RS-13-248, Dresden Nuclear Power Station, Units 2 and 3, Relief Request 14R-17, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval

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Dresden Nuclear Power Station, Units 2 and 3, Relief Request 14R-17, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval
ML13364A361
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/30/2013
From: Simpson P R
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-13-248
Download: ML13364A361 (19)
v • d • e


Text

RS-13-248December30, 201310 CFR 50.55aU. S. Nuclear Regulatory CommissionATTN:Document Control DeskWashington, D.C. 20555-0001Dresden Nuclear Power Station, Units 2 and 3Renewed Facility Operating License Nos. DPR-19 and DPR-25NRC DocketNos. 50-237 and 50-249

Subject:

Relief Request14R-17,Inservice Inspection Program Relief Request RegardingExamination Coveragefor the FourthInservice Inspection IntervalIn accordancewith 10 CFR 50.55a, "Codes and standards," paragraph (g)(5)(iii), ExelonGeneration Company,LLC (EGC),requests NRC approval of the attached relief requestassociated with the fourth inservice inspection (ISI) interval for Dresden Nuclear Power Station,Units 2 and 3(DNPS).Relief is requested due to the impracticality of satisfying therequirements of the American Society of Mechanical Engineers(ASME)Boiler and PressureVesselCode,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"due to plant design.The fourthISI interval for DNPS endedJanuary 19, 2013.The relief request is based on the limitations that precluded completion of full Code examinationrequirements of ASME Class 1 and 2 welds during the fourth interval. Code examination of thewelds was limited due to the materials of construction and design configurations.The DNPSfourth ten-year ISI program plan met the requirementsof ASME Code,Section XI,1995 Editionwith 1996 Addenda.EGC requests approval ofthese requestsby December 30, 2014.There are no regulatory commitments contained within this letter. Should you have anyquestions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.Exelon GenerationCompany, LLC

Attachment:

Dresden NuclearPowerStation10 CFR 50.55aRequestNo. 14R-17 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I4R-17Relief Requested In Accordancewith 10 CFR50.55a(g)(5)(iii)--inservice Inspection Impracticality-1.ASME Code Component(s) AffectedCode Class:1and 2

References:

IWB-2500, IWC-2500, Table IWB-2500-1,Table IWC-2500-1, ASME Code Case N-460,ASME Code Case N-578-1, Table 1Examination Category:B-A, B-D, B-K, B-M-1, C-B, C-C, R-AItem Number:B1.12, B1.40, B3.90, B3.100, B10.10, B10.20, B12.40,C2.21, C3.20, R1.11, R1.20Description:Limited examination coverageComponent Number:See Tables 1 and 2 below for specific componentidentification2.ApplicableCodeEdition and AddendaThe Inservice Inspection (ISI) Program for the Dresden Nuclear Power Station (DNPS),Units 2 and 3 fourth ISI interval was based on the American Society of MechanicalEngineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, 1995 Edition withthe 1996 Addenda.3.Applicable Code Requirement(s)Table IWB-2500-1, Table IWC-2500-1, and Table 1 of Code Case N-578-1 ExaminationCategories/Item Numbers B-A, B1.12, B1.40, B-D, B3.90, B3.100; B-K, B10.10, B10.20; B-M-1, B12.40; C-B, C-C, C2.21, C3.20; and R-A, R1.11, R1.20 require a volumetric and/orsurface examination, which includes