ML20070Q500
| ML20070Q500 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 01/31/1989 |
| From: | Finn S, Lobner P SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
| To: | NRC |
| References | |
| CON-FIN-D-1763, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-89-1016, NUDOCS 9103290099 | |
| Download: ML20070Q500 (112) | |
Text
_. _ _ _ _ _ _ _ _ - _ _ _ _
O f, e.,%
\\
i NUCLEAR POWER PLANT
$y
.p i SYSTEM SOURCEBOOK g'$ @..g %*w* f[
i
[
BRAIDWOOD 1 AND 2
50 456 and 50 457 O
=--
~~
-=
9103290099 910327 PDR ADOCK 05000029 P
P SAIC 89/1016 R REGg A
n>og y *
.,3d).3 i NUCLEAR POWER PLANT o
$g 1
SYSTEM SOURCFBOOK t
49
% w+
4 5
BRAIDWOOD 1 AND 2 50 456 and 50 457 Editor: Peter Lobner Author: Stephen Finn l
l l
I t
i Prepared for:
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 4
Contract NRC 03 87 029 FIN D 1763
' O
= =,
=
mmy "w..
~
4
Braidwood 1 & 2 TABLE OF CONTENTS V
Section Eagg 1
S U 515 t A R Y D ATA ON PLANT................................................
1 2
IDENTIFICATION OF SlhilLAR NUCLEAR POWER PLANTS........
1 3
S Y S TE.N ! I NFO RM ATI O N.....................................................
2 3.1 R eac tor Coolant S yste m ( RCS).........................................
7 3.2 Auxiliary Feedwater (AFW) System and Secondary S team Relic f (S S R) S vstem............................................
13 3.3 Emergency Core Cooling System (ECCS)............................
20 3.4 Charging S ystem ( CVCS)...............................................
30 3,5 Contain ment H eat Removal S ystems...................................
35 3,6 Instrumentation and Con trol (I & C) System..........................
41 3.7 Elec tric Powe r S y ste m..................................................
45 3.8 Component Co o l i n g S y s t e m.............................................
60 3.9 Essential Service Water (ES W) S ystem................................
65 4
P i A NT I NFO R h 1 ATI ON.......................................................
72 4.1 S it e and B uildin g S u mmary.................................. '...........
72 4.2 Fa cili t y Layou t Dra wing s...........,,,,,................,,,,,.........
72 5
BIB LIOG R A PH Y FOR BR AIDWOOD 1 AND 2.......................
93 (N
APPENDIN A. Definition of Symbols Used in the System and
(
La yo u t D ra wi n g s..............................................94 APPENDIX B. Definition of Temis Used in the Data Tables.............. 101 l
l 0
t
\\
i 1/89
~
4 4
Braidwooc' 1 & 2
,f LIST OF FIGURES U
Ficure g
31 Cooling Water Systems Functional Diagram for Braidwood 1 and 2...
6 3,1 1 Isometric View of a 4 Loop Westinghouse RCS..........................
9 3.1 2 Braidwoal Unit 1 Reactor Coolant System..............................
10 3.1 3 Braidwood Unit 1 Reactor Coolant System Showing Component Lceations.......
I1 3.2 1 Braidwood Unit 1 Auxiliary Feedwater System...........................
16 3.2 2 Braidwood Unit 1 Auxiliary Feedwater System Showing Component Locations.........................................................
17 3.2-3 Braidw cod Unit S tartup Feedwater System...............................
18 3.3-1 Braidwood Unit 1 Safety injection System................................
24 3.3-0 Braidwood Unit 1 Safet Lceadons.,.............yInjection System Showing Component 25 3.3-3 Braidwood Unit 1 Residual Heat Removal System.......................
26 ik 3.3 4 Braidwood Unit 1 Residual Heat Removal System Showing Componeni Locations........................................................
27 3.4-1 B raidwood U ni t 1 Charging S ystem........................................32 3.4 2 Braidwood Unit 1 Char Locations................ging System Showing Component 33 3.5-1 B raid wood Uni t 1 Con tainmen t Spray System........................... 38 3.5 2 Braidwood Unit 1 Containment Spray System Showing Component Locations.........................................................
39 3.7 1 Braidwood Unit 14160 and 480 VAC Electric Power Di S y s te m........................................................s t 48-3.7-2 Braidwood Unit 14160 and 480 VAC Electric Power Distribution S ys tem S howi ng Componen t Locations....................................
49 3.7 3 Braidwood Unit 1 125 VDC and 120 VAC Electric Power D i s tri b u d o n S y s t e m..........................................................
50 3.7-4 Braidwood Unit 1 125 VDC and 120 VAC Electric Power Distribution System Showing Component Locations.....................
51 3.7 5 B raidwood Unit 1 Diesel Fuel Oil System.................................
52 ii 1/89
Braidwood 1 & 2 LIST OF FIGURES (continued)
O Ficure Eage 3.S.1 Braidwood Unit 1 & 2 Component Cooling Water System............
62 3.S.2 Braidwood Unit 1 & 2 Component Cooling Water S Showing Component Locations........................ystem 63 3.9 1 Braidwood Unit 1 & 2 Essential Service Water System.................,
67 3.9 2 Braidwood Unit 1 & 2 Essential Service Water System Showing Component Locations........................................................
69 4
41 General View of Braidwood Nuclear Station and Vicinity...............
73 42 B raid wood ! & 2 Plot Plan.................................................
74 43 Braidwood Unit 1 Reactor. Auxiliary, and Turbine Building Elevation Drawing.............................................................
75 4-4 Braidwood 1 & 2 Reactor. Auxiliary, and Fuel Handling Building Elevatton Drawing...........................................................
76 45 Braidwcod 1 & 2 Station Arrangement, Elevation 330'of the
)
Auxiliary Building.............................................................
77 a
"~
4-6 Braidwood 1 & 2 Station Arrangement, Elevation 346'................
78 4-7 Braidwood 1 & 2 Station Arrangement. Elevation 364'................
79 48 Braidwood 1 & 2 Station Arrangement, Elevation 383'..........,,......
80 4-9 Braidwood I & 2 Station Arrangement, Elevation 401'..................
81 4-10 Braidwood 1 & 2 Station Arrangement, Elevation 426'..................
82 4 11 Braidwood 1 & 2 Station Arrangement, Elevation 451'.................
83 A1 Key to Symbols in Fluid System Drawings...............................,
97 A-2 Key to Symbols in Electrical System Drawings...........................
99 A-3 Key to Symbols in Facility Layout Drawings..............................
100 i
h
' v iii 1/89
-- ~.
Braidwood 1 & 2 LIST OF TAllLES
\\
T2k Pan 3-1 Summary of Braidwood Systems Covered in this Report...............
3 4
3.1-1 Braidwood Unit 1 Reactor Coolant System Data Summary l
for S elee t ed Co mpon en ts....................................................
12 3.2-1 Braidwood Unit 1 Auxiliary Feedwater System Data Summary fo r S e l ec t ed Co mpon en ts.....................................................
19 3.3 1 Braidwood Unit 1 Emergency Core Cooling System Data S u mm ary for S e i e e t ed Com po ne n ts.........................................
28 3.4-1 Braidwood Unit 1 Charging System Data Summary for S el ec t ed Co mpon en ts.....................................................
34 3.5 - 1 Braidwood Unit 1 Containment Heat Removal System Data S u m m a ry fo r S e I ee t ed Com po ne n ts.........................................
40 3.6-1 Braidwood Equipment Contr'ols Available Outside the l
Contro1 Room.....................,........................................
44 l
s 3.7 1 Braidwood Unit 1 Electric Power System Data Summary l
x for S elec ted Compon en ts.....................................................
53 3.7 2 Partial Listing of Electrical Sources and Loads at Braidwood Unit 1...
55 3.8 1 Br:iiwood Unit 1 Component Cooling System Data Summary for S elec t ed Co mpo n e n ts.................................................... _64 3.9 1 Braidwood Unit 1 Essential Setvice Water System Data Summar for S elected Compon en ts.............................................y 71 41 Definition of Braidwood 1 Building and Location Codes................
84 4-2 Partial Listing of Components by Location at Braidwood Unit 1.......
87 B1 Compone nt Type Cod e s...................................................... - 103 x
iv 1/89
Braidwood 1 & 2 CAUTION The infom1ation in this repon has been developed over an extended period of time based on a site visit, the Final Safety Analysis Repon, system and 4
layout drawings, and other published information. To the best of our knowledge, it accurately reflects the plant configuration at the time the 4
infonnation was obtained, however, the information in this document has not been independently verified by the licensee or the NRC, I
i NOTICE i
This sourcebook will be periodically updated with new and/or replacement pages as appropriate to incorporate additional information on this reactor plant. Technical errors in this repon should be brought to the attention of the following:
Mr. Mark Rubin p
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Engineering and Systems Technology Mail stop 7E4 Washington, D.C. 20555 With copy to:
Mr. Peter Lobner Manager, Systems Engineering Division Science Applications International Corporation 10210 Campus Point Drive San Diego, CA 92131 (619) 458-2673 Correction and other recommended changes should be submitted in the form of marked up copies of the affected text, tables or figures, Supporting _
l documentation should be included if possible.
v v
1/89 e
+w w w
,-e v:-r.+
- -. - -. -..=. -
1 i
O IIRAIDWOOD 1 AND 2 U
RECORD OF REVISIONS REY!SION ISSUE COMMENTS 0
1/89 Original report I
O I'
4
?
l J
i vi 1/89
Braidwood 1 & 2 BR AIDWOOD 1 AND 2 SYSTEA1 SOURCEBOOK V
This sourcebook contains summary information on Braidwood 1 and 2. Summary data on this plant are presented in Section 1, and similar nuclear power plants are identified in Section 2. Infonnation on selected reactor plant systems is p.*esented in Section 3, and the site and building layout is illustrated in Section 1. A bibliography of reports that describe features of this plant or site is presented in Section 5. Symbols used in the system and layout drawings are defined in Appendix A, Terms used in data tables are defined in Appendix B.
1, SU5151ARY DATA ON PLANT Basic information on the Braidwood 1 & 2 nuclear power plant is listed below:
Docket number 50-456 (Unit 1),50-457 (Unit 2)
Operator Commonwealth Edison Company Location Braidwood, Illinois Commercial operation date 9/88 (Unit 1), early 1989 (Unit 2, expected)
Reactor type PWR NSSS vendor Westinghouse Number ofloops 4
Power (N!Wt/hlWe) 3411/1120 Architect-engineer Sargent & Lundy Containment type Reinforced concrete cylinder with steel liner Q]
,f 2.
IDENTIFICATION OF SIhtILAR NUCLEAR POWER PLANTS Each Braidwood unit has a Westinghouse PWR four-loo) nuclear steam supply system (SSSS). Other four loop Westinghouse plants in the Unitec States include:
Byron 1 and 2 Callaway Catawba 1 and 2 Comanche Peak I and 2 Donald C, Cook I and 2 (ice condenser containment)
Diablo Canyon 1 and 2 Haddam Neck Indian Point 2 and 3
)
hicGuire 1 and 2 (ice condenser containment)
Niillstone 3 Salem 1 and 2 Seabrook 1 Sequoyah I and 2 (ice condensercontainment)
Shearon Harris 1 and 2 l
South Texas 1 and 2 l
Trojan Vogtle 1 and 2 Watts Bar 1 and 2 Wolf Creek Yankee Rowe Zion I and 2 G
1 1/89
Braidwood I & 2 p<
Braidwood differs from the majority of Westinghouse plants in that the gd auxiliary feedwater system consists of one motor driven and one diesel driven pump, whereas other plants contain some number of motor criven and turbine driven pumps.
Braidwood is similar to other plants in the number and type of charging and high pressure intecuon pumps.
Braidwood is a twin of the Byron plant However, there are minor differences between the two plants. These differences are noted in the appropriate sections of this report.
3.
SYSTEN! INFOR51 ATION This section contains descriptions of selected systems at Braidwood I and 2 in terms of general function, operation, system success criteria, major components, and support system requirements. A summary of major systems at Braidwood I and 2 is presented in Table 3-1, in the " Report Section" column of this table, a section reference (i.e. 3.1,3.2, etc.) is provided for all systems that are described in this report. An entry of "X"in this colamn means that the system is not described in this report In the "FSAR Section Reference" column, a cross reference is provided to the section of the Final Safety Analysis Report u here additional information on each system can be found. Other sources of infom1 anon on this plant are identified in the bibliography in'Section 5.
Several cooling water systems are identified in Table 31. The functional relationships that exist among cooling water systems required for safe shutdown are shown in Figure 31. Details on the individual cooling water systems are provided in the report secaens iden:itleti :n Table 3 1.
1 i
J 2
1/89
^
\\
Table 3-1.
Summary of Ilraidwood Systems Coscred in this Iteport t
Generic Plant-Specific Report FSAR Sectmn i
System. Na me System Name Sectinn Re ference i
e Reactor IIcat ' Removal S5 stems Reactor Coolant System (itCS)
Same 3.I 5
l Auxiliary Feedwater (AITV)and Same 3.2 10.4.9 Secondary Steam Relief (SSR)
Systems
'i Emergency Core Cooling Systems Same
' (ECCS)
I
+ liigh-Pressure Injectionj Safety injection System.'
3.3 6.3
& Recirculation ~
Charging System -
3.4 6.3 1
- Low-pressure Injection.-
Residual IIcat Removal System.
3.3.
~ 6.3 i
' & Recirculation L
t
. us
- ' Decay llent Removal (DilR) z Residual IIeat Removal (RIIR) -
3.3 6.3
'l
. System (Residual IIcat Removal
. System (RIIR) System)-
Main Steam and Power Conversion Main Steam Supply System
'X 10.3,
. Systems
. Condensate and Feedwater System.
-. OtherIIeat Removal Systems -
None identified '
X.
Reactor Coolant Inventory Control. Systems.
Chemicaland Volume Control System Same 3.4 9.3.4, 6.3 (CVCS)(Charging System) ~
t ECCS.
See ECCS; above-R.
.l t
i
~-
N
,a Table 3-1.
Summary of Itraidwood Systeins Covered in this Report (Continned)
Generic Plant-Specific Report FSAR Section System Name System Name Efesion Reference Containment Systems Containment Same X
6.2.1 Containment Ilear Renoval Systems Same 3.5 6.5.2
- Containment Spray System
- Containment Fan CoolerSystem Reactor Containment Fan 3.5 9.4.8.1, 6.2.2 Cooler Subsystem Containment Normal Ventilation Systems Containment Ventilation System X
9.4.8 Combustible Gas Contml Systems flydrogen Reconbiner System, X
6.2.5
' Ilydrogen Monitoring System, Ilydrogen Mixing System.
u Post-LOCA Purge System Reactor and Reactivity Control Systems Reactor Core Same X
4.0 Control Rod System.
Control Rod Ihive System X
4.6
- ' Boration Systems See CVCS, above Instrumentation. &. Control' (I&C) Systems Reactor Protection System (RPS)
ReactorTrip System 3.6 7.2 Engineered Safety Feature Actuation Same 3.6 '
'7.3 System (ESFAS) g Remote Shutdown System -
Various Remote Shutdown Panels X
7.4 e
i Table 3-1. : Summary of Braidwood Systems Covered in this Report (Continued)
Generic Plant-Specific Report FSAR Section System Name System Name Section Reference i
Instrumentation &. Control (I&C) Systems (continued) f Other I&C Systems Various systems X
7.5,7.6.7.7 Support Systems Class IE Electric Power System Same 3.7 8.1,8.3 4
Non-Class IE Electric Power System
.Same 3.7 8.2,8.3
'I Diesel Generator Anxiliary Systems Same 3.7 9.5.4 thru 9.5.8 Component Cooling Water (CCW)
Component Cooling System 3.8 9.2.2 System Service Water System (SWS).
L v.
Essential Service Water System, 3.9 9.2.1 Non-essential Service Water System.
-- Other Cooling Water Systems Plant Chilled Water System X
9.2.7' Fire Protection Systems Same X'
9.5.1.
- - Room Heating, Ventilating, and Air-Same-X 9.4 Conditioning (IIVAC) Systems i
Instrument and Service Air Systems Cocpressed Air Systems X-9.3.1 i
- - Refueling and Spent Fuel Systems'
. Spent Fuel Pit Cooling and Cleanup X 9.1.3, 9.1.4 i
System, Fuel Handling System Radioactive Waste Systems Radioactive Waste Management X
11 p
' Systems.
.c I
- -Radiation Protection Systems Same X
12
s.
_,_._-_.__..m__.....___.
.i i
4
'I t
f 3
CilARGING PUMP 1A i
Oil AND CUBICI E COOLER
-[
- u J
.. p r
3 DIESEL 1 A 11X
(
J
- i l
f AFWS FUMP 1A '
Olt COOL EH t'
J F
ESWS A a
r 3
L J
(
j
- t l
BRAIDWOOD LAKE /
r 3
a
'i COOLING POND 1
(
r 3
p ESWS B as
/
(
3 L
.J
./
k J
f AFWS PUMP 1B '
OIL COOLER v
J 4
4 i
i DIESEL 1B HX t
J r I r
3 CHARGING PUMP 1B Olt AND CUBICLE COOLER
-y
(
4,-
l
/
AFWS = Auxiriary FeedwaterSystem CCS = Component Cooling System g
r C
ESWS' = Essennal Sennce Water System Figure 3-1. Cooling Water Systems Functional Diagram for Braidwood 1 and 2
'I
.I l
'l
.)
_ _ __.~.
l 2
i Braidwood 1 & 2 3.1 REACTOR COOLANT SYSTEM (RCS) 3.1.1 System Function The RCS transfers heat from the reactor core to the econdary coolant system via the steam generators. The RCS pressure boundary also establishes a boundary against i
the uncontrolled release of radioactive material from the reactor core and primary coolant.
3.1.2 Svstem Definition l
The RCS includes: (a) the reactor vessel. ('o) reactor coolant loops, (c) reactor-coolant pumps, (d) the primary side of the team generators, (c) pressurizer, and (f) 4 connected piping out to a suitable isolatien valve boundary. An isometric drawing of a 4 -
loop Westinghouse RCS is shown in Figure 3.1-1. A simplified diagram of the RCS and important system interfaces is shown in Figure 3.1-2; A summary of data on selected RCS components is presented in Table 3.1-1.
3.1.3 Sv< tem Ooeration Durinc power operation, circulation in the RCS is maintained by one reactor coolant pump in e'ach of the four reactor coolant loops. RCS pressure is mairitained within a prescribed band by the combined action of pressurizer heaters and pressurizer spray.
RCS coolant inventory is measured by pressurizer water level which is maintained withm a -
prescribed hand by the chemical and volume control system (charging system).
At power, core heat is transferred to secondary coolant (feedwater) in the steam-generators. The heat transfer path to the ultimate heat sink is completed by the main steam.
and power conversion system and the circulating water system.
g Following a transient or small LOCA (if RCS inventory is maintained), reactor core heat is still transferred to secondary coolant in the steam generators. Flow in the RCS 4
o is maintained by the reactor coolant pumps or by natural circulation, The heat transfer pa.th j
to the ultimate heat sink can be established by using the secondary steam relief system (see Section 3.2) to vent main steam to atmosphere when the power conversion and circulating -
water systems are not available. If reactor core heat removal by this alternate path is not.
adequate, the RCS pressure will increase and a heat balance will be established in the RCS
]
by venting steam or reactor coolant to the containment through the pressurizer relief valves, There are two power-operated relief valves and three safety valves on the pressurizer. A j
continued inability to establish adequate heat transfer to the steam generators will result in a l
LOCA like condition (i.e., continumg loss of reactor coolant through the pressurizer relief l
valves). -Repeated _ cycling of these relief valves has resulted in valve failure (i.e., relief valve stuck open).
i Following a large LOCA, reactor core heat is dumped to the containment as
containment can act as a heat sink: however, the containment cooling systems must operate e
in order to complete a heat transfer path to the ultimate heat sink (see Section 3.5).
t i
t
\\
i 1
7 1/89 rv v 1.
,,-.. w w r -.,,w r w-,
e v
-e..
.w---
a v
.-e--,
,,1.r,m c
- Braidwood 1 & 2 3.1.4 Svctem Success Criteria.
I The RCS success critena can be described in terms of LOCA and transient mitigation, as follows:
An unmitigatible LOCA is not initiated.
If a mitigatible LOCA is initiated, then LOCA mitigating systems are successful.
If a transient is initiated, then either:
RCS integrity is maintained and transient mitigating systems are successful, or RCS integrity is not maintained, leading to a LOCA-like condition'-(i.e.
stuck open safety or relief valve, reactor coolant pump seal failure), and LOCA mitigating systems are successful.
