ML18227B015
| ML18227B015 | |
| 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: ML18227B015 (40) | |
Text
NRC FORM 195 US, NUOLSAR RSOULATORSQMMISS ION g-NI ~
NRC DISTRIBUTION FDR PART 50 DOCKET MATERIAL DOCKET NUMB 50-250 25 FILE NUMBER TP:
V. STELLO, JR.
FROM: FLORDIA POWER
& LIGHT CO ~
MIAMI, FLORDIA R.E.
UHRIG r
DATE OF DOCUMENT 1/3/77 DATE RECEIVED 1/10/77 DLETTER JHIORIGINAL
- 0COPV, I
, ClNOTORIZED "la UNC LASS IF I E D II I
'S VT PROP DESCRIPTION
'-..LTR.
PE. THEIR,12/30/76..SUBMITTAL,...
S INPUT FORM NUMBER OF COPIES RECEIVED
- 40 I
l S
I ENCLOSURE, RESULTSrOFMHE.REVISED ECCS CALCULATXONS......
SUPPL~~AL INFORMATION,..
( 40 CYS. RECEIVED).
( 20 PAGES)
PLANT~:
TURKEY PT.
f/ 3 a 4 ACKNOVKEDGED
> >EM
. SAFETY ASSIGNED AD:
FOR ACTION/INFORMATION SAB 1
11 77 N
. MOJEC MANA ER
~.'
ASST O-l A
I S
'ARR~ISH' P OJECT MANAGER LIC "ASS'P-" '
NlAA APISg S S 'l S A ~ S M RR '
l
~ ~
P,'RS'4)1 R
S M INTERNALDISTRIBUTION l
S>>NU
~
h)S G.FI
~ NRC PDR I&E 2
.OELD GOSSICK & STAFF MIPC CASE HANAUER IARLESS
.SYSTEMS SAFETY
.HEXNEMAN SCHROEDER
"".:ENGINEERING K:JIGHT SIHWEIL PAWLICK
'.'ROJECT MANAGEMENT REA'CTOR'AFE BOYD ROSS P,
COLLIiVS NOVAK ROSZTOCZY
. HOIJSTQiV.
PETERSON MELTZ HELTEMES CIIECK AT& I SKOVHOLT SALTZMAN RUTBERG EXTERNAL DISTRIBUTION LPDR NAT LAB TIC:
REG V IE NSIC:
LA PDR ASLB:
CONSULTANTS.
ACRS YS HOBBRfB'/ E T PLANT SYSTEMS
~
TEDESCO.
N 0 A IPPOElTO
'PERATXNG REACTORS STELLO OPERATINC TECH" EISENHUT BUTLE B 00 SITE SAFE
~
ENV 0
~
ERNST BALLARD SPANGLER SITE TECH GAMMIIIL-"yAq "K>""">'T STEPP HULMAN
=
SITE ANALYSIS VOLLlER BUNCH J
COLLINS KREGER CONTROL NUMBER I
8QC 176
1 I\\
~egUFatory
~ '
n cP PA,M fl 810~977 ~
~ 1iyfoh 1 i Cloi'k Doc ~
t P. O. BOX 013100, MIAMI, FL 33101 ilail I/i FLORIDAPOWER & LIGHTCOMPANY January 3',
197 7 L-77-1 0ffice of Nuclear Reactor Regulation Attn:
Victor Stello, Jr
, Director Division of Operating Reactors U.
S. Nuclear Regulatory 'Commission Washington, D.
C.
20555 p g, ygggAa KCIIIIT0l5
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,
& Light Company forwarded the resul+s of the revised ECCS calcu-lations performed using a rated power level of 2200 Migt.
Several of the pages in our December 30, 1976, trans-mittal have been revised to improve their clarity.
A copy of the revised reoort is forwarded herewith.
Very truly yours,
~~DEÃ Robert E. Uhrig Vice Presiden+
REU/GDW/hlc Attachm nt cc; Norman C. Moseley, Region 1X Robert Lowenstein, Esp.
