ML21252A514

Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Rev 1, Using the Consolidated Line Item Improvement Process

ML21252A514
Person / Time
Site:	North Anna
Issue date:	09/09/2021
From:	Mark D. Sartain Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
21-214, TSTF-577, Rev 1
Download: ML21252A514 (21)

Text

VIRGINIA ELECTRIC AND POWER COMPANY 23261 RICHMOND,VIRGINIA September 9,2021 10CFR50.90 U.S.Nuclear RegulatoryCommission SerialNo.: 21-214 ATTN:Document Control Desk NRA/ENC: RO )

DC20555-0001 Washington, Docket Nos.:50-338 50-339 License Nos.: NPF-4 j NPF-7 j NORTHANNAPOWER STATION UNITS1AND2 j APPLICATION TOREVISE TECHNICAL SPECIFICATIONS TOADOPT TSTF577

- i USINGTHE CONSOLIDATED LINEITEMIMPRQVEMENT PROCESS i

to10CFR50.90, Pursuant Dominion Energy Virginia issubmitting a requestfor an l amendmenttothe TechnicalSpecifications(TS) forNorthAnnaPower Station (NAPS), l 1 and2.Dominion Units Energy Virginiarequests adoptionofTSTF-577, Revision 1, l "Revised for Frequencies Steam Generator TubeInspections."Theproposed changes TS5.6.7, revise "SteamGenerator based Report,"

inspection (SG) onoperating Program,"

history.

andTS5.5.8, "Steam Generator Tube l TheEnclosureprovides a description andassessment oftheproposed changes.

Attachment theexisting 1contains TS pages marked toshowtheproposed changes. l Attachment 2contains revised (clean) TSpages. the TS Bases arenotaffected bythe j proposed changes.

DominionEnergy Virginiarequests that thea'mendment be reviewed under the l Consolidated Line improvement Item Process (CLllP).

Approval oftheamendment is requested bySeptember 1, 2022tosupport steatngeneratortube inspection activities during theUnit1 refueling theamendment

approved, outage shall (RFO) scheduled beimplemented to w'ithin begin 30 inthefall days.

of2022. Once )

l s

Inaccordance with10CFR50.91, a copy ofthisapplication, with attachments, isbeing ,

tothedesignated provided Virginia Official. g r

b t

Serial No.: 21-214 DocketNos.: 50-338/50-339 Page2 of3 Should you have anyquestions orrequireadditional information, pleasecontact Erica N.

Combs at 804-273-3386.

Sincerely, f/ -

MarkD.Sartain Vice President -

Nuclear Engineering & Fleet Support COMMONWEALTH OFVIRGINIA )

)

COUNTY OFHENRICO )

Theforegoing document wasacknowledged before me,inand fortheCounty andCommonwealth aforesaid,today byMr.MarkD.Sartain, whoisVicePresident -

Nuclear Engineering andFleet Support, ofVirginia andPowerCompany.

Electric He hasaffirmed before me that heisduly authorized toexecute andfiletheforegoingdocumentinbehalfof that company, andthat the statements inthe documentaretrue tothebest ofhis knowledge andbelief.

Acknowledged beforemethis dayof ,

2021, MyCommission Expires: 183/,24 CRAIG D SLY Notary Public Commonwealth ofVirginia Reg.# 7518653 9

Noary 22-Expires December 31, MyCommission

Enclosure:

Description andAssessment ofProposed Change Attachments:

1.Proposed Technical Specification Changes (Mark-Up) 2.Revised Technical Specification Pages Commitments madebythis letter:

An SGTubeInspection Report will besubmittedwithin 30days afterimplementation of theapproved license amendment.

