ML20248E765
| ML20248E765 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/30/1989 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20248E763 | List: |
| References | |
| NUDOCS 8904120362 | |
| Download: ML20248E765 (50) | |
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. gf Inservice Inspection Report of Wolf Creek Generating Station P.O. Box 411 Burlington, Kansas 66839 For Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington,.Kansaa 66839 Commercial Service Dates September 3, 1985 Operating Capacity:. 3411 MWt/1200 MWe Refueling Outage: 3 End of Periods' 1 Interval: 1 Prepared by:
Wolf Creek Generating Station Results Engineering P.O. Box 411 Burlington, Kansas 66839 Date of Report Completions- March 30, 1989 s
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8904120362 890403 PDR ADOCK0500ggB2 ,
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'INEE & GBElWEEi M
- Introduction 1 Results- 2 Examinations 5 Deferred Exams 22 .-
Supports 23 Steam Generator Tubing 24 Appendix A Form NIS-1 Owner's Report for Inservice Inspections 25 Appendix B Repair /Replacment Sumary Index 39-i i
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INm000LTIN Inservice Inspection Examinations of ASME Class 1, 2 and 3 Cmponents and piping were conducted at Wolf Creek Generating Station in accordance with ASME Section XI, 1980 Riition with Addenda through Winter 1981, the ISI Proytan Plans, Regulatory Guides, and Relief Requests previously subnitted. Wis report sunnarizes the ISI Examinations empleted since the Second Refueling Outage through thg Wird Refueling Outage to the end of the first period. Approximately 32% of the Interval 1 Examinations (IWB-2412a) have been completed to end Period 1.
Inspections and surveillance required by IWA-2120 (Authorized Nuclear Inservice Inspector) were performed by Inmhwmns Mutual Casualty Cmpany (Kaper Group).
Additional surveillance were performed by NOGS Quality Assurance.
Volumetric Exams: Nuclear Energy Services and Westinghouse ultrasonically examined four (4) Reactor Pressure Vessel Outlet Nozzles. Wree (3) separate examinations were performd on each nozzle: Nozzle to Shell Weld, Nozzle to Safe-End and Nozzle Inner Radius.
Babcock and Wilcox ultrasonically examined the Centrifugal Cast Stainless Steel Material Welds. Eleven (11) separate exams were performed: two (2) RPV Outlet Nozzle Safe-End to pipe welds, eight (8) Reactor Coolant System Primary Icop Piping Welds and one (1) Boron Injection Tank Shell to Upper Head Weld.
Surface Exams: NCGS Quality Control Department perfornal a Dye Penetrant Test or Magnetic Particle Test on 33 welds: 13 Cmponent Support,1 equipment support and 19 pipe welds.
f Visual Exams: N WS Quality Control Department performed VT-1, 2, 3 and 4 exams in t
l support of ISI Program: 26 exams on System /Cmponent bolting / washers, 3 valve
! internal surfaces, 66 supports and a leakage test of all ASME Class 1, 2 and 3 Systes.
Relief Recuested Exams: NOGS has been granted Relief Requests for sme Period 1 Exams. Relief was granted for two (2) Weld Exams plus one (1) Support Exam which were to have been performed during this outage. Rese Cmponents are listed in the Examinations Section of this report and are identified by the words " Relief Request" followed by the Relief Request Number written below the Cmponent Number and an explanation to the extent of exam performed is in the Cmponent Description.
Code Case N460: NCGS received authorization frcrn the NRC to use Code Case N460.
This Code Case was applied in the exam results of one (1) Cmponent this outage.
%is Cmponent is listed in the Examinations Section of this report and is identified by " Code Case N460" below the Cmponent Number.
Auamnted Exams: NWS Quality Control Department performed 6 Augmented Exams (NUREG 0800 or Reg. Guide 1.14) this outage.
Eddy Current: Westinghouse performed Steam Generator Eddy Current Testing on approximately 12,000 tubes.
All of the ISI Proytan Plan Scheduled Examinations for Period 1 of Interval 1 at HOGS have been cmpleted, deferred or relief granted.
1 h e percentile complete was derived using the methodology outlined in Administrative Procedure ADM 05-107 - Attachinent 7.
Page 1 of 48 j
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ik Examinations resulted in a total of 11 exams with recordable-indications (this does ,
not include Geuiub:ic Reflectors in Ultrasonic Examinations). Bis is the .
information supplied for It ms 11 and 12 of the Fbrm NIS-1. . .q tese are:
_IDt . CGWUEBtr TitPE W ENWE REBER
' Volumetric Exams:
1-RV-107-121-A Reactor Pressure Vessel W hree (3) indica-Outlet Nozzle Icop A tions discovered Nozzle to Shell Weld during exam *. .All three found to be-acceptable to ASME Section XI Table IWB-3512-1 Acceptance Criteria 1-RV-107-121-B Reactor Pressure Vessel W 'Iwo (2) indications Outlet Nozzle loop B discovered during Nozzle to Shell Weld exam *. All found to be acceptable to.
ASME Section XI Table IWB-3512-1 Acceptance Criteria 1-RV-301-121-B Reactor Pressure Vessel W me (1) indication Outlet Nozzle Inop B discovered during. !
