ML080290674
| ML080290674 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/12/2005 |
| From: | Consumers Energy |
| To: | NRC/RGN-III |
| References | |
| FOIA/PA-2008-0046 EA-ELEC08-0001, Rev 12 | |
| Download: ML080290674 (23) | |
Text
.Attachment I Revision.12
'Page 1-of11 CONSUMERS ENERGY PAUSADES NUCLEAR PLANT EIk*,INEERING ANALYSIS COVERSHEET EA-o NmEr tSECO&CM~
hUencedtalnhbL Cgbculatb~io irthSaodr Colmtlietaone INITIATION AND REVIEW Calbulati*n Statusý
.Rev, Desi~lpilon 0
orIginalIssue 1
See;Record-01 Revislon Sheet, Revise Feedwater Error 2
See'Recordof:Revi'sion Preliminar
- PeOnding, Final Superseded 0
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Initiated miht ReView MethOdý Technicaily
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PALISADES NUCLI,R PLANT A*NALYS'IS i C
lNT IWATION SHEET
'EA-ELECO08,O001 Sheet 2 of`20` Rvio 2 REC*ORDOF REwVSION Reviision'Number 1
Descriptionh Of Change.
- F;A-ELEC08-0004, 'UncertaintyvCalculation for UFM Gorrected, Density
(:ompens.ated, Total.Feedwater Flow.Measurement (PPC Only)" has been 3iývised *Which.resulted in an in&cease'in the, Total Loop Uncertainty used as n.inputto this calculation.; The.uncertaity ofthe temperature input to the eat balance changed dUe to the revision of EA-ELEC08-0004. The xp*ected power uprate p!ant peo'atingparameters-areinicluded in 2ection
.1.1 as a major assumption.
he, indicated calculation-.status on the cover 'Sheet has been changed to
!0ending.
0ection 1.0; Added, reference to p0ower uprate, i*ection:3.2.3; Changed dW*ctd 28,614.9, Ibm/hr iection 3.2.7;,Changed T, wto.+/-3.636F and3.ý41.34aFAto,3.625ý1 F ect7io 4.1.ý;Added this section to provide plaiit parameters.expected ollowinig the power uporate.
,3ection 5.1; Changed Total Uncetdainty,(Uncorrected). to
+1.13% Power -1.21%q/'o. Power s3ection 5.2;, Changed Ttotali Uncertainty(Corrected).to
+0.49%%Power,
'0.55%
Powerý 3eCtion 7.0; *Changed Total Uhcertainty (Uncorrected) to
+I.13% Powerý -1f2% %Power ChAngedt TotaflUncertainty (Corrected) to
+0.49%P0Woer, -0,55% Power S.eption 9.p9; Changed'the'revision level to Rev.1 Section 9.11; Changed
,to RI-24A Revisibn,o.
.Section 9:;12;. Added RI-24B Revisi0n 0.
Revised Total Feedwater flow enibr, (dWFwc)) from' 28.6,149 Kibm/hrto 29:-389 Klb-m/hr based on IEELE C08-004, "Unceitainty Calculation for UFM Corrected, Density.Compensated 'Total Feedwater Flow.
Measurement (PPC Only)." Error was changed based on a change in location of the UFM measruring the B feedwater loop-flow.
2
PALISA~pES HU.;LEAR.PLANT EA-ELECO8-0001 ANALYsiS cONk INUATTIONWSHEET 2Sheet 2 of 2lRevlIon.2 RECORD OF REVISION Revision Numbedr Description Of Change EA-ELEC'O,0*0,
"!Uncertainty CaicUlation ifor UFM Corrected, Density Compensated, Total FeedwaterFlow Measuremient (PPC Qnly)",has been revised. wvhichr"esultedin*inincr'ease in the-Total Loo6p Uncertainty used :as an in put to, th.s calculation. The uncedtaintyrof the temperatUreinpUtto the heat balance changed due to therevision of EA-ELEGC8,-0004. The
- expeted power uprate plantoperating'parameters are included in Section 4.1.r1 as a majOr assumption.
Theý irdicated'calculation:: status on the cover.sheet-has:been changed to Pending.
Section 1.0; Added' reference'to power uprate.
Section3.12.3; Changed dWFwc t6 28,'6144.9 Ibm/hr Section: 3.2.7; Changed, Tw to +/-3.63°F and.,31.41340 F to i.3.6251°F ISectiohn4.1.1; Added this section to provide plant parameters expected following the power uprate.
Section 5.1; Changed Total Uncertainty (Uncorrected) to,,
!+.1.13% Po'er -1.21I%.Power(
Section 5`2; Change d Total Uncertainty (CQorrected) to
+0.49%RPoWer, -0.55% Power Section 7.0; 1Changed,Totl Uncertainty (Uncorrected),.to
+T.1.3% Power -1.21%,Power, Changed Total Uncertainty (Corrected) to
,0.49% Power, -0.55%, Power Section 9.9; Changedithe revision level 'to Rev.1l Section ;.11;:hanged dto Rl-24 ARevision 0.
section 9.12;,Added Ri-24B Revsion 0.
2 :Revised Total Feedwater flow error, (dWrWc))ý fRom28,6014Klbm1hr to 9.,389 Klbm/hr based on EA-ELEC08-004,. "'Uncertainty:Calculation for JFM Corrected, Dehnsity Compiensated Totall Feedwater Flow A.,ieasuremenht(PPC O'Orily)," Error was chariges based,on,a change in cation of:the UFM measuringthe B feedwater loeop flow.
PALISADES NUMC.I-1ARPLANT EA-ELECO 08001 ANALYSIS CONTiil!IA'T"TION SHEET Sheet 3 of*2oWRbvision 2 1.0 OBJECTIlVE SCOPE This calculatib
,n will compute the uncertainty associated with.the secondary calorimetric heat balance ;alculation with and without the Ultrasonic FTow Meter correction factor.
Heat balanc:,, uncertainties are computed for the manual heat balancecalcUlation
.performed.th* iugh performance of DWO-1 with utilizing the power upratbevalues (Re.fe ren ce*." 10):.
