L-83-593, Forwards Addl Info Requested by Re Operational Limits Tech Spec Amend
| ML17345B375 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/17/1983 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| L-83-593, NUDOCS 8312190129 | |
| Download: ML17345B375 (62) | |
Text
I~
REGULATOR NFORMATION DISTRIBUTION.
TEM ('RIDS)
ACCESSION NBR!8312190129 DOC, DATE: 83/12/17 NOTARIZED! NO FACIL's50 280 Turkey Point 'Planti 'Uni,t 3i. Flor)da 'Power and Light C
- 50 251 Turkey Point.Planti 'Uni;t 0i-Florida 'Power and Light C
AUTH BYNAME AUTHOR AFFILIATION WILLIAMS/J ~ li ~
F l or i dai Power L Light. Co<
RECIP ~ NAME'ECIPIENT AFFILIATION VARGAgS,"A ~
Oper ating Reactor s Branch 1-
SUBJECT:
Forwards addi info requested by 831216 l,tr r e. operational limits Tech Spec =emend, DISTRIBUTION 'CODE:
A001'S
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P.O. BOX 529100 MIAMI,FL 33162 J 1'vlria4%
FLORIDAPOWER & LIGHTCOMPANY December 17, 1983'-83-593 Office of Nuclear Reactor Regulation Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch b1 Division of Licensing U.
S. Nuclear Regulatory Commission Washington, D C.
20555 Be:
Turkey Point Units 3'i 4 Docket Nos.
50-250 h 50-251 Additional'nformation.
For Operational Limits Technical Specification.Amendment
Dear 'Mr. Varga:
Please find attached the information requested in your letter dated. December 1'6, 1983.
Please contact us if further inform-ation is required, Very truly,yours, J.
W. Williams, Jr.
Vice President
.Nuclear Energy Attachment JWW/SAV/dab 90zg9 83><17 DR ADOCK 05000250
.PDR oII~
PEOPLE SERVING PEOPLE
I i5
ATTACHMENT A SAFETY ANALYSIS FOR TURKEY POINT UNIT 3 AND 4 LOSSWF-COOLANT ACCIDENT The loss-of-coolant accident (LOCA) has been reanalyzed for Turkey Point Unit 3 and 4 in order to remove the BART Model from the large break LOCA evaluation.
The worst break case (i.e.,
C
~ 0.4 DECLG break) was reanalyzed to provide additional information as required in your letter of December 16, 1983, in support of our analysis filed on 'August 19 and September,9, 1983.
The analysis presented here is in accordance with the requirements of 10 CFR 50.46, Appendix K provided in reference l.
A description of the various aspects of the LOCA analysis is presented in WCAP-8339 (reference 2).
'The Revised PAD Fuel Thermal Safety Model, described
.in reference 3, generates the initial fuel rod conditions.
The individual computer codes which comprise the Westinghouse Emergency.Core Cooling System (ECCS) Evaluation Model are described in detail in references 4,, 5, 6, and 7.
Code modifications are specified in reference 8.
The results of several sensitivity studies are reported'n reference 9.
These results are for conditions which are not limiting in nature and'ence are reported on a generic basis.
The LOCA analysis presented in this report utilized the 1981 version of the Evaluation Model which is the model currently used and accepted for plant licensing calculations.
The modifications which comprisei the 1981 Evaluation Model are delineated in reference 10.
Results The analysis of the loss-of-coolant accident is performed at 102 percent
'of the licensed core power rating.
The peak linear power and total core power used in the analysis are given in Table 2.
<~
it
Table 1 presents the occurrence time for various events throughout the accident transient.
Tabje 2 presents selected input, values and results from ~the hot fuel rod thermal transient, calculation.
For these results, the hot spot's defined as the location.of maxim'eak clad temperatures.
That location is specified in Table 2 for. the break case analyzed.
The 1'ocation indicated in'eet is the elevation
'above the bottom of the active fuel stack.
Table 3:presents a
summary of the various containment system parameters and structural parameters which were used as input, to the COCO computer code used in this analysis.
Tables 0 and 5 present reflood mass and energy releases to the containment, and the broken loop accumulator..mass and energy release.to the conta-'r-en, respectively.
Figures 1 through 17 present the transient; for the principle parameters for the break case analyzed.
The followirig items are noted:
Figures 1-3:
Quality, mass velocity and clad heat. transfer coefficient for. the hot spot, and burst locations.
Figures 4-6 Core pressure, break flow, and core pressure drop.
The break flow is the sum of the flowrates from both ends of the guillotine break.