essentially 100% of the weld. Dresden Nuclear PowerStation (DNPS), Units 2 and 3 adopted ASME Code Case N-460, "Alternative ExaminationCoverage for Class 1 and Class 2 Welds,Section XI, Division 1," which defines "essentially100%" as greater than 90% coverage of the examination volume or surface area, asapplicable.4.Impracticality of ComplianceRelief is requested in accordance with 10 CFR 50.55a(g)(5)(iii), on the basis thatconformance with these Code requirements is impractical. Conformance would requireextensive structural modifications to the component structure.DNPS, Units 2 and 3, obtained Construction Permits CPPR-18 and CPPR-22 on January10, 1966, and October 14, 1966, respectively. The piping systems and associatedcomponents were designed and fabricated before the examination requirements of ASMESection XI were formalized and published. Since DNPS, Units 2 and 3 were not specificallyPage 1 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief Requested In Accordancewith 10 CFR50.55a(g)(5)(iii)--lnservice Inspection Impracticality-designed to meet the requirements of ASME Section XI, full compliance is not feasible orpractical within the limits of the current plant design.Physical obstructions imposed by design, geometry, and materials of construction are typicalof vessel appurtenances and sacrificial shield, insulation support rings, structural andcomponent support members, adjacent component weldments in close proximity, uniquecomponent configurations and dissimilar metal weldments.Tables 1 and 2 below indicate the refueling outage in which these welds were examined,and the coverage percentages obtained for those welds that have been examined. Thesetables are cumulative lists of all welds with limited examination coverage during the FourthInterval.Based on the above explanation, DNPS requests relief from the requirement to achievegreater than 90% volume and/or area coverage for the components listed in Tables 1 and 2below, where greater than 90% coverage is impractical.5.Burden Caused by ComplianceCompliance with the examination requirements of ASME Section XI would requiremodification of plant components to remove obstructions, redesigning of plant systems, andreplacement of components where geometry is inherent to component design.6.Proposed Alternativeand Basis for UseProposed AlternativeIn accordance with 10 CFR 50.55a(g)(5)(iii), EGC requests relief from ASME Section XICode requirements on the basis that the required "essentially 100%" coverage examinationis impractical due to physical obstructions and limitations imposed by design, geometry, andmaterials of construction for the components discussed in Tables 1 and 2 below.EGC willcontinue to perform best effort examinations in order to achieve the maximumamount of coverage.Additionally, a VT-2examination performed on the subjectcomponents during system pressure test per examination category B-P each refuelingoutage andcategory C-Heach inspection period is performed.Basis for UseExamination techniques have been progressively upgraded during this interval to augmentthe required Section XI examinations. EGC has used the Electric Power Research Institute(EPRI), the Performance Demonstration Initiative (PDI), Inservice Inspection vendors andother industry sources to encourage the development and provide an awareness ofimproved examination techniques. The goal of these initiatives