ML20062G722
| ML20062G722 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/12/1990 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20062G720 | List: |
| References | |
| NUDOCS 9011300162 | |
| Download: ML20062G722 (146) | |
Text
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- V 145 Paces FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules i , o,,,, Duke Power Company, 422 S.~ Church St., Charlotte, NC 28201 (Name and Addres of Owner)
- 2. Plant CJtawba Nuclear Station. Hiahway 274. Newoort. SC 29710 (Name and Address of Plant)
- 3. Plant Unit 2 4. Owner Ceruficaer of Authonaation (if requwed) N/A
- 3. Cocunercial Service Date 8/19/8b 6, National Board Number for Unit l73
- 7. Componene inspected Manufacturer Component of Manufacturer or lastaller . State or Nanonal Appurtensace of installer Senal No. Province No. Board No.
SEE SECTION 1 PARAGRAPH 1.5 IN THE ATTACHED REPORT 1
Notei Supplemental sheets in form of lists, sketches, of drawings may be used provided (1) size b 8% in x 11 in., ;
(2) information in items I through 6 on this data report u included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
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3 9011300162 901120 hDR ADOCK 05000414 PDC l
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INSERVICE INSPECTION REPORT UNIT 2 CATAWBA 1990 REFUELING OUTAGE 3 Location: Hyw. 274, Newport, South Carolina 29710 NATIONAL BOARD NO. 173-00tNERCIAL SERVICE DATE: AUGUST 19, 1986 Owner: Duke Power Company 422 S. Church St.
Charlotte, NC 28201 Revision 0
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d Prepared By: .
M ** Date // -N ' fd Reviewed By: n D -Date // 'l 17 d Approved'By: G Date /[- /2-98 Copy.No.- 5 >
Assigned To NRC -Document- Control.
Controlled X Uncontrolled l,Q
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-t CONTROLLED DISTRIBUTION
~ < Copy No. Assigned To.
- Original- C. B. Cheezem El=
J. E. Cherry 2 J. O. Barbour (Catawba)
W. D. Minton-(BWNS-Lynchburg)
R. G. Morgan (To Licensing File) u .4
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V. TABLE OF CONTENTS Section Title Revision
- 1. Summary of Inservice Inspection 0
- 2. Status of Required Inspections 0
- 3. Final inservice Inspection Plan for Outage 3 0
- 4. Results of Inspections Performed During Outage 3 0
- 5. Class 1 Inspection Results 0
- 6. Class 2 Inspection Results 0
- 7. Augmented Inspection Results 0
- 8. Personnel, Equipment, and Material Certifications 0
- 9. Problem Investigation Reports 0
- 10. Reference Documents 0
,~ 11. Class 1 and 2 Repairs and Replacements 0
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l' (f 1.0 Summary of Inservice Inspection This report describes the Inservice Inspection of Duke Power Company's Catawba Nuclear Station Unit 2 during the 1990 Refueling Outage (also referred to as Outage 3).
Included in the report are the final Inservice Inspection Plan, the inspection results for each item, a summary for each category'of exami-nations, and corrective action taken when unacceptable conditions were found. In addition, there is a section included for repairs and replace-ments required since June 4, 1989. '
- 1. E Class l' Inspection The Class 1 Inservice Inspections included examinations on the Reactor Vessel Interior Surface, Steam Generator 2B Channel Head to Tubesheet Weld, Steam Generator 2B Primary Inlet and Outlet Nozzle Radiused Sec-tions and Inlet and Outlet Nozzle to Safe End Butt welds. In addition, the Dissimilar Metal Butt Welds in Reactor Coolant (NC) System were examined. Reactor coolant Pump 28 Main Flange Bolts and Seal Gland and Seal Housing Bolting and Class 1 Valve Bolting and Internal Surfaces received examinations. Circumferential butt welds in piping of Reactor-Coolant (NC), Residual Heat Removal (NO), Safety Injection (NI) and Chemical and Volume Control (NV) Systems were examined. Socket welds in '
the Chemical and Volume Control (NV) System also received examinations.
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Visual examinations were performed on the Class 1 Pressure Boundary during System Leakage Tests. Also, visual examinations were performed on Class 1 Component Supports of Reactor Coolant (NC), Safety Injection (NI), and Chemical and Volume Control-(NV) Systems.
The Inconel 600 tubing in Steam Generators 2A, 2B, 2C and 2D was inspected by eddy current during outage 3. The results are shown in the Catawba 2 Refueling Outage 3 Eddy Current Examination Report, s
' Reportable indications were found on the Class 1 Inspection shown in this section. Inspection and evaluation' data for each reportable indication found-on Class 1 Inspections is included in Section 5 of this- -
report. Inspection and evaluation data for each reportable incication found during Class 1. Eddy Current Inspection is found in the Catawba 2 Refueling Outage 3 Eddy Current Examination Report.
A detail description of each inspection is found in the final Inservice Inspect' ion Plan in Section 3 of this report. Results of each examination are found in Section 4.
1.2 Class 2 Inspection The Class 2 Inspections included examinecions on the Safety Injeccior.
Accumulator Tank 28 Shell to Lower Head Weld, Outlet Nozzle to Lover
/7 Head Weld and on vessel integrally-welJed attachment on Support Siirt to V' Lower Head. Also, examinations were performed on piping integraliy-Page 1 Revision 0 EQA298 November 2, 1990
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welded attachments of the Safety Injection (NI) and Main Steam (SM) '
Systems. In addition, examinations were performed on circumferential butt welds in the Auxiliary Feedwater (CA), Residual Heat Removal (ND),
Feedwater-(CF), Safety Injection (NI), and Main Steam (SM) Systems.
Examinations were performed on longitudinal butt welds in Residual Heat Removal (ND) System and on 2CF60 Valve Body Weld.
Visual examinations were performed on the Class 2 Component Supports of Auxiliary Feedwater (CA), Residual Heat Removal (ND), Safety injection (NI), and Main Steani (SM) Systems.
Reportable indications were found on the Class 2 Inspections shown in this section. Inspection and evaluation data for each reportable indi-cation found on Class 2 Inspections is_ included in Section 6 of this report.
A detailed description of each inspection is found in the Final Inservice Inspection Plan in Section 3 of this report. Results of each examination are found in Section 4.
1.3 Augmented Inspection Augmented inspections consisted of Reactor Coolant Pump Flywheel exami-nations, Steam Generator Tubing examinations and examinations on the Main-Steam System for Pipe Rupture Protection. .
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- Reportable indications were found on the Augmented Inspections shown in
-this section. Inspection and-evalua. ion data for each reportable indi-cation found on Augmented Inspection is included in Section 7 of this report.
A. detailed description of each examination is found in the Final Inservice _ Inspection Plan in Section 3 of this report. Results of each examination are found in Section 4.