PEOPLE... SERVING PEOPLE
p 9wy t
ly i
k 4P
- ~ 4 rl I
Pi II Wp lt a
sl "
5 ~
'll r
'I
TABLE LARGE BREAK TIME SE UENCE OP EVENTS STEAM GENERATOR 10% TUBE PLUGGING DECL (CD 0.4)
(Sec)
START Reactor Trip Signal S. I. Signal Acc.
Zng ection End of Bypass End of Blowdown Bottom of Core Recovery Acc. Empty Pump Injection 0.0 0:595 0.67
- 16. 3 27.52 27.66
- 46. 59
- 61. 02 25.67
II
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.
lle922 6.0
<0. 3
- 22. 8 6.0 Calculation
'et Core Power Mwt 102% of Peak Linear Power kw/ft 102% of Peaking Factor Accumulator Water Volume (ft )
3 2200
- 12. 61 2.22 87S (per accumulator)
Fuel region + cycle analyzed Cycl.e
~Re 1ou UNITS 3 and 4
C TABLE 3
/
LARGE BREAK CONTAINiKNT DATA (DRY CONTAItPiiENT)
NET FREEVOLE'.55 x 10 Ft INITIALCONDITIONS Pressure Temperature RWST Temperature k
Service Water Temperature Outside Temperature 14 7
psia 90
'F 39
'F 63
'F 39
'F SPRAY SYSTEM Number of Pumps Operating Runout Plow Rate r.
Actuation Time 1450 gpm 26 secs SAWeGUARDS FAN COOLERS Number of Fan Coolers Operating Minimum Post Accident Initiation Time for Fan Coolers 26 secs
ill C
l U
ri
TABLE 3
(Continued)
LARGE BREAK CONTALWiENT DATA (DRY CONTAVa~1ENT)
STRUCTURAL HEAT SINKS Thickness (In)
Area (Ft )
Steel Steel Steel Steel Steel Steel Concrete Steel Steel Steel Steel Steel Steel Steel Steel Steel Stainless Concrete Stainless Stainless Stainless 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 31,400 107, 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 3s 704 102,400 59,132
t
TABLE REFLOOD MASS AND ENERGY RELEASES
'FOR LIMITING CASE DECLG (C =0.4)
AND 10%
STEAM GENERATOR TUBE PLUGGING TIME (SEC).
TOTAL MASS FLOWRATE (LBM/SEC)
TOTAL EPRGY FLOUR'ATE 10 BTU/SEC) 46.589 48.714 54.286 64.436
?7.136 92.136 107.936 124.236 159.236 19 7. 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 0.4614
- 1. 189
- 1. 219
- 1. 280 1.603 1.678 1.607 1.514
l 1
TABLE 5
BROKEN LOOP.
ACCUMULATOR FLOP TO CONTAINMENT FOR LIMITING C&E DECLG (C =0.4) 10X D.
STEAM GENERATOR TUBE PLUGGING TIME SEC)
MASS FLOmmTZ (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
I0,833-I l.05 I. 00 0.95
- 0. 90 CD 0.85 0.80 0.75 IO 2
II 6
8 IOI 2
0 6
8 IO 2
TIME (SECONDS) 6 8IO Figure 1 Fluid Quality - DECLG (CD = 0.4)
l0,833-2 30 20 UJ cv IP o-0 I
CD CD
- IO 6.O Ft;
-20
-30 IOO 2
0 6
8 10 2.