Serial 21-214 No.:

Docket Nos.:

50-338/50-339 Page3 of3 cc: Regional Administrator, Region II U. S. Nuclear Regulatory Commission Marquis One Tower 245Peachtree CenterAvenue, 1200 NE,Suite Atlanta, Georgia 30303-1257 Mr. G.E.Miller Senior Project Manager -

Station North AnnaPower U.S.Nuclear Regulatory Commission Mail Stop 09E-3 OneWhite Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 NRCSenior Resident Inspector North AnnaPower Station OldDominion Electric Cooperative R-North-Anna-Correspondence@odec.com State Health Commissioner Virginia Department ofHealth JamesMadison Building -

7thfloor 109Governor Street, Suite 730 Richmond, Virginia 23219

Serial 21-214 No.:

Docket Nos.:

50-338/339 ENCLOSURE Electric Virginia andPowerCompany (Dominion Virginia)

Energy North Unit AnnaPowerStation 1andUnit 2

SerialNo.: 21-214 Docket Nos.: 50-338/339 Enclosure Page1of4 DESCRIPTION ANDASSESSMENT

1.0DESCRIPTION

Pursuantto10CFR 50.90, VirginiaElectric andPowerCompany (Dominion Energy Virginia) proposes changes totheNorth AnnaPowerStation (NAPS) Units 1 and2 OperatingLicenses (OLs)and Technical Specifications(TS) toadopt TSTF-577, Rev. 1, "RevisedFrequencies for Steam Generator TubeInspections." TheTS related tosteam generator(SG) inspections and reporting tube are being revised based on operating history.

Theproposed changes revise theTS related toSG tubeinspection andreporting intheAdministrative requirements: Controls section oftheTS.Specifically, theNAPS Units1and2 TS arebeing revisedtodefinea new, fixed SGtube inspection frequency ofatleastevery 96effective full power months(EFPMs) andtorevise inspection period requirements.

Thenewinspection period starts after a 100% inspection of all SGtubes hasbeenperformed during a single outage (past orfuture), whichwascompleted for NAPSUnits and2 during

1. thespring 2018andspring 2019 refueling outages (RFOs),

Thecurrent respectively. TS requirement toperform aninspection aftera crack isfound "24effective within, fullpower months oronerefueling outage (whichever results in morefrequent inspections)," isalsobeing revised torequire an inspection during the nextRFO.Finally,theproposed change rearranges theexisting reporting requirements TS in 5.6.7 forc larity.

2.0ASSESSMENT 2.1ApplicabilityofSafety Evaluation Dominion Energy Virginia hasreviewed thesafety evaluation for TSTF-577, Rev.1, providedtotheTechnical Speci'fications TaskForce ina letter dated April 14,2021 (ADAMS Accession No. ML21'098A188). Thisreview included theNRC staff's evaluationandtheinformation provided inTSTF-577, Rev.1 As described inthe subsequent paragraphs, Dominion Energy Virginia hasconcluded that the justifications presentedinTSTF-577, Rev.1,andthesafety evaluation prepared bytheNRCstaff toNAPSUnits areapplicable 1and2andjustify this amendment for theincorporation of thechanges intotheNAPSTS.

The current SG TS requirements arebasedon TSTF-510, "Revision toSteam GeneratorProgram Inspection Frequencies andTubeSample Selection." Both NAPS Units1 and2 SGshaveAlloy 690thermally treated (Alloy 690TT) tubes. Thecurrent

Serial No.:21-214 Docket Nos.: 50-338/339 Enclosure Page2 of4 inspection period followingimplementation ofTSTF-577, Rev. 1,will beestablished as beginningin March 2018for NAPSUnit 1 andMarch 2019for NAPSUnit 2.Dominion Energy Virginia will submit a SGTubeInspection Reportmeeting therevised TS 5.6.7 requirements within 30 days afterimplementationofthe licenseamendment.

2.2Variations Dominion Energy Virginiaisnot proposing anytechnical variations ordeviations from theTS changes described inTSTF-577, Rev.1,ortheapplicable parts ofthe NRC staff's safety evaluation dated April14, 2021. (ADAMSAccession No.ML21098A188).

TheNAPSTSutilize different numbering than the StandardTechnical Specificationson which TSTF-577, Rev. 1,wasbased. Specifically, the"SteamGenerator (SG) Program" isnumbered 5.5.8 intheNAPSUnits 1 and 2 TS ratherthan 5.5.9 asstated inthe TSTF. This difference isadministrative anddoes not affecttheapplicability ofTSTF-577, Rev. 1,totheNAPSUnits 1and2TS.

