ML20070Q643
| ML20070Q643 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/31/1989 |
| From: | 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-88-1021, NUDOCS 9103290140 | |
| Download: ML20070Q643 (120) | |
Text
-
O kB REGO NUCLEAR POWER PLANT
%e E
SYSTEM SOURCEBOOK
+
DAVIS-BESSE O
se.34e
(
O 21.==
_m
,,1,
{'DR _ADOCK 050E M D.
9
l SAIC 88/1021 h
W*p r eco%
py~
- g NUCLEAR POWER PLANT SYSTEM SOURCEBOOK o
h 4
s
-4 449 4
~
D AVIS-B ESS E 50 346 Editor: Peter Lobner Author: Peter Lohner Prepared for:
U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Contract NRC 03 87 029 FIN D 1763 O
5~
_d cM
^^
G i EJ -1,
~:;-
l
. -. ~.-..- -
t l
Davis Besse TABLE OF CONTENTS Section Eage 1
S UhiMA R Y D ATA ON PLANT............................................
1 2
IDENTIFICATION OF SIMILA R NUCLEA R POWER PLANTS....
1 3
S YSTEM INFO RMATION................................................,
2 3.I Reactor Coolant System ( RCS)................................
8 3.2 Auxiliary Feedwater (AFW) System and Secondary S team Relief (S S R) Syste m..................................
15 3.3 Emergency Core Coolitig System CICCS)...................
23 3.4 M ake ap and Pu rification S ystem...............................
31 3.5 Instrumentation and Control (I & C) Systems...............
38 3.6 Elec tric Powe r Syste m..........................................
42 3.7 Component Cooling Water (CCW) System..................
60 3.8 Service Water (S W) System...................................
67 3.9 Equipment and Control Room Emergency Ventilation Systems...........................................................
72 4
PLANT INFORM ATION....................................................
76 4.1 S ite and B uildin g S ummary....................................
76 4.2 Facility Layou t Drawin gs......................................
76 i (
5 BIBLIOGRAPHY FOR D AVIS BESS E.................................. 100 l
APPENDIX A Definition of S and Layout Drawings...........ymbols Used in the System i
............................................. 101 APPENDIX B Definition of Terms Used in the Data Tamet............
108 l
t i
V i
i.
1/89 l
-~
Davis Besse LIST OF FIGURES Ficure EEa 31 Cooling Water Systems Functional Diagram for Davis Besse............
7
.3-1 Elevation View of a Raised. Loop Babcock & Wilcox RCS...............
I1 3,1 2 Davis Besse Reactor Coolant System......................................
12 3.1-3 Davis Bc.te Reactor Coolant System Showing Component Loc ati o n s........................................................................
13 3.2 1 Davis Besse Auxiliary Feedwater and Secondary Steam Relief Systems..........................................................................
18 s
3.2 2 Davis Besse Auxiliary Feedwater and Secondary Steam Relief Systems S howing Component Location s...................................
19 3.2-3 Davis Bc:se Fire Water Supply to the AFW System.......................
20 3.2-4 Davis Besse AFW Pump Cooling and Minimum Flow and Full Flow Recirculation Features........................................,................ 21 3.3 1 Davis Besse High Pressure injection System............................... 26 rD e
3.3-2 Davis Besse Hi O
Locations.......gh Pressure Injection System Showing Componen:
.................................................................-27 3.3-3 Davis Besse Low Prenure Injection / Recirculation System...............
28 3.3-4 Davis Besse Low Pressure Injection / Recirculation System Showing Component Locations..........................................................
29 3.4-1 Davi s B es se M ake u p S ys t e m................................................. 33 3.4-2 Davis Besse Makeup System Showing Component Locations........... 34 3.4-3 Davis Besse Normal Water Sources for Makeup System................. 33 3.4-4 Davis Besse Normal Water Sources fcr Makeup System Showing Component Locations..............,
.................................... 36 3.6-1 Davis Besse 4160 and 480 VAC Electric Power System................. 45 3.6-2 Davis Besse Details of 480 VAC Electric Power Distribution............ 46 3.6-3 Davis Besse 125 and 250 VDC and 120 VAC Electric Power Systems.
47 3.6 4 Davis Besse Diesel Generator Fuel Oil Storage ard Transfer System.. 48 (c
li.
1/89
Davis Besse LIST OF FIGURES (continued)
O Ficure Eag 3.7-1 Davis Besse Com Loops..............ponent Cooling Water System, Essential Cooling
.............................................................. 62 3.7-2 Davis Besse Component Cooling Water System, Essentia' Cooling Loops S howin g Component Location s...................................... 63 3.7-3 Davis Besse Com Cooling Loop.....ponent Cooling Water System, Nonessential 64 3.7 4 Davis Besse Component Cooling Water System, Nonessemial Cooling Loop Sh owing Compone nt Locations............................. 65 3.8 1 Davis B e s se S e rvicc Wate r Sys t e m.......................................... 69 3.8 2 Davis Besse Service Water System Showing Component Loc a ti o n s........................................................................ 70 4-1 General View of the Davis Besse Nuclear Power Plant and Vicinity.... 77 42 D avis B esse Plot Plan.....................................................
78 4-3 Davis Besse G eneral S tation Arran gemen t.................................
79
\\
44 Davis Besse Containment and Auxiliary Buildings, Elevation 545 feet.........................................................................
80 4-5 Davis Bessc. Containment and Auxiliary Buildings, Elevation 565 feet.........................................................................
81 4-6 Davis Besse Containment and Auxiliary Buildings, Elevation 5 8 5 to 5 95 fe e t.................................................................
82 4-7 Davis Besse Containment and Auxiliary Buildin 603 feet...............................................gs, Elevation 83 48 Davis Besse Containment and Auxiliary Buildings, Elevadon -
613 feet.........................................................................
84 4-9 Davis Besse Containment and Auxiliar 623 feet....................................y 3 uildin gs, Elevation 85 4-10 Davis Besse Containment and Auxiliary Buildings, Elevation 6 3 8 to 64 3 fe e t..............................................................
86 4 11 Davis Besse Turbine Building, Elevation 565 to 623 feet (typical).....
57 4-12 Davis Besse Auxiliary B uilding Section....................................
88
%_.}
iii.
1/89
Davis Besse LIST OF FIGUltES (continued.
Figure Pace A-1 Key to S ymbols in Fluid S ystem Drawings................................
104 A2 Key to S ymbols in Electrical S ystem Drawings........................... 106 A3 Key to Symbols in Facility Layout Drawings..............................
107 u
IV.
1/89 4
Davis-Besse LIST OF TABLES O)s
(
Inhk P.m 3-1 Summary of Davis Besse Systems Covered in this Report...............
3 3.1-1 Davis Besse Reactor Coolant System Data Summary for S e lec ted Compo ne nts,.........................................................
14 3.2 1 Davis Besse Auxiliary Feedwater System Data Summary for S elec ted Com po ne nt s..........................................................
22 3.3 1 Davis Besse Emergency Core Cooling System Data Summary for S elec ted Com po ne n ts.......................................................... 30 3.4 1 Davis Besse Makeup and Purification System Data Summary for S el e c t e d Com po n e n t s..........................................................
37 3.6-1 Davis Besse Electric Power System Data Summary for S e le c t ed Com po ne n t s......................................................,,,,
49 3.6 2 Fartial Listing of Electrical Sources and Loads at Davis Besse...........
53 3.7-1 Davis Besse Component Cooling Water System Data Summar Selected Components................................................y 66 1
3.8 1 Davis Besse Service Water System Data Summary for j
S ele c ted Com po n e n t s..........................................................
71 3.9-1 Davis Besse Equipment and Control Room Emergency Ventilation System Data Summary for Selected Components.............
75 41 Definition of Davis Besse Building and Location Codes..................
89 4-2 Partial Listing of Components by Location at Davis Besse...............
92 B1 Compone nt Type Cod es......................................................,
110 0
v.
1/89 l
Davis Besse CAUTION :
- The information in this report has been developed over an extended period-
.t of time based on a site visit, the Final. Safety Analysis Report, system and layout drawings, and other published information.. To the best of our 1
4 knowledge, it accurately reflects the plant configuration at the time the information was obtained, however, the information'in this document has not been independently venfied by the licensee or the NRC..
NOTICE
.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 report should be brought to the attention of the following:
Mr. Mark Rubin U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation.
Division of Engineering and Systems Technology Mail stop 7E4 i Washington,'.D.C, 20555 L
With copy to:
Mr. Peter Lobner Manager, Systems Engineering Division
- Science Applications International Corporation L 10210 Campus Point Drive -
ESan 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 documentation should be included if possible,.
a r
5
.g vi.
1/89 ~
w e-e w
- v*d-
-eaea ww-cwn--e+,1& m +1r -m m m e ri-o s-w e
e
-v
=.++s.
ta 9
i DAVIS-BESSE RECORD OF REVISIONS REVISION ISSUE COhth!ENTS 4
0 1/89 Original report O
O
- vii, 1/89
DAVIS BESSE SYSTEM SOURCEBOOK This sourcebook contains summary information on Davis Besse. Summary data on this plant are presented in Section 1, and similar nuclear power plants are identified in Section 2.. Information on selected reactor plant systems is presented in Section 3, and the_ site and building layout is illustrated in Section 4. - A bibliography of reaorts that i
describe features of this plant or site is presented in Section 5. Symbols used in tae system and layout drawings are defined in Appendix A. Terms used in data tables are defined in Appendix B.
1.
SUMMARY
DATA ON PLANT Basic information on the Davis-Besse nuclear power plant is listed below:
Docket number 50-346 Operator Tt.edo Edison Company Location Oak Harbor, Ohio Commercial operation date Il#7' Reactor type PWR' NSSS vendor Babcock & Wilcox Number ofloops 2
Power (MWt/MWe) 2772/906 Architect engineer Bechtel Containment type Freestanding cylindrical steel contain-ment vessel enclosed by a separate reinforced concrete shield building -
2.
IDENTIFICATION OF SIMILAR NUCLEAR POWER _ PLANTS The Davis Besse plant has a Babcock & Wilcox PWR two loop nuclear steam su ply system (NSSS) and a dry containment.
U ted States include:
Other Babcock & Wilcox plants in the Oconee 1,2 & 3 ANO-1 TMI1
- Rancho Seco Crystal River
- - Bellefonte 1 & 2 Davis Besse is _different from other Babcock & Wilcox PWR plants in that:
s
.Only Davis Besse and Bellefonte have a " raised loop" RCS.
The Davis Besse AFW system uses only turbine driven pumps.
Davis Besse has separate charging and HPI pumps. The HPI pumps are not capable of providing RCS makeup at normal RCS pressure, d
i 1/89-
3.
SYSTEM INFORMATION This section contains descriptions of selected systems at Davis Besse in terms Q
of general function, operation, system success criteria, major components, and support system requirements. A summary of major systems at Davis Besse 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 column 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 where additiorniinformation on each system can be found. Other sources ofinformation on this plant are identified in the bibliography in Section 5.
Several cooling water systems are identified in Table 3-1. 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 sections identified in Table 31.
O oa 2
1/gg
~. -.-
O f
()
\\
Table 3-1.