2.0 FUNC-TION/.
D,,-,
- ESCRIPTION The Steam (:.:nerators (.S.G) :serve to r'emove energy from the PrimaryG Coolant System
(.PCS) and s&, tiply high quality steam to.the main tur*bin and.vtarious :auxiliary services.
steam exits p:ie SGs through two 36'" headers (Main Steam Lines). Each Main Steam Line
-(MSL)
Cjntains a Main Steam psolation ValVe which provides the ability to isolate the MSL fro'rn lth:e bremainder of the secondary system., An accurate caiculation of Reactor po* ris. obtained byperforlming a seco6ndary he~at balance.
The e quatio usedtoi perfor the.Secondary Calorimetric power,..calculationisd*erived as follows::
Applying the 1, st Law of Thermodynahmics-,(Conservation ofEnergy) top!the:Primary Coolant Sys';i::m (POS) yields the following energy equation:
.Z.EncE.gy*N -EnergyUT 0
Note:- Steadi s~tate:conditions are, assuimed:.
Fortlhe. PC$, it is reasonable to assume'that no external work is performed and changes in kinetic rencv-,gy areý negligible. Tterfore,i.%,toh heI at 60u*cesarid heat-iksin-the PC.S'nbed;itc~ij bec,ýonsidered..*h folowingd hekat sourcesgl itouce energ,(Q) 'into thte Primary Coo' tntfSystem:
aRe>:. ctor (Qkx) o Prinary Coolant Pumps(Qpcp)
'p-i-,
ssurizer Heaters (QPz,)
. cl'~rging Flow (QcH)
The followin,,:, heat sinksr remove, energy* (Q)0 from the Primary.Coolant System:
Stliam Generators (QSG) a LEcI own Flow (QLD) oF Fi:,,d Insulation Losses (QFL)
PALISADES NUOý LEAR, PLANT EA-ELECO8-0001 ANALYSIS CON I INiJiON' SHEET..
Sheet.4 of 20 Revision 2 Substitutini,; the.heat sourceS and heat sinks into. the.,energyequation and solvihg for QrOx yields 4i., e following equation:
Q Q
+/-QLD :QFL -QFL QPzR -QCP Note: Enie! jy removed fro0m the Priimary-Coolant System due to, POS lSeakage, is con* idered to benegligibleband is not included in theReactor Power equation.
Per Referer.ce 9.7, the energy terms associated withtheprima' coolant pumps, letdownflov., charging tflow,, fixede insulation lossess and*the pressurizer *haterse are
&o~mbin-ed iiir;to one.const-ant value (C). Therefore; the energy equation is simplified as follows:
QRx;:I*:Q~SG,-:*C'
,Per Referene 9. 7, the value of CGwil.vary,:depending on'the: number oftcharging pumps,
/lIetdown or 0ices in service. (up.to 3 total). Reference 9.7Tdetermines a conservatively Iow'value.6o C for each combination.with the following :results:!
C 9.t72M h (one orifice)
C =, 8.52VMWth (two orifices)
C 7; 14MWth (threeeorifices)
DWO-1 is u,ized to compute the valueof QSG given in the:equation presented above.:
The determil,ation. of the.Steam Generator-term (QsG),requires the:application of the energy equAiion with the*Steam Generato'rlconsidie~red ýas *the control volume:
- The folJowin, heat.sourcesihntroduce energy-in-to the :Steam.Generators:
SEi: rgy ::fromthePOS (QsO)
The foilowin: rheat sinksý remiove energy from the,SteamGenerators:,
o B;t ddown Flow (.Q 6)
SSti;am Flow (QSt):
Substituting tieheat sources and heat sinks, into thebenergy equatiohrand Solving for QSG yields,tlhr followingequatioh:.
'SG ;*QST+QB -BQFw
PA/LISADES NUCLII !AR PL,*ANT EA-ELECOM08OO1 ANALYSIS,CONTlI'djJATtON SHEET Sheet 5 of20 Revision 2 3.0 ANALYSIS lHiPUTs 3.1 HEAT BALA.CE UNCERTAINT EQUATiON Per'Referen(':.4,.9,j the following equation repteSents the heat balance calculation as
-computed by- :WwO1l QSG =,(435.8 4+.1753 PsG -1.1O0 4 5Tw + X(851.7-89-6 020257PSG))W*
'x (85:1 789--O.20257 PS'G) WiaD QSG = -*eat, removed fromr the PCSi by the Steam Generators- (btu i.ihr)
PSG -Steam.Generator'Pressure (psia)
TFw '17eedwater-Temperature (0F),
X.
= Sr*team. quality (unit-less).
WFW"*=' 'eedwatet flow (Ibm I hr):
Note: The eq: ujation given. above is simplified in DWO;-.1 and broken down irito multiple steps. 'Steam quality is noi measured when performing.the heat balance.
The effects cl instrunment uncertainties on the heat balance are comput~d by taking.the
'total derivati.:,bof~the.,overall energyequation given aboveas follows:
d'sG
-WSG d
+
SG'
____QS
"..WF awD
+
dSG",-
- T
÷ G d
.Using the mc",, hodologydescribed, in References,9.1 and 9.2,Athe individual..randrom
,uncertainy t"m ms are co mbi nhed using the Square. Root. Sum of Squares rnethodýýas' follows:
dQSG.
a~W
~
b)2~S dW8 0
j (SG, dýsG
+
dTFJW
(;
dýj
':, SG dWF
- W OpQI:
a s* "
'*SG aýSG The partial d:ivatives, int~h~e equation given.above,-represe)ntthe weighting.factor of each"parampýý arued sfor the heatý baance.calculation.' The differentials in the equation given above :,pr~ese.nt the uncertaintY associatedjwitheabch parameter.
PALISADES NUCGil ARýPLANT ANALYS9S CoNT-I' AUIAION.SHEET
,EA4ELECO8.OO1.
SSheet!6-f:20Re*lslon 2 I
The partial diiirivatives are as follows:
i/
- A-QSG
ý, = -435.804+1
+ 01753P' -1 1045 5 1 789- ý0 20257PsG),
- 09k =- X (51.789-0.20257 PýSG)ý aWBD 0T
-1.1045 A -FW DT-w WQSG
- 0.