1.4. Alternate Examination No alternate examinations were performed during Outage 3. ,
-1.5 Identification Numbers i'
Owner: Duke Power Company, 422 S. Church St., Charlotte, NC 28201 Plant: Catawba Nuclear Station, Highway 274, Newport, SC 29710 Plant Unit: 2 Owner Ccrtificate of Authorization: N/A Commercial Service Date: 8/19/86 Page 2 Revision 0 4 November 2, 1990 EQA298
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L v -. Manufacturer State.or National Manufacturer or Installer Province Board Item or Installer Serial No. No. No.
Reactor Vessel CE 8871 N/A 21667 Pressurizer- Westinghouse 1931 N/A W26949 Steam Generator 2A Westinghouse 1923 N/A 4 Steam Generator 2B Westinghouse 1922 N/A 3 Steam Generator 2C Westinghouse 1921 N/A 2 Steam Gcnerator 2D Westinghouse 1924 N/A 5 Reactor Coolant System Duke Power Co. C-2NC N/A 171 Residual Heat Removal System Duke Power Co. C-2ND N/A 154 Safety Injection System Duke Power Co. C-2NI N/A 172 Chemical: And Volume Control System Duke Power Co. C-2NV N/A 170 Auxiliary Feedwater System Duke Power Co. C-2CA N/A 159 Feedwater System Duke Power Co. C-2CF N/A 158 Refueling Water System Duke Power Co. C-2KF N/A 151 Main Steam Supply to Auxiliary Equipment System Duke Power Co. C-2SA. N/A- 134 Main Steam System Duke Power Co. C-2SM N/A 162
,, Main Steam Vent to t Atmosphere System -Duke. Power Co. C-2SV N/A 156 (V - Safety Injection. Southwest Accumulator Tank 2A Fabrication &
Welding Co. 0023 N/'t 313 Safety Injection Southwest Accumulator Tank 2B Fabrication &
Welding Co. 0024 N/A -314 Safety: Injection Southwest Accumulator Tank 2C Fabrication &
Welding Co. 0030 N/A 320
-Safety' injection. Southwest Accumulator Tank 2D Fabrication &
Welding Co. 0031 N/A 321 Unit 2 Duke Power-Co. N/A N/A 173 1.6 The Reactor Vessel', Steam Generators, Pressurizer, Reactor Coolant System Piping, Reactor Coolant Pumps, and Safety Injection Accumulator Tanks were manufactured by or for Westinghouse Elect: Carporation, Pittsburgh, PA.under purchase agreements from Duke Power Company.
All other systems were fabricated and installed by Duke Power Company, 422 S. Church St., Charlotte, NC 28201.
Page 3 Revision 0 EQA298 November 2, 1990
' {] 1.7 Authorized Nuclear Inservice Inspector (s)
Name(s): R. N. McGill 1 /
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Employer: The Hartford Steam Boiler Inspection and Insurance Company Business Address: The Hartford Steam Boiler Inspection and Insurance Company 1117 Perimeter Center W., Suite E-301 Atlanta, GA 30338 i
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QUALITY ASSURAfCE DEPARTIENT 04TE 11/01/90 LANT: CATA>6A UNIT 2 PRE-SERVICE Afe IN-SERVICE INSPECTItSt SYSTEM EY ITEM tRJteER 816 CATAPSA 2 CLASS 1 REPORTABLE ITEMS - ERFTAGE 3 l
. INSP PROC.. MATERIAL OIAM./ CALIS IEM tt."eER ID. NU2ER DRAMING IGASERS LOCS. RE9. ft99ERS TYPE / GRADE TNICK BLOCK Ct90ENTS
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11.023.000 ********* STEAM GEDERAftNt TUBINGe**w *** **e**** meeem _._ ***** ******* Lf-TtBE DESIGN #####e*#
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16.020.001 2SGA-TUBES C1912201.01-102 ET 15I-424 IN 00.75 SELECT CALIBRATItps STAfeast0 00.044 PE3 VOLT #E 1 SECT 3tD810.2 15.623.002 2SGB-TUBES Ctet2201.01-102 ET ISI-424 IN 00.75 SELECT CaC**ATION STAfeAste 00.044 PER VOLUDE 1 xCTIt9010.2 ,
14.023.003 2SGC-TUBES Cta12201.01-102 ET 151-424 IN 00.75 SELECT CALIBIC ION STANDARD 00.044 PER VUltFE 1 set.896 10.2 16.C23.004 2SGO-TUBES Clet2201.01-102 'ET ISI-424 IM 00.75 SELECT CALIBRATION STA8eARO 00.044 PER VULt#tE 1 SECTItSt 10.2
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ROGRAM: NISIRUMS-GAISIO2 OtKE PtBIC CtDFANY PAGE 20 ILE: C007133 etMLITY atgeABCE DEPAltTENT ' SATE 16/26/96 LANT: CATASSA LMIT 2 PRE-SERVICE ADS IM-SERVICE INSPECTIt90 SYSTEM EY: ITEM NUPBER Col. CATUBA 2 CLASS 2 REPENtTABLE ITENS - StJTAGE 3 INSP PRCE. - MATERIAL DIAN./ CALIS TEM NUPSE2 ID. MJPSER DRANING IOSERS LtES. REG. IRJPBERS TYPE / GRADE THICK SLOCK Ct99EENTS
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ATT ACHMENTS********* [._ ** ::::::::::::::: r:::::r :::
D3.C23.064 2-R-SM-1555 CH-2691-SM-003 MT NDE-25 CS . MLD Nt#SER I 1.95.750 REF PIR 52-090-0Z%
T3.C33.000 ********** PUMP INTEGRALLY MELDEDe** *** ******* ***** . ***** "'"! """"P ATTACitENTS********* ~.1
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-LADR s CATAMBA (MIT 2 PRE-SERVICE Afe IN-SERVICE INSPECTItBI SYSTEM EY: ITEM PRDBER G02 CAT. 2 AUGIENTED INSP. REPENtTABLE ITEMS - tRffAGE 3 INSP PREE. MATERIAL 01498./ CALIS CtWWENTS TEM M99ED ID. NtDeER ORANING M. DEERS LOCS. RES. MAeERS TYPE / GRADE THICK SLOCK ==============================
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- 2.0 Status of Required Inspections The completion status of inspections required by the 1980 ASME Section XI Code, including Addenda through Winter 1981, is summarized in this section. The requirements are listed by the ASME Section XI examination category as defined in Table IWB-2500-1 for Class 1 Inspections and in IWC-2500-1 for Class 2 Inspections. Augmented inspections are also included.
