ML18227C904
| ML18227C904 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/03/1977 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| L-77-1 | |
| Download: ML18227C904 (49) | |
Text
{2.16I
~
NRC DISTRIBUTION FDR PART 50 DOCKET MATERIAL DOCKET NUMBER 50 251 FILE NUMBER TO:
V. STELLO, JR.
FROM: FLORDIA POWER
& LIGHT CO.
MIAMI, FLORDIA R.E.
UHRIG DATE OF DOCUMENT 1/3/77 DATE RECEIVED 1/10/77 OLETTE R IHI ORIGINAL OCOA
'0 NOTOR IZE D lHUNCLASS IF I E D PROP INPUT FORM NUMBER OF COPIES RECEIVED DESCRIPTION LTR. RE.
THEIR 12/30/76 SUBMITTAL.....
PLANT NAME:
TURKEY PT.
ft 3
& 4 40 DQ NQT REMQVg CRNQWI@DGED ENCLOSURE RESULTS OF THE REVISED ECCS CALCULATIONS SUPPLFM~AL INFORMATION,......
I
( 40 CYS.
RECEIVED).
( =20 PAGES)
SAFETY ASSIGNED AD:
N
'P C
MANA E FOR ACTION/INFORMATION PROJECT MANAGER~
SAB 1 I1 77
~ ~
C ASST 0
"PARRISH-LIC ASST INTERNALDISTRIBUTION G FILE
~ NRC PDR I&E 2
OELD GOSSICK & STAFF MIPC CASE RLESS
'" PROJECT MANAGEMENT BOYD P
COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR TIC:
NSIC:
ASLB0 ACRS YS 89hBBf8'/
SYSTEMS SAFETY HEINEMAN SCHROEDER
- ENGINEERING MACARRY KNIGHT SIHWEIL PAWLICK REACTOR'AFE ROSS NOVAK ROSZTOCZY CHECK AT& I SALTZMAN RUTBERG EXTERNAL DISTRIBUTION NAT LAB REG V.IE LA PDR CONSULTANTS.
PLANT SYSTEMS TEDESCO IPPOLI 0 OPERATING REACTORS STELLO OPERATING TECH '-
EISENHUT BUTLE S
SAFE ERNST BALLARD SPANGLER SITE TECH GAMMILL STEPP HULMAN SITE ANALYSIS VOLLMER BUNCH J
COLLINS KREGER CONTROL NUMBER ECCJ'6 J
r h
8T 'Og k
j)
~
H
g
~egVaa'os fjl0 Cy,!
0GOym P. O. BOX 013100, MIAMI, FL 33101 gQll/gg
+/p naP'LORIDA POWER 5 LIGHTCOMPANY January 3,
1977 L-77-1 Office of Nuclear Reactor Regulation Attn:
Victor Stello, Jr., Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Stello:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 ECCS Reevaluation
~Su lemental Information On December 30, 1976, (L-76-438), Florida Power a Light Company forwarded the results of the revised ECCS calcu-lations performed using a rated power level of.2200 Mkft:
Several of the pages in our December 30, 1976, trans-mittal have been revised to improve their clarity.
A copy of the revised report is forwarded herewith.
Very truly yours, Robert E. Uhrig Vice President REU/GDW/hlc Attachment cc:
Norman C. Moseley, Region II Robert Lowenstein, Esq.
P EOP LE... S ER VIN G P EOP LE
il ~
~"
p
~
I p ~
I
'P N 'r.e s,/
j(
4
%I E
I A
J
~r JP b'
p' UPo E't k
W E
I 1 E p
E I
I, l,
I' t
ll
~'
~ (
~
TABLE 1
LARGE BREAK TIME SE UENCE OF EVENTS STEAN GENERATOR 10% TUBE PLUGGING DECL (CD 0.4).
(Sec)
START 0.0 Reactor Trip Signal S. I. Signal Acc. Injection End of Bypass End of Bio+down Bottom of Core Recovery Acc. Empty Pump Injection 0:595
- 0. 67
- 16. 3 27.52 27.66
- 46. 59
- 61. 02 25.67
P
'I
~
A II
'I, fl
TABLE 2
LARGE BREAK STEAM GENERATOR 10% TUBE PLUGGING Results DECL (CD 0.4)
Peak Clad Temp..'F Peak Clad Location Ft.
Local Zr/H20 Rxn(max)%
Local Zr/H20 Location Ft.