+
1753XW.,+ X (0.20257) (W~ -W6I6 )
aQSG (85ý151.78
.05 PG)(FW -: WDD awx The followinh nominalfufii power,valueslare used to compute the value of each partial d~erivative:,
WVBO TPSG
= 5,678,50,oI!bm / hir [Reference"9.10]
=,30,00 Ibm 1.hr
[Reference 9.41
=-440.7 0F I[Refeence A9.0]
=.7.65.8 psia
[Reference 9.10]
= 0.9989.
[Ayerage of SG A value and SG B value from Reference.9
].
Substitutingt ese values into each partial derivativeyields the following weighting
-factors for e'h parameter usedin the heat balancecalculation:
OQ~=77.lgbtU/lbrm
-695.895ý btu */bm 6=
i2-71,9.03 btu /(hr -°Fq
-147,517 btu I (hr-, psia)
$SG ax
=3,935,089,059 btuJ hr
ANALYSIS CONTIIUATIQN-SHEET Sheet 7,of,20 iRevQision 2'2
ý3.2 HEAT BALA XICE INPUT UNCERTAINTIES 3.2-.
- Per Referenc.,, 9.5., the uncertainty associated with the-blowdown flow (Wi o),input, to the heat balahnce.ncertainty calculationzisas: follows:
dWD= +/-2,500 Ibm. hr 3.2.2' Per Referentb: 9.4, the uncertatinty assdociatedwith the steam quality:(dX) measurement which is used in-the heat balance calCulationis as* follows:*
dX
- , 00006 3.2.3 Per Referenci, 9.3,,the feedwaterflow input to the heat balance is obtained by reading PPC points. F ýIEDWTRFLOWSGA,_AVEiand FEEDWTR_0LOW _SGBAVG. Ifthese points are no l:available; alternateýýcomputer points(FT-0701 oa6ndFT-070 kar used to measure feedI vater flow;. Per Reference 9.6, the Ultrasonic Flow' Meter (UFM) corrected Uncertainty (,Vw,).
associated,with the PPCi fee66water flow foreichlo'op' reading
,consists of th: uncertainty associated With thefl6w transmitter and theRPPCGA/D uncertainty:
Wc:. *+/-29.389 KIbm /hr
- Per Referenci: 9.10, the nominal post powerfuprate feedWater flow riate iýs,5,678,500 Ibm
/'hr. Therefork.!,
.dWc:--+05'1% %Flow 3:2.4 Pe6rReferenci!9:;, 9.14, the random uncertainty of thoePPCý feedWaterfloWe, ading (without UFM correctic(, i), consists of theA uncertainty associated wi thhe, flow element, the flow triansmitter, th:. temperature. loop error, and the PP PC AID unernty:A dWFw\\
0.2,24/%o Flow Usingthe:pos! uprate feedwater flow value per steamgenerator from Refetence 9.10, 5,678,500 Ibr*I hr,,.yields the following uncertainty expressed in units of Ibm /hr:
dWFw..: +/-1.3,628.4Jbm Ihr@'10% Power
LI~?U~
ru~
Ef~
rLI~tff IEA-ELECO8-OOO ANALYSIS CONSiHfJUATION ShEET Sheet8of2O Revision 2 3,2.5 PerRefereri :e 9.11,.the bias Uncertainty associated with the feedwater flow me.surem6rit (without UFM correction) consists of the bias, uncertainty associated with the, flow eleJi.ent, and the As-Left;tolerance of'the trtansmitter. Therefore,.,the !total biasI uncertainty Vii.' treated as a bi-directioneal bias as follows-Bias
= (+/-0. 5.0%+/-25%)Flow.@oo 1%4.Power Bias. =+0.75% Flow @.100% Power Using the p(n,;t uprate feedwater flow value from Refer-nce:9.1*!0,. 5,678.,500 Ibm [ hr, yiei1is*l the following uncertaintyexpressed in u nits; oflbm !hr d'WýVo.= +/-42,588 Ibm I hr@ 100% Power 3.2'6& Attthepresi L it time, per Reference.9..3,, PPC points PT _0751B and PT 0752B are Used to,7obtain SW ;t,:im; GeneratorpressUre. If-these points are unavailable,1SteamnGenerator pressure (P, indicators PIC-o751A, 07516B, 07510, :and. 751D are averaged to,obtain Steam Genilator A pressure,ý and PIC.-0752A, 0752BB0752C,anhd.0752,D are averaged to 6btaihnSte:iiim' G*eneretator B pressure. Per Assumption 4.1t, the procedure Will require the average,tif at least-13 Steam Generatbr PreSsure reaadings:,perSteam.Generator when the he,:it-balance is performed inthelfuture. Per Reference.,98, the uncertainty ass oc!iated viith PIC'-0751A, 0,751B,. 0751,C 0751 Dand.PIC-0752A,,0752B', 752C, and
- 07:52D i:s as ftllows:
ePSG
= +27.48 psia
-28.44 psia For conseirv~ism, the:Steaam Generator pressure indicator uncertainty is rounded toM+/-29 psia, and.on :: steam generator. pressurechannel is assumed to be out of service.
Therefore, thi', uncettainty associated' with the averaging oflthree pressure inputs is'
,ormputeda.
blilows:.
dP 3+/-3Va29 siaJ2 +/-( 2 9 psi 2 +/-(29sia2 dPSG
_16.74~psia
PALISADES, NOJ(I, EARPLANT EA-!ELECO8-'9001, ANALY.SIS"ý C',
Ii0N *AIN SHEET "Sheto9 of 20 Reioih2 32.7 Per Refererice' 9.3, the feedwater temperature input to the heat balanceis obtained by reading PPI:: points HB _TEMP-STEADYSGA and HBTEM*PTEADY_ SGB If these points are nri)t available, alterate computer points (ýTT 0706A.'and TT 0708A) are -used to.measure,eedwater:temperature! Referenceg9.5 provides a.PPC Feedwater TemperatU1 i I uncertainty yvalueof
- 1_.36F. Hni ',vever, iReference 9.6. calculates a more.conservative uncertainty assoCiated with the Pp:. feedwater temperatur-ereadingiof+/-+3.63OF (rounded up from 3.62511F).