Summary of Davis Besse Systems Covered in this Report 1
Generic Plant-Specific Report FSAR Section System Name System Name Section Reference Reactor Ileat Removal Systems Reactor Coolant System (RCS)
Same 3.1 5
Anxiliary Feedwater(AFW)and Same 3.2 9.2.7 i
- Secondary Steam Relief (SSR)
' Systems i
Emergency Core Cooling Systems 1
(ECCS)
- Iligh-Pressure Injection Same' 3.3 6.3 s
& Recirculation
- Low-pressure Injection Same 3.3 6.3
& Recirculation u
Decay IIcat Removal (DIIR)
Same 3.3 9.3.5 i
' System (ResidualIIeat Removal (RIIR) System)
Main Steam and Power Conversion Main Steam Supply System, X
10.3
[
Systems Condensate and Feed Water System, 10.4 i
Circulating WaterSystem i
t OtherIleat Removal Systems None identified--
X Reactor Coolant Inventory Control Systems Chemical and Volume Control System
. Makeup and Purification System, 3.4 9.3.4 1
(CVCS)(Charging System)
Chemical Addition System X
9.3.6 ECCS q
See ECCS, above '
c?c c
.t 1
1,
1 Y
~
Table 3-1.
Summary of Davis'Hesse Systems Covered in this Report (Continued)
Generic Plant-Specific Report FSAR Section
[
System Name System Narae Sect!nn Reference Containment Systems i
Containment Same~
X 6
i Containment IIcar RemovalSystems P
- Containment Spray System Same X
6.2.2
- Containment Fan CoolerSystem Containment Air Cooling System X
6.2.2 a
Containment Normal Ventilation Systems
. See Containment Air Cooling X
6.2.2 System Combustible Gas Control Systems Containment Hydrogen Dilution X
6.2.5
.f
- System, IIydrogen Purge System r
Reactor 'and ' Reactivity Control Systems Reactor Core Same' X:
4 Control Rod System Control Rod Drive ControlSystem X
4.2.3 Boration Systems See Makeup & Purification System, -
above Instrumentation & Control (I&C) Systems Reactor Proicetion System (RPS)
Same 3.5 7.2
,.t
-. Engineered Safety Feature Actuation Safety Features' Actuation System, 3.5 7.3 System (ESFAS)
Steam and Feedwater Line Rupture Control System.
r Generator Level Control System c
E Remote Shur'down System Auxiliary Shutdown Panel 3.5 7.4.1.6 i
L m._,.,. -, - _.
x N
e (v)
Table 3-1.
Summary of Davis Besse Systems Covered in this Report (Continued)
Generic Plant-Specific Report FSAR Section System Name System Name Section Reference Instrumentation & Control (I&C) Systems (continued)
Other I&C Systems Various systems X
7.6 to 7.13 Support Systems Class 1E Electric Power System Same 3.6 8.2,8.3 Non-Class 1E Electric Power System Same 3.6 8.2,8.3 Diesel Generator Auxiliary Systems Same 3.6 9.5.4,9.5.5,9.5.6, 9.5.7 Component Cooling Wster (CCW)
Same 3.7 9.2.2 System u
Service Water System (SWS)
Same 3.8 9.2.1 Other Cooling Water Systems Non-identified X
Fire Protection Systems Same X
9.5.1 Room IIcating. Ventilating, and Air-
- Control Room Air Conditioning X
9.4 Conditioning (IIVAC) Systems System, Auxiliary Building Ventilation System, Fuel Area llandling Ventilation System, Turbine Building Ventilation System Instrument and Service Air Systems Station and Instrument Air System X
9.3.1 3
Table 3-1.
Summary of Davis liesse Systems Covered in this Report (Continued)
Generic Plant-Specific Report FSAR Section Systeni Name System Name
.Section Reference Refueling and Spent FuelSystems Same X
9.1 Radioactive Waste Systems Same
'X 11
~
-l Radiation Protection Systems Same X
12 cs
.g~
s
'l' ' -
F 3
HPi PUMPS L
J r
3 DHR
' PUMPS L
J r
3 DIESEL -
GEf4ERATOR k
J r
3 r
3 l
OfiR IfEAT CCWS-t EXCHAtJGER v
J L
J A
9 F
r LAKE INTAKE COMPOfJEtJT COOLifJG TO CIRCULATitJG FORE-SWS WATER SYSTEM iWATER MAKEUP -
ER!E WATER i
BAY SYSTEM HEAT EXCHAtJGER SYSTEM j
j f
3 d
ROOM.
COOLERS
(
)
ccws. *e cooing water system onn - D car Aashawar s
ifPt. Hit it Pressure injectori SWS - E ervce Wrer System
&c Figure 3-1. Cooling Water Systems Functional Diagrarn for Davis-Besse
- -- - ~ - - -
-- -~- -- - -'
~
a Davis Besse 3.1 REACTOR COOLANT SYSTEM (RCS) 3.1.1 System Function
,(
The RCS transfers heat from the reactor core to the secondary coolant system via the steam generators. The RCS pressure boundary also establishes a boundary against the uncontrolled release of radioactive material from the reactor core and primary coolant.
3.1.2 System Definition The RCS includes: (a) the reactor vessel, (b) main coolant loops, (c) main coolant pumps, (d) the primary side of the steam generators, (e) pressurizer, and (f) i connected piping out to a suitable isolation valve boundary. An elevation drawing of a B&W " raised loop" RCS similar to Davis Besse is shown in Figure 3.1-1. A simplified diagram of the RCS and important system interfaces is shown in Figurc 3.12. A summary of data on selected RCS components is presented in Table 3.1 1 3.1.3 System Oneration During power operation, circulation in the RCS is maintained by two main coolant pumps in each of the two main coolant loops. RCS pressure is maintained 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 within a prescribed band by the chemical and volume control system (makeup and purification system).
At power, core heat is transferred to secondary coolant (feedwater) in the steam generators. The heat transfer path to the ultimate hec: sink is completed by the main steam and power conversion system and the circulating water system.
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 is maintained by the main coolant pumps or by natural circulation, The heat transfer path to i
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 adequate, the RCS pressure will increase and a heat balance will be establis by venting steam or reactor coolant to the containment through the pressurizer relief valves.
There is one power operated relief valve (PORV) and two safety valves on the pressurizer. -
A continued inability to establish adequate heat transfer to the steam generators will result in a LOCA-like conditiou (i.e., continuing loss of reactor coolant through the pressurizer relief valves). Repeated cycling of these relief valves has resulted in valve failure (i.e.,
relief valve stuck open).
Following a large LOCA, reactor core heat is dumped to the containment as reactor coolant and ECCS makeup water spills from the break. For a short-term period, the -
containment can act as a heat sink: however, the containment spray systems operates in order to complete a heat transfer 3ath to the ultimate heat sink.
The RCS is equippec with a High Point Vent System which provides vents on each of the two hot legs and on the pressurizer.= This system vents noncondensable gases
- to aid in refilling the RCS and to promote natural circulation flow following a transient or small LOCA and loss of normal circulation. Redundant solenoid isolation valves are remotely operated from the control room. -Orifices and line sizing limit the' flow rate through these vent paths.
s 8
1/89
Davis-Besse 3,1,4-System Success Criterin The RCS success criteria 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 integnty 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
- 1. Volume: 11,440 ft3, including pressurizer
- 2. Normaloperating pressure: 2185 psig B. Pressurizer
- 1. Normal water volume: 800 ft3
- 2. Normal steam volume: 700 ft3 C. Safety Valves (2)-
1.-' Set pressure: 2435 psig
- 2. Reliefcapacity: 336,000.lb/hr each-D. Power-Operated Relief Valve
,1.
Set pressure: L 2400 psig
- 2. Relief capacity: unknown
- 3. Type: Electromatic (solenoid-controlled, pilot operated)-
E. SteamGenerators(2)
- 1. Type: Once-through
- 2. Primary side volume: 2030 ft3 F. Pressurizer Heaters
'A.- Motive Power
. the standby diesel generators as described in Section 3.6.. Each AC division.
supplies one half of the Class lE heaterload.
- 2. The main coolant pumps are supplied from Non Class IE switchgear.
9 1/89 l
Davis-Besse B. Main Coolant Pump SealInjection Water System The makeup system supplies seal water to cool the main coolant pump shaft j
seals and to maintain a controlled inleakage of seal water into the RCS, Loss of seal water flow may result in RCS leakage through the pump shaft seals which will resemble a small LOCA.
C. Backup Main Coolant Pump Seal Cooling On each pump, an integral heat exchanger supplied by the CCW system provides,enough cooling capacity to prevent excessive seal heating if seal injecuon is lost.
O o
V 10 1/89
. -. -. =
~\\
o PRESSURIZER
~
(SEE INSERT) i s s l
I di
{
l t
AUX l
t FEED -
I INLET I
l MAIN 4
H T'
, 4 FEED +
OTSG t
OTSG lNLET Il j
II
- P i i e
i i S UR CE ~~~*'
I l
\\
LINE s,/
}
v r
< REACTOR COLANT C". ;*
~.YO i
l l
I
'x f
/
\\
i
' 1- )
L
\\Il i
l
- i
~
(
i r~s i
f cv N,
-f(+,' +
i s
j s.
i s,)
+~
s
\\
7 COLo REACTOR PRESSURIZER INSERT LEG VESSEL g
=
I y
a,===
,,,,,,m,
-, s..m.
Y I\\
/
-}j....
...a k
am W of sads twe* >sts.st ss m g
i
.w orn
,-nirg'<2,....
m am in-eau
..a@
s
. 2 5-a,- o =
N i
i
&s
,.~.o aa O-igure 3.1-1.
Elevation View of a Raised-Loop Babcock & Wilcox RCS 11 1/89
t
>b
{3tI
-?!
!+
"i i :
k' f,
sei 1jf 1yl>5Il.'
t E
rT AS A.
eY
+S v
AE-c A
=
n-acW
,O-sr oEO s
r,aL Ly Ps L,,,
1 3
L e H3 u
3 A
t 2
o M
e H2 t
9 a.
o~
o ue 2
E P
P.a R
M n
c E
2 N
m a
s0 n
.a
- c..
t,M*
te1 gG
=
e 1
i P
sE
.s
. g e
t n8 L
sD Pn g
c s
0 O
na O
4 LN r
y ot o
oR nO o
D S
tOC c
t t
t A.
n o
a u
lo x
o ft o-C A
=
t r
M a
o
>B E
grT
&7 F
. * *i t
xxM 8
F c
w-uA a
s e
o 0
R 5
e "g-sse B
~m J
~
s iva m
oA p
D cte o8A
,c F Q
WA n
n-6*
2-A r
1 2
a C
e 4;3 3
s r
k e
pJ e
r
=.
pt
&+ r u
H s
g M
i O
F R
F 2,.a. 4i ca
=
f e.
3
.A G
.A a
(
)a
'=4 AG e
a
- ==R E
8 21 G
L
- 2 a
n ND s
5t P
o
=
n O T A
L OO OO O
L S
C L
C e.
g m
v_
3 1'
g 2
k c
P P
~
l, CR M
nM EAcA rI uH 5C 5N f
R (U LT PO O
f
&O k~
i 7!
.' : 1,
li;
)
-.j!
lIl1 i'l M
W E
1 fT 77 sS 4
i dY (3
Y eS vL
- S j
A aa IJ Ch s
I,u CV C
s
EL
,f OE 0E n
s D,,t T8 f8 n
v P
e i
- 4
+
p y
s Q
g, g
s g
3 e.
sn gH2 s
g t
3 L
(
t io eW g
t ac o,
g H2 t
L g
e 2
wD t
u n
t 2
pG i
L E
e 9
9 A
R n
S C
o G
L L
O O
p t
O f
O SG p2 3e g
r C
W m
L e
i pC eI eG 9G e
P tE e1 eds L
1 m
Mc C
OW r
P OC oD OD^
o
{
0
- C o
4 C
L D
0 Le oL OO T
1 tO L
C C
i f
t t
gn t
e i
A n
w ta w
t o
g hS A
l f
m P
.'M
^
O M
_. A D.
e
_E,O_-.
v y
O Sf ts
,4 L
o 3_
m5,
S 05 t
8 u
a 1
n j
lo a:
oC s
C s
8 tv r
s o
c t
D.
a' c
l
_D_..
e o
a LF, R
T 3,,.