Class 1 Inspections s
Section XI Inspections Inspections Percentage Deferral Category' Description Required Completed Completed Allowed Pressure Retaining-B-A 24 Welds 6 Welds 25% Yes Welds in Reactor Vessel B-B- Pressure Retaining 8 Welds 3 Welds 37.50% No Welds in Vessels Other than Reactor Vessels
. B-D Full Penetration Welds 36 Inspections 12 Inspections 33.33% Partial of Nozzles in Vessels B-E Pressure Retaining 55 Welds 55 Welds 67% Credited No Partial Penetration ;
_ Welds in Vessels B-F- Pressure Retaining 46 Welds 18 Wolds 39.13% No Dissimilar. Metal i Welds B-G-1 Pressure Retaining 466 Items 171 Items 36.69% Yes Bolting Greater Than 2 Inch =in Diameter B-G-2 Pressure Retaining *68 Connections 28 Connections 41.17% No Bolting 2 Inches and i
'Less in Diameter B-H Integral Attachments- 9 Attachments 3 Attachments- 33.33% No For Vessels
- Total Connections include CRDMs that are disassembled.
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- EQA298 November 2, 1990 i
l' v Class 1 Inspections (Continued)
Section XI Inspections Inspections Percentacc Deferral Category Description Required Completed Completed Allowed B-J Pressure Retaining 203 Welds 89 Welds 43.84% No Welds in Piping B-K-1 Integral Attachments for None N/A N/A N/A Piping, Pumps, & Valves B-L-1 Pressure Retaining Welds None N/A N/A N/A in Pump Casings B-L-2 Pump Casings None N/A N/A N/A B-M-1 Pressure Retaining Welds 2 Welds None 0% Yes in Valve Bodies B-M-2 Valve Body > 4 In. 7 Valves 4 Valves 57.14% Yes Nominal Pipe Size B-N-1 Interior of Reactor 3 Items 2 Items 66.66% No Vessel lh I
B-N-2 Integrally Welded Core None N/A N/A N/A Support Structures and Interior Attachments to Reactor Vessels
'B-N-3 Removable Core 1 Item None 0% Yes Support Structures B-0 Pressure Retaining 3 Housings 1 Housing 33.33%- Yes Welds in Control Rod Housings B-P All Pressure No-Retaining Components System Leakage Test 160 Components 60 Components 37.50%
System Hydrostatic 20 Components 0 Components 0%
Test B-Q -Steam Generator Tubing 100% of Technical Specifications met N/A F1.01 Class 1 Component 218 Supports 78 Supports 35.77% No Supports t rx l' O s
Page 2 Revision 0 EQA298 November 2, 1990 1
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) Class 2 InspectionsSection XI Inspections Inspections Percentage Deferral
-Category Description Required Completed Completed Allowed C-A Pressure Retaining 9 Welds 4 Welds 44.44% No Welds In Pressure Vessels e C-B Pressure Retaining 6 Welds 3 Welds 50% No Nozzle Welds in Vessels C-C Integral Attachments 50 Attachments 2C attachments 56% No for Vessels, Piping, Pumps and Valves C-D Pressure Retaining None N/A N/A N/A Bolting Exceeding 2 Inches in Diameter C-F Pressure Retaining 347 Welds 117 Welds 33.71% No Welds in Piping l O C-G Pressure Retaining 25 Welds 8 Welds 32% No V Welds in Pumps and Valves C-H All Pressure Retaining No Components System or Component 68 Components 34 Components 50%
Functional Test System Hydrostatic 92 Components 0 Components 0%
Test F1.02 Class 2 Component 492 Supports 191 Supports 38.82% No Supports A.
V Page 3 Revision 0 EQA298 November 2, 1990
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Augmented Inspections Description -
Percentage Complete ;
Reactor Coolant Pump Flywheels 100% of Technical Specifications met Steam Generator Tubes on 100% of requirements for Outages 1, 2, & 3 Preheater Section Main Steam Pipe Rupture Protection 100% of requirements for Outages 1, 2, & 3 Class 2 Piping Systems 100% of requirements for Outages 1, 2, & 3 Thermal Stress Piping 100% of requirements for Outages 2 & 3
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l 3.0 Final inservice Inspection Plan for Outage 3 The final ISI Plan presented in this section lists all examinations f"/
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credited for Outage 3 at Catawba Unit 2. This includes ASME Section XI Class 1, 2 and augmented. Inspections required by the plant technical specifications.
The information shown below is a field description for the reporting format included in this section of the report:
Item Number = ASME Section XI Tables IWB-2500-1 (Class 1),
IWC-2500-1 (Class 2), IWD-2500-1 (Class 3),
IWF-2500-1 (Class-1, Class-2, & Class-3), and Augmented Requirements ID Number = Unique Identification Number Drawing Number = Location and/or Detail Drawing Locs. = Location Insp. Req.- = Examination Technique - Magnetic Particle, Dye Penetrant, etc.
Proc. Numbers = Examination Procedures j Material Type / Grade = General Description cf Material h Diam./ Thick = Diameter / Thickness Calib Block. = Calibration Block Comments = General and/or Detail Description i
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PAGE' 1 PROGRAM. NISIRt.98-GAISIO2 DUKE Pt94E't CO W AfW OtTE 1C/26/90 FILE COO 7133 ' 9tMLITY ASStNEAfEE DEPARTMNT
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'INSP PROC. MATERIAL DIAM./ CALIS ITEM IO BER 10. MASER 'DRANING ISABERS LOCS. REQ. NUPSERS ' TYPE / GRADE THICK BLOCK Ct9mENTS
====== ==================== ==================== ===== ==== ======== ========== ====== ===== ========================
6 CO2.000.000 *** PRESSURIZER Ate STEAM GEfERATOR *** ******* ***** ***** * - -----e****e***ew ee VESSEL NELDS******** [1 **we== m e w**** m ew ***, m e 5
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ITEM 9499ER 10 MD9ER OATE -STATUS LIMITED REF. Ctp0EteTS
====== ==================== ========== ==========- -==========- ==== ===================--==
C05.021.237 298188-03 07/03/90 CLR L Y C05.021.237A 2NI88-03 '06/26/90 CLR _- M l C05.021.238 2NI88-05 07/03/90 CLR L Y C05.021.238A 2NI88-05 06/26/90 CLR ,, N C05.021.239 2MI88-24 07/03/90 CLR L M C05.021.2394 ZNI88-24 06/26/90 CLR _
h C05.021.244 2NI90-04 07/03/90 CLR _
N C05.021.244A 2NI90-04 06/26/90 CLR _
N C05.021.245 2NI90-06 07/03/90 CLR L M _
-i COS.021.2454 2NI90-06 06/26/90 CLR _
N C05.021.246 2NI90-21 07/03/90 CLR L M C05.021.246A 2NI90-21= 06/26/90 CLR _
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GLRLITY ASSLRNEE DEPARN DATE 10/26/90
' PLANT CATADSA LMIT 2 - ' PRE-SERVICE AMD IM-SERVICE INSPECTItRt SYSTEM
_ REY: ' ITEM NINSER - C05 ' CATADSA 2 IN5ERVICE 'INSPECTItBE RESULTS f elffAGE 3 l IN5PECTItti . ' IM5PECTItSt IM5PECTItDe GEtr.