is to enhance coverage andflaw detection commensurate with radiation dose reduction.Page 2 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and3 10 CFR 50.55a Request Number 14R-17Relief Requested In Accordancewith 10 CFR50.55a(g)(5)(iii)--Inservice Inspection Impracticality-EGC examination procedures are revised on a continuing basis to incorporate proventechniques for a higher level of safety and quality as they become available. Theexaminations and techniques used today exceed the examinations conducted in the past oneach component.All components received as a minimum, the required examination(s) applicable to the extentpractical due to the limited or lack of access available. The examinations conducted,confirmed satisfactory results evidencing no unacceptable flaws present, even though"essentially 100%" coverage was not attained. EGC has concluded that if any activedegradation mechanisms were to exist in the subject welds, those degradations would havebeen identified in the examinations performed.Based on the above, with the vintage of the DNPS, Units 2 and 3 designs, the underlyingobjectives of the code required volumetric and surface examinations have been met. Theexaminations were completed to the extent practical and evidenced no unacceptable flawspresent. Additionally, a VT-2 examination performed on the subject components duringsystem pressure test per examination category B-P each refueling outage and category C-Heach period provides additional assurance that the structural integrity of the subjectcomponents is maintained.7.Duration of Proposed AlternativeRelief is requested for the fourth ten-year inspection interval of the Inservice InspectionProgram for DNPS, Units 2 and 3.8.PrecedentsRelief was granted for the DNPS, Units 2 and 3 third ISI intervals in NRC safety evaluationsdated January 8, 2003, and October 1, 2004.Page 3 of 18 ATTACHMENTDresden NuclearPowerStation, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Table 1: Dresden Nuclear Power Station,Unit 2 FourthInservice Inspection IntervalLimited Coverage Co ponentsComponent IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completed2/1/RPVLONGITUDINALIWB-2500-2examination was limitedSHELL/2-SC1A-WELDVolumetricB1.12D2R2288.0%UTto 88.0% coverage due toVERTproximity of the jet pumpdiffuser.The completed2/1/RPVLONGITUDINALIWB-2500-2examination was limitedSHELL/2-SC1B-WELDVolumetricB1.12D2R2240.2%UTto 40.2% coverage due toVERTproximity of the shroudrepair lower contact.The completed2/1/RPVLONGITUDINALIWB-2500-2examination was limitedSHELL/2-SC1C-WELDVolumetricB1.12D2R2240.2%UTto 40.2% coverage due toVERTproximity of shroud repairlower contact.The completed2/1/RPVexamination was limitedSHELL/2-SC1D-LONGITUDINALIWB-2500-2B112D2R22714%UTto 71.4% coverage due toVERTWELDVolumetric..proximity of jet pumprestrainers and jet pumpdiffuser.The completedexamination was limited2/1/RPVLONGITUDINALIWB-2500-2to 69.0% coverage due toSHELL/2-SC2A-WELDVolumetricB1.12D2R2269.0%UTproximity of the jet pumpVERTriser brace, lowerspecimen and upperspecimen brackets.Page 4 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief Requested In Accordancewith 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completedexamination was limited2/1/RPVLONGITUDINALIWB-2500-2to 78.2% coverage due toSHELU2-SC2B-WELDVolumetricB1.12D2R2278.2%UTproximity of the jet pumpVERTriser