4s.:
e A2 A
s C
a s
A 7
k 7
e
.A B
8'
- 4. + t t
r' s
i M
v OR a
t Aw t
3 F
D A
c, 2
e 6
1 ps 3
k m
v',,
3 mL aG 33 LG pt P I._
fO Ah r
aG 4G Wa e
=
3I 2I C
r L
R P
oD OD P
u E
T t
I O0 tC C
RL O4$
C g
L U
i 5
F 5
2 e
l 2
f 2
2 i
G M
9 P
a.
C C
k A
a Rn
~
Eh m
tA t
FuI e
uH SC Sh g
Et Au PO O
T l
w Cce c
1 Table 3.1-1.
Davis Besse Reactor Coolant System Data Summary for Selected Components t
COMPONEtJT ID COMP.
LOCAT!ON POWER SOURCE VOLTAG E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
Dil11 MOV RC MCC-F11 A 480 ELEClPENilM2 B
Dil12 MOV RC MCC-E118 480 585ABilALL A
MU1 A MOV RC MCC-F12A 480 LVSGHM2 B
{
MU18-MOV.
RC MCC-F12A 480 LVSGIIM2 B
MU2A MOV RC MCC-E11B 480 585ABif ALL A
.[
MU2B MOV RC MCC-E11B 480 58SABliALL A
]
PZR-ilIR-A -
filR -
RC MCC-E12A 480 LVSGRM1 -
A I
PZR-tilR-B IITH RC MCC-F12A 480 LVSGRM2 -
B RC11 MOV RC MCC-F12A 480-LVSGRM2 B
RC2A-SOV RC PNL-DBP 125 LVSGRM2 2-RCS-VESSEL RV RC E.
i.
i bC
{
Davis Desse 3,2 AUXILIARY FEEDWATER (AFW) SYSTEh! AND SECONDARY STEAhl RELIEF (SSR) SYSTEh!
(
)
(/
3,2,1 Svctem Function The AFW system provides a source of feedwater to the swam generators to remove heat from the reactor coolant system (RCS) when: (a) the main feedwater system is not available, and (b) RCS pressure is too high to permit heat removal by the residual heat removal (RHR) system. The SSR system provides a steam vent path from the steam generators to the atmosphere, thereby completing the heat transfer path to an ultimate heat sink when the main steam and 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 and small break LOCAs A separate startup feedwater pump provides steam generator makeup during startup and snutdown of the plant.
3.2.2 System Definition The AFW system consists of two turbine-driven pumps. The normal water source for the pumps is the condensate storage tank. Alternate sources of water are the Service Water System, the deaerator storage tanks, and the fire water system. Each pump is normally aligned to supply one of two steam generators, but can be aligned to supply the opposite steam generator througn a crosstie containing a normally closed motor-operated valve. The turbine-driven pumps receive their steam supply from both steam generators and exhaust to the atmosphere.
The SSR system includes nine safety valves and one power-operated pressure control valve on each of the two main steam lines.
Simplified drawings of the ARV and SSR systems are shown in Figures 3.21 and 3.2-2. A summary of data on selected AFW system components is presented in Table 3.2-1.
Ad 3.2.3 System _ O nera tion During normal operation the ARV system is in standby, and is automatically actuated by the Steam and Feedwater Line Rupture Control System (SFRCS) when needed to mabtain the secondary coolant inventor be manually started from the control room,y in thu steam generators. The system can also and the turbine driven pump can be started and controlled locally. Operation of the AFW system is independent of the Integrated Control System (ICS).
AFW pump 1 1 is normally aligned to feed steam generator 1-1. Similarly, pump 12 is normally aligned to feed SG 1-2. Both pumps can be aligried to feed the opposite steam generator. This realignment takes place when a faulted steam generator is detected and isolated by the SFRCS. Each turbine driven ARV pump is supplied with steam from both steam generators.
During AFW operation, level in the steam generators is maintained automatically by a safety grade steam generator level control system which modulates turbine speed as needed to maintain SG level.
Both AFW pumps are normally supplied via a common-header from the condensate storage tank. The service water system is the preferred backup water source for the AFW system (see Section 3.8). Alternate water sources for the AFW system are the fire protection system (see Figure 3.2 3) and the deaerator storage tanks.
When the main condenser is not available as a heat sink, reactor core decay heat is rejected to an ultimate heat sink by venting to atmosphere via nine safety /aives or a power-operated pressure control valve on each main steam line, a
15 1/89 1
Davis Besse 3.2.4 Snym Success Crlierin For u.e decay heat removal function to be successful, both the AFW system and O
the SSR system must operate successfully. The AFW success criteria are the following d
(Ref.1):
' Makeup of 800 gpm to either steam generator provides adequate decay heat -
removal from the Reactor Coolant System.
Either AFW pump can provide adequate flow.
Either the condensate storage tank, or the Service Water System is an adequate source of water for the AFW pumps. No credit was taken for water from the fire protection system or the deaerator storage tanks.
g 3.2.5 Comoonent Information A. Steam turbine driven AFW pumps 1-1 and 1-2
- 1. Rated flow: 1050 gpm @ -1050 psi head
- 2. Rated capacity: 100% (Ref.1)
- 3. Type: Centrifugal.
B. Condensate storage tanks (2)
- 1. Capacity: 250,000 gallons each C. Deaeratorstorage tanks
- 1. Capacity: 128,000 gallons D. Secondary steam relief valves -
- l. Nine safety valves per main steam line
- 2. One power operated pressure control valve per main steam line 3.2.6 Suonort Systems and Interfaces A. ControlSignals
- 1. Automatic
- a. Pump Start -
The AFW pumps are automatically actuated by the Steam and Feedwater Line Rupture Control System (SFRCS) as described in Section 3.5.
- b. AFW flow control The pump speed (i.e. govemor setting) is controlled by the safety-grade
. steam generator level control system described in Secuon 3.5.
- c. Watersource switch over When an -AFW pump-low suction pressure is sensed. this will automatically cause the steam supply to the turbine to be inhibited and-the pump suction shifted to the service water system. When suction pressure is restored, steam is automatically readmitted to the turbine.
- d. Pump discharge realignment The SFRCS will automatically isolate a faulted (i.e. low pressure) steam generator by closing the respective' isolation valve (AFW599 or AFW608). The associated AFW pump is' automatically realigned to feed the opposite steam generator by. opening valve AFW 3869 or ~AFW :
3871 as appropriate (Refs.1,2),
f~
s 16 1/89
Davis Besse
- 2. Remote manual
- a. Plant operators can place the ARV system in operation from the main Os\\
control room.
O
- b. ARV pump speed can be controlled from the remote shutdown panel.
- 3. Manual
- a. The ARV pumps can be started and controlled locally. Valves can be operated locally,
- b. Alignment to supply the AFW system fr 'm the fire protection system must be done manually.
B. Motive Power
Note that DC powered valves AFW106, AFW360 and AFW3870 are all associated with AFW pump 1-1 supplying steam generator 1-1. The remaining valves in the system require AC power.
Operation of ARV aump 12 requires AC power or local manual actions to open its steam supp y valve AFW107. All cross-ties also require AC power or local manual actions (Ref.1).
- 2. The power supply paths for isolation valves ARV599 and ARV608 have series circuit breakers (actually series magnetic contactors) in two different motor control centers. Operation of these valves requires that both sets of contactors be closed. This design feature appears to be intended to reduce the probability of a spurious closure of the steam generator isolation valves.
C. Other O
- 1. Lubrication and cooling are provided locally for pumps and the turbine -
drive. The pump cooling sys, tem is shown in Figure 3.2 4.
Q
- 2. Both AFW pumps require minimum flow protection which is provided by-the normally open recirculation flow path shown in Figure 3.2-4.
- 3. AFW pump room ventilation is discussed in Section 3.9.
- 4. Control att requirements to support operation of the atmospheric steam -
dump valves is not known, 3.2.7 Section 3.2 References
- 1. Youngblood, R. and Papzoglou, I.A., " Review of the Davis Besse Unit No.1 Auxiliary Feedwater System Reliability Analysis", NUREG/CR-3530, Brookhaven National Laboratory, February 1984
- 2. NUREG-1154, " Loss of Main and Auxiliar Feedwater Event at the Davis Besse Plant on June 9,1985", USN1C, July 1985.
O 17 1/89
j!I1 y
4'. ~
h8 n.
f.
n_
{. 8
.f
_ '-f_.
n u.
w i-
- d. -.
1" S,
MTIg
)
[
o o.
i.
, m_..
y o h_.hh_Md.,.
N.
a n.n O
w,. $"' W,.
g_.
wm o.a s
n '
m e
I
=_ g.
t n
sy S
f ie l
le R
mae tS y
ra dn
,l oc I
- e d
ge u
n n
a es r
=
e 4
S'= ng~ -
' t 4
k2 w-a 3
w d
e m
e k
[n F
[
]
]
X x.
yra i
ux _
,[
l i
]
x f, L w _'
X. "
uA e
s f'
4_
s c.
s
.,'c N.
e A"n B
,o
,, s L
i.
v a
D m
- n..
MT y
"Ln 1-a n.
3 2
+
^
.H" E
o, ';,
A e
s, e
u d
r r
b m.
iF g
-o y"
h 9 =,.
+1-
,T.
x" i
H=*
m s
9H-h""'
+
s
- +
~
=*,
S mu-
/
L.
b
(
=.
".I t_ " = v
+
a m
a CcC -
c I
tl; ll,:;'
- l el l'
1 t
c!,
4 k
t
- L y
?1 e
.m n
s H=
g.
I n
g g-l n
S l
L~
E g,.
W g.
=
I
~
.o*
M*
pv *l 9
s s
0 Jk 1s A
o n
0 l
=
1 o
e m
i l}
ta
~
1II c
H'
.. s.
~
m_." v o
O M nVW.
J:=
^
r L
c
=
t
=
=.r.a O gng
~
s.
n
=
i e
=
a
=.*o.
n
=
g>,,,
-.m-g, o
r A"_ m 4 +' r
+1n t-Wr D'i u
=
n p
+
m g
I y,,
~ -
o
=
C l
g n
i w
li o
h S
l s
m e
t s
y S
f q
ie le
[
1l R
j m
g
..r+n &1.
,.s.
,;x *.x<
a e
g.ms u
t S
v e
y
,2w g
n r
Qp.q$*-
o 4=
a d
I u
n O_:+ m -
c
.~. g. -
a
,*e-1n 9A r'
P' e
-+
S ym m
d I
i n
a i{j r
l l
r,A 1
r 2
4* "
g.
e I
- a.
a t
+
w d
7 u.
.mm +.
.J'n e
5-e
_7<
ix u
>C e
o v
=TO F
- t. s.
b
.e y
uu' r
,g,,
a l
g l
I 3,
ng 3
a
>o u
=cM.
e
== -
A e
T-g'-
aYEs u
f s
s m
m.sO e
a H.
B
-w.
