to Elbow 3-PIB2-7 B05.050.007 B2 Suction,Pump S/E to Pipe 3-PDB2-2 B05.050.008 B2 Discharge, S/E to Elbow 3-PSP-1 B05.050.012 Pressure Spray T/E to S/E 3-PIB2-1 B09.011.043 Terminal End to SG Nozzle 3-53A-16-05 B09.011.160 Core Flood Sy A-17-02 B09.011.161 Core Flood Sy A-17-04 B09.011.162 Core Flood Sy a-17-12 B09.011.164 Core Flood Sy Within the areas examined, no violation or deviation was identifie )
10 Review of Radiographic Film Packages For Anderson Greenwood Relief Valve Welds and Plant Modifications (57090)
The inspector examined the radiographic film and records for the welds listed below to determine whether they were prepared, evaluated, disposition, and maintained in accordance with the licensee's approved procedure NDE-10, Rev. 1 The radiographic examination of the Anderson Greenwood Valve welds is due to the vendor missing this examination during the fabrication process in 199 The valves were subsequently installed in plant systems. The licensee issued Problem Investigation Report No. 0-090-0342 to investigate and correct the cause of this program failur Anderson Greenwood Valve Radiographs Examined Component ID N Weld SIZE N06-1516.002(N26908)
Inlet 1.0"Dia.x.250" N06-1516.002(N26908)
Outlet 1.0"Dia.x.250" NO6-1051.005(N26026)
Inlet
.750"Dia.x.250" N06-1051.005(N26026)
Outlet
.750"Dia.x.250" NO6-1516.002(N26906)
Inlet
.750"Dia.x.218" N06-1516.002(N26906)
Outlet 1.0"Dia.x.250" N06-1051.005(N26027)
Inlet
.750"Dia.x.230" NO6-1051.005(N26027)
Outlet 1.0"Dia.x.250" N06-1051.006(N26030)
Inlet 1.0"Dia.x.230" MO6-1051.006(N26030)
Outlet 1.0"Dia.x.250" NO6-1051.006(N26028)
Inlet
.750"Dia.x.250" NO6-1051.006(N26028)
Outlet 1.0"Dia.x.250" N06-1051.007(N26035)
Inlet
.750"Dia.x.250" NO6-1051.007(N26035)
Outlet
.750"Dia.x.250" 0I
Plant Modification Weld Radiographs Weld ID N Size 3-54B-8-43 8" Diameter x.250" Thickness 3-54B-6-40 8" Diameter x.250" Thickness 3-03A-15-31 6" Diameter x.432" Thickness During the review of the above accepted radiographs the inspector discovered that the radiographs for the Inlet weld on relief valve N06-1051.007 (N26035) failed to exhibit the required sensitivity in that the image of the penetrameter was burnt-out due to its placement on the taper of the valve.. DPC's Radiographic Procedure NDE-10, Rev. 18, paragraph 13.0 (a) requires.that, the radiography shall be performed with a technique of sufficient sensitivity to display the pentrameter image and the specified hole. Although the penetrameter image was not distinguishable, the required 4T hole was very distinguishable. The licensee subsequently discovered that several techniques had been tried during the initial radiography of this weld and that acceptable radiographs were available for review without re-radiographing the wel The apparent cause of this discrepancy was that the 4T hole was so apparent that the radiographic examiner had focused his attention on this parameter and had missed the fact that the technique was not demonstrating the 2% sensitivity of the pentrameter imag Based on the radiographic quality of the film for the other relief valve welds this appeared to be an isolated examiner error and was reported as NCV50-287/92-21-01. "This NRC identified violation is not being cited because the criteria specified in Section VII.B of the NRC Enforcement Policy were satisfied".
Within the areas examined, no violations or deviations were identified, with the exception of the non-cited violation identified abov.
Followup on Previous Inspection Findings (92701)
(Closed) Unresolved Item 50-269,270,287/92-19-01, "Failure of Vendor to Document Geometrical Reflectors"
Further review of Code requirements invoked during the time of the vendor's examinations revealed thatthere were no specific requirements delineated in the Code at that time to record geometrical reflectors. This item is considered close In the areas inspected, no violations or deviations were identifie.
Exit Interview The inspection scope and results listed below were summarized on August 28, 1992, with those persons indicated in paragraph 1. The inspectors described the areas inspected. Proprietary information is not contained in this report. Dissenting comments were not received from the license NOV 50-287/92-21-01, "Failure of Radiographic Technique to Discern Penetrameter Image", para. 3 (Closed) 50-269,270,287/92-19-01,"Failure of Vendor to Document Geometrical Refectors", par.
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American Society of Mechanical Engineers B&PV
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Boiler and Pressure Vessel B&W
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Babcock and Wilcox DPC
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Duke Power Company EC
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Eddy Current EPRI
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Electric Power Research Institute ID
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Identification ISI
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Inservice Inspection MT
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Magnetic Particle NDE
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Nondestructive Examination N Number NRC
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Nuclear Regulatory Commission NSR
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Non Safety-Related OTSG
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Once Through Steam Generator PT
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Quality Assurance RT
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Radiographic Examination Rev
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Revision SE
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Safe End S/G
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Terminal End UT
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Ultrasonic 0I