ML21252A514
| 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 POWERCOMPANY RICHMOND,VIRGINIA 23261 September 9,2021 10CFR50.90 U.S.Nuclear Regulatory Commission Serial No.: 21-214 ATTN:Document Control Desk NRA/ENC: RO Washington, DC20555-0001 Docket Nos.:50-338 50-339 License Nos.:NPF-4 NPF-7 NORTHANNAPOWERSTATIONUNITS1AND2 APPLICATION TOREVISETECHNICAL SPECIFICATIONS TOADOPTTSTF577 USINGTHECONSOLIDATED LINEITEMIMPRQVEMENT PROCESS Pursuant to10CFR50.90, Dominion Energy Virginia issubmitting a requestforan amendment totheTechnical Specifications (TS) forNorth AnnaPower Station (NAPS),
Units 1and2.Dominion Energy Virginia requests adoption ofTSTF-577, Revision 1,
"Revised Frequencies forSteamGenerator TubeInspections."
Theproposed changes revise TS5.6.7, "Steam Generator (SG)
Program,"
andTS5.5.8, "Steam Generator Tube inspection Report,"
based onoperating history.
TheEnclosure provides a description andassessment oftheproposed changes.
Attachment 1contains theexisting TSpagesmarkedtoshowtheproposed changes.
Attachment 2contains revised (clean)
TSpages.
theTSBasesarenotaffected bythe proposed changes.
Dominion EnergyVirginia requests thatthea'mendment be reviewed underthe Consolidated LineItemimprovement Process (CLllP).
Approval oftheamendment is requested bySeptember 1,2022tosupport steatn generator tubeinspection activities during theUnit1refueling outage(RFO) scheduled tobegin inthefall of2022.Once
- approved, theamendment shall beimplemented w'ithin 30days.
s Inaccordance with10CFR50.91, acopyofthis application, withattachments, isbeing provided tothedesignated Virginia Official.
gr b
t
Serial No.:
21-214 Docket Nos.:
50-338/50-339 Page2of3 Should you haveanyquestions orrequire additional information, please contact Erica N.
Combs at 804-273-3386.
Sincerely, f/
MarkD.Sartain VicePresident
- Nuclear Engineering
&FleetSupport COMMONWEALTH OFVIRGINIA
))
COUNTY OFHENRICO
)
Theforegoing document wasacknowledged before me,inand fortheCounty andCommonwealth aforesaid, today byMr.MarkD.Sartain, whoisVice President Nuclear EngineeringandFleet
- Support, ofVirginia Electric andPowerCompany.
Hehasaffirmed before methat heisduly authorized toexecute andfile theforegoing document inbehalfof that
- company, andthat the statements inthedocument aretrue tothebest ofhisknowledge andbelief.
Acknowledged before methis dayof
, 2021, MyCommission Expires:183/,24 CRAIG DSLY Notary Public Commonwealth ofVirginia Reg.# 7518653 9
Noary MyCommission Expires December31,22-
Enclosure:
Description andAssessment ofProposed Change Attachments:
1.Proposed Technical Specification Changes (Mark-Up) 2.Revised Technical Specification Pages Commitments madebythis letter:
AnSGTubeInspection Report will besubmitted within 30daysafter implementation of theapproved license amendment.
Serial No.:21-214 Docket Nos.:
50-338/50-339 Page3of3 cc: Regional Administrator, Region II U. S. Nuclear RegulatoryCommission Marquis One Tower 245Peachtree CenterAvenue, NE,Suite 1200
- Atlanta, Georgia 30303-1257 Mr.G.E.Miller Senior Project Manager
- NorthAnnaPowerStation U.S.Nuclear Regulatory Commission Mail Stop09E-3 OneWhiteFlint North 11555Rockville Pike Rockville, Maryland 20852-2738 NRCSenior Resident Inspector North AnnaPowerStation 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 No.:21-214 Docket Nos.:
50-338/339 ENCLOSURE Virginia Electric andPowerCompany (Dominion EnergyVirginia)
North AnnaPowerStation Unit 1andUnit 2
Serial No.:21-214 Docket Nos.:
50-338/339 Enclosure Page1of4 DESCRIPTIONANDASSESSMENT
1.0DESCRIPTION
Pursuant to10CFR 50.90, VirginiaElectric andPowerCompany(Dominion Energy Virginia) proposes changes totheNorthAnnaPowerStation (NAPS)
Units 1 and2 Operating Licenses (OLs)and Technical Specifications(TS) toadopt TSTF-577, Rev.1, "Revised Frequencies for Steam Generator TubeInspections."