Nozzle to Safe-End Weld exam *.- his .
indication found to ')
be acceptable to ASME Section XI Table IWB-3514-3 -)
Acceptance Criteria I
- j. 1-RV-107-121-C Reactor Pressure Vessel W @ e (1) indication Outlet Nozzle Icop C discovered during Nozzle to Shell Weld exam *. Wis indication found to be acceptable to ASME Section XI Table IWB-3512-1 Acceptance Criteria 1-RV-301-121-C Reactor Pressure Vessel W 'IWo (2) indications Outlet Nozzle locp C discovered during Nozzle to Safe-End Weld exam *. his indication was found to be acceptable to ASME Section XI Table IWB-3514-3 Acceptance Criteria
- All indications were compared to PSI Data. In no cases were new relevant indications identified or apparent growth in existing indications identified.
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M C G E G EEtt TIPE & EIAM RIEiWE 1-RV-107-121-D- Reactor Pressure Vessel UP Five (5) i Outlet Nozzle Icop B indications _ _
Nozzle to Shell Weld diswvmai during exam *. These indications found to be acceptable to ASME Section XI Table IWB-3512-1 Acceptance Criteria-1-RV-301-121-D Reactor Pressure Vessel Uf Two (2) indications Outlet Nozzle Icop D discovered during Nozzle to Safe-End Weld exam *. 1hese
' indications found to be acceptable to.
Table IWB-3514-3 Acceptance Criteria.
Surface Exams i
1-EP-01-S011-J Safety Injection Test Line PT Three (3) indica-Connections to h =ilator tions detected
'Line Sockolet to Pipe Weld during exam. All three found to be acceptable to ASME Section XI Table '
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.IWB-3514-3 ;
Acceptance.
Criteria. This weld to be examined in Period 2.
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1-PEJ01A-SUP-1 Residual Heat Removal PT .Five.(5) indica-Heat Exchanger A Integrally tions detected Attached Support Foot Weld - during exam. All found to be-acceptable to ASME Section XI Table IWB-3514-3 Acceptance Criteria. 'Ihis weld to be examined in Period 2.
- All indications were ccanpared to PSI Data. In no cases were new relevant indications identified or apparent growth in existing indications identified. j Page 3 of 48 i
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'JDi (X31E G EBtr TIPE @ EEAM RBSEE c
Visual Exams e AE05-R003-242 Snubber Support, 14" Main .Vf-3 h beam supporting Feedwater Supply to Steam the Snubber Beam Generator "C".. Attachment was bent at the web. A VI-3 was performed on i the upstream and downstream supports and were found to be satisfactory.
The beam was modified under Repair / Replacement Package RR 88-105.
Failure analysis is per 83A1714, Statistical '
Ramnling Plan.
This support will be re-examined in Period 2.
AB01-R504-145 Snubber Support, Icop 3 Main .VI-3 h snnbhar setting Steam Isolation Valve was found to be out
-AB HV-20 2" Bypass Line out of design just downstream of AB-V222. tolerance
>; indicating a possible pipe shift. Failure.
Analysis is per-83A1714,~ Statistical Ramnling Plan.
'Ihis support will be examined in Period 2.
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.. J EIAMDIATIGES >
'Ihe following is a sunmary of the ISI Examinations perfonned and is supplied for ,
Itan 10 of the Form NIS-1: ('Ihis listing does not include VI-2 Exams or Vf-4 Exams i on snubbers which are done in accordance with Technical Specifications).
Ome nnm CDEFOGENT COIPOGENT 'ITPE T I CA'IKKEY 1YEM IDIBER DESCRIPTION EIAM .i B-D B3.90 RV-107-121-A Reactor Pressure Vessel Uf Loop A Outlet Nozzle to Vessel Shell Weld RV-107-121-B Reactor Pressure Vessel Uf !
Loop B Outlet Nozzle to Vessel Shell Weld [
1 RV-107-121-C Reactor Pressure Vessel Uf Irop C Outlet Nozzle to Vessel Shell Weld l RV-107-121-D Reactor Pressure Vessel UP Icop D Outlet Nozzle to Vessel Shell Weld B3.100 RV-107-121-A-IR Reactor Pressure Vessel Uf Icop A Outlet Nozzle Inner Radius RV-107-121-B-IR Reactor Pressure Vessel UT Icop B Outlet Nozzle Inner Radius RV-107-121-C-IR Reactor Pressure Vessel Uf {
l Ioop C Outlet Nozzle
! Inner Radius l RV-107-121-D-IR Reactor Pressure Vessel UT Icop D Outlet Nozzle j Inner Radius l B-F B5.10 RV-301-121-A Reactor Pressure Vessel Uf Icop A Outlet Nozzle to l
Safe-End Weld RV-301-121-B Reactor Pressure Vessel UT Icop B Outlet Nozzle to Safe-End Weld l
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4 C3E CTE C3GOERP C3fEQUEIR TYPE & )
Cearmr rm mem oernuPrIm Exm 1 RV-201-121-C Reactor Pressure Vessel UP l Icop C Outlet Nozzle to 1 Safe-End Weld RV-301-121-D Reactor Pressure Vessel Uf Icop D Outlet Nozzle to !
Safe-End Weld l
B-G-1 B6.50 CH-WASH-1 Reactor Pressure Vessel .Vf-1 through Closure Head Washers CH-WASH-54 B-G-2 B7.20 TBB03-10D-b Pressurizer Manway Vf-1 Bolting B7.30 EBB 01A-2-A-1-b Steam Generator A Hot Iag Vf-1 through Prinary Manway Bolting EBB 01A-2-A-16-b EBB 01A-2-B-1-b Steam Generator A Cold Iag Vf-1 through Primary Manway Bolting i EBB 01A-2-B-16-b 1
EBB 01B-2-A-1-b Steam Generator B Hot Iag Vf-1 )
through Primary Manway Bolting i i
EBB 01B-2-A-16-b EBB 01B-2-B-1-b Steam Generator B Cold Iag Vf-1 through Primary Manway Bolting !