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C05.021.406A 2SM13-01 07/02/90 - CLK - _
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N C05.021.412 2SM-88-C. ' 08/07/90 CLR L M C05.021.412A 2SM-88-C 07/26/90 CLR _
M C05.021.415 '2SM-88-E 08/07/90 CLR L M C05.021.413A 2SM-88-E 08/01/90 CLR _
N-C05.021.414 2SM-88-F 08/07/90 CLR L M C05.021.414A -2SM-88-F 08/01/90 CLR _
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. . SJALITY meeCE BEPARTIENT DATE 1~,/2*,/90 ;
PLFT CATApeA tsf!T 2 ' PRE-SERVICE AND IM-SERVICE INSPECTItpl SYSTEM i stEY: ITEM fAASER F1. CATApSA 2 INSERVICE INSPECTIt98 RESULTS - StRAGE 3.
'INSPECTItSt INSPECTItSt INSPECTItDI .GES.
11fMPR9eER 10 Nt9eER . DATE STATUS LIfMTED REF. CtpWENTS
====== ==================== ========== ========== ===.-===== ====- ========================
F1.01.009 2-R-NC-1662L 06/14/90.- .CLR _
'N F1.01.145 2-R-NC-1068 06/14/90 CLR _
N F1.01.146 2-R-NC-1067 .06/14/?9 CLR _
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' F1.01.147 . ~ 2-R-NC-1065 06/14/90 CLR _
N F1.07 476 2-R-NI-1757 06/14/90 CLR .- _
N 8
F1.01.477 2-R-MI-1758 06/14/90 CLR _
N F1.01.478 2-R-MI-1764 06/14/90 CLR _
M F1.01.479 2-R-MI-1765' 06/14/90 CLR _
N F1.01.480 2-R-MI-1766 06/14/90 -CLR ,
N-F1.01.616 2-R-NV-1450 06/14/90. CLR _
N F1.01.617 ~2-R-HV-1451 '06/14/90 CLR _
N F1.01.647 2-R-HV-1160 06/14/90 CLR' _
N I
F1.01.648 2-R-HV-1161' 06/14/90 CLR _
N F1.01.649 2-R-NV-1162 06/14/96 CLR _
M F1.01.650 2-R-HV-1163 06/14/90 CLR _
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'PRtRIRAPts MISIRL95-4AISIO6 OlstE PEBER CN PAGE ~ 25 FILti: CSD7153 EIALITy. ausmangt OEPARTPENT
- OATE 10/2$/90-PLANT: CATApSA 13 TIT 2 PRE-SERVICE Ape IM-SERVICE INSPECTItWe SYSTEM KEY: ITEN PR99ER F1. CATApSA 2 INSERVICE INSPECTIt90 RESULTS - StJTAGE 3 INSPECTISt INSPECTIt90- INSPECTItNf 'GES.
ITEN PRDeER' 10 Nt991ER CATE STATUS LIMITED REF. ' CtWOENTS
====== ==================== =====y==== ========== ========== ==== ========================
l
.F1.01.651 '2-R-NV-1164 06/14/90 CLR- _
N
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F1.01.652 2-R-fW-1169 06/14/90 CLR' _
M F1.01.653 2-R-NV-1770 07/30/90 CLR _
N F1.02.009 2-R-CA-1609 06/12/90 CLR _
N F1.02.010 2-R-CA-1610 06/12/*O CLR _
N F1.02.011 2-R-CA-1611 06/12/90 CLR _
N i
F1.02.012 2-R-CA-1612 - 06/12/90 CLR _
N
-F1.02.022 2-R-CA-1571 06/12/90 CLR _
N F1.02.023 2-R-CA-1573 - 06/12/90 CBR _
M F1.02.024 2-R-CA-1574 06/12/90 CLR _
N F1.02.025 2-R-CA-1575 06/12/90 CLR _
N F1.02.026 2-R-CA-1577 06/12/90 CLR _
N F1.02.027 2-R-CA-1578 06/12/90 CLR _
N F1.02.028 2-R-CA-1579 06/12/90 CLR _
N F1.02.029 2-R-CA-1581 06/12/90 CLR _
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PROGRAM: MISISLSe-gAIS104 OIstE PE9ER Ct9FANF - PAGE 26-FILE: C007133 . WALITY meeCE SEPARTVENT OATE 10/26/90 :
~ PLANT:' CATApSA LptIT 2 . PRE-SERVICE se 194-SERVICE INSPECTIt90 SYSTEM
. KEY: ITEM PRASER F1. . CATApSA 2 INSERVICE INSPECTIEpt RESULTS - tRffAGE 3
^ INSPECTItSt INSPECTItps INSPECTION GES.
STATUS LIMITE0 'WEF. Ct90ENTS -
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=== 33 ====ss=======s=m=ws= ========== ensusszzw . sensmes=== sess s====n==================
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INSPECTItD4 .INSPECTItDI . .1MSPECTitM SES. .
~ ITEN NL99ER .IDPRDSER- . . DaTE STATtR LIMIT REF. Ct,99ENTS
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N F1.02.360- 2-R-te-0050 05/15/90 CLR _ :N F1.02.361' 2-R-NO-0051 05/15/90 CLR _
N F1.02.362 2-R-te-0249 05/10/90 CLR _
N F1.02.363 2-R-ND-0250 05/10/90 CLR _
N F1.02.567 2-R-MI-1670 06/14/90 CLR _
N F1.02.568 2-R-MI-1671 06/14/90 CLR _
M F1.02.569 2-R-MI-1672 06/14/90 CLR _
N F1.02.570 2-R-MI-1673 06/14/90 ~CLR _
N F1.02.571 2-R-MI-16S7- 06/14/90 CLR _
N i
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M F1.02.573 2-R-MI-1684 06/14/90 CLR _
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OATE 10/2u90 PLANT: CATA9eA 1981T 2 PRE-SEllVICE Afe IN-SERVICE INSPECTit94 SYSTEM .
KEY ITEM Nt#SER F1. CATAfeA 2 INSERVICE INSPECTIf9I REStJt.TS - SUTAGE 5 .
. INSPECTItpf INSPECTItN4 INSPECTItSt- GES.