TheTSrelated tosteam generator (SG) tubeinspections and reporting arebeing revised basedonoperating history.
Theproposed changesrevise theTS related toSGtubeinspection andreporting requirements:
intheAdministrative Controls section oftheTS.Specifically, theNAPS Units 1and2TSarebeing revised todefinea new, fixedSGtubeinspection frequency ofatleast every 96effective full powermonths(EFPMs) andtorevise inspection period requirements.
Thenewinspection period starts after a 100%
inspection ofall SGtubes hasbeenperformed during a single outage(past orfuture),
whichwascompleted for NAPSUnits 1.and2during thespring 2018andspring 2019 refueling outages (RFOs),
respectively.
Thecurrent TSrequirement toperform aninspection afteracrack isfound
- within, "24effective full powermonthsoronerefueling outage (whichever results in morefrequent inspections),"
isalsobeingrevised torequire aninspection during the nextRFO.Finally, theproposed change rearranges theexisting reporting requirements inTS5.6.7 forclarity.
2.0ASSESSMENT
2.1Applicability ofSafety Evaluation Dominion Energy Virginia hasreviewed thesafety evaluation forTSTF-577, Rev.1, provided totheTechnical Speci'fications TaskForceina letter datedApril 14,2021 (ADAMS Accession No.ML21'098A188).
Thisreview included theNRC staff's evaluation andtheinformation provided inTSTF-577, Rev.1 Asdescribed inthe subsequent paragraphs, Dominion Energy Virginia hasconcluded thatthejustifications presented inTSTF-577, Rev.1,andthesafety evaluation prepared bytheNRCstaff areapplicable toNAPSUnits 1and2andjustify this amendment fortheincorporation of thechanges into theNAPSTS.
Thecurrent SG TS requirements arebasedon TSTF-510, "Revision toSteam Generator Program Inspection Frequencies andTubeSampleSelection."
BothNAPS Units 1and2 SGshaveAlloy 690thermally treated (Alloy 690TT) tubes.
Thecurrent
Serial No.:21-214 Docket Nos.:
50-338/339 Enclosure Page2of4 inspection period followingimplementation ofTSTF-577, Rev.1,will beestablished as beginningin March 2018forNAPSUnit1andMarch2019forNAPSUnit2.Dominion Energy Virginia will submit aSGTubeInspection Report meeting therevised TS5.6.7 requirements within 30daysafter implementationofthelicense amendment.
2.2Variations Dominion Energy Virginia isnot proposing anytechnical variations ordeviations from theTS changes described inTSTF-577, Rev.1,ortheapplicable parts oftheNRC staff's safety evaluation dated
- April14, 2021. (ADAMSAccession No.ML21098A188).
TheNAPSTSutilize different numbering than theStandardTechnical Specifications on which TSTF-577, Rev.1,wasbased.
Specifically, the"Steam Generator (SG)
Program" isnumbered 5.5.8intheNAPSUnits1 and 2 TS ratherthan5.5.9 asstated inthe TSTF.Thisdifference isadministrative anddoes not affecttheapplicability ofTSTF-577,Rev.1,totheNAPSUnits 1and2TS.
TheNAPSUnits 1 and2 TScontains a requirement that differs fromtheStandard Technical Specifications onwhich TSTF-577, Rev.1,wasbased butisencompassed in theTSTF-577, Rev.1, justification.
Specifically, NAPSUnits1 and 2TS5.5.8, "Steam Generator (SG)
Program,"
itemb.2,states, "Leakage isnotto exceed 1gpmforall SGs,"rather than,"Leakage isnottoexceed1gpmperSG;"
- however, theNAPSTS requirement forSGleakage ismoreconservative andistherefore acceptable.
3.0REGULATORY ANALYSIS 3.1NoSignificant Hazards Consideration Analysis Dominion EnergyVirginia requests adoption ofTSTF577,Rev.1, "Revised Frequencies forSteamGenerator TubeInspections."
TheTechnical Specifications (TS) related tosteamgenerator tubeinspections andreporting arerevised basedon operating history.
Dominion EnergyVirginia hasevaluated ifa signifi'cant hazards consideration isinvo'Ived withtheproposed amendment(s) byfocusing bnthethree standards setforth in10CFR50.92, "Issuance ofamendment,"
asdiscussed below:
1 Doestheproposed amendment involve asignificant increase inthe.probability or consequences ofanaccident previously evaluated?
