ML20034G523
| ML20034G523 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/04/1993 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20034G521 | List: |
| References | |
| NUDOCS 9303100018 | |
| Download: ML20034G523 (7) | |
Text
l INSERVICE INSPECTION REPORT UNIT 1 CATAWBA 1991 REFUELING OUTAGE 5 Location:
4800 Concord Road, York, SC 29745 NATIONAL BOARD NO. 130 COMMERCIAL SERVICE DATE: JUNE 29, 1985 Owner: Duke Power Company 422 S. Church Street Charlotte, NC 28201 Revision 1 O
Date
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Prepared By:
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Reviewed By:
A Date I"$-hb Approved By:
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Date 7
' D Copy No.
Assigned To NRC Docuent Control CJ Controlled X
Uncontrolled 9303100018 930305 EQA373 PDR ADOCK 05000413 G
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TABLE OF CONTENTS i
i Section Title Revision i
1.
Summary of Inservice Inspection 0
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2.
Status of Required Inspections 0
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3.
Final Inservice Inspection plan for Outage 5 0'
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Results of Inspections Performed During Outage 5 0
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Class 1 Inspection Results 1
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Class 2 Inspection Results 1
7.
Augmented Inspection Results 0
8.
Personnel, Equipment, and Material Certifications 1
9.
problem Investigation Reports 0
10.
Reference Documents 0
11.
Class 1 and 2 Repairs and Replacements 1
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50 Class 1_ Inspection Results O
i Examinations were performed during Outage 5 on the Reactor Vessel, Pressurizer, Steam Generators IA, 18, JC and 1D, Piping Welds of Reactor Coolant, Residual Heat Removal, Safety Injection, and Chemical and Volume Control Systems, Valve Bolting, Valves' and Supports 5.1 Reactor Vessel Seventy-eight (78) CRDM Tube to Upper Head Welds and fif ty-eight (58)
Incore Instrument Tubes to Lower Head Welds received a visual examination.
No reportable conditions were found.
5.2 Pressurizer The Pressurizer Surge Nozzle to Lower Head Weld and Inside Radius Section received an ultrasonic examination.
No reportable indications were found.
Seventy-eight (78) Heater Penetrations to Lower llead Welds received a visual examination.
No reportable conditions were found.
The Pressurizer Surge Nozzle Safe-End Weld received an ultrasonic and a dye penetrant examination.
No reportable indication were foimd.
5.3 Valves Bolting for Valves INI-54A, 1NI-59, 1NI60, 1NI-65B, 1NI-70, 1NI-71, 1NI-76A and 1NI-81 received a visual examination.
The internal surface of Valve INC-1 received a visual examination.
No reportable conditions were found.
5.4 P_i pi n_q Similar Metal Butt Welds:
Eleven (11) circumferential welds nominal pipe size four inches and greater received ultrasonic and dye penetrant examination.
Three (3) circumferential welds and ten (10) socket welds received a dye penetrant examination.
No reportable indications were found.
5.5 Steam Generator Tubing (See Catawba 1 Refueling Outage 5 Eddy Current Examination Report.)
5.6 System Leakage Test The Class 1 Pressure Boundary was subjected to a system leakage test as required by ASME Section XI, Article IWB-5000.
No reportable conditions were found.
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i 5.7 dlass1RepairsandReplacements Repairs and replacements for work' performed from April 22, 1990 to June 9, 1991 are itemized in Section 11 of this report.
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j blass2InspectionResults l
- 6. 0 Inspections were performed during Outage 5 on Piping Welds of Residual Heat Removal (ND), Safety Injection (NI), Main Steam (SM), and Main l
. Steam Vent to Atmosphere (SV) Systems and Supports.
i 6.1 P_iping Welds one-half inch and less nominal wall thickness.
i Thirty-three (33) circumferential welds and twelve (12) longitudinal welds received a dye penetrant examination.
No reportable indications I
were found.
Welds greater than one-half inch nominal wall thickness:
Nine (9) circumferential welds received an ultrasonic and a magnetic particle examination. Two (2) circumferential welds received an ultrasonic and a dye penetrant examination.
One (1) circumferential weld received a radiographic and a magnetic particle examination.
One (1) circumferential weld received a radiographic examination.
No reportable indications were found.
l 6.2 Component Supports Fifty-five (55) Class 2 Component Supports received a visual examination O
as required by ASME Section XI, Article IWF-2000.
No reportable conditions were found.
6.3 System or Component Functional Test Cir.ss 2 Functional Tests were performed as required by ASME Section XI, Article IWC-5000 No reportable conditions were found.
6.4 Class 2_ Repairs an_d Replac_e_ments Repairs and replacements for work performed from April 22, 1990 to June 9, 1991 are itemized in Section 11 of this report.
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l personnel._Equ_ipment, and Material Certifications 8.0 i
All personnel who performed or evaluated results of inservice inspections from April 21, 1990 to June 9, 1991 at Catawba 1 were certified in accordance with the requirements of the 1980 ASME Section XI with Addenda through Winter 1981. The appropriate certification records for each Duke Power Company inspector and periodic calibration records for Duke Power Company inspection equipment are.on file at Catawba Nuclear Station or in the Corporate offices in Charlotte, North Carolina.
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11.0 Class 1 and 2 Repairs and Replacements 9
As required by ASME Section XI, 1980 Edition, a record of the Class 1 and 2 Repairs and Replacements for work performed from April 22, 1990 to June 9,1991 is provided and is included in this section of the report.
The individual work request documents are on file at the Catawba Nuclear Station.
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