The core pressure drop is taken as the pressure just before the cor e inlet to the pressure just beyond the core outlet.
Figures 7. Clad temperature, fluid temperature and core flow.
The clad and fluid temperatures are for the hot spot and burst location.
II
Figures 10-11 Downcomer and core water'level during reflood and flooding rate.
Figures 12-13 Emergency core cooling system flowrates, for both accumulator and pumped safety injection.
Figures 14-15 Containment pressure and core power transient.
Figures 16-17 Break energy release during blowdown and the containment wall condensing heat transfer coefficient for the worst break.
Conclus'on
e a
An For break up to and including the double-ended'severance of a reactor coolant
- pipe, the Emergency Core Cooling System will meet the Acceptance Criteria as presented in 10CFR50
.46 That, is (1)
The calculated peak clad temperature does not exceed 2200 F based on a
total core peaking factor of 2.32.
2.
The amount of fuel element cladding that reacts chemically with water or steam does not exceed one percent of the total amount of Zircaloy in the reactor.
3.
,The localized cladding oxidation limit of 17 percent is not exceeded during or.after quenching.
4.
~ The core remains amenable to cooling during and after the break.
5.
The core temperature is reduced and decay heat is removed for an extended period of time, as required by the long-lived radioactivity remaining in the core.
0
e nc 1.
"Acceptance Criteria for Emergency Core Cooling Systems for Light Mater Cooled Nuclear Power Reactors, " 10CFR50.46 and Appendix K of 10CFR50
'Federal Register, Volume 39, Number 2, January 4, 1974.
2.
- Bordelon, F. H., Hassie, H. M., and Zordan, T. A., "Mestinghouse ECCS Evaluation Model-Subpar y," MCAP-8339, July 1974.
3.
- Rahe, E. P., Mestinghouse Letter to C.. O. Thomas of NRC; Letter No.
NS-EPR-2673, October 27, 1982,
Subject:
"Mestinghouse Revised PAD Code Thermal Safety Model," MCAP-8720 A'ddendum 2 (Proprietary).
4.
- Bordelon, F. M., et al.,
"SATAN-VI Program:
Comprehensive Space-Time Dependent Analysis of Loss-of-Coolant,"
MCAP-8302 (Proprietary Version),
WCAP-8306 (Non-Proprietary Version),
June 1974.
" 5.
- Bordelon, F. M., et al.,
"LOCTA-ZV Progran:
Loss-of-Coolant Transient Analysis," MCAP-8301 (Proprietary Version),
MCAP-8305 (Non-Proprietary Version),
June 1974.
6.
Kelly, R. D., et al., "Calculational Model for Core Reflooding After a Loss-of-Coolant; Accident (MREFLOOD Code)."
MCAP-8170 (Proprietary Version),
MCAP-8171 (Non-Proprietary Verison),
June 1974.
7.
- Bordelon, F.
M. and Murphy, E. T., "Containment Pressure Analysis Code (COCO}," MCAP-8327 (Proprietary Version),
MCAP-8326 (Non-Proprietary Version}, June 1974.
Bordelin, F. M., et al., "The 'Westinghouse ECCS Evaluation hhdel:
Supplementary Information,." WCAP-8471 (Proprietary Version),
WCAP-8472 (Non-Proprietary Version), January.19?5.
Ck
9.
Salvatori, R.,
'Westinghouse ECUS Plant Sensitivity Stuaies,
>> WCAP-8340
(-Proprietary Version),
WCAP-8356 (Non-Proprietary Version), July 1974.
10.
Eicheldinger, C.,
>>Westinghouse ECCS, Evaluation Model, 19U1 Version,"
WCAP-9220-P-A (Proprietary Version),
WCAP-9221-A (Non-Proprietary Version),
Revision 1, December 1951.
0 0
TABLE 1 LARGE BREAK TIME SEQUENCE OF EVENTS START Rx Trip Signal S. I. Signal Acc. Injection End of Blowdown Bottom of Core Recovery Acc. Empty, Pump Injection DECLG C
= 0.4
- {sec) 0.00
.0.72 1.20 15.10 31.50 51.50 60.10 26.20'
Ci
'TABLE 2 Results Peak Clad Tenperature F
Peak Clad Location 'Ft.
Local Zr/H 0 Rxn (max)$
Local Zr/H 0 Location Ft.
Total Zr/H 0 Rxn 5 Hot Rod Burst T~e sec Hot Rod Burst Location Ft.