- ITEM MD9ER - IDIRASER . 0 ATE ' STATUS LIMITED REF. Ct90ENTS
====== ==================== esswww.ss. ========== :s===s=== ==== ========================
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F1.02.824 2-R-SM-1577 06/12/90 CLR _
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F1.02.826 2-R-SM-1579 06/12/90 CLR _
N F1.02.827 2-R-SH-1580 06/12/90 CLR _
N i
F1.02.328 2-R-SM-1581 06/12/90 CLR _
N F1.02.829 2-R-SM-1582 06/12/90 CLR- _
N F1.02.830 2-R-SM-1583 06/12/90 CLR _
N F1.02.831 2-R-SM-1584 06/12/90 CLR _
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N l F1.02.833 2-R-SM-1566 06/12/90 CLR _
N F1.02.834 .2-R-SM-1587 06/12/90 CLR _
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N F1.03.043 2-R-CA-0027 05/10/90 CLR ._ N F1.03.044 2-R-CA-0029 05/10/90 -CLR _
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FILE: C00F133 ..WALITY ASSIAtABCE OEPARTIENT DATE 1 724/90 PLANT . CATApeA tMIT 2 PRE-SERV 1CE ADR3 IN-SERVICE IN5PECTItDI SYSTEN '
KEY: ITEN fRJPSER F1. CATASSA 2 INSERVICE INSPECTItpt RESULTS - tRITAGE 3 INSPECTIt98 INSPECTitpl INSPECTItDS GES.
ITEN MRSER 20 M99ER . 'DATE . STATUS LINETEO REF. CfDOENTS
======- ====================.========== ========= r3======== ==== ========================
' F1.03.0% 2-R-CA-0032- .05/10/90- ~ CLR _
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N F1.03.283 2-R-KC-0019 05/10/90 CLR _
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M F1.03.285 2-R-KC-0038 05/10/90 CLR ._ N .
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N F1.03.287 2-R-KC-0053 05/10/90 CLR _
N F1.03.288 '2-R-KC-0381 05/10/90 CLR _
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PRE-SE9VICE Ape IM-SERVICE INSPECTIt94 SYSTEM PLANT: CATApeA INtIT 2 KEY: ITEM NUpeER F1.- CATAfeA 2 INSERVICE INSPECTION RESULTS - SUTAGE 5 INSPECTIODt INSPECTIEpt' INSPECTItBe ' GES.
STATUS LIMITED REF. Cip01ENTS ITEM MDBER 10sesSER .DATE ========== ==== ==============================
====== ==================== ========== ====
05/10/90 'CLR, M.
F1.03.307 2-R-KC-0268 _
05/10/90 CLR .M F1.C3.308 2-R-KC-0270 _
05/10/90 CLR M F1.03.309. 2-R-KC-0288 _
05/10/90 CLR N F1.03.310 2-R-4tC-0290 05/10/90 CLR M F1.03.311 2-R-KC-0368 _
08/11/90 CLR N F1.03.796 2-R-IIN-0182 _
08/11/90 CLR. M F1.03.797 2-R-fee-0183 _
08/11/90 .CLR M F1.03.798 Z-R-IEN-0184 __
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- F.EY:
ITEM PtfeER 601 . . CATASSA 2 INSERVICE INSPECTIERG RESULTS - (RITA9E 3 1
3NSPECTItDi '~ INSPECTItSt IM5PECTItSt GES.
ITEM 949eER LID 8tASER DATE STATUS LIMITED REF. CipWENTS
====== .==================== ========== ========== ne======== ==== ,========================
601.001.001 ~ 2RCP-2A 06/27/90 CLR L M i-G01.001.002 2RCP-28 06/27/90 CLR L 'N D
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PROGRAPf: N1SIMSG-gAISIO4 ' OUKE PtBER CE9eANY PAGE 33 t FILE: .C007133- WALITY meAfCE SEPARTVE9ff DATE 10/26/99 '
PLANT: PRE-SERVICE Afe IN-SERVICE INSPECTItBd SYSTEM KEY: ' CATafeA 1981T 2GO3 ITEM PGJUSER CATApeA 2 INSERVICE INSPECTIt90 RESUL(5 - SJTAGE 3 6 I
INSPECTIt96- INSPECTIt90 INSPECTItSt GES.
' ITEM 9RDBER ID9tpeER DATE STATUS LIMITE8 REF. Ct99ENTS i
====== ==================== ========== =s======== ========== ==== ========================
G03.001.0094 2SM38-15 07/26/90' CLR ,,
N 903.001.010 2SM-88-A 08/07/90 CLR L' Y G03.001.010A 2SM-88-A 08/01/90 .CLR _
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5.0 Class 1 Inspection Results Examinations were performed during Outage 3 on the Reactor Vessel, Steam Generators 2A,.2B, 2C and 2D, Piping Welds of Reactor Coolant (NC),
Residual Heat Removal (ND), Safety Injection (NI), and Chemical and Volume Control (NV) Systems, Pump Bolting, Valve Bolting, Valve Internal Surfaces and Supports.
5.1 Reactor Vessel The accessible internal surfaces of the Reactor Vessel were visually inspected. No reportable conditions were found.
5.2 Steam Generators Steam Generator 2B Channel Head to Tubesheet Weld received an ultrasonic examination. No reportable indications were found.
Steam Generator 2B Primary Inlet and Outlet Nozzles Radiused Section received an ultraronic examination. No reportable indications were found. ~
Steam Generator 2B Inlet and Outlet Nozzle Safe-End Welds received ultrasonic and dye penetrant examinations. No reportable indications
()
n were found.
5.3 Pumcs Reactor Coolant Pump 28 Main Flange Bolting received ultrasonic and visual: examinations- No reportable indications or condition were found.
~ Reactor Coolant Pump 2B Seal Gland and Seal Housing Bolts received a visual examination. No reportable conditions were found.
'5.4 .Pipina Dissimilar Metal Butt Welds- l Two (2) Reactor Coolant System (NC)-Safe-End to pipe welds four inches and greater received ultrasonic and dye penetrant examinations. No i reportable indications were found, i 1
Similar Metal Butt Welds:
Eleven (11) circumferential welds four inches and greater received i ultrasonic and dye penetrant-examinations. Two (2) circumferential welds less than four inches received a dye penetrant examination. Fourteen I (14) socket welds received a dye penetrant examination. No reportable indications were found. '
l Page 1 Revision 0 E0A298 , _
November 2, 1990
l.
.wl2 i
Piping Supports:
Eighteen-(18) Class 1 Component Supports received a visual examination as required by ASME Section XI, Article IWF-2000. No reportable conditions were found. -
5.5 Valves The internal surface of valves 2NI-82, 2NI-125 and 2NI-175 received a visual examination. No reportable conditions were found, f' 5.6 Steam Generator Tubing (See Catawba 2 Refueling Outage 3 Eddy Current Examination Report) 5.7 System t.eakage 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.
-5.8 Class 1 Repairs and Replacements 7-~3 Repairs and replacements for work performed from June 5, 1989 to Septem-(j ber 8, 1990 are itemized in Section 11 of this report.
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_EQA298 November 2n 1990
t t
u 6.0 Class 2 Inspection Results Inspections were performed during Outage 3 on Safety injection Accumula-tion Tank 2B, piping integrally-welded attachments, Piping Welds of Reactor Coolant (NC), Residual Heat Removal (ND), Safety Injection (NI) and Chemical and Volume Control (NV) Systems, Valve and Supports.
