ML18114A208
| ML18114A208 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/24/1978 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18114A208 (28) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM DISTRIBUTION FOR INCOMING MATERIAL REC:
STELLO V NRC ORG:
335 FL PWR Sc LIGHT DOCTYPE:
LETTER NOTARIZED:
NO
SUBJECT:
FORWARDING 19 UPDATED PAGES TO SUBJECT FACILITY"S CYCLE EVALUATION TO INCLUDE THE EFFECT OF CEA GUIDE TUBE'WEAR CONFIGURATION... W/ATT.
<RIDS)50-335 DOCDATE: 04/24/78 DATE RCVD: 05/01/78 COPIES RECEIVED LTR 3 ENCL 3 2 RELOAD SAFETY ON THE CYCLE 2 CORE PLANT NAME: ST LUCIE ei REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001)
FOR ACTION:
INTERNAL':
EXTERNAL:
BR CHIEF REID>+W/7 ENCL EG FILE++W/E NCL HANAUER++W/ENCL EISENHUT4 +W/ENCL BAER+4~W/ENCL EEB4+W/ENCL J.
MCGOUGH+wW/ENCL LPDR S FT P IERCEi FL4.4 W/ENCL TIC++W/ENCL NSIC~~W/ENCL ACRS CAT B++W/16 ENCL NRC PDR++W/ENCL OELD++LTR ONLY CHECK++W/ENCL SHA044W/ENCL BUTLER4+W/ENCL J COLLINS++W/ENCL DISTRIBUTION:
LTR 40 ENCL 39 SIZE:
iP+iP+19P THE END CONTROL NBR:
781220 8
h F>>
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~
FLORIDA POWER & LIGHTCOMPANY April 24, 1978 L-78-148 Office-of Nuclear Reactor Regulation Attention:
Mr. Victor Stello, Director Division of Operating Reactors U.
S. Nuclear-Regulatory Commission Washington, D.
C.
20555
'LQ t
Dear Mr. Stello:
N.';"
'978~ -Q
~~4 1ecTr~
Re:
St. Lucie Unit 1 Docket Vo. 50-335 RSE Revision E
Nineteen pages of the St. Lucie Unit 1, Cycle 2, Reload Safety Evaluation (RSE) have been revised to include the effect of CEA guide tube wear on the Cycle 2 core configuration.
The attached revised pages can be used to update the RSE which was forwarded to your office as an attachment to letter L-78-99 of March 22, 1978.
The revisions are marked by a line in the right hand margin.
Very tr
- yours, ert E.
hrig Vice President REU/MAS/mb Attachment cc:
Mr. James P. O'Reilly, Region II Harold F. Reis, Esquire d~
r t'8Z22C OSS dO/
93 PEOPLE... SERVING PEOPLE
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ATTACHMENT Re:
St. Lucie Unit. 1 Docket No.
50-335 RSE Revision The following RSE pages (L-78-99, March 22, 1978) are revised to include the effect of CEA guide tube wear on the Cycle'2 core configuration:
Pacae No.
'80 81 82 83 84 87 88 89 90 91 92 93 94 95 96 97 98 99 100
~
e J
~ e SQ would significant reduce the'ate retlood peaks r both fuel types.
Since the low density fuel experienceSblowdoim rupturethe first and second peak temperatures are higher than that for the high density fuel.
Use of the PARCH code would thus resu3-l: in demonstrating (10) the low density fuel to be. the limiting fuel.
I The blowdown (CEEASH-4A) { ), r'efill 'CQPERC=II) i"~ a;.d core-wide clad oxidation COii1ZIRC analyses from the Cycle I analysis rema'n valid for Cycle-Il. -Accordingly, only the new STRIKIN-II results. for the-worst break size for the limiting low density fuel and as applied to the'igh density fu 1 is being reported in this analysis.
e e
The results of this study supercede those reported in preference
- 9. and show that the plant meets the appropriate I'lRC Acceptance Criteria published in the Fed ral Register on January 4, 1974.
.Conformance is su,-:earized as follows:,
Criterion (1)
PEP~
CLAD TP~PERCTURE-.
"lee calculat, d maximum fuel element cladding temperature shall not exceed 2200 F".
The analysis for the low density fuel yielded a peak clad temperature of 1972 F for the 0.8 DES/PD"'" break at 14.8 kw/ft.
The peak clad temperature for the high density fuel case was 2035 F at 14.8 kw/ft.
Criterion (2)
YAXINMCl ADDING OXIDATION"'.
"The calculated total oxidation of the cladding shall nowhere exceed 178 of the total cladding thickness before oxidation".
The analysis for the low density fuel yielded a pea'-
~i v'~ ee
~
P"'.','
t 4f e
e
~
'e local clad oxidation percentage of ll.sq, for the 0.8 DES/PD break at. 14.8 kw/ft.