iI 6
8 IO 2
. 0 6
8 l03 TIME (SECONDS)
Figure 2 Mass Velocity - DECLG (CD = 0.4)
l I
1J li tt
pl IO, 833-3 io" 8
6' 2
)
I l08 2
l02 8
6 I
I l0 6
~ 6.0 Ft-l00 0
l00 TIME (SECOHDS) 200
'00 Figure 3 Heat Transfer Coefficient - DECLG (CD = 0.4)
t
2500 2000 l500 l000 500
.00'0 T I thE (SECONDS) 20 30 Figure 4 Core Pressure
- DECLG (Cp = 0.4)
l0,833-5 llxlO" exlo'xio~
Sxlo U
g 3x IO~
lxlo"
-lxlo' 10 TIME (SECONDS) 20 30 Figure 5 Break Flow Rate-DECLG tCD =0.4)
75 50 25 0
-25
-50
-75 IO TlME (SECONDS) 20 30 Figure 6 Core Pressure Drop - DECLG (CD = OA)
l0,833-7 2500 2000 Cl CD CD I
l 500 l000 W
500 h
6.O.Ft; 0
0 l00 TIME (SECONDS) 300'igure 7 Peak Clad Temperature
- DECLG (C
= 0.4)
D
l0,833-8 2000 l750
!500 I 250 l000 I
a 750 500 6.0 Ft.
250 0
0 IOO TIME (SECONDS) 200 300 Figure 8 Fluid Temperature
- DECLG {CD = 0.4)
10,833-9 lOOQO 7500 5000 2500 C)
-2500 l(e
-5000
-7500
-I0000 0
l0 TIME (SECOHDS) 20 30 Figure 9 Core Flow - Top and Bottom - DECLG (CD = 0.4)
2.00 I.75 I. 50 I. 25 l.pp I-o 0,75
- 0. 50
- 0. 25
- 0. 00 0
25
/
50 75 lpp TIME (SECOHDSj 125 l50 l75 200 Figure 10 Reflood Transient - DECLG (CD = 0.4)
Core Inlet Velocity CI CO CD CD I
Ct
20.0
'7.5 DOWHCOt4ER LEVEL
- 15. 0
- 12. 5
- 10. 0 7.5 5.0 CORE LEVEL 2.5 0.0 0
25 50 75 100 125 150 175 200 TIME (SECONDS)
Figure ll Reflood Transient - OECLG (CO = 0.4)
Downcomer and Core Water Levels
l0,833-I2
'000 5000
%000 3000 2000 CD IOOO 0
0 IO 20 TIME (SECONDS) 30 Figure 12 Accumulator Flow (Blowdown) - DECLG (C> = 0.4)
8.0 6.0 II.0 2.0 0.0 0
QO I
t I
I I
t 80 I20 TIME (SECONDS)
I60 200 Figure 13 Pumped ECCS Flow (Reflood) - DECLG (CD = 0.4)
30.
25 20 l5 I
l0 I-ED 0
0
%0 80 120
!60 200 200 280 320 360
%00 TIME (SECONDS)
Figure 14 'ontainment Pressure -.DECLG (C~
0.4)
0
l.o 0.8 0.6 IAo
- 0. ll 0.2 0.0 0
l0 TlME (SECONDS) 20 30 Figure 15 Core Power Transient - DECLG (CD = 0.4)
55x I 06
%5x IO 35xl06 25x I 06 l5xl06 5xl06
-.5x IO6 0
IO 20 TIME (SECONDS) 30 Figure 16 Break Energy Released to Containment
l0,833-l7 I I 00 U
OI I
U 1
l-CCl I
UJ CD U
UUJ CD CD UJ I
I-UJ CQ UJ C5 CD CD I
UJ l
ID I 000 900 800 700 600 500
'I
%0 300 200 IOO 0
0 IOO TIME (SECOIIDS) 200 300 Figure 17 Containment Wall Condensing Heat Transfer Coefficient
(0,833-l7 I IOO U
O I
I U
I CC I
le I 000 900 I
UJ CD U
U UJ ED CD UJ U
C/)
UJ I
C)
CD 800 700 600 500 KO 300 200 IOO 0
0 IOO TIME,.(SECONDS) 200 300 Figure 17 Containment Wall Condensing Heat Transfer Coefficient
0 p
Q
0 l0, 833-l7 I l00 U
O II-U I
I Cl I
M CD LL U
LU 000 900 800 700 600 CO Ul C5 CD 500
%00 300 I
UJ I
200 l00 0
0 l00 TIME (SECONDS) 200 300 Figure 17 Containment Wall Condensing Heat Transfer Coefficient
e i'