6.1- Safety Injection Accumulator Tanks Safety Injection Accumulator Tank 28 Shell to Lower Head Weld received an ultrasonic examination, and Outlet Nozzle Weld to lower Head received ultrasonic and magnetic particle examinations. No reportable indications were found.
Safety Injection Accumulator Tank 2B Support Skirt to Lower Head Inte-grally-Welded Attachment received a magnetic particle examination. No reportable indications were found.
6.2 piping Welds:one-half inch and less nominal vall thickness:
Nine (9) circumferential welds received a magnetic particle examination.
Twelve (12) circumferential welds and eight (8) longitudinal welds jg[ received a dye penetrant examination. No reportable indications were w found.
Welds greater than one-half inch nominal wall thickness:
Eight (8) circumferential welds received an ultrasonic and a magnetic particle examination. Twelve (12) circumferential welds received an ultrasonic and a dye penetrant examination. One'(1) circumferential weld received a radiographic and a magnetic particle examination. No report-able indications were found.
piping Integrally-Welded Attachments:
Eleven (11) integrally-welded attachments on Main Steam (SM) System received a magnetic particle examination and one (1) integrally-welded attachment on Safety injection (NI) System received a dye penetrant examination. A reportable indication was found on weld 2-R-SM-1555,
^(Item Number _C03.020.064). The weld indication was repaired and.re-ex-amined and found acceptable (refer to, Problem Investigation Report 2-C90-0246 included in Section 9 of this report). The inspection data sheets are included in this section of the report. The scope of the inspection was extended to include eleven (11) additional attachment welds,.per ASME Section XI, Paragraph IWF-2430(a). No other reportable indications were found, p- One (1) integrally-welded attachment on the Safety injection (NI) System-( received a dye penetrant examination. No reportable indications were found.
Page 1 Revision 0 EQA298-. November 2, 1990-
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O 6.3 Valves ,
Valve 2CF60 valve-to-bonnet weld received a magnetic particle examina-tion. No reportable indications were found.
6.4 Component Supports Fifty-three (53) Class 2 Component Supports received a visual examination as required by ASME Section XI, Article IWF-2000. No reportable condi-tions were found.
6.5 Class 2 Repairs and Replacements Repairs and replacements for work performed from June 5, 1989 to Septem-ber 8, 1990 are itemized in Section 11 of this report.
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Revision 0 1 EQA298 November 2, 1990 l
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DUKE POWER COMPANY PROJECT CATAWBA MAGDETIC PARTICLE /UQUC PEPETRANT EXAMMATION REPORT Weid Na 2-R-SM-1555 Unit Na 2 Date 8-28-90 Diameter N/A Senedule/TNcknees
.750 Type Material SS O CS E Work Order Na 3045 MES QA CondWon 1 Procedure NDE2SB-J / Rev 14 SKETCH OF ITEM EXAMINED NDE.96 Appmed M/A Radle.cn Lewel N/A Inspector Level lh/AA1)f II LO in - e.co in - e.on - Reference Documents Number Length / Width / Diameter, etc. Acceptable Repvrtable NONE _
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MT DATA PT DATA MT Method Used FT Batch Number O FluorsecentXINonfluorescent O Wet nDry Cleaner Penetrant Ale /
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f) sm-7.0 Augmented Inspection Results
. Augmented inspections were performed on the Reactor Coolant Pump Fly-wheels, Steam Generator Preheater Sections and on the Main Stream System for Pipe Rupture Protection.
7.1 Reactor Coolant pump Flywheels Reactor Coolant Pump 2A and 2B Flywheels received an ultrasonic examina-tion in place. No reportable indications were found.
7.2 Pipe Rupture Protection Ten (10) welds on the Main Steam System received an ultrasonic and a magnetic particle examination. No reportable indications r- e found.
7.3. Steam Generator preheater Section All four steam generators were examined by eddy current methods. Results and evaluation data for examinations are shown in the Catawba 2 Refueling Outage 3 Eddy Current Examination Reports.
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i O 8.0 Personnel. Equipment, and Material Certifications All personnel who performed or evaluated the results of inservice inspections from June 4, 1989 to September 8, 1990 at Catawba 2 were certified in accordance with the requirements of the 1980 ASME Section XI with Addenda through Winter 1981. The appropriate certification record for each Duke Power Company inspector is on file at Catawba Nuclear Station or in the Corporate Offices in Charlotte, North Carolina. The certification records for the Babcock and Wilcox inspectors are on file at the Babcock and Wilcox offices in Lynchburg, Virginia.
Records of periodic calibration of Babcock and Wilcox inspection equip-ment are on file at the Babcock and Wilcox offices in Lynchburg, Virginia.
Records of periodic calibration of Duke Power Company inspection equip-ment are on file at Catawba Nuclear Station or in the Corporate Offices in Charlotte, North Carolina, e
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EQA298 November 2, 1990
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-- 9.0 Problem Investication Reports l
l A copy of each Problem Investigation Report resulting from reportable I items, originated against scheduled inservice inspections performed -
during Outage 3, is included in this section.- All were resolved and found acceptable by Duke Power's Quality Assurance Department before returning Unit 2-to service. The following Problem Investigation Report- l was issued:
P.I.R. No. Description Date Issued 2-C90-0246 Class 2 Integrally-Welded 07-20-90 Attachment - SM System D
J Page 1 Revision 0 EQA298 November 2, 1990
I marim*es consptava ronas sY PRINTING WITH BLACM BALL POINT PEN OR TYPE 1
DUKE POWER COMPANY E NUCLEAR STA110N Repost M k 2-c90-o246
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OmarDuhoStatone A9ectedO Yes UNo O Unimown Osestr'anedBy/Date M h 'F- So- 10 Lneannn oiPIQbtem: Interior Dochousa.Elev.5R78 , cal. 60-61.EE-FF Method M 20 h Pl000ern. IET Tnmeaet4nn immagene Conecove Actions Tbhan/Tb 8e Thhan:
l Want $40C$lege ModRoanon (Perm QCM.2A) SeM Ngg N/A in$ormalan 6(WCrtt M Documente Vloiesed 9to-). AAME Eaetion X1. NDE25R-J 9Onphr ey M A 8*- Deat '# 8 '9 Dept./Goup/Seccan GA f/8 l
.. CompGence 5 Opereele O Yes O No INot g a mmart By/D ele: - ^ 7 ** -98 Comrnente- il M *~3 " 'A Reportable O Yes 5%o .
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Oate Due to Compeance efter twilustion
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i l-C) PROBLEM INVESTIGATION REPORT VI. Proposed Hoeolution of Probier.1 C ,MlN
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oou QA 0.te SCAE Required O Yes O No Determned By/Dete QA om SCAE Assigned To: Senal No.