Total Zr/H20 Reaction Hot Rod Burst Time sec Hot Rod Burst Location Ft.
2190.
6.0
- 11. 922 6.0
<<0. 3
- 22. 8 6.0 Calculation Core Power Mwt 102% of Peak Linear Power kw/ft 102% of Peaking Factor Accumulator Water Volume (ft )
3 2200
- 12. 61 2.22 875 (per accumulator)
Fuel region + cycle analyzed
~Cele
~Re ion UNITS 3 and 4
'4 V
V 4
p 4f 4
1 V
~ 4
~
k TABLE 3
/
LARGE BREAK CONTAINMENT DATA (DRY CONTAII61ENT)
NET FREE VOLUME 1.55 x 10 Ft INITIALCONDITIONS Pressure Temperature RWST Temperature Service Water Temperature Outside Temperature 14<<7 psia 90
'F'9
'F 63
'F 39
'F SPRAY SYSTEM
.Number of Pumps Operating Runout Flow Rate Actuation Time 1450 gpm 26
.secs SAFEGUARDS FAN COOLERS Number of Fan Coolers Operating Minimum Post Accident Initiation Time for Fan Coolers 3
26 secs
'l 4(
1
TABLE 3
'Continued)
LARGE BREAK COiHTAXaiLLENT DATA (DRY CONTAXat~fE'LLlT)
STRUCTURAL ERAT SXNKS Thickness (Xn Area (Ft )
Steel Steel Steel Steel Steel Steel Concrete
, Steel Steel Steel Steel Steel Steel Steel Steel Steel Stainless Concrete Stainless Stainless S"ain" ess Concrete 0.03
- 0. 063 0.1 0.2
- 0. 24
- 0. 2898
- 24. 0 0.4896
- 0. 6396 0.8904 1.256 1.56 2.0 2.75 5.5 9.0
- 0. 14 24.0 0.44
- 2. 126
- 0. 007
- 24. 0 31s400 107,158 56,371 57,185 9,931 136,000 23,677 6,537 4,915 27,802 5,307 668 1268. 7 1277.4 260. 4 14,392 768 3,704 102, 400 59)132
gl I
8'
'L
~ )
~
TABLE 4
REFLOOD MASS AND ENERGY RELEASES FOR LIMITING CASE DECLG (C =0.4)'AND 10%
STEAM GENERATOR TUBE PLUGGING TIME (SEC)
TOTAL MASS FLOMRATE (LBM/SEC)
TOTAL ENERGY FLORATE 10 BTU/SEC) 46.589 48.714 54.286 64.436
- 77. 136 92.136 107.936 124.236 159.236 197.536
0.0
- 0. 0415 35.50
"'95.65
- 98. 17 103. 9 220. 9 263.2 274. 8 281. 5 0.0 0.0005
'.4614
- 1. 189 1.. 219
- 1. 280
- 1. 603 1.678 1.60/
3.. 514
TABLE 5
BROKEN LOOP ACCUMtJLATOR FLOW TO CONTAINMENT FOR LIMITING CASE DECLG (C =0.4) lOX D
STEAM GENERATOR TtJBE PLUGGING TIME SEC)
MASS FLOWRATE (LBM/SEC) 0.0
- 0. 02
- 2. 00 4.00 6.00 8.00
>0.0 15.0 20.0 25.0
- 30. 0 35.0
- 38. 9 0.0 2723.5 2276.0 1994.9 1793.1 1645.5 1526. 4 1302. 5 1137. 8 1034. 6 954. 2 887. 0 842. 6
'I
l0,833-I 6
8 IO 2
II 6
8 IO 2
TIME (SECONDS) 6 8 I08 I
(
Figure 1
Fluid Quality - DECLG (GD = OA)
IO, 833-2
.30 20 c4 10 0
- IO 6.O Ft.