3.1.5 Comoonent Information A. RCS 3
- 1. Volume: 12,257 ft, including pressurizer
- 2. Normal operating pressure: 2250 psia B. Pressurizer
- 1. Volume: 1800 ft3 C. Safety Valves (3) 1, Set pressure: 2485 psig
- 2. Relief capacity:.420,000lb/hreach
! \\
D. Power Operated Relief Valves (2)
- 1. Set pressure: 2335 psig -
- 2. Relief capacity: 210,000lb/hreach E. Steam Generators _
- 1. Type: Vertical shell and U Tube
- 2. hiodel: Westinghouse 51 Series y
F. Pressurizer Heaters
- 1. Capacity: 1800 kW--
3.1.6 Suonort Svstems and-Interfaces A. Motive Power
- 1. The p' ressurizer heaters are Class 1E AC loads that can be supplied from the i standby diesel generators as described in Section 3.7.
- 2. The reactor coolant pumps are supplied from Non. Class IE-switchgear.
B. Reactor Coolant Pump SealInjection Water System The chemical and volume control system supplies seal water to cool the reactor coolant pump shaft seals and to maintain a controlled inleakage of seal water :
. into the RCS. _ Loss of seal water flow may result in RCS leakage through thel l
- pump shaft seals which will resemble a small LOCA;
\\
4 8-1/89'
--.v-v.ir9 r
v.,,.,.,y,
,.,4
,,w.._
y y
,.y-%,y-n, w. -,, n o r eg %ge r
,,, p-y, we. w p e v. w -
c-r l
V l
GENE ATOR PY m
v v
0 LA N T Q
PUMP A
A V
M qB V
g.
E of ll I
I k.
L PRES $URl2ER REACTOR 0
0 9
1/89 j
c
r~N It-)
i 5
i 025
.I I. Ok"k i
1,
-lh i
!! ( r },
ll r
ir 0-il
(
&hi o
o 33 w
T3
'- w j!
- i. l fd. !
IE e
i ! fd5 e
e u
ue s.
Okff.hjf{O$i 4l I
l L_._-q g
Oli q) _
i' 1
{,;).de._gl.
(
]
h g;{}m{
o p
g g
O o
/3 5
V)
@1^
E
\\
'i l i
'~
E jj olv-E E
+
8 4
1%
i
/
]
I
} ---
lv ll1-
/
isi 3
.L 3,
Oi!
til
(
h fjOEiD O-l#
OI! fhl ffl E! *gv O$a e1cp j
4 I
!!!!'i; e
tf! r4g
-Q l tf1 ff!
e
- DSU Li 3
l' r
IE i.!
$E 0-Il II gjg IE 85 u
ns se v
r 6*
l e
[
i T
! O[*
O q.-)
t t
I
~
I 10 1/89
_ _ - - - - - - - - - - - - - - - ^ - - - " ' '
~
i Iok'I l 0l j
I tl I
l i
+ij f si th Di ts Ia
- l
(
c
+Ti eji g
o (I'm (La d
ff! til tf.!rf.i j ili!
!q i
'c!
o
- t Ir. 09',
3 Of; 4i Eiolf.
j!
-4g g[
((_
g a
f I
Y ffI d "I
l l#
-f I
l#
\\t
/
i y(-
- n 2
V i
e!
E ll P
[
N I4 l
14}w dh l
5 fggog!,,
D-Ok!'
tNI' C
f OX, a 1 fil 1o71 y
0 o 1 o<'l n
la W
W 4.
'?
-a y
as V
,T f
&Jj&{j-Q]
I j!
- I!
't ! ff!;
W 1
- 8 E
l Sk!
f!
- i
'g p
&{l
~~
.O l' tL l'4!
i 1
11 1/x9 1
....... ~. -.
i i
t k
Table 3.1-1.
Braidwood Unit 1 Reactor Coolant System Data Summary
(
for Selected Components f
f COMPONENT ID COMP.
LOCATION POWER SOURCE VOLT A GE POWER SOURCE EMEHG.
TYPE t OC ATION t.OAD GRP
[
HC-455A TJV TO l
RC-456 -
fJV RC 4
HC-8000A.
MOV FC MCC-131X2 480 414PEfJRM AC/A HC-80008 MOV FC MCC-132X2 480 420PENRM AC/B i
i HC-8001A MOV FC
\\
HC-80018 -
MOV 10
~
HC-8001C MOV FO HC-8001 D MOV HC HC-8002A.-
MOV RC 1'
HC-80028 MOV FC i-R RC-8002C uOy 50 HC-8002D MOV FC HC-8701 A -
MOV-RC-MCC-131X2 -
480 414PENG A AC/A i
i RC-87018 MOV FC ;
MCC-132X2 '
480 42SPENHM AC/B
(
HC-8702A MOV TO MCC-131X2 480 414PENAM AC/A E
t j-HC-87028 MOV:
RC MCC-132X2 480 426PENRM AC/B f
i RV FC t
i RCS-VESSEL E
j
'f i
i '
6 f
i.
- -g 4
t-I
\\
t
.{
t
.q p
=
. ~.
Braidwood 1 & 2 3.2 AUXILI ARY I EEDWATER (AFW) SYSTEh! AND SECONDARY d
STEASI REl.!EF (SSR) SYSTESI 3.2.1 Sutem functinn The AFW system provides a source of feedwater to the steam generators to remove heat from the reactor coolant system (RCS) when: (a) the main feedwater system is not available, and (b) RCS nessure is too high to permit heat removal by the resid'ual heat removal (RHR) system. "Jhe SSR system provides a steam vent path from the steam generators to the atmosphe 1, thereby completing the heat transfer path to an bitimate heat smk when the main steam a"d power conversion systems are not available. Together, the AFW and SSR systems constitute an open loop fluid system that provides for heat transfer from the RCS following transients :uid small break LOCAs.
3.2.2 Sutem Definition The AFW system consists of one motor-driven pump and one diesel driven pumr. The normal water sources for the pumps is the condensate storage tank. An alternate source of water is the Essential Suvice Water system. Either pump can supply all few steam cenerators. Interfacing with the ARV system is the startup feedwater system, whica consists of onc s:artup feedwater pump supplied from the main condenser hotwell cia the main condensate and feed booster pumps.
The SSi< system includes five safety valves and one power-operated pressure control valve or each of the four main steam lines.
Simplified drawings of the AFW and SSR systems are shown in Figures 3.2-1 and 3.2 2. The startup feedwater system is shown in Fl;ure 3.2 3, A summary of data on selected AFW system components is presented in Ta ale 3.21.
g 3.2.3 Snte m O ner.u.lle Dunng normal operation the AFW system is in standby, and is automatically actuated on either a low-low level in any steam ge nerator, a safety injection signal, or a loss of power to the reactor coolant pumps. The syst :m can also be manually started from the control room. Ordinarily, the AFW system is required to operate for about 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to cool the unit down to 350'F, below which temperature the low pressure residual heat r:moval system 0;3erates.
Both ARY pumps are 1165 brake horsepower units. The diesel driven ARY pump is capable of providing 840 ppm at 3350 feet head, which is nearly twice the capacity required for system success. This pump is capable of supplying its own cooling and lubncation independently of AC ower, but when AC power is available backup pumis are provided for oil pressure, water acket cooling, and room air cooling. The motor c riven ARY pump is capable of provic ing 890 gpm at 3350 feet of head, it requires essential service water for cooling (Ref.1).
The primary suction source is the condensate storage tank. Redundant flow paths becin at the CST and meet at a header which supplies both pumps. No single valve can bloik the flow path, in the event of low suction pressure, there is automatic switchover to service water at the ARV pump water source.
Flr n each AFW pump goes to all four steam generators through independen'
..... Flow is re which fail ope,n on loss of air. gulated by eight manually controlled air operated valves 3.2.4 Sntem Roccess Crlierla For the decay heat removal function to be successful both the ARV system and b
the SSR system must operate successfully. The ARY success criteria are the following (Ref. I and 2):
(
13 1/89
Braidwood 1 & 2 Either AFW ump can provide adequate Dow.
?
Water must 3e provided from the Condensate Storage Tank or Essential Service Water System Delivery require'ments are 160 gpm to each of three steam generators or 240 ppm to each of two steam generators. This delivery must commence prior to the steam generators boiling dry (within 20 to 30 minutes)
The SSR system must operate to complete the heat transfer path to the environment. The number of safety valves which must open for the decay heat removal function is not known.
The startup feedwater system may be available as an attemate source of steam generator makeup if offsite power is available and the suction path from the main condenser hotu ell via the condensate and feed booster pumps is functional.
3.2.5 Cmnannent Information A. Motor driven AISV pump 1 A
- 1. Rated flow: 890 gpm @ 3350 ft. head (1452 psid)
- 2. Rated capacity: 175% (Ref.1)
.L Type: Cenuilupal IL Diesel driven AFW pump
- 1. Rated Dow: 840 gpm @ 3350 ft head (1452 psid)
- 2. Rated capacity: 1859 (Ref.1)
- 3. Tvpe: Centrifugal O
~
G C. Startup Feedwater Pump
- 1. Rated flow: unknown
- 2. Type: Centrifugal D. Condensate stoiage tank
- 1. Capacity: Unkn
- 2. Design Dressure:ownAtmospheric E. Secondary steam relief valves
- 1. Five safety valves per main steam line
- 2. One power-operated pressure control valve per main steam line 3.2.6 Sunonrt Svstems and Interfaces A. Control Signals
- 1. Automatic The AFW pumps are automatically actuated based on the a.
following signals:
low-low water level in any one steam generator safety injection signal loss of offsite power and station normal auxiliary power (blackout),
(
- b. The water source for the AFW pumps is automatically switched to the Essential Service Water system on low pump suction pressure, w
14 1/89
Braidwood 1 & 2 1
- c. The AFW pumps are automatically tripped on low suction pressure, j
- 2. Remote manual The AFW system can be actuated by remote manual means from the main control room and from the remote shutdown control panel.
B. Motive power
- 1. The AFW motor-driven pump and motor operated valves are Class IE AC loads that can be supplied from the standby diesel generators as described in Section 3.7. Redundant loads are supplied from separate load goups.
- 2. The AFW diesel driven pump is supplied with fuel from a day tank, C. Other
- 1. Cooling for the motor driven pump is provided by the essential service water system (see Section 3.9). Cooling for the diesel driven punip is arovided locally.
2.
' ump cubicle coolers are cooled by essential service water (see Section
- 3. 9 ).
- 3. Each AFW pump has an auxiliary tube oil pump that provides lubrication prior to starting the pump. For a normal pump startup, the pump will start when an oil pressure interlock is satisfied, Under emergency start condition.prelubrication is not required for AFW pump start tref. 2h 3.2.7 Section 3.2 References
- 1. Youngb! nod, R. and Papazaglou,I.A., " Review of the Byron /Braidwood Units 1 and 2 Auxiliary Feedwater System Reliability Analysis, NUREG/CR.3096, BNL NUREG 51633, Brookhaven National Laboratory, November 1983.
- 2. Byron /Braidwood Final Safety Analysis Report, Section 10.4.9.
l 15 1/89
-my+
---m-ey-
,yg3
--7y
.,--w+-----ie-----.a y
g y
-w--=-vr i 9 ey r-+w7 y-a-7---
1,
. ~ "
a.
g w.
7 m
~'
m, w.
l q
o w
e
?.
m jh m.,
s ha w
w oM
~
Fc s -
C o-y :.
5 pl nA wg wQl o,
,h c.
'}
1
,g4lnn
.pI l ya e
m y,
(l s
vm vS g
C 9
G s
(
e c
+.:
- r: s.
,%~*_N-
,y N=
_N m
m
_r
4
,e.
e r
t
,qs
=
s n
,n y
, e
_n
>N **
, a 3
n 4N-
_u S
~
w
.w 1
r
,. n t
,.si
, P"
.n m,m e
,i.
- n. + "
'p" s
. i '
t nw a
'n'
.es w
+
. t
,. t
,T
'u 54 r.
r Y
d m
5 ee F
Q.
,N'"
+N "
- 5 '
y J
R_
+4.._N-3, a
=
r a
i l
i x
J 4,
S*
0' 3
r u
h, g *'
$a 0~a' h
h,., oM' A
C v
3 D
a m
1
' d;. *o 9 "
t 0
3 3
sa $>n t 8e Ohs o
i
'oywreD-C n
o F
r co o
o C
U doo w
d ia r
0 B
o[g. o o5 "
$a 9Ne.
0a e
y,-
d t
a 0
3 3
1
{
i E
)
2
- a 9
%e c
iN" 6'
s 3
o
-J t
r A
e rU1 P
mm u
~
g 4
i r
et F
Qn,,.
_e
~s r
.c
, Q.
,g,,oq,,
2 i
mm Qu.,
r e
Q,, o y,,,
o n
,en s
&n, W
a g
m m
w i
m
=
0:
ey 4
e A
o e
a e
Ol!
ll.
E2 SNeOl N
ti OI; j
s tk iM
'tZe Ol!
i
~
a I
u
=
A C
0 i
f 323
\\
d
- C
~
~pqm
!!L 14 w i
17 1/80 L
f) h I.
]
-,, }
V tIl tii l
t$j t$i tI! 121 t$itIl t l t3l d.
t$! 12l 4
4
-4 II 6j El II $l 61 II %l %i II 6l l
l l
l
_1
- lia[
g
.r
- rel Ili 4,
rs i
i e
OE!
12 tZ t
s l
l G
8t 6t Et t
4 4
4
?
t2i 11i
?
w' e
65
!!I el!!
I
\\
n
.T3 V
j.
- l I'!!
l lri 8
FR i
m iklkl5.1 0
t.It[t4It.I N
,Il E
I i
k! 5!
! 5!
lt ! ri t21 r!
lI liii
(~N, hhi E
i i
m
.'V i
! A r
18 1/89
Table 3.2-1.
Braidwood Unit 1 Auxiliary Feedwater System Data Summary for Selected Components COMPONENT ' ID COMP.
LOCATION POWER SOtfRCE VOLTAGE POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP AFW-13A MOV-AFWPPINL MCC-131X1 480 364PENRM AC/A AFW-13B MOV AFWPPINL MCC-131X1 480 364PENRM AC/A AFW-13C MOV AFWPPINL MCC-131X1 460 364PENRM AC/A AFW-13D MOV AFWPPINL MCC-131X1 480 364PENRM AC/A AFW-13E MOV AFWPPINL MCC-132X4 400 426PENRM AC/B AFW 13F MOV.
AFWPPINL MCC-132X4 480 426PENRFA ACIB AFW-13G -
MOV AFWPPINL MCC-132X4 480 426PENRM AC/B
(.
AFW-13H MOV AFWPPTNL MCC-132X4 480 426PENRM AC/B AFW-17A MOV 383AB MCC-131X3 480 383AB AC/A AFW-17B MOV DDAFW MCC-132X3 480 383AB AC/B 2
AFW-6A MOV 383AB MCC-131X3 480 383AB AC/A AFW-68 MOV-DDAFW MCC-132X3 480 383AB AC/B AFW-CST TANK CST-AFW-P1 A MOP 383AB BUS-141 4160 ESF11-AC/A AFW-PI B DDP DDAFW SG-1 A.
SG HC l
l SG-1B -
[
SG-1D SG RC.
I t
I e
i l
f M
o-l i
I i'
r I
t
Braidwood 1 & 2 3.3 EMERGENCY CORE COOLING SYSTEM (ECCS) 3.3.1 Sntem Function The ECCS is an integrated set of subsystems that perforn emergency coolant injection and recirculation functions to maintain reactor core coolant inventory and adequate decay heat removal following a LOCA. The coolant injection function is performed dunng a relatively short tenn pened after LOCA initiation, followed by realignment to a recirculation mode of operation to maintain long-tenn, post LOCA core cooling Ileat from the reactor core is transferred to the containment. The heat transfer path to the ultimate heat sink is completed by the containment cooling systems (see Section 3.5).
3.3.2 Sutem Definition
'I he emergency coolant injection (ECI) function is perfonned by the following ECCS subsystems:
Passive cold leg accumulators Charging system (CVCS)
Safety injection (SI) system Residual heat removal (RllR) system The charpmg function of the CVCS is described in Section 3.4 The SI system provides high pressure coolant injection capability. The RilR pumps perform the low pressure injection function. The Refueling Water $torage Tank (RWST)is the water source for both the high and low pressure in,)ection systems. Both systems injtet coolant into all four RCS cold legs. The Si system can also inject into all four hot legs, w hile the RilR system can inject into two hot legs.
After the injection phase is completed, recirculation (ECR)is performed by the
\\
RIIR pum cold legs.ps drawing suction from the containment sump and discharging into exchangers. The RIIR pumps can also deliver water to the suction of the Si and charging pumps durine recireulauon.
Simplified drawings of the safety injection system are shown in Figures 3.31 and 3.3 2.
The residual heat removal system is shown in Figures 3.3 3 and 3.3 4.
Interfaces between the accumulators, the ECCS injection and recirculation subsystems, and the RCS are shown in Section 3.1. A summary of data on selected ECCS components is presented in Table 3.31, 3.3.3 Sntem Ooeration Dunng normal operation, the ECCS is in standby. Following a LOCA, the four cold leg injection accumulators (one for each loop) se, ply borated water to the RCS as soon as RCS pressure drops below accumulator pressure (approximately 585 psig). A safety injection signal (SIS) automatically starts the two charging pumps, the two safety l
injection pumps, and the two RIIR pumps, and aligns the charging pumps for injection.
l The charging pumps inject through the boron injection tank (BIT)into the four RCS cold legs. The Sl and RHR pumps can inject into either the cold legs or the hot legs. All pumps are aligned to take suction on the RWST.
For small breaks, operator action can be taken to augment the RCS depressurization by utilizing the secondary steam dump capability and the auxiliary feedwater (AFW) system (i.e., depressurization due to rapid heat transfer from the RCS).
When the RWST water level drops to a prescribed low level setpoint, the RilR pumps are realigned to draw a suction from the containment sump and deliver water to the RCS cold legs, if depressurization of the RCS' proceeds slowly, high pressure recirculation can be accomplished by manually aligning the discharge of the RiiR pumps to 20 1/89
Braidwood 1 & 2 the su; tion of the charging and SI pumps. Approximately 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> after the accident, hot leg recirculation is initiated to ensure tennination of boiling and preclude excessive boron i
concentration in the reactor vessel.
3,3,4 h sf em Euccess Criterin LOCA mitigation requires that both the emergency coolant injection and emergency coolant recirculation functions be accomplished. The success criteria for a large LOCA are the following (Ref.1):
3 of 4 accumulators provide makeup as RCS pressure drops below tank pressure.
One safety injection pump injects its flow to the RCS, One RilR pump delivers its Dow to the RCS, One centrifugal charging pump injects from the RWST into the RCS, and 1
Coolant recirculation occurs on a low level signal from the RWST or by remote manual means.
The recirculation success criteria are not clearly defined in the FSAR.
Success Criteria for a small LOCA is not clearly delined in the FS AR, however it is noted that (Ref. 2):
The Safety injection pump si atoff head is less than RCS normal operating
,ressure, therefore, a sma:1 LOCA must be of sufficient size to cause some RCS depressurization, or the RCS must be depressurized by other means if the safety injection pumps are to provide makeup. Options for depressurizing the RCS may include:
Opening power operated relief valves on the pressurizer (two PORVs are available, see Section 3,1)
RCS cooldown (i.e. using the auxiliary feedwater system, see Section 3.2)
The combined capacity of the two centrifugal charging pumps is 300 gpm (i.e.
150 ppm each) @ 5,800 ft. head. One charging pump can maintain normal operating 3ressure (2,250 psia) following a 0.375" equivalent diameter mpture (127 gpm eak/ charging rate).
3,3.5 Comoonent Information A. Safety injection (high pressure) pumps l A and IB 1, Rated Dow: 400 rpm @ 2540 ft head (1101 psid)
- 2. Rated capacity: 1007c
- 3. Shutoff head: 3922 ft head (1700 psig)
- 4. Type: horizontalcentrifugal B. Residual heat removal (low pressure) pumps l A and 1B
- 1. Rated flow: 3000 ppm @ 375 ft head (163 psid)-
- 2. Rated capacity: 1007c
- 3. Shutoff head: 450 ft head (195 psid)
- 4. Type: verticalcentrifugal 1
21 1/89
i l
Braidwood I & 2 O
C. Cold leg injection accumulators (4)
- 1. Accumulator volume: 1350 ft3
- 2. Niinimum water volume: 935 ft3
- 3. Nomial operating picssure: 585 psig
- 4. Nominal boric acid concentration: 2000 ppm D. Refueling water storage tank
- 1. Capacity: 458,000 gallons
- 2. Design pressure: Atmospheric
- 3. Niinimum toron concentration.1900 ppm
- 4. hiinimum water volume: 420,000 gallons E. RifR heat exchangers l A and ID 6
- 1. Design duty: 28.95 x 10 Bru/hr
- 2. Type: Vertical, shell and U tube 3.3.6 Sunnort Systems and Interfaces 1
A. Control signals
- a. Low pressurizer pressure l
- b. High containment pressure
- c. Low steam line pressure
- d. hianualactuation
(
The SIS automatically initiates the following actions:
starts the diesel generators starts the charging, SI, and RHR pumps aligns the chargmg pumps for injection Switchover to the recirculation mode occurs automatically on low level in the RWST.
i
- 2. Remote manual An SIS signal can be initiated by remote manual means from the main control room. The transition from the injection to the recirculation phase of ECCS operation can be initiated by remote manual means, hianual action is required to realign the charging and safety injection pumps for recirculation.