brace, lowerspecimen and upperspecimen brackets.The completedexamination was limited2/1/RPVLONGITUDINALIWB-2500-2to 87.0% coverage due toSHELU2-SC2C-WELDVolumetricB1.12D2R2287.0%UTproximity of the jet pumpVERTriser brace, lowerspecimen and upperspecimen brackets.The completed2/1/RPVexamination was limitedSHELU2-SC3A-LONGITUDINALIWB-2500-2B112D2R221%69UTto 69.1% coverage due toVERTWELDVolumetric..proximity of the feedwatersparger and core spraydowncomer piping.The completedexamination was limited2/1/RPVLONGITUDINALIWB-2500-2to 72.9% coverage due toSHELU2-SC3B-WELDVolumetric61.12D2R2272.9%UTproximity of the lowerVERTguide rod, feedwatersparger and core spraypipingPage 5 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and3 10 CFR 50.55aRequest Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completedexamination was limited2/1/RPVto 68.7% coverage due toSHELU2-SC3C-LONGITUDINALIWB-2500-2131.12D2R22a68.7%UTproximity of the shroudVERTWELDVolumetricrepair tie rod, feedwatersparger andcore spraypiping.The completedexamination was limited2/1/RPVSHELU2-SC3D-LONGITUDINALIWB-2500-212131D2R22o73.7%UTto 73.7% coverage due toWELDVolumetric.proximity of the coreVERTspraypipingandfeedwater s ar ers.The completedexaminationwas limited2/1/RPVto 74.2% coverage due toSHELU2-SC3E-LONGITUDINALIWB-2500-2B1.12D2R22o74.2%UTproximity of the upperVERTWELDVolumetricguide rod, core spraypiping and feedwaters ar ers.The completed2/1/RPVexamination was limitedSHELU2-SC4C-LONGITUDINALIWB-2500-281.12D2R2285.7%UTto 85.7% coverage due toVERTWELDVolumetricproximity of the steamdryer support.The completedexaminationwas limited2/1/RPVNOZZLE-IWB-2500-7B390D2R207%4750S60°600 Lto 47.7% coverage due toSHELUN19A-2VESSELVolumetric..,nozzle configuration andinsulation supportinterference.Page 6 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief Requested In Accordancewith 10 CFR50.55a(g)(5)(iii)--inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completedexamination was limited2/1/RPVNOZZLE-IWB-2500-790B3D2R18380%UTto 38.0% coverage due toSHELUN19B-2VESSELVolumetric..nozzle configuration andan insulation supportbracket below the nozzle.UT-60° SThe completed2/1/RPVVESSEL-IWB-2500-7B3.90D2R2127.2%60 °70-Sexamination was limitedSHELUN1A-2NOZZLEVolumetric,Lto 27.2% coverage due tonozzle configuration.The completed2/1/RPVVESSEL-IWB-2500-790B3D2R18260%UTexamination was limitedSHELUNI B-2NOZZLEVolumetric..to 26.0% coverage due tonozzle configuration.The completed2/1/RPVNOZZLE-Section XIB3.90D2R2039.2%UT-60° Lexamination was limitedSHELUN2A-2VESSELto 39.2% coverage due tonozzle configuration.The completed2/1/RPVNOZZLE-IWB-2500-790B3D2R20392%UT-60° Lexamination was limitedSHELUN2B-2VESSELVolumetric..to 39.2% coverage due tonozzle configuration.The completed211/RPVNOZZLE-IWB-2500-790B3D2R18420%UTexamination was limitedSHELUN2C-2VESSELVolumetric..to 42.0% coverage due tonozzle configuration.The completed2/1/RPVNOZZLE-IWB-2500-790B3D2R18420%UTexamination was limitedSHELUN2F-2VESSELVolumetric..to 42.0% coverage due tonozzle configuration.Page 7 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completed2/1/RPVNOZZLE-IWB-2500-7B390D2R18420%UTexamination was limitedSHELUN2H-2VESSELVolumetric..to 42.0% coverage due tonozzle configuration.The completed2/1/RPVVESSEL-IWB-2500-76390D2R22335%UTexamination was limitedSHELUN3D-2NOZZLEVolumetric..to 33.5% coverage due tonozzle configuration.The