Qx-g*
s 1
M,,
a i
v E
+
- 94 "*
g3 D
3 2
-l b">
2 H.,.
QH..
3 s
QH *",-
r I
e c.
se i "'
O u
n TC ig t
f mmP
_m1 O
F "u "~
l.
a e
t e
Lw e
i
. g.
u,u m a.-
g s
r u
c a
c.
}
c c
c 1
e hc
.tj;. j ; ; 2;
- l;1!
- It
~
i,.., _s
,_r"%
f,
)
/
\\
]
LJ
'- J
)
(fil WAf f R STORACE TAxn 1
e TOleg l
WATE R y
HE ADEHs j
l F Pl 4
j F eE WATEH PUVPS
~
EElh FP194 yp:3, p p.
3 32*
FV329 FP2P gny g.pg fE4 f?4 FP2 4
i p
j
' JOCAE Y PUup
^
W F P185 FPf 2 F P.18
- P36 (J
-h, TO STNUup Q
FPt0 F E LD Asup 6'ysi TOffE TOfft WATKR W ATE R (v
A h
S HEADERS 2 L
IIE1M
~^
fE47 FPS 2 fp176 FF;g NIM 6 SYRUCTOFE 12 I
l Figure 32-3. Davis Besse Fire Water Supply to the AFW System f
i f
en I
L.._.__.
W
's ?
z c
O.-
(^
\\
N RETUffJ 1 TO CST i
+
to uttJi rLOW HECtfic. t rJE k
h TURB2JE DfWEf4 IHOM AFW IMMP E
FOR AfW 19 MArJ D T E E LO 3
13 10 23 21 AiWPUUP l Puuf
-[.__
fiOWTEST os ~. -
6 g
b 9
J L TUROINE SEARINGS d'
7 T
l CTOSd-TIE TO
[~
@EM ATW PUMP f-2 DtSCitARGE
[
FROM SERVCE WATER SWTEM
?
L FOR PUuP ccmo I
n3 Figure 3.2-4.
Davis Besse AFW Pump Cooling And Minimum Flow And Full Flow Recirculatior; Features
~
_m
_h
N
. (D '
LJ Table 3.2-1.
Davis Besse Auxiliary Feedwater System Data Summary for Selected Components COMPOf1ENT ID
' COMP.
LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
TYPE LOCATION LOAO GR9.
AFW1-1 TDP AFPRM1 AFW1-2 TDP-AFPRM2 AFW106 MOV 623ABHVACAREA DC-MCC1 125 LVSGRM1 lA AFW106A MOV 623ABHVACAREA MCC-E128 480 DGRM1 A
AFW106A MOV 623ASHVACAREA MCC-E128 480 DGRM1 A
AFW107 MOV 623ABHVACAREA MCC-F11 A 480 ELECTPENRM2 B
AFW107A MOV 623ABHVACAREA MCC-F11B 480 MCCF11BftM B
~
AFW360 MOV AFPRM1 DC-MCC1 -
125 LVSGRM1 A
AFW3869 MOV-AFPRM1 MCC-E11E 4b0 CRDRM A
AFW3870 MOV
/.FPRM1 DC-MCC1 1?S LVSGRM1 A
AFW3871 MOV AFPRM2.
MCC-F12A -
480 LVSGRM2 B
U AFW3871 MOV-AFPRM2 MCC-F12A 480 LVSGRM2 8
^
AFW3872.
MOV AFPRM2 MCC-F'2B 460 DGRM2 B
AFW388 MOV' AFPRM2 MCC-F12A 480 LVSGRM2 B
AFW599 MOV PENRM4 MCC-F11 A 480 ELECTPENRM2 8
(
AFW608 MOV' PENRM3 MCC-E12E 480 PPTUN A
j AFW729 XV AFPRM2 AFW730 XV AFPRM2 I
AFW786 MOV:
AFPRM1 -
MCC-E11D 480 MKUPCOR A
AFW790 MOV
- AFPRM2 MCC-F12A 480 LVSGRM2 B
CST 1-1 TK CSTRM CST 1-2 TK CSIRM
(
MS11 A NV MNSTMRM1 ICS A/B p
MS11B NV MNSTMRM2 ICS A/B SW1382 MOV AFPRM1 MCC-E12A 480 LVSGRM1 A
SW1383 MOV PENRM2 MCC-F11C 480 PENRM2 B
-s 4 7 4
DavibBesse 3.3 EhlERGENCY CORE COOLING SYSTE%1 (ECCS) 3.3.1 System Ftmetton The ECCS is an integrated at of subsystems that perform emergency coolant injection and recirculation functions to maintain reactor core coolant inventory and adequate decay heat removal following a LOCA. The.,colant injection function 's perfonned during a relatively short-term period after LOCA initiation, followed by realignme t to a recirculation mode of o aeration to maintain long term, post LOCA core cooling. H at from the reactor core is transferred to the contair. ment. The heat transfer path to the ultimate heat f
4 sink is completed by the containment spray system and fan cooler systems.
3.3.2 Sgtem Definition The eergency coolant injection (ECI) function h performed by the following three ECCS subsystems:
Passive core flood tanks (accumulators)
High pressure injection (HPI) system Low pressure injection (LPD system The HP1 system provides the high pressure coolant injection capability. The decay heat removal (DHR) pumps perform the low pressure injection function. The g
Borated Water Storage Tank (BWST) is the water source for both the high and low 3
pressure injection systems. The HPl system injects coolant into all four RCR cold legs widle the LPI system and ihe core flood tanks inject dinctly into the reactor ven
. After the injection phase is completed, recirculation (ECR) is perfo m
'y the DHR pumps drawing suction from the containment sump and discharging ints "
A
. actor vessel (low pressure recirculation) or to the suction of the HPI pumps (higu
- r. essure recirculation). Heat is transferred to the component cooling water system by the RHR heat v
exchangers.
Simplified drawings of the high pressure injection system are shown in Figures 3.3 1 h,3 3.3 2.
The low pressure injection / recirculation 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 3.3 1.
3.3.3 System Oneration During normal operation, the ECCS is in s andby. Following a LOCA, the core flood tanks will supply borated water to the RCE as soon as RCS pressure drops below accumulator pressure (about 600 psig). A safety feature actuation system (SFAS, see Section 3.5) automatically starts the two HPI pumps, and the two LP! pumps. Ali pumps are aligned to take suction on the BWST.
The shutoff head of the HPI pumps is less than normal RCS operating 1
pressure, therefore the RCS must depressurize somewhat in order to receive makeup from the HPI pumps (Ref.1) For small breaks, operatar 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 BWST water level drops to a prescribed low level setpoint, the low pressum injection pumps are manually realigned to draw a suction from the containment sump a;d deliver water to the RCS cold legs. If depressurization of the RCS proceeds slowly, high pressure recirculation can be accomplished by aligning the discharge of the LPI pumps to the suction of the HPI pumps.
O 23 1/89
Davis Besse Os 3.3.4 System Success Criteria LOCA mitigation requires that the fonctions of ernergency coolant injection, and emergency coolant recirculation be accomplished. The ECl system success criteria for a small LOCA inside containment are the following (Ref.1):
At least one HPl pumm or both makeup pumps take a suction on N BWST and inject into the RCS co d legs Heat is removed via the steam generators by the auxiliary feedwater and secondary steam relief systems (to reduce RCS pressure)
If the above system success criteria are met, then the following ECR success criterion for a small LOCA will apply:
At least one DHR pump is aligned and takes suction on the containment sump, and directs flow to the suction side of the corresponding HPI pump which returns the water to the RCS. This is the high pressure recirculation flow path (Ref. 2, Section 6.3.1.4).
The ECl system success criteria for a large LOCA inside containment are the following (Ref. 2 Section 6.3.2.11).
At least one core Good tank injects into the RCS, and At least one HPl pump takc a suction on the BWST and inject into the RCS cold legs, and At least one DHR pump take a suction on the BWST and inject into the RCS cold legs ECR for a large LOCA can be established by realigning the suction of one DHR pump to the containment sump, 3.3.5 comoonent Information A. High pressure injection pumps 1 1 and 1-2
- 1. Rated flow: 500 gpm @ 2700 ft head (1170 psid)
- 1. Rated capacity: 1007o
- 3. Discharge pressure at shutoff head: 1625 psig
- 4. Type: centrifugal B. Low pressure injection (decay heat removal) pumps 1 1 and 12 1, Rated flow: 3000 gpm @ 350 ft. head (152 psid)
- 2. Rated capacity: 1007o
- 3. Discharge pressure at shutoff head: 186 psig
- 4. Type: cultrifugal C. Core '.lood tariks (2)
- 1. / ceumubtor total volume: 1410 ft3 l
- 2. - Minimsm water volume: 1040 ft3
(]
- 3. Normal operating pressure: 600 psig 9
- 4. Nominal boric acid concentration: 1800 ppm 24 1/89
-. ~
Davis.Besse D. Borated water storage tank O
- 1. Capacity: 550,000 gallons Q
- 2. Minimum water volume: 482,778 gallons
- 3. Design pressure: Atmospheric
Design duty: 30 x 106 Btu /hr 2.
Type: shell and tube 3.3.6 Suonort Systems and Interfaces A. Control signals
- 1. Automatic The ECCS injection subsystems are automatically actuated by the safety features actuation system (SFAS) as described in Section 3.5.
- 2. Remote manual
- a. An SFAS signal can be initiaten by remote manual means from the main control room.
- b. The transit on from the injection to the recirculation phase of ECCS i
operation is initiated by remote manual means.
B. Motive Power
- 1. The ECCS motor-driven Jumps and motor operated valves are Class lE AC loads that can be suppliec from the standby diesel generators as described in Section 3.6.
V C. Other
- 1. Each HPI and DHR pump and the DHR coolers are served from redundant loops of the CCW system (see Section 3.7).
- 2. An external circulaung tube oil system is provided for the HPI oump thrust bearings. The forced lube oil system for each HPI pump util zes two oil pumps, one AC powered and one supplied from 125 VDC. Normal operation utilizes the AC pump. Power sources for these lube oil pumps are listed below:
HPI Pump AC lube nump DC lube numn 11 MCC E12E DC-MCCl 12 MCC-F12A DC MCC2
- 3. ECCS pump room ventilation is discussed in Section 3.9.
3.3.7 Section 3.3. References
- 1. NUREG.0565," Generic Evaluation of Small Break Loss of Coolant Accident Behavior in Babcock and Wilcox Designed 177 FA Operating l'i.:nt", USNRC, January 1980,
- 2. Davis Besse Updated Final Safety Analysis l<eport.
(h g
25 1/89
E E
E 5
e e
9e,a 9 a UnDa a
a e.
e.
eo da da da dz St 8t 8tt St=
oil &Il 9.oli oII l
1 1
1 E
e k
c
.e
~o o
.S.,
m Y
y 5
w SXA 9g sXc g
-e-
!!!5 tZa 4
t$a E
a w
[
2-
,e 6*
67
.9
,5) n' I
k g- ) k G
z e
eX
[a sX j
~
si m
92 A
^
O) [k f 8 hS8 d [k f$
j' G:15
- G 15 o
c.
en e
o g
.9 p
u.