The high density fuel
---...,-,'Ctaei O'XYGaeiaripeiCeri age i aS Z2;OaaS'lel:3" ~~i/2','; '
Neither the low nor the high density fuel cases employed the PARCH code(
)
Since the peak clad temperatures occur during late reflood, use of PARCH would, result in lower peak clad temperatures, lo>>er local clad oxidation and lo>>er core wide clad oxidation.
Usc of PARQt,would.;
also show that the low density fuel is the more limiting fQe]
Qyp~
"'-DES/PD = Double-Ended. Slot at Puinp Discharge 4/24/78
~
I
~
81 Criterion (3)
? AXISWil ~KDPOGBf C'FiX~BATIGX"'.
"The calculated total
~ 'mount of hydrogen generated from the chemical reaction of the cladding with water or steam shall not exceed 1': of the hypothetical amount that would be generated if. all of the metal in the cladding cylinders surrounding the fuel, excluding the cladding surrounding
--- the plenum volume, were to react".
'Ihe analysis for the lo>> density fuel yielded a peaR core-wide clad oxidation percentage of <. 674 for the 0.8 DES/PD break at 14.8 la~/ft.
The core wide clad.
oxidation percentage for the high density fuel-is
<. 63~ at 14.8 h~/<t.
3"eak A~alysi
'..'e"ho~ of Calcu't ation calculations reported in this section were performed using Cm+ustion Regin ering's Large Break Fvaluation bfodel >>hich is
"=scribed in Re erences 2, 3, and 6.
~+
~
In tne CE model, the CEFLVH-4A computer program is usecl to determine-the primary system flow parameters during the bloivclown
- phase, and, the CO~PERC-IX~
~ computer program is used to describe the system behavior during the refill and reflnod phases.
The core flow and. thermodynamic parameters from these two codes are used.
as input to the STRIKIN-II
~ program which is used to calculate the hot rod clad temperature transient.
The peak clad temperature and
'eak local clad. oxidation percentage are therefore obtained from the STRIKIN-II calculation.
The STRIKIN-IT. pro@rom has been revised (6, Sup.
4)
- -.... -and includes the prevention of a return to nucleate boiling
'Ihe core-wide clad oxidation percentage is 'obtainecl from the. results l'5, Sup.
1) of both the STRIKI'3-II and CG~lZIRC
- 'omputer programs.
B.
Emer~enc Core Coolin~ S 'stem Asstuwtions The ECCS'ssumptions are the sam as those stated in ReFerence 9.
4/24/78
82 C.
- Core, S stem and Contaiztment Parameters Those parameters which differ from the previous analysis are
~
(93 shown in Table 8 -1.
.D.- B~RS Only the worst break as identified in the Cycle I ECCS perfoxmance analysis 'as analyzed for Cycle II.
This break was the 0.8 DES/PD Cgl (the worst break identified in the Cycle I spectrum for the low density fuel)
. and was used for the high density fuel'lso-
'nalyses of this break for Cycle II resulted in peak clad temperatures of >97> oF and 2035 F respectively.
The substantially low peak clad ratures or these bxeaks are due to the fact that the Cycle II Gal stored energy at the time in life of the minimum gap conductance is appreciably lower than that for Cycle I.
Furthermore, since'he "eak clad temperatures for Cycle II show an appreciable margin relative to the criterion limits, a re-analysis of the full break specter is ot warranted since it is expected that the performance for the remaining brea< sizes will also display these margins.
E.
Results A re-analysis of only the worst break identified as the 0.8 DES/PD from the previous Cycle I FCCS performance report
>>as performed.
(9)
Table 8-2 identifies the breaks analyzed in this study for the low and high density fuels along with the figure number presenting the pertinent transient data'or each analysis.
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.-As noted in Table 8 -.2 the results for each of the cases analyzed are
~ 'b
'- 'displayed graphically in Figures 8.1 and, 8.2.
For each case, the variables listed in Table 8-3 are plotted as a function of time.
Times of interest for the various breaks are sho>>n in Table 8 -4, while Table 8-S summarizes peal'. clad temperatures and. clad oxidation percentages.
4/24/78
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As shown in Table 8 -1, the Cycle II analysis represents a
reduction in initial fuel average temperature stored energy for the low density fuel of 134.5 F when compared to the Cycle I analysis.
The initial high density fuel stored 'energy was even lower The'analysis yielded low peak clad.
temperatures of >>72 F for the low density fuel and, F for the high density fuel which are directly attributable to the reduction in stored energy.
These results clearly identify the temperature margin relative to the Acceptance Criteria limit.
Since t¹ ECCS performance for this break for Cycle II represents performance results well below the Acceptance Criteria~~ limits,.
a complete spectrun analysis is not warranted as the remaining
=
brea& in the large break spectrum would also display these large m)argi~
s and. energy release'o the contairmert during blowdown has not changed from those values presented in the Cycle I analysis IXI.