EBB 01B-2-B-16-b EBB 01C-2-A-1-b Steam Generator C Hot Iag Vf-l through Primary Manway Bolting EBB 01C-2-A-16-b EBB 01C-2-B-1-b Steam Generator C Cold Iag Vf-1 through Primary Manway Bolting EBB 01C-2-B-16-b EBB 01D-2-A-1-b Steam Generator D Hot Iag Vf-1 through Primary Manway Bolting EBB 01D-2-A-16-b EBB 01D-2-B-1-b Steam Generator D Cold Iag Vf-1 through Prinary Manway Bolting EBB 01D-2-B-16-b Page 6 of 48
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CD0E 000E 00EOlENf COGGBff TEPE & l CmHIRY ITEM N[MBER n erRIPf1Gi __E_ KAM l B7.50 BB-06-FE-427- L b Resistance 'Ibmperature VT-1 :
Device Manifold's Discharge Line to RCS' Icop 2 Flow Elsnent Flange Bolting BB-06-FO-2-Lb Resistance Temperature 'Vf-l Device Manifold's Discharge Line to RCS Icop 2 Flcw Orifice ,
Flange Bolting 1 BB-08-FL1-b Reactor Coolant Pump "A" VT-1 Seal Water Injection In-Line Flange Bolting B7.70 BB-06-8073B-b . Resistance Tsuperature Vf-l Device Manifold's Disch. Line to RCS Icop 2 Valve BB-8073B Bolting BB 8074B-b Resistance Temperature Vf-l Device Manifold's Disch. Line to RCS Icop 2 Valve BB-8074B Bolting L 24-HV8145-b Chanical and Volume VI-l Systen Aux. Spray Line to Pressurizer Valve BG HV-8145 Bolting FJ-04-BB-PV8702B-b Residual Heat Raroval Vf-l Train B Suction Line ,
frcxn RCS Icop 4 Hot Iag Valve BB PV-8702B Bolting EM-03-8841A-b Residual Heat Raroval VI-l to Safety Injection Systen Hot Ing Recirc.
Icop 2 Valve FJ-8841A Bolting EM-03-BB-8949C-b Safety Injection to VI-l Residual Heat Raraval Line Isolation Check Valve BG-8949C Bolting Page 7 of 48
4 03E CGE CIMEDIENT CGEEQENT TEPE T CASH D E ITIM MMBER W EIAM N 05-BB-8949A-b Safety Injection to W-1 Residual Heat Ratoval Line Isolation Check Valve BB-8949A Bolting EM-05-BB-8949D-b Safety Injection to W-1 Residual Heat Removal Line Isolation Check Valve BB-8949D Bolting EP-01-8818A-b Residual Heat Removal W-1 to Am=ilator Safety Injection Check Valve EP-8818A Bolting EP-01-8818D-b Residual Heat Ranoval VT-1 to Ammilator Safety Injection Check Valve EP-8818D Bolting EP-01-8956A-b Ammilator Safety VT-1 Injection to RCS Cold Iag Icop 1 Isolation Check Valve EP-'8956A Bolting EP-01-BB-8948A-b Ammilator Safety VT-1 Injection to RCS Cold Iag Icop 1 Isolation Check Valve BB-8948A Bolting EP-02-8956C-b Am=ilator Safety VT-1 Injection to RCS Cold Iag Icop 3 Isolation Check Valve EP-8956C Bolting B-J B9.11 BB-01-F201 Reactor Coolant Pump B PT Discharge Nozzle Safe-End to RCS Cold Iag Pipe Weld BB-01-F203 Reactor Pressure Vessel UT Outlet Nozzle Safe-End to RCS Hot Iag Icop 2 Pipe Weld (perpendicular scan only)
BB-01-F207 Reactor Coolant Pump B PT, UT Inlet Nozzle Safe-End to RCS Crossover Ieg Pipe Weld (perperrlicular scan only)
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(IEE 03E CXMEGENT (XMEGEBFf TYPE &
CATIGG E ITEM MMBER MRPRIPTI(M EIAM BB-01-F303 Reactor Pressure Vessel UT Outlet Nozzle Safe-End I to RCS Hot Iag Imp 3 Pipe Weld (perpendicular scan only) -)
BB-01-F305 Steam Generator C Outlet PT, UT Nozzle Safe-End to RCS Crossover Iag Pipe Weld (perpendicular scan only)
BB-01-F306 Reactor Coolant Systen PT, UT Icop 3 Crossover Iag Pipe to Elbow Weld (perpendicular scan only)
BB-01-F307 Reactor Coolant Punp C .PT, UT Inlet Nozzle Safe-End to RCS Crossover Iag Pipe Weld (perpenMoilar scan only)
BB-01-F308 Reactor Coolant System PT, UP Isop 3 Crossover Iag Pipe to Elbow Weld (peWimilar and parallel scan)
BB-01-F405 Steam Generator D PT, UT Outlet Nozzle Safe-End to RCS Crossover Ing Pipe Weld (perpendimilar scan only)
BB-01-F407 Reactor Coolant Pump D PT, UP Inlet Nozzle Safe-End to RCS Crossover Iag Pipe Weld (perpenMoilar scan only)
BB-01-S305-4 Reactor Coolant Systen PT, UT Icop 3 Crossover Iag Pipe to Elbow Weld (perpendoilar and parallel scan)
EP-01-F007A Accumulator Safety Ur (Relief Request Injection Tank A Discharge I1R-19) into RCS Icop 1 Cold Iag Valve EP-8948A Weld to Pipe (Reverification of Exam Limitation)
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<O CEE CTE (XMEGENT CIMEQHPF TYPE (F CMHXRY ITEM MMBER DESCRIPTION EDM EP-02-F007 Am-lator Safety Ur (Relief Request Injection Tank B Discharge I1R-19) into RCS Icop 2 Cold Iag Valve EP-8948B Weld to Pipe (Reverification of Exam Limitation)
B9.32 EP-01-S011-J Safety Injection Test PT Line Cannection to Am=1ator Line Socket to Pipe Weld B-L-2 B12.50 EM-03-8841A-SURF Residual Heat Ranoval VI-3 to Safety Injection Hot Iag Recire. Icop 3 Check Valve Internal Surfaces B-M-2 B12.50 EP-01-8818A-SURF Residual Heat Renoval VI-3 to Am=1ator Safety Injection Check Valve EP-8818A Internal Surfaces EP-01-8818D-SURF Residual Heat Renoval VI-3 to Am=1ator Safety Injection Isolation Check Valve EP-8818D Internal Surfa s l C-A C1.20 TEM 01-SEAM-2-W Boron Injection Tank Ur l Top Head to Shell Weld (perpendimlar scan only)
C-C C3.20 AB-01-R005 Steam Generator D MP ,
Main Steam Outlet ;
i Pipe Hanger Integrally l l
Welded Lugs AB-01-R006 Steam Generator A Mr Main Steam Outlet !