I4 II g
g h
2 a
~
4 v
ye m
1 i
36-1/89-m 3r,m, y w.w -- --
.-%--g
. +
,,e.e-v-
-,+-,s*
3 e
,,,.-4-ur-
+*e-*--ewutu-w+---r a w
-eve-v'-
--e
--eve.-~,v*-w-Tw'*"w
++=e+e-v "s'uwe****-**
t l
HWSi l
l PPIUN
[
l ECCSRM1 l l PENRMS l l
RC
{
i 3
SWST C
79 LO F Ku th FOR r
to Rcs
. RECIRCUL ATION 1
HPI-I LO l M-COLD LEG 2
+
g r
j y
4a atOOP vp i
OH7E
. to -
!2 22 2e 4
- )
heGH PHE SSURE l
Z i
Q'TO HCS
.NKCTICN PUuP HP2O
'+
COLD LEG t 11 26 as (LOOP t)
I 35 TOLPt 83.
PlusP t-1,
[
1556
- 30 29 l PENRM2 l O
"A 9
0 TOuAKEUP, 4 FLOWTEST
{
PuuPs snou 2c.
+
1 33 uAKEUP
- Fu DHXRM l WS asanrup. tes eeuPs y
FRou L
-,Pi-+
~
- 27 2 ' an
.s o
a FORHP
+
_N ~
~
7 TOACS
{,
AECMATION W12 LO HP2A
+
59 COLD LEG 3
$1 LW 2I HsGH PRESSORE
_- M _
TO stCs NJECTION PUuP
+
CClDLEG 4
+
12
(
e 56 itOOP 2)
+-70 LPI 82 PUUP t 2 '
] BWSIVPtf l l ECCSRM2 l Ao l
j Figure 3.3-2.
Davis-Besse High Pressure Injection System Showing Compoaent Locations t
1 i
i i
l I
p-~x
,s %
-ry AJ
%s
.wst
_ FtCo.TE.SYtesE e ee
- fO MStatssG
., m O
wgr.3,
&~,,,,,..
n., -
~g:
- ::2...
Ct. wit esG tene raf SStath ammfER Lorjp a StA CTKM 4DMAD
?
$-t.?<:
h.. St
~
0 k0 5,,
@^%"J"
-r <:
28
(>st3 I-X-
o H
m.
s-to neamg.tJP h
~-s s
.m I
On*64 I-I-
Sim8P
~~~
O
,~. =,
l y,,
.afa.
M,*::=~..
w
=
~
.a J
L J
Es'se?
Dee t 3 C*- N ER N
Doet t 2
,?O set,,
I,'
O O
O x.. _
_ y __ y _
,1 6 e.ar S O
~~~
y_
_y _ y_
<===-~
ste F 23 2*
nr.-vesti
- n..
ca %sme.
Figure 3.3-3. Davis-Besse Low Pressure Injection / Recirculation System cc C
s G
g u
O0 m
s e
n g
r o
. =.
O =
t i
a c
o il L
m.
6-tnenop l
e m
e e.
o s
=
H m.
C
=
=-
_mE in s
=
v e
e.
r g
G
,o s,e w
+
a l
i r
,mC D
o oHp. J A _ & _. Oe aw t
OE o_
m 5
hS i
m I
I e
ts y
l S
4.
n z_
,I io t
I a
l
].
u mc. $m2..
_ =.,N e
e s
,gse.4 c
e e
r
, sa i
.ut c
am
_.t H
" re-a 4
c n
/
I no
~
u om.
5 it c
s e
u I
jn
=
i l
a e.
9 e
a c
r e
a u
s sn s
t m e,mu.
T s
._. g.
S um I
e E
sr T
e P
se r
n ai
.s n w o
i o.m
.c F
e w
t o
L e
I i
s e
s
,w A
=
f e
e B
f
,o T
s L
g i
r v
a s
D L
t F L EAe 8 W OJ 4
+
3 Ma 3
s
~
e ru o
g g,
X.
v.^
iF A.
g i
9u-6 r
r n
m 1yi 1od t
1 j
_Me
t I
Table 3.3-1.
Davis' Besse Emergency Core Cooling System Data Summary for Selected Components i
COMPONENT ID COMP.
LOCATIOrt POWER SOURCE VOLTAGE POWER SOURCE EMERG.
i s
TYPE' LOC ATION LOAD GRP.
f PP PENRM1 l
DH1-1 MDP ECCSRM1 BUS-C1 4160 HvSGRM1 A
DH1-2 MDP ECCSRM2 BUS-D1 4160 tiVSGRM2 B
DH14A NV-DHXFDA UNKtJOWN
~t DH148 NV DHXFDA UNKflOWN Dif1A MOV PENRM2 MCC-F11C 480 PENRM2 B
L DH18 MOV.
PENRM1 MCC-E11 A 480 56SABilALL A
i DH2733 MOV ECCSRM2 MCC-E11 A 480 565ABHALL A
Dil2734 MOV-DHXFDA MCC-F11C 480 PEtJRM2 8
D1163 MOV ECCSHM2 MCC-F11E 480 PP1Uf4 8
t
. U DH64 MOV ECCSHM1 MCC-E11E 480 CRDHf.1 A
Dd9A MOV MKUPRM MCC-F11C 480 PEFJFD.12 B
l DH98 MOVl MKUPRM MCC-Et1 A 480 565ABHALL A
DHX 1-2 iM DHXFDA -
i DHX1 iM DHXRM e
HP2A MOV PENRM2 MCC-F11C 480 PEfJRM2 8
HP2B MOV PENRM2 MCC-F11C.
480 PENRM2 B
I HP2C MOV PENRM1 MCC-Ell A 480 FSABHALL A
HP2D MOV PENRM1 MCC-E11 A 480 565A.BHALL A
HPil-1 MDP ECCSRM1 BUS-C1 4160 tiVSGRM1
-A HPI1-2 MDP ECCSRM2 BUS-D1 4160 HVSGRM2 B
t L
t
{
l
-.. -. - -. - - - ~ - - - - ~ = -,
.-n.,.
-n---.
~.~. -
-. - -.., - - - _ ~,
~ -.
Davis Besse 3.4 MAKEI'P AND PURIFICATION SYSTEM 3.4.1 Svetem Function k
The makeup system, in conjunction with the purification system, is responsible for maintaining the proper water inventory in the Reactor Coolant System and maintaining water purity and the proper concentration of neutron absorbing and corrosion inhibiting chemicals in the reactor coolant.
The makeup function is assumed to be required to maintain tne olant in a long term hot shutdown condition. The makeup system is not considered to x part of the Emergency Core Cooling System (ECCS, see Section 3.3),
3.4.2 Svstem Definition i
The niakeup and purification system provides a means for injection of control poison in the form of boric acid solution, chemical additions for corrosion control, and reactor coolant cleanu) and degasification. This system also adds makeup water to the RCS, draws of a smal side stream of reactor coolant for purification and provides seal water injection to the reactor coolant pump seals.
The functions of the makeup and purification system tee and demineralized waer transferp' umps, pumps, (b) bor following components: (a) the charging (c) primary water (d) makeup tank, (c) bonc acid addition tank, (f) arimary water storage tank (PWS l), (g) deminerahzed water storage tank, and (h) various 1 eat exchangers and demineralizers.
Simplified drawings of the makeup and purification system, focusing on the maxeup portion of the system, are shown in Figures 3.41 to 3.4 4. A summary of data on selected makeup system components is presented in Table 3.4 1, 3.4.3 System Onerntion g
Dunn normal plant operation, one makeup ump is running with its suction aligned to the ma cup tank. The letdown flow from RC cold leg 1 is cooled in the shell g
side of the regenerative heat exchanger then directed to the purification system aid the l
makeup tank. The reactor makeup control system maintains the desired inventory ta the makeup tank. The bulk of the makeup flowls pumped back to the RCS through the tube
-side of the regenerative heat exchanger One makeup line into cold leg 3 is provided. A portion of the charging flow is directed to the reactor coolant pumps through a seal wates injection filter.
l 3.4.4 Svetem %ccess Criterin The following success criterion is assumed for post transient makeup:
i 1 of 2 centrifugal makeup pumps 3.4.5 Cnmnnnent Informntion A. Makeup pumps 1 1 and 12
- 1. Rated flow: 150 @ 2514 psid
- 2. Rated capacity: 100% (based on makeup function)
- 3. Type: centrifugal B. Borated Water Storage Tank (BWST)
- 1. Capacity: 550,000 gallons
- 2. Minimum water volume: 482,778 gallons
- 3. Boron concentration: 1.800 minimum
- 4. Operating pressure: atmospheric l
31 1/89
Davis.Besse C. Makeu) Tank O
- 1. Vo ume: 600 ft3
- 2. Nominal Water Volume: 400 ft3 (about 3000 gallons)
- 3. Operating pressure: 15 to 35 psig D. Boric Acid Addition Tanks
- 1. Capacity: 6893 gallons
- 2. Operating pressure: 15 psig E. Boric Acid Pumps (2)
- 1. Rated capacity: 25 gpm @ 140 ft head (61 psid)
- 2. Type: centrifugal F. Deminemllzed Water Storage Tank (DWST)
- 1. Capacity: 30.000 gallons
- 2. Operating pressure: atmospheric G. Demineralized Water Transfer Pumps (2)
- 1. Capacity: 200 gpm @ unknown head
- 2. Type: centrifugal 3.4.6 Sunnort Systems nnd interfaces A. Control Signals
- 1. Automatic
(
- a. During normal operation, the makeup pumps are automatically controlled by the pressurizer level control system.
- b. The SFAS automatically isolates the nonessential CCW header which supplies the makeup pumps and the makeup pumps are shut down.
- 2. Remote Manual The makeup pumps can be actuated by remote manual means from the control room.
B. Motive Power
- 1. The makeup pumps and motor operated valves are Class IE AC loads that can be supplied from the standby diesel generators as described in Section 3.6.
C. Other
- 1. The makeup pumps are cooled by the nonessentialloop of the component cooling water system.
- 2. Pump lubrication is provided locally.
- 3. The method of makeup pump room ventilation has not been determined.
Od 32 1/89
(O
!!I
/
=
v L
t28 Eta oil t$5 l
4 s-
-l *Si l*
l el m
XI Et I
coEl 2-Sc 5
l n
ijurti -x
}AD t
XnIt Am IPI E
im c
)
i 1
V t! I!
I!
a
?
15 t 5 t!
B l
A
%g i
i !s 5
a 1I "I
S
,1i
$5
$5 1
,e I,
b a
a 1-a! aO i
11 si O
t$= t$-
.i 5i v w-e-e-
/^\\
i_
@Xk 5
iC cN 33 vs9
- L,f.\\<
! [.- [ t [ i,.
i:
I
- E l.jl.i 5
- l r'ti!!;
IlllJ u a
% c.,L g
m..
F+
.c g
T+v g
I QH.
F.4.
+
e a,.
ms cy
=-,e d;a_
l
.a s
s n
=
o
.o i
t ac i
lI o
L g.
gn
- c t
nen l
o fr;a_
oA,*.
o p
m o
e t.u =.
c.
C r-w H"'
bnH_m 8
ut s
E 1
s7rT g
3s5
=F. s fI n
1 V
.oa
~
i c., e 8
w c v8
.t o
hS m
. D W
e l
ts y
S a.
p m +)
e ue l
k a
r M
a
~
e
- m. L.
=
c s
a.
s
.E.
oa S
e D..
- v. c 3
1 4=.
R is B
.. ss.
A 3
f
, s H
r.
s s
c eu
,,s f
, u 5a
, a v
=
a-
,1
~
a vc S
D
,u T..
ath X'l t
a' 2
s rr te e
s
.o "
~
p I
t 4
o m
%a 5
3 ga +
c l
e c
l
.n a
r rp ia" u
e
=
O-o-
g I
F
=
i a'
T v
se c
l
. ba i
(
)
pI L I
Og_o,.