Thiough'the esults of Refe'recde. 9.6 (stated in Section 8.0),are val.id for.restricted use, this valueis ased as:it boundsthe value frm Ref erence 965.. Therefore:
dTm, =3.*363 0*F NOTE: Temp~ia!ture input uncer'tainties are calcul.atedfor singlepoirit teal:timie FW Temperatuire measi,' ements. Any time averaging, of FW Thmperaturevaluesriort t
incalometric c alcbWi~ ions wotldprovide 'F.W Temperature, (and. uncertainty) valuesb'duhded by the single.point real IM~
FW" Temperature measurements.
.3.2:8 :Per Referer e 9.4, the Heat Ba6lan-e_ Uncertaihny, equation.(stated in Section 3.1) hast as' part-of its asis, enthalpycalculation.equations. Differences, beteenesteam enthalpiesc.dlitermined byu5sing thes'e 'equati6nsý and those determined,using,the ASME Steam TabI iý,, could imbpart-a:;bias uncertainty into. theý calcUlationrof overa'll uncertainty for the secovi ary calorimetric. This-additional biaspterm is computed below: by determining team and-feedwater enthalpy errors at various pointS and choosing a representati',, bias fromthe caiculated' errors..
Attachment., show'the determinationof` bounding values for:enthalpy errorS in Feedwater' a id Steam. ASME Steam enthalpies, were determined fdr satMurated steam conditions, vwliie feedwater enthalpies were determined-for compressed liquid at 830 psia. Minor : ifferences betweený the assumed feedwater pressure and actual feedwater pressure wo,',Id result in negligible enthtalpy bias differences.. Feedwater,.enthalpy Delta h ei-rror iS bo~u-dedl by+0..17 btu/Ibm. inother words,- calculate4d' FWis larg.er than actual hFW.",steam :(mixture. enthalpy Delta h error is boUnded b -0.108,btu Ibm. In the-calc~ulatict i of sicondary¢calrim6etric uncertaintY, these erMrrs would result in thermal ppowrcalcul1 tions. that are tower than' actual therma powervwhich is non conservative.
These errors :.an be added to yield an overall.enthalpy bias, term', as follows:.
hb =,hsbl t
Ihfbl) where:
hb=, total enthalpy bias, uncertainty hsb = steamenthalpy bias-hcertainty hfb - feedwater enthalpy bias uncertainty Therefore:
hb = -(0.08 + 0.17) btu/lbm
- -,J hb = -0.25 btu I/ibm' P1'
PALISADES NUCII1EARWPLANT ANALYSIS,CONTIl TJTATION lSEET EAtoELEC*8*000,1 I.
3.3
-HEAT BALI MCE INPUTSo 3.3.1 Per_-Refereri e,97, a conservatively determined cdnstant value (C) is, used to account for the ener! iterms asesocatd, With'theprimary coolant pumps, letdown flow, charging flow, "f~kdjixe Ifl bution losses, and the,-pressurizer hetr. Te constant C varies, depending: o inumber f charging,pump, Ietdown ýflow-orifices ýin serice(up tothree total). Parat eters suchascharging fow, letdow*nTWl, etc. are re6ltivly constant during the pirfomance odif the eat babldce, and treating these parameters aspconstants simplifies tho heat balance. Reference 9.7 demonstr~ates thatthe calculated. C values are lower tho 1,aactual, which'woq-uld tendjto nompensate;for any actual varaionsa in then parameters ifiat make'up the Cconstant. The following equation: from Section 2.0 demonstratei.that using a lowerthan actual C value isconservative.
This: equatio' shows, that using a:smaller value ofC" would resultin a higher calculated QRx.
As nitý:lear instrumentation is calibrated to the heatbbalance results; th*s would
'Causeoindicaql'ý,d power-to be, greaterthan actual,, Which iS con ervative.
3.3;.2 The 1followin, plant parametersare~used for the heat. balance uncertainrt.calculatiomn:
.PsiG =s.ýteam Generator Pressore (ýpsia)"
PSG
-76,5'8 p-sia TFW
- `eedWater Temiperature. (6F):
Tp :440:7°F x
,= !.team quality (unit..ess) 0X
- -.9989 WD.= ',3lbWdownjflow (Ibm thr)
,V3D 8;
30,000 Ibm / hr
[Reference 9.10]
"[Refere nce 9.;10],
[Reference, 9.4
[Reference-9.4]
PALISADESNU(t,',*EAR!PLANT EA-ELEC8 0001 ANALYSS CO
ýNil INATTON SHEET Sheet I If 2' 011tvison.-2 4.0 ASSUMPTi i)NS 4j1 MAJOR A,:1t iUMPTIONS 4.1.-1 Nolne 4.2 M1NOPR-AS1',1UMPTl6NS 4.2.:1 Per*R efe re;e 9.3th'e manual heat balance'calculation, :withoUt the WPPCSteam Generator, i:,!essure values aVailabile, will use the:average of-at least three pressure indications,*Fr Steam Generator each time the Secondary Heat Balanceis" performed.
4.2.2 All uncertai i~Iies associated with the ultrasonicflow meter are random 6ahd independent.
4.2.3, Per Refereii :e,9.10, the following plant parameters are anticipated' after the power up-rate project If actual plant conditions are similat thes this calculation. remains valid.
QR Reactor1oo% Powefr QR' 2565.4-Mt PSG Steam Generator.Pressure (psia)
PSG 11 765.8 psia Tfw -
Feedwater Temperature (TF)
T f~:w 44067 0F FW
'FeedWater Flow (M lb' Ih)
FFW.
