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| | number = ML091320639 | | | number = ML091320639 |
| | issue date = 05/12/2009 | | | issue date = 05/12/2009 |
| | title = North Anna, Units 1 and 2 - Reactor Coolant Pressure Boundary Visual Inspections Proposed Alternative - N1-I3-NDE-024 and N2-I3-NDE-025 | | | title = Reactor Coolant Pressure Boundary Visual Inspections Proposed Alternative - N1-I3-NDE-024 and N2-I3-NDE-025 |
| | author name = Hartz L | | | author name = Hartz L |
| | author affiliation = Virginia Electric & Power Co (VEPCO) | | | author affiliation = Virginia Electric & Power Co (VEPCO) |
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| =Text= | | =Text= |
| {{#Wiki_filter:SerialNo.09-253 NL&OS/ETS RODocketNos.50-338 50-339LicenseNos.NPF-4 NPF-710CFR50.55a VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261May12,2009U.S.NuclearRegulatoryCommissionAttention:DocumentControlDeskWashington,D.C.20555 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) | | {{#Wiki_filter:10 CFR 50.55a VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 12, 2009 U.S. Nuclear Regulatory Commission Serial No. 09-253 Attention: Document Control Desk NL&OS/ETS RO Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) |
| NORTH ANNA POWER STATION UNITS1AND2 REACTOR COOLANT PRESSURE BOUNDARY VISUAL INSPECTIONS PROPOSED ALTERNATIVE-N1-13-NDE-024ANDN2-13-NDE-025Pursuantto10CFR50.55a(a)(3)(i),Dominionrequestsapprovalofanalternativetotheinspectionrequirementsoffootnote1includedin10 CFR50.55a(g)(6)(ii)(E), ReactorCoolantPressure BoundaryVisualInspections,forNorthAnnaUnits1and2.TherequestedalternativewillpermittheinspectionsperformedduringtheUnit1fall2007andUnit2fall2008refuelingoutagesonthebottommounted instrumenttubes(8MI)tobeusedastheinitialreactorcoolantpressureboundaryvisualinspectioninplaceofthefootnoterequirementfortheinitialinspectiontobeperformedatthenextrefuelingoutageafterJanuary 1,2009.Alternatives N1-13-NDE-024andN2-13-NDE-025areincludedintheattachmenttothisletteraswellasthebasisforthealternative.The8MIinspectionsperformedduringthefall2007and2008refuelingoutagesforNorthAnnaUnits1and2,respectively,conformedtotherequirementsofCodeCaseN-722andmettherequirementsof10CFR50.55a(g)(6)(ii)(E).Therefore,Dominionconsidersthevisualexaminationsperformedduringthefall2007refuelingoutageforNAPSUnit1andfall2008refuelingoutageforNAPSUnit2toprovideanacceptablelevelofqualityandsafetyasanalternativetoperformingtheinitialinspectionsinthenextrefuelingoutageafterJanuary 1,2009,asindicatedin10CFR50.55a(g)(6)(ii)(E).Ifyoushouldhaveanyquestionsregardingthissubmittal,pleasecontactMr.ThomasShaubat(804)273-2763. | | NORTH ANNA POWER STATION UNITS 1 AND 2 REACTOR COOLANT PRESSURE BOUNDARY VISUAL INSPECTIONS PROPOSED ALTERNATIVE - N1-13-NDE-024 AND N2-13-NDE-025 Pursuant to 10 CFR 50.55a(a)(3)(i), Dominion requests approval of an alternative to the inspection requirements of footnote 1 included in 10 CFR50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Visual Inspections, for North Anna Units 1 and 2. The requested alternative will permit the inspections performed during the Unit 1 fall 2007 and Unit 2 fall 2008 refueling outages on the bottom mounted instrument tubes (8MI) to be used as the initial reactor coolant pressure boundary visual inspection in place of the footnote requirement for the initial inspection to be performed at the next refueling outage after January 1,2009. Alternatives N1-13-NDE-024 and N2-13-NDE-025 are included in the attachment to this letter as well as the basis for the alternative. |
| Sincerely,LeslieHartzVicePresident-NuclearSupportServices | | The 8MI inspections performed during the fall 2007 and 2008 refueling outages for North Anna Units 1 and 2, respectively, conformed to the requirements of Code Case N-722 and met the requirements of 10 CFR50.55a(g)(6)(ii)(E). Therefore, Dominion considers the visual examinations performed during the fall 2007 refueling outage for NAPS Unit 1 and fall 2008 refueling outage for NAPS Unit 2 to provide an acceptable level of quality and safety as an alternative to performing the initial inspections in the next refueling outage after January 1,2009, as indicated in 10 CFR 50.55a(g)(6)(ii)(E). |
| | If you should have any questions regarding this submittal, please contact Mr. Thomas Shaub at (804) 273-2763. |
| | Sincerely, |
| | ~~ci Leslie Hartz Vice President - Nuclear Support Services |
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| ==Attachment:== | | ==Attachment:== |
| ProposedAlternatives-N1-13-NDE-024 and N2-13-NDE-025Commitmentsmadeinthisletter:None cc:U.S.NuclearRegulatoryCommissionRegionIISamNunnAtlantaFederalCenter 61ForsythStreet,SWSuite23T85 Atlanta, Georgia 30303Mr.J.E.Reasor,Jr.OldDominionElectricCooperative InnsbrookCorporateCenter4201DominionBlvd.Suite300GlenAllen,Virginia23060 NRC SeniorResidentInspectorNorthAnnaPowerStationMs.D.N.WrightNRCProject ManagerU.S.NuclearRegulatoryCommissionOneWhiteFlintNorthMailStop 0-8 H4A11555RockvillePikeRockville,Maryland20852Mr.J.F.Stang,Jr.NRCProject ManagerU.S.NuclearRegulatoryCommissionOneWhiteFlintNorthMaiIStop 0-8 G9A11555RockvillePikeRockville,Maryland20852SerialNo.09-253 Docket Nos.50-338/339 AlternativeforBMI Baseline Inspections Page 2 of 2 SerialNo.09-253DocketNos.
| | Proposed Alternatives - N1-13-NDE-024 and N2-13-NDE-025 Commitments made in this letter: None |
| 50-338/339 ATTACHMENT REACTOR COOLANT PRESSURE BOUNDARY VISUAL INSPECTIONS PROPOSED ALTERNATIVEN1-13-NDE-024andN2-13-NDE-025 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
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| NORTH ANNA POWER STATION UNITS1AND2 10CFR50.55aRequestNumber N1-13-NDE-024/N2-13-NDE-025 AlternativeBMIVisual Examinations Requirement Proposed Alternative in Accordance with10CFR 50.55a(a)(3)(i)
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| **Alternative Provides AcceptableLevelof QualityorSafety--1.0ASMECodeComponentsAffectedCodecomponentsassociatedwiththisrequestareClass1ReactorPressureVessel(RPV)bottom-mountedinstrumentpenetrations(BMI)havingpressureretainingpartialorfullpenetrationweldsincomponentsfabricatedwithAlloy600/82/182material.