TheNAPSUnits 1 and2 TS contains a requirement that differs fromtheStandard Technical Specifications onwhich TSTF-577, Rev.1,wasbased butisencompassed in the TSTF-577, Rev.1, justification.

Specifically, NAPSUnits1 and 2 TS 5.5.8, "Steam Generator (SG) Program," item b .2,s tates, "Leakage isnot to exceed 1 gpm for all SGs," rather than, "Leakage isnottoexceed 1 gpm perSG;"however, theNAPSTS requirement for SGleakage ismoreconservative andistherefore acceptable.

3.0REGULATORY ANALYSIS 3.1NoSignificant Hazards Consideration Analysis Dominion EnergyVirginia requests adoption ofTSTF 577,Rev.1, "Revised Frequencies for SteamGenerator TubeInspections." TheTechnical Specifications (TS) related tosteamgenerator tubeinspections andreporting arerevised based on operating history. Dominion Energy Virginia hasevaluated ifa signifi'cant hazards consideration isinvo'Ived with theproposed amendment(s) by focusing bn thethree standards set forth in10CFR50.92, "Issuance ofamendment," asdiscussed below:

1 Doesthe proposed amendment involve a significant increase inthe.probability or consequences ofanaccident previously evaluated?

Respoonse: Non :m The proposed change revises theinspection frequencies forsteamgenerator tube inspections andassociated reporting requirements. Inspection frequencies

No.:

Serial 21-214 Docket 50-338/339 Nos.:

Enclosure Page3 of4 are not an initiator toa steamgenerator tuberupture accident, oranyother accident previously evaluated. As a result, theprobability ofanyaccident previously evaluated isnotsignificantly increased. TheSG tubes inspected by theSG Program continue toberequired tomeettheSG Program performance criteria andto be capable ofperforming anyfunctions assumed intheaccident analysis. Asa result, theconsequences ofanyaccident previouslyevaluated are notsignificantly increased.

Therefore, theproposed change doesnotinvolve a significant increase inthe probability orconsequences of anaccident previously evaluated.

2.Doesthe proposed amendment create the possibility ofa newordifferent kindof accident from anyaccident previously evaluated?

Response: No.

Theproposed change revises theinspection frequencies forsteamgenerator tube inspections andassociated reporting requirements. Theproposed change doesnot alter:the design function oroperation ofthe SGs ortheability ofanSG toperform the'design function.TheSGtubes continue to be required tomeet the SGProgramperformance criteria. Theproposed change does notcreate the possibility ofa newordifferent kind ofaccident duetocredible new failure mechanisms, malfunctions, oraccident initiators that arenotconsidered inthe design andlicensing bases.

Therefore, theproposed change doesnotcreate thepossibility of a new or different kind ofaccident from anyaccident previously evaluated.

3.Doesthe.proposed .amendment involve a significant reduction ina margin of safety?

Response:'No.

The roposed change revisestheinspection frequencied forsteamgenerator tube inspections andassociated reporting requirements. Theproposed change doesnotchange any the of controlling values of parameters used toavoid exceeding regulatory orlicensing limits.

Theproposed change doesnotaffect a design basis orsafety limit, oranycontrolling value for a* xparameterestablished inthe' UFSARorthe license.

Serial No.: 21-214 Docket Nos.:50-338/339 Enclosure Page4 of4 Therefore, theproposed change doesnotinvolve a significant reduction ina margin ofsafety.

Based on theabove, Dominion Energy Virginia concludes that theproposed change presentsnosignificant hazards considerationunder thestandards in10CFR setforth and, 50.92(c), accordingly, a findingof"no significant hazards consideration" isjustified.

3.2Conclusion Inconclusion,'based ontheconsiderations discussedabove, (1) there isreasonable assurance thatthe health andsafety of the publicwill notbeendangered byoperation in theproposed manner, (2) activities willbe conductedincompliance such with the Commission5sregulations, and(3) th'eissuance oftheamendment will notbeinimical to thecommon2defense andsecurity ortothe health andsafety ofthe public.