Pipe Hanger Integrally Welded Ings AB-01-R009 Steam Generator A MP Main Steam Outlet Pipe Hanger Integrally Welded Lugs AE-04-R010 Steam Generator A Mr Feedwater Inlet Pipe Hanger Integrally Welded Lugs Page 10 of 48
,' w 03E CWE CGGGIENf CGEOENP TIPE &
CMHIRY ITIM _ IUlBER DESCRIPTIGi EIAM AE-04-R014. Steam Generator B MP Feedwater Inlet Pipe Hanger Integrally Welded Lugs AE-04-R019 Steam Generator A MP Feedwater Inlet Pipe Hanger Integrally Welded Iugs FJ-01-C007 Residual Heat Renoval' PT Heat Exchanger A Outlet Pipe Hanger Integrally Welded Iugs FJ-01-C014 Residual Heat Renoval PT Pump A Discharge Pipe Hanger Integrally Welded Lugs
- FJ-01-C015 Residual Heat Ranoval Pr Heat Exchanger A Bypass Line Pipe Hanger Integrally Welded Lugs FJ-01-H016 Residual Heat Ratoval PT Heat Exchanger A Inlet i
Pipe Hanger Integrally l Welded Lugs FJ-01-R020 Residual Heat Removal PT Heat Exchanger A Bypass Line Pipe Hanger Integrally Welded Lugs j FJ-01-R022 Residual Heat Removal PT (Code Case N460) Heat Exchanger A Outlet )
l Pipe Hanger Integrally Welded Lugs FJ-01-R028 Residual Heat Renoval PT ,
Heat Exchanger A Outlet Pipe Hanger Integrally Welded Lugs C3.30 PEJ01A-SUP-1 Residual Heat Ranoval PT Pump A Integrally <
Welded Support Foot Block Page 11 of 48
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GIE C3E GEgnmarr N' TIPE &
CIWKKEY M EBEEL IMK3UPrKW EI7M C-F- C5.11 FJ-01-S017-B Residual Heat Remwal FT Heat Exchanger _A Outlet to CVCS Charging Punp Pipe _to. Tee Weld C5.12 EJ-01-S014-A-LD Residual Heat Renwal PT PLMp A Discharge Line Flow Orifice Pipe Seam Weld.
EJ-01-S017-B-ID Residual Heat Removal PT Heat Exchanger A Outlet .
In-Line Tee Seam Weld j i FJ-01-S017-B-LU Residual Heat Renwal PT.
L ~ Heat Exchanger A Outlet Pipe Seam Weld
.D-B D2.20 EBG01-SUPPCRT-2 Istdown Heat Exchanger .VT-3 Cmponent Support Integral Attachment
.EIE01A-SUPPORT-1 Ca ponent Cooling Water VT-3 Heat Exchanger A Equip-ment Support including Integral Attachment Weld at Heat Exchanger Shell EEG01A-SUPPCRT-2 Cmponent Cooling Water VT-3 Heat Exchanger A Equip-ment Support' including Integral Attachment Weld at Heat Exchanger Shell EIE01A-SUPPCRT-3 Conpanent Cooling Water VT-3 Heat Exchanger A Ek]uip-ment Support including Integral Attachment Weld at Heat Exchanger Shell EEG01A-SUPPCRT-4 Cw g mint Cooling Water VT-3 Heat Exchanger A Et]uip-ment Support including Integral Attachment Weld at Heat Exchanger Shell EG-01-A001 Anchor Support Cmponent VT-3 Cooling Water Train A, CCW Heat Exchanger A Outlet to Fuel Pool Cooling and Service Icop Integral Attachments Page 12 of 48
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(I7)E C3E CXMPORKl' 03EGEiff TEPE CF Q1HIRY TIEM MMBER DES RIPHQi EEAM B3-01-H001 Variable Spring Support, vr-3 Component Cooling Water Train A, Pump A Suction EG-01-R014 Rigid Support, Conpanent vr-3 Cooling Water Train A Pump A Discharge down-stream of B3 FE-95 E 01-R023 Frame Support, Camponent VI-3 Coolfng Water Train A-Pump C Discharge down-stream of G V000 EG-02-A003 Anchor Support, Cmponent vr-3 Cooling Water 'Irain A, Fuel Pool Heat Exch'nger A Return Header 5 02-A005 Anchor Support, Caponent VI-3 Cooling Water ')tain A, Fuel Pool Cooling Heat Exchanger A Supply Header EG-02-C003 Frame Support Cmponent vr-3 Cooling Water Train A, Fuel Pool Heat Exchanger A Supply Header EKJ06A-SUP-1 Diesel Engine A Jacket vr-3 Water Heat Exchanger Equipnent Support including Integral Attachment Weld at Heat Exchanger Shell EKJ06A-SUP-2 Diesel Engine A Jacket VT-3 Water Heat Exchanger R]uipnent Support including Integral Attachment Weld at Heat Exchanger Shell IF J06B-SIiP-2 Diesel Engine B Jacket VI-3 Water Heat Exchanger RIuipnent Support including Integral Attachment Weld at Heat Exchanger Shell Page 13 of 48
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CTE CGE COGGIENf Q MPG EttP TYPE T CN1HIRY IWM IUEER mR[RIPfKM EDM PEF 01A-SUPPORT-1 Essential Service Water VI-3 Pump A Sole Plate Foundation Bolts, Discharge Head Assmbly, Flange to Sole Plate Bolts and Discharge Head Assmbly Shell to Discharge Pipe Fillet Welds .