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| 1.1CategoryandSystemDetails:CodeClass:
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| System:ExaminationCategory:ItemNumber:Class1ReactorPressureVessel B-P B15.801.2ComponentDescriptions:ReactorVessel-RPVbottom-mountedinstrumentpenetrations 2.0ApplicableCodeEditionAndAddendaNorthAnnaPowerStationUnits1and2arecompletingtheirthird10-yearlSIIntervals.Unit1'sthirdintervalbeganonMay1,1999andendsonApril30,2009andUnit2'sthirdintervalbeganonDecember14, 2001andendsonDecember13,2010.TheASMEBoilerandPressureVesselCode(ASMECode)ofrecordfortheapplicableintervalisthe1989EditionforUnit1andthe1995Edition,1996AddendaforUnit2.
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| 3.0ApplicableCodeRequirements10CFR50.55a(g)(6)(ii)(E),Reactorcoolantpressureboundaryvisual inspections,wasrecentlyincorporatedintothe10CFR50.55a.Thenewregulationsaugmentedtheinserviceinspectionrequirements(effectivedate October 10,2008).Specifically,10CFR50.55a(g)(6)(ii)(E)requiresthat"AlllicenseesofpressurizedwaterreactorsshallaugmenttheirinserviceinspectionprogrambyimplementingASMECodeCaseN-722subjecttotheconditionsspecifiedin10CFR50.55a(g)(6)(ii)(E)(2)through(4)ofthissection.TheinspectionrequirementsofASMECodeCaseN-722donotapplytocomponentswithpressureretainingweldsfabricatedwithAlloy600/82/182materialsthathavebeenmitigatedbyweldoverlayorstressimprovement."Page1of4 10CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative 8MI Visual Examinations Requirement In addition, footnoteoneto10CFR 50.55a(g)(6)(ii)(E) statesinpart:"For inspectionstobe conductedeveryrefuelingoutageand inspections conducted every otherrefuelingoutage,theinitial inspectionshallbe performedatthenext refueling outage after January1,2009." 4.0ReasonFor Request North AnnaPowerStation(NAPS)Unit1andUnit2 completedbaremetalvisual examinationofRPV bottom-mounted instrument penetrations priortothe"initial inspection" indicatedby10CFR 50.55a(g)(6)(ii)(E), which became effective October10,2008.NAPSUnit1 inspections were performed duringthefall2007 refuelingoutage,andNAPSUnit2 inspections were performed duringthefall2008refuelingoutage.Thesebaremetalvisual inspectionsmetthe intent ofASMECodeCaseN-722.
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| CodeCaseN-722,"Additional ExaminationsforPWR Pressure Retaining WeldsinClass1 ComponentsFabricatedwithAlloy 600/82/182 Material," establishes additional requirementstothe examination requirements of TableIWB-2500-1for pressurized waterreactorplantshavingpartialorfull penetration welds in Class 1 components fabricatedwithAlloy 600/82/182 material.For ReactorVesselItem NumberB15.80,RPV bottom-mounted instrument penetrations, all penetrationsrequireVisual Examination(VE)tothe requirementsofIWB-3522,everyotherrefuelingoutage.ASMECodeCaseN-722 includes specific requirementsfortheVEandthe qualification of personnel performingtheVE:(3)TheVisual Examination (VE)performedonAlloy 600/82/182 components for evidence of pressure boundary leakage and corrosion on adjacentferriticsteel components shall consistofthe following:(a)A directVEofthe bare-metal surface performedwiththe insulation removed.Alternatively,theVEmaybe performed with insulation inplaceusingremotevisual inspection equipment that provides resolutionofthe component metal surface equivalenttoa metal direct VE.(b)TheVEmaybe performedwhenthesystemor component is depressurized.(c)The directVEshallbe performedata distance not greaterthan4 ft(1.2m)fromthe componentandwitha demonstrated illumination level sufficienttoallowresolutionof lower case charactershavinga heightofnot greaterthan0.105in(2.7mm).
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| (4)Personnel performingtheVEshallbe qualifiedasVT-2visual examinersandshallhave completed a minimumoffour (4)hours of additionaltrainingin detection of borated water leakage from Alloy 600/82/182 componentsandtheresultingboricacid corrosion of adjacentferriticsteel components.
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| Page 2of4 10CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative 8MI Visual Examinations RequirementThebottom-mountedRPVinstrumentpenetrationsexaminationsduringthefall2007andfall2008refuelingoutageswereperformedtotheenhancedVisualExamination(VE)requirementsandthepersonneltrainingandqualificationrequirementsasdescribedinEnclosure1,"ExaminerQualificationandResolutionsRequirements."5.0ProposedAlternativesAndBasisForUseVirginiaElectricandPowerCompany(Dominion)considersthevisualexaminationsperformedduringthefall2007refuelingoutageforNAPSUnit1andfall2008refuelingoutageforNAPSUnit2toprovideanacceptablelevelofqualityandsafetyasanalternativetoperformingtheinitialinspectionsinthenextrefuelingoutageafterJanuary1,2009,asindicatedin10CFR50.55a(g)(6)(ii)(E).Therefore,theinspectionperformedduringthefall2007refuelingoutageforNAPSUnit1andfall2008refuelingoutageforNAPSUnit2canbeconsideredtheinitialinspectionstomeetthe10CFR50.55a(g)(6)(ii)(E)footnoterequirementsfortheperformanceoftheinitialinspection.InaccordancewithASMECodeCaseN-722,thebottom-mountedRPVinstrumentpenetrationexaminationsarerequiredtobeperformedatleasteveryotherrefuelingoutage.Therefore,thenextexaminationsofItemNo.B15.80components(bottom-mountedRPVinstrumentpenetration)willbeperformednolaterthanthefall2010refuelingoutageforUnit1andnolaterthanthefall 2011refuelingoutageforUnit2.Dominionrequestsapprovalofthisalternativepursuanttotheprovisionsof10CFR50.55a(a)(3)(i).