DECLG C
= '0 4 2130 7.25
- 5. 04
- 7. 50
( 0.30 42.'40 6.00 Calculation NSSS Power MNt 102$ of Peak Linear Power'kw/ft 102$ of Peaking Factor (At License Rating)
Accumulator Water Volume (per accumulator) 2200'2.96 2.32 875 ft3 r
Fuel region-~ cycle, analyzed Unit 3 Unit 4 Cycle 10 Region
0
~
TABLE 3 (Page 1 of 3) 0 CONTAINMENT DATA (DRY CONTAINMENT)
Ne't.Free Volume 1-55 x 106 Ft3 Initial Conditions Pressure Temperature RMST Temperature Service Mater Temperature Outside Temperature 14.7 psia 90.0 'F 39.0
'F 63.0
'F 39 O' Spray System Number of Pumps Operating Runout Flow Rate...
Actuation Time 2
1450 gpm 26 sec.
Safeguards Fan Coolers Number of F'an Coolers Operating Fastest Post Acciderit Initiation of Fan Coolers secs.
0
~
TABLE 3 (P.age 2 of 3)
STRUCTURAL HEAT SINK DATA Wall Material Thickness (in),
Area (Ft
)
- Paint, Carbon Steel 0.006996 0.2898-87335.8 Carbon Steel 0.006996 1000086.0 3'aint 0..006996 Carbon Steel 0.4896 35660.11 Carbon Steel '.4896 12367.5 Paint..
"Carbon Steel Concrete 0.006996 0.2898 24.0 50430.0 Carbon Steel'oncrete 0.2898 24.0 1 6810 0
Paint Carbon Steel 0.006996 1.56 4622.69 Carbon Steel
- 1. 56 1540. 89 Paint Carbon Steel 0.006996 5.496 1277.87 10 Carbon Steel-5.496 425.93 Paint Carbon Steel 0.006996 2.748 951.525
II
~ STRUCTURAL HEAT SINK DATA Wall Material Thickness (in),
Area (Ft
)
12 Carbon Steel
- 2. 748.
317.1?5 13 Paint Carbon Steel 0.006996 0.'03 23550.0 14 Paint Carbon Steel 0.006996 0.063 80368. 5 15 Paint Carbon Steel 0.006996 0.10 42278.25 16 Carbon Steel
- 0. 2898.
1?190.0 1?
Stainless Steel 0.032 1'13253.4 18 Stainless Steel 2.1264 3704.0 19 20 Stainless Steel Concrete Concrete 0.1398 24.0 24.0 14392.0 59132.0
TABL'f 4 REFLOOD MASS AND ENERGY RELEASES DECLG CD = 0.4 TIME sec
'51.502
. 52.527 53.827 59.190 69.455 85.555 103.355 121.555 139.455 176.055 216.355 312.355 374.455 Htot 1 ibm/sec) 0.0000 "0.027-0.179 35,78 49'4 63.77 77.36 89.74
,191'.83 281.32 293.54 324.7 343.08 Mhtot 1 (Btu/sec) 0.00 34.52 232.0 46,341.0 62,609.0 80,044.0 96,457.0 111,386.0 221,792.0 161,979.0 152,528.0 130,185.0 115,523'.0
41'
TABLE 5 DECLG C M0.4 Broken Loop injection SpiU. During Blowdown '
IIEE 0.000
- . 1 010 2 0 IO 3.010 4.010 5.010 6.010 7.010 8.010 9 010 10 010 11 010 12;010 13 010 14 010 15.010 16.010 17.010 18.010 19 010 20.0'I 0 21.010 22.010 23.010 "24.010 25 010 26 010 27.010 28.010 29.010 30.010 31 010 MASS 3535.277 3141.651 2860.790 2644.289 2470.732 2327.014 2204.531 2098.115 2004.118 1920 165 1844.473 1775.820 1713.335 1656.217 1603.810 1555.497 151O.SO6 1469.260 1430.312 1393.989 1360. 196 1328 768 1299.586 1272.391 124 6.995 1223.331 1201 261 1188.372 1169.'855 1152.163 1135.222 1119.132 ENESEGT 210914 639 1 874 30.924 170674.748 157758 278 147403.882 138829.651 131522.319 125173.549 119565.664 114557 023'10041277 105945.393 102217.588 98809.927 95683.328 92800.962 9013I
.687 87656.030 85332.398 83165 360 81149.315 79274 276 77533 298 75910 '39 74395.704 72983.901 71667 223 68705.285 67596.183 66536.555 65521.964 64558.282 EHTHALPT 59 660 59 660 59.'660 59 660 59 660 59.660 59.660 59 660 59.660 59.660 59 '60 59.660 59.660 59 660 59.660 59.660 59.660 59.660 59;660 59 660 59.660 59.660 59 660 59.660 59'.660 59 660 59 660 57.815
,57.782 57,.749 57.717 57.686
0
Figure<<1.