B. hiotive Power
Section 3.7.
I
/
k 22 1/89-
l i
Draidwood I & 2 C. Cier
- 1. Each Si and charging pump is ccoled by the Essential Service Water system (see Section 3.9).
- 2. The RilR pumps and heat exchangers are cooled by the Component Cooling Water system (see Section 3.8).
- 3. Lubrication and ventilation are provided locally for the SI, RilR and earging pumps and motors.
1 3.3.7 Mut 3.3 References i
1, Byron /Braidwood Final Safety Analysis Report Section 6.3.2.
- 2. Byron /Braidwood Final Safety Analysis Report, Section 6.3.3.
I h
s l
l 4
i I
23 1,8, I
4
-,--ee e ne g y
,y,--w-4,w w eve -, v e,.,--, w vy ~
,,,f e y,r.w ww ww v ve cew __ _. _. _ -, _. _.
re e
_ _ # mw er ew+.em;
em ie B
t;
(., )
p1 n
te 9
a se ss d
d d
d i
i i
i i
i; 58 i:
n
- s ti ft Si t$i tkj IlP
- lP llP llDtki tki t$i thi tki t%l ffi f! ff! tXi tf! tXI ffi tZi tXV th
!a!
X!
Xi 2s X1!
s!
Xi
!E XI XI
!i S
Zi
!E n
as g
m 8=
8g oli OR' oII a
e a
2
>0
-M m
O O
M t2I tXl E
V y2 E
L O
{
i e
I.
i le m
n s
Il I!
?!
OV! %!
4 of.i ofi.
S, t"D LE I
s g
II E
P if
=
en en se li I
el 9 71 Re Re 1
et b
bO O
Oi C
/
\\
I
!vl
?!
IE T
p er ER E"
24 1/89
.--*,a__4_a
__AA___4,_a-.44M Am_aA.,_m,_u,a5.6,A,a
__2_
m._4__,_,_.4m,,._,4w,,u.
p.
,,4,p-.a.
.a sag,u,.
__a e,,_.,am 4_
a m.,_._,_.m,w
. 4 m2,
,4
..,am,,
l e;
t ce;
- s o
eo n
se 55 kb kh hb t
t i
i Y
Y j
l/
pf lP si.t E
It 4
3 t21 tzt l
l l
l til t7d 9
a XI !!X!Ei ll El !.!
El
.ls IIllXIXIll l
a a
.Em I
h a
i i
A g
1 B
6 1
ta.
til a
E Y.
E b
b.i i
i oli oI! ov,e
~l oKt T
pa a
i i
p m
.?
E co c4 en 6
T DE O{h l
lI
~
O g}
o j
g e
j OX OX O
g a!: p-p o
e p d
o i
IE i
_n 25 1/69 i
I.
i;
/]
l:
[E d
i tk ik ik ik V
t3 t2 t
t T
p p
fi si l
l l
lffl thi tZj ffl tXI ffj tXI fff tXI ffl tki ffi tIl thi
- 1
1 ol OXl 0 11 1
s g
ti
?!
=
E
'c
[,t.,
I!
JE v'4.!
t i
s
[
[
oil a
i e
a E
cI!
- g p-n:
2 2
02:
om i
O 1- :
3
(
j eIt o]:t
. m 3:
e v
- s
... h J
4 i
.e 4h y
~J L. J i
E yin y1 y
y i
It r
S s
s 2
Y q.
9 g
oli oK.I oX.I ob C
4 i
i j oli e
o):6 s
a OI!
--o]
l;e sj
,v.
i.
cI. !!q!!*i g!i 1
OI!
a li I
e.l; i.f in n
n u
(
)
I OE! of'i of! ok! of!
g l
J J
v j'if U
26 1/89
if is li li it is at a
f f
i fl, tp' t$
el ti lj' l$l1t$1 Ol l.
It' il' l
lt tsit$.1ttit$.1 trit $.1tsit$.1tkit$.1tAlt$.1 g
1 11 11 11 11 11 1
=
9 o$l oil oil
]
b I
1
((
d sj 5
3 I
F t
,1 l
1 oil i
i l
-a u
--.s
- f Ig
~~'$
8*
g d_
g 0i*;,1 OEt 8
t e
o.);g.
I.
I g
r oli a
a g
e
+
+
x f
f I
3
[
l i
e
")l l k
W oI I o o
))(I
~
Qj'
- ff.
2 o
OIl-
[-
g
(
I c
ol; >l l*
I..,Ioll!
l*1
,r 13 I
l' l
j:)
en l
r!
Al O
U ob oZi o$i oI! oI!
jg li i
27 1/89
ir j
.[f I
f[
h j'
t P
l
.R y
G G r
R a
ED A A
A B
B A
B A
B B
A B
A B
A A
B B
A A
B B A
B m
A I
/
/
/
/
/
/
/
/
/
/
e
/
i
/
/
/
/
I
/
I f A G C
C C
C C
C C C C
C C C C
C C
C C C C C C C C m
EO A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
A A
L uS E
C a
R N U
t O
a OI D
ST M
M M
M M
M M M
M M M M M M M M
M M A R R
R R
R R
R R
R R
R R
R R
R R
R R
m RC N
N N
N N
N N
N N
N N
N N
N N
N N
N 1
2 E
E E
E B
E E
E E
E E
E E
E B
1 2
EO E
E E
E E
e WL P P
P P
P P
P P
P A
P P
P P
P P
P P
P A
1 1
1 1
F F
F F
ts O
4 4
4 6
6 4
6 6
4 4
4 6
4 4
6 6
4 4
6 4
6 6
6 2
2 S
S 6
2 2
6 6
5 2
6 6
2 2
6 6
2 6
S S
y P
3 3
3 4
4 E
E 3
4 4
3 3
3 4
3 3
4 4
3 3
4 3
E E
S E
g G
n A
i T
0 0
0 0
los L
0 0
0 0
0 6
6 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
6 6
Ot O
3 8
0 8
8 1
1 8
8 8
8 3
8 8
8 8
8 8
8 8
8 8
1 1
Cn V
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
e E
e n C
r O R
Op U
A A
A A
Cm O
1 1
1 4
4 1
4 4
1 1
1 4
1 1
4 4
1 1
4 1
S X
X X
X X
X X
X X
X X
X X
X X
X X
X X
X o
1 1
1 2
2 1
2 1
2 2
1 2
1 2
1 1
2 2
1 1
2 2
1 2
y s
cC R
3 3
3 3
3 4
4 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
4 4
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
n E
ed W
C C
C C
C S
S C C C
C C C C C C C C C C C C S
S C
C C
C C
U U
C C
C C
C C
C C
C C
C C
C C
C U
U ge O
M M M M M
B B
M M M
M M M
M M M M M M M M
M B
B t
r P
e ce ml Ee t
S t
O M
M M
M M
M M
M M
M M M M M f
I r
T R
R R
R R
R R
R R
R R
R R
R t o A
if N
N N
N N
A B
N N
N N
N N
N N
N n
C X
X E
E E
E E
H A
B E
E E
E E
E E
E E
i U
O P
P P
P P
D R
R R
P P
P P
P P
P P
P L
4 4
4 4
4 i
4 4
B I
A A
I H
H H
6 6
I B
I A
4 4
4 4
4 4
4 A
B A
I B
6 6
6 6
G D
6 6
6 6
6 6
6 d
I R
R R
3 3
S S
S S
3 3
3 3
3 3
3 S
S S
S S
I I
I 3
3 3
3 3
f O
O w
PE d
MP V V
V V
V P
P V
V V
V V
V V
V V
V V
V V
V V
V P
P OY O O
O O O
X X
D D
O O
O O O O O O O O O O O
O O
O D
D ia C T M M
M M M H
H M M M M M M M M M M M M M M M M M M M M r
B D
I 1
T 3
it 3
E l
A A
A 8
8 t
e O
4 6
6 6
6 A
B A
B 8
A B
A 8
A A
8 B
A B
P 0
1 1
1 1
1 1
l A
B 2
2 4
6 7
7 1
1 1
1 1
1 5
3 3
4 b
M 8
7 7
7 7
X X
1 0
0 0
0 0
0 1
1 2
2 2
2 3
2 2
2 A
B a
O 8
8 8
8 8
H H
P P
8 8
8 8
8 8
8 8
8 8
8 8
8 9
9 9
1 1
T C
V H
H H
H H
H H
I S
S S
S S
S S
S S
S S
S S
S S
S S
l 8
8 8
4 8
B 4 8
8 8
8 8
8 8
8 8
P P
u C
R H
R H
R R
R S
I I
1 I
I 1
I I
I I
I I
I I
I I
I f
,z gC L
' i ti
d
/"
(J-
)
1 s
Table 3.3-1.
Braidwood Urit 1 Emergency Core Cooling System Data Summary for Selected Components (Continued) l COfA PONENT ID Co nE P.
LOCATION POWCR SOURCE VOLTAGE POWER SOURCE E tt E R G.
TYPE toc ATION LOAD Gnr SI RWSI TATJK HWST SUMP-A SUMP FC SUMPB SUMP FC i
b t
E l
m c
Braidwood 1 & 2 3.4 Cil ARGING SYSTEM (CYCS) 3.4.1 Sistem Fung 1[nn The charging system is part of the Chemica' and Volume Control System (CYCS L The CYCS is responsible for maintaining the proper water inventory in the Reactor Coolant System and maintaining water purity hnd the proper concentration of neutron absorbing and corrosion inhibiting chemicals in the reactor coolant. The makeup function of the CYCS is assumed to be required to maintain the pl ant in a long term (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) bot shutdown condition, The charging pumps also operate as part of the ECCS in the event of a LOCA.
3.4.2 System Definition The CYCS provides a means forinjection of control poison in the form of boric acid solution, chemical additions for corrosion control, and reactor coolant cleanup and degasification. This system also adds makeup water to the RCS, reprocesses water that is letdown from the RCS, provides seal water injection to the reactor coolant pump seals, and perfonns an emergency core cooling function.
The CVCS consists of several subsystems: ti e charging, letdown, and seal water system, the reactor coolant purification and chemistry control system, the reactor makeup control system, and the boron thermal regeneration systein. The functions of the CYCS are perfomied by the following components the charging pumps,(two centrifugal, one positive displacement), boric acid transfer pumps, volume control thnk, boric acid tanks, and various heat exchangers and deminerahzers.
Simplified drawings of the CVCS, focusin ; on the charging portion of the system, are shown in Figutes 3.41 and 3,4 2 Note that tie normal chargmg paths to the reactor coolant loops did not appear on the available drawings, so the arrangement for the Byron O
plant was assumed in these figures. A summary of data on selec;cd charging system components is presented in Table 3.41.
3,4.3 Sntem Oneration Dunng normal plant operation, one charging pum) is running with its suction aligned to the Volume Control Tank (VCT). The letdown f ow from a RCS cold leg is-cooled in the shell side of the regenerative heat exchanger, then directed to the VCT. The reactor makeup control system maintains the desired inventory in the VCT. The bulk of the.
charging flow is pumped back to the RCS through the tube side of the regenerative heat exchanger via two charging lines. Portions of the charging flow are directed to the reactor coolant pumps through a seal water injection filter, and to pressurizer spray.
The centrifugal charging pumps also provide high head injection as part of the ECCS (see Section 3.3). During a LOCA the CVCS is iso,ated except for the centrifugal charging p% ater Storage Tank (RWST) and inject via the Boron Injectio umps and the piping in the safety injection path. The pumps take suction on the Refueling cold legs.
The reciprocating (positive displacement) charging pump is also used to perfonn hydrostatic tests which verify the integrity of the RCS. The pump can pressurize the RCS to the maximum design test pressure.
3.4.4 Success Criteria For post transient makeup to the RCS the following charging system success criteria is assumed:
A long term water source must be available to the charging pumps, p]
One of three charging pumps is available.
i A makeup path to the RCS is available.
30 1/89 i
....-.s
Braidwood 1 & 2 For LOCA success criteria, see Section 3.3.4.
3.4.5 Comnonent information A. Centnfugal charging pumps l A and IB
- 1. Rated flow: 150 @ $800 ft head (2514 psid)
- 2. Rated capacity: 100'7c
- 3. Type: centrifugal i3. Reciprocating charging pump 1
- 1. Rated flow: 95 gpm
- 2. Rated capacity:displaecment 100c 3, Type: positive 3.4.6 Sunnort Ntems and Interfagu A. Control Signals
- 1. Automatic
- a. The centrifugal chatging pumps are automatically actuated by a safety in,iection signal (SIS).
- b. The reciptorating charging pump is tripped and the normal charging line is isolated by an SIS.
- 2. Remote hianual The charging pumps can be ectuated by remote manual means from the control room.
B. Stotive Power
C. Other
- 1. The centrifugal charging pumps are cooled by the Essential Service Water system (see Section 3.9).
- 2. Pump lubrication and ventilation are provided locally.
O V
31 1/89
,..n
.a k
i 1
h i
t l
i i
A
,f
$3EFUEl #sC WATE 84 twas STORAGE Tex e
_voi tang,,
c x
Gt AWsf -
Test L
i i
4 84C*A te 54 T orare,s SYSTtu + 7 3 y
se pt.ps Q
70 sit g as ;gt:4 Cy s8044 sipre 44g e4mf Encs.vsgia f
cr> ~
j
~
pear.:PIC PA fut g
TO SI t
1
. SYSTEM i
l
$8 B=J6 i;
f TOHEAC104 TOCS PUuptA
+f Cto wartoop A i
g, l
CS 1 A SM4
~
.j l
O
. TO REACTOR k d g
,7
' CCa0tMeTtOOP19 e
r do-
- >c i
4 psetA 9495A 121 e347 164 g
ej '
~
d 8471 A 1
. gg f
CYPTA COOLANT LOOP PC
-[
TOREACTOR ri 2
CV-1120
+N rN i
eC36C i
Q e546 mT,
+'
TO FIACTOR Q
- COOLA*4T LOOP t
e mm _ torgjecTcq r7 sette 84956 SE ALS
' CV 1tzE e472B 7N ec380
' CVPTB '
C l
Tome
. gonome 3
PUMP 1A sWECTiord
+
70LOOPt i
Sf4812A TMM
,X, i
3 CRO LEG To t.a O
PUMP 79 mTa stoetzB TOLOOP2 wm COLD LEC
$resetA 4
88'N N.
h W
?
Q'
.m ggggg gq s,'L;;.
TOLOOP3
[
sysuu e,,
co'c uc ens
.mc i
l bE'oTJ t'
' ]
4 setto egoco c.
i i-i Figure 3.4-1.
Braidwood Unit 1 Charging System i
Ii llj' I[
!ll!{(.
,if I
l
,!f i{
i:[i:l
- Pl,I
.i!.
to
'c
. G Pt To i
we E
a C
O Ot t
t 7
Oo l
t T
p N
P' L t g
mO t
O Oo qo w
+@ %m +Wn4m T T C#
T T TT C
c g
R A A AA AA t
e
=
E 5 O M
AeC 0C O
OO OO e
' C TC TC sn
+
4 l
o g.
, [g C
2'g 3
s 3
g Xg xs Xc x,,,
i c
e e
3 t
i
.e a
h
_M g
e c
o
>g L
'A Ls t
4e n
, r t
[ n S
e
,E*
4 P
n 8
O o
M
^
1 RO Ot p
C Ti cms m
M}8 A
o 4t L 3
OA 4
4,-
C 0OE 7 CS 9;,
w e
?
?,
g
~
_g
- s n
i w
l M2 o
g h
1 S
?
ra MON i
m sT 38 aCT M'
N8 A
a eT e
A l
E L
t 8
t s
4 se y
S
+y A
l g
+l Nit i
i 1
t 8
s n
4 e
6 g
l E
r i
A e,
l a
1 o
h sv v
a C
V c
/'
C
/,
C R
n 1
u o
n 4
,A-t M
1 y,-
i T
n LG 4
i 8 --
U d
l oo s
A
- 'g w
+N 5 6
6 4
d 7
e 8
- g iar pttuoM 3
l B
AC e
r ptf TT S
i y t 4
sT OP Y
g ss wO S
Oy A
B D
C A
a 2
Ts t
?
2 2it M1 Sp SP r
f P
CA Cu LrV ru 4
t s
Ot Ou OU c
TP 3
T a
S e
R N
M P A
e f
A f
2 r
A*
1 t
i A
S WT S
s C
a u
OE' l
G s
s.
g t
P l
i A
ER F
L T
>O S
lF T l
l M
W ES
,3 5
P H
,7
=
i 8
a h
a t
t e
l "r
s u
P w
t 4
R uS 2
v o
mS I
l yy cg 1
,.j!
i' i'
j.'
,'II j
{4
- l j : fl j; ; j4 't
$j1 Il1
.C I
r j
i i
Table 3.4-1.
Braidwood Unit 1 Charging System Data Summary l
for Selected Components j
COMPONENT ID COMP.
LOCATION POWER SOURCE VOLTA G E POWER SOURCE EMERG.
i.-
TYPE' t.OC A TION LOAD GRP j:.
CV-112D MOV 364PENHM MCC-131 X1 480 364PETARM AC/A l
c Cv-112E MOV 364PE NRM MCC-132X4 480 426PENRM AC/B
.l CV-P1 A MDP CVA BUS 141 4160 ESF11 AC/A
[
CV-P1B MDP CVB.
BUS-142 4160 ESF12 AC43 j
SI-8801A MOV 3G4PENRM MCC-131X1 480 364PENRM AC/A I
(
SI-8801B MOV 364PENRM MCC-132XS 480 426AB AC43 l
SIMVST IANK HWST-
[
1 t
3 f
i w
M b
t i
i,
.l i-l s.,
I s
1 i-I
).
l I
o:
C 7-i
[
i 1
4 i
)
i
Braidwood I & 2 q
3,5 CONTAINMENT llEAT REMOVAL SYSTEM 3,5.1 System functi;q Containment heat temoval systems perform the functions of containment heat removal and pressure control following a loss of coolant accident. In conjunction with the 1
ECCS, the containment heat removal systems completes the post LOCA heat transfer path from the reactor core to the ultimate heat sink. The Containment Spray System, which is one of the containment heat removal systems, also serves to remove elemental iodine from the containment atmosphere.
3.5,2 System Definition Containment heat removal systems include the following two systems:
Reactor Containment Fan Cooler (RCFC) System Containment Spray (CS) System The RCFC system provides the design heat removal capacity for the containment following a LOCA, assuming that core residual heat is released to the containment as steam. This is accomplished by the continuous recirculation of the air-steam mixture through cooling coils to transfer heat to essential service water. The RCFC system consists of two redundant trains, each powered from a separate bus. Each train consists of two 507c capacity fan cooler units.
The Containment Spray system is designed to remove fission products, primarily elemental iodine, from the containment atmosphere following a LOCA. The syster ; also serves to reduce containment pressure and temperature during the injection phase of LOCA mitigation. The CS system consists of two independent trains, each O
containing a 100% capacity pump and three ring type spray headers. During the injection
\\d phase of LOCA mitigation thc, CS aumps draw suction from the RWST. During recirculation the CS pumps draw from t le containment sumps.
Sim and 3.5 2. plified drawings of the Containment Spray system are shown in Figures 3.51 The interface between the containment fan cooler units and essential service water is shown on the ESW system drawings in Section 3.9. The interfaces are thrcugh motor operated valves CC-16A and CC 16B. A summary of data on selected containment spray system components is presented in Table 3.51, 3,5,3 System Oneration The Reactor Containment Fan Cooler system consists of two trains, each containing two 50?c capacity fan cooler units. The RCFC is designed to commence operation approximately 45 seconds following the initiation of a safety injection signal.
Heat is transferred through cooling coils to essential service water. During nonnal operation the RCFC fan motor operates in the high speed mode. On initiation of post-LOCA mode of operation the motor will shift to low speed, resulting in lower air flow.
The lower air flow compensates for the increase in containment air density resulting from the higher pressure following a LOCA (Ref.1).
The Containment Spray system consists of two pumps, each supplying three spray headers located in the containment dome area. The spray system will be actuated by high.high-high containment pressure (approximately 23 psig). During the injection phase, water from the RWST is sprayed into the containment atmosphere by the CS pumps.
Following the injection phase the spra containment sump during recirculation. y pumps are realigned to draw suction from the O)
(v 35 1/89 i
Braidwood 1 & 2 3.5.4 System success criterin The CS success enteria are not clearly defined in the FSAR in terms of j
s containment heat removal. However, the following is noted (Ref.1):
j Operation of one of the two independent CS trains will ptovide 100% of I
systern capacity, l
Operation of one CS train will lower containment pressure enough so that containment design leakage is not exceeded, and enough iodine will be removed to restrict the site boundary and offsite doses to below the limits of 10 CFR 100.