4.0ENVIRONNIENTAL EVALUATION A reviewhasdete:rmined that theproposed amendment would change a requirement withrespectoto,.installation oruseofa facility componentlocated withintherestricted area,as defined Tin 10 CFR 20, orwouldchange an inspection orsurveillance requirement.KHowe.verc the proposed amendment doesnotinvolve:

(i) a significant hazards consideration, (ii)a significantchangemin the.types ora significant increase intheamounts ofany effluents that may:be released offsite, or (iii) a sinificant' increase 'inindividual or cumulative occupational radiation exposure.

Accordingly, ithe proposed amendment meetstheeligibility criterion forcategorical

! exclusion set4forth in10CFR51.22(c)(9). Therefore, pursuant to10CFR51.22(b), no environmental: .impact statement orenvironmental assessment needbe prepared in connectionwith theproposed amendment. j l

a p

Serial No.:

21-214 Docket Nos.:

50-338/339 ATTACHMENT 1 Electric Virginia andPowerCompany (Dominion Virginia)

Energy AnnaPowerStationUnit North 1andUnit 2

Serial Nox21-214 Docket Nosx50-338/339 Attachment 1 Page1of6 Programs andManuals 5.5 5.5 Programs andManuals 5.5.7 M This program provides controls forinservice testing ofASME Code Class 1, 2, and3 components. Theprogram shall include the following:

a. Testing frequencies specifiedintheASME Code forOperation and Maintenance of Nuclear Power Plantsandapplicable Addenda as follows:

ASME CodeforOperation and Maintenance ofNuclear Power Plants andapplicable Addenda Required Frequencies for terminology forinservice performing inservice testing activities testing activities Weekly At least onceper7 days Monthly At least onceper31days Quarterly orevery 3 months At least once per92days Semiannually orevery 6 months At least onceper184days Every9 months At least once per276days Yearly or annually At least onceper366days Biennially orevery 2 years At least onceper731days

b. Theprovisions ofSR3.,0.2 areapplicable to the above required Frequencies forperforming inservice testingactivities;

c. Theprovisions ofSR3.0.3 areapplicable to inservice testing activities; and

d. Nothing intheASME Code forOperationandMaintenance of Nuclear Power Plants shall beconstrued tosupersede therequirements of anyTS.

5.5.8 W AnSGSteam-Generates Program shallbeestablished andimplemented /

toensure that SGtubeintegrity ismaintained. Inaddition, the SGSteamGeneFates Program shall includethefollowing: j a Provisions forcondition monitoring assessments. Condition monitoring assessment means anevaluation ofthe"as found" condition ofthetubing withrespect totheperformance criteria

for structural integrity andaccident induced leakage. The"as found" condition refers to thecondition ofthetubing during a SGinspection outage, asdeterminedfromtheinservice (continued)

North AnnaUnits 1 and2 5.5-5 Amendments 369/360l

Serial 21-214 No.:

Docket Nos.: 50-338/339 Attachment 1 Page2 of6 Programs andManuals 5.5 5.5 Programs andManuals 5.5.8 M

a. (continued) inspection results orby other means, prior to theplugging of tubes. Condition monitoring assessments shall beconducted during eachoutage duringwhich theSGtubes areinspected or plugged to confirm that theperformance criteria are being met.

b. Performance criteria for SGtube integrity. SGtubeintegrity shall bemaintainedby meeting theperformance criteria fortube structural integrity,accident inducedleakage, andoperational LEAKAGE.

1.Structural integrity performance criterion: Allin-service SGsteam-genepates over tubes shall retain thefullrangeofnormal operating conditions structural integrity l

(including startup, operation in the power range, hotstandby, andcool down), andallanticipated transients included inthey design specification, design basisaccidents Thisincludes retaining a safety factor of3.0against burst under normal steady state fullpower operation primary to secondary pressure differential anda safety factor of 1.4 against burst applied to thedesign basis accidentprimary to secondary pressure differentials. Apart fromthe above requirements, additional loading conditions associated with thedesign basis accidents, or combination ofaccidents in accordance withthedesign andlicensing basis, shall also be evaluated todetermine iftheassociated loads contribute significantly to burst or collapse. Intheassessment of tube integrity, those loads thatdosignificantly affect burstor collapse shall bedetermined andassessed incombination with theloads dueto pressure witha safety factor of1.2onthe combined primary loads and1.0onaxial secondary loads.