completedUT-45° S,examination was limited2/1/RPVNOZZLE-IWB-2500-763.90D2R2039.3%60° L, 60°to 39.3% coverage due toSHELUN4A-2VESSELVolumetricSnozzle configuration andinsulation interference.The completedUT-45° S,examination was limited2/1/RPVNOZZLE-IWB-2500-7B3.90D2R2039.3%60° L, 60°to 39.3% coverage due toSHELUN4B-2VESSELVolumetricSnozzle configuration andinsulation interference.The completedUT-45° Sexamination was limited2/1/RPVNOZZLE-IWB-2500-7B3.90D2R2039.3%,60° L, 60°to 39.3% coverage due toSHELUN4C-2VESSELVolumetricSnozzle configuration andinsulation interference.The completed2/1/RPVNOZZLE-IWB-2500-7UT-45° S,examination was limitedB3.90D2R2039.3%60° L, 60°to 39.3% coverage due toSHELUN4D-2VESSELVolumetricSnozzle configuration andinsulation interference.Page 8 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)--inservice Inspection Impracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completedexamination was limited2/1/RPVVESSEL-IWB-2500-7B390D2R22285%UTto 28.5% coverage due toSHELUN5A-2NOZZLEVolumetric..nozzle configuration andproximity of the insulationsupport bracket.The completedexamination was limited2/1/RPVVESSEL-IWB-2500-7B390D2R18310%UTto 31.0% coverage due toSHELUN5B-2NOZZLEVolumetric..the nozzle configurationand a stabilizer lug belowthe nozzle.The completed211/RPVNOZZLE-IWB-2500-7B390D2R18750%UTexamination was limitedSHELUN9-2VESSELVolumetric..to 75.0% coverage due tonozzle configuration.VESSEL-The completed2/1/RPV UPPUPPER TOPIWB-2500-5examination coverageHD/2-THD-FLGHEAD FLANGEVolumetricB1.40D2R2041.7%UTwas limited to 41.7% dueWELDto being single sided dueto flange configuration.The completed2/2/1302A-ISOIWC-2500-4examination coverage12/12-9CONDENSERVolumetricC2.21D2R2250.0%UTwas limited to 50.0% dueNOZZLE WELDto componentconfi uration.The completed2/2/1302B-ISOIWC-2500-4examination coverage12/12-8CONDENSERVolumetricC2.21D2R2250.0%UTwas limited to 50.0% dueNOZZLE WELDto componentconfiguration.Page 9 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief Requested In Accordancewith 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completedISOexaminationcoverage2/2/1303A-8/8-9CONDENSERIWC-2500-4C2.21D2R2250.0%UTwas limited to 50.0% dueNOZZLE WELDVolumetricto componentconfiguration.The completedISOexamination coverage21211303B-8/8-8CONDENSERIWC-2500-4C2.21D2R2250.0%UTwas limited to 50.0% dueNOZZLE WELDVolumetrictocomponentconfiguration.The completed2/1/RPV UPPNOZZLE-IWB-2500-7B390D2R22742%UTexaminationwas limitedHD/N18A-2VESSELVolumetric..to 74.2%coverage due tonozzle configuration.The completedexamination was limited2/1/RPVNOZZLE INSIDEIWB-2500-783.100D2R1886.0%UTto 86.0% coverage due toSHELUN56-1RADIUSVolumetricastabilizer lug below thenozzle.The completed2/1/RPVINTEGRALIWB-2500-13tion was limitedexaminSHELL/M-WELDEDIWB-2500-14B10.10D2R20o56.0%MTato 56.0%coverage due to1175D-1(IWA)ATTACHMENTIWB-2500-15inaccessibility to theSurfacebottom of the lug.The completedexamination was limitedINTEGRALIWB-2500-130to 50.0%coverage due to2/1/1506-16/M-WELDEDIWB-2500-14B10.20D2R2050.0%PTtheinner weld on the1164D-296(IWA)ATTACHMENTIWB-2500-15attachment was notSurfaceaccessible and could notbeprepped.Page 10 of 18 ATTACHMENTDresden Nuclear Power Station,Units2 and 3 10 CFR 50.55a Request Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completed2/1/3001 D-IWB-2500-17examination was limited6/ERV-2-203-VALVE