The RCFC success criteria are as follows (Ref. 2):
One of two redundant trains is in operation approximately 45 seconds after a safety injection signal is initiated.
Partial CS and RCFS success criteria may exist. but are not defined in the FSAR..
3.5.5 Comnonent Information A. Reactor Containment Fan Cooler Units I A, IB, IC, and ID
- 1. Fan type: vane axial
- 2. Rated capacity: 507c 6
- 3. Accident mode heat removal: 132 x 10 Blu/hr B. Containment Spray Pump 1 A O
- 1. Rated flow: 3415 gpm @ 450 ft head (195 psid) _
- 2. Rated capacity: 100(7o
- 3. Type: verticalcentrifugal C. Containment Spray Pump 1B -
- 1. Rated flow: 3925 gpm @ 450 ft. head (195 psid)
- 2. Ratedcapacity: 1007o-
- 3. Type: verticalcentrifugal 4
3.5.6
. Supnort Systems and Interrnees A. Control Signals
- 1. Automatic The fan cooler units are automatically actuated by a safety injection signal.
The containment spray system is automatically actuated on high high high containment pressure.
- 2. Remote manual -
The RCFC and CS systems can be actuated by remote manual means from the control room.
B. Motive Power
i Section 3.7. - Redundant loads are suppli d from separate load groups.-
1
'36L
- 1/89 -
...,,L..,..~.,,,.,_,.,,--+
..A
.,,,,,s,-.,
,_.e 4-_-_--.
-w,.
Braidwood 1 & 2 C. Cooling Water
- 1. The RCFC units are cooled by the Essential Service Water system (see Section 3.9).
D. Odier l. Lubrication. ventilation, and pump cooling are provided locally for the CS pumps.
3.5.7 Section M Re egg 3 r
1
- 1. Byron /Braidwood Final Safety Analysis Report,6.C.2.
- 2. Byron /Braidwocxl Final Safety Analysis Report. Section 6.2.2.
i 1
i i
i 1
l 37 1/gg i
r~s
/'m..
\\a)/
(
I
(
1
(
V Fad f Ul WA!( 64 $,i pw2 g sty g T Anat a
ta erwst sw
)
'-'a n r. n}a a a a c=},.n,,
~
,, m,,
~#
,o P,
.--.....j sytriu EEP.' A E 7.~ra o u,.. ~., r.,
9 a.1,.
J Q
Q I
V r a a n's a a a a cwut Ario.,
H H - -pq --
~h+ ~~~ y*
~ ~ ~
,-- Q::+b
'*9 **vtiis SWA
$1 apt 1 A GA
- A 4'JA G'8 y
- y. A
- E E
y g ; ga._
i x,,4 C.a 2-x.
u 9
X,s
$3--H N
r wa se a
y anaassaa Q
St $F14Af %O2,{$
g toucvcn i X
.ie ice 90 $ PRAY NOCT E 5 CS 18 I
CONT AfMAK NT g
aaaaacaa MCNT1008 112 $Pha f 'uCULE S as
==
suuP a c s 7.
CS PIB O
-n,,zo-
--+ wy, ev
--~CuAsex PUMPS CW t*2E O
m N
aa
._.g
$14412A PuuPtA e
To swu
=ae a e -. H,,, _
PuuPis s,,,,,,
svsit-Figure 3.5-1. Braidwood Unit 1 Containment Spray System
~_m.
... ~.-.~.
b l
i
/
I a
l l
aws:
3-
~
g At TLdtesG 1
' WAY1 R SYtVu% -
TANK C
St FMr$7 t
l awsrs"L l 3saPEmats l C
i 589 v
]
gag AfOtThti EEE dl @
J L
T Aw se tPttav motlt 8 5
)
TO RA
., TO St W 1*
ff hm l
YSTE M g
l 4
iFk.
g L$ v%Av %r>fft E s
{
4 I
CDNTenNar
)
((E
~EE'h
[
SW A. %. _
L 3
f(CW4Ctx.7 123 SPstAv mw2T?tES
(
04 l
I St eett A eA 2A '
CS P1A -
C. '
sog
~
y g
.R x,
c=a l
,<,,A usucion g i
4
.,, A s m
]
(sa l
2t A.
2p tu 4u i
W css l
E><
b.
X 4
' 218., 200 998 469 g
l 4
nannanan i
n mamms c g,, y
- q q~
M nanannan
+
C's-s e -
"*""^ * '*
CONTAMSEtif n
j v ;-
,,5
,,. 1p-O-@
gr aaaaaana
~ ~ ~ ~
> CS 9s8 Tome..
(
CV-ti20 w
2
,10
- PUw 18 p j
%gm
]
'I 354PE NRas l
. ' Cv st2Ci a-k l 10 '
24m
{
$4 8812A ;/ ' W1A
(
M
'O
] sesptanas [
}
-m sums -
ram t
an + N sa me,2s PWP tB s ys'E ss.am i
I e
I l
Figure 3.5-2. Braidwood Unit
.watainment Spray System Showing Component Locations 4
1
?
1 I
i' l
Table 3.5-1.
Braidwood Unit.1 Containment Heat Removal System Data Summary fOr Selected Components COMPONENT ID COMP.
LOCATION POWER SOURCE VO LT A G E POWER SOURCE EMERG.
TYPE LOCATION lot.D GRP CC-16A MOV 364PENRM MCC-131XS 480 426AB ACIA CC-16B MOV 36ePENRM MCC-132X4 480 42GPENRM AC/B CC-27A MOV 364PENRM MCC-131XS 480 426AB AC/A i-CC-27B MOV 364PENRM MCC-132X4 480 426PENRM Af /B.
4 e
CC-FANA ACU RC l
CC-FANB ACU RC 4
4.
J CC-FANC ACU RC i
CC-FAND ACU RC i
CS-1 A MOV 364PENRM MCC-131X1 480 364PENRM AC/A CS-1B MOV 364PENRM MCC-132X4A 480 426 Pelf:lM AC/B nO CS-7A MOV 364PENRM '
MCC-131XS 480 426AB AC/A CS-78
- MOV 364PENRM MCC-132X4 480 426PENRM AC/B j
CS-9A MOV CSA-MCC-131X1 480 364PENRM '
AC/A 1
CS-98 MOV' CSB MCC-132X1 480 364AB AC/A f
i CS-P1 A MDP CSA BUS-141 4160.
ESF11 AC/A -
j CS-P1 B MDP..
CSB BUS-142 4160 ESF12 AC/B i
J'
)
1 x
i l
i
l
. 1 Braidwood I & 2 3.6 INSTRUMENTATION AND CONTROL (I & C) SYSTEMS-3.6.1 System Function The instrumentation nr.d control systems consist of the Reactor Protection System (RPS), the Engineered Safe;y Features Actuation System (ESFAS), and systems for the display of plant infom1ation to the operators. The RPS and ESFAS monitor the reactor plant, and alert the operrter to take corrective action before specified limits are exceeded. The RPS will initiate an automatic reactor trip (scram) to rapidly shutdown the reactor when plant conditions exceed one or more specified limits. - The ESFAS will automatically actuate selected safety systems based on the specific limits or combinations of limits that are exceeded. A remote shutdown capability is provide to ensure that the reactor can be placed in a safe condition in the event that the main control room has to be evacuated.
3.6.2 Svstem Definition The RPS includes sensor and transmitter units, logic units, and output trip relays that operate reactor trip circuit breakers to cause a rea'etor scram. The ESFAS includes independent sensor and transmitter units, logic units and relays that interface with.
the control circuits for the many different sets of components that can be actuated by the ESFAS, Operator instrumentation display systems consist of display panels in the control room that are powered by the 120 VAd electric power system (see Section 3.7). The remote shutdown capability is provided by the remote shutdown panel in conjunction with normal automatic systems and local controls outside the control room.
3.6.3 Svstem Ooeration Oh A. RPS The Westinghouse RPS (or Reactor Trip System, RTS) has two to four redundant input instrument channels for each sensed parameter and two output actuation trams (A and B), The A and B logic trains independently generate a-reactor trip command when prescribed parameters are outside the safe operating range, Either RPS train is capable of opening a separate and independent reactor trip circuit breaker to cause a scram. The manual scram A and B circuits bypass the RPS logic tnins and send a reactor trip command directly to shunt tnp circuitry in the reactor trip circuit breakers.
1
- B. ESFAS
{
The ESFAS has three or four input instrument channels for each sensed parameter, and two output actuation trains (A and B). In gener-1, each train j
controls equipment powered from different Class 1E AC electrical buses. An individual component usually receives an actuation signal from only one ESFAS train. The ESFAS generates the following signais: (a) reactor trip, 1
_provided one has not already been generated by the RPS,(b) safety injection signal (SIS), (3) containment isolation, (4) main steam line isolation, (5) main 1
feedwater line isolation, (6) emergency diesel start, (7) control room isolation and (8) containment spray actuation. The control room operators can manually trip the various ESFAS logic subsystems. Details regarding ESFAS actuation-logic are included in' the system description for the actuated system.
- (
i 41 1/89L r-e er.
<v e
e c.-c w* *,, -
w,wr---.-...,-,e,we,e,wr-
, <, - +
-->,w yye-,,w.*
w r-pr s -
e.,yw,
, y e-y
,w-
- ~_- -..
l
- Braidwood 1 & 2 -
C. Remote Shutdown O
For equipment having controls outside the control room (which duplicate the -
functions inside the control room), the controls are provided with a selector switch which transfers control of the switchgear from the control room to a local station. Placing the local selector switch in the local operating position gives an annunciating alarm in the control room and turns off the indicating lights on the control room panel.
The remote shutdown panels are located at plant elevation 383 feet in the radwaste control area.
The main control room panels and the remote shutdown panels are located in separate physical locations, on separate elevations, with separate ventilation -
systems and multiple communication systems, and with lighted access routes -
between the two locations. Therefore, it is expected that no sin ;le credible event which will cause evacuation of the main control room wil. also cause remote shutdown panels to be ino serable. Equipment having controls available outside the conte room are listec in Table 3.6-1 (Ref.1),
3.6.4 System Success Criteria A. RPS in the analog portion, two to four redundant sensors and channels are used.
The coincidence required to cause a trip varies from parameter to parameter.
The channel's analog input is converted into a digital signal for the logic-portion. The RPS uses hindrance logic (normal = 1, trip = 0)in both the input and output logic. Therefore, a channel will be in a trip rate when input signals are lost, when control power is lost, or.when the channel is temporarily removed from service for testing or maintenance (i.e. the channel has a fall safe.
failure mode). A reactor scram will occur upon loss of control power to the RPS. A reactor scram usually it implemented by the scram circuit breakers which must open in response to a scram signal.;There are two series scram circuit breakers in the power path to the scram rods. In this case, one of two -
circuit breakers must open. Details of the scram system for Braidwood have-not been determined.
B. ESFAS
. A single component usually receives a signal from only one ESFAS output train although both AFW pumps receive signals from both trains. ESFAS Trains A -
and.B must be available in order to automatically actuate their respective components. ESFAS typically uses hindrance input logic (normal = 1, trip = 0) ;
and transmission output logic (normal = 0, trip = 1). In this case, an input-channel will be in a mp state when input signals are lost, when control power is-7 lost, or when the channel is temporarily removed from service for testing or-maintenance (i.e. the channel has a fail se.fe failure mode). Control power is-needed for the ESFAS output channels to send an actuation signal. Note that -
there may be some ESFAS actuation subsystems that utilize hindrance output logic. For these subsystems, loss of control: power will cause system or component actuation, as is the case with the RPS. Details of the ESFAS system for Braidwood have not been d,:termined; l
42 11/89
,-----r-
-eg-e yr enp v-e e
ry,
,1
--..e.,
,n
,y a
~~.~,,,+-+.e~
<.- w s - v e v - ~
i Braidwood:1 & 2-3.6.5 Suonort Systems and interfaces V
A Control Power
instrument buses (see Section 3.7). It is assumed that the RPS A and B
~
output logic trains are powered from separate 125 VDC distribution panels,
- 3. OperatorInstrumentation Operator instrumentation displays 'are powered from the 120' VAC instrument buses, 3,6,6 Sectinn 3% References l.
- 1. Byron /Braidwood Final Safety Analysis Report, Section 7,4.1, 1
i i
i k
i i
+
^
k l
i i
d f.-
- f..
4 1
k
-l 43-1/89 ~
j 3
.u-.......
.-._.,-.n,..-._..,_-.....,.~..-...
,--._.,....,a
O Table 3.61.
13raidwood Equipment Controls Available Q
Outside the Control Room The following equipment can be controlled from local stations outside the main control room:
Auxiliary Feedwater Pumps Centrifugal Charging Pumps Boric Acid Transfer Pumps Essential Serv Water Pump Component Cooling Water Pump Reactor Containment Fan Coolers Control Room Ventilation Unit including Control Room Air Inlet Dampers Primary Water Makeup Pumps Charging Flow Control Valve Letdown Orifice Isolation Valves 1
Aux. Feedwater Control Valves Power-Operated Atmospheric Steam Relief Pressunzer Heater Control Emergency Boration isolation Valve bU 4
- \\
44 1/89
Braidwood I & 2
)
p 3.7 ELECTRIC POWER SYSTEM 6V) 3.7.1 Ssstem Function The electne power system supplies power to various equipment and systems needed for nonnal operation and accident response. The onsite Class lE electric power system supports the operation of safety class systems and instrumentation needed to establish and maintain a safe shutdown plant condition following an accident, when the normal electric power sources are not available.
l 3.7.2 System liefinition 1
The onsite Class lE electric power system consists of two 4160 switchgear buses, designated 141 and 142. There are two standby diesel generators cor.nected to the buses. Diesel generator I A is connected to bus 141, and diesel generator 1B is connected to bus 142. There are also four 480 VAC switchgear buses, designated 131X,1312, 132X and 132Z. Buses 131X and 131Z are connected to 4160 bus 141 through i
transformers, and buses 132X and 132Z are connected to 4160 bus 142 through transformers. Buses 131Z and 132Z serve loads associated with the essential cooling towers. Various motor control centers (MCCs) receive their power from the 480 VAC buses.
Emergency power for vital instruments, control, and emergency lighting is supplied by two 125 VDC station batteries. The batteries energize two DC butes, designated 111 and 112. Four 120 VAC instrument buses are connected to the DC buses through inveners, and to 480 VAC MCCs through transfomiers.
Simplified one line diagrams of the electric power system are shown in Figures 3.7 1 through 3.7-4.
A diagram of the diesel generator fuel oil system is shown in Figure 3.7 5. A summary of data on selected electric power system components is
[V presented in Table 3.71. A partial listing of electrical sources and loads is presented in 3
Table 3.7-2.
3,7.3 Svstem Onerntion Dunng nomial operation, the Class IE electric power system is supplied from the 345 kV switchyard, directly to the two 4160 buses through two system auxiliary transformers. An alternate source of power is also from the 345 kV switchyard but through Unit 2's 4160 switchgear. The emergency sources of AC power are the diesel l
generators. The transfer from the preferred power source to the diesel generators is accomplished automatically by opening the normal source circuit breakers and then reenergizing the Class IE portion of the electric power system from the diesel generators.
The DC power system normally is supplied through the battery chargers, with the batteries "Roating" on the system, maintaining a full charge. Upon loss of AC power, the entire DC load draws from the batteries. The batteries are sized to supply the instrument inveners for up to 30 minutes, and other loads such as diesel generator control power for up to 4 hot The 120 VAC vital buses normally receive power from the DC buses through an invener. An attemate source is from the 480 VAC system through transformers.
Redundant safeguards equipment such as motor driven pumps and motor operated valves are supplied by different VAC buses. For the purpose of discussion, this equipment has been grouped into " load groups". Load group "AC/A" contains components I
receiving electric power either directly or indirectly from 4160 bus 141, Load group "AC/B" contains components powered either directly or indirectly from 4160 bus 142.
l Components receiving DC power are assigned to load groups "DC/A" and "DC/B", based on the battery power source, i
OV 45 1/89 l
Braidwood 1 & 2 3,7,4 System Success ' Criterin I
Basic system success critena for mitigating transients and loss of coolant accidents are defined by front line systems, which then create demands on support systems. Electric power system success criteria are defined as follows, without taking credit for cross. ties that may exist between independent load groups:
Each Class 1E DC load group is supplied initially from its respective battery-Each Class 1E AC load group is isolated from the non-Class 1E system and is supplied from its respective emergency power source (i.e. diesel generator)
Power distribution paths to essennal loads are intact Power to the battery chargers is restored before the batteries are exhausted 3,7,5 Comoonent Information j
A. Standby diesel generators (2) 1, Maximum continuous rating: 5500 kW
- 2. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating: 6050 kW i
- 3. Rated voltage: 4160 VAC
- 4. Manufacturer: unknown B. Batteries (2)
- 1. Rated voltage: 125 VDC -
3,7.6 Suonort Svstems and Interfaces t
A. Control Signals
- 1. Automatic 5
The standby diesel generators are automatically started based on: -
Undervoltage on the normal bus Safety injection signal (SIS, see Section 3.3) i
- 2. Remote manual The diesel generators can be started, and many distribution circuit breakers; can be operated, from the main control room.
B. Diesel Generator Auxiliary Systems
- 1. Diesel Cooling _ Water System Heat is transferred from a jacket water system to the Essential Service Water system. Each diesel receives redundant cooling water supplies from the ESW "A" and "B" headers (see Section 3.9).
t
- 2. Diesel Staning System Each diesel has an air starting system.
- 3. Diesel Fuel Oil Transfer and Storage System A 500 gallon " day tank" supplies the relatively short term (approximately 72-minutes) fuel needs of each diesel. Each day tank is replenished from two 25.000 gallon storage tanks dunng engme operation.
4 -
- 4. Diesel Lubrication System Each diesel generator has its own lubrication system.
4
- 5. Combustion Air Intake and Exhaust System-This system supplies fresh air to the diesel intake, and directs the diesel l
exhaust outside of the diesel building -
e 5 \\
46 1/89.
J
-_,.-____......,_,,_.._m.-.%m.,~.
g.m.__.-,.o
Braidwood 1 & 2
- 6. Diesel Room Ventilation System This system maintains the environmental conditions in the diesel room i
within limits for which the diesel generator and switchgear have been qualified. This system may be needed forlong term operation of the diesel generator.
i l
l i
J
-l 47 1/89-
L
' i t
t I
yo m av v aro s +* *d w. xv vano a
o I
f f
uw i
G MHA MM
/-
34sdNO M
= N 34*45 el 1
4 4
I
- I==
1
.wia
- n -
em mo me MW l L2,
]
o to wn san iv LM
"""*wtn i
Et>SES 157.159 at60 6900 69no 4160 MS N 8
' f 2
o
{
i 6
to uwsAn ry To a sAruv
+
o Toe seuy auses,ss. tu.
eusts ise. is7-sore sas tn
}
. aus 3 3 vsa. ese
- m. m sus i.4 FHou4nov -
. I BUS 249,
. pm,,gey
?
Wi r
.l, l,
gus 7,7, tref 2 oc i A oc *s y CS-14 y (B 78 i
.ien vac aus m i
I em vac eus is I
c
~lB II ll ll ll
'11
(
l
= = -
= = '
==
==
==
. = =
4160/440
. YRt31st 41ety480, -
4160r480 -
d o60+4a0 TR132X 4 560,4a0 416 h
I 7
e 1I P2R HEATER 483 VC BfJS 831R..
PER pt ATER PZRif ATE F 480 VAC BUS T3rg Plft f( ATE 84
[
BACKtP CRP. A BACMtp GRP. O BAcatipCFP. A CONTHOL cAIP.C 11 IB'
' IB.'il' sp gr ll Ir i.
1 I
)
i t
l j
l ucces,x. 1 I =cc.3 x2 I-I wecnins i I ucc 3 x4 1 l uccisens 1 -
l wec wn, l
. I wec,wx: 1 I =ccium. I I wccern I l =cc,-ru l l
j g.
g
- ?
. (co l uCC131x1 A l l MOC132n*4 l to.
I i
c I
j Figure 3.7-1.
Braidwood Unit 14160 and 480 VAC Electric Power Distribution System-I' t
- )
.1
. _.. ~, - -.. - -... ~. _ _
N 10 m sty v a:t1 Hu m w,.y w :s
<l 34WS
'L
I CIta fWOR \\
I,N38975
.1 i
I
=L_
==
690C 4160 4 tt o f 4m I
_L
+
TO NON SAFE TY U
~
8:X,E S 157.159 4160 6900 ew0 4tEO 8
h TO NON SAF E TV 1r
?O NON SAFE TV f
<r TO NEW SAF E TY 0
8,_1 TO NON SME T V
'i #-
'57 BUS 143 BUS 144 F3WW 4160V e BCS 241
- s sa.w a y.cv gg t#87 2 Od1 A 2
g BUS 2e2, OG tG (SF
l C& tA l
45Ft2 C818 l
. 4160 V AC SUS 14 5 l-l 4160 VAC RUS 142 l
~
3 t
it k
h is I
4
- 4.M M,
i_ Mk-ly ~ f
' JMME MM
~-
4160/480 :
. TR 131E '
stocr430 4160/480 I
.gg 4160/480 TR-132X 4160/400 -
4190sda0
<ll (l-PZR HEATER 480 VAC Bus 13f x PJH t(ATER P2R HE A TE R 480 VAC SUS 132X FIR p( A TE R BACsa.FGFP, A SACMP CRP.D BACMLP GFP.B CONTHOL GRP C II
,11 II:-11
'll.