2. Accident induced leakage performance criterion: Theprimary to secondary accident induced leakage rateifor anydesign basis accident, other thana SGtube ruptur.e, shall not I exceed theleakage rateassumed intheaccident analysis in terms oftotal leakage rateforallSGsandleakage ratefor

! anindividual SG.Leakage isnotto exceed 1 gpmforallSGs 3.Theoperational LEAKAGE performance criterion isspecified inLCO3.4.13,RCSOperational LEAKAGE."

North AnnaUnits 1 and2 5.5-6 Amendments 249/250 [

Serial No.:21-214 Docket Nos.: 50-338/339 Attachment 1 Page3of6 Programs andManuals 5.5 5.5 Programs andManuals 5.5.8 W (continued) c Provisions forSGtube plugging criteria. Tubes found by f inservice inspection to contain flaws witha depth equal to or exceeding 40%ofthenominal tubewallthickness shall be plugged.

d. Provisions for SGtubeinspections. Periodic SGtube inspections shall beperformed. Thenumber andportions ofthetubes inspected and methods of inspection shall beperformed withthe objective of detecting flaws of anytype (e.g., volumetric flaws, axial and circumferential cracks) that maybepresent along the length of the tube, from thetube-to-tubesheet weldat thetubeinlet to the tube-to-tubesheet weld atthetube outlet, andthat maysatisfy the applicable tubeplugging criteria. TheJ tube-to-tubesheet weldis not partofthetube. Inaddition to meeting therequirements of d.1, d.2,andd3 below, the inspection scope, inspection methods, andinspection intervals shall be such astoensure that SG tube integrity ismaintained until thenextSGinspection. A degradation assessmentshall bef performed to determine thetypeand location offlaws to which thetubes maybesusceptible and,based onthis assessment, to determine which inspection methods need to beemployed and at what locations 1.Inspect 100% ofthetubes ineach SGduring the first refueling outage following SGinstallation 2 After thefirst refueling outage following SGinstal lation, 100% of the tubes in 96 . .

, defines the

,which , 1 irtspection period a-location-net-prev4ous4-y-4nspected-with-a-teeknique-eapable t of-detecting-this-type-of-degradation-at-this-location-and that--may-satisfy-the-appl4sable-plugging-cr-4ter-4a3--t-he minimum-numben-of-loeations-4nspected-w4th-sush-a-eapable 4nspection-teeknique-dur-4ng-the-r-emainder-of-the-4nspestion per-iod-may-be-pr-eratedThe-4rastion-of-10sations-te4e inspected--for--this-potentia-1-type-of-4egr-adation-at-this location-at-the-end-of-the-4nspection-per4od-shallbe-no-les than--the-r-atte-of--the-number-of-times4he4G-4s--sc-hedu444-(sonttnued)

North AnnaUnits 1 and2 5.5-7 Amendments 249/240j

No.:

Serial 21-214 Docket Nos.:

50-338/339 Attachment 1

Page4of6 ProgramsandManuals 5.5 5.5 Programs andManuals 5.5.8 M (continued)

2. (continued) m a.

W b.

W c.

W d

3. Ifcrack indications arefoundinanySGtube,thenthenext inspection foreachaffected andpotentially SGforf affected thedegradation thatcaused mechanism thecrack indication

/

sha eling outage l

be at the next i 4.aspecM.sas). Ifdefinitive suchasfrom information, ,

examination ;tube, ofa pulled non-destructave diagnostic ,

testing, evaluation orengineering indicates thata crack-like indication witha crack(s),

isnotassociated 1 thentheindication neednotbetreatedasa crack, NorthAnnaUnits 1 and2 5.5-8 2-69/240 Amendments

Serial No.: 21-214 Docket Nos.: 50-338/339 Attachment 1 Page5 of6 Programs andManuals 5.5 5.5 Programs andManuals 5.5.8 W (continued)

e. Provisions formonitoring operational primary to secondary LEAKAGE.