WELDVolumetricB12.40D2P2287.3%VOLto 87.3% coverage due to3D(WELD)integrally welded cage onthe valve ID.The completedexamination was limitedINTEGRALto 81.6% coverage due to2/2/2304-14/M-WELDEDIWC-2500-5C3.20D2P1981.6%MTonly examining three1151 D-10(IWA)ATTACHMENTsides since presence ofpipe clamp preventedexamining fourth side.IWB-2500-8(c)The completed2/1/1001A-IWB-2500-9UT-E-45°examination was limited16/16-11TEE-PIPEIWB-2500-10R1.11D2R19°36.0%60° LSto 36.0% coverage due toIWB-2500-11,weld obstruction andVolumetriccomponent configuration.IWB-2500-8(c)The completed2/1/1001 B-FLANGE-PIPEIWB-2500-9IWB-2500-10R111D2R20850%UT-E-45°examination was limited16/16-2IWB-2500-11..Sto 85.0% coverage due tocomponent configuration.VolumetricIWB-2500-8(c)The completed2/1/1005B-IWB-2500-9UT-E-45°tion was limitedexamin14/14-7VALVE-PIPEIWB-2500-10R1.11D2R2050.0%S, 60 Lato 50.0% coverage due toIWB-2500-11component configuration.VolumetricIWB-2500-8(c)The completed2/1/1403-101W-IWB-2500-9°UT-E-45was limitedexamination103IWB-2500-10R1.20D2R2081.0%L, 45° S,verage due toto 81.0% coverageIWB-2500-11°L60component configuration.VolumetricPage 11 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number I4R-17Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)--Inservice Inspection Impracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeIWB-2500-8(c)°The completed2/1/1404-10/W-IWB-2500-9UT-E-45wasexaminationlimited112VALVE-PIPEIWB-2500-10R1.20D2R2085.0%°S, 45L,°to 85.0% coverage due toIWB-2500-1160Lcomponent configuration.VolumetricTable 2: Dresden Nuclear Power Station, Unit 3 Fourth Inservice Inspection Interval Limited Coverage ComponentsComponent IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completed3/1/RPVLONGITUDINALIWB-2500-2examination coverageSHELL/3-SC1A-81.12D3R22%85.0%UT-45was limited to 85.0% dueVERTWELDVolumetricto proximity of the jetpumpdiffuser.The completed3/1/RPVLONGITUDENALIWB-2500-2UT-45examination coverageSHELU3-SC1B-81.12D3R2239.8%S,UT-70was limitedto 39.8% dueVERTWELDVolumetricRLto proximity of the shroudrepairtie rod.The completed3/1/RPVLONGITUDENALIWB-2500-2UT-45Sexamination coverageSHELU3-SC1C-WELDVolumetric81.12D3R2283.4%-70 RLUTwas limitedto 83.4% dueVERTto proximity of the jetpumpdiffuser.The completed3/1/RPVLONGITUDENALIWB-2500-2UT-45 Sexamination coverageSHELU3-SC2A-WELDVolumetric81.12D3R2275.8%UT-70 RLwas limited to75.8% dueVERTto the tie-rod stabilizerbracket.Page 12 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completed3/1/RPVSHELL/3-SC2C-LONGITUDENALIWB-2500-2B112D3R2284.2%UT-45 Sexamination coveragewas limited to 84.2% dueVERTWELDVolumetric.-70 RLUTto proximity of the corespraypiping.The completedexamination coverage3/1/RPVSHELL/3-SC3A-LONGITUDENALIWB-2500-2B112D3R2222.6%UT-45 Swas limited to 22.6% dueWELDVolumetric.UT-70 RLto proximity of theVERTfeedwater sparger andcore spray downcomer.The completedexamination was limited to3/1/RPVNOZZLE-IWB-2500-2B390D3R20°530%UT-60° L,53.0% coverage due toSHELL/N19A-2VESSELVolumetric..60°Snozzle configuration andinsulation supportinterference.The completedexamination coverage3/1/RPVSHELL/3-SC36-LONGITUDENALIWB-2500-212B1D3R22660%UT-45 Swas limited to 66.0% dueWELDVolumetric..UT-70 RLto proximity of the shroudVERTrepair tie rod and coresprayiinbracket.The completedexamination coverage3/1/RPVLONGITUDENALIWB-2500-2UT-45 Swas limited to 55.7% dueSHELL/3SC3C-WELDVolumetricB1.12D3R2255.7%UT-70 