11 ll' 'll t
i y
r l.
I i
l MCC13t El l.'
. l MCC131x2 l
.. l MCCt3t X3 ll l MCC131N4 l l MCCitiXS l l MCC1MN1 l l MCCf32x2 l l MCCluna l l tsCCTPts l l MCC132s3 l t
(
l MCC131x1 A l..
00
' l M'32 A*4 l
_j 364PENRM l l 434PtNRM l l
383A8 l
l LfmKNOwM l j 426A8 l
l 364 A s l l 426PENRM l l
42649 l l 383 A S l
ft)iC Lees May tk.>t Represcre Actual Catde rom &fme Rooms Figure 3.7-2.
Braidwood Unit 14160 and 480 VAC Electric Power Distribution System Showing Component Locations i
r t
I i
h 4
P
$ ly)pA froA Fir)fA ffKtA f tOA I F K 4.4 f iF '*.9 isras f ig;t.,
f f y 4,q i
MCC131X1 LeCC13 t x2 4t4 VAC DUS 131X L1CC t 31 x4 teCC t31x3 E4CC1rm s atCC1 M *2 inn sac ta;s t32x teCC',32p a s.scct nx3 p-y o
I I
nc E
oc 111
_ BT-111 2
Z BT it?
112 n
o T.
t v.
==
==
==
1'
==
C l
in 111 4 eon 20 la voc aus ut in 113 asonzo in us
<ami2o 12s voc eus n2 -
'80" 20 1
u u
a n.
i,.
e
= -
123 voC oista 2
~;
.Nv 1: s voC o,st 1.
f 111 PAtJEL 113
- 113 p
112 PAfd L 114 114 g
+
o o
1 i
120 VAC IfJS1FtUMENT BUS 120 VAC INSifulMENI BUS 120 VAC INSifRAT PJi BUS 120 VAC INSTHE e.4 NI BUS j
111 113 n2 11s
[
i i
i j
6
-=
w C.
[
Figure 3.7-3.
Braidwood Unit 1 125 VDC and 120 VAC Electric Power Distribution System i
e i
.... ~..,,.
. ~... -.... - ~.
O l
4 l
ESF11 l
j LSF12
[
f 364PE NHM 414 P[ NH M 414PE NH M ]
[
383AH 364AU 4 76 Pl. N H M 424 0'I NHM l
{
38 3 A fg f f tou Fpinu f fOA if TOM ff40u f f K4A i1Inu IIKV '-
5840sA f fF #A MCC131 x1 MCC131 X2 493 VAC IMIS 131 X
' MCC131)f4 MCC131 X3 -
MCC132x1 fACC132X2 480 VAC f S 132X
- MCCl32x4 1X C132x3 t
it
<r
'r i
)
k a
JL
~
.11 2
[ 81 111 2
BT112 t2 1
T e
==.
-i
==
- =
?
==
l l
TF1til 480/120 125 VDC DOS 111
' TR.1*3 480/120 TR-113 430r120 125 VDC DOS 112 TH 114 480r120 i
i-i iiI IB-
- 1B 1B i
't i
t i
WW f 125 VDC D15171
- 9f/
trN 125 VDC DIST.
- 8tu -f f
111-PAtEL 113 113 f
112.
PANEL 114 114 ji.
- II
- '
11
l[
jg 120 VAC INSifDJMENT DUS
~
gg.
g.
111
'~
15 'e AC tN51FRJuENT CUS 120 VAC IPG1F4tAff NT DUS 120 VAC INSTERP.4 NT BUS 113 3
112 114 i
.l l
l BATHM111 l
^
l B A TR M112 l 1
3 C
NOTE 'ines May Not Reprew Actual Cat.fo FbsAbrr; Octw,er Rooms ao e
j Figure 3.7-4.
Braidwood Unit 1125 VDC and 120 VAC Electric Power Distribution System j
Showing Component Locations i
O O
O w
DAY TAtJK 4A g3 DIE tt A
2A STORAGE TANK 1A e
1A TO DIESEL i
SA p
v GENERATOR 1A
[
l 3C 4C DlESEL Olt 63C 100C 2C STORAGE TANK 1C IC 1
i 1
fl
-l
(
YJ y
DAY TANK 38 4R jo
' DIESEL OIL 638 1
28 l
STORAGE TANK B
Q i
1B TO DIESEL C
58 y
GENERATOR 18 l
i 3D 4o DIESEL. Olt 63D 1000 2D STORAGE TANK 1D 1D E
c i
Figure 3.7-5. Braidwood Unit 1 Diesel Fuel Oil System i
= -
t Table 3.7-1.
Braidwood Unit 1-Electric Power System Data Summary for Selected Components COMPONENT ID COMP.
LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
' TYPE LOCATION LOAD GRP ACBUS-111 BUS iMTRM111 TR-111 120 BATRM111 AC/A j
ACBUS-111 BUS WATRMi11 INV-111 120 BAT HM111 ACIA ACBUS-112 BUS BA THM112 1f0112 120 BATHM112 AC/B ACBUS-112 BUS BAIRM112 INV-112 120 BA THM112 AC/B ACBUS-113 BUS BATRM111 TR-113 120 BATRM111 AC/A ACBUS-113 BUS BATRM111 INV-113 120 BAT RM111 AC/A ACBUS-114 BUS BATHM112
'R-114 120 BAIRM112 AC/B ACBUS-114 BUS.
BATRM112
!NV-114 120 BATRM112 AC/B
{
BC-111.
BC BATRM111 BUS-131X 125 ESF11 DC/A i
BC-112.:
BC-BATHM112 BUS-132X 125 ESF12 DC/B u.
w BT-111 BATT BATRM111 125 DC/A BT-112 -
BATT BATRM112.
125 DC/B l
BUS-131 X -
BUS ESF11 T R-131X 480 ESF11 AC/A i
BUS-132X BUS ESF12 TR-132X 480 ESF12 ACiB BUS-141 BUS ESF11 DG-1A 4160 DGA AC/A
[
BUS-142.
BUS ESF12 DG-1B 4160 DGB AC/B CB-1A CB ESF11 DG-1A 4160 DGA AC/A CB-1B CB ESF12 DG-18 4160 DGB AC/B DCBUS-111 BUS BATRM111 -
BT-111 125.
BATRM111 DC/A -
1 DCBUS-111 BUS BATRM111 BC-111 125 BATRM111 DC/A t
DCBUS-112 BUS BATRM112 BT-112 125 BAT RM112.
DC/B i
DCBUS-112 BUS BATRM112 BC-112 125 BATRM112 DC/B DG-1 A -
DG DGA 4160-AC/A DG-1B DG DGB 4160' AC/B
!NV-111 INV BATHM111 -
MCC-131X2 120 414PENRM DC/A INV 9ATRM111 DCBUS-111 120..
BATRM111 DC/A INV-111 j
j INV-112 INV l BATRM112 MCC-132X2 120 426PENRM DC/B h
'i Table 3.7-1.
Braidwood Unit 1 Electric Powar System Data Summary i
for Selected Components (Continued) i COMPONENT ID COMP.
LOCATION POWER SOURCE VOLT A G E POWER SOURCE EMERG.
' TYPE LOCATION LOAD GDP INV-112 INV BATRM112 DCBUS-112 120 BAIRM112
- )C/B INV-113 INV CATRM111 MCC-131X4 120 414PENRM -
DCIA INV-113 INV BATRM111 DCBUS-111 120 BAlRM111 DCIA -
a INV-114 INV SA TRM112 MCC-132X4 129 426PENRM DC/B INV-114 INV BATRM112 DCBJS-112 120 BATRM112 DC/B 1
MCC-131X1 MCC 364PENRM i BUS-131X 480 ESF11 AC/A MCC-131X1 A MCC 364PENRM MCC-131X1 480 364PENRM AC/A MCC-131 X2 MCC 414PENRM BUS-131X 480 ESF11 AC/A MCC-131X3 MCC 383AB BUS-131X 480 ESF11 AC/A
.j l
MCC-131X4 MCC 414PENRM BlJS-131X 480 ESF11 AC/A t.as MCC-131XS MCC-426AB BUS-131X 480 ESF11 AC/A t'
MCC-132X1 MCC 364AB BUS-132X 480 ESF12 AC/B MCC-132X2 MCC 426PENRM BUS-132X 480 ESF12 AC/B 1
MCC-132X3 MCC 383AB BUS-132X 480 ESF12 AC/B MCC-132X4 MCC 426PENRM.
BUS-132X 480 ESF12 AC/B
.f MOC-132X4A MCC 426PENRM MCC-132X4 -
480 42SPENRM AC/B
]
MCC-132X5 MCC.
426AB-BUS-132X 480 ESF12.
AC/B
- t TR-111 XFMR BATHM111 MCC-131X1 120 364PENRM.
AC/A j
TR-112 XFMR BATRM112 -
MCC-d2X1 120 364 AB -
AC/B l
TR-113 XFMR -
BATRM111 MCC-131X3 120 383AB AC/A j
TR-114 XFMR BATRM112 MCC-132X3 120 383AB AC/B T R-131 X -
XFMR ESF11 BUS-141 480 ESF11..
AC/A
{
I TR-132X XFMR ESF12 BUS-142 :
480 ESF12 AC/B '
~
e i
t t
e
-.s,
Table 3.7 2.
Partial Listing of Electrical Sources and Loads at Braldwood Unit 1 t
POWER VOLTAGE EMERG POWER SOURCE LOAD LOAD-COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT 10 7YPE LOCATION BC 111 125 DCcA.
D A TRM111 E P.
OCBV& t t i BUS
' 1 E 41:1 i
j 60-112 l2b OC B BATRM112 EP-OCOVSt12 BUS BATRM112~
+
l ei111 125 DC. A BATRM111 EP DCBUS 111 BUS BAIRM111 i
)
BI112 12b OC.B BAT R M1'12 EP DG BUS-112 BUS BATRM112 j
bu>131A 125 DC<A E dF 11 EP BC 111 BC BATPM111 B u b-131x di AC/A ESF11 EP MCC 131x1 MCC 364PENRM j
bus 131x 480 ACiA ESF 11 EP MCC 131X2 MCC 414PENRM f
BVS 13 t A 460 AC. A ESF11-EP MCC 131X3 MCC-383AB 1
l BUS 13 t X 480 AC A ESF t 1 EP MCC 13tx4 MCC 414PENRM BUS 13tA 460 AC/A ESFit EP MCC-131XS MCC 426AB i
i Euw13iA 125 deb E SF 12 EP BC 112 BC BATRM112 -
BUS 132A 480 A C. B E SF 12 EP MCC 132x1 MCC 364AB l
6U S-132X 460 AC. B E SF 12 kP MCC-132x2 MCC 426PENRM BU5-132A 460 ACi8 E SF 12 EP MCC 132x3 MCO 383AB -
+
i BUS-132X 480 AC,8 -
E SF 12 EP MCC-132x4.
MCC 426PENRM BUS 132A 480 AC/B E SF 12 EP MCC-132x5 MCC 426AB 4
BUS 141 4160 AC/A ESF t 1 AFW-AFW PtA MOP 383AB
{
CCW PO MDP 364AB 1
BUS 141 4160 AC, A ESF11 CVCS.
CV P1A MDP CVA l-BUS-141 4160 AC/A ESF 11 ECCS RH P1A MOP.
RHRA BUS 141 4160 AC/A ESF11 ECCS SIP 1A MOP SLA Bub-141 480-AC/A ESFil EP TR 13 t X.
XFMR ESFt1 i
Bub 141 4160 AC/A ESFt1 ESW.
ESW P1A MOP ESWPMPA BUS 141 4160
. ACeA ESFil PAHRS CS-PIA MOP CSA-
?
BUS 142 -
4160 ESF12 CCW CCW PO MDP 364AB d
BUS 142 4160 A C< B E SF 12 CCW CCW P1B MOP.
364AB h
BUS 142 4100 ACiB ESF 12 CVCS CV PtB MDP CVB
'dVS 142 4)60 ACiB E SF 12 ECCS.
RH PIB MDP RHRB i
BUS 142 4160 ACs 8 E SF 12 ECCS SbPIB MOP SIB i
BUS 142 480 ACs0 E SF 12 EP TR-132x XFMR ESF 12 BUS 142-4160 ACiB ESF t2 ESW ESW PIB MOP ESWPMPB 1
. 55 1/89 s
e
<,,n
--., m
,nv,-
-..n.-
n.,
r,
--wwe-.,,,,-.--,.,-smw.
em n
Table 3.7 2.
Partial Listing of Electrical Sources and Loads at Draldwood Unit 1 (Continued)
\\u
\\
FOWE4 VOL T AGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT SOUROE LOAD GRP LOCATION SYSTEM COMPONENTID TYPE LOCATION 6vd-14i 4 I t. O AccB E SF 12 PAHRS CS PIB MDP CSB Os514t
.1 1 (. D AC A E SF 11 CCW CCW PtA MDP 364AB DCbs5-111 lie DC. A BATRM111 EP INV 111 INV BATRM111 DCbV5111 120 DC. A BA TRM t 11 EP INV 113 INV BATRM111 DCBs5112 120 DC. B B A IRM t 12 EP INV 142 INV BATRM112 DCbJd ils liO DC4 6 bAIRM112 EP INV 114 INV BATRM112 DG 1 A 4160 AC/A DGA EP BUS 141 BUS E5F11 DG-1A 4160 AC< A DGA EP CB 1 A CB ESF11 DG-16 4160 A C> B DOB EP BUS 142 BUS ESF12 DG-18 41(0 AC. B OGB EP CB 10 CB ESF12 INv 111 120 AC. A BATRM111 EP ACBUS111 BUS BATRMi t t IN V l ii' 100 AC B B A T AM112 EP ACBUS 112 BUS BATRM112 INv 113 12; AC< A BATRM111 EP ACBUS 113 BUS BATRM111 INV 114 1;0 AC. b BATRM112 EP ACBUS 114 BUS BATAM 112
/%
l I
MCC 13 t A1 480 AC A 364PENRM AFW AF W-13A MOV AFWPPINL U
MCC-131 A1 480 AC. A 364PENAM AFW AFW 13B MOV AFWPPTNL MCC 131 A1 460 A C. A 364PENRM AFW AFW 13C MOV AFWPPTNL MCC 13 t A1 460 ACIA 364PENRM AFW AFW 13D MOV AFWPP TNL MCC 131A1 480 ACsA 364PENRM CCW CCW 9412A MOV 364AB MCC 131 A1 480 AC. A 364PENRM CVCS CV 112D MOV 364PENRM MCC-131 A1 4eo ACsA 364PENRM CVCS SI-8801 A MOV 364PENAM MCC-131 A 1 480 AC/A 364PENRM ECCS CV 8804A MOV 364PENRM MCC431A1 480 AC/A 364PENRM ECCS RH 8716A MOV 364PENRM MCC 131 A1 480 A C< A 364PENRM ECCS RH 8716A MOV 364PENRM MCC 13 t A1 460 AC/A 364PENRM ECCS SI8807A MOV SIA MCC 13t Al de0 AC<A 364PENRM ECCS SI 8811 A MOV 364PE NRM MCC 13 t A) 460 AC. A 364PENRM ECCS SI882tA MOV 364PE NRM MCC 13tX1 480 AC/A 3b4PENRM ECCS Si882tA MOV 364 PENRM MCC 131 A1 480 ACiA 364PENRM ECCS SI8923A MOV SIA MCC 13 tx t 480 AC, A 364PENRM EP MCC-13 t X 1 A MCC 364PENRM m
MCC 13 t A l 120 AC/A 364PENRM EP TR 111 XFMR BATRM t 11 m
56 1/89 w
Table 3.7 2.
Partial Listing of Electrical Sources and Loads at Braldwood Unit 1 (Continued) rh I
\\
POM R VOLTAGE EMER3 POWER SOURCE LCAD LOAD COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION MCC-131 A1 460 AC A 354PENRM ESW ESW 133 MOV ESWPMPA MCC 131 A1 460 AC A 364 Pt N A M ESW ESW 133 MOV ESWPMPA MCC 131 A1 400 AC:A 364PENRM ESW ESW 14 MOV ESWPMPA MCC 131 A1 460 AC: A 364PENRM ESW ESW t 4 MOV ESWPMPA MC C-131 x 1 460 AC A 364 PE N RM ESW ESW 17 MOV 346AB MCC 131 A1 460 i ACeA 364PENRM PAHRS CS1A MOV 364PENRM MCC-131 x 1 4fD AC. A 364PENRM PAHRS CS 9A MOV CSA MCC 131A1A 46V AC A 364PENRM ECCS SI8802A MOV 364PE NRM MCC-13 t A1 A 46v
. ACiA 364PENRM ECCS SI6835 MOV 364PENRM MCC 131A2 120 DC A 414 PE NRM EP INV 111 INV BATRMi t i MCC-131 A2 46; AC A 414PENRM RCS RC 8000A iMOV RC MCC 131x0 460 AC A 414PENRM RCS RC 8701 A MOV RC MCC-131 A2 480 AC. A 414PE N RM RCS RC 6702A MOV RC MCC-131 A3 4SO AC A 383AB AFW AFW 17A MOV 383AB MCC 131 A3 460 ACcA 383AB AFW AFW 6A MOV 383AB r
\\j MC C-131X 3 480 ACiA 383AB CCW CCW 19473A MOV 364AB MCC-131A3 460 AC. A 383AB CCW CCW 19473A MOV 364AB MCC 131 A3 120 AC/A 383AB EP TR 113 AFMR BATRM111 MCC 131X3 480 AC. A 383AB ESW ESW 11A MOV SX1A I
MC C-131X4 120 DC/A 414 PEN RM EP INV 113 INV BATRMi t t MCC 131A5 480 AC, A 446AB PAHRS CC-16A MOV 364PENRM 1
l MCC-131 A5 480 AC. A 426AB PAHRS CC-27A MOV 364PENRM MCC-13 t Ab 400 A C. A 426AB FAHRS CS 7A MOV 364PENRM MC C-132A 1 400 AC'8 364AB CCW CCW 194738 MOV 364AB MCC-132A 1 460 AC/B 364AB CCW CCW 194738 MOV 364AB MCC 13EX1 dbo AC/B 364AB CCW CCW 94120 MOV 364AB MCC 13;Al 430 AC< B 364AB ECCS SI88070 MOV StA MCC 132A1 480 A C< B 364AB ECCS SI8924 MOV SIA MG C-132X I 120 AC/B 364A8 EP TR 112 XFMR BATRM112 MCC 132XI 400 AC/6 364A6 ESW ESW O 7 MOV 346AB
{\\,
v}
MCC 132XI 480 AC< B 364 A B ESW ESW 11B MOV Sxia
(
57 1/89
Table 3.7 2.
Partial Listing of Electrical Sources and Loads i
at Braldwood Unit 1 (Continued)
(%
\\
POWER VOLTAGE EMERG POWE R SOURCE LOAD LOAD COMP COMPONENT SOURCE LOAD GRP LOC # ?!ON SYSTEM COMPONENTID TYPE l.OCATION M;C 132A1 400 AC. B 364AB ESW ESW 134 MOV ESWPMPB MC C-132 A1 460 AC. B 364 AB ESW ES E 14 MOV E SWPM'2B l
M CC 132A1 460 AC, B 364AB ESW ESW16 MOV ESWPMPB j
l MCC 132A1 480 AC. B 364tt4 ESW ESW16 Mov ESWPMPB i
MCC 132A1 460 AC A 364AB PAHRS CS 98 MdV CSB T1CC132A2 120 DC< B 426PENRM EP 1NV 112 INV BATRM112 MCC 132A2 46V AC 6 426PENRM RC4 RC 80008 MOV AC 4
MCC-142A2 400 AC. B 426PENRM RCS RC 87016 MOV RC MCC 132A2 480 AC/B ai6PENAM RCS RC 8702B MOV AC MCC W 2A3 460 A C. B 383AB AFW AFW 178 MOV DDAFW MCC W AJ 460
'A B
383AB AFW AF W.68 MOV DDAF W MCC 13;X3 lic A C. B 363AB EP TR 114 AF MR BAT AM112 MCC 132Ai 460 AC B 426 PEN AM AF W AFW 13E MOV AFWPPTNL MCC 131A4 460 A#B 426PENRM AFW AFW-13F MOV AF WPP TNL MCC 132A4 480 AC;B 426PENRM AFW AFW 13G MOV AFWPPINL W C 132A4 460 AC B 426PENRM AFW AFW 13H MOV AFWPPTNL MCC 132A4 400 AC d 426PENRM CVCS CV 112E MOV 364PENRM MCC 132Ao 480 AC/B 426PENRM ECCS RH 87160 MOV 364PENRM MC C-13?)4 460 ACs 0 426PENRM ECCS RH 87168 MOV ab4PENRM MCG 132A4 480 AC/B 426PENRM ECCS SI-8804 B MOV SIB MCC-132A4 480 AC/B 426PENRM ECCS SI-88218 -
MOV 364PENRM MCC 132A4 460 AC B 426PENRM ECCS SI88218 MOV 364PENRM wiCC 132A4 480 ace 6 426PENRM ECCS SI8923B MOV SIB liCG-132A4 120 DC/B 426PENRM EP INV 114 lNV BATRM112 i
MCC,132A4 480 A C. B 426PENRM EP MCC-132 A4 A MCC 426PENRM MCC 1JRA4 480 AC,6 426PENRM PAHRt' CC 168 MOV 364PENRM l
1 MCC 132%4 480 AC B 426PENRM PAHRS CC-278 MOV 364PE NRM MCC 132A4 460 AC/B 426PENRM PAHRS CS 78 MOV 364PENRM MCC-132 A4 A 460 AC4 0 426PENRM ECCS SI8802B MOV 364PENRM MCC 131A4A 480 AC/B 426PENRM ECCS SI8611B MOV 364PENRM (O
d' MCC 132A4A 480 ACs B 426PENRM PAHAS CS 1B MOV 364PENRM 5S 1/89
Table 3.7 2.
