L-12-331, Technical Specification 5.6.6.1 - Steam Generator Inspection Report
| ML12299A088 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/24/2012 |
| From: | Harden P FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-12-331 | |
| Download: ML12299A088 (10) | |
Text
{{#Wiki_filter:FENOG Beaver ValleyPower Station P.O.Box 4 FlrstEnergy NuclearOperatlngCompany Shippingport,PA 15077 Paul A, Harden 724-682-5234 Sife Vice President 724-643-8069 October24, 20Lz L-12-331 ATTN: Document ControlDesk U . S ,N u c l e aR r e g u l a t o rCyo m m i s s i o n Washington, DC 20555-0001
SUBJECT:
BeaverValleyPowerStation,UnitNo. 1 DocketNo.50-334,LicenseNo. DPR-66 Technic-al Specification 5.O6,1 - SteamGeneratorInspeqtion.Report ln accordance withTechnical Specification 5,6,6.1, FirstEnergy NuclearOperating Companyherebysubmitsinformation relatedto steam generator inspectionspeformed duringthe BeaverValleyPowerStation,UnitNo. 1, spring2012refueling outage.The enclosedreportincludes the required informationaboutthe inspections, including tabulations of steamgenerator examination resultsfor tubesin theA, B, and C steam generators. Thereare no regulatory commitments containedin this letter.lf thereare any questions or if additional information is required, pleasecontactMr, ThomasA, Lentz,Manager-FleetLicensing, at (330)315-6810. PaulA. Harden
Enclosure:
Unit#1 - 1R21SteamGenerator '180DayReport cc. NRCRegionI Administrator NRCResidentInspector NRCProjectManager Director BRP/DEP SiteBRP/DEPRepresentative
Enclosu re L-12-331 U n i t# 1 - 1 R 2 1S t e a mG e n e r a t o1r8 0D a yR e p o r l (B PagesFollow)
OPERATINC F I R S TE N E R G YN U C L E A R GO M P A N Y Technical Services Department Engineering NuclearEngineering ProgramsSection lssueDate:September 4,2012
Subject:
Unit#1 - 1R21SteamGenerator 180DayReport Preparedby: Date:qloqltz SteamGenerator m Owner
't- ' t-Reviewedby: Date: Q' ActingSupervisor,Nu ar Programs
/') , i(
Approvedby: CarlBattistoneLq^J-Y WTf," Date: ActingManager, Technical Services
gn Requlled"b,vTechnfcal.I peclfication 5.6.6,1 Inforrn?,t! Technical Specification 5.6,6,1 requires roportlngof thefollowlng information aftercompletion of an inspoction performed inaccordance withSpeclfication 5,5,5.1, "Unit1 Stearn Generator Program", lnformation requlred byTS 5.6.6,1 ls provided belowforactivities performed durlngthespring2012 refuelingoutage(1R21),Referto theDefinitions of Abbreviations, Codes, andReporting Termlnology section of thisrepoftforabbreviations, codesandotherterrns usedlhroughout thisreport, a) Scopeof inspections performed on eachstearngenerator: Prirnary Slde: a 50 percenl fulllengthbobbin probeexaminatlon (Rows3 andup) a 50 percentbobbinexamlnallon of hotandcoldlegstralght sectlons in Rows1 and2 a 50 percentPlusPointprobe(magnetically biased) inspection of all Row1 and2 U-bends c 100 percent PlusPointprobeinspectlon of tubesheet dlametrlcal over-expansions andbulges reported fromthepre-serulce examination at 10.0inchesor hlgherreferenced frornthehotleg tubeend,ontubesin the50 percent bobbln coilinspectlon program Hot and coldlegtopof lubosheet PlusPoint probe inspection 360degrees aroundthetube bundle periphery andtubelanoregion(twoto threetubesdeopIntotubebundle) 100percent PlusPointprobeinspection of bobbin coilslgnals reported asan "l-code" PlusPolntprobetesting of anyspeclal interest tubes/locations, as required Visualoxamlnations werepefformed of thedivider plateto channelhead wefd,thetubesheet to stubrunnerweldandstubrunnerto dividerplateweld.Theseexaminatlons wereperformed in response toWestlnghouse Nuclear Safety Advisory LetterNSAL-12-1, "Steam GeneratorChannel HeadDegradation," January 2A12andNRCInformation Notice lN 2010-07, "Weldlng Defects in Replacement SGs,"April2010,Noanornalies werenoted, Visualexamination andaccountabllity of