Fluid Oual ity DECLG(CD = 0.4)
I.IOOO l.2500 TURKE Y POINT (FPL)
- 0. I OECLG,. l98 I HOOEY F0=2. 32 REPLACEHENT SC MITN Q f'ERCENT TUBE PLVOOING ANO.FON=l.62 OUALITY OF FLU10 BURST ~
6 ~ 00 FT(
)
PEAK ~
7 ~ 25 FT( ~ )
4J 1.0000 0.1500 P
Oo 0.5000 0.2500 0.0 0
C) 0
<<<<)0 C) 0 0
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IQ
'Fiqure 2..
Mass Yelocity DECLG(CD = 0.0)
I00.00 TURKEY POINT (FPL)
O.i OECLI" l98I MODEL F0=2.32 REPLACEHENT SG MITH 5 PERCEHT TUBE PLUGGIHG AHO FOH=I.62 HASS VELOCITY BURST ~
6 ~ 00 FTl
)
. PEAK ~
7 ~ 25 FTI+)
Q 75.000 0
50.000 25.000 Iv 0.0
~ W 4J g -25.000 X
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~
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IP
Figure 3.
Heat Transfer Coefficient DECLG(CD = 0.4)
Illlfsll 600.00 500.00 100.00 300.00 200.00 TURKEY P01HT (FPL) 0.4'ECLG 1381 HOC 'L F0=2.32'EPLACEMENT SG MITH 5 PERCENT TUBE.
PLUGGIHG AHO FOH=1.62 NEAT TRANS.COEFF[ClENT BURST>>
6.00 FT(
)
PEAK. 7.25 IFT(~ )
I0.000 vI 30 000 20.000 6.0000 5.0000 1.0000 3.0090 2-0000 1 0000 CD CD CIC CD CDnn
~>>1 CD CD CD IC>>
i5
~ Fiaure 4.
Core Pressure DECLG(CD =
0:4)'$
00.0 I
312 FPLI ISX IS OFA -
1981 HOOEL 'M/ ACC/Sl INTERACTION OOUBLE EHOEO COLO LEG GUILLOTINE BREAK CO=0.C / fOH=I.62 PRESSURE CORE BOTTOH 1
I TOP
~
I ~ )
~
2OOO.O lsl 1500.0 CL 1000.0 soo.oo 0.0
~
CD CD CD CD CD CD AJ TIHE (SEC)
CD CD CD CDc CD CD
0
Figure'.
Break Flow Rate DECLG(CD = 0.4) 1.00E+05 7.50E+Oo LJ lal 5.00EK)O 312 FPL/ISX15 OFA - I98I MOOEL M/ ACC/SI INTERACTION oouBLE ENOEO COLO
- LEF, GulLLOTIHE BRE~~ Co=0.i /
FOH=1.62 BREAK FLOM 2.50EN)w 0.0
-2.50E<l
-5.00cioi
-1.50EK)i
- I.oof<05 C7 C>
ED CV TIVE )Sf C)
ED ED 4D C)
~
il 4
I Figure 6.
Core Pressure Drop DECLG(CD = 0.4) 70.000 3I2 FPL/I5X I5 OFA - I98 I MOOEL M/ ACC/Sl INTERACTION OOVBLE EHOEO COLO LEG GUILLOTINE BREAK CO=0.4 / FOH=I CORE PR.OROP 50.000 0<
25.000 ls Ja tf 0.0
-25.000
-50.000
-70.000 o
IDn C)n CU TIME ISEC)
C)nn C)
Figure 7.
Peak Clad Tenperature DECLG(CO
= 0.4) 2500.0 I
TURKEY POINT IFPL)
O.i OECLG l981 HOOEL F0=2
~ 32 REPLACEMENT SG MITH 5 PERCENT TUBE PLUGGIHG, AHD FDN=I.62 CLAD AVG ~ TEMP ~ HOT ROO BURST ~
6.00 FTI
)
PEAKED 7.25 FT)I)
~
2000.0 1500.0 I
~D o
1000.0 500.00 0.0 C>
C>
C7 CV 0
CI C)
Figure 8.