Respoonse:
Non
- m Theproposed changerevises theinspection frequencies forsteamgenerator tubeinspections andassociated reporting requirements.
Inspection frequencies
Serial No.:
21-214 Docket Nos.:
50-338/339 Enclosure Page3of4 are not an initiator toa steamgenerator tuberupture
- accident, oranyother accident previously evaluated.
As a result, theprobability ofanyaccident previously evaluated isnotsignificantly increased.
TheSGtubesinspected by theSG Program continue toberequired tomeettheSGProgram performance criteria andto be capable ofperforming anyfunctions assumedintheaccident analysis.
Asa result, theconsequences ofanyaccident previously evaluated are notsignificantly increased.
Therefore, theproposed change doesnotinvolve a significant increase inthe probability orconsequences ofanaccident previously evaluated 2.Doestheproposed amendment create thepossibility ofanewordifferent kind of accident fromanyaccident previously evaluated?
Response
No.
Theproposed changerevises theinspection frequencies forsteamgenerator tubeinspections andassociated reporting requirements.
Theproposed change doesnot alter:the design function oroperation ofthe SGs ortheability ofanSG toperform the'design function.
TheSGtubes continueto be required tomeetthe SGProgramperformance criteria.
Theproposed change does notcreate the possibility ofa newordifferent kindofaccident duetocredible newfailure mechanisms, malfunctions, oraccident initiators thatarenotconsidered inthe design andlicensing bases.
Therefore, theproposed changedoesnotcreate thepossibility ofa new or different kindofaccident fromanyaccident previously evaluated.
3.Doesthe.proposed
.amendment involve a significant reduction ina margin of safety?
Response:'No.
The roposed changerevises theinspection frequencied forsteamgenerator tubeinspections andassociated reporting requirements.
Theproposed change doesnotchangeanyofthecontrolling values ofparameters usedtoavoid exceeding regulatory orlicensing limits.
Theproposed changedoesnotaffect a
design basis orsafety
- limit, oranycontrolling valueforaxparameter established inthe' UFSARorthelicense.
Serial No.:21-214 Docket Nos.:
50-338/339 Enclosure Page4of4 Therefore, theproposed changedoesnotinvolve a significant reduction ina margin ofsafety.
Basedontheabove, Dominion Energy Virginia concludes that theproposed change presents nosignificant hazards considerationunderthestandards setforth in10CFR 50.92(c),
- and, accordingly, afindingof"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) suchactivities willbeconductedincompliance withthe Commission5sregulations, and(3) th'e issuance oftheamendmentwill notbeinimical to thecommon2defense andsecurity ortothe health andsafetyofthepublic.
4.0ENVIRONNIENTAL EVALUATION A review hasdete:rmined thattheproposed amendment would change a requirement withrespectoto,.installation oruseofa facility componentlocated withintherestricted area,asdefined Tin10CFR 20,orwouldchangean inspection orsurveillance requirement.KHowe.verc theproposed amendment doesnotinvolve:
(i) asignificant hazards consideration, (ii) asignificantchangemin the.types orasignificant increase inthe amounts ofany effluents that may:bereleased
- offsite, or (iii) a sinificant' increase
'inindividual or cumulative occupational radiation exposure.
Accordingly, itheproposed amendment meetstheeligibility criterion forcategorical exclusion set4forth in10CFR51.22(c)(9).
Therefore, pursuant to10CFR51.22(b),
no environmental:
.impact statement orenvironmental assessment needbeprepared in connection withtheproposed amendment.
j l
a p
Serial No.:
21-214 Docket Nos.:
50-338/339 ATTACHMENT 1 Virginia Electric andPowerCompany (Dominion Energy Virginia)
NorthAnnaPowerStationUnit 1andUnit2
Serial Nox21-214 Docket Nosx50-338/339 Attachment 1
Page1of6 Programs andManuals 5.5 5.5 Programs andManuals 5.5.7 M
This program providescontrols forinservice testing ofASME Code Class 1, 2,and3 components.Theprogram shallinclude the following:
- a. Testing frequencies specified intheASMECodeforOperation and Maintenance ofNuclear PowerPlantsandapplicable Addenda as follows:
ASMECodeforOperation and Maintenance ofNuclear Power Plants andapplicable Addenda Required Frequencies for terminology forinservice performing inservice testing activities testing activities Weekly Atleast onceper7 days Monthly Atleastonceper31days Quarterly orevery3 months Atleastonceper92days Semiannually orevery6 months Atleastonceper184days Every9 months At least onceper276days Yearlyorannually At least onceper366days Biennially orevery2 years At least onceper731days
- b. Theprovisions ofSR3.,0.2areapplicable to the above required Frequencies forperforming inservice testingactivities;
- c. Theprovisions ofSR3.0.3areapplicable to inservice testing activities; and
- d. Nothing intheASME CodeforOperation andMaintenance of Nuclear PowerPlants shall beconstrued tosupersede therequirements of anyTS.