MWo-e r
a i
r r
s-a
=
o m
t 5
~
=
1 I
w4
~wme
10 1
\\'-)
IsE s
!! l+
=1)g 8
d u
a t
b T
b!!
r I
oI!
H i
,! c W-h &
A b
e
$j s-
, 4J i IE "5
s E
p1-e a,
rZK R
6' f
3 tZl
- Il IE E
I 8
III!
28 E
O o
U#
t fil tEl i
^5 3
T ela a
Xi Xi I'
.. ]
i I
X a
r m
X 1
&I I
.e l a a
a:.s I eX o
X j
3 g
a tZ E3EX i
-v-e-i f
X*
- X f
f tf f
f 5
d, 1
-s f
f i
i i
il hX 5l!
i l
fm 1
E!
k!!
!! b"
@!I x-i (p
m-35 1/89 i
i
f l58l9-1 i i i
=ili r
e e g W
e t
8 ogj g_
g i
I o
En lv
-ep
- R k-A-
{
- l -
x-
=
Ig gg n!
a I
.o a.
1 Il-V 5
tZi
.E f
5 5
[
tfl reil Is j
A s
III!
i a
I i
e tXI tEl
. I a
i ip Xi XI i' E
iI:
-X j
t N
1ri o-I I
E X
a g
I.eX
['
5 X.-
i X
tZ E
E-EX E
=
l y-e-1 l
l X
"X f
f f
f f
s a
i
- [.
I s
f f
e!-
i i
?
??
5 e-a a
a ai n
0 1--
g
- - l 8
f c
A t
klp~ ~r su-l..-l b
O--+o-O-c+-
=
t 36
g.s
.s Table 3.4-1.
Davis Besse Makeup and Purification System Data Summary for Selected Components l
COf.tPOtJEf3T ID COf.t P.
LOCATIOri POWER SOURCE VOLTAGE PCWER SOURCE E fA E R G.
TYPE L OC ATIOri LOAD GRP.
BA-T K 1 -1 IK BAltJKIlM BA-1K1-2 IK BAlt!KilfA BA1-1
'MDP BAltJKPM MCC-E11D 480 FAKUPCOft A
BA1-2 FADP BAlf4KliM MCC-F11D 480 f.tKUPCOH B
BWSt IK BWST D117A FAOV BWSTVPIT MCC-F118 480 FACCF11Bilu P
Dil78 MOV BWSTVPIT MCC-El i A 480 565AUllALL A
DWST IK UtJKtJOWN
[
DWX1-1 MDP UtJKfJOWri UfJKtJOWTJ 4
DWX1-2 MDP UrJKfJOWTJ UtJKtJOWt2 DWX1-3 MDP UtJKtJOWri UrJKtJO WiJ U
^
FAU1-1 MDP MKUPRfA BUS-C1 4160 HVSGRM1 A
t.1U1-2 MDP MKUPRM BUS-D1 -
4160 IIVSGRM2 B
MU32 tJV MKUPHM UtJKtJO WTJ MU33 tJV PEtJRM2 UtJKf10 Wri FAU3971 MOV MKUPRM MCC-E11D.
480 MKUPCOR A
e MU3971 MOV FAKUPRM MCC-E11 D 480 UKUPCOH A
MU40 MOV UtJKfJO WiJ MCC-E11 A 480 565ABilALL A
PWSI TK PWST PWX1-1 MDP 585ABilALL MCC-E11C 480 585ABHALL A
PWX1-2 MDP 585ABHALL MCC-F118 480 f.1CCF11Bilt.1 B
i k
t i
I Davis Besse 1
3.5 INSTRUhlENTATION AND CONTROL (I & C) SYSTESIS
! O 3.5.1 Svctem Function
'l Q The instrumentation and control systems include the Reactor Protection System (RPS), Anticipatory Reactor Trip System (ARTS), the Safety Features Actuation System (SFAS), the Steam and Feedwater Line Rupture Control System (SFRCS), the Steam Generator Level Control System and tvstems for the display of plant information to the operators. The RPS, SFAS and SFRCl nonnor the reactor plant, and alert the operator to
- ake 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 SFAS and SFRCS will automatically actuate selected
- afety systems based on the specific limits or combinations oflimits that are exceeded. A remote shutdown capability is provided to ensure the reactor can be brought to a safe condition in the event the main control room must be evacuated.
3.5.2 Svetem Definition The RPS includes sensor and transmitter units, logic units, and output trip relays that operate reactor trip circuit breakers to cause a reactor scram. The ARTS is an input to the RPS. The SFAS and SFRCS includes 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 these systems. Operator instmmentation display s of display panels in the control room and at the Auxiliary Shutdown Panel (ystems consist ASP) that are powered by the 120 VAC and 125 VDC electric power system (see Section 3.6).
3.5.3 Svetem Onerntina A. RPS The B&W RPS has four input instrument channels (1, 2, 3, and 4), each terminating in a channel trip relay that provides an input to four reactor trip mouules. Each reactor trip module is a 2-out of 4 logic unit that is controlled l
by the four input instrument channels. A trip of any two of the four input channels should trip all four reactor trip modules. The scram breaker contacts l
are arranged in what is effectively a 1 out of 2 taken twice logic. RPS trips are i
listed below (Ref.1, Section 7.2):
Manual Overpower High neutron aux (flow biased limit)
High, neutron flux for number and combination of cc,olant Mtp; in operanon High reactor outlet temperature Low RCS pressure High RCS pressure High contamment pressure in addition, the Anticipatory Reactor Trip System (ARTS) provides a trip input to the RPS based on the following (Ref.1, Section 7.4):
O l
38 1/89 l
Davis Besse Loss of both main feedwater pumps Main turbine tri?
Steam and Feec water Line Rupture Control System (SFRCS) trip The manual scram circuit bypasses the RPS logic trains and directly deenergizes the undervoltage coils in the scram breakers, causing these breakers to open.
B.SFAS The SFAS has four input instrument channels (1,2,3 and 4) and a 2-out of-four trip logic that is designed to be failsafe (i.e. a channel will trip upon loss of control power). The four input logic channels monitor the following plant parameters (Ref.1, Section 7.3):
Containment radiation level Containment pressure RCS pressure Essential bus voltag BWSTlevel There are two SFAS output actuation trains, A and B. In general, tne SFAS "A" train controls f:
and the SFAS "B" quipment powered from Class IE AC electrical Division A tram controls redundant equipment powered from Division B. An individual component usually receives an actuation signal from only one SPAS train. The SFAS generates the following signals: (1) high pressure injection actuation, (2) low pressure injection actuation, (3) containment isolation, (4) containment spray actuation, (5) containment fan cooler actuation, (6) CCW system actuation (7) service water system actuation, (8) emergency O
ventilation system actuation, (9) BWST low level alarm, and (10) diese!
Q generator and load sequencer actuation. The control room operators can manually trip the SFAS logic subsystems.
C. SFRCS The SFRCS is an automatic actuation system that performs the following functions (Ref.1, Section 7.4):
Auxil!ary Feedwater System actuation based on the following:
t Loss of both main feedwater pumps Loss of all main coolant pumps Main feedwater or main steam line rupture as determined by:
Main steam pressure drops to 591.6 psig, or Steam generator pressure more than 197.6 psig above. main l
feedwater pressure AFW feed isolation to a faulted steam generator (Ref. 2)'
Main steam or feedwater line isolation following detection of a steam or feed line breach Anticipatory Reactor Trip System (ARTS) input The SFRCS has two redundant,indepehdent actuation channels. Within each actuation channel, one logic channel is AC powered and one is DC powered.
i Both logic channels must trip in order to actuate most components controlled by.
the SFRCS actuation channel.
l l
r s
. v 39 1/89
Davis Besse The SFRCS is a failsafe (deenergize to trip) system, therefore loss of control power will cause the logic to trip.
\\
D. Steam Generator Level Control System When auxiliary feedwater is required, essential level control is provided to maintain the steam generator at an uncompensated level of 99 inches.
E. Auxiliary Shutdown Panel (ASP)
Plant o aerators can establish and maintain a safe hot shutdown condition from the AS? when the main control room is not habitable. The following controls are provided on this panel to accomplish hot shutdewn (Ref.1):
Pressurizer heater controls and control transfer switches (to er from the Main Control Boards)
Auxiliary feed pump governor controls and control transfer switches (to or from the Main Control boards)
Service water isolation valve switches and control transfer switches (to or from the Main Control Boards)
Inasmuch as the station can be maintained in a safe hot shutdown condition from the outside the control room until access to the control room is regained, the need for taking the station to a cold shutdown condition from outside the control room is not anticipated, However, the ability to bring the station to a cold shutdown condition from outside the control room exists with the present station design. Through local controls, all necessary functions can be perfomied outside the control room.
(
3.S.4 System Success Criteria
- 1. RPS The RPS uses hindrance logic (normal = 1, trip = 0) in both the input and output logic. Therefore, a channel will be in a trip state 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 is implemented by the semm circuit breakers which must open in response to a scram signal. Typically, 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 Davis Besse have not been determined.
- 2. SFAS and SFRCS A single component usually receives a signal from only one actuation system output train. SFAS and SFRCS Trains A and B must be available in order to automatically actuate the respective components listed in A, above. The Davis.
l Besse US AR (Ref.1) states that these systems are failsafe (i.e. use hindrance input logic with normal = 1, trip = 0); therefore, the inpjuledq channels will trip on loss of control power. It is not clear if control power is needed for the SFAS and SFRCS to send an actuation signal from the outnut locie to the respective actuated component
- 3. Manually Initiated Protective Actions l
When reasonable time is available, certain protective actions may be performed manually by plant personnel. The control room operators are capable of
/Q operating individual components using normal control circuitry, or cperating U
40 1/89
Davis Besse groups of components by manually tripping the RPS or an SFAS subsystem.
The control room operators also may send qualified persons into the plant to (v
operate components locally or from some other remote control location (i.e., the remote shutdown panel or a motor control center). To make these judgments, data on key plant parameters must be available to the operators.
3.5.5 Suonort Systems and Interfaces A. Control Power
- 1. RPS The RPS input instrument channels are powered from 120 VAC essential distribution panels Yl, Y2, Y3 and Y4 2, SFAS The SFAS input instrument channels are powered from 120 VAC essential Mstribution panels Yl, Y2, Y3 and Y4. The SFAS A and 8 output logic
, uin power sources have not been identified, however, some SFAS solenoid valves are known to be powered from 125 VDC essential distribution panels DlP nnd D2P.
- 3. SFRCS The SFRCS instrument channels are powered from 120 VAC essential distribution panels Y1 and Y2. The power sources for SFRCS DC.
powered logic channels have not been identified.
- 4. Steam Generator Water Level Control System Control power source has not been identified.
- 5. Auxiliary Shutdown Panel The auxiliary shutdown panel is powered from 120 VAC essential distribution panels Y1 and Y2.
(d
- 6. OperatorInstrumentation O)erator instrume'ntation displays are powered from 120 VAC and/or 125 V 3C essential distribution panels.
B. Control Room Emergency Ventilation System
- 1. The emergency ventilation system for the control room area is discussed in Section 3.9.
3.5,6 Section 3.5 References
- 1. Davis Besse Updated Final Safety Analysis Report, Section 7,4.1.6.