11.357 Mlbm. Ihr 5.0
-ANALYSIS, Computation f;lare performed to an.accurary of'severalsigsnifibaht digits, but presented in this calculaiii:
roundedto to decimal places inmost cases. Hand verificaiion of this, alculation uw Iizing the rounded values may resultin. slightly different results dUe to round off er'n' s;
PALISADES NUCOGý ARRPLANT ANALY-SIS, CONThIPIUA iO SHEET EA-ELECO8-0001 Set412 of 2O.`Revisidn.2 I
5.1 SECONDA'ý 1'i HEAT BALANCE U NCERTAINTY (Without UFM Correction)
Random.Uniiertainties-Per Analysis nput3.1, the:following equation is used to computethe random
'uncertainties tssociated With the* heat ibalance:
dQGQSGS
ýG
+2 ~ Sb OTF(W'd T0.eP a
t (F.asT The ýuncer.taji i 'es 0assocbiated w~ith e6ach inpu't parameter `(differenial1s) are,.as follo~w~s dWpw= feewater "flow (random)
.=
+/-'13,628,Ibm Lhr dW~wt.- feedwater floW (bias)
+/- 42,588 Ibml./hr dWA D bloWdown flow-2,5001Ibm 1
hr dTW
- = feed Water temperatir
.=+/-3,63 - F dPsG
.=.,Steam'Generatotp.ressure
+/--1÷ri 6.74,psia dX
= steam quality,
+/-'0.00016
[Analysis Input*3.2.41]
[IAnalysis input3.,2.5]1
[Analysis, Input 3,2.11
[Analysis lnpu 3.2.]
[Analysis'Inpu't 3*.26]
.[Analysis Input:32:2]
Per Analysis ti iput 3.1, the partialderivatives are, as follows:
`QsG
=_7791 90btut I bmm aw
~*s~. -695.895:btu !iIbm AG,
-- 6',271,;903 btu / (hr-- F),
aQG -147,51 btu / (hr: - pslia)
OQPSGý
':..3,935,i089,059:btu,./hr Therefore;,the' aindom uncertainty associated with.the heat balance calculation is as foll.ows:
dQSG--
02531 0409 btu/ hr
'Per
Reference:
..A4, the conversion from btu I hr-to Wt is performed by multiplying'by a factor of'0.292!13.Wtt-hr/btu. Per Reference 9.10, 100% Power equates to 2,565.4 MWt. Thereforet, the random heat balance, uncertainty is converted to%.Power with the
PALISADES NUCII.iFAR PLANT EA-ELECOEI-O01 ANALYSIS CON:TII*0UATION SHEET Sheet3 of,20 Revision 2 following ey,tation:
dQsGd.% Pouwer)"
dQsG(bt/ hr(0.29293 Wt:-/r('
100% Power Therefore, ds
+/-029 % Power (Single Steam JhGenerator)
The total railtom u ncertainty associated w.ith the heat balance'calculation is~computed with. the follciýiýing equation:h dQ.SG d
+ dQS 2 (Both Steam Generators) dQs: Fd
- Q;3G' r a*,
dQsG
+/-01.41 % Power (BothSteam Generator):
Bias Uncert.:sinties There are t*: bias uncertainties ithat mustbe: considered, Feedwater Flow Measurement
,bias (FWb) ard enthalp bias (6hb. 'These bias ter*msare calculated' beIow, then combined toýi ield the'total bias un'certaintylforone steam generator. This result can be multiplied by. I, to yield total bias uncertainty for.-both,stea-m generaftrs.
Feedwater Ffi Measurement Bias Uncertainty.
Per Section 2.51
, the followirig!bi-directional bias uncertainty iSassociated with the feedwater ilo*i i measurement for one Steam Generator-:
FWb (,:im.1 hr) = :+/-42,588.Ibm / hr Per Analysis.1,Iput3.1, the weighting fabtor (partial derivative) associated with the, feedwater~flo* heat balance inputis as Sfollows:
SQsG 779.190 btud/ Ibm The feedwate i flow-measuremenht bias term is converted, to btu.i hr with the foqlowing equation:
FWb.(T,'Ju hr)= FWb(llbtn/hr(*,
I.
FWb (Rl1,j/ hr) = +/-÷33,1i 84,144btu/hr E nthalpy Biaiii UOncertainty Per Section 3.;.8, the followring enthalpy bias: is associated with the feedwater flow to each steam ge,-,, 'erator Which* is5,678,500 Ibm/hr:o 1
PALISA DES NUCILEAR PLANT' EIAELECO8-001 hb,= O.256btu/lbm hb (bj / hr) = hb (btu lb)
WFw
.hb (bI:i,./hr) #-0.25 btu I ibm
- 5,678,500 lbm./ hr
- hb (bLI I!hr): = -1.,4,!9625 ;btu I hr.
To talBia, UNI 6certainty Total bias ui.
ur,ýlelrtain'ty (BiasT) isthe su'm of the Feedwater Flow Measuremenht uricertainty, b:,as and the enthalpywbias. Therefore:.
BiasT = FWb + hb-BiapsT = +/-33,184,144 btu jIhrI,.-1,419,625 btu / hr.
Biasf = +31,764,5.519 btu.,/ hr 4,6031,769 btu hr Per.Referenm:'!* 9.4, the conversion from btu I hr toWt is performed bymultipying byea fact(or of-0.21,93 Wt.- hr/btu. Per, Refern.ce,9.10i, 100% Powerequates to 2.565.4 MWt. There:l )re, the. bias term is converted to % Poweri utilizingithefollowing equation:
=
Wt 00
,%POwer Biast Power)
Bias (btu/hr 0.29293ý btu /' he,\\Z-,565;4O0,00 Wt BlaST,V Power) = +0.36% Power -0.40 % Power (One Steam Generator)
The total bia 1 uncertainty:associated with the feedwater flow.to bo:thSteam Generators is obtained b I multiplying the bias uncertainties for a single Steam 'Generator by "2".
Therefore,
- BiasT,
'/0 Power)'= + 0.72%/a-,0.80%Power(BothSteam Genrators)'
Secondary HKiat Balarice Total UIncetainhtv. (UnorrectedFeedwater Flow)
Total Uncert*.nty (Uncorrected) = _+0,41% Power + 0.7,2% Power -0.80% Powe-f Total Uncertn'ty (Uncorrected)= +1.13% Power-- 1.21% Power
.1'
'l I
II E"
PAUSADES NUCi', EAR IPLANT ANALYSIS-CONTO iiLIITOHEET Shee t~ kh 15OS2.e I~OP 2 5.2 SECONDAb1Y.HEAT BALANCE UNCERTAINTY (Wit hUFi Corection)
Random Umimrertainties Per'AnaIYs i Input 3.1, the,following equation is usged-to dompute'the random Uncertaintie&i associated withKthe heatbalahce:
T;'SGit aw c
a 2
d~s =~~dW J+j -50+
PS
+
dT~wýJý7 a
d)
Th-e -uncertah iities assojciated with e~ac.h in~put. pa.rameter (different.iails) aire.ais,follows:
dW,, = UFM corrected feedwater flow dW r'b=
blowdown flow dT
.= feedwater temperature dPS'G, =. Steam.Generator, press!ure dX.