5.5.8 W AnSGSteam-Generates Programshallbeestablished andimplemented
/
toensure thatSGtubeintegrity ismaintained.
Inaddition, the SGSteamGeneFates Programshallinclude thefollowing:
j a
Provisions forcondition monitoring assessments.
Condition monitoring assessment meansanevaluation ofthe"as found" condition ofthetubing withrespect totheperformance criteria
- forstructural integrity andaccident induced leakage.
The"as found" condition refers tothecondition ofthetubing during a
SGinspection outage,asdetermined fromtheinservice (continued)
NorthAnnaUnits1 and2 5.5-5 Amendments 369/360l
Serial No.:21-214 Docket Nos.:
50-338/339 Attachment 1
Page2of6 Programs andManuals 5.5 5.5 Programs andManuals 5.5.8 M
- a. (continued) inspection results orbyothermeans,prior totheplugging of tubes.
Condition monitoring assessments shallbeconducted during eachoutage duringwhichtheSGtubes areinspected or plugged toconfirm thattheperformancecriteria arebeingmet.
- b. Performance criteria for SGtubeintegrity.
SGtubeintegrity shall bemaintainedby meeting theperformancecriteria fortube structural integrity,accident inducedleakage, andoperational LEAKAGE.
1.Structural integrity performance criterion:
Allin-service SGsteam-genepates tubes shall retain structural integrity l
overthefullrangeofnormal operating conditions (including
- startup, operation in the power range, hotstandby, andcooldown),
andallanticipated transients included inthey design specification, design basisaccidents Thisincludes retaining a safetyfactorof3.0against burst undernormal steadystatefullpoweroperation primary to secondary pressure differential anda safety factor of 1.4 against burstapplied tothedesign basis accidentprimary to secondary pressure differentials.
Apart fromthe above requirements, additional loading conditions associated with thedesign basis accidents, orcombination ofaccidents in accordance withthedesign andlicensing basis,shall also be evaluated todetermine iftheassociated loads contribute significantly toburstorcollapse.
Intheassessment of tube integrity, thoseloads thatdosignificantly affect burstor collapse shallbedetermined andassessed incombination with theloads duetopressure witha safetyfactor of1.2onthe combined primary loads and1.0onaxial secondary loads.
2.Accident induced leakage performance criterion:
Theprimary tosecondary accident induced leakage rateifor anydesign basisaccident, otherthana SGtuberuptur.e, shallnot I
exceed theleakage rateassumed intheaccident analysis in termsoftotal leakage rateforallSGsandleakage ratefor anindividual SG.Leakage isnottoexceed 1 gpmforallSGs 3.Theoperational LEAKAGE performance criterion isspecified inLCO3.4.13,RCSOperational LEAKAGE."
NorthAnnaUnits1 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 forSGtubeplugging criteria.
Tubesfound by f
inservice inspection tocontain flawswitha depthequaltoor exceeding 40%ofthenominal tubewallthickness shall be plugged.
- d. Provisions for SGtubeinspections.Periodic SGtubeinspections shallbeperformed.
Thenumber andportions ofthetubes inspected and methods ofinspectionshallbeperformed withthe objective ofdetecting flawsofanytype(e.g.,
volumetric flaws,axial and circumferential cracks) thatmaybepresent alongthelength of the tube, fromthetube-to-tubesheetweldat thetubeinlet tothe tube-to-tubesheet weldatthetubeoutlet, andthatmaysatisfy 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 besuchastoensure that SG tube integrityismaintained untilthenextSGinspection.