- 2. NUREG ll54, " Loss of Main and Auxiliary Feedwater Event at the Davis Besse Plant on June 9,1985", USNRC, July 1985.
yy 41 1/S9
. ~ -
l Davis Besse 3.6 ELECTRIC FOWER SYSTE51 3.6.1 Svctem Function The electric power system supplies power to various equipment and systems needed for nonnal operation and/or response to accidents. The onsite Class IE electric power system suppons 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.
3,6,2 System Definition The onsite Class IE electric power system consists of two 4160 buses, designated C1 and Dl. There are two standby diesel generators connected to the buses.
Diesel generator 1 is connected to bus Cl, and diesel generator 2 is connected to bus Dl.
There are also two 480 VAC load center buses, designated El and Fl. Bus IE is connected to 4160 bus Cl through a transformer, and bus F1 is connected to 4160 bus DI.
Various motor control centers receive their power from the 480 VAC buses Emergency )ower for vital instruments, control, and emergency lighting is supplied by four 125 V JC station batteries. The batteries energize four DC distribution centers, designated DIP, DIN, D2F, and D2N Four 120 VAC instrument buses are connected to the DC distribution centers through inverters.
A simplified one line diagram of the 4160 and 480 VAC electric power system is shown in Figure 3.61. Additional details of the 480 VAC distribution system are shown in Figure 3.6 2. The 125 VDC and 120 VAC distribution systems are shown in Figure 3.6 3. A summary of data on selected electric power system components is presented in Table 3.61. A partiallisting of electrical sources and loads is presented in Table 3.6 2, 3,6,3 Svetem Ooerntion p
During normal operation, the Class IE electric power system is supplied by Q
station service power from the main generator and the 345 kV switching ~ station. The normal source for 4160 buses C1 and D1 is the 345 kV system, via two station auxiliary transformers and two 13.8 kV buses. The transfer from the pteferred power source to the diesel generators is accomplishtd automatically by opening the normal source circuit breakers and then reenergizing the Class IE portion of tbe electric power system from the diesel generators. Following a start command, each diesel generator is designed to reach rated speed and be capable of accepting loads within 10 seconds.
The DC power system normally is supp!!cd through the battery chargers, with the batteries " floating" on the system, maintaining a full charge. Upon loss of AC power, the entire DC load draws from the batteries. The batteries can support the design DC load for about one hour.
The 120 VAC vital buses nomially receive power from DC distribution centers through an invener.
Redundant safety equipment such as motor driven pumps and motor operated valves are supplied by different Class IE buses. For the purpose of discussion, this equipment has been grouped into " load groups". Load group "AC/A" contains components receiving electric power either directly or indirectly from 4160 bus C1 Load group "AC/B" contains components powered either directly or indirectly from 4160 bus Dl.
Components receiving DC power or 120 VAC power are assigned to load groups "1" to "4", based on the battery power source.
3,6,4 Svctem Success Criterin Basic system success criteria for mitigating transients and loss of coolant accidents are defined by front-line systems, which then create demands on support (O
()
42' 1/89
Dads Besse systems. Eiecnic power system success criteria are defined as follows, without taking bl credit for cross ties that may exist between independent load groups:
V Each Class lE DC load group is supplied initially from its respective battery (also needed for diesel stanlag)
Each Class lE AC load group is isolated from the non Class lE system and is supplied from its respective emergency power source (i.e. diesel generator)
Power distribution paths to essential loads are intact Power to the battery chargers is restored before the batteries are exhausted 3.6.5 Comnonent Information A. Standby diesel generators (2)
- 1. Maximum continuous rating: 2600 kW
- 2. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating: 2860 kW
- 3. Rated voltage: 4160 VAC
- 4. Manufacturer: GeneralMotors B. Batteries (4)
- 1. Rated Voltage: 125 VDC
- 2. Capacity: approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with design loads (Ref 1, Section 8.3.2.1.2) 3.6.6 Sunnort Systems nnd interfaces A. Control Signals
- 1. Automatic h
The standby diesel generators are automatically started based by the Safety V
Features Actuation System (SFAS, See Section 3.5)
- 2. Remote manual The diesel generators can be started, and man can be operated from the main control room. y distribution circuit breakers B. Interlocks
- 1. The third of a kind CCW and SW pumps are powered from bus CD via interlocked circuit breakers that permit the load to be aligned to either bus Cl or Dl, but not both.
- 2. Interlocks prevent more than one CCW and SW pump from being powered from a given diesel pencrator at a given time cannot be energized if the A and B pumps are o(i.e, the third of a kind pump perating',.
C. Diesel Generator Auxillary Systems
- 1. Diesel Cooling Water System Heat is transferred from a jacket water system to the component cooling water system (see Section 3.7).
- 2. Diesel Starting System The air starting system for each diesel is capable of multiple start attempts without requ; ring AC power to recharge the starting air accumulators.
- 3. Diesel Fue; Oil Transfer and Storage System A 5000 gallon " day tank" for each diesel generator provides for approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> of operation. The day tanks are automatically replenished.from separate underground storage tanks during engine b
43 1/89
Davis Besse operation. A fuel oil transfer pump is activated by a level switch on the day tank. This system is shown in Figure 3.6 4 O
- 4. Diesel Lubrication System Each diesel generator has its own lubrication system.
S. Combustion Air Intake and Exhaust System This system supplies fr:sh air to the diesel intake, and directs the diesel exhaust outside of the diesel building.
- 6. Diesel Room Ventilation System This system is described in Section 3.9.
D. Other Emergency ventilation systems for AC switchgear and battery rooms are discussed in Section 3.9.
3.6.7 Section 3.6 References
- 1. Davis Besse Updated FSAR. Toledo Edison Company.
OV I
i 1
/^T U
44 1/89 4
4
..-~~_a__.
_~-m.-
--_m.._--
_.m-
- ~~ _.. -
..m..
._.-4 TO M6 KV rh0MESMV FRou blKV tmTCHYARD'
$MTCwvARD SMTCHVARD o
o n
3 VAN 4
TRANSFORutR = M s
23.7F345KV 1
STARTUP STARfpp U
MNt Mto TRAN570RVERC1 O g CQ TRANSFORutR02 34Wt$ $
W13 8 j
1
]-
AutittARY j
TRANssonven _,
twis s<V i
[ iwv swacmi;an sus a l 1 is s<v swneworan sus e 1 1
i i
g xtuR ac xrun eo e d
is a +ie i3 e e4.is I
11-t i
I a tenv smiegtan aus c l I 4 isav swife%Esa sus os I
{
EPA 1:
E8 Oct J
f i
g EP-CBig 15 g EPC82g W
-l 4 iso vac sus ci l-l 4 iso vac acs oi j
j ll 11 bb bb il l'1 t*4tti 41ao4ao gg g g csia 0711)00:3 Og EP oria diso4ao p...g y...y I
I 1 3-is y
9 e
l assa vAc fgNSFER l
.ao vac aus s i 1
g e gq
[
46Hac BvS H
].
j 11 1111 II l1.11 an co giqii, i, q,
t d'
.ll 3c-s i nna io Ei 1 I ucc-tis <asoF1 I ucc.sitia io si 1 -
. [ uce si
,a aa, j -
i I WCC-E i?ia io O l
[.uCC s 17 la to 01 l 4
e i
i l-e e-if 11 l
H I ucc tsire 1 p.. 4 j
l ucc-t s ira I.
i l uce tis 1
Ib***-
I ucc.s i4 I
-I ucc-s is 1-I ucc Eis I
i ucc s is l
[
i.. 4
- r
'9....
i 5
I
.I.6ucctFt6 I-
- o-s I
l-
-l l-Figure 3.61., Davls Besse 4160-and 480 VAC Electric Power System. -
45 l/89
.-r, r --w-e m sww -.--%we e
- *w w.wre e--+-te~a+
+,
- .*r--r..-=*
we-,-
. r e w-ee e.,- m -m - %-.
. ve-.w w-m, v c e'--%e,~-,,
. -. -...- ~ _. _. - -. -. _... _ -. - -. -. _ -.. - - - - -
l ochui l
l imineur l l
puHua l
I vec4 ies l l uccisire j IF I
l VCC E 170 l
[ vc0Ft?D l
[_UCCs173 1 f9Cc.s 120 l l9
+
l A(3GhM3 l MVSQMut l DVSci 1
[ WCC E itC _ l l VC4 $ 'PC 1 l
BUSOi j
O h
E S
l-1 I
I i
l Lvbanui l l LvacHua l t
tun TMN CE t t Dri2 7-i e
S
{ aus4i l l susse l 6
I I
i e
e E
E l
l ucct+2a l I ucc.s ita l I ) ii i
i i
le e a e W W W l'
l 1...
e.
I
! ucc.esira 1 l sesauMaLL l,
[ totcietawwa l
[ ucc.s o a l
.I vcc4 na I l
}
I I
i W 8 8
! I I I e5ea 1
I l
l l
v e
t
+
+
i I vecEne 1I ucc. enc l l uccano l
. I ucc4oo 1 l ucca nO I occ s n.
I n
l sesaDMALL l l wnupcon ]
l uccriisnu {
ethaus [
l E
B l
l Tc4 'E I
-1 i ucc siet 1 I ucesnt ]
I l
u
"*638 ONLY e
= - -
l l caonu l
- j g yec,g, i
perum l
NOTE: UNES MAY NOT REPRESENT TRUE CABLE ROUTING BETWEEN ROOMS.
Figure 3.6 2.
Davis Besse Details of 480 VAC Electric Power Distribution 46 1/h9 J
.-----.m
~
..__,_,mm....
,.m.,,_,,,,.
,~m
,,,.-,,_,..,..,,-rnwy--ey..p.v
FADM FACM rn M MCC E11D Fnou FROM MCC F11D rRoM MCC E12A l
MCC F12A n
I BATT BC CATT l
l BATT BC EAIT f
/
i iP 1FN 2
1N DC EC 2P E
( j,C 2PN 2N BC P
2 E
IN 2P 2 j
2 2N i
i l
I i
l i
I I
I T
l s
a C
o a
a e
a p
Q u
e l
- C ucci l l DCi.cGi l t DC uCC:
l l DC uCC2 l
l e
a l
i a
p l
6 m
I I
6 m
?
??
?
?t 70 TO CHANNEL A T2 TO CHANNEL B 125 VDC 250 VDC LCADS 125 VD*
250 VDC LOADS A LC ADS yegg 7;qo gp3 DLOADS y
C E
Q Q
E Q
E
[ iss CC C bT PANEL OtP l ESS DC D ST P ANEL 01N l l ESS DC Dibi PANEL dip l [ LSS DC DIST PANEL din l l
u a
a u
l e
u l
m a
?
FACM t
FACM t
FROM V
FAOM TOESS MCO.E12A TO ESS MCC E12A TO ESS MCC F12 A TO ESS MCC-F 12 A 125 VDC
}
125 VOC y
125 VDC 175 VDC y
LCADS LOADS LCADS LOADS yj)T MANNEL "yp p ET AE T E
CHANNE E
CHANNE 2
CHANNEL g
y yp
'n-I l
I I
lDC DiST PANEL DAPl lDC D ST PANEL CANl lDC DiST PANEL DDPl
{DC DIST PANEL C8]
Na E2 E4
- )
I
'l I
IJ - h 5-h 5-h 5 -h l E5s INST Ddi PANEL Y1 l
[ CSS INST D67 PANEL r3 l
{ ESS INST DIST PANEL 12 l
@S INbi DiST PANEL v4 l t
t ir
?
TO ESS TO ESS TO ESS TO ESS 120 VAC 120 VAC 120 V AC 120 VAC LOADS.