Co. uter Code Version Identification
'Ihe following versions of the Combustion Engineering FCCS Evaluation Ifodel computer codes were used for this analysis:
CEFLASH-4A:
Version No. 76041 STRIKIN-II: Version No. 76234 CRPERC-II:
Version No. 75097 COXZIRC Version No. 75055 4/24/78
Table
'8 -1 St. Lucie I Cycle II General System Parameters guant~it Value
~Cele II Reactor Power Level 0.02: of Nominal)
Average Linear Heat Rate (102: of Nominal)
Ifoderator Temperature Coefficient at Initial Density
- Sys em Flow Rate {Total)
Core Flow Rate Initial System Pressure
---= Core Inlet, Temperature Core Outlet Temperature T
~ 'e A 'li
-.="Active Core H ight Fuel Rod OD Nmber of Cold Legs Number of Hot 'egs Cold Leg Dim ter Hot, Leg Diameter Safety Injection Tank Pressure Safety Injection Tank Gas/Water Volume
'eak Linear Heat G neration Rate (PLHGR) 2611 6.2126
+0.2x10 139.44x10 134.6x10 2250 548 S98 11.39 0.44 2
30 42 215 930/1090 14.8
+0.2x10 139.44x10 134.6xl0 2250 548 598 11.39 0.44 4
2 30 42 215 930/1090 14.8 ap/
F lbs/hr lbs/hr psia OF OF In In In psia Ft hv/ft
'611 IINt
- 6. 2126 hv/ft Gap Conductance at PLHGR Fuel Centerlin Temperature at PLHGR Fuel Average Temperature at PLHGR
,.T=ot Rod Gas Pressure
')
--~~o~=-'Rod Burnup 714~
3835&
2563&
1115.5'791.'-
947.2 A 1552
- 3751.1" 3484 2428.5" 2181 1297.4" 1047.8~":
10081
820;A'TU/hr-ft
- p t
2 0-OF F
psia N'..'D/iitTU
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~
-".For low ense.ty uel, >>nen gap conductance is minimum-s -"'For high density fuel, when gap. conductance is minim.m-4/24/78
87 Table 8 -4
.;-':-'::St Lucie I - Cycle II"
, Times of Interest (Seconds),
Brea!
Low Oensity Residual Fuel (14.8 kw/ft)
Hot Rod SI"Tare&
Start of future On Reflood SI Tanks
~Bn t 0.8 x DH/PD 9.92
~ 17. 6
, 35.84 70.33 High Densi Fuel (14.8 h~/ft) 0.8 x D"-S/PD-.
17e6 35.84, 70.33' 1
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4/24/78
88 Table 8 -5
" .:St. Lucie I-- Cycle. II -
Peak'lad'emperatures and.
oxidation;.Percentagesor the 0.8 DES/PD Break
/
Low Eensit Residual Fuel 14.8 hv/A)
A Peak Clad Clad Oxidation P}
.Tem erarure F
'ocal Core l(i-de 0.8 x Dd~/PD
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4 1972 11.8
<.67 Hi~h Densit Fuel
- 14. 9 h~/ft)
L 0.8 x D".-S/PD-203S 12.0
<.63
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4/24/78
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t 1GURE 8t-1A N
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ST, LljCIE biilT I ~
0,8 x DOUHLE f=iii3Eo SLOl P~f<EAtl Ii< PUilP DISChARGE LEi'EAI; CU~i3 TEf:If'ERATUflE 1800 1600 1400 I
O~
1200 1000 LOW i3Ei<SITY FUEL AT 14,8 K~(/f-T 800 600 400 0
100 200 500 400 TIfiL, SECOi>liS 500 600 4/24/78 700
f-reunE g,-lH gp
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LliCIE liiiIT I 0
0,8 x DOUBLE EllOED SLOT BREAI> If] PUf'1P DISClfk"'GE LEG llOT Sf'OT GAP COi]DUCTAi)CE 160 120 D
1 100'0 f
Z 60" 8
LO~'t DEi]SITY f UEL AT lq 8 Vht/FT 00 20 0
100 300 il00 TIi'lE, SECOIlOS SOO 600 4/24/78 700
e P
II
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I-1GURE 8-1C ST.
LUCIE UIIIT I 0
O,o x DOUBLE El'JUEJJ Sl OT BREAK Iil PUP'1P DISCllARGE l EG PEAK LOCAL CLAD OXIDATIOH 16 10 CD g
OC CD LOH iiEt/SITY FUEL'AT ld, o~ Kl'(/FT 0
0 200 F00 900 TIt'lE, SECOikDS 500 GOO 4/24/78 700
FIGURE 8-1D
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ST.