A degradation assessmentshallbef performed todetermine thetypeand location offlaws towhich thetubesmaybesusceptible and,based onthisassessment, to determine whichinspection methods need to beemployed andat whatlocations 1.Inspect 100%ofthetubesineachSGduring the first refueling outagefollowing SGinstallation 2 Afterthefirstrefueling outagefollowing SGinstal
- lation, 100% of the tubesin 96
,,which definesthe 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-thi 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 AnnaUnits1 and2 5.5-7 Amendments 249/240 j
Serial No.:
21-214 Docket Nos.:
50-338/339 Attachment 1
Page4of6 Programs andManuals 5.5 5.5 Programs andManuals 5.5.8 M (continued) 2.(continued) m a.
W b.
W c.
W d
3.Ifcrackindications arefoundinanySGtube,thenthenext inspection foreachaffected andpotentially affected SGforf thedegradation mechanism thatcaused thecrackindication sha l
be at the next elingoutage
/
i 4.aspecM.sas).
Ifdefinitive information, suchasfrom examination ofa pulled
- tube, diagnostic non-destructave
- testing, orengineering evaluation indicates thata crack-like indication isnotassociated witha crack(s),
1 thentheindication neednotbetreated asa crack, NorthAnnaUnits1 and2 5.5-8 Amendments 2-69/240
Serial No.:21-214 Docket Nos.:
50-338/339 Attachment 1
Page5of6 Programs andManuals 5.5 5.5 Programs andManuals 5.5.8 W (continued) e.
Provisions formonitoring operational primary tosecondary LEAKAGE.
5.5.9 m Thisprogramprovides controlsformonitoring secondary water chemistry toinhibit SGtubedegradation andlowpressure turbine discstress corrosion cracking.
Theprogram shallinclude:
- 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, whichshallinclude monitoring thedischarge ofthe condensate pumpsforevidence 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,whichisrequired toinitiate corrective action.
5.5.10 A program shallbeestablished toimplement thefollowing required testing ofEngineered SafetyFeature(ESF) filter ventilation systemsingeneral conformance withthefrequencies andrequirements ofRegulatory Positions C.5.a,C.5.c,C.5.d,andC.6.b ofRegulatory Guide1.52,Revision 2,March1978,andANSIN510-1975.
- a. Demonstrate foreachoftheESF-systems thataninplace testof thehighefficiency particulate
,air(HEPA) filters showsa penetration andsystembypass
< 11.0%
whentestedinaccordance (continued)
NorthAnnaUnits1and2 5.5-9 Amendments 369/350 l
SerialNo.:21-214 DocketNos.:
50-338/339 Page6of6 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 W A report shallbesubmitted within 180daysaftertheinitial entry into MODE 4 following completion ofaninspection performed in accordance with theSpecification5.5.8,"Steam Generator (SG)
Program."
The report shallinclude:
- a. Thescope of inspections performed
- oneachSG, b-,W G
M A
e M
eL Thenumber andpercentage oftubes plugged todate,andthe effective plugging percentage ineachsteam generator, and 9r W
- b. Thenondestructive examination techniques utilized fortubes withincreased degradation susceptibility;
- c. Foreachdegradation mechanism found:
1 Thenondestructive examination techniques utilized; 2.Thelocation, orientation (if linear),
measured size(if available),
andvoltage response foreachindication.
Fortubewearatsupport structures less than 20 percent through-wall, only thetotal numberofindications needstobereported; 3.Adescription ofthecondition monitoring assessment andresults, including the margin tothetubeintegrity performance criteria andcomparison withthemargin predicted toexist attheinspection bytheprevious forward-looking tubeintegrity assessment; and 4.Thenumberoftubes plugged during theinspection outage.
d.Ananalysis summary ofthetubeintegrity conditions predicted toexist atthenext scheduled inspection (forward-looking tubeintegrity assessment) relative tothe applicable performance
- criteria, including theanalysis methodology,
- inputs, and results; f.Theresults ofanySGsecondary sideinspections.
North AnnUnits1 and2 5.6-5 Amendments a
Serial No.:21-214 Docket Nos.:
50-338/339 ATTACHMENT2 Virginia Electric andPowerCompany (Dominion EnergyVirginia)
NorthAnnaPowerStation Unit 1andUnit2
Serial No.:21-214 Docket Nos.:
50-338/339 Attachment 2
Page1of5 ProgramsandManuals 5.5 5.5 Programs andManuals 5.5.7 M
This program providescontrols forinservice testingofASMECode Class 1, 2,and3 componentsTheprogram shallinclude the following:
a.