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| 6.0DurationOfProposedAlternativeTheproposedalternativetothe10CFR50.55a(g)(6)(ii)(E)requirementsisapplicablefortheremainderofthethird10-yearinserviceinspection(lSI)intervalatNAPSUnits1and2.
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| ==7.0 Precedents== | | Serial No. 09-253 Docket Nos. 50-338/339 Alternative for BMI Baseline Inspections Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. J. E. Reasor, Jr. |
| None 8.0 References None9.0Enclosures(1)ExaminerQualificationandResolutionRequirements Page3of4 10CFR 50.55a Request Number N1*13*NDE*024/N2*13*NDE*025 AlternativeBMIVisual Examinations Requirement ENCLOSURE 1ExaminerQualificationsandResolutionRequirementsThisenclosuredocumentsacomparisonofthebaremetalvisualexaminationsperformedonthereactorpressurevesselbottommountedinstrumentation(BMI)nozzlesatNorthAnnaPowerStationUnits1 | | Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd. |
| &2performedduringpreviousoutages (N1R19andN2R19)withthenewrequirementsofCodeCaseN-722.Twoareasrelatedtoexaminationequivalencywererequiredtobeaddressed;personnelqualificationsandresolutionrequirements. | | Suite 300 Glen Allen, Virginia 23060 NRC Senior Resident Inspector North Anna Power Station Ms. D. N. Wright NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 H4A 11555 Rockville Pike Rockville, Maryland 20852 Mr. J. F. Stang, Jr. |
| Personnel QualificationsTheexaminersthatperformedtheseexaminationsheldcurrentVT-2(non-alternative)andVT-3qualifications.Inaddition,eachoftheexaminershadsuccessfullytakentheDominionBoricAcidCorrosionControl(BACC)Inspectortraining.TheinspectionteamincludedatleastoneVTexaminerthathasalsocompletedtheDominionBACCEvaluatortrainingandqualificationrequirements.TheexaminersthatperformedthesebaremetalvisualexaminationsmettherequirementsofCodeCaseN-722asVT-2qualifiedexaminerswithanadditionalfourhoursoftrainingaddressingthedetectionofboratedwaterleakagefromAlloy600/82/182componentsandtheresultingboricacidcorrosionofadjacentferriticsteel components.Basedupontheadditionaltrainingofthevisualexaminers;thebaremetalvisualexaminationsoftheBMInozzlepenetrationsperformedduringthe N1R19andN2R19outagesareconsideredequivalenttothepersonnelqualificationrequirementsofCodeCaseN-722. | | NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North MaiI Stop 0-8 G9A 11555 Rockville Pike Rockville, Maryland 20852 |
| Resolution RequirementsThepreviousbaremetalvisualexaminationswereperformedusinga(VT-2)examinationtechniqueandrequiredeachpenetrationtobeexaminedforevidenceofleakagefor360degreesaroundeachnozzle.ThebaremetalvisualexaminationsweredocumentedintheapplicableEngineeringPeriodicTestProcedure.Theseperiodictestproceduresspecifytheuseofinspectionequipmenttobeusedfortheinspection,whichconsistsofamirror,portablelights,andavisualtestingexaminationresolutioncard.AccesstotheBMInozzlesforthebaremetalvisualexaminationisthroughremovableinsulationpanels.ThebaremetalvisualexaminationsoftheBMInozzleswereperformedinaccordancewiththedirectvisualexaminationrequirementsofwithin4feetandsufficientilluminationtoresolve0.105incheslowercasecharacters.BasedupontheaccessfortheexaminertoperformthebaremetalvisualexaminationsoftheBMInozzlepenetrations,theequipmentusedtoperformtheexamination(mirror,flashlight,0.105incheslowcasecharacterresolutioncard),thepreviouslyperformedbaremetalvisualexaminationsoftheBMInozzlepenetrationareconsideredequivalenttotheresolutionrequirementsofCodeCaseN-722.Page4 of 4}} | | |
| | Serial No. 09-253 Docket Nos. 50-338/339 ATTACHMENT REACTOR COOLANT PRESSURE BOUNDARY VISUAL INSPECTIONS PROPOSED ALTERNATIVE N1-13-NDE-024 and N2-13-NDE-025 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION) |
| | NORTH ANNA POWER STATION UNITS 1 AND 2 |
| | |
| | 10 CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative BMI Visual Examinations Requirement Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i) |
| | ** Alternative Provides Acceptable Level of Quality or Safety -- |
| | |
| | ===1.0 ASME Code Components Affected=== |
| | Code components associated with this request are Class 1 Reactor Pressure Vessel (RPV) bottom-mounted instrument penetrations (BMI) having pressure retaining partial or full penetration welds in components fabricated with Alloy 600/82/182 material. |
| | 1.1 Category and System Details: |
| | Code Class: Class 1 System: Reactor Pressure Vessel Examination Category: B-P Item Number: B15.80 1.2 Component Descriptions: |
| | Reactor Vessel - RPV bottom-mounted instrument penetrations 2.0 Applicable Code Edition And Addenda North Anna Power Station Units 1 and 2 are completing their third 10-year lSI Intervals. Unit 1's third interval began on May 1, 1999 and ends on April 30, 2009 and Unit 2's third interval began on December 14, 2001 and ends on December 13, 2010. The ASME Boiler and Pressure Vessel Code (ASME Code) of record for the applicable interval is the 1989 Edition for Unit 1 and the 1995 Edition, 1996 Addenda for Unit 2. |
| | 3.0 Applicable Code Requirements 10 CFR 50.55a(g)(6)(ii)(E), Reactor coolant pressure boundary visual inspections, was recently incorporated into the 10 CFR 50.55a. The new regulations augmented the inservice inspection requirements (effective date October 10,2008). |
| | Specifically, 10 CFR 50.55a(g)(6)(ii)(E) requires that "Alllicensees of pressurized water reactors shall augment their inservice inspection program by implementing ASME Code Case N-722 subject to the conditions specified in 10 CFR 50.55a(g)(6)(ii)(E)(2) through (4) of this section. The inspection requirements of ASME Code Case N-722 do not apply to components with pressure retaining welds fabricated with Alloy 600/82/182 materials that have been mitigated by weld overlay or stress improvement." |
| | Page 1 of 4 |
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| | 10 CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative 8MI Visual Examinations Requirement In addition, footnote one to 10 CFR 50.55a(g)(6)(ii)(E) states in part: "For inspections to be conducted every refueling outage and inspections conducted every other refueling outage, the initial inspection shall be performed at the next refueling outage after January 1, 2009." |
| | 4.0 Reason For Request North Anna Power Station (NAPS) Unit 1 and Unit 2 completed bare metal visual examination of RPV bottom-mounted instrument penetrations prior to the "initial inspection" indicated by 10 CFR 50.55a(g)(6)(ii)(E), which became effective October 10, 2008. NAPS Unit 1 inspections were performed during the fall 2007 refueling outage, and NAPS Unit 2 inspections were performed during the fall 2008 refueling outage. These bare metal visual inspections met the intent of ASME Code Case N-722. |