= stea'm quality
= +/-29,389 ibtnri hr
- +/-250o, Ibm', r
=,+/-3.639F'
-= +/-0.4psi0
[Analysis Input 3.2.31
[Analysis Input 3.2.1]
[AnalySi!nsi ut 3o2.7]
[Analysis Input 3".2:6
[Anlyss npu.t 3.2.2]
Per Anialysis riput 3.i, thepartial derivatives are as foRlows:
ýsG
- 779.190 btuv /Ibm,
.; 395:.'895 btu.'ibm.
=.-6,271,903. b:tU / (hr -,° N.SG 8PsG
=-147,517 btu /(hr psi
- G :3,935,089,'059 btu / hr:
F) a)
Therefore, AN: r'andom 'uncertainIty: a ssoc.i ated wiith theý heat. hbaIoncec~uaini d.QS 32438ý,84.1 btu t hr.
I it 1/4
FAL15AUES NUCLL:J.AR.PLANT EA-ELECOAB-001 ANALYVSIS,CONT.II'JAI S HEE She 6
of0 vIsio 2b Per Refereqnc the conversion from btu / hrlto Wt is pe.rformed by.multipiying by a factor of. Q.29;,!93 Wt-hr/btU. Per Reference 9.10, 100% Power equates to :2,565.4 MWt. The'rel'*re;rthe random heat balance uncertainty s converedto % Power With the following eqiwtion:-
V t,)( Y 100% Power dQS(
Power) =
r!-@Iuo -o3 d.../hrkO.29293 btu, r
hr) 2,5665ib40,b0 vvt)
Therefore, dQsG l0'.3704% Power (Single Steam Generator)
Thebtotal random uncertaintyassociated With-the heat balance calculation is computed With*,the followving equation:
2 ýý oi Sd iditd.i.
dQsG = FdQZ dsG÷ (Both Steam Generators) dQSG- =.+/--0.5238% PoWer (Both S'eam"Generators)
Bias iuncertaii Mties Per Sect ion 3*; 1.3, there :bare nhofeedwater flow measurement: bias terms associatebd With the heat balabii,:e when UFM~corrected feedwater flow is utilized as aninput PerSection 3.2.8, there is !n enthalpy'bias ter that mustbe considered;.,
tn-
/p-Biwi Uncrt2 Jnn'y~ai unceeint qlylis.ascae~ihte Per-Section 3,i>,8,.the following enthalpy biasis associated with thefeedwater flow to.
each steam gi!- 1erator which is 5,678,500 Ibm/h.
.hb
-(1..25 btu I Ibm hb (btu, hr) = hb (btuW/O bm)
WF hb (btuCil r) =. -0.25btuq Iibm ý 5,678,50,0 Ibm / hr-hb. (btu),1 hr) = -1,41!9,625*:b tu /lhr Per Reference 1.4,the conversion6from btu /ihr to"Wt 'is performed by multiplying by a ftot of 0.292,:3. Wt - hr/btu. Per Ref9erence`9.0, 100%/od Power equates to.2,565.4 M' t There 6' the bias term. isconverted to % Power utilizing-the following equation:
Bias M( 'ower)= Bi)a (biJz /,Iirn0 229293 Y
00% Power btu:/hkr2,565,400,000.Wt)
Bias(% 'ower) =-0-01/62% Power (One Steam. Generator) 4L
'ANALYSIkS CON TU SHEET Sheet: 18,Of 20 Revision 2 8.0 CONCLUSk'I1h This calculatm*,n computed the uncert.ihnty asociated With the secondar calorimetric heat balance calcula*tioni With and without'.the.Ultrasonic, Fl6w Meter correction factor.
Heat balanci, uncertainties were comptedfor the manual heat b'alancecalculatioh perfo'rmed thv)ugQhg!peffom.ance ;of.DWO,-1.. See Section 7.0 for resuits. The results of this calculatbi iaresubject tio the following limitations:"...
- This calci!i:ation assumes thatReference.3.will be revised to use the a verage of PIC-075 i,, 0751*.B, 0751C-,and.0751D to obtain.Steam GeneratorA pressure, and the avera!!je of PIC-0752Ak07528, 0_752C,:and 0752D will be usedJto obtain Steam Generatoi B pressure every ti'methe Secondary He Baanceis. performe;. The results :of ibis: calculatiotn are based. on lthe'use of at least 3 Steam Generator,-r Pressure lndicati6ns persteaqener-at or.
- Per Refet 'iince 9.3, 1thefeedwater flow< contrlrom-indicators (il-0701 and FI-0703)'
may a!so le Used as.the.feedWater flow-ihput.j tohe. heat.balance. Th&e ;uncertainty
.associate.:i withthe..cpntfrol room feedwaer flow.Pinca0tors is larger than the.
ujncertaiinl;' associated. With Ithe.PRO computer`--
poinndctnsofewar flow.
Referenc c, 9.6.doe' not comutethe un6e*'tinties ;associated.with'the feedwater fl:w control. ru,:m indicators. The:results ofthis.calculation.are bas§ed-.on the use ofthe.
Pcrr cor uter poinits or the feed-water. flow Me6a "sur.ementen o Per Refe!;.nce 9.3. the feedwater.temperture control roomA ndicators (11-0701 6 ;,tnd T!10708) orlrecorder T R-0706may'also be used as the feedwater temperatblire input. to the.heat balance. Th'e uncertainties asso'iated'with the control.
room indi,:rators and the recorde'r are largbr than theuncertain-yassociated with the PPC corrtiluter p0iht indicationsof feedwAater temperature. RKeferen*ce 9.6 does not compute iIe uncertainties associated with the
'anl-og'indicatibns of:feedwater temr perati we,. The: -results.;of this calculation are based,6on.the;use. of the.PPC computer.Points for,,the, feedwaterftemperature measuem6ent.