F1uid Temperature DECLG(CD = 0.4) 2000.0 p
1750.0 TURKEY'OINT (FPL) 0.4 OECLC 1981 HOOEL F0=2.32 REPLACEHENT SG
'MITH 5 PERCENT TUBE PLUGGING ANO FOH=1.62 FLUIO TEHPERATURE BURST ~
6;00 FT(
)
PEAK ~
7 25 FT( ~ )
1500.0' W
1250.0
~ w 1000.0 K
Lal 750.00 500.00 250.00 0 ~ 0
~
Cl ID C)
C)
C7 C)
C7 TIHE [SEC)
Figure 9.
Core Flow (Top and Bottom)
DECLG(CD = 0.4) 7000.0 312 fPL/15X15 OfA -
1981 MOOEL M/ ACC/Sl INTERACTION OOVBLE EHOEO COLO LEG GUILLOTINE BREAK CO=0.a / fOH=I.62 7-fLOMRATE CORE BOTTOM I
)
TOP e
(I)
I LJle lA 5000.0 2500.0 0.0
-2500.0
-5000.0
-7000.0 C)
C>
fV TIME (SEC)
C)
C)m
Fiqure 10.
Reflood Transient-Core
& Downcomer Water Levels DECLG(CD = 0.4) 20.000 17.500 TVRKE Y PolHT (FPL) 0.4 OECLG 1981 MOOEL IKCREASEO FOH REPL'ACEMEKT STEAM CEHERATORS MITH 5 PERCEKT TUBE PLVGGlKS MATER LEVEL(FT) 15.000 12.500 10.000 le)
T.SOeo le I
~
5.0000 2.5000 0.0 nn nnn n
T I ME 1 SE C) nnn n
nn
Ih
'Figure.11.
Reflood Transient Core Inlet Yelocity DECLG(CD = 0.4) 2.0000
- 1. 7500 TURKEY POINT (FPL)
O.o OECLC 198 t HOOEL IRCREASEO FOR REPLACEHEHT STEAH GENERATORS MITH 5 PERCENT TUBE PLUCGIHC FL000 RATE)IN/SEC)
I.5000 I.2500 Q '1.0000 4J X'
7500 CD 0.5090 0.2500 0.0 CD C)
CD CD CD CD EQ TIHE (SEC)
CD CD CD CD CD CD CD CD
0 0
Fi gure 12.
Accunulator Flow (Blowdown)
DECLG(CO = 0.4) 5000.0
'12 FPL/15X15 OFA ISBI HOOEL Ml ACCISI INTERACTION
~ OouBLE ENOEO COLO LEC. GUILLOTINE BREA~ Co=0.a i FOR=1,62 7-FLOMRATE LJ
~~
oooo.o I
CC.'00.0 I
~V 2000.0 1000.0 0.0 CD n
CD CD n
CD TIHE (SEC) n n
CDnn nn nfl
Fichu)'e 13.
Pumped EC).'S Flout (Reflood}
OECLG(CO = 0.4)
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0 100 200 TINE (seconds) 300
0 0
Figure 14.
Containment Pressure DECLG(CD = 0.4,)
120 160 200 240 280 320 360 noo TIHE (SECQNOS)
ig 0
Fiqupe 15.
Core Power Transient DECLG(CD ~ 0.4) 1 ~
~
i?.0000
- 1. 1500 312 FPL/15X 15 OFA - 1981 HOOEL V/ ACC/Sl 1HTKRACTION OOU8LK EHDKO. COLO LE'G. CUTLLOTlNE BREAK CO=0.i / Fg)H=1,82 POVER
~
~
1.5000 1.2500 1'.0000 0.7500 0.5000 0.2500 0.0 Ci Cl C)
C7 C7 tV T]HE lSEC)
Cl C'
ik t'
Figur'e 16.
Break Energy Released to Containment DECLG(CD = 0-4) 5.00E+01 31'FPL/15X15 Of'A -
19S1 HOOEl. Ml ACCISl )kTERACT10k OOUBLE EMOEO COLO LEG GUlLLOTlNE BREAK CO=0.1 l fOH=1.42'REAK ERERGT lal 3.00ERl 1.00E+7 LIJ la)
-1. OOE <07
-S.OOE+Q1
-S.OOEi01 C>
C>
C)
CI C7 CP TlHE (5ECl C)
O
~g no O
<i
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QQQ Finure 17.
Containment Mall Beat Transfer Coefficient DECLG(CD = 0.4) 800 700 600 500 400 300 209 100 lop TINE (Sr.CONDS) 200
h li t