Remarks Vit. OA Venfcation Requimments Assgned To om Vill Conectiw Action Cort pieted Approved om
) IX. OA Venfcation Results x_/
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Attschment to PIR 2-C90-0246 A
VI. Proposed Resolution of Problem:
The weld identified on this " ~. As shown on drawing 2-R-SM-1555 as being a 5/16 inch by 1 (one) inch fillet weld attaching a saddle plate to the ,
main steam piping. The main steam pipe is 34 inches in diameter and approximately 1-1/2 inches thick. The saddle plate is 3/4 of.an inch thick. Any thermal growth of the SM (main steam) pipe could initiate a crack in this size weld. There have been other failures on saddle welds of this design. These weld failures were in the same location. Design should evaluate the significance and structurai integrity of the weld identified by this PIR to preclude repetitive analysis.
bY YYAAdhl- . Date 64-$C O W o
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DUKE POWER COMPANY 10/11/90 PIR RES01MIION PAGE 1 0F 1 Problem Investigation Report Serial No. 2-C90-0246 The reference PIR identifies a fillet weld 5/16 inch by 1 l inch attaching a saddle plate to the main steam piping (2-R-SM-1555). The main steam pipe is 34 inches in diameter and approximately 1-1/2 inches thick. The saddle plate is 3/4 inches thick. Any thermal growth of the SM (main steam) pipe could initiate a crack in the saddle plate weld. There have been other failures on saddle welds of this design. ;
These weld failures were in the same location. Design l should evaluate the significance and structural integrity of the weld identified by this PIR to preclude repetitive analysis. .
O The Proposed Resolution To PIR 2-C90-0245 l I
l The saddle weld on support (2-R-SM-1555) is not a structural load bearing weld. It's primary function is to prevent misalignment, to hold the saddle in place. In this case, if both saddle welds were cracked to the point they could no longer carry any load the integrity of the support to perform it's intended function would still not be compromised. Therefore, the we k identified by this PIR has ,
no significant impact on the structural integrity of the !
, support.
This resolution does not attempt to classify or qualify all saddle welds as non-structural. Other saddle weld failure's 1 must be evaluated on a case by case basis.
By 'BA 4M '
__ . Date 10/11b8:=
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M O, ^us isties ror 203i DUKE POWER COMPANY DE m. m N Wi-PIR REYlEW OE0 VEST NTE- 8'7'T REF. PIR- 8 ~ #- f * # E V '
(COPY ATTACHED)
THROUGH PIR COORDINATOR, PR(UECT MAP AGEMENT OROUP T0. - I d (TO BE FILLED IN BY PMG)
DE$10NTNGINEERING DEPARTMENT 5
I DESION ENGINEERING l$ REQUIRED TO PROYlDE AS$1 STANCE AS SPECIFIED SELO FOR THE ATTACHED PIR.
REPLY NEEDED BY:
E OPERA 81LITY EVALUAil0N $UPPORT REPORTA61LITY EVALVATION SUPPORT '
I/ PROPOSED RESOLUTION p: ws )
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I'3848 (ITEM O ,
arso'ut'o" co"','o" vtac^o" -
(CORRECilVE ACil0N ITEM Ylll)-
$10NIFICANT CORRECilVE ACTION EVALUATION (SCAE)/
k CRITERl0N XVI ( 10CFR 50 APP.. B ] EVALVATION * .:--
(* REQUEST ONLY AFTER STATION QA APPROYAL OF RESOLUTION)
STAil0N CONTACT IS: %Al 8 & 41 # EXT. M/
DNC (PR-202) APPLICABLE YES Y NO FORM 202.1 NOT REQUIRED UTION ADEQUATELY ADDRESSES CORRECilVE ACTION) g g-DETERMINED 6Y:
'f %I XJ(tkCD DATE /B-//-90
- g (Dt310NAILD INDIVIDUAL)
DATE: lo!// !96
! THR PIR COORDINATOR, PMG TO: . $ *
. ATTN:
OROUP MANAGER OR PLANT MANGER /
THE REQUESTED INFORMATION l$ ENCLOSED FROM: PIR COORDINATOR, PMG
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, 10.0 Reference Documentt !
The following reference documents apply to the inservice inspection l performed during Outage 3 at Catawba 2:
None. !
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- . . . -' EQA298L
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11.0 Class 1 and 2 Repairs and Replacements As required by ASME Section XI, 1980 Edition, a record of the Class 1 and 2 Repairs and Replacements for work performed from June 5, 1989 to '
September 8, 1990 is provided and is included in this section of the report. The individual work request documents are on file at the Catawba Nuclear Station. I l
O Page 1 Revision 0 EQA298 November 2, 1990
i; n
CATAWBA NUCLEAR STATION UNIT 2 EOC 3 REPAIR / REPLACEMENT LOG ASME SECTION XI-1981
,Lo Examination Dates: From 06/05/89 To 09/08/90 QA Technical Support Prepared By:
Transhiitted By: N* J Date: /0 4 90 I
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ME5: 00193 [B- ' REPLtd.'E STRAP [ PORTION .. OF FIG ' aim MINI-STIFF CLAMP 2-R-BD-1010, .
R-BB-1041x AND 2-R-DB-1043
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-Bi - REPLACE:51 RAP: PORTION OF f-20 P W MINI-STIFF... CLAMP 2-R-KN-1708, g- -
22-R-KC-1901,y2-R-KC-1724 AND'2-R-KC-1728 c6ME5 00743 Ai -STEAMLGCNERA10R 2A,~28.-2C, 2D MANWAYJBOLTS WERE GOUND AND.MACIIINED
- MES OOG48e 2B! :
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- MES;01965 AJ DISASSEMBLED.VALUE'2NI125 - NO Pn'tT5 REPLACED 1
MCG'Otv46 A1 . DISASSEMBLED VALVE 2NI175 -- NO PARTS REPLACED
- NES-02201 'S- ' REPLACED ANCHORS ON SUPPORT 2-R-ND-OO47 NE5 02470' B RCPLSSTRP PORTION OFfMINI STIFF CLAMP 2-R-NU-264 ME5 02477 LDL : REPLACED STRAP ' PORTION ' OF ~ TIE MINI STIFF CLAMP DN
- 2-R-ND-474,-2-R-ND-498, 2-R-ND-410, 2-R-ND-415
.MES ~ 02470. :B- REPL'5TRPJORTION OF MINI, STIFF CLAMP 2-R-N."-1530 MES O2479 B" :REPL'STRP PORTION-OF MINI STIFF CLAMP 2-R-NI-1564 MES O2489. 8L REPLACED STRAP? PORTION HINI STIFF CLAMP-ON
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.MES:02G07 B REPLACED DONNET/ BODY CASKET AND VALVE DISC 5 ON 2NV338
.MC5~02YOO: B- C REPLACED PIPE CL(+lP 2-R-5A-0014
,MES O2939- =B REPLACED SNOBBCR t2-R-5M-1556)
[ MES O2739 -D. :2-R-SM-1S61-REPLACED WF DCAM & GU55ET-F' HE5 203039 B l CUT DUrfVALVE 2NV325 MES 03040 D : CUT DUT VALVE'2NV326 i REPLACC SNUBBER'2-R-ND-0326
.MES 03501: D i.:
.MES 03541 .D REPLACED SNUBBER BODY 2-R NO-0277 HEG'03562 :O. ; REPLACE SNUBBER 2-R-5A-1SO3, REPLACED STUD hES 03567.' B :/ REPLACED $ NAP RING 2-R-NI-1685 MES'03610 0 ... REPLACED CAP 15 CREWS ON SNUBBER 2-R-UB-1003 MES'03630 A- , REPLACED'VALUE5-2NC19 &.2NC2O
-- M E 5 03647: -D REPLACED SNUBBER! & LOAD ~STUO 2-R -5M-1000 MES 03647' 8- REPt. ACE'SNUeDER 2-R-SM-1oOo MES 03660- Di - REPLACED 15A PIPING 1150 25A4.