Partial Listing of Electrical Sources and Loads at Braidwood Unit 1 (Continued)
{
'\\
POWER v0LTAGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION MGC 132A6 480 AC< B 426AB CVCS Si680lb MOV 364PENRM M00-231 A3 460 AC/A 383AB CCW CCW 2-9473A MOV 364AB MeC 2J2A1 400 ACiB 364AB CCW CCW 2 94738 MOV 364AB TR 111 120 ACiA BATRMill EP ACBUS 111 BUS BATRM111 i4 112 120 AC,8 BAIRM112 EP ACBUS 112 BUS BATRM112 TR 11J 120 A G, A BATRM111 cP ACBUS 113 BUS BAT AMi t t Th 114 120 AC. B BATRM112 EP ACBUS 114 BUS BAI RMI 12 IR 131X 460 AC A ESFt1 EP Bub.13tA BUS ESF11 1R-130A 480 AC. B E SF 12 EP BUS 132X BUS ESF12 1
V o
i I
V 59 1/89
l Braidwood 1 & 2 3,8 COMPONENT COOLING SYSTEM 3,8.I Svetem - Function The Component Cooling system provides cooling water to various plant components in both units during nonnal operation, and plant shutdown. After an accident,
~
the Component Cooling system acts as an intermediate system between the components being cocied and the Essential Service Water system, Separation is required to mimmize the possible release of radioactive matenal. The Component Cooling System serves to remove residual and sensible heat from the RCS during plant shutdown by cooling the RHR heat exchangers.
3,8,2 Svstem Definition motor driven pumps,ponent Cooling system is a closed loop system consisting of f The Com three heat exchangers, two surge tanks, and associated piping and valves. The system is designed to serve both units. The major heat loads in the plant can be divided into a Unit I loop and a Unit 2 loop, with each loop containing two pumps and one heat exchanger. An exception is the~RHR heat exchangers and pumps, which are cooled by a common header which may be aligned with the Component Coolmg pumps for Unit 1 or Unit 2, or isolated and supplied by the fifth pump and third heat exchanger, =
which are common to both units. These components are designated pump 0 and heat exchanger 0.
The heat exchangers transfer heat to the Essential Service Water system. The surge tanks accommodate expansion, contraction, and in leakage of water.
Simplified drawings of the Component Coo _ ling system are shown in Figures 3.8-1 and 3.8 2. These drawings show some components from Unit 2. Unit I component ids begin with "I', Unit 2 component ids begin with "2", - A summary of the data on-selected Component Cooling system components is presented in Table 3.81, 3,8,3 Svstem Oneration Three component cooling pumps, two component cooling heat exchangers, and :
the two surge tanks are sufficient for normal operation of the two units. The remaining two pumps and one heat exchanger serve as backups. Cooling water is circulated by the pumps through the shell side of the heat exchangers to the components being cooled,' then back to the pump suction. Demineralized makeup water is added into the surge tanks as needed to maintam coolant inventory. A backup source of makeup water is the primary water storage tank.
Heat loads supported by the Component Cooling system include the following:
RHR heat exchangers and pumps Spent fuel pit heat exchangers Letdown heat exchanger Excess letdown heat exchanger Positive displacement charging pump
-Component cooling is also ?rovided for additional components such as the reactor coolant pumps and components of t ie Chemical and Volume Control System.
3.8,4 Svstem Success criterin Following a LOCA, the following success criteria apply to the Component Cooling System (Ref.1):
- Following a LOCA, Unit 1 equipment is normally isolated from Unit 2 equipment. Component Cooling System equipment in the unit experiencing the LOCA is then divided into two redundant trains each consisting of one 60 1/89 4
1 4
.- l
'l
'l Braidwood I & 2:
n Component Cooling pump, one heat exchanger and half of the baf0ed surge I
tank. One Component Cooling train is adequate for establishing a safe shutdown condition.
- Essential Service water must be supplied to the Compouent Cooling heat exchanger used for post LCCA recovery.
3.8,5 Comoonent Informedan A. Component Cooling Pumps 1 A, IB,2A,28 and 0
- 1. Rated Dow: 4800 gpm @ 250 ft head (108 psid)
- 2. Rated capacity: 33% (to su 3 ply both units)
- 3. Type: horizontal centrifuga B. Component Cooling Heat Exchangers l A, IB, and 0 6
- 1. Design dutv: 40.87 x 10 Btu /hr
- 2. Type: shelland straight tube 3.S 6 Suonort Svstems and Interfaces A. Control Signals
- 1. Automatic The Component Cooling pumps are not automatically actuated.
- 2. Remote Manual The Component Cooling pumps can be actuated by remote manual means -
from the control room and from the iemote shutdown control panel.
B. Motive Power
- l. The Component Cooling motor driven pumps -and motor operated valves are Class 1E'AC loads that can be supplied from the standby _ diesel generators as described in Section 3.7.
C. Other
- 1. The Component Cooling heat exchangers are cooled by the Essential.
Service Water system.
- 2. Lubrication, ventilation, and cooling are provided locally for the Component Cooling pumps.
3.8.7 Section 3.8 References
- 1. Byron /Braidwood Final Safety Analysis Report, Section 9.2.2.
l
-61
- l/89
f'N l'mk E
)
/
s
,)
t
\\
\\,s-)
L/
+--
-- -. ~ _ _ - _
??
,,... w.
P6M4ARY WA ?t R e us.g m
a",ti
" 2-
~ "a W,_Q_g 1
_. _ _. _ _. g __ K { M -_-~ __-
.- g _ 4 g.
o g __;
,.c,r,<
r X i s.*
a cca e,e
~ ~ = -
,*c
..y,,,
s,,,,,
w.. e WA T. re 8
,M
-+ 70 At P e4 A4 S
[
s.m,uu ~4 l
Fe.PtatP ge t
ggfys,,,,
- y.,,,,
oyu...n. ofcc.,u,.
I, _s
.A u- ~
e...
._,J 9
i Xcc- -.
L, X -'
X" ' *
,_4
, -z. L m- -
u.
,,4 o
,aa., cc P,.m _
IJ 3,.
co' a m '= >
coJtsalw 2 X
s wo n a O
2.
2.*u
,,c_,__
- CR.,I.ro cce.4 c
-g_(
=a n-,A
}_1 506A m
COOT ed10PsT 2 P4A 29 $
l'EI I 1 9%t,9 2S.%A 2950 2 9 6FC 2 98474 Ccw 2 un r
em.ccwo,4 m X
X X
- Scaam cau.a.tm 2=
y I.,,:.w'.wzmh.
auu.
2,me 2 wee r-2 -mA ca< m ~r s
,= 4. u T. d re-t sb.A<
o,snx,- a y
l
"~
l
$U6EE T A,et go togy g MRWI p
St.54Gf IANK
=
un e o a r., u,, 2 x.. em.w Figure 3.8-1.
Braidwood Unit 1 & 2 Component Cooling System c
_m..
m
-.m.-
pg
\\M a
g
...A.
g
~ $UWA 7Am
- 462
,-,r ruu. y _
Mit4ARY WAff R g g454g j
p,g g,
~
CCw e e,A
, us.A i - -. 1 o i
- m...
N M
J D<1 DC-5' 4
- =; g__
D 9 Se62 9 64668 -
S 98708
{
9 u,0A 4
gg, g,,.,,
3 swee y
Ct W Pit.
I e.54 -
K e SM7C,
h f
_ f,
' S.E R.WE' E I
a--
rEn FR ud ACP SEAT 1%
+W CWCS MX5 w=r m L --
70 RCP 5f AL5 fDSIPtAr et
..M:
,u,,
CvCs =s
- 444eA
,CCw-t #4738
,CCw1u?34
, u?
%f
$ PENT FtXL h4
'ssews "*
JL,,
. CCwd.,
I a-a- -
h_._
AJ
~
d.
_i><3- ;
,w, su
. sus ;
- eso*
3 9 73 l.
im
.J CCw Po '
se n A cc,,,,,
Ccw 2 9473e l CCw 2 ursa -
Lrown Q
FRossConsopfMT +
4 "MNE
. COOLING UNrf 2 l
COOLSd3 LNT2.
A**m a e
mg F3tohs W W h 2M '
J 2 43A ' 2 94M./
2., - -,NT g-g
..2 TOCOnaPONE phea 9uup sA 2
2 uSSA ".
2-tese.
2 847C 946FA CCw s ka
- EfaOMCon@ONENT l <sma moo se r TOCOMPO8dNT COOLMUpdf 2.
29442 2 Seta
' 2 94708 - L m,o %
2 uroA.
Coots.a uNer 2 -
.,,mN u,,,,.
m
$ URGE TAM
.,ss,,,,,,,.-
-. u.a r, u.,
TO LPd' 2 SERtmCE
- SW3CE TANN.
WAM
~
1 wne om.a rw uns s a,. nm e=w Figure 3.8-2.
Braidwoon Unit 1 & 2 Component Cooling System Ebowir.'.) Ccmponent Locations C
wC mm
...a
m.
(
(J Table 3.8-1.
Braidwood Unit 1 Component Cooling System Data Summary for Selected Components COMPONENT #D.
COMP.
LDCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
TVPE LOCATION LOAD GRP
'CCVioHX HX 364AB CCW-1-9473A MOV 364AB MCC-131X3 480 383AB AC/A CCW-1-9473A MOV 364AB MCC-131X3 180 383AB AC/A CCW-1-9473B MOV 364AB MCC-132XI 480 364AB AC/B CCW-1-94738 MOV 354AB MCC-132X1 480 364AB AC/B CCW-1-HX HX 364AB CCW-2-9473A MOV 364AB MCC-231X3 480-383AB AC/A CCW-2-9473B MOV 364A8 MCC-232X1 480 364AB AC/B CGW 9412A MOV 364AB MCC-131X1 480 364PENRM AC/A CCW S4128 MOV
,$A2B MCC-132X1 480 364AB AC/B cs" CCW-P0 (ADP 364AB BUS-141 4160 ESF11' CCW-P0 MDP.
364AB BUS-142 4160 ESF12 CCW-P1A.
MDP 364AB BUS 141' 4160 ESF11 AC/A
)
364 AB.
'6U S-142.
4160' ESF12 AC/B C
I l-l l
m t..m.
_ = - - _ _
2-,-.1
._._m___._____._._____u
1 Braidwood 1 '. '
3.9 ESSENTIAL SERVICE WATER (ESW) SYSTEM 3,9,1 Svctem Function The Essential Service Water System supplies cooling water from the ultimate heat sink to various heat loads in both the primary and secondary portions of the plant. The system is designed a provide a continuous flow of cooling water to those loads which are safety related or essential to the safe shutdown of the reactor.
3.9.2 Svstem Definition The Essential Service Water System contains two headers, each supplied by a single motor driven pump. The system is designed to serve both units. The source of water -
for the system is the lake screen house essential cooling pond Strainers are provided to remove impurities from the raw water before it enters the ESW pumps, Heat is rejected to the essential cooling pond.
Simplified drawings of the ESW system are shown in Figures 3.91 and 3,9-2; These drawings show some components from Unit 2. Unit I component ids begin with "1", Unit 2 component ids begin with "2",
A summary of data on selected ESW components is presented in Table 3,9-1.
3.9,3 System Oneration Dunng normat operation, one of the ESW pumps is in continuous operation providing cooling water to essential loads. Essential loads are those required for safe shutdown, and are therefore redundant and served by the corresponding channels of the ESW system. Heat loads supponed by the ESW system include the following:
Diesel generatorcoolers Containment fan coolers Component Cooling System heat exchangers AFW, ESW, SI, and centrifugal charging pump lube oil coolers -
AFW, ESW, SI, RHR, CS, and centrifur..! and positive displacement charging --
pump cubicle coolers, The ESW also provides an assured supply of water to the Auxiliary Feedwater System. ESW header 1 A supplies the motor driven AFW pump 1 A and ESW header IB -
supplies the diesel driven AFW pump IB.
3.9,4 Sntem success Criterin Followet a LOCA the following success criteria apply to the ESW system
- One out of two ESW pumps operates supplying cooling water to essential loads.
3,9,5 Comoonent Information A.. Service Water Pumps I A and IB
- 1. Rated flow: 24,000 gpm @ 180 ft head (78 psid)-
- 2. Rated capacity: 100%
3, Type: horizontalcentrifugal B. Ultimate Heat Sink - Essential cooling pond 65 1/89
i Braidwood I & 2 3.9.6 Sunnort hstems nnd_Intrrhten A. Control Signhls
- 1. Automatic The ESW pumps are not automatically actuated.
- 2. Remote Manual The ESW pumps can be actuated by remote manual means from the control roor" and from the remot shutdown control panel.
B. Motive Power The ESW motor driven pumps and motor operated valves are Class IE AC loads that can be supplied from the standby diesel generators as described in Section 3J.
C. Other
- 1. Lubricetion, ventilation, and cooling are provided locally for the ESW pumps.
3.9.7 Section 3M References
- 1. Byron /Braidwood Final Safety An.dysis Report Section 9.2.1.
i r
(
l 66 1/89 l
v.t i
2
,2
- i) ffi 5D l
I
)r
~
s r
=
I ll
,k e
jj
-g g-
- e.1 R
0-I!
!}
n{
0%!
OX E
i..,
n is!
l (9
E!
e
!O
- ) A I
m' lij OI!
r, r
E p.
i e
i r
!-l1 d~'I}
}i 5
I OI,;
[,2L "cL i
f
~
i
{
R I
V n
it i
t
- (
15
?..
D we e
jh; OXi OX:
p
,c:
N 5
e no g
,M
--Cgo-4ga Isl 3
,i g-l-
s!
I mW s.
~nII n
VI Q
j
.e eo
>c-B B
1 5
o a
3 m
I l
E A)
Y.
ta tZz An
?
c ac s
O.3j O, i
\\
fiiltiifi 67 I/89
p) i ftt
'V l(*,
h v
i k
h-II l5 t
it
~
jg Il I
R t-y, CIrcc f'
p er
,g eIt 1
i A
e C a s$
Ol'$
I I
3 lt m
a r
+
f'*
l, e\\? E Lb i
o.
r c>I:
t.h, s,
i
.Ek Aj A
4 y
CC EU h$
fN m
ss ta u
lTjI E
2,i s :
D v
o t0 a
j e
.p g-g-s g
g d
x
(,)
h l!
,9 d'
h.
5 W
U
.pg
?I O}pa N
X E
V!
g!
v 5
3 u
p r
a 0
1 I
4 3
b tR A R I
w E
C%),j e
.9 O!
L
.m
?
\\s/
yyl 2
Il!
6S 1/89
a i aem.a ee,a4-a-a-.--
al_.m44J._-4_.4, Aa4.
aaW-.o.i-,..a..
J
.-.,_.4.L_-t.aS amm.Aaem a
,4..-e as.
-m1mm-
.m aa s.
.4-h>-
w
&-.m-.m
--v-..-
n-, - - - - -
1 7
e 1
i l'!
!!i t
t E
,l,! l=>;u i
3 3
-+
- n
_.L i
i a
I li O'
N
~
-er C
I hH O{'
0 0
l
'Q t
w 8
r b,t6 A
1 d
c h, _!
j I
f I'
I"'
h fa li ti I
i
- . L Ecf 8
t g
4 1
te
'l, 4 oI!
Y c_
u e
1 v
h.
f f
o$.i
, of:
t [.!1,,
i g
. +.E i
a t
g g
g 5
i a
l[lI i
r l
=
3 g *s S
=
.e g
Oh h
3 I
l
[
r E
'g.
-,g
d n
4 l
e 4
w a
M
.f i
i i
o t,-
O a
R E
t
~
E i
i v
a e
a c
\\
Ej R
\\
.E !
l a
.Jl[
69 ljsg
~
m fi li
{
I l
oX
+
_S.
f'"
_ g e,s.s-.m,...
op.,,
.m
. s..
S,,, orm.
- ms o
[r oy,.
n
... w e sc =,. c -
l f,
- 'SE ' "'*a' gX,s 01,..
,,a o
+
T i_ M._-
s-.m,,,,.
I m s. ~.
2 cx w
M Ata.3 wC s 'a 'p'
(""'
i....
g l
l n s..
l I
I o
o
.H.,7._ H. __-
- m. s,.t
. ue o
..n 2o,
- 3. c.o t= s...m 3
cm =
r.coote s cc actt cmans )
cci
. g o.
p H.9 i
.c t
%+
t-f3B
_T 3 -.
...1..-
a o.
.attctmactgc m.t
,O oTME4.
.rg a ' "" ',"Ac5
-- c.. w._
er;
.... i c- -
i
= =~"
C 1
Figure 3.9-2. Braidwood Units 1 & 2 Essential Service Water System Showing Component Locatior- 'Page 2 of 2)
_- - _ _ - -.. _ _ -.. -. -._~_
I 1
r i.
t
.{
Table 3.9-1.
Braidwood Unit 1 Essential Service Water System Data Summary
{
for Selected Components f
t I
COMPONENT ID COMP.
LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
I TYPE LOCATION LOAD GHP ESW-0-7 MOV 346AB MCC-132X1 480 364AB AC/B ESW-1 -1 A MOV SX1A.
MCC-131X3 480 383AB AC/A ESW-1-1 B MOV SX1B MCC-132X1 480 364AB AC/B
[
ESW-1-33 MOV ESWPMPA MCC-131X1 480 364PENRM AC/A L
ESW-1-33 MOV ESWPMPA MCC-131X1 480 364PENRM AC/A ESW-1-34 MOV ESWPMPB MCC-132X1 480 364AB AC/B ESW-1-34 MOV ESWPMPB MCC-132X1 480 364AB ACIO ESW-1 MOV ESWPMPA MCC-131X1 480 364PENRM AC/A ESW-1-4 MOV.
ESWPMPA MCC-131X1 480 364PENRM AC/A E
i ESW-1-5 MO'/
ESWPMPB MCC-132X1 480 364AB AC/3 j
ESW-1-5 MOV ESWPMPB MCC-132X1 480 364AB AC/B i
ESW-1-7 MOV 346AB MCC-131X1 480 364PENRM AQA f
ESW-P1 A.
MDP.
ESWPMPA BUS-141 4160 ESF11 A2A
[
ESW-P1B MDP ESWPMPB BUS-142 4160 ESF12 AC/B I
t i
i 6
E c
t i
I t
i i
)
d Braidwood I & 2 4.
PLANT INFORMATION L
4.1 SITE AND BUILDING
SUMMARY
The Braidwood Station Units I and 2,is located in northern Illinois,2 miles south of the town of Braidwood and 50 miles southwest of Chicago. The site is in the southwest corner of Will County in a predominately agricultural area. The site occupies approximately 4320 acres of land. Figure 41 is a general view of the plant and vicinity (from Rcf.1).
The major structures at this unit include the two containment buildings, a shared turbine building, a shared auxiliary building, and a shared fuel building. A site plot plan is shown in Figure 4 2. Plant section drawings are shown in Figures 4 3 and 4 4 Each containment structure is a reinforced concrete cylinder with a steel liner.
The containment contains the reactor vessel, reactor coolant pumps, steam genemtors, and pressurizer. Pumps, piping, and valving for the reactor coolant system is completely contained within the conta;nment structure. Access to the building is via an equipment-hatch or a personnel hatch. Piping and electrical penetration areas are on various levels of the auxiliary building.
The turbine building, located west of the containments, houses the turbine generator and the associated power generating auxiliaries.
The auxiliary building is located to the west of and between the containments and contains much of the plant's safety related equipment, specifically the auxiliary -
feedwater pumps, high pressure injection containment spray pumps, charging pumps, pumps, RHR pumps and heat exchan component cooling water pumps and heat t
exchangers, and motor control centers supplying power to safety system components.