.1.-
- .. ~
.~.
~
AN ALY CONT i JATlN SHheot1of2R sin
'2 9.0 REFERENCEI" 9.1 NUREG/CR-,:)359, "A Mathematical Model forAssessig.the Uncertantis of SInstrumentatii,>: Measuremehts forPowerand Flow of PWR6R8ctors-, Dated February 1985.
9.2
-iSA-RP67.04, Part1 l - 1,994, I"Methodologies.forlthe Determin ationofSetpoints for Nuclearsafel R~elatedIhtst'f melitati;n", May 1995.
9,33 DWO-1, "Opr:,ators DMily/! Weeklyltemis, Mode§s 1,. 2,'3& and 4", ReviSion70.
9.4 EA-HARý-91--!i, "Heat Balance Adjustment for Moisture Content of Steam", '.Revision 0.
-9.5 EA-AFZ-96-01, "Analysisof Various Heat'Balance Input!naccuracies", Revision 2.
9.6 iEA-ELEC08*(
04,i "Uinceainty-Calculation-for: UFM :iCorrected, Density Compensa ted Total, Feedwa ',ir Fo.Maueet(COnyRevision-2.
9.7 EA-BWB-96-,:, Heat Balance Calculation Usinglthe Ultrasonic owmeter:.Measurement DeVice,,i ReuiFion 50.'
9.8.EA-ELEC08-; i'04, "uncertainty Calculation Steam GenertorPressure Lodps!, Revision 9.9 Deleted 9.10 EA-ýRCH-O -O;i I" Calculdation:of Chapter 14.Safety Analysis Parameter Changes Due to FC-977 Powe;: Upra'e," Revision'.
9.11 RI-24A, "SteO in.Generato Fdwter Temperature nstrimetLp Calibration,"
Procedure, Rlmision,0; 9'.12' RI1-24B "Ste,,i Generator Feedwater Flowlinstrument Loop.Calibration," Procedure, Revision 0..
PALISADES, NU*I. 11:AR
!PL,-ANT ANAYSI COT~lLJAIONSHET EA-ELEGO,8-01*1 Shee 20 of,20 eiso ATTACHMENT A The following table i.*Sstabliihes,boundingdifferences between steam and feedwater enthalpy taken-from ASME ei3arn Tables and calculated using"approximationPsfromrt Reference 9.4; STEAM ENTHALILY
- (Saturated Conditions)=,
(SGA).
(aGB)
.hm =,220.3-6-7,27Q9VPSG-hm = i219097ý.Q27600SG XB. =
0).9991135 11.998668 PSGz AS 1AE (pliq2) hp 765.ý8 1,200.29, 50 7.70, 12 00.18 5(
Calc.
h
'mA ASME Calc.
Bfltif h:
hmBR hmR 1hf
,hmA, DClta h hf hinA-ffiiiA DO-ft'n-hý htn'B; htnE 3-.75
)4.5, 1 199.361,1099.*7721,0,b.065 1199.6871199:614: -A0,73 1 1r9 9`578 1 19906!, -0.0 :789 "T199;362 11 99.253.
119--4 -0J.0I6.
1199.2931 0.067 119O9.18 -0.073z
.FEEDWATE.1 ENTHALPY (Compressed liquid at'830 psia) hFw
-1.1045*Tf:",V - 66.493.
K:
.442.7 422.32.
440.7 420M.1 1 438.7-417.89.
,hF*
Delta :h 42-2.47 0.150' 420.26 0150.
418.05 0.,160
PALISADEN UM LEARPLANT ENGINEERINGtANALYSIS CHECILIST At.tahment 4 Revision 12 P09ge 1 Of I
.EA -ELECOB-0D0l REV.K
ýx 7
SECTON Il Items Affected By This fA Affected
ýYes No Revision Required ldenUfy*
- Closeout,
+
4
- 4.
1.t0!
Other EA's..
2.0' Design Documeits E.ectnc* i E-,38thrdugh E949
-3`0 D.esignDocuments Mechanii!.
- M240-M246 M257,M261.., Mii*B4-M6661.
4.0 LICENSING
DOCUMENTS 4.1 Final Safe'ty Analysis Reporn, FSAR)
- 4.2
.Tech nical Specifications 4.3 Operating RiequireentsMaz j Jai 5.0 PROCEDURES 5.1 Administrative Procedures 5ý.2 Operating Procedur6es (SOP, OP, ONP, etc)'
5.3 WorkingProcedures 5.41
_Tech Spec Sureillance Tes: "rocedures; 6.0 OTfER DOCUMENTS 6.61 QdList 6.2 Plant Drawings:
6.38 qEqupipment Data, B*se.
6.4 SparPe Pait (Stoc kMMS),
6.5- *:Fire Protecton Prgram Rei!.rtt(FPPR) 6.6 Design Basis Documerits 6.7 operating5Checklists 6.8 SPCCI*PIPP Oil and Hazard* is' IMaterialdaSpill Prevention. Plat, 6.69
.- ~Documents 6-10 MOV/AOV Pr'ograrm:Documci ts !(Voltage, thrust, weak link, etc) 6.11
ýWr'k]nstrdcti6ns 6.12! Otherý ýS 0-t2j.~~
Dl 43 Im 0
ml o
mi El Elm Ul/
SECTiON iI bo anyaof he f6llo~winig documnentsti eed to'be 1 generated" of the~onclusIons reached in this EA:
31.¸
,6.1
.CorectiVe Action Documentfi
'EQ Evaluation.Sheet?
Safety Eqalduaii6n?.
Design Basis Document Chýti.ge Request?
FSARiChat6ig trocue s Iq uet Verifiationi Tes§tProce'dure (.i~lirchanges to' thDesign Baisis)?~
Yes'
'El El El No..
El.
El El El El El Reference Referencer 2.*
"bmtt-Reference Reference.
Reference,,
Completed By:Richard A. Bischoff.
Date: July-15. 2002 Tech'nical Revieed B3y b
L1
/
at 8
'Identify;Seetioni, No Drawing.,,Ddcurihiint, etc T..
TECHNrcAL REVIEW CHECKLIST Proc No 9.11 Revision 1 Page-1-of I EA - ELECOB:- 0001 REV. I.