D2.30 EU-01-R027 Snubber Support, Cmponent vr-3 Cooling Water Train A Carman Discharge EG-01-R030 Snubber Support, Caponent VI-3 Cooling Water Train A, RHR Heat Exchanger A Inlet D2.40 EG-01-C001 Variable Spring Support, vr-3 Caponent Cooling Water Train A, Pump C Suction F-A F1.30 EDG01-SUPPTT-2 Chmical and Volume VT-3 Control I'?tdown Heat Exchanger Et[uipment Support EEG01A-SUPPCRT-1 Cmponent Cooling Water VI-3 l- Train "A" Heat Exchanger Cmponent Support EEG01A-SUPPORT-2 Cmponent Cooling Water Vr-3 Train "A" Heat Exchanger s
Cmponent Support EEG01A-SUPPORT-3 Cmponent Cooling Water VI-3 Train "A" Heat Exchanger Cmponent Support h EEG01A-SUPPORT-4 Cmponent Cooling Water Vr-3 Train "A" Heat Exchanger Cmponent Support EKJ06A-SUP-1 Emergency Diesel Generator VI-3 Train "A" Jacket Water Heat Exchanger Cmponent Support Page 14 of 48 L - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ _ _ _ _
'b OTE COE CCMEGIENT CGEGERIT TIPE &
CMHIRY ITEM N,3fBER IESCRIPTIQi EDM EKJ06A-SUP-2 Fom.yaicy Diesel Generator VI-3 Trair. "A" Jacket Water Heat Exchanger Cmponent Support f i
EKJ06B-SUP-2 Diesel Engine B Jacket Vr-3 l Water Heat Exchanger ]
-Equipment Support K-EF11-R001 Essential Service Water VI-3 Pump A lower Pimp Shaft Support PEF 01A-SUPPCRT Essential Service Water VI-3 Pump A Sole Plate Foundation Bolts,' Discharge Head Assmbly Flange to Sole Plate Bolts and Discharge Head Assmbly Shell to Discharge Pipe Fillet Welds F-B AIL BG-01-C009-112 Frame Support Chemical vr-3 and Volume Control Systan Charging Flow Downstream of BG-V8902B BG-22-HOO1-231 Variable Spring Support vr-3, 4 Chenical and Volume Control Systs, Istdown Flow to Ietdown Heat Exchanger Upstream of Valve BG HV-8160 EG-01-A001-142 Anchor Support, Cmponent vr-3 Cooling Water Train A, CCW Heat Exchanger A Outlet to Fuel Pool Cooling and l Service Icop l EG-01-R023-142 Frame Support, Cmponent vr-3 Cooling Ptter Train A Pump C t scharge down-stream vf G V008 L O2-A003-142 Anchor Support, Cmponent vr-3 4 Cooling Water Train A, !