Testing frequencies specified intheASMECodeforOperation and Maintenance ofNuclear PowerPlantsandapplicable Addenda as follows:
ASMECodeforOperation and Maintenance ofNuclear Power Plantsandapplicable Addenda Required Frequencies for terminology forinservice performing inservice testing activities testing activities Weekly Atleastonceper7 days Monthly Atleastonceper31days Quarterly orevery3 months Atleastonceper92days Semiannually orevery6 months Atleastonceper184days Every9 months At least onceper276days Yearlyorannually At least onceper366days Biennially orevery2 years At least onceper731days
- b. 'Theprovisions ofSR3.0.2areapplicableto the aboverequired Frequencies forperforming inservice testingactivities;
- c. Theprovisions ofSR3.0.3areapplicable to inservice testing activities; and
- d. Nothing intheASMECodeforOperation andMaintenance of Nuclear PowerPlants shallbeconstrued tosupersede therequirements of anyTS.
5.5.8 EW AnSGProgramshallbeestablished andimplemented toensurethatSG tubeintegrity ismaintained.
Inaddition, theSGProgramshall include thefollowing:
a Provisions forcondition monitoring assessments.
Condition monitoring assessment meansanevaluation ofthe"asfound" condition ofthetubing withrespect totheperformance criteria forstructural integrity andaccident induced leakage.
The"as found" condition refers tothecondition ofthetubingduring a
SGinspection outage,asdetermined fromtheinservice (continued)
NorthAnnaUnits1 and2 5.5-5 Amendments
Serial Nox21-214 Docket Nosx50-338/339 Page2of5 Programs andManuals 5.5 5.5 Programs andManuals 5.5.8 M
- a. (continued) inspection results orbyothermeans,priortotheplugging of tubes.
Condition monitoring assessments shallbeconducted duringeachoutage duringwhichtheSGtubesareinspected or plugged toconfirm thattheperformancecriteria arebeingmet
- b. Performance criteria for SGtubeintegrity.
SGtubeintegrity shallbemaintainedby meeting theperformancecriteria fortube structural integrity,accident inducedleakage, andoperational LEAKAGE.
1.Structural integrity performance criterion:
Allin-service SGtubesshallretain structural integrity overthefull l
rangeofnormaloperating conditions (including
- startup, operation inthepowerrange,hot
- standby, andcooldown),
andallanticipated transients included inthedesign specification, design basis accidents This includes retaining a safetyfactor of3.0against burst undernormal steadystatefullpoweroperation primary to secondary pressure differential anda safety factor of 1.4against burstapplied tothedesignbasisaccidentprimary to secondary pressure differentials.
Apartfromthe above requirements, additional loading conditions associated with thedesign basisaccidents, orcombination ofaccidents in accordance withthedesignandlicensing
- basis, shall also beevaluated todetermine iftheassociated loads contribute significantly toburstorcollapse Intheassessmentof tubeintegrity, thoseloadsthatdosignificantly affect burstorcollapse shallbedetermined andassessed in combination withtheloadsduetopressure witha safety factorof1.2onthecombined primary loadsand1.0onaxial secondary loads.
2.Accident induced leakageperformance criterion:
Theprimary tosecondary accident induced leakage rateforanydesign basisaccident, otherthana SGtuberupture, shallnot exceedtheleakage rateassumed intheaccident analysis in termsoftotalleakage rateforallSGsandleakage ratefor anindividual SG.Leakage isnottoexceed 1 gpmforallSGs.
3.Theoperational LEAKAGE performance criterion isspecified inLCO3.4.13,"RCSOperational LEAKAGE."
NorthAnnaUnits1 and2 5.5-6 Amendments
Serial Nos:21-214 Docket Nos.:
50-338/339 Attachrnent2 Page3of5 Programs andManuals 5.5 5.5 Programs andManuals 5 5.8 W
(con tinued) c.
Provisions forSGtubeplugging criteria.
Tubesfoundby inservice inspection tocontain flawswitha depthequaltoor exceeding 40%ofthenominal tubewallthickness shallbe plugged.
- d. Provisions for SGtubeinspections.Periodic SGtubeinspections shallbeperformed.
Thenumberandportions ofthetubes inspected and methods ofinspectionshallbeperformed withthe objective ofdetecting flawsofanytype(e.g.,
volumetric flaws,axial and circumferential cracks) thatmaybepresent alongthelength of the tube, fromthetube-to-tubesheet weldat thetubeinlettothe tube-to-tubesheet weldatthetubeoutlet, andthatmaysatisfythe applicable tubeplugging criteria.