I This:checkli st provii: es guidance for the review of engineering analyses. Answer questions`Yes or Ni, or N/A if they.do.not apply. Document all commentoson a EA Reiew "Sheet.. Sai' actoryrespOlution of cmment**nsand completionof'this che cklist is noted by theI Tech alReview signturat the bottom Ofthis sheiet.
(YIN, N /A)
- 1.
Have the proI:,r,,,r input codes;, standards and design principles been specified?
- 2.
Haveothe inpuii. codes, standards and design principil'es'been properly-applind?
- 3.
Are all. inputs;nind assumptionsý,validaind th. basis for their use documented?
- 4.
Is Vendor information used as input addressed correctly in the
- 5.
If the analysis,;rgument departs ifr.omVendor lnformation/
Recommend, ions, is the departure justifi'cation dcumented?
- 6.
t aed and teasonable?
- 7.
Are the desigi* basis changes permitted by this EA bounded'by-the applicable 50;9 Review?
- 8.
Ar-e',allconstants, variablesand formulas correct and properly
,9.
Have all comimnents been documented on an EA. Review Sheet-and resolved, or hNive any minor (insignificant) errors:been identified anid their ihsignificiiince justified? (Indicate "No Comments,"if 'nonewer-e 1f0.
If the.analysis involves Welding,, is 'the foilowing information accurately repr esented on the analysis.,drawing.,(Output document)?
o Type c,'t Weld SSi2ze oi ti/eld
- MateriolFBeing Joined
- aý'ThiCkn',vss of MateilBeing
.Joined
.e. Locatki,, of.. eld(s)........ "..
- Appror late Weld-ymbology V
Y
- f 1.i.
Has the objecpd.req of the analysis been met?"
- 12.
Have *a-driiis:iative requirements such as nUmbering, format, and S indeing been iatisfied?
Technical Revit wer Date..---,
Date 4
'1
-I---
P roc No 3.07 Attachment I
,Revisi6n 12 Page 1 of 1 50.59 SCREEN Page 1 of 1 SDR Log No ActlvltylDocumentII[,
-EA - ELEC08 - 0001 Revislon No 2 AY"Ž T
U t
altidfor the S-condarCaloimetri6c HeatBalanwce Brief6 Dscr tin-oUictivty (WhatIs Bein Clhanged and Why) FC977 is Derformina a 0weruorate for the.
areator-powermlevel. licertainties:associated with ýthe S!econdary C6l6r!6ietic iMnt W determined: This gnntsi determines
]total i!tji secondarv catorimbt ichlf6at nc lc,6Wt6*ith snd*itho th00 UlrS6nic Flow
-tI
~fcgrrecti6n ~f6a(6r ýWiijthetl lower bngeri~ais.t~reco oudo~
te~ata
~oowr tvell~sr tii~ liensvaluwitassrane o no exeediiothe license value'.,:-
-Contined I.,.
.1
.1
.1 1I.
.50.59 Screening QUi,*:*itlons: (Cheik.Correct Response)
.(See. AtchmentKBf:1 d Guidance)
List the documents (UIPSAR, Technicial Specificlionsfand other documents) reVie',ed~where feleVant.r iriforTTation "as found including sectioh'nunibers:.FSAR 7.5-3-3. Operatinq Reqiuirements Mahual section 3.17.633: Technical ýSiiciCicatibns jBasis SR3.3.1.3 A&SR 3.1.4.3 NRC Reau!torv. Issue Summar 2002-03
- Sec:tions l. l.F andl.2,:199g6 Annual report of Facility Cha'nges. Tests arnd Exoerments-it~ern 96*1362.*
Sec jr~clrmtipetaanceAwihhand'wth6ut the UFEM' ffortitkmnfactor. The rea6torpnowgrflev~l.
- orequioment, This ejjiineennaanalvsis only evaluates tlieiucertaitvofthesecondar calormetrc heat balan~e calculation.
1..
Doest~heprop*.;ed activity involve a change to an SsC thatadverselvyaffects, an UFSAR describ. 3ddesignmfunction?
- 12.
Does the prop:iedactivityinvolve a changetoa procedure that adve-dely
,:fects, how: U.: ;AR'described:SSC design func.iions.are. performed'or controlled?'
- 3.
Does thepropb*;ed actijvity involve, revising.,0r-replacing.an-UFSAR.described evaluation rne l iodoloy thlat'is used in establishinhgthe-design bases or~used. in the" safety ana~i, ;e~s?
4:.
Doesthe pop:, !ed activity involve a test or experiment not described'ih the' UFSAR, wher: C~
in SSC is :utilized o'r conhtrolle~dinamrinzi rijha~th
'is"6uside~the.
refe*rence bouivr; s of~thei design for that: SSC orissinconsistentwithh.analyses. or, descriptions in ie UFSAR?
- 5.
Ddest4e pr0 :ied, aitivify, requirea cta.g6 to-the6TeChhical.$ped:ifidati6rtis?
_Yes
'V7. No:
__Yes.
-No,
__Yes V No
-Yes V No
-Yes V ~Noý Ill.
If alI questions are'nah!,efed NO, then implementlthe.activitywithout perfotming a 50.59 Evaluation or, obtain~ing NRC appr;ovgI.l, If question 5isiswe-d YES,.then a Li.cense Amendment must be obtained.,from the NRC prior to implementation.ofjthe *.!tivity.
If question 5 is answen!,d NO and question 1, 2, 3'or4 is answered'YES, then a 50.59 Evaluation s-hall be p erormed.
I.
I, I,
IV.
Prbvide.a.ov0erall jus-,i c'ation for theýanswers tolthe screenihgqýuestions.
'This'engineering:analysis ai: :Iresses the second'ary caibrimetrid heat balance.uncertinty. The resultslwill beused
'for the power uprate progra" 3vauatin, This enginnot perform any changes, or moIaians.
.I
- o.
e eigt*ys n
e.isting eup n a d
Continued 04a/c*]..
._/
2 V.
Screen Signoffs.
3creen Preparer: RicahrdA. Bisnhoff 215ate 325/02 3creren Reviewer:-e Date: "____,6_