tubeplugs(as-found andas-leftcondltlon). Thisis performed as partof theroutlne steamgenerator inspectlon process eachtirnetheprlmary slde is opened,During1R21,theexaminatlons verifled thatthecorrect number of tubeplugswere presentandIn thepropertubelocations. Noanomalies w6rereported. Secondary Slde: A vlsualinspection of thesecondary sidetubesheot face,annulus, andtubelanewasperforrned durlng1R21ln allthreesteamgenerators. Forelgn objectsearch andretrieval (FOSAR) was alsoperformed. Oftheslxty-eight obJects identifled duringtheFOSAR inspectlon, allbuteight objectswerCI retrleved, Foreign rnaterlafthatwasnotremoved frornthesecondary sideof the steamgenerators wa$evaluated anddocumented in Westinghouse LetterFENOC12-74, "Transmittal of Evaluatlon of Secondary SideLooseParts- 1R21Refueling Outage."Basedon thisevafuatlon, theforeign materlal thatremalned in thesecondary sideof thesteamgenerator wasdetermined to beacceptable forcontlnued operatlon (1,e., tubeintegrity wouldbe maintained at for leastthreemore operating cycles).Table1 contains a listof thematerial not retrievod fromthesecondary sideof thestoam generators and provides (a)a descriptlon of the foreignmaterial leftin eachsteamgenerator, (b)thelocation of theforeign materlal, and(c)the finalevaluation of theforelgn material. Forthosetubelocations wherepotential loosepartindications werereported fromthe1R21 eddycurrent examinatlons (e.9.,bobbln collor PlusPolntprobes) andnovisualinspection was performed at lhoseparticular tubelocations, thePlusPolntprobewasusedto vorlfythatno degradation or tubewallwearwaspresent.Thosotubesremained Inservice,
b) Actlve(1) degradation mechanlsrns found; Thefollowlng existing degradatlon mechanlsms wereobserved during1R21:
. Wearat tubesupport platelocations
. Wearat antl-vlbratlon barlocations c) Nondestructlve examlnatlon techniques utiflzedfor eachdegradation mechanism:
Forthedegradatfon mechanlsrns observed during1R21,bobbln collprobe$ wereusedasthe prlmarymethodof detection exceptat or belowTTS,lowrowU-bends wherebobblnprobesarenot quallfied. Intheseareasr PlusPointprobes wereemployed, PlusPolntprobes werealsousedto re-examine anyamblguous bobbin collslgnals thatwerereported, The1R21examination technlques werequalified, fordetectlonandslzing(asapplfcable) of the existing andpotential degradation mechanisrns llstedin the1R21degradation assessment, In accordance withAppendices H andlof theEPRl,"Steam Generator Management Program: Pressurized WaterReactor $teamGenerator Examinatlon Guidelines, Revision 7," 1R21Examinatlon Technlques Usedfor Degradation Detection/Slzlng DegradationMode TubeLocation Probe EPRIETSS, Freespan Differential Bobbin 128413 Slsnals Freespan Manufacturing Burnish AllLocatlons Bobbin 9601 0.1 Marks Absolute DriftSisnals Freespan Bobbin 96010.1 TubeWear Anti-Vibration BarIntersectlons Bobbln 96004,1 TuboWear TubeSupport Plateslntersections Bobbin 96001,1 Bobbln t28413 TubeWear Tubesheet Periphery, TubeLane 3 CoilPlusPoint 21998.1 Bobbln t28413 Volurnetrlc Signals Entire TubeLength 3 CollPlusPoint 2 19 9 8 . 1 20510,1 PWSCC Tubesheet Region 3 CoilPlusPoint 20511 ,1 AxialODSCC Dentsat AVBs(> 1 volt),Dentsat 3 CoilPlusPoint 22401,1 TSPs(> 2 volts),Dinqs(> 5 volts) (2)- TheEPRIExamlnatlon Technlque Speclficatlon Sheet(ETSS)is llstedforreference only. Stte-speclflc ETSSsaredeveloped prlorto eachsteamgenerator lnspection foreachexistlng and potential degradation mechanism in the1R21degradation identlfled assessmont, Thesite-specific ETSSsaredeveloped in accordance withAppendlces H andI of lheEPRI,"Steam Generator Managernent Program: Pressurized WaterReactor SteamGenerator Examination Guidellnes, Revision 7." Theexamination technlques utilized during1R21areconsidered "$iteValidated" as dofined ln the EPRI,"SteamGonerator Management Prograrn: Pressurized WaterReactor SteamGenerator Examination Guldellnes, Revision 7," fotoachexisting andpotential degradatlon mechanfsm llsted Inthe1R21degradation assessment, (1)- Per the EPRI,"SteamGonerator Managoment Program:SteamGoneralor Integrlty AssossmentGuldellnes," ls nowusedIn lieuof theword"actlve" Rovlslon3, lhe word"exl$llng" whondescrlblng lhathasboen dogradatlon prevlously and/orcurrently obeervod In thestoamgenerators,