5.5.9 m Thisprogram provides controlsformonitoring secondary water chemistry to inhibit SGtube degradation andlowpressure turbine discstress corrosion cracking. Theprogram shall include:

a. Identificationof a sampling schedule forthecritical variables andcontrol points for these variables;

b. Identification oftheprocedures usedtomeasure thevalues of thecritical variables;

c. Identification ofprocess sampling points, which shall include monitoring thedischarge ofthe condensate pumps forevidence of condenser inleakage;

d. Procedures fortherecording andmanagement ofdata;

e. Procedures defining corrective actions for all offcontrolpoint chemistry conditions; and

f. A procedure identifying theauthority responsible for the interpretation ofthedataandthesequence andtiming of administrative events, which isrequired to initiate corrective action.

5.5.10 A program shall beestablished to implement thefollowing required testing ofEngineered Safety Feature (ESF) filter ventilation systems ingeneral conformance with thefrequencies andrequirements ofRegulatory Positions C.5.a, C.5.c, C.5.d, andC.6.b ofRegulatory Guide 1.52,Revision 2, March 1978,andANSI N510-1975.

a. Demonstrate foreach oftheESF- systems thataninplace testof thehighefficiency particulate ,air( HEPA) filters shows a penetration andsystem bypass < 11.0%whentested inaccordance (continued)

North AnnaUnits 1 and2 5.5-9 Amendments 369/350 l

SerialNo.:21-214 DocketNos.: 50-338/339 Attachment1 Page6of6 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 W A report shallbesubmitted within 180daysafter theinitial entry into MODE 4 following completion ofaninspection performed in accordance with theSpecification 5.5.8, "Steam Generator (SG)

Program." The report shall include:

a. Thescope of inspections performed on each SG, b-, W #

G M

A e

M eL Thenumber andpercentage oftubes plugged to date,andthe effective plugging percentage ineachsteam generator, and 9r W

b. Thenondestructive examination utilized techniques fortubeswith increased degradationsusceptibility;

c. Foreach degradationmechanism found:

1 Thenondestructive examination techniquesutilized; 2.Thelocation,orientation (if measured linear), size (ifavailable),

andvoltage responseforeach indication.Fortubewearatsupport structures less than 20 percentthrough-wall, only thetotal number ofindicationsneeds tobereported; 3.Adescriptionofthecondition monitoring assessment andresults, including the margintothetube integrityperformance criteriaandcomparison with the margin toexist predicted atthe inspection bytheprevious forward-looking tube integrity and assessment; 4.Thenumber oftubes plugged during the inspectionoutage.

d. An analysis summary ofthetube conditions integrity predictedtoexist atthe next scheduledinspection(forward-lookingtube assessment) integrity relative tothe applicable performance criteria,including theanalysis methodology, inputs, and results;

f. Theresults ofanySGsecondary side inspections.

North Ann Units 1 and2 5.6-5 Amendments a

Serial 21-214 No.:

Docket Nos.:

50-338/339 ATTACHMENT2 Virginia andPowerCompany Electric Virginia)

Energy (Dominion North Unit AnnaPowerStation 1andUnit 2

Serial No.: 21-214 Docket Nos.: 50-338/339 Attachment 2 Page1of5 Programs andManuals 5.5 5.5 Programs andManuals 5.5.7 M This program provides controls forinservice testing ofASME Code Class 1, 2, and3 components Theprogram shall include the following:

a. Testing frequencies specified intheASME CodeforOperation and Maintenance of Nuclear Power Plantsandapplicable Addenda as follows:

ASME CodeforOperation and Maintenance ofNuclear Power Plants andapplicable Addenda Required Frequencies for terminology forinservice performing inservice testing activities testing activities Weekly At least onceper7 days Monthly At least onceper31days Quarterly orevery3 months At least onceper92 days Semiannually orevery 6 months At least onceper184days Every9 months At least onceper276days Yearly or annually At least onceper366days Biennially orevery2 years At least onceper731days

b. 'The provisions of SR3.0.2 areapplicableto the above required Frequencies forperforming inservicetestingactivities;

c. Theprovisions of SR3.0.3 areapplicable to inservice testing activities; and

d. Nothing intheASME CodeforOperation andMaintenance of Nuclear PowerPlants shall beconstrued to supersede therequirements of anyTS.