| | Code Case N-722, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Material," establishes additional requirements to the examination requirements of Table IWB-2500-1 for pressurized water reactor plants having partial or full penetration welds in Class 1 components fabricated with Alloy 600/82/182 material. |
| | For Reactor Vessel Item Number B15.80, RPV bottom-mounted instrument penetrations, all penetrations require Visual Examination (VE) to the requirements of IWB-3522, every other refueling outage. |
| | ASME Code Case N-722 includes specific requirements for the VE and the qualification of personnel performing the VE: |
| | (3) The Visual Examination (VE) performed on Alloy 600/82/182 components for evidence of pressure boundary leakage and corrosion on adjacent ferritic steel components shall consist of the following: |
| | (a) A direct VE of the bare-metal surface performed with the insulation removed. Alternatively, the VE may be performed with insulation in place using remote visual inspection equipment that provides resolution of the component metal surface equivalent to a bare-metal direct VE. |
| | (b) The VE may be performed when the system or component is depressurized. |
| | (c) The direct VE shall be performed at a distance not greater than 4 ft (1.2 m) from the component and with a demonstrated illumination level sufficient to allow resolution of lower case characters having a height of not greater than 0.105 in (2.7 mm). |
| | (4) Personnel performing the VE shall be qualified as VT-2 visual examiners and shall have completed a minimum of four (4) hours of additional training in detection of borated water leakage from Alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components. |
| | Page 2 of 4 |
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| | 10 CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative 8MI Visual Examinations Requirement The bottom-mounted RPV instrument penetrations examinations during the fall 2007 and fall 2008 refueling outages were performed to the enhanced Visual Examination (VE) requirements and the personnel training and qualification requirements as described in Enclosure 1, "Examiner Qualification and Resolutions Requirements." |
| | 5.0 Proposed Alternatives And Basis For Use Virginia Electric and Power Company (Dominion) considers the visual examinations performed during the fall 2007 refueling outage for NAPS Unit 1 and fall 2008 refueling outage for NAPS Unit 2 to provide an acceptable level of quality and safety as an alternative to performing the initial inspections in the next refueling outage after January 1, 2009, as indicated in 10 CFR 50.55a(g)(6)(ii)(E). Therefore, the inspection performed during the fall 2007 refueling outage for NAPS Unit 1 and fall 2008 refueling outage for NAPS Unit 2 can be considered the initial inspections to meet the 10 CFR 50.55a(g)(6)(ii)(E) footnote requirements for the performance of the initial inspection. |
| | In accordance with ASME Code Case N-722, the bottom-mounted RPV instrument penetration examinations are required to be performed at least every other refueling outage. Therefore, the next examinations of Item No. B15.80 components (bottom-mounted RPV instrument penetration) will be performed no later than the fall 2010 refueling outage for Unit 1 and no later than the fall 2011 refueling outage for Unit 2. Dominion requests approval of this alternative pursuant to the provisions of 10 CFR 50.55a(a)(3)(i). |
| | 6.0 Duration Of Proposed Alternative The proposed alternative to the 10 CFR 50.55a(g)(6)(ii)(E) requirements is applicable for the remainder of the third 10-year inservice inspection (lSI) interval at NAPS Units 1 and 2. |
| | 7.0 Precedents None 8.0 References None 9.0 Enclosures (1) Examiner Qualification and Resolution Requirements Page 3 of 4 |
| | |
| | 10 CFR 50.55a Request Number N1*13*NDE*024/N2*13*NDE*025 Alternative BMI Visual Examinations Requirement ENCLOSURE 1 Examiner Qualifications and Resolution Requirements This enclosure documents a comparison of the bare metal visual examinations performed on the reactor pressure vessel bottom mounted instrumentation (BMI) nozzles at North Anna Power Station Units 1 & 2 performed during previous outages (N1 R19 and N2R19) with the new requirements of Code Case N-722. Two areas related to examination equivalency were required to be addressed; personnel qualifications and resolution requirements. |
| | Personnel Qualifications The examiners that performed these examinations held current VT-2 (non-alternative) and VT-3 qualifications. In addition, each of the examiners had successfully taken the Dominion Boric Acid Corrosion Control (BACC) Inspector training. The inspection team included at least one VT examiner that has also completed the Dominion BACC Evaluator training and qualification requirements. |
| | The examiners that performed these bare metal visual examinations met the requirements of Code Case N-722 as VT-2 qualified examiners with an additional four hours of training addressing the detection of borated water leakage from Alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components. |
| | Based upon the additional training of the visual examiners; the bare metal visual examinations of the BMI nozzle penetrations performed during the N1 R19 and N2R19 outages are considered equivalent to the personnel qualification requirements of Code Case N-722. |
| | Resolution Requirements The previous bare metal visual examinations were performed using a (VT-2) examination technique and required each penetration to be examined for evidence of leakage for 360 degrees around each nozzle. The bare metal visual examinations were documented in the applicable Engineering Periodic Test Procedure. These periodic test procedures specify the use of inspection equipment to be used for the inspection, which consists of a mirror, portable lights, and a visual testing examination resolution card. |
| | Access to the BMI nozzles for the bare metal visual examination is through removable insulation panels. The bare metal visual examinations of the BMI nozzles were performed in accordance with the direct visual examination requirements of within 4 feet and sufficient illumination to resolve 0.105 inches lower case characters. |