The fuel building is between the two containments and houses the spent fuel pool.
4,2 FACILITY LAYOUT DRAWINGS l
Figures 4 5 throu ;h:411 are simplified building layout -drawings for Braidwood. Details of the turaine building and many of the outlying buildings are not shown on these drawings. Major rooms, stairways, elevators, and doorways are shown in i
the simplified layout drawings, however, many interior walls have been omitted for clarity.
Labels printed in uppercase correspond to the location codes listed in Table 4 1 and used m..
i the component data listings and system drawings in Section 3. Some additionallabels are included for information and are printed in lowercase type.
A listing of components by location is presented in Table 4 2. Components included in Table 4 2 are those found In the system data tables in Section 3, therefore this table is only a partial listing of the componensand equipment that are located in a particular room or area of the plantc 4.3 SECTION 4 REFERENCES
I 72
- 1/89 t
-,u -
- )
~
hr s
\\
T 6\\
'u b
e e,,
Nil,/
N-e
,gl)k y (sS,
\\'
o m
F h',, ol 3
6w+
) k\\.
.h"\\
9 8
2 r,v a s
e
.s j
\\ a~. a g w \\ d,i
,g i
o
)
. t e
3,
.m-
. o, s n i
l y!,;
k.
'k h,, /'
..\\
h (}
E
\\
l N
\\\\ \\ >,A) \\ s u
t tt
'.t ;
e i
i(,
Q c
\\;s
- 3 c
s Iy
.o s-O
,',i s
y
,)
s a
,dtt i
t 3,
e e
s s
e a
p \\h,-
4 o.
Y,
's oI W
gtg{
p s
%q',i k.
wj i o
jg' w
4 o
i o
t h-5 o
h l. '
", e,
<<sl
\\ ',
R St
\\
f g <..;4 R
sS}3'
,i
,V ifg 1
\\,*j"?df,h p. i t e
n s i
oj%
l l,.
CD
\\' i pn g o P
g
,i
(.,,
f }, h, ;
ft>
8
{
g I
l (1
\\
ob s 5; e
/
l.
9 g'
%p L.jb))lt..'s' e/
j.
I s
e jh 9
0 l
l Is t
p 's c,i!. ;
w:,. :)
s g
[$3
/
?
4 k
8 q y.;e h,$
\\
Y
.?
=
s Y
i ;\\ : p,.,
g ort v &. y p\\, h y
i a
n :
y:
\\
('
\\
a s.
i e
v i
1 73 1/8_9:-
t i
~ -,
. _ -. ~...
....,... _. -., +., ~.,
l
[
?
k CALLED 3-15 KV Smtchyard 1
Unit tio,1 & 2 tiOHTil
]'
A i
m
?
-- +
x x
x Sidog Gate Y
v
^
I
):
MH:!!!!! !!!"!!!!!!Hf HHHilH WHHHHmmHHimmHmmHHHHHmmmmmHmW f
v v
x y
-(
e a
a l
?:
1 Refueling Water Heactor i
Storage Tanks Containment 2C X
Bu;1 ding Fucillardthng Reactor x
Unit tJo.1 RWST Buildiry Containment Ut 2
x
/
noua
- c v
v x
x a
Radaaste &
Clean Up Service X
l I'
& TSC Building Building Unis 1 & 2 I
Auxiliary Building
\\
I x
?
Demineralizer A
[
. l Unit 1 l
l Unit 2 [:
p Permanent
"" y Building - N x
Turbine Room Gate House
' c
[
l Heater Bay I
4 P
Slidi"9 rw I-Instrumentation L.I ' Gate FuelOil p gg g9 Storage CST Tank Prrnary l
WaterStorage
(
[
1-3t Receiving Receiving Training l
EE Condensate TarAs h
Settling EE Storage Tanks Building -
- Building Fac&ty j
Building Pond Warehouse
)
x x
x X
x-X X
X X'
Figure 4-2. Braidwood 1 & 2 Plot Plan 1
I
2aj
.e-,6-.41-.J.-
u----44*>a.1mmadL.a4--a--1MJ-h---*+>-h 4.
m 4
-alA-awe %1
-s.S J
- e. mees.e-A 4-Ma.u--
-+4, e
iamde m-u aae
- mm m.,_-5..r*
+.
we,a A-e
- mmi-.Es-wm-m
.--4 n
I;!!
3 e
b 9
l, m
I, i
- .i cl.
!l i
_'j(( ~,
C n
p d.
CD I
3thii l' h 4
R P.'li l'i' l
': 1 j '
g a
i I
J
._.d.4. Ofp4*s.)'.g ' '
,E,
.. p ' l -'
..e.
t
. - ~*
=.
- [.
b,
"!1 -[. t} +
e 1
e
, d.-
. - ~.r,.~< ~~ ~!.Tl P '
i a
i j;
g l
e
. v_.
r
- a.
.. -,,; ;- - =_
s - yp-J.
ai 1_:..
,p +I.
9t __
si L.u
,I y;
,,,..di ;.
. I r __.
i i
l;. l
.-n
. o,......~ _. -.. g..,.u., i.3'rg*
3 J.
- u. r
.s
-.a._,,)
p
\\
- O ',, b. N (g-
~~f
'5 t
y
- t b llI I j th, h, 4 f I, f 3.,l!
\\
d g
w
_q P...i.
,r-.-
m,p;j p
,. 7
,+
H,l: it
.d r
- ill!!i., f
!j o.
9 m
a.
m
[
- "N*,. l 2. ' ' ' ')
fp_y g
'g 8*
_.,p. p. j; g-mtg 4
m o
. -., j ll il..
.~ igj
'. _ - * '.,., #,, i,{
c,'
,i i
M 1 i. 4..
O; @ l; liii 0.
s= :.
,. g:.
O x
...g.
3;: (
3 a
D
- 6. ga r
ti r..
t*y bi i
r ii i
'n A
b
~4
!,j'"y.v g@,,, -
.=m wa~. ~ _k,. l {1 rs
-*=
j j
- g 3,.,
o j! - k O' l(i "g"'
i i
a N
i ::W h
! m. J. v.i, N..e. n.,l 14 k.i, i i
..w.
i e
4
- -i Hy.
f tware.=*eq g
or -
+.
I pp 'L-.kf*[' h3d,l,;&-.h.'t.
, '5 > !
92 % i?
- E I
- i !
. g. Il.. !
'W"
,lgt.
p i, c.i i
. m 4
t g
=
-w r. =wvw 0
- g-- -icG
'f p;;,m. 4,;"u!E 4%11'
... _.. _-_.._-__. L.i.! M.ya ei j i,.e I q s
i h
g
_ " i...
is_
k.__._..._ _ _ L. IN pau', (
co i
1 _ p f' b
'.o L
s a 'q, njh n 4
i 4i c l
2 e;-
--..~,r-1 g
h h hj.lj( {;Ii h];
! I l
LT.
=
l a
s 1 (
U 'll!
t L.j L[
t; Lj tl 75 1/J9
. w.. -
.-. u
.Mt.,
4
!! j 93 N
4;JI{it,
44.
s I l';..t U,a' t,,n __j c
z en g.
.c
,n, y
. %vTvw l
.v.;
E r
u
+
g
.a lt
-- ~---
.- lj i 9
y O
l,-
...., ll aJ, a
e 1-e
.9 ii l.*
m.~.e - ] b.: - r !..y. _.. [ li li 1@
ii ue j :' 6 y
a.t p
n,..-----.-
gg..__.f.i s y,y w-,r--
li
- -)}==;_. m; e
-c.!
g, i,.
s
..%.[&
cn
.I 1.J n 0 ' f- 'r: IYp.,R j
)
I..
3 ", = w s-~d;ap t
q4 1; ;
=,
5 y
- 1, l
\\\\
i
't...
. 1..,lsia m
.yi -1:p(3 Q,
At i il 4 tn
_J s
,c
,,,n m-
. e
,/ -
,4.wrf.'d'.**~{d""*"Oj, [\\,j P-
~~
p' 4 '
E
- Cl
~
p d
1 e
. Il E
> l.
g' iWa -.
. m..
77 11 C
- 1. i 4..
m
-g 1
..-n
- bs.__. r u,- -
1 ih;-wY.-g,:sY 1!
o il i
d 8
(V 44'L---p.ac g g %;dT M L 5 u.
i
- 1. ' 8 idair :
):
E d.
7]l 4 [j)'~p I m
h
.8 m
t-1%;i!
.jp._%l.a @M r-W Piir' '
g
! i f. :'I /-
.i m
- ar_ I! - th, b.J,j 1,
'i3 r---
t t
x v.
j m
2,.
_ _.l.i o]Ij!
._ e = _ d.; f L IL).'M ~N au l -
i'
,h.-n
%['J![4ldjl11!d
}
' :~24.-see m.~ll 4
!!!i, inP
- /
j.
1, J
..... q 3;e i em T1-L l) b l:7 d,j, E
d'
'I a
n!
j Lt-NL:. :;.wa G
T we-jH am L r
~
1 m
liti I
N
!.; g p:.i il i
73 -'-) _q l !
%y.,...
. t e
-- l li f,
,f r 1
n
.w.-. - c a. 4. #
c w._... _
\\
- 1.,
+
n:., li (,m.
e i..
- 6. 1, i k 7,_.. " E T(
j m
..u.,.. e -
3,
,{
i g 3)
K
- .i.:
!_ w,a
.: : r L.Q~. 3"
- )l,
9 i'
s m
e tel E
i s
a en.
t ;;
g,Q. O g
A I
I I li
,b
- ~,
g j!i t; Ii L:
L:
L;.
Li Q Li 76 1/89
. \\1 1
i f
r.
i t
CALLED
[
i
(
NO RTil k
i A
+
i t
i i
r i
1 A
d ESWPMPA ESWPMPB i
n i
t.
s 4
I i-I 4
1 py
() u i
u j'
I III III j
=
l i
1 i
t i
I l
1:
l t
g i
1 1
l I
f; l
Figure 4-5. Braidwood 1 & 2 Station Arrangement, Elevation 330*
I
{-
of the Auxiliary Building l
l :.
4 i
E
-._._.__.-._.--.--1.-
O O
O
.}
CAI I.f D tlOttfle i.
4
{'
RHRB CSB
-O-1-
i HC CSA i
(
4 L
T i,
tRA 1
e
-C
}'
i t
346PENRM 346AB O
o w
i i
cc ud M
E I-i o-9 M
M-i i
l i
I
.i 4
j M
l t
o-
[
Figure 4-6. Braidwood 1 & 2 Station Arrangement, Elevation 346' i
i m
m
O O
O CALLED FlOH tit CVDp o --o-[
sis o-o-AFWPPTNL RHRHXB under STMTNL RC N
b ik S
CVA u
-c Ou 364PENRM
\\
~
StA l RHRHXA a'
f
- f. 3 g ho nat O OF i oo Te J-5.o.
Figure 4-7. Braidwood 1 & 2 Station Arrangement, Elevation 364'
O O
O F
i
(
CALLEO l
NORTH RWSTTNL q
~
[
3 E
t l
)
RHRHXB i
Pipe Tunnet.
RC I
N f
a a
I b
{
364PENRM j
RHRHXA i
m 383AB "d
Eb I
I I
cN 4
-c asce I
aL ai g-
/
]
9
_o_c
/
t
~-
I DGBFUEL DDAFW WN I
driven pump
[
3
{
DGAFUEL
[
I l
/
c
- 8 i
Figure 4-8. Braidwood 1 & 2 Station Arrangement, Elevation 383*
1 r
+
..= -
.. -, 1
O O
O C A tt.E D NORT11 i
i Fuct liarvfing Building i
(
i ac 1
i i
401AB b
M O
b o
=
2 I
Ed DGB DGA
.OC.
O.
p IBri Ibb h--
Em
___c c
i e
o__
4 i..
l
,t 2
o Figure 4-9. Braidwood 1 & 2 Station Arrangement, Elevation 401' i
I' l
3 i
i
- * ~ " '
O O
O CALLED nonm L amsp 4
i TLSF f
t ac l
l
-(
o-c6 i
13 4-o-
1 426 PEN N
% Volume f
controi
-C O
C O---
426AB v o G @
ESF12 '-
ESF11 6
v 7
O Itm Sgmi v
v o--
v m
- t
[Pf 1
Figure 4-10. Braidwood 1 & 2 Station Arrangement, Elevation 426'
_.-._ _: L
__.____..__.:n_
I!ll!!) ! i iI1I!!!
ij -
,'fs 1I:, !
O nV Dtl ELu o
F L O '
AC N c
nv 15 o-4n o
k k
itave lE t
b v
n e
m f
o_
e o
gnarr A
n O
Mn_n o
1 i
ta R
t C
S 2
1 d
f>
Q_ "
o
[
o c
w R
d E
i E
a A
r
, /
. 0 1
B o
Oj 1-c 4
-Q1 g
e a
2 1
r i
i 1
m oM u
a R0 g
t i
T T
A A
F l
c c
O 5='
Table 41, Definition of Braldwood 1 Building and t
Location Codes Cod (s Descrintlems 1.
346AB 346' elevation of the Auxiliary Building 2.
346PENRh1 Penetration Area, located on the 346' elevation of the Auxiliary Building 3.
3MAB 346' elevation of the Auxiliary Building 4
364PENRN1 Penetration Area, located on the 364' elevation of the Auxiliary Building l
S.
383AB 383' elevation of the Auxiliary Building 6.
401AB 401' elevation of the Auxiliary Building 414PENRhl Penetration Area, located on the 414'of the Auxiliary Building S.
426AB 426' elevation of the Auxiliary Building 9.
426PENRhl Penetration Area, located on the 426'of the Auxiliary Building b
- 10. AEER Auxiliary Electric Equipment Room, located on the 451' i O elevation of the Auxiliary Building
- 11. AFWPPTNL Auxiliary Feedwater Pipe Tunnel under hiain Steam Tunnel
- 12. BATRht!11 111 Battery Room, located on the 451' elevation of the Auxiliary Building
- 13. B ATRh1112 112 Battery Room, located on the 451' elevation of the Auxiliary Building
- 14. CR Control Room, located on the 451' elevation of the Auxiliary Building
- 15. CSA Core Spray Pump A Room, located on the 346' elevation of the Auxiliary Building
- 16. CSB Core Spray Pump B Room, located on the 346' elevation of the Auxiliary Building
- 17. CST Condensate Storage Tank
't
- 18. CVA Centrifugal Charging Pump A Room, located on the 364' elevation of the Auxiliary Building p
- 19. CVB Centrifugal Charging Pump B Room, located on the 364'
(
elevation of the Auxiliary Building 84 1/89
1 i
Table 41.
Definition of Braldwood 1 Building and Location Codes (Continued)
Codei Descriotions
- 20. DDAlw Diesel Driven Auxille.ry Feedwater Pump Room, located on the 3S' elevation of the Auxiliary Building
- 21. DGA Diesel Generator l A Room, located on the 401' elevation of the Auxiliary Building
- 22. DGAIUEL Diesel Generator I A Fuel Storage Room, located on the 383' elevation of the Auxiliary Building
- 23. DGB Diesel Generator iB Room, located on the 401' elevation of the Auxihary Building
- 21. DGBFUEL Diesel Generator IB Fuel Storage Room, located on the 383' elevation of the Auxiliary Building
- 25. ESFil Division 11 ESF Switchgear Room, located on the 426' elevation of the Auxiliary Building
- 26. ESF12 Division 12 ESF Switchgear Room, located on the 426'
\\,
elevation of the Auxiliary Building
- 27. ESWPMPA Emergency Service Water A Pump Room, located on the 330' elevation of the Auxiliary Building
- 28. ESWPMPB Emergency Service Water B Pump Room, located on the 330' elevauon of the Auxihary Building
- 29. LOCSR Residual lleat Removal System "A" Pump Room, located in the Auxiliary Building on the 93' elevation east side of the Reactor Containment Building
- 30. RC Reactor Containment Building i
31, RHRA RHR Pump A Room, located on the 346' elevation of the Auxiliary Building
- 32. RilRB-RHR Pump B Room, located on the 346' elevation of the Auxiliary Building
- 33. RHRHXA RHR Heat Exchanger A Room, located on the 364' elevation of the Auuliary Buildmg
- 34. RHRHXB RHR Heat Exchanger B Room, located aon the 364' elevation of the Auxiliary Building
- 35. RWST Refueling Water Storage Tank S5 1/S9 p
c--
e-e~r----
w--,--
-m e,.
a nve w
-- - -r-
>t Table 41, Definition of Braldwood 1 Bullding and Location Codes (Continued) f;tu[n Descriotions
- 30. RWS*ITNL Tunnel from RWST. located on the 364' elevation of the Auxiliary Building
- 37. RSCP Remote Shutdown Control Panel, located on the 383' elevation of the Auxiliary Building
- 38. SIA Safety injection Pump A Room, located on the 364' elevation of the Auxiliary Building
- 39. SlB Safety injection Pump B Room, located on the 364' elevation of the Auxiliary Building
- 40. ST51TNL hiain Steam Tunnel, locatec on the 364 elevation outboard side of Containment
- 41. SX1A Pit containing ESW Valve IS001 A located on the 330' elevation of the Auxiliary Building
- 42. SX1B Pit containing ESW Valve 1S001B, located on the 330' s
elevation of the Auxiliary Building
- 43. SXCTA Emergency Service Water A Cooling Tower
- 44. SXCTASG Switchgear Room for the ESW A Cooling Tower
- 45. TB Turbine Building
- 46. TLSF Spent fuel pool operating floor, located on the 426' elevation of the Fuel Building
- 47. UPCSR Upper Cable Spreading Room, located on the 467' of the Auxilituy Building o
86 1/89 I
Table 4 2-Partial Listing of Components by Location at Braidwood Unit 1 LOCAIION SYSTEM COMPONEN T ID COMT TYPE 34bAB E5W ESW 17 MOV 34bAB ESW ESW 0 7 MOV 364AB CCW CCW 19473A MOV 364AB CCW CCW 19473A MOV 364AB CCW CCW 194738 MOV 364AD CCW CCW 194738 MOV 364AB CCW CCW 2 9473A MOV 364AB CCW CCW 2 94738 MOV 364AB CCW CCW P0 MDP 364AB CCW CCW PIA MDP 364AB CCW CCW P1B MDP 3b4AB CCW CCW 9412A MOV 364AB CCW CCW 9412B MOV 364AB CCW CCW 0 HX HX 364AB CCW CCW 1 HX HX 364AB CCW CCW PO MDP 364AB EP MCC 132X1 MCC 364PENRM CVCS CV 112D MOV 364PENRM CVCS CV 112E MOV 364PENRM
, CVCS Sb8801 A.
MOV 364PENRM CVCS SI8801B MOV 364PENRM ECCS RH 8716A MOV 364PENRM ECCS' RH 8716A MOV-364PENRM ECCS CV 8804A MOV 364PENRM ECCS SI8811A MOV 364PENRM ECCS RH 8716B MOV 364PENRM ECCS RH 87168 MOV 364PENRM ECCS C; 00H S MOV 364PENRM ECCS Sb8821A MOV 364PENRM ECCS SI 8821 A MOV 364PENRM-ECCS 318821B MOV S7 1/89
i Table 4 2.
Partial Listing of Components by Location at Braidwood Unit 1 (Continued) l
\\
[
LOCAT ION SYSTEM COMPONENT ID COMP TYPE 304PENRM ECCS SI66210 MOV I
364PENRM ECCS SI8835 MOV 3b4PENRM ECCS SI8802A MOV 364PENRM ECCS SI 68028 MOV 364PENRM EP MCC 131X1 MCC 364PENRM EP MCC 131X1 A MCC 364PENRM PAHRS CC 16A MOV 364PENRM PAHRS CC 27A MOV 364PENRM PAHRS CC 160 MOV 364PENRM PAHRS CC 278 MOV l
364PENRM PAHRS CS 1 A MOV 364PENRM PAHRS CS 7A MOV 364PENRM PAHRS CS 1B MOV 364FENRM PAHRS CS 78 MCV i
t 363AB AFW AFW P1 A MDP 363AB AFW AFW 17A MOV 363AB AFW AFW 6A MOV 383AB EP MCC 131X3 MCC 383AB EP MCC 132X3 MCC 414PENRM EP MCC 131X2 MCC 4
414 PEN RM EP MCC 131X4 MCC 426AB EP MCC 131X5 MCC 426AB EP MCC 132X5 MCC 426PENRM EP MCC 132X2 MCC 426PENRM EP MCC 132X4 MCC t
426PENRM EP MCC 132X4A MCC AFWPPTNL AFW AFW 13E MOV AFWPPTNL AFW AFW 13F MOV AFWPPTNL AFW AFW 13G MOV AFWPPINL AFW AFW 10H MOV AFWPPINL AFW AFW 13A MOV 88 I/89
Tablo 4 2.