Fuel Pool Heat Exchanger A Return Header Page 15 of 48
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t 03E C00E 03GOENT OCM OENF TIPE T CM1103E HTM NGEER DESCRIPf1(M EDM E 02-A005-141 Anchor Support, Cauponent vr-3 Cooling Water Train A, Fuel Pool Cooling Heat Exchanger A Supply Header L O2-C003-133 Frame Support Canponent vr-3 Cooling Water Train A, Fuel Pool Heat Exchanger A Supply Header EG-18-R005-621 Frame Support, Cmponent vr-3 Cooling Water Train B, Fuel Pool Cooling Heat Exchanger B Return Header F2.30 PBB01A-SUP-1A Reactor Coolant Pump A VI-3 Column Support F2.40 RBB01-01-231 Reactor Pressure Vessel vr-3 (Relief Request Support I1R-18) (Partial Exam Perfonned)
F-C ALL AB-01-H501-145 Variable Spring Support, vr-3, 4 Main Steam System, Loop 3 MSIV .(AB HV-20) Bypass between AB-V221 and AB HV-21 AB-01-H503-145 var 'ble Spring Support, vr-3, 4 Main Steam System, Icop 2 MSIV (AB HV-17) Bypass between AB-V219 and AB HV-18 AB-01-H507-145 Variable Spring Support, vr-3, 4 Main Steam System, Icop 4 MSIV (AB HV-11) Bypass between AB-V215 and AB HV-12 AB-01-R031-145 Snubber Support, Main VI-3 Steam Systen, Icop 3 Isolation Valve AB HV-20 l
l BB-01-H001-231 Variable Spring Support, vr-3, 4 Reactor Coolant Systan l Pressurizer Surge Line Page 16 of 48
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GEE CGE GEEGEBEF GEEEEEEEP TTPE OF CNtBGGE _EB IDEER DIBOUPTEGI EERN BB-01-H002-231 Rigid Support, Reactor W-3 Coolant System' Pressurizer Surge Line BB-01-R001-231 Snubber Support, Reactor W-3 Coolant Systen Pressurizer Surge Line '
L BB-01-R002-231 Snubber Support,, Reactor W-3 Coolant Systen Pressurizer Surge Line BB-01-R003-231 Sonhhar Support, Reactor W-3 '
Coolant Systen Pressurizer
, Surge Line BB~01-R004-231 Snubber Support, Reactor W-3 Coolant Systen Pressurizer Surge Line BB-04-H008-261 Constant Spring Support, W-3, 4 Reactor Coolant Systen, Cold Iag Pressurizer Spray Line BB-04-H009-261 0:nstant Spring Support, . W-3, 4 Reactor Coolant Systen, Cold Iag Pressurizer Spray Line at Bypass Line Tee BG-09-H519-112 variable Spring Support, W-3, 4 Chanical and Volume Control Systen Charging Pun 1p A to -
RCP Seal Water Supply Downstream of Valve BG-V590 BG-22-H003-242 Variable Spring Support, W-3, 4 Cb = W 1 and Volume Control Systen, Istdown Flow to Charging /Istdown Regenerative Heat Exchanger BG-22-H010-232 variable Spring Support, W-3, 4 Chanical and Volume Control Systan at BS ICV-460, RCS Istdown -
frun Icop 3 Crossover Iag Page 17 of 48 L___________________.._______.__._ __ _ _ . . _ . . _ _ . _
5 000E cme 035 GENT ONEGEMP TYPE &
CNIEGE ITEM NMEER IES RIPFIGi EIAM BG-22-H0ll-232 Variable Spring Support, VT-3, 4 Chanical and Volume i Control Systan at BG ILV-459, RCS Ietdown i frcrn Icop 3 Crossover Iag BG-22-R012-232 Snubber Support, Chemical W-3 and Volume Control Systen, RCS letdown frun Icop 3 Crossover Iag just down-stream of Drain Line Tee to Valve BB-V290 BM-03-H509-232 variable Spring Support, W-3, 4 l Steam Generator Blowdown Systen, Steam Generator C Drain Idne between Drain Valves BM-V027 and BM-V119 EF-03-H004-122 Variable Spring Support, W-3, 4 Essential Service Water l Systen Train A, Branch I Return Header Upstream of Drain Idne Tee to Valve EF-V228 EF-03-H005-122 Variable Spring Support, W-3, 4 Essential Service Water Systan Train A Return Header Upstream of EF-03-H004-122
! EF-09-C549-134 Frame Support, Essential VT-3 Service Water Systan Train A, Fuel Pool Cooling Pump Rocun Cooler A Outlet Header Upstream of Vent EF-V268 EF-09-C561-134 Frame Support, Essential VT-3 Service Water Systen Train A, Fuel Pool Cooling Pump Rocrn Cooler A Outlet l Header near EF-052-HBC-4" Tie-In l
Page 18 of 48 l
e CODE OTE 03EGENf 03EOEMP TYPE T CNIRDN T11M NWIBER DEl$GRIPTIGi EDM EF-14-H003-341 variable Spring Support, VT-3, 4 Essential Service Water System Train A, Class 1E Switchgaar A/C Condenser Unit Inlet Upstream of Valve EF-V054 EF-14-H007-341 Variable Spring Support, VT-3, 4 :
Essential Service Water Systan Train A, Class 1E Switchgear A/C Condensing Unit Outlet Downstream of Valve EF-V055 EF-15-H002-341 variable 6pring Support, VT-3, 4 Essential Service Water Systen Train B, Class 1E Switchgear A/C Condensing Unit Outlet Downstream of Valve EF-V082 5 01-C001-142 Variable Spring Support, VT-3, 4 C mponent Cooling Water Train A, Pur:p C Suction 5 01-H001-142 Variable Spring Support, VT-3, 4 cmponent Cooling Water Train A, Pump A Suction
& 01-R014-142 Rigid Support, Cmponent VT-3 Cooling Water Train A Pump A Discharge down-stream of FC FE-95 5 01-R027-142 Snubber Support, Cmponent vr-3 Cooling Water Train A Camon Discharge 5 01-R030-142 Snubber Support, Camponent VT-3 Cooling Water Train A, RHR Heat Exchanger A Inlet 5 04-R011-131 Snubber Support, Cmponent VT-3 Cooling Water System Train B, RHR Heat Exchanger B Outlet Page 19 of 48