| | Based upon the access for the examiner to perform the bare metal visual examinations of the BMI nozzle penetrations, the equipment used to perform the examination (mirror, flashlight, 0.105 inches low case character resolution card), the previously performed bare metal visual examinations of the BMI nozzle penetration are considered equivalent to the resolution requirements of Code Case N-722. |
| | Page 4 of 4}} |
Letter Sequence Request |
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MONTHYEARML0913206392009-05-12012 May 2009
Reactor Coolant Pressure Boundary Visual Inspections Proposed Alternative - N1-I3-NDE-024 and N2-I3-NDE-025
Project stage: Request
ML0916204232009-06-11011 June 2009
Unit 2, N1-13-NDE-024 and N2-13-NDE-025: Acceptance of Requested Licensing Action Relief Request-Reactor Coolant Pressure Boundary Visual Inspection
Project stage: Acceptance Review
ML0923706462009-08-24024 August 2009
Response to Request for Additional Information Reactor Coolant Pressure Boundary Visual Inspections Proposed Alternative - N1-I3-nde-024 and N2-I3-NDE-025
Project stage: Response to RAI
ML0927902102009-10-0909 October 2009
Third 10-Year Interval Inservice Inspection Program, Reactor Coolant Pressure Boundary Visual Inspections - N1-I3-NDE-024 and N2-I3-NDE-025
Project stage: Other
2009-05-12
[Table View] |
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Category:Letter
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Letter to Russell Townsend, Thpo, Eastern Band of Cherokee Indians
ML24003A8402024-01-0909 January 2024
Letter to Katelyn Lucas, Thpo, Delaware Nation, Oklahoma, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal
ML24003A8452024-01-0909 January 2024
Letter to Stephen Adkins, Chief, Chickahominy Indian Tribe, Notice of Availability of Draft Site-Specific Environmental Impact Statement for North Anna Power Station Units 1 and 2, Subsequent License Renewal
ML23332A1852024-01-0404 January 2024
Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal
ML23332A0872024-01-0404 January 2024
Notice of Availability of the Draft Site-Specific Environmental Impact Statement for the North Anna Power Station, Units 1 and 2, Subsequent License Renewal
ML23360A6352024-01-0404 January 2024
Letter to Dominion Availability for North Anna Units 1 and 2 Draft Site Specific Environmental Impact Statement
ML23332A1472023-12-21021 December 2023
Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the North Anna Power Station, Units 1 and 2, Subsequent License Renewal Application
ML23283A3052023-12-20020 December 2023
Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary)
ML23346A0972023-12-11011 December 2023
License Amendment Request to Revise the Emergency Plan Relocation of the Technical Support Center - Response to NRC Request for Additional Information
ML23346A1022023-12-11011 December 2023
2024 North Anna Power Station Brq Inspection Notification Letter
ML24012A0942023-12-0707 December 2023
GL Report from Dominion Virginia Power Regarding Transfer of Devices
ML24012A0892023-12-0707 December 2023
GL Registration from Dominion Virginia Power
ML23334A2432023-11-30030 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23362A0602023-11-29029 November 2023
ISFSI, Submittal of Cask Registration for Spent Fuel Storage
IR 05000339/20234022023-11-27027 November 2023
Security Baseline Inspection Report 05000338 and 05000339/2023402
IR 05000338/20230032023-11-13013 November 2023
Integrated Inspection Report 05000338/2023003 and 05000339/2023003
ML23311A2042023-10-0909 October 2023
Annual Submittal of Technical Specification Bases Changes Pursuant to Technical Specification 5.5.13.d
IR 05000338/20234032023-10-0505 October 2023
Reissue - North Anna Power Station - Cyber Security Inspection Report 05000338/2023403 and 05000339/2023403 (Cover Letter)
ML23279A0612023-10-0505 October 2023
Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs)
ML23230A0502023-10-0202 October 2023
5 of the Quality Assurance Topical Report - Review of Program Changes
ML23275A0992023-09-28028 September 2023
Subsequent License Renewal Application Third 10 CFR 54.21(b) Annual Amendment
IR 05000338/20230112023-09-26026 September 2023
Quadrennial Focused Engineering Inspection Commercial Grade Dedication Report 05000338/2023011 and 05000339/2023011
ML23242A3482023-09-11011 September 2023
Cyber Security Inspection Report 05000338/2023403 and 05000339/2023403 - Cover
ML23254A0242023-09-0606 September 2023
Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs)
ML23249A2592023-09-0606 September 2023
Core Operating Limits Report Cycle 30, Pattern Ukr, Revision 0
ML23214A2022023-09-0505 September 2023
Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information
2024-02-01
[Table view]
Category:Report
MONTHYEARML24032A1112024-02-0101 February 2024
Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval
ML24032A4662024-01-16016 January 2024
Response to Comments on Draft Vpdes Permit No. VA0052451
ML23214A1942023-09-0505 September 2023
Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information - Report
ML23103A2282023-04-12012 April 2023
Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code
ML22353A6202022-12-19019 December 2022
Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code
ML22255A0102022-06-28028 June 2022
Owner'S Activity Report
ML22263A2852022-05-23023 May 2022
Alert and Notification System Evaluation Report_Ans Evaluation_Redacted Page 1-65
ML22119A1722022-04-13013 April 2022
Post-Accident Monitoring (PAM) Report
ML21333A2842021-11-29029 November 2021
Requal Notification Letter
ML21175A2472021-06-24024 June 2021
2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....-
ML21036A0772021-02-23023 February 2021
Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2019 Refueling Outage
ML21042B3212021-02-11011 February 2021
Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code
ML20254A3472020-09-0808 September 2020
Supplement to Operator License Examination Comments
ML20247J6162020-09-0303 September 2020
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20246G7062020-08-24024 August 2020
Enclosure 4: Attachment 1 - PWROG-18005-NP, Revision 2, Determination of Unirradiated Rt and Upper-Shelf Values of the North Anna Units 1 and 2 Reactor Vessel Materials
ML20203M1602020-07-20020 July 2020
VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status
ML20149K6712020-05-31031 May 2020
PWROG-19047-NP, Revision 0, North Anna, Units 1 and 2, Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis
ML20140A2392020-05-18018 May 2020
ASME Section XI Inservicee Inspection Program Proposed Inservice Inspection Alternative N1-15-NDE-002
ML20246G7012020-03-31031 March 2020