d) Location, orientation (if linear),andmeasured slzes(lf avallable) of serviceInduced indlcationsl The1R21stoamgenerator examlnatlon results areincluded in theAttachmont andprovlde the followinginformation (a)locatlon, (b)orientatlon and(c)measured slzesof servlce-lnduced indlcatlons, 1 ) Bobbln probeIndlcations reporled as "l-codes" werere-lnspected withthePlusPolntprobe,lf thepluspolntprobeIndlcated thatnodegradation or ffawswerepresent, thetubewould remainIn.service, lf the Plus Polnt pronjinOicated that degradation or flaws werepresent, the tubewouldbe rernoved fromservlce vlaplugglng,
- 2) NewAVBindica6ons reported fromthebobbinprobelistedas PCTwerere-inspected with.the pluspointprobe,lf theplusPointprobeindlcaied nocrack-llke flaws were present within the wearscar,a wearcall(WAR)wouldbeasslgned to thePlusPoint report, e) Numberof tubespluggeddurlngtheInspectlon outagefor eachactivedegradation rnechanism:
Notubeswereplugged during 1R21. Totatnumberandpercentage of tubespluggedto date: Thetotalnurnber of tubesplugged asof iheendof 1R21ls ono(0.01percent)' s) Theresultsof conditionmonitorlng, includlng the resultsof tubepullsandIn'sltutesting: Duringthe1R21stoamgenerator lubeinspections, no lndications wereobserved thatexceeded the itmit*Tor struit[rattntegiity ettheraxlalor ilrcumferential (burst degradation Integrity greater than threetimes normhl operating primary to secondary pressuredifferential). Notubescontained lndicationsthatcoutci poteniially chailenge thetube'lntegrity recommsndations of NEI97'06, Revision 3, "SleamGenerator Program Guidellnes." Basedon theIndlcations obserued at 1R21 , lhe steamgenerator tublngis expected to meetall operational structural andleakage Integrlty requirem"nts at end-of-cycle 24 which is thenextoutage wh"n primary sideinspectlons ire scn6OriteO. Noneof theIndlcatlons rep_ortedduring 1R21 represented'a leakagd potential at postulated malnsteamlinebreak conditions. h) Theeffective plugglngpercentage for allplugglngIn eachSG: Thefolowing tableliststheplugging percentages foreachsteamgenerator as of theendof 1R21'
$G TotalTubesPlugged Percent Plugged RC.E.1A 0 0,00 RC-E.18 0 0.00 RC.E-1C 1 0,03
p H N N c.l F{ z d) g g t) c) {) {-, t) f.l {) rd o o H o
+,
z z EE,z z z z o o o B ol c) () c) () {t) o 4) V) v7 u (t) Q
- 0) n) O
{.) O() d)(u {,) v) (/) v) ul I a F{ F.'t gz o v, o o o . o o 7 zzzz U) (l)
).r tq k
.f) H o
t-, ct l.i q) H a FI (, zo EIzIE, a ,o o E cl o FIE trl I
&l
- 7. Z z
{-) mH t d
*, o
.{1 EN )- E
)- vot tl oa rl H<
hoa
\{
F( r-\ { FIF F tt
#l#lsl# #l* d o
I irv o
.({ t* : j FI
.JJ i< tr hF frI a O lal (n <) ,8 y, cn (J \n t'- r.t ca ca crl O
r.- aaO Flr{ r{h ,-{ crl o O q () () () a F{0Jk tEl O o o a a o o c, Pq,E H H 6.Et E.E F i l o oqU l'E
'a v) )
)ri H
H alo
\lO (n o N \ O O o a
<) ( Q O o F$'
- lcd a c.l lN O ni (rl q .1 ct! . EE <
'5 t\
F dlo o c> o e O EEs O l! F{ tre oN Fo .Oo>' Hg0 () m.A F (J () c) z rrl q
? a O e o o rl \n O O o O n tr- vl r4 fa O E.E t,9 c i
E ! tsl{ E c) O Ff .s I
.D O O O o
,4 V)
H I Bb A tr b0 d) I t'l l-{ H
.Fl o
}l'
'rJ U
o ,g B
+,
l*a o o UU E no .F' o
+)
q T1 O o ;iH
.p$b k
o H ' Hq fjq F HfrE F{ o o\ cn a4 v v \f cfl co f.l
' F nU o &
rE E6g tr Fl o \f an lrl O v ,EHvr' H V
\n re \o \o \n cl p sg#
- 6) tf't N U
lH{ 0)dx z q)
'E'H
-=u L A e '
C);i a) () F (uo (.),g .u o) o a o F EF s H U s (n o O
.:4 ta
{s () v) .a d J4 P{ o (\, s a) H F oct _q 4 o ut s { Fh eO p gl E E' f'l A H,E6
' 6HtOA ro.