MES 09660-2 D REILACED COTTER PIN ( 2--R-5 A-1529 )
' 1REPt. ACED PIPEiCLAMP (2-R-5A-1530)
MES 03664 IL - REPLACED ROD END ON' CLAMP END OF STRUT R-CA-1643 REPLACED PLATC MATERIAL U 2-R-CA-1442
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- HNI?064 % ? n- ~ REPLACED NOT;ON:UDNNET-VALVE 2NV17 7
? N5M ' 03;M7 ; D :RCPLACED BONfE1 5TU05 AND NUT 5 ON VALVE 25VO13
- i. ' NSf t 0 H2110 LO : EPLACED #dLfDONNET STUD 5 ON: VALVE 25V019
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- Class Descrip t.io tt NSM 03609- D REPLACED VALUE 2NI161
- NSM OD702 D: - REPf_ ACED - VALUE- 2NV205 .
i' H5M 03714 D ' CUT ACCESS HOLE 5/G "2A" -- W . FLANGE AND- BOLTING MATERI AL
' N5M 11936 0 - REPL.5NUBBER WITH STRUT, REPL LOAD PIN 2-R-ND-0337 N5M 19053 .O CUT-OUT' VALVE 2BOOBA NSM 13462 'O CUT DUT UALVE-2CA30A N5M 13063 0 . CUT.DUT VALVE 2CA42B NSM 1 3 0 6 4 .. O ; CUT GUT' UALUE 2CA468 N5M A3065. O CUT DUT UALVE 2CASOA N5M 13046 U CUT GUT VALUE,2CAS4D N5M 13067' B CUT DUT VALVE 2CASDA NSM 13060 7 UCT DUT VALUE 2CA62A l-JSM 13069 O CUT'OUT VALVE 2CA668 N5M 13093 G CUT GUT VALVE 2BB19A N5M u 130'74 'O CUT-OUT VALVE 2 GDS 6A NLM-13095 .D -CUT OUT VALVE 2BD60A~
N5M 13327 - D CUT OUT VALUES'25AOO2 & 25AOOS N5M 1932/ O 2-It-5A-1520 -_ REPLACE ANCHOR 5, TUDE STEEL, PLATE OPS 30033-4 D CUT DUT-VALUE:25AOO2, WELD 5 25Al-5,4 OPS 304.13 :O CUT OUT'UALUE 2NU315 - WELDS 2NU626-14,15 OPS 39729 D _ REPLACED BONNET STUD 5.ON VALUE L%eLA12 OPS el1092 D REPLACED INTERNALS &' NOZZLE ON RELIEF VALVE 2NI161 Ops 41099 A- - REPLACEO'SOME-INTERNAL PARTS ON ENI-163 OPS 41357 O - 25V1 REPLACE DONNET, STUD 5 AND NUTS OPS 43391 O REPLACED STUD 5/ NUT 5 ON FLANGES - UALUE 2NV172A OPS 45120-2 O REPLACED LOAD PINS 2-R-NM-1414 OPS 4 *', 3 3 2 '- 18 REPLACED VALUE'2NV14 OPS elS390 0 REPLACE RELIEF VALVE 2NV305 UP5 45452 D Ct M OUT'UALVE 25M748 OPS elS435 D RL ACE TI'E f WEDGE AND STEM ON VALUE EMIlO3A OPS 45YO6 0 REa 4.CED, NUZZLE IN RELIEF. VALVE 2NI119 OPS-464P/: D REPLACED DONNET ON VALUE 25U204 UPS 46S$P 'A- DISASSEMBLED UALUE ENC 106'- NO PARTS REPLACEL OPS 467341 - UALVC 2NDOO3.WA5: REPAIRED AND REPLACED t IPS 4N/60 A DIEA55EME2ED UALVE ENC 13 - NO PARTS REPLACED OPS 468741 A - DISA55EMDLEC VALVE ~UNC94 - NO PARTS REPLACED pl tl 03206 11 ' CliT-UUT UALUE 2BDO60A - tJELD5 2BB41-1,2,3,7 AND 20042-3 PLtd (s3M96 A . RCPLACE SNAP. RINGS ON WASHERS 2-R-NC-1700.' REPLACED PIN & SNAP RING 5 ON 2-R-tvC-167S n . , ~ . . . .s.w n - ,we.. , , + a ,-
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Wor k - Request. # .. C l a s s '. Description 4 -_5WR . 04472 A REPLACED VALUE.2NC2
-SWR 04473 ' A - REPLACED UALUE-2NC3 ,
SWR'04499 i A REPLACED VALVE 2NC1
' SWR 05292 A ~ REACTOR'VE5SEL. FLANGE, CHASED THREADS ON STUD HOLE #6 l- SWR OS292 A DI5A55EMDLED RV teEAD'- NO PARTS REPLACED
-SWR 05312 A DISA55EMDLEO.RV HEAD THERMOCOUPLE - NO PARTS REPLACED SWR-06204 A- DISA55EMDLED UALVE 2NIO1 -- NO PARTS REPLACED SWR 06200' Az ' DISA5SEMBLED VALVE 2NIGE REPLACED DONNET, STUD 5, NUT 5 SWR.06310 A= ENTEREI' 5/G "2D" . NO PARTS: REPLACED A
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SWR 06319.c ENTERED 5/G "2C" 'NO'PART5 REPLACED SWR 06320 ' A SINTERED . 5/G "2D" -. NO PARTS FMPLACED SWR 06321 A: ENTERED 5/G:"2A"'- NO PARTS REPLACED j' SWR 06061 D ' REPLACED HANDHOLE/ INSTRUMENT COVERS - REPLACED DOLT 5 DN COVER
- SWR 06081 ~ R.C.-PUMP "D" REPLACEO MECH. SEAL 5 ON PUMP
' SWR 09442-2 D ' REPLACED SPACER WASHER & SNAP RING 2-R-NU-139 Y t
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