Enclosure 4: Attachment 3 - WCAP-18364-NP, Rev. 1, North Anna Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity for Subsequent License Renewal (SLR)
ML20090B3972020-03-26026 March 2020
Revised License Renewal Commitment Pressurizer Surge Line Weld Inspection Frequency
ML20246G7072020-01-31031 January 2020
Enclosure 4: Attachment 4 - WCAP-11164-NP, Rev. 2, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for North Anna Units 1 and 2 Nuclear Power Plants for the Subsequent License Renewal
ML19347A4212019-11-26026 November 2019
Owner'S Activity Report
ML19249B7742019-08-29029 August 2019
Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated)
ML19249B7682019-08-29029 August 2019
Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated)
ML19249B7782019-08-29029 August 2019
Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1
ML19249B7722019-08-29029 August 2019
Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated)
ML19106A3562019-04-23023 April 2019
Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2018 Refueling Outage
ML19011A1722019-01-0404 January 2019
Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up)
ML19011A1732019-01-0404 January 2019
Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents
ML19011A1742019-01-0404 January 2019
Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents
ML20246G7092018-10-31031 October 2018
Enclosure 4: Attachment 2 - WCAP-18353-NP, Rev. 0, Reactor Internals Fluence Evaluation for a Westinghouse 3-Loop Plant with Two Units - Subsequent License Renewal
ML18198A1192018-05-31031 May 2018
Attachment 5 to 18-233, ANP-3467NP, Rev. 0, North Anna Fuel-Vendor Independent Small Break LOCA Analysis Licensing Report
ML17186A0842017-06-29029 June 2017
Flooding Focused Evaluation Summary
ML16187A3232016-06-24024 June 2016
Submittal of Owner'S Activity Report (Form OAR-1), for Refueling Outage N2R24
ML15253A4102016-03-11011 March 2016
Enclosure 2 Screening Analysis Report
ML15238A8442015-09-25025 September 2015
Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation
ML15259A3422015-08-24024 August 2015
10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al
ML15232A8112015-08-24024 August 2015
Evaluation of Information Related to Commitments 6 and 8 from Confirmatory Action Letter No. NRR-2011-002
ML15238B5922015-08-17017 August 2015
Review of Commitment Action Completion Confirmation Action Letter Regarding Earthquake in 2011
ML15175A1902015-06-17017 June 2015
Owner'S Activity Report
ML15057A2492015-04-20020 April 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1
ML15058A0342015-02-23023 February 2015
Summary of Facility Changes, Tests and Experiments
ML14133A0112014-05-0707 May 2014
March 12, 2012 Information Request Phase 2 Staffing Assessment Report
ML14092A4162014-03-31031 March 2014
Response to March 12, 2012 Information Request Seismic Hazard and Screening Report (CEUS Sites)For Recommendation 2.1
ML14080A0022014-03-31031 March 2014
PNNL-22553, Final Assessment of Manual Ultrasonic Examinations Applied to Detect Flaws in Primary System Dissimilar Metal Welds at North Anna Power Station.
ML14084A3272014-03-27027 March 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14084A2122014-03-27027 March 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14283A0462014-02-28028 February 2014
MRP-375, Technical Basis for Reexamination Interval Extension for Alloy 690 PWR Reactor Vessel Top Head Penetration Nozzles (EPRI 3002002441), Attachment 1
ML13338A4482014-01-29029 January 2014
Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14006A1712014-01-23023 January 2014
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for North Anna Power Station, Units 1 and 2, TAC Nos.: MF0998 and MF0999
2024-02-01
[Table view]
Category:Miscellaneous
MONTHYEARML24032A1112024-02-0101 February 2024
Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval
ML22353A6202022-12-19019 December 2022
Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code
ML22255A0102022-06-28028 June 2022
Owner'S Activity Report
ML21333A2842021-11-29029 November 2021
Requal Notification Letter
ML21036A0772021-02-23023 February 2021
Review of Steam Generator Tube Inspection Report for the Cycle 26 Spring 2019 Refueling Outage
ML20254A3472020-09-0808 September 2020
Supplement to Operator License Examination Comments
ML20247J6162020-09-0303 September 2020
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML19347A4212019-11-26026 November 2019
Owner'S Activity Report
ML17186A0842017-06-29029 June 2017
Flooding Focused Evaluation Summary
ML16187A3232016-06-24024 June 2016
Submittal of Owner'S Activity Report (Form OAR-1), for Refueling Outage N2R24
ML15253A4102016-03-11011 March 2016
Enclosure 2 Screening Analysis Report
ML15238A8442015-09-25025 September 2015
Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation
ML15259A3422015-08-24024 August 2015
10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al
ML15232A8112015-08-24024 August 2015
Evaluation of Information Related to Commitments 6 and 8 from Confirmatory Action Letter No. NRR-2011-002
ML15238B5922015-08-17017 August 2015
Review of Commitment Action Completion Confirmation Action Letter Regarding Earthquake in 2011
ML15175A1902015-06-17017 June 2015
Owner'S Activity Report
ML15057A2492015-04-20020 April 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1
ML15058A0342015-02-23023 February 2015
Summary of Facility Changes, Tests and Experiments
ML14084A3272014-03-27027 March 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14084A2122014-03-27027 March 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML14024A6022014-01-10010 January 2014
Post Accident Monitoring (PAM) Report
ML14015A3142014-01-0808 January 2014
Submittal of Owner'S Activity Report Refueling Outage N1R23 (Form OAR-1)
ML12160A2682012-06-11011 June 2012
Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident
ML12060A3492012-02-16016 February 2012
Owner'S Activity Report for Refueling Outage N2R21
ML12039A1602012-01-25025 January 2012
Steam Generator Tube Inspection Report
ML12039A1612012-01-25025 January 2012
Steam Generator Tube Inspection Report
ML12005A0112011-12-0909 December 2011
Independent Spent Fuel Storage Installation Response to Earthquake
ML1103107402011-01-25025 January 2011
Owner'S Activity Report
ML1019304172010-05-0606 May 2010
Tritium Database Report
ML0921908942009-08-0404 August 2009
Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A
ML0913206392009-05-12012 May 2009
Reactor Coolant Pressure Boundary Visual Inspections Proposed Alternative - N1-I3-NDE-024 and N2-I3-NDE-025
ML0912504812009-05-0404 May 2009