. .c CKEE CUE CIMPG EBtr (IEEn ner TYPE T CATIGIE ITEM 1(BER IMIBCRIPTI(N EIAM EJ-01-H013-132 Variable Spring Support, VT-4 Residual Heat Remwal-System Train A, RHR Heat Exchanger A Outlet Header FJ-01-H014-134 Variable Spring Support, VT-4 Residual Heat Remwal System Train A RHR Heat Exchanger A Outlet Upstream of FJ IN-8809A PJ-01-H016-132 Variable Spring Support, VT-4 Residual Heat Remwal System Train A, RHR Heat Exchanger A Inlet Header ai-03-H006-231 Variable Spring Support, VT-4 High Pressure Coolant Injection Systen to RCS -
Loop 1 Cold Iag fran Boron Injection Tank at Valve BB-V001 FC-01-H001-135 Variable Spring Support, VT-3, 4 Auxiliary Feedwater Pump Turbine Steam Exhaust at Condensate Collection Iag FC-01-H002-135 Variable Spring Support, VT-3, 4 Auxiliary Feedwater Pump Turbine Steam Exhaust Line EU-01-H003-135 Variable Spring Support, VT-3, 4 Auxiliary Feedwater Pump Turbine Steam Supply Header
! JE-03-C004-511 Rigid Support, ER=u.yuucy VT-3 Fuel Oil System Train B, Overflow and Recirculation Line frun Day Tank Stand-Pipe to Storage Tank i
JE-03-C525-511 Frame Support, Bergency VT-3 Fuel Oil Systen Train B, i
Fuel Oil Supply to Day Tank just upstream of Strainer Manifold i Page 20 of 48 E -- -
1
.o CODE QJDE 03tPONEttr 03GOiEttr TIPE OF CMHIEY ITEM NLEIBER IESCRIPTI(N EEAM F3.30 CRmPIr-SUP-1 Control Rod Drive VI-3 through Mechanism Seismic Support CR mPL-SUP-6 Augmented:
N/A N/A BG-09-EW369-CA Reactor Coolant Pump "B" PT Seal Injection 'Ihrottle Valve BG-V199 to Pipe-Weld (downstream side of valve)
BG-09-FW370-OA Reactor Coolant Pump "B" PT Seal Injection '1hrottle Valve BG-V199 to Pipe Weld (upstream side of valve)
BG-09-FW877-Oh Reactor Coolant Pump "C" Pr Seal Injection '1hrottle Valve BG-V200 to Pipe Weld (upstream side of valve)
BG-09-EW878-OA Reactor Cooling Pump "C" PT Seal Injection '1hrottle Valve BG-V200 to Pipe Weld (downstream side of valve)
BG-09-IW879-OB Reactor Coolant Pump "D" PT Seal Injection '1hrottle Valve BG-V201 to Pipe Weld (upstream side of valve)
BG-09-FW880-OB Reactor Coolant Pump "D" PT Seal Injection 'Ihrottle Valve BG-V201 to Pipe 1 Weld (downstream side of valve) i l
I Page 21 of 48
DEFERRED EIRMS NCGS has elected to defer eleven (11) exams as allowed by ASME Section XI. '
1he .
exams being deferred are: l CODE CODE CDfEGENT CCMPGENT TYPE T CATIKXEY lYDi MMBER IEpQRIPTICN EKAM B-G-1 B6.180 PBB01B-BOLT Reactor Coolant Pump B Ur Main Casing Bolts B-L-2 B12.20 PBB01B-SURF Reactor Coolant Pump B Vr- 3 Internal Surfaces B-M-2 B12.50 EJ-04-BB-PV-8702B-SURF Residual Heat Renoval VI-3 Punp B Suction Isolation Valve frun Icop 4 Hot Iag - Internal Surfaces EP-01-8956A-SURF Accumulator Safety Vr-3 Injection Tank A Discharge Check Valve Internal Surfaces B-N-2 B13.31 RV-CSL-104-142-A Core Support Lugs vr-3 RV-CSL-104-142-B Core Support Lugs vr-3 RV-CSL-104-142-C Core Support Lugs vr-3 RV-CSL-104-142-D Core Support Imp VI-3 RV-CSL-104-142-E Core Support Lugs VI-3 RV-CSL-104-142-F Core Support Lugs VI-3 B-N-3 B13.32 RV-CORE-STRUCT Removable Core Support VI-3 Structures l
I l
Page 22 of 48
. e i e
SWPORES Six (6) Supports were selected for ISI Examination per the Statistical 9 mnling Plan. This cmpletes the Period _1 Support Examinations.
'Ihe systems in which the supports were exanined are:
SYSTEM IMBER & SUPPORIS Refuel 3 i Chemical Volume Control 1 Essential Service Water 2 Cmponent Cooling Water 1 Auxiliary Turbines 1 Bnergency Fuel Oil _1 6
A total of 143 of the 440 Supports scheduled for Interval 1 which required examination, have been examined, per the Statistical pmnli_ng Plan.
SYSTEM N[MBER T SUPPW'IS Interval 1 .
Main Steam 3 Main Feedwater 4 Auxiliary Feedwater 2 Reactor Coolant 16 Chenical arxi Vclume Control 16 Steam Generator Blowdown 12 Fuel Pool Cooling and Cleanup 2 Essential Service Water 17 Cmponent Cooling Water 33 Residual Heat Removal 3 l High Pressure Safety Injection 11 Containment Spray 9 Accumulator Safety Injection 3 l Auxiliary Turbines 2 Containment Coolers 3 Emergency Fuel Oil 2 Standby Diesel Generator 5 143 i
Page 23 of 48 1
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s STEAM GENEIUSTR 'ITEING Steam Generator (S/G) U-Tube Eddy Current Inspecticn is perfonned in accordance with Technical Specification 4.4.5.
This was the Second Steam Generator Inservice Eddy Current Exam. The examinations were performed fran November 3,1988 through Novanber 18, 1988, during Refuel III.
All 4 steam generators were inspected. A total of 11,889 tubes were examined full length. 'Ihe inspection program required that all tubes fran Rows 25 through 59 be examined to assess the integrity of the Anti-Vibration Bar (AVB) Region.
Additionally a sampling of tubes fran Rows 1 through 24 were examined. Below is a table indicating the number of Steam Generator Tubes plugged to date. Further details are available in the full report which is maintained on file at the Wolf Creek Generating Station.