RLto proximity of the coreVERTspray piping, feedwatersparger and specimenbracket.Page 13 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completed3/1/RPVLONGITUDENALIWB-2500-2UT-45 Sexamination coverageSHELU3-SC3D-WELDVolumetric81.12D3R2271.8%UT-70 RLwas limited to 71.8% dueVERTto core spray piping andfeedwater s ar er.The completedexamination coverage3/1/RPVwas limited to 80.2% dueSHELU3-SC46-LONGITUDENALIWB-2500-26112D3R22802%UT-45 Sto proximity of the dryerVERTWELDVolumetric..UT-70 RLbracket and the mismatchbetween the RPV andflange for thisexamination.The completed3/1/RPVNOZZLE-IWB-2500-7UT-45° Sexamination was limited toSHELUNI9B-2VESSELVolumetricB3.90D3R1838.0%,600 L38.0% coverage due tonozzle configuration andan insulation support ring.UT-60° SThe completed3/1/RPVVESSEL-IWB-2500-7B3.90D3R1825.0%,60°700Sexamination was limited toSHELUNIA-2NOZZLEVolumetric,125.0% coverage due toLnozzle configuration.The completed3/1/RPVVESSEL-IWB-2500-7B390D3R20313%UT-60° Sexamination was limited toSHELUN1 B-2NOZZLEVolumetric..70°S31.3% coverage due tonozzle configuration.The completed3/1/RPVNOZZLE-IWB-2500-7B390D3R20°417%UT°-60 Sexamination was limited toSHELUN2B-2VESSELVolumetric..41.7% coverage due tonozzle configuration.Page 14 of 18 ATTACHMENTDresden Nuclear Power Station,Units2 and 3 10 CFR 50.55a Request Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice Inspection Impracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completed3/1/RPVNOZZLE-IWB-2500-7B390D3R18420%UT-60° S,examination was limited toSHELL/N2D-2VESSELVolumetric..60° L42.0% coverage due tonozzle configuration.UT-60° SThe completed3/1/RPVNOZZLE-IWB-2500-7B3.90D3R1842.0%,60 °700Sexamination was limited toSHELL/N2E-2VESSELVolumetric,L42.0% coverage due tonozzle configuration.The completed3/1/RPVNOZZLE-IWB-2500-7B390D3R20°417%SUT-600examination was limited toSHELL/N2G-2VESSELVolumetric..41.7% coverage due tonozzle configuration.The completed3/1/RPVVESSEL-IWB-2500-7B390D3R21310%UT-60° S,examination was limited toSHELL/N3A-2NOZZLEVolumetric..60° L31.0% coverage due tonozzle configuration.The completed3/1/RPVVESSEL-IWB-2500-7B390D3R21310%UT-60° S,examination was limited toSHELL/N3B-2NOZZLEVolumetric..60° L31.0% coverage due tonozzle configuration.The completed3/1/RPVVESSEL-IWB-2500-7UT-60° L,examination was limited toSHELL/N3C-2NOZZLEVolumetricB3.90D3R1835.0%700S,60035.0% coverage due toSnozzle configuration andthermocouples.UT-60° LThe completed3/1/RPVVESSEL-IWB-2500-7B3.90D3R1940.8%60 ,°700Sexamination was limited toSHELL/N3D-2NOZZLEVolumetric,S40.8% coverage due tonozzle configuration.UT-45° SThe completed3/1/RPVVESSEL-IWB-2500-7B3.90D3R2036.3%,60° L60°examination was limited toSHELL/N4A-2NOZZLEVolumetric,36.3% coverage due toISnozzle configuration.Page 15 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeUT-45° SThe completed3/1/RPVVESSEL-IWB-2500-7B3.90D3R2036.3%,60° L60°examination was limited toSHELUN4B-2NOZZLEVolumetric,36.3% coverage due toSnozzle configuration.SUT-450The completedNOZZLE-IWB-2500-7B3.90D3R2036.3%,70°600Sexamination was limited toSHELUN4C-2VESSELVolumetric,LT36.3% coverage due tonozzle configuration.UT-45° SThe completed3/1/RPVNOZZLE-IWB-2500-7B3.90D3R2036.3%,60°600Sexamination was limited toSHELUN4D-2VESSELVolumetric,L36.3% coverage due tonozzle configuration.The completed3/1/RPVVESSEL-IWB-2500-7UT-60° Lexamination was