N e{ \o C) r< O o r-{ a <) <) FAq a m H r{ O
)+{
al r-a ra F{ O ca O O O a r\ EAg
-i.i; a){)dJ Hl<pq pq fi pa (J O ooo zzz
of Ahbrevlaljorls, D.efiqitigns GoCeq, and RepgrtinqTer,minolqsy 3 LetterCodeDefinitlons Term B o b b l nG o i lP r o b e DSI Distorted TubeSupport PlateSlqnal withPossibleIndlcation PCT Percent Throush Wall Term PlusPolntProbe SVI Sinqle Volumetric Indication WAR Wear Addltlonal Deflnltions Term Definitlon AVB Anti-Vlbration Bar EPRI Electrlc PowerResearch Instltute FOSAR ForeignObjectSearchandRetrieval ODSCC OulsideDiameter StressCorrosion Crackins PLP Posslble LoosePart PWR Pressurized WaterReactor PWSCC PrlmaryWaterStressCorrosion Crackinq SG SteamGenerator TSC Tubesheet " ColdLeq(Secondarv Face) TSH - TubesheetHotLoq (Secondary Face) TSP TuboSunporl Plate TTS Topof Tubesheet
1R21SteamGenerator Exarnination Results TheAttachmentprovides thesteamgenerator oxamination results fortubeswithservice-induced indications, Referto thefollowing tablesfora description of thetermsusedin the Attachment. Descriptionof ColumnHeadlngsand DataAbbreviatlons Usedin StearnGeneratorExamlnationResults ReportHeaderDefinitions Definitlon ROW/COL Row& Column of tubelocation Tvpeof indicatlon Locatlon of noarest support structure Indlcationdistance fromnearest support structure Fieldmeasured percont throuqh wallof indlcatlon LENGTH Fieldmeasured lenqthof indicatlon Fieldmeasured phasea le of indlcation Fieldmeasured voltaqeamplitude of indlcation Fiefdrneasured anqular rolation of indlcatlon channelof indicatfon Startinqpointof examination Endpointof examlnation Examinatlon ExtentDefinltlons (FROM - TO) Term Deflnition TEH TubeEnd- HotLeq TSH HotLeqTubesheet (Secondarv Face) TEC TubeEnd- ColdLeq TSC ColdLeoTubesheet (Secondary Face) 01H FirstTubeSupport Plateon HotLesSlde 01c FirstTubeSupportPlateon ColdLeq Side AVBl Bar(Numbered FirstAntl-Vibratlon hotleqto coldleq)
ATTACHMENT Beaver Valley PowerStation, UnitNo 1 1R21Examlnation Results (TUBESWrTHSERVTCE TNDUCED TNDICATTONS) RC.E.1A
$G ROW COL IND LOC I N C H %TW LENGTHANGLE VOLTS PHASE CHAN FROM TO A 6 eB DSt 01C 0.54 0.16 41 P1 TEC TEH A 6 98 SVt 01C 0.54 0,09 267 P4 01C 01C A 6 98 PCT 01C 0.54 1 7 0.09 84 P4 01C 01C RC-E.18 SG ROW COL IND LOC INCH %TW LENGTH ANGLE VOLTS PHA$E CHAN FROM TO B 38 78 DSI 02H 0,46 AJ4 97 P1 TEC TEH B 3B 7B SVI 02H 0,48 0.11 135 P4 02H 02H B 38 78 PCT 02H 0,47 1 9 0.11 135 P4 02H 02H RC-E-1Q SG ROW COL IND LOC INCH % T W L E N G T H A N G L E VOLTS PHASE CHAN FROM TO c 1 20 DSt 03c 0.34 0.13 61 P1 O7C TEC C 1 20 SVI 03c 0,38 0,08 127 P4 03c 03c c 1 20 SVI 03c 0.42 0.08 274 P4 03c 03c c 1 20 PcT 03c 0.46 1 5 0.08 134 P4 03c 03c 1 20 PCT 03c 0.48 1 6 0,09 90 P4 03c 03c}}