5.5.8 EW AnSGProgram shall beestablished andimplemented toensure that SG tubeintegrity ismaintained. Inaddition, theSGProgram shall include thefollowing:

a Provisions forcondition monitoringassessments. Condition monitoring assessment meansan evaluation ofthe"as found" condition ofthetubing withrespect to theperformance criteria forstructural integrity andaccident induced leakage. The"as found" condition refers to thecondition ofthetubing during a SGinspection outage, as determinedfromtheinservice (continued)

North AnnaUnits1 and2 5.5-5 Amendments

Serial Nox21-214 Docket Nosx50-338/339 Attachment2 Page2 of5 Programs andManuals 5.5 5.5 Programs andManuals 5.5.8 M

a. (continued) inspection results or byother means,prior to theplugging of tubes. Condition monitoring assessments shall beconducted during eachoutage duringwhich theSGtubes areinspected or plugged to confirm that theperformance criteria arebeing met

b. Performance criteria for SGtube integrity. SGtube integrity shall bemaintainedby meeting theperformance criteria fortube structural integrity,accident inducedleakage, andoperational LEAKAGE.

1.Structural integrity performance criterion: Allin-service SGtubes shall retain structural integrity overthefull l rangeofnormal operating conditions (including startup, operation inthepower range,hot standby, andcooldown),

andallanticipated transients included inthedesign specification, design basis accidents This includes retaining a safety factor of 3.0against burst under normal steady statefullpower operation primary to secondary pressure differential anda safety factor of 1.4against burst applied to thedesign basis accident primary to secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with thedesign basis accidents, or combination ofaccidents in accordance withthedesign andlicensing basis, shall also beevaluated todetermine iftheassociated loads contribute significantly to burst or collapse Intheassessmentof tubeintegrity, those loads thatdo significantly affect burst or collapse shall bedetermined andassessed in combination withtheloads dueto pressure witha safety factor of 1.2on thecombined primary loads and1.0on axial secondary loads.

2.Accident induced leakage performance criterion: Theprimary to secondary accident induced leakage rateforanydesign basis accident, other thana SGtuberupture, shall not exceed theleakage rateassumed in theaccident analysis in termsoftotal leakage rateforallSGsandleakage ratefor an individual SG.Leakage isnotto exceed 1 gpmforallSGs.

3.Theoperational LEAKAGE performance criterion isspecified inLCO3.4.13, "RCS Operational LEAKAGE."

North AnnaUnits1 and2 5.5-6 Amendments

Serial Nos: 21-214 Docket Nos.: 50-338/339 Attachrnent2 Page3 of5 Programs andManuals 5.5 5.5 Programs andManuals 558 . W (con tinued)

c. Provisions forSGtubeplugging criteria. Tubes found by inservice inspection to contain flaws witha depth equal to or exceeding 40%ofthenominal tubewallthickness shall be plugged.

d. Provisions for SGtube inspections. Periodic SGtubeinspections shall beperformed. Thenumber andportions of thetubes inspected and methods of inspection shall beperformed withthe objective of detecting flaws ofanytype(e.g., volumetric flaws, axial and circumferential cracks) that maybepresent along thelength of the tube, fromthetube-to-tubesheet weldat thetubeinlet to the tube-to-tubesheet weldatthetubeoutlet, andthat may satisfy the applicable tubeplugging criteria. The tube-to-tubesheet weldis not partofthetube. Inaddition to meeting therequirements of d.1, d.2,andd.3below, the inspection scope, inspection methods, andinspection intervals shall be such as to ensure that SG tube integrity ismaintained until thenextSGinspection. A degradation assessmentshall be performed to determine thetypeand location offlaws towhich thetubes maybe susceptible and,based on thisassessment, to determine which inspection methods need to beemployed andat whatlocations.