limited toSHELUNSA-2NOZZLEVolumetricB3.90D3R2129.0%,600S29.0% coverage due tothe nozzle configurationand stabilizer bracket.The completed3/1/RPVVESSEL-IWB-2500-7B390D3R18360%UT-60° S,examination was limited toSHELUN5B-2NOZZLEVolumetric..60° L36.0% coverage due tonozzle configuration.The completed3/1/RPVNOZZLE-IWB-2500-7UT-45° Sexamination was limited toSHELUN9-2VESSELVolumetricB3.90D3R1862.0%60° L62.0% coverage due tonozzle configuration andinsulation support ring.VESSEL-UPPERThe completed3/1/RPV UPPTOP HEADIWB-2500-56140D3R19720%UTexamination was limited toHD/3-THD-FLGFLANGE WELDVolumetric..72.0% coverage due toflange configuration.Page 16 of 18 ATTACHMENTDresden Nuclear Power Station, Units2 and 3 10 CFR50.55a Request Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice InspectionImpracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageType-45° SUTThe completed3/1/RPV UPPNOZZLE-IWB-2500-7B3.90D3R1966.6%,60°600Sexamination was limited toHD/N18A-2VESSELVolumetric,L lcoverage due tonozzle configuration.UT-45° SThe completed3/1/RPV UPPVESSEL-IWB-2500-7B3.90D3R1966.6%,60°600Sexamination was limited toHD/N18B-2NOZZLEVolumetric,L66.6% coverage due tonozzle configuration.The completed3/1/RPV UPPVESSEL-IWB-2500-7B390D3R19743%UT-60° S,examination was limited toHD/N8-2NOZZLEVolumetric..60° L74.3% coverage due tonozzle configuration.ISOThe completed3/2/1302A-CONDENSERIWC-2500-4C221D3R20378%UTexamination was limited to12/12-8NOZZLE WELDVolumetric..37.8% coverage due tonozzle configuration.ISOThe completed3/2/1302B-CONDENSERIWC-2500-4C221D3R20378%UTexamination was limited to12/12-9NOZZLE WELDVolumetric..37.8% coverage due tocomponent configuration.ISOThe completed3/2/1303A-8/8-8CONDENSERIWC-2500-4C2.21D3R21500%UTexamination was limited toNOZZLE WELDVolumetric.50.0% coverage due tocomponent configuration,ISOThe completed3/2/1303B-8/8-9CONDENSERIWC-2500-4C2.21D3R21523%UTexamination was limited toNOZZLE WELDVolumetric.52.3% coverage due tocomponent configuration.Page 17 of 18 ATTACHMENTDresden Nuclear Power Station, Units 2 and 3 10 CFR 50.55a Request Number 14R-17Relief RequestedIn Accordance with 10 CFR50.55a(g)(5)(iii)--Inservice Inspection Impracticality-Component IDWeldExamItemOutageActualExamRemarksDescriptionRequirementsNumberExaminedCoverageTypeThe completed3/1/RPVINTEGRALIWB-2500-13examination was limited toSHELUM-WELDEDIWB-2500-14B10.10D3R19600%PT60.0% coverage due to1211 D-1 (IWA)ATTACHMENTIWB-2500-15.being only able toSurfaceexamine three sides of thelug.The completed3/1/0202A-28/M-INTEGRALIWB-2500-13examination was limited to1193D-WELDEDIWB-2500-14B1020D3R18880%PT88.0% coverage due to1002(IWA)ATTACHMENTIWB-2500-15..presence of sway braceSurfacewhich reducedaccessibility.IWB-2500-8(c)The completedIWB-2500-9examination was limited to3/2/320413-VALVE-TEEIWB-2500-10R111D3R21789%UT-E-45°78.9% coverage due to18/18-1IWB-2500-11..Spresence of saddleVolumetricweldment, weld-o-let andvalve configuration.The completed3/1/3001 B-IWB-2500-17examination was limited to6/ERV-3-203-VALVE WELDVolumetric812.40D3P2289.4%VOL89.4% coverage due to3B(WELD)integrally welded cage onvalve ID.IWB-2500-8(c)IWB-2500-9The completed3/1/1302-14/14-FLANGE-PIPEIWB-2500-10R120D3R21500%UT-E-60°examination was limited to9(A)IWB-2500-11..L, 45° S50.0% coverage due toVolumetricHued head configuration.Page 18 of 18

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