-20
-30 IO 2
4 6
8 IO 2
0 6
8 IO 2
. 0 6
8 IO TIME (SECONDS)
Figure 2 Mass Velocity - DECLG (CD = 0.4)
'I
l0,833-3 lp" 8
6 0
CU lp3 8
I ca 6
2 LU lp2 8
6 CC 2
I-lp' 6
6.0 Ft.
lpp 0
lpp TlHE (SECONDS) 200 300 Figure 3 Heat Transfer Coefficient - DECLG (CD = 0.4)
~
~
II II
~ I 4
v V
"r C
'I I
I I I J,
I Il I
I I I
l0, 833-'0 2500 2000 I500 IOOO CL 500 0
0 l0 TIME (SECOHDS) 20 30 Figure 4 Core Pressure
- DECLG (Cp = 0.4)
~
/
iixl04 exio~
Txlo" 5XI04 g
3x IO" Ixlo~
-ixlo~
0 IO TIME (SECONDS) 20 30 Figure 5 Break Flow Rate-DECLG (CD =0.4)
1 l
~ ~
~
I
~
~
U
~ I0,833-6 75 50 25 0
-25
-50
-75 0
IO TIME (SECOIIDS) 20 30 Figure 6 Core Pressure Drop - DECLG (CD = 0.4)
h
~
~
M Il t ~ ~
I
~
h
~
l0,833-7 2500 U
O 2000 6.0 Ft.'J I
OC LJJ D
UJ I
LLI JJj 1500 I000 500 0
0 IOO TIME (SECOHDS) 200 300 Figure 7 Peak Clad Temperature
- DECLG'(C
= OA)
D
0 g
1
~
I V
I "I
(
~
J
'I P
III
2000-I750 I500 w
I 250 w
IPPP 750 500 6.0 Ft.'50 0
0 IOO 200 TIME (SECONDS) 300 Figure 8 Fluid Temperature
- DECLG (Cg = 0.4)
II LLL
l0000 7500 I
I II.-
5000 2500 lli ED
-2500
-5000
-7500
-l0000 0
IO TIME (SECONDS) 20 30 Figure 9 Core Flow - Top and Bottom - DECLG (CD = 0.4)
5-
~
~
~,
~
nl CI n
'4
/
IP n
2.00 l.75 I. 50 g
0.75 0'0
- 0. 25
- 0. 00 0
25 50 75 l00 TIME (SECONDS)
I25 l50 l75 200 Figure 10 Reflood Transient-DECLG (CD = 0.4)
Core Inlet Velocity
N I
r
,~
~
~ ~
P
'Ij
~
1 I
T F
I I
II e
e l
J
~,
~.-
l
- 20. 0 17.5 00MHCOMER LEVEL l5.0
- 12. 5
- 10. 0 7.5 5.0 CORE LEVEL.
P 2.5 0.0 0
100
~ 125 150 175 200 TlME (SECONDS)
Figure U Reflood Transient - DECLG (Cp = OA)
Downcorner and Core M/ater Levels
1 t'f S
lt
'0,833-l2
'000 5000 4000 3000 I-,
2000
'I 000 0
0 l0 20 T IME (SECONDS) 30 Figure 12 Accumulator Flow (8lowdown) --DECLG (CD = 0.4)
P f C
~
8.0 6.0
%.0 2.0 0 ~ 0 0
%0 I
a I
e I
t 80
)20 T I t tE (SECOHDS) leo 200 Figure l3, Pumped ECCS Flow (Reflood) - DECLG (CD = 0.4)
P P
l L
~
~ g 1
l V
c C't t
r' 4
1
\\
'1 I
l
~
~
1 c
e 1
P
'N l
30.
25 20 a=
l5 I
l0 l
CP 0
0 40 80 l20 l60 200 240 280 320 360 400 TlME (SECONDS)
Figure 14
- Containment Pressure
- DECLG (CD OA)
Ct V
00 Col CO I
II
~ a I
'4
~
I
C
~
~ ~
l.o 0.8 0.6 LUo 0.%
0.2 0.0 0
l0 TlWE (SECOHOS) 20 30 Figure l5 Core Power Transient - DECLG (CD = 0.4)
I
0 4
~
\\ ~ f T
r
I0,833-I6 55xl06 tl5x I 0 CD LLj CQ CCI 35xl06 25xl06 l5x I 0 5xl06
-.5x I 06 0
IO 20 T IME (SECONDS) 30
'igure 16 Break Energy Released to Containment
~
I v
~
l ~
k ~
~ I ~
~ D L0,833-I7 IIOO U
OI I
Ll I
Ch I
CKL I
LLI Ll ULll ED CD IOOO 900 800 700 600 500 CQ Lal Ch ED CD
%00 300
~'
LIJ l
ID CD 200 IOO 0
0 l00 TIME (SECONDS) 200 300 Figure 17; Containment Wall Condensing Heat Transfer Coefficient
C ~