1.Inspect 100%ofthetubes ineachSGduring the first refueling outage following SGinstallation.

2.Afterthefirst refueling outage following SGinstallation, inspect 100%ofthetubes ineachSGat least every 96 effective fullpower months, whichdefines theinspection period 3 Ifcrack indications arefound inanySGtube,thenthenext inspection foreachaffected andpotentially affected SGfor thedegradation mechanism thatcaused thecrack indication shall beat thenextrefueling outage. Ifdefinitive l t information, such as fromexamination ofa pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates thata crack-like indication isnot associated witha crack(s), thentheindication neednotbe treated as a crack.

North AnnaUnits 1 and2 5.5-7 Amendments

Serial 21-214 boo.:

Docket Nos.: 50-338/;339 Attachment 2

Page4of5 Programs andManuals 5.5 5.5 Programs andManuals 5.5.8 W (continued)

e. Provisions formonitoring operational primary to secondary LEAKAGE.

5.5.9 m Thisprogram provides controls formonitoring secondary water chemistry to inhibit SG tube degradation andlowpressure turbine idisc stress corrosioncracking. Theprogram shall include:

a. Identification ofa sampling schedule forthecritical variables and;control points forthese variables;

b. Identification oftheprocedures used to measure thevalues of the- cri'tical variables;

c. Identification of process sampling points, which shall include monitoring thedischarge ofthecondensate pumps forevidence of 1 'co'ndenser inleakage;

d.Proceduresfor -the recording andmanagement of data;

e. Procedures defining corrective actions foralloff control point c chemistry :conditions; and ef.sAprocedure identifying theauthority responsible for the interpretation ofthedataandthesequence andtimingof sadministrative events, which isrequired to initiate corrective vaction.

5.5.,10.

s A.program shall be-established to implement thefollowing required

,testingxofEngineered5Safety Feature (ESF) filter ventilation systems >in !generalconformance withthefrequencies andrequirements

>ofRegulatorysPositions C.S.a, C.5c,C.5.d, andC.6.b ofRegulatory

! Guide.1.52,xRevision 2, March 1978,andANSIN510-1975.

an Demonstrate foreachoftheESFsystems thatan inplace testof thehighefficiency particulate air(HEPA) fi1ters shows a penetration andsystem bypass < 1.0% whentes'ted inaccordance (continued)

North AnnaUnits1 and2 5.5-8 Amendments

Serial No.: 21-214 Docket Nos.: 50-338/339 Attachment 2 Page5 of5 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator TubeInspection Report A report shallbesubmitted within 180daysafter theinitial entry into MODE 4 following completion of an inspection performed in accordance with theSpecification5.5.8, "Steam Generator (SG)

Program." The "report shall include:

a. The.scope of inspections performed on eachSG,

b. The1nondestructive examination techniques utilized fortubes withincreased degradation susceptibility;

c. For:eachsdegradation mechanism found:

L <Thenondestructive examination techniques utilized; 2 The.1ocation, orientation (if linear), measured size(if x .available), andvoltageresponse foreachindication. For

.'tubeswear at support structures lessthan20 percent xthrough-wall, onlythetotalnumber ofindications needs to bereparted; 3..aAdescription ofthecondition monitoring assessment and resuTts,"including themarginto thetube integrity

~performance criteria andcomparison with the margin s spredicted ~to= existat theinspection bythe previous eforward-looking tubeintegrity assessment;and

4. ':The inumber oftubes plugged during theinspection outage xd An.analysis .summ'ary ofthetubeintegrity conditions predicted

n. toex:ist at,thenextscheduled inspection (forward-looking tube s x :integrityassessment) relative to theapplicable performance

[ criteria., .inclu'ding theanalysis methodology, inputs, and results;

. , i

e. Thenumber andpercentage oftubes plugged to date,andthe effective pl:ugging percentage in eachsteamgenerator, and Af.Theresults of anySGsecondary sideinspections.

North AnnaUnits1 and2 5.6-5 Amendments