LUCIL Ul<lT I
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0,8 x DOUBLE EilDED SLOT ORE/'il< Ifl PUfdP DISCIIARGE'EG CLAD TEilPEHATURE, CEi'lTERLIi'lE I=LiEL TENPERATURE, AVERAGE FUEL TEl'iPEI<AluRE Af]D COOLAilT TEVIPERATUffE FOR llOTTEST lkODE 4000 5500 LOW DENSITY FUEL AT 14,8 KH/FT 3000 FUEL CEflTERLIikE t-2000 1500 AVERAGE FUFL 1000 i
500 COOLAi<T 0
0 100 200 500
'00 TIf'lE, SECOilDS 500 600 4/24/78 700
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0,8 x DOUBLE EflDED SLOT Hf<EAK Iih PUi:1P DISClfAfAGE LEG HOT Sf'OT flEAT TRANSFER COEFFICIENT 160 1LfO LL.
o I~ 120 CA t
100 80
~s 60 LOW DEi<SITY FUEL AT ltf,8 KIt/FT Lf0 20 0
0 100 200 gPP tfOP T IftE, SECOIlDS 500 600 4/24/78 700
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FIGURE 8;1F 94 ~
ST.
LUCIE UHIT I 0,8 x DOUBLE EHDED SLOT BREAK Ilk PUliP DISCtiAR E. LEG I{OT ROD IiiTEl(ikALGAS PRESSURE LO'~/ DENSITY FUEL 1400
.1200 RUPTURE = 9,92 seconds 1000 800 C/)
600 LOH DEi'<SITY.FU L AT 14,8 KH/f-t 400 200 0.
0 20 40 60 TIi'lE, SECOflDS 80 100 4/24/78
I 16Ul<F-8-2A 95
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ST, LSClE hitT t
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0.,8 x DOUBLE Ei'll)L13 SLOT BREAll lid PUHP DISCllARGE LEG PEAl; CLAu TEr'>PEnATunE 2000 1800 1600 1000
.'HIGH DENSITY FUEL AT 14.8 Kh/FT 800 600 400 0
100 200 500 400 TII'lE, SECOilDS
@00 600 700 4/24/78
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F1GUI<E S'-28 ST.
LUCIL IIrIIT I 0.8 x DOUHLE EilUEJ3 SLOT Bf<EAfl Iif f'Ui'1P i3ISCflAfAGE LEG I-lOT Sf'Of GAP COf<DUCTAPJCE 3.MQ 1Lf00
'200 D
I 1000 800 5
600 HIGH DEHSITY FUEL AT 1<1,8 Ktl/FT 400 200 0
0 100 200 00 l}QQ TIilE, SECONDS 500 GOO 4/24/78 700
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,8-2C ST, LUCIE Ui)IT I 0,8. x DOUBLE Ei/BED Sl OT Hf<EAK IN PUf"IP DISCINixGE LEG PEAli LOCAL CLAD OXIDATION llI6ll DENSITY FUEL AT 14,8 l<H/FT 200 gpp clpp fIf's.,
SECpilDS 500 600 4/24/78 700
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ST.
LUCIE Uf'IIT I 0,8 x i30UBLE EilDEii SLOT ilf<EAI'>3 PUf'1P DISCIIARGE LEG CLAD TEflPEBATUPE, CEiITEIlLIIIE FUEL TEYiPElMTUflEr AYERAGE FUEL TEI'IPERATURE AND COOLAi<T TEf'lPERATURE FOR llOTTEST f<ODE 3500 llIGll DENSITY FUEL AT liI.8 KH/FT 5000 2500 FUEL CEi'>TERLIi'lE t2000 AYERAGE FUEL CLAD j.OOO 0
0 100 200 500 000 Tr~ c' em.>.>c 500 600 4/24/78 700
'0
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180 5 j GOBE '8 '-2L 99 ST, LUCIF UIIIT I 0,8 x DOUBLE ELJDED SLOT Bf<EAfl li~ Flii'lf'ISflAf AGE LEG HOT SPOT HEAT TRAiPSFER COEFFICIEi'0T 160 140 120 HIGH DEI)SITY FUEL AT 14.8 KH/FT I
LLI
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LL(
LL LLI CD 100 80 60:
00 0
0 100 200
~500
<f00 TIf'lE, SECOifDS 500 600 4/24/78 700
FtouRE
'8-2F Qo ST.
LUCIE UHIT I 0,8 x DOUBLE EilDED SLOT BREt'll IH PUf(P DISCflAflt E LE" HOT ROD IHIEIEHAL GAS PRESSURE HIGH i3EiPSITY FUEL HI6H DEi'JSITY FUEL AT 1Il 8 KH/FT 1200 10GC P'INITIAL = 10 f7i8 PSIA
~ 'INITIAL RUPTURE = St),91 sEc 800 600 Il00 200 0
0 20 60 TIflE, SECONDS 80 100 4/24/78 J
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