The tube-to-tubesheet weldis not partofthetube.Inaddition to meetingtherequirementsof d.1, d.2,andd.3below,the inspection
- scope, inspection methods, andinspection intervals shallbesuchastoensure that SG tube integrity ismaintained untilthenextSGinspection.
A degradation assessmentshallbe performed todetermine thetypeand location offlawstowhich thetubesmaybesusceptible and,based onthisassessment,to determine whichinspection methods need to beemployed andat whatlocations.
1.Inspect 100%ofthetubesineachSGduring the first refueling outagefollowing SGinstallation.
2.Afterthefirstrefueling outagefollowing SGinstallation, inspect 100%ofthetubesineachSGatleast every 96 effective fullpowermonths,whichdefines theinspection period 3 Ifcrackindications arefoundinanySGtube,thenthenext inspection foreachaffected andpotentially affected SGfor thedegradation mechanism thatcaused thecrackindication shallbeatthenextrefueling outage.Ifdefinitive l
t information, suchas fromexamination ofa pulledtube, diagnostic non-destructive
- testing, orengineering evaluation indicates thata crack-like indication isnot associated witha crack(s),
thentheindication neednotbe treated asa crack.
NorthAnnaUnits1 and2 5.5-7 Amendments
Serial boo.:
21-214 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 tosecondary LEAKAGE.
5.5.9 m Thisprogram provides controls formonitoring secondary water chemistry to inhibit SG tube degradation andlowpressure turbine idisc stress corrosioncracking.
Theprogram shallinclude:
- a. Identification ofa sampling schedule forthecritical variables and;controlpointsforthese variables;
- b. Identification oftheprocedures usedtomeasure thevaluesof the-cri'tical variables;
- c. Identification ofprocess sampling points, whichshallinclude monitoring thedischarge ofthecondensate pumpsforevidence of 1
'co'ndenser inleakage;
- d.Proceduresfor
-therecording 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,whichisrequired toinitiate corrective vaction.
5.5.,10 s
A.program shallbe-established toimplement thefollowing required
,testingxofEngineered5Safety Feature(ESF) filterventilation systems
>in!generalconformance withthefrequencies andrequirements
>ofRegulatorysPositions C.S.a,C.5c,C.5.d,andC.6.bofRegulatory Guide.1.52,xRevision 2,March1978,andANSIN510-1975.
an Demonstrate foreachoftheESFsystemsthataninplace testof thehighefficiency particulate air(HEPA) fi1ters showsa penetration andsystembypass
< 1.0%whentes'ted inaccordance (continued)
NorthAnnaUnits1 and2 5.5-8 Amendments
Serial No.:21-214 Docket Nos.:
50-338/339 Attachment 2
Page5of5 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator TubeInspection Report A report shallbesubmitted within 180daysaftertheinitial entry into MODE 4 following completion ofaninspection performed in accordance withtheSpecification5.5.8,"Steam Generator (SG)
Program."
The "report shallinclude:
- a. The.scope of inspections performed
- oneachSG,
- b. The1nondestructive examination techniques utilized fortubes withincreased degradation susceptibility;
- c. For:eachsdegradation mechanism found:
- L <Thenondestructive examination techniquesutilized; 2
The.1ocation, orientation (if linear), measured size(if x.available),
andvoltageresponse foreachindication.
For
.'tube swearatsupport structures lessthan20percent xthrough-wall, onlythetotalnumber ofindications needsto bereparted; 3..aAdescription ofthecondition monitoring assessment and resuTts,"including themargintothetube integrity
~performance criteria andcomparison with the margin sspredicted
~to=
existattheinspection bythe previous eforward-looking tubeintegrity assessment;and 4.':The inumber oftubesplugged duringtheinspection outage xd An.analysis
.summ'ary ofthetubeintegrity conditions predicted n.
toex:ist at,thenextscheduled inspection (forward-lookingtube s
x
- integrityassessment) relative totheapplicable performance
[
criteria.,
.inclu'ding theanalysis methodology,
- inputs, and results; i
- e. Thenumber andpercentage oftubesplugged todate,andthe effective pl:ugging percentage ineachsteamgenerator, and Af.
' Theresults ofanySGsecondary sideinspections.
NorthAnnaUnits1 and2 5.6-5 Amendments