HISTORY OF STFR4 GENERA'IOR TUBE PLUGGIN3 S/G A S/G B S/G C S/G D F1CIORY 3 2 2 0 PSI 5 1 2 0 RF 1 NO EXAM 0 0 NO EXAM RF 2 NO EXAM NO EXAM NO EXAM NO EXAM RF 3 1 1 3 17
'1UTAL 9 4 7 17 Steam Generator "A" (EBB 01A) 2,969 tubes were examined full length. 'Ihis corresponds to 52.8% of the inservice tubes of S/G A. Six (6) tubes had indications in the AVB Area ranging fn2n 15 to 36% through wall. One tube was plugged.
Steam Generator "B" (EBB 01B) 2,972 tubes were examined full length. 'Ihis corresponds to 52.9% of the inservj,o tubes in S/G B. Fifteen (15) tubes had indications in the AVB Area ranging fran less than 20 to 32% through wall. One tube was plugged.
Steam Generator "C" (EBB 01C) 2,973 tubes were examined full length. 'Ihis corresponds to 52.9% of the inservice tubes in S/G C. Eight (8) tubes had indications in the AVB Area ranging fran 14 to 29% through wall. Nine (9) tubes had non-AVB Area indications ranging fran 18 to 45% through wall. 'Ihree tubes were plugged.
Steam Generator "D" (EBB 01D) 2,975 tubes were examined full length. This corresponds to 52.9% of the inservice tubes in S/G D. Fifty (50) tubes had indications in the AVB Area ranging fran 18 to 73% through wall. Seven (7) of these tubes had indications greater than 40%
l through wall. Seventeen (17) tubes were plugged.
1 Page 24 of 48 l
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APPENDIX A FORM NIS-1 OWNER'S REPORT KR INSERVICE INSPECTIONS Page 25 of 48
FORM NIS-I OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 1. Owner Wolf Creek Nuclear Operating Corporation, P.O. Box 411, Burlington KS 66839 (Name and Address of Owner)
- 2. Plant _.. Wolf Creek Generating Station, P.O. Box 411, Burlington KS 66839 (Name and Address of Plant)
- 3. Plant Unit 1 4. Owner Certifieste of Authorization (if required) NA
- 5. Commercial Service Date 9-3-85 6. National Bo;.d Number for Unit NA
- 7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or installer } Serial No. Province No. Board No.
See attached. l l
Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., I (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00029) may be obtained from the Order Dept., ASME,345 E. 47th St.. New York, N.Y.10017 Page 26 of 47
v L ,
+ o FORM NIS-1 (Back)
- 8. Examination Dates 01-06-88 to 01-05-89 9, inspection interval from 09-03-85 to 09-02 l
- 10. Abstract of Examinations. Include a list of examiidtfoMYand A sta'tement concerning status of work required for current interval.
See Examination Section in the .ISI Summary Report.
11, Abstract of Conditions Noted See Results Section in the ISI Summary Report.
- 12. Abstract of Corrective Measures Recommended and Taken See Results Section in.the ISI Summary Report.
We certify that the statements made in this report are correct and the examinations and corrective mea-sures taken conform to the rules of the ASME Code,Section XI.
Certificate of Authorization No. (if applicable) NA Expiration Date NA Wolf Creek Nuclear Date 30 19 D__ Signed ._ Operating Corp By _ _ _ "
Owner V\
CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a vganSaSd commission issued by the National Lumbermens Board of BoilerMutua and Pressure Vesse{In,specto og and the State or Province of and employed by Lona Grove. IL have inspected the components described in this Owner's Report during the period 01-06-88 to 01-05-89 , and state that to the best of my knowledge and belief, the Owner i
has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or conne ted with this inspection.
i
. Commissions KS 299 1 ector's Signaturei National Board, State, Province, and Endorsements Date _[b 19 (12/82)
- Casualty Company )
i e i
! {
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l Page 26a of 47 I
I
o4 FORM NIS-1 (Back)
,,, '8. Examination Dates 01-06-88' to 01-05-89 9._ Inspection. Interval from 09-03-85 o 09-02-95 t
- 10. Abstract of Examinations. Include a list of examiri'~tio2s'and a a' statement concerning status of work required for current interval.
See Examination Section in the ISI Summary Report.
- 11. Abstract of Conditions Noted See Results Section in the ISI Summary Report.
- 12. Abstract of Corrective Measures Recommended and Taken See Results Section in the ISI Summary Report.
We certify that the statements made in this report are correct and the examinations and corrective mea- !
sures taken conform to the rules of the ASME Code,Section XI. j Certificate of Authorization No. (if applicable) NA Expiration Date NA i Wolf Creek Nuclear i Date 30 19 . Signed Operating Corp By ' "
Owner V\
CERTIFICATE OF INSERVICE INSPECTION !
I, the undersigned, holding a vpanSa5d commission issued by the National Lumbermens Board of BoilerMutua and Pressure Vesse{In,specto]
and the State or Province of and employed by of Lona Grove.' IL have inspected the components described in this Owner's Report during the period 01-06-88 to 01-05-89 , and state that to the best of my knowledge and belief, the Owner -
has performed examinations and taken corrective measures described in this Owner's '
Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector not his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or conne ted with this inspection.
. Commissions KS 299 W IQector's Signaturei National Board, State, Province, and Endorsements Date N 19 (12/82)
- Casualty Company p
Page 26a of 47
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4 APPENDIX B REPAIR /REPLAQ MENT
SUMMARY
INDEK i
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