Partial Listing of Components by Location at Braidwood Unit 1 (Continued)
LOCATION SYST EM COMPONENT :D COMP TYPE AFWPPINL AF W AFW 13B MOV AFWPPINL AFW AFW 130 MOV AFWPPINL AFW AFW 130 MOV BAIRM111 EP DCBUS 111 BUS BATRM111 EP BC 111 BC BATRM111 EP BT 111 BATT-l BAlRM111 EP DCBUS 111 BUS BATRM111 EP TR 111 XFMR 1
BATRM111 EP TR 1VJ XFMR BAT RM111 EP INV 111 INV BATRM111 iD-INV 111 (NV BAT RM 111 EP INV 113 IN V BAT RM111 EP INV 113 INV BATRM111 EP ACBUS 111 BUS I
BATRM111 EP ACBUS 111 BUS t
BATRM111 EP ACBUS 113 BUS BAT RM111 EP ACBUS 113 BUS BAT RM112 EP DCBUS 112 BUS BATRM112 EP BC 112 BC BATRM112 EP BT 112 BATT BATRM112 EP DCSUS 112 BUS BATRM112 EP TR 112 XFMR BAT RM112 EP-T R 114 XFMR BATRM112 EP INV 112 INV BAT RM112 EP INV 112 (NV 1
BATRM112 EP INV 114 iSV BATRM112 F.P INV 114 INV BATRM112 EP ACBUS 112 BUS BAT RM112 EP ACBUS 112 BUS BAT RM112 EP ACBUS 114 BUS
(
BAT RM112 EP ACBUS 114 BUS 89 1/S9
+
-+r+-
.-+rve e-~-
"w-=
--"n fw-*
--Tw-r--4'
Tablo 4 2. Partial Listing of Components by Location at Braldwood Unit 1 (Continued)
LOCAllON SYST E M COMPONENT ID COMP TYPE CSA PAHRS CS P1 A MDP CSA PAHRS CS 9A MOV CSB PAHRS CS P1B MDP CSB PAHRS CS 98 MOV CSl AFW AFW CST TANK CVA CVCS CV P1A MDP CVB CVCS CV P1B MDP DDAF W AFW AFW PIB DDP DDAF W AFW AFW 178 MOV DDAFW AFW AFW bD MOV DGA EP DG 1 A DG DGB EP DG 10 DG ESF11 EP BUS 141 BUS ESF11 EP BUS 131X BUS ESF11 EP TR 131X XFMR ESF11 EP CB 1 A CB ESF12 EP BUS 142 BUS ESF12 EP BUS 132X BUS ESF12 EP TR 132X XFMR ESF12 EP CB 's CB
~ESWPMPA ESW ESW 133 MOV T5WPMPA ESW ESW 133 MOV ESWPMPA ESW ESW 14 MOV ESWPMPA ESW ESW 14 MOV ESWPMPA ESW ESW P1 A MDP ESWPMPB ESW ESW 134 MOV ESWPMPB ESW ESW 134 MOV ESWPMPB ESW ESW 15 MOV ESWPMPB-ESW E Sn'e1 5 MOV ESWPMPB ESW ESW P1B MDP RC AFW SG 1 A SG i
90 1/S9
Tablo 4 2. Partial Listing of Components by Location at Braldwood Unit 1 (Continued)
O LOCATION SYSTEM COMPONENT ID COMP TYPE RC AF W SG 1B SG RC AFW
, SEiG SG RC AFW SG.1 D SG RC ECCS SGMP A SUMP RC ECOS SUMPB bump RC PAHRS CC FANA AQU RC PAHRS CC FANC ACU RC PAHRS CC FANS ACU RC PAHRS CC FAND ACV RC RCS RCS VESSEL RV RC RCS RC 455A NV RC RCS RC 456 NV RC RCS RC 8000A MOV j
RC RCS RC 87010 MOV RC RCS RC 8702A MOV RC RCS RC 87028 1MOV RC RCS RC 8001a MF 77 RCS RC 8002A MOV i
TC~~
RCS RC 8001B MOV RC RCS RC 8002B
'MOV RC RCS RC 8001C MOV RC RCS RC 8002C MOV RC RC3 RC 8001D MOV RC RCS RC 8002D MC RHRA ECCS RH P1A MDP RHRB ECCS RH P1B MF RHRHXA ECCS RH HX1A HX RHRHxB ECCS RH HX1B
'HX C
(
RWST OvCS St RWSI TANK-s 91
!!89-
. _ _ ~
Table 4 2.
Partial Llo(Ing of Components by Location 4
at Braldwood Unit 1 (Continued)
LOCAliON SYSTEM COMPONENT ID'CQMP jTYPE RWST ECCS SI RWST
,f TANK j
SIA ECCS Sbb92NA MOV k SI A ECCS SIP 1A MDP~
[
SLA ECCS SI58570 MOV~
SIA ECCS 618924 MOV stb ECCS Sb6804B MOV stb IZCS SI8600 MOV 3
[3Id ECC ISIPIB MDP TRT ESw eswii.1 A MOV TRIB ESW E SW.i.18
,l F l
-1 o
a n
a i
l 2
F4 4
92 1/39 1
Braidwood I & 2 5,
IllllLIOGRAl'IlY FOR IiRAIDWOOD 1 AND 2 L
1, UREC.75/023. " Safety Evaluation Report on Byron :itation, Units 1 and
. and "he Braidwood Station, Units 1 and 2," U5NRU. April 1975.
- 2. NUN,010')2, " Safety Evaluation Report Related to the Operation of Braidu d Liation, Units I and 2 " USNRC, November 1963.
3 NUREG 026 " Draft Envire, mental Statement Related to the Operation of Braldwo0<. Stuion, Units 1 and 2," USNRC, December 1983,
- . NURE( ~, 176, fechnical Specifications for Braidwood Station, Units 1 and 2,* l iNRC.
- 5. Wungblood, R. and Papazoglou, l.A, " Review of the Byroct vMwood Units 1 and 2 Auxiliary Feedwater System Reliability Ami' sis,"
NUREG/CR 3096, Brookhaven National Laboratory, Novembei f N:.
i h
w 1
j l
R6A
Braidwood 1-& 2 APPENDIX A-DEFINITION OF SYM110LS USED IN TIIE SYSTEM AND LAYOUT DRAWINGS A 1.
SYSTEM DRAWINGS i
A 1.1 Fluid - System Drawings The simplified system drawings are accurate representations of the major flow paths i in a system and the important interfaces with other fluid systems._ As a general rule, small -
fluid lines that are not essential to the basic operation of the s dzawings. Lines of this type include instrumentation lines,ystem are not shown in these vent lines, drain lines, and :
other lines that are less than 1/3 the diameter of the conneceng major flow path. There.
usually are two versions of eacn fluid system drawingt a simpified system drawing, and a a
comparable drawing showing component locations. The drawing conventions used in the
~
fluid system drawings are the following:
Flow generally is left to right.
Water sources are located on the left and water " users" (i.e., heat loa'ds) or discharge paths ue located on the right.
One exception is the return flow path in closed loop systems which is tight to left, Another exception is the Reactor Coolant System (RCS) drawing which is "vessebeentered", with the primary loops on both sides of the vessel.
Horizontal lines always dominate and break vertical lines.
O Component symbols used in the fluid system drawings are defined in Figare-A 1.
Most valve and pump symbols are designed to allow the reader to-distinguish among sim,ilar components based on their; support system requirements (i.e., electric power for a motor or solenoid, steam to drive a:
turbine, pneumatic or hydraulic source for valve operation, etc.)
- Valve. symbols allow the reader to d.istinguish among valves that allow flow -
~
in either direction, check (non return) valves, and valves that perform an overpressure protection function. No attempt has been made to define the-specific type cf valve (i.es, as a globe, gate, butterfly, or other specific type of valve).
Pump symbols distinguish between centrifugal and positive displacement pumps and between types of pump drives (i.e., motor, turbine, or engine);
Locations are identified in terms of plant location codes defined in Section 4 of-
~ his Sourcebook.
t Location is indicated by shaded " zones" that are not intended to represent the attual room geoinetry.
Locations of discrete components represent the actual physical location of the component.
Piping locations between discrete components represent the plant areas hrough which the piping passes-(i.e.Lincluding pipe tunnels and t
underground pipe runs).
Component locations that are not known are indicated by placing the components in an unshaded (white) zone.
(
The primary flow path in the system is highlighted (! - Sold white line) in-the location version of the fluid system drawings.
94 1/89
u i
Braidwood 1 & 2 A 1,2 Electrical System Drawings The electric power system drawings focus on the Class lE portions of the plant's electric power system. Separate drawings are provided for the AC and DC portions of the Class lE system. There often are two versions of each electrical system drawing; a simplified system drawing, and a comparable drawing showing component locations. The drawing conventions used in the electrical system drawings are the following Flow generally is top to bottom In the AC power drawings, the interface with the switchyard and/or offsite grid is shown at the top of the drawing.
In the DC power drawings, the batteries and the interface with the AC power system are shown at the top of the diawing.
Vertical lines dominate and break horizontal lines.
Component symbols used in the electrical system drawings are defined in Figure A 2.
Locations are identified in terms of plant location codes defined in Section 4 of this Sourcebook.
Locations are indicated by shaded " zones" that are not intended to represent the actual room geometry.
Locations of discrete components represent the actual physical location of the component.
The electrical connections (i.e., cable runs) between discrete components, as shown on the electrical system drawings, DO NOT tepresent the actual cable routing in the plant.
Q Component locations that are not known are indicated by placing the discrete components in an unshaded (white) zone.
A2, SITE AND LAYOUT DRAWINGS A2.1 Site Drawings site plan showing the arrangement of the major buildings, tanks, a site. The general view of the reactor site is obtained from ORNL-NSIC 55 (Ref.1). The site drawings are ap aroximately to scale, but should not be used to estimate distances on the site. As built sea e drawings should be consulted for this purpose.
Labels printed in bold uppercase correspond to the locanon codes defined in Section 4 and used in the component data listings and system drawings in Section 3. Some additional labels are included for information and are printed in lowercase type.
A2.2 Layout Drawings Simplified building layout drawings are developed for the portions of the plant that
- contain components and systems that are described in Section 3 of this Sourcebook.
Generally, the following buildings are included: reactor building, auxiliary building, fuel building, diesel building, and the intake structure or pumphouse. Layout drawings generally are not developed for other buildings.
Symbols used in the simplified layout drawings are defined in Figure A 3. Major rooms, stairways. elevators, 'nd doorways are shown in the simplified layout drawings however, many interior walls have been omitted for clarity. The building layout drawings t
,(
95 U89 i
I
Braidwood I & 2 are approximately to scale, should not be used to estimate room size or distances. As built t
scale drawings for should be consulted his purpose.
Labels printed in uppercase bolded also correspond to the location codes defined in Section 4 and used in the component data listings and system drawings in Section 3. Some additional labels are included for information and are prin'ed in lowercase type.
A3, APPENDIX A REFERENCES 1.
Heddleson, F. A., " Design Data and Safety Features of Commercial Nuclear -
Power Plants." ORNL NSIC-55, Volumes 1 to 4, Oak Ridge National Laboratory, Nuclear Safety Information Center, December 1973 (Vol.1),
January 1972 (Vol. 2), April 1974 (Vol. 3), and March 1975 (Vol. 4)
O Q)
(O
' g 1/89
}
O, f\\ j\\
MANUAL V AlvE XV
_ (O P E N 'C L OS E D)
L
{_
MANUAL NON RE TUP'd 4
VALVE
- XCV (OPEN ClottD) s O
O MC?OR CPF9 ATED VALVE MOV MOTOR OPER ATED
~>' /
~
~ ( O P E N C t.'S E D) 3.W AY V ALVE. MOV N
l (CLOSED PORT M AY V Any)
Y CF
_QL _
_ (CPEN CLCS(04 SOLf hblD OPE R ATED V ALVE EOV dV-SOLENQlD CPER ATED A
'N 3 WAY YALVE. SOV i
l (Ct OSED PORY M AY V ARY) n n
g HYDR AULIC V ALVE. HV p_
L HYDR AULIC NON RETURN
_ (O P E N 'C LO S E D) 4 4
VALVE
- HCV (CDEN: CLOSED)
C C
_N
_ 'CPEN CLCSEO)
DNELMATIC V ALN E. NV L_
PNE UM ATIC NO N.R E TU R N 4
vat.VL. NCY (OPEN CLOSED)
[
6 CHECK V ALVE - CY SAFETY VALVE SV I
/
l (CLOSED)
\\d
~
~T a
rh POWER OPER ATED REllEF V ALVE, c'k A'
SOLE N0!D PILOT TYPE. PORV AN POWER OPER ATED RELIE ' V ALVE.
l l
(CLOSED)
PHEUMATIC ALLY OPERI.iED PORV l
l OR DU A L.FUNC TIO N S AFE TYiR ELIE F VALVE.SRV (CLOSED) i i
I CENinlFUG AL CENTRIFUC AL MOTOR. DRIVEN PUMP. MDP TURBINE. DRIVEN PUMP. TDP
\\
t i
-!,L PoslT!vE OrSPLACEMENT L,
POSITIVE DISPL ACEMENI MOTCa.catvEN pvMP MDP
]
TURDINE+ DRIVEN PUMP. TDP I
\\
/
I A
('
\\/
Figure A 1.
Key To Symbols in Fluid System Drawingt.,
97 1/89
P A
~
\\
I u
PW84 PWR MAIN CONDENSER
- COND RE AC TOR VE5SEL. RV O
v i,
I r
9
- @J'm HE AT E ACH ANGER HI MECH ANIC AL DR AFT 6
l l
I r**
- h'7 STE AM TO.W ATER AIR COOLING UNIT ACU
' I CR v< ATER TC-STE AM HE AT EXCH ANGER D E. FEEDWATER NE AtEn. DRAIN COOLER. ETC.). HX f
)
OR T L'. s i s SPR AY N022LES. SN aaaagaga
(;
w i \\w r-
- +i RUPTURE DISK RD L
FILTER. FLT CRJICE. OR
~
l l
l l
i s
Figure A-1.
Key To Symbols in Fluid System Drawings (Continued) 98 1/S9 i
., __ _ _.. _ _.. _ - _ _....... ~. _..... _ _ _ _. -.. _.... -.. _ _. _. _ _... _ _. _, _ _ _.
A.C. DIESEL GENER ATOR
- 00 2
8 ATTERY. B ATT OR A C. TURBINE CENERATOR TO -
1 I
yd CR CIRCUti BRE AKER. CB g
(3
-H OR 4 :3 INTERLCCKED-(O PE N:CLC S E D)
CIRCUlf BRE AKERS + C8 SWITCH + SW AUTOM ATIC OR O
CR OTHER TYPE OF g
TR ANSFER SWITCH e ATS Di& CONNECT CEVIC E
}
OR-(OPEN1 CLOSED)
MANUAL TRANSFER SWITCH- + Mf 8 d
l I
SWITCHOE AR BUS
- BUS CR I N8 "I I
MOTOR CONTROL CENTER. MCC CR T,7 7,7 TR ANSFORMER. TR AN
)
CR I
DISTRIBUTION P ANEL. PNL i
I l.
a I
e ATTEnv CH ARcER (RECTiriER). eC l
52 L INVERTER
- INV --
g j
1 i
L 4
i i
M[
l CR RELAY CONTACTS
~
- FUSE
- FS l
l Fl I.
toPEN!CLCSED).
1 4
i i
ELECTRIC uoToR. uTR g
,, yo,,,,,,,7,,,,,
s Figure A-2. _ Key To' Symbols-In-Electrical System Drawings
-99
.1/89 -
1
,,.)
.g
,.w3 a yh_.,,E.y....,yr,-.%,,,...~
,,Ew.,..w3m',,,,..,,.,.e...,w.,,,,w.,
....e,,.
r-o,E,,-,,3,%_ t
,.e,,..-,.
-u..c...ms 5.w - _ m/ + M m,.-r-,
,.,q.,
-.. -. -. ~. -....... - - - - - - ~
~
i-
'l STAIRS A
SPIRAL
=g-U = Up w
.0mDown
-ST AIR C A S E w
LADDER (3,
- u. Up.
ELEVATOR o
Down i
J p
HATCH OR OPEN AREA:
GRATING DECK (NO FLOOR)--
- O --
PERSONNEL DOOR H
-EQUIPMENT DOOR O
h::
RAILROAD TRACKS.
FENCE LINE -
=
E 4
2 i
TANK / WATER AREA 4
i i
l i
i.
i.
i-z e
i Figure A-3.
Key To Symbols-In Facility Layout Drawings i
100 1/89 I
t.
..._.... _ ___ _.c. _ _...................-._, _..
Braidwood 1 & 2 APPENDlX B d
DEFINITION OF TERMS USED IN TIIE DATA TABLES-t Terms appearing in the data tables in Sections 3 and 4 of this Sourcebook are denned as follows:
SYSTEM (also LOAD SYSTEM) All components associated with a particular system description in the Sourcebook have the same system code in the data base. System codes used in this Sourcebook are the following:
Code Definition RCS Reactor Coolant System AFW Auxiliary Feedwater System ECCS Emergency Core Coolmg System CVCS Charging System PAHRS Containment. Heat Removal Systems (including containment spray system and fan coolers) 1&C Instrumentation and Control Systems EP Electric Power System CCW Component Cooline Water System ESW Essential Service Water System COMPONENT ID (also LOAD COMPONENT ID) - The component identification (ID)-
code in a data table matches the component ID that appears in the coinsponding system
. Q drawing. The component ID_ generally begins with a system preface followed by a 1y component number.- The system preface is not necessarily the same as the system code described above, For component ids, the sy' stem preface corresponds to what the plant calls the component (e.g. HPI, RHR), - An example is_ HPI-730, denoting valve number
'i30 in the high pressure injection system, which is part of the ECCS. The component number is a contraction of the component number appearing in the plant piping and1 instrumentation drawings (P& ids) and electrical one line system drawings, l
l LOCATION (also COMPONENT LOCATION and POWER SOURCE LOCATION) -
Refer to the location codes defined in Section 4, COMPONENT TYPE (COMP TYPE)- Refer to Table B-1 for a list of component type codes.
POWER SOURCE The component ID of the power source is listed in this field (see COMPONENT ID, above). In this data base, a " power source" for a particular component -
(i.e. a load or a distribution component) is the next hi,her e*cetrical distribution or t
generating component in a distribution system. A single component may have more than I
one power source (i.e. a DC bus powered from a battery and a battery charger).
POWER SOURCE VOLTAGE (also VOLTAGE)- The voltage "seen" by a load'of a power source is entered in this field. The downstream (output) voltage of a transformer -
inverter, or battery charger is used; O
V 101
_1/89
Braidwood I & 2 EhlERGENCY LOAD GROUP (EMERG LOAD GROUP) AC and DC load groups (or eleenical divisions) are defined as appropriate to the )lant. Generally, AC load groups are identified as AC/A, AC/B, etc. The emergency loac group for a third of a kind load i
ti.e. a " swing" load) that can be powered from either of two AC load groups would be identified as AC/AB. DC load group follows similar naming conventions, i
i l
l l
l I
J j
102 1/89
i TAllLE II.l.
COMPONENT TYPE CODES V
CO N1PONENT CON 1P TYPE VALVES:
Motor operated valve MOV-Pneumatic (air operated) valve NV or AOV Hvdraulic valve HV S61enoid operated valve SOV Manual valve XV Check valve CV Pneumatic non return valve NCV Hydraulic non return valve HCV Safety valve SV Dual function safety / relief valve SRV Power operated relief valve PORV (pneumatic or solenoid uperated)
PUMPS:
Moto*-driven pump (centrifugal or PD)
MDP Turbine driven pump (centrifugal of PD)
TDP Diesel-dnven pump (centrifugal of PD)
DDP OTHER FLUID SYSTEM COMPONENTS:
Reactor vessel RV Steam generator (U tube or once through)
SG b
Heat exchanger (water to water HX, HX or water-to air HX)
Cooling tower CT Tank TANK or TK Sump SUMP-Rupture disk RD Orifice ORIF Filter or strat FLT Spray nozzle SN Heaters (i.e. pre ~urizer heaters)
HTR VENTILATION SYSTEM COMPONENTS:
Fan (motor-driven, any type)
FAN Air cooling unit (air to-water HX, usually
' CU or FCU A
including a fan)
Condensing (air conditioning) unit -
COND EMERGENCY POWER SOURCES:
Diesel generator DG Gas turbine generator GT Battery BATT O}
t%J i
103 1/S9
I i
l TAllLE 11 1.
COMPONENT TYPE CODES (Continued)
V CO\\1PONENT CONIP TYPE El.ECTRIC POWER DISTRIBUTION EQUIPMENT:
Bus or switchgear BUS h
Motor control center MCC Distribution panel or cabinet PNL or CAB Transformer TRAN or XFMR Battery charger (rectifier)
BC or RECT invener INV Uninterruptible power supply (a unit that may UPS include battery, battery charger, and invener)
Motor generator MG Circuit breaker CB Switch SW Automatic transfer switch ATS Manual transfer switch MTS l
O i
I k
E i
l 104 1/89 4
-