30-Day Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46
ML0901304802009-01-0505 January 2009
Owner'S Activity Report for Refueling Outage
ML0812702032008-04-25025 April 2008
Summary of Facility Changes, Tests and Experiments
ML0807903432008-03-18018 March 2008
Response to Request for Additional Information Steam Generator Tube Inspection Report
ML0802800722008-01-0808 January 2008
Update on North Anna Zirlo Characterization and LOCA Embrittlement Testing
ML0732002342007-11-15015 November 2007
Steam Generator Tube Inspection Report
ML0728205762007-10-0909 October 2007
Steam Generator Tube Inspection Report
ML0719704722007-07-13013 July 2007
Owner'S Activity Reports, for Refueling Outage (N2R18)
ML0705903272007-02-27027 February 2007
Fitness-For-Duty Program Semi-Annual Performance Data Report
ML0623300712006-08-16016 August 2006
Fitness-for-Duty Program Semi-Annual Performance Data Report
ML0609404202006-03-27027 March 2006
Summary of Facility Changes, Tests and Experiments
ML0634101622006-02-27027 February 2006
Fitness-For-Duty Program Semi-Annual Performance Data Report
ML0602600412006-01-25025 January 2006
Virginia Electric and Power Company North Anna Power Station Unit 2 - Owner'S Activity Reports
ML0523501142005-08-22022 August 2005
Fitness-For-Duty Program Semi-Annual Performance Data Report
ML0514603252005-05-25025 May 2005
.2 & 3, North Anna Power Station Units 1 & 2, Surry Power Station Units 1 & 2 - Nuclear Liability Insurance Endorsement
ML0505403042005-02-22022 February 2005
Fitness-for-Duty Program Semi-Annual Performance Data Report Correction of Information
ML0505300392005-02-21021 February 2005
Fitness-for-duty Program Semi-Annual Performance Data Report
ML0727008492005-01-31031 January 2005
Caldon Experience in Nuclear Feedwater Flow Measurement
ML0427101862004-09-24024 September 2004
Emergency Response Data System (ERDS) Database Revisions
2024-02-01
[Table view] |
Text
10 CFR 50.55a VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 12, 2009 U.S. Nuclear Regulatory Commission Serial No.09-253 Attention: Document Control Desk NL&OS/ETS RO Washington, D.C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS 1 AND 2 REACTOR COOLANT PRESSURE BOUNDARY VISUAL INSPECTIONS PROPOSED ALTERNATIVE - N1-13-NDE-024 AND N2-13-NDE-025 Pursuant to 10 CFR 50.55a(a)(3)(i), Dominion requests approval of an alternative to the inspection requirements of footnote 1 included in 10 CFR50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Visual Inspections, for North Anna Units 1 and 2. The requested alternative will permit the inspections performed during the Unit 1 fall 2007 and Unit 2 fall 2008 refueling outages on the bottom mounted instrument tubes (8MI) to be used as the initial reactor coolant pressure boundary visual inspection in place of the footnote requirement for the initial inspection to be performed at the next refueling outage after January 1,2009. Alternatives N1-13-NDE-024 and N2-13-NDE-025 are included in the attachment to this letter as well as the basis for the alternative.
The 8MI inspections performed during the fall 2007 and 2008 refueling outages for North Anna Units 1 and 2, respectively, conformed to the requirements of Code Case N-722 and met the requirements of 10 CFR50.55a(g)(6)(ii)(E). Therefore, Dominion considers the visual examinations performed during the fall 2007 refueling outage for NAPS Unit 1 and fall 2008 refueling outage for NAPS Unit 2 to provide an acceptable level of quality and safety as an alternative to performing the initial inspections in the next refueling outage after January 1,2009, as indicated in 10 CFR 50.55a(g)(6)(ii)(E).
If you should have any questions regarding this submittal, please contact Mr. Thomas Shaub at (804) 273-2763.
Sincerely,
~~ci Leslie Hartz Vice President - Nuclear Support Services
Attachment:
Proposed Alternatives - N1-13-NDE-024 and N2-13-NDE-025 Commitments made in this letter: None
Serial No.09-253 Docket Nos. 50-338/339 Alternative for BMI Baseline Inspections Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
Suite 300 Glen Allen, Virginia 23060 NRC Senior Resident Inspector North Anna Power Station Ms. D. N. Wright NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 H4A 11555 Rockville Pike Rockville, Maryland 20852 Mr. J. F. Stang, Jr.
NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North MaiI Stop 0-8 G9A 11555 Rockville Pike Rockville, Maryland 20852
Serial No.09-253 Docket Nos. 50-338/339 ATTACHMENT REACTOR COOLANT PRESSURE BOUNDARY VISUAL INSPECTIONS PROPOSED ALTERNATIVE N1-13-NDE-024 and N2-13-NDE-025 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNITS 1 AND 2
10 CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative BMI Visual Examinations Requirement Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
- Alternative Provides Acceptable Level of Quality or Safety --
1.0 ASME Code Components Affected
Code components associated with this request are Class 1 Reactor Pressure Vessel (RPV) bottom-mounted instrument penetrations (BMI) having pressure retaining partial or full penetration welds in components fabricated with Alloy 600/82/182 material.
1.1 Category and System Details:
Code Class: Class 1 System: Reactor Pressure Vessel Examination Category: B-P Item Number: B15.80 1.2 Component Descriptions:
Reactor Vessel - RPV bottom-mounted instrument penetrations 2.0 Applicable Code Edition And Addenda North Anna Power Station Units 1 and 2 are completing their third 10-year lSI Intervals. Unit 1's third interval began on May 1, 1999 and ends on April 30, 2009 and Unit 2's third interval began on December 14, 2001 and ends on December 13, 2010. The ASME Boiler and Pressure Vessel Code (ASME Code) of record for the applicable interval is the 1989 Edition for Unit 1 and the 1995 Edition, 1996 Addenda for Unit 2.
3.0 Applicable Code Requirements 10 CFR 50.55a(g)(6)(ii)(E), Reactor coolant pressure boundary visual inspections, was recently incorporated into the 10 CFR 50.55a. The new regulations augmented the inservice inspection requirements (effective date October 10,2008).
Specifically, 10 CFR 50.55a(g)(6)(ii)(E) requires that "Alllicensees of pressurized water reactors shall augment their inservice inspection program by implementing ASME Code Case N-722 subject to the conditions specified in 10 CFR 50.55a(g)(6)(ii)(E)(2) through (4) of this section. The inspection requirements of ASME Code Case N-722 do not apply to components with pressure retaining welds fabricated with Alloy 600/82/182 materials that have been mitigated by weld overlay or stress improvement."
Page 1 of 4
10 CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative 8MI Visual Examinations Requirement In addition, footnote one to 10 CFR 50.55a(g)(6)(ii)(E) states in part: "For inspections to be conducted every refueling outage and inspections conducted every other refueling outage, the initial inspection shall be performed at the next refueling outage after January 1, 2009."
4.0 Reason For Request North Anna Power Station (NAPS) Unit 1 and Unit 2 completed bare metal visual examination of RPV bottom-mounted instrument penetrations prior to the "initial inspection" indicated by 10 CFR 50.55a(g)(6)(ii)(E), which became effective October 10, 2008. NAPS Unit 1 inspections were performed during the fall 2007 refueling outage, and NAPS Unit 2 inspections were performed during the fall 2008 refueling outage. These bare metal visual inspections met the intent of ASME Code Case N-722.
Code Case N-722, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Material," establishes additional requirements to the examination requirements of Table IWB-2500-1 for pressurized water reactor plants having partial or full penetration welds in Class 1 components fabricated with Alloy 600/82/182 material.
For Reactor Vessel Item Number B15.80, RPV bottom-mounted instrument penetrations, all penetrations require Visual Examination (VE) to the requirements of IWB-3522, every other refueling outage.
ASME Code Case N-722 includes specific requirements for the VE and the qualification of personnel performing the VE:
(3) The Visual Examination (VE) performed on Alloy 600/82/182 components for evidence of pressure boundary leakage and corrosion on adjacent ferritic steel components shall consist of the following:
(a) A direct VE of the bare-metal surface performed with the insulation removed. Alternatively, the VE may be performed with insulation in place using remote visual inspection equipment that provides resolution of the component metal surface equivalent to a bare-metal direct VE.
(b) The VE may be performed when the system or component is depressurized.
(c) The direct VE shall be performed at a distance not greater than 4 ft (1.2 m) from the component and with a demonstrated illumination level sufficient to allow resolution of lower case characters having a height of not greater than 0.105 in (2.7 mm).
(4) Personnel performing the VE shall be qualified as VT-2 visual examiners and shall have completed a minimum of four (4) hours of additional training in detection of borated water leakage from Alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.
Page 2 of 4
10 CFR 50.55a Request Number N1-13-NDE-024/N2-13-NDE-025 Alternative 8MI Visual Examinations Requirement The bottom-mounted RPV instrument penetrations examinations during the fall 2007 and fall 2008 refueling outages were performed to the enhanced Visual Examination (VE) requirements and the personnel training and qualification requirements as described in Enclosure 1, "Examiner Qualification and Resolutions Requirements."
5.0 Proposed Alternatives And Basis For Use Virginia Electric and Power Company (Dominion) considers the visual examinations performed during the fall 2007 refueling outage for NAPS Unit 1 and fall 2008 refueling outage for NAPS Unit 2 to provide an acceptable level of quality and safety as an alternative to performing the initial inspections in the next refueling outage after January 1, 2009, as indicated in 10 CFR 50.55a(g)(6)(ii)(E). Therefore, the inspection performed during the fall 2007 refueling outage for NAPS Unit 1 and fall 2008 refueling outage for NAPS Unit 2 can be considered the initial inspections to meet the 10 CFR 50.55a(g)(6)(ii)(E) footnote requirements for the performance of the initial inspection.
In accordance with ASME Code Case N-722, the bottom-mounted RPV instrument penetration examinations are required to be performed at least every other refueling outage. Therefore, the next examinations of Item No. B15.80 components (bottom-mounted RPV instrument penetration) will be performed no later than the fall 2010 refueling outage for Unit 1 and no later than the fall 2011 refueling outage for Unit 2. Dominion requests approval of this alternative pursuant to the provisions of 10 CFR 50.55a(a)(3)(i).
6.0 Duration Of Proposed Alternative The proposed alternative to the 10 CFR 50.55a(g)(6)(ii)(E) requirements is applicable for the remainder of the third 10-year inservice inspection (lSI) interval at NAPS Units 1 and 2.
7.0 Precedents None 8.0 References None 9.0 Enclosures (1) Examiner Qualification and Resolution Requirements Page 3 of 4
10 CFR 50.55a Request Number N1*13*NDE*024/N2*13*NDE*025 Alternative BMI Visual Examinations Requirement ENCLOSURE 1 Examiner Qualifications and Resolution Requirements This enclosure documents a comparison of the bare metal visual examinations performed on the reactor pressure vessel bottom mounted instrumentation (BMI) nozzles at North Anna Power Station Units 1 & 2 performed during previous outages (N1 R19 and N2R19) with the new requirements of Code Case N-722. Two areas related to examination equivalency were required to be addressed; personnel qualifications and resolution requirements.
Personnel Qualifications The examiners that performed these examinations held current VT-2 (non-alternative) and VT-3 qualifications. In addition, each of the examiners had successfully taken the Dominion Boric Acid Corrosion Control (BACC) Inspector training. The inspection team included at least one VT examiner that has also completed the Dominion BACC Evaluator training and qualification requirements.
The examiners that performed these bare metal visual examinations met the requirements of Code Case N-722 as VT-2 qualified examiners with an additional four hours of training addressing the detection of borated water leakage from Alloy 600/82/182 components and the resulting boric acid corrosion of adjacent ferritic steel components.
Based upon the additional training of the visual examiners; the bare metal visual examinations of the BMI nozzle penetrations performed during the N1 R19 and N2R19 outages are considered equivalent to the personnel qualification requirements of Code Case N-722.
Resolution Requirements The previous bare metal visual examinations were performed using a (VT-2) examination technique and required each penetration to be examined for evidence of leakage for 360 degrees around each nozzle. The bare metal visual examinations were documented in the applicable Engineering Periodic Test Procedure. These periodic test procedures specify the use of inspection equipment to be used for the inspection, which consists of a mirror, portable lights, and a visual testing examination resolution card.
Access to the BMI nozzles for the bare metal visual examination is through removable insulation panels. The bare metal visual examinations of the BMI nozzles were performed in accordance with the direct visual examination requirements of within 4 feet and sufficient illumination to resolve 0.105 inches lower case characters.
Based upon the access for the examiner to perform the bare metal visual examinations of the BMI nozzle penetrations, the equipment used to perform the examination (mirror, flashlight, 0.105 inches low case character resolution card), the previously performed bare metal visual examinations of the BMI nozzle penetration are considered equivalent to the resolution requirements of Code Case N-722.
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