LOADS.
LOADS.
LOADS.
CHANNEL 1 CH ANNEL 3 CHANNEL 2 CHANNEL 4 e
F AOM AECULATED ->-
- FACM AEGULATED ->
g.....h INST OfST PANEL YAR h.....h INST D!ST PANEL YD A I
l l ESS iN5T C:ST F ANEL V1 A l l ESS INST D!ST PANEL Y2A l l
i t
t
, TO ESSENTIAL TO ESSENTIAL POWE A SUPPLY SYS POWER SUPPLY SYS CHANNEL 1 CHANNEL 2 (O
g' Figure 3.6 3.
Davis Besse 125 and 250 VDC and 120 VAC Electt!c Power Systems 47 1/89
t I
f EMERGEi
- L 1 f 56 A L LJ l
Vm
}
21 f
EMERGENCY DIESEL FUEL Oil STORAGE 83 TANK 1-1 1 F_1r w
l
> FUEL i
49 TO DIESEL t
(.'
j DAY GErJERATOR 1-1 f
^
1-1 3 y
[
TRATJSF6R
$8 PUMP 1-1 10G j
22 j
EME41GEtJCY DIESEL FUEL Olt S TOHAGE 84 I I i
101 TANK 1-2
'P'P 2 k I
(
]-
> FUEL f
DAY 53 TO DIESEL
(
--)
GErJERATOR 1-2 TAf1K TRAtJSFER 1-2 c
. PUMP 1-2 Figure 3.6-4. Davis Besse Diesel Generator Fuel Oil Storage and Transfer System
]
d1..
..,__.__._4
y D
Tah ie 3.6-1.
Davis Besse EicCtric Power System Data Summary for Selected Components COMPOf4 Etat ID COMP.
LOCATIOf4 POWER SOURCE VOLTAGE POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
BA FT-ItJ BAT BATTRMA A
BATT-1 P OAT BATTHMA A
BATT-2tJ 1.T BATTRMB B
BATT-2P
' BAT BtTTRMB B
BC-1N BC LVSGRM1 MCC-E12A 480 LVSGRMt
.A BC-1P BC LVSGRM1 MCC-E12A 480 LVSGRM1 A
BC-1PtJ BC LVSGRM1 MCC-E11D 480 MKUPCO'l A
BC-2r4 BC LVSGRM2 MCC-F12A 480 LVSGRLt2 B
BC-2P BC LVSGRM2 MCC-F12A 480 LVSGRM2 B
BC-2PtJ BC LVdGRM2 MCC-F11D 480 MKUPCOR B
BUS-C1 -
BUS HVSGRM1 EP-DG1 4160 DGHM1 A
g C-BUS-D1 BUS liVSGRM2 EP-DG2 4160 DGEM2 d
BUS-Et BUS LVSGRM1 EP-CE11 480 LVSGRM1 A
BUS-F1 -
BUS LVSGRM2 EP-DF12 480 LVSGRLt2 B
DC-MCC1 MCC LVSGRM1 BATT-1P 125 BATTRMA A
DC-MCC1 MCC LVSGRM1 BATT-1N 125 BATTRMA A
DC-MCC1 MCC LVSGRM1 BC-1 P 125 LVSGRM1 A
DC-MCC1 MCC LVSGRM1 BC-1TJ 125 LVSGRM1 A
DC-MCC1 MCC LVSGRM1 BC-1PtJ 125 LVSGRM1 A
DC-MCC2 MCC-LVSGRM2 BATT-2P 125 BATTRMB B
DC-MCC2 MCC LVSGRM2 BATT-2N 125 BATTR*AB cB OC MCC2 MCC LVSGRM2 BC-2P 125 LVSGRM2 B
1&MCC2 MCC LVSGRM2 BC-2tJ 125 LVSGHM2 lB t
DC-MCC2 MCC LVSGRM2 BC-2Pfl 125 LVSGRM2 8
EP-CB1 CB.
HVSGRM1 EP-CB2 CB HVSGRM2 EP-CE11 TRAri LVSGRM1 BUS-C1 4t60 HVSGRM1 A
EP-DF12 TRAtJ LVSGRM2 BUS-D1 4160 tiVSGHLt2 B
j t
Table 3.6-1.
Davis Besse Electric Power System Data Summary for Selected Components (Continued) a 4
COMPOt4EtiT ID COMP.
LOCATIOtt POWER SOUP.CE VOLTA GE POWER SOURCE EMERG.
TYPE LOCATIOtt LOAD GRP.
EP-DG1 DG DGRM1 EP-DG2 DG DGRM2 l
INV-YV1
!?N LVSGRM1 PNL-D1P 125 LVSGRM1 1
g INV-YV1 ITN LVSGRM1 RECT-YRF1 125 LVSGRM1 1
ItW-YV2 ifN LVSGRM2 PNL-D2P I125 LVSGRM2 2
~
INV-YV2 IfN LVSGRM2 RECT-YRF2 125 LVSGRM2 2
IfW-YV3
!tW LVSGRM1 PNL-D1N 125 LVSGRM1 3
IfN-YV3 ITN LVSGRM1 RECT-YRF3 12.5 LVSGRM1 3
IfW-YV4 ITN LVSGRM2 PtJL-D2N 125 LVSGRM2 4
ITN-YV4 ITN LVSGRM2 RECT-YRF4 125 LVSGRM2 4
MCC-Ell A MCC 565ABHALL BUS-E1 480 LVSGHM1 A
MCC-E118 MCC 585ABHALL MCC-E11 A 480 565ABHALL A
MCC-E11C MCC 585ABHALL-MCC-E11 A 480 565ABHALL A
MCC-E11D MCC MKUPCOR MCC-Ell A 480 565ABHALL i
MCC-E11E
'MCC CRDRM MCC-E11C 480 585ABHALL A
MCC-E12A MCC LVSGRM1 BUS-El 480 LVSGRM1 A
MCC-E128 MCC DGRM1 MCC-E12A 480 LVSGRM1 A
MCC-E12C MCC INIKPMP MCC-E12A
. 480 LVSGRM1 A
MCC-E120 MCC INIKPMP MCC-E12C 480 LVSGRM1 A
MCC-E12E PACC PPIUN MCC-E12A 1480
.LVSGRM1 A
MCC-E12E MCC PPTUN MCC-E11E 480 CRDRM A
MCC-E12F MCC DGRM1 MCC-E128 480 DGRM1 A
MCC-E14 MCC LVSGRM1 BUS-E1 480 LVSGRM1 A
M MCC-E15 y.r/
LVSGRM1 BUS-E1 480 LVSGRM1 A
t' MCC-EF12C
.jMCC INIKPMP MCC-E12C 480 ItJTKPUP A
i MCC-EF12C MCC INIKPMP MCC-Ft2C 480 INIKPt.1P B
MCC-EF12D fACC LVSGRM1 MCC-E12A 480 LVSGRM1 A
MCC-EF12D MCC LVSGRM1 MCC F12A 480 LVSGRM2 B
~
i
\\,3 G
V Table 3.6-1.
Davis Besse Electric Power System Data Summary for Selected Components (Continued)
COMPONENT ID COMP.
LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
MCC-EF15 MCC LVSGRM1 MCC-E15 480 LVSGRMI A
MCC-EF15 MCC LVSGRM1 MCC F15 480 LVSGRM2 B
MCC-F11 A MCC ELECTPENRM2 BUS-F1 480 LVSGRA:
8 MCC-F118 r.1CC MCCF11BRM MCC-F11 A 480 LVSGRM2 8
MCC-F11C MCC PENRM2 MCC-F11 A 480 LVSGRM2 B
MCC-F11D MCC MKUPCOH MCC-F11 A 480 LBSGRM2 B
TiCC-F11F MCC PPTUN MCC-F11E 480 PPTUN B
MCC-F12A MCC LVSGHM2 BUS-F1 480 LVSGRM2 8
MCC-F128 MCC DGRM2 MCC-F12A 480 LVSGRM2 B
MCC-F12C MCC INIKPMP MCC-F12A 480 LVSGRM2 B
P1CC-F12D MCC INIKPMP MCC-12C 480 If4TKPMP B
MCC-F13 f3CC TB603 BUS-F1 480 LVSGRM2 B
MCC-F13 MCC TB603 BUS-El 480 LVSGRM1 A
MCC-F14 MCC LVSGRM2 BUS-F1 480 LVSGRM2 B
MCC-F15 MCC LVSGRM2 BUS-F1
,480 LVSGRM2 8
PNL-DIN PNL LVSGRM1 DC-MCC1 I125 LVSGRf.11 3
i PNL-D1 P PNL LVSGRH1 DC-MCC1 125 LVSGRt.11 1
1 PNL-D2N PNL LVSGRM2 DC-MCC2 125 LVSGRM2 4
PNL-D2P PNL LVSGRM2 DC-MCC2 125 LVSGRM2 2
PNL-DAN PNL LVSGHMI PtJL-DIN 125 i_VSGflM1 3
PNL-DAP PNL LVSGRM1 Pfft-D1 P 125 LVSGRM1 1
PtJL-DBt1 PfJL LVSGRM2 PtJL-D2N 125 LVSGRM2 4
PNL-DBP PNL LVSGRM2 PNL-D2P 125 LVSGRM2 2
g PNL-ESS-Y1 PNL LVSGRM1 ItJV-YV1 120 LVSGRM1 1
PNL-ESS-Y2 PNL LVSGRM2 ItJV-YV2 120 LVSGRF12 2
PNL-ESS-Y3 PNL LVSGRM1 INV-YV3 120 LVSGRM1 3
Pt1L-ESS-Y4 PtJL LVSdRM2 ItJV-YV4 120 LVSGRM2 4
PNL-Y1 A PNL UtJKtJOWN INV-YV1 120 LVSGRM1 A
l
2 o
Table -3.6-1.
Davis Besse Electric Power System Data Summary for Selected Components (Continued)
COMPONENT ID COMP.
LOCATION POWER ' SOURCE VOLTAG E POWER ' SOURCE EMERG.
L
--T Y P E LOCATION LOAD GRP.
PNL-Y2A
'PNL UNKNOWN INV-YV2 '
120 LVSGilM2 B
RECT-YRF1 RECT LVSGRM1 MCC-E12A 480 LVSGilM1 1
RECT-YRF2 RECT LVSGRM2 MCC-F12A,
480 LVSGRM2 2
t RECT-YRF3 RECT LVSGRM1 MCC-Ei2A 480 LVSGRM1 3
RECT-YRF4 RECT LVSGRM2 MCC-F12A -
480 LVSGRM2 4
e r
k
}
l 1
h i
i Q -.
I
,.t i
k i
.... _. ~. _ _
TABL'i 3.6 2.
PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT DAVIS BESSE
[T POWER YOLTAGE EMERG POWER SOURCE LOAD LOAO COMP COMPOt'EN I t
SOURCE LOAD GRP LOCATION SYSTEM COMPONENT 10 TYPE LOCATION INV YV4 120 4
LVSGRM2 EP PNL ESS-Y4 PNL LVSGAM2 BATT.1 N 125 A
BATTRMA EP OC MCCI MCC LVSGRM)
B A T T.1 P 125 A
DATTRMA EP OC-MCC1 MCC LVSGRM1 BATT 2N 125 B
BATTRMB EP OC-MCC2 MCC LYSGRM2 BATT 2P 125 B
BATTRM8 EP OC MCC2 MCC LVSGRM2 BC-1 N 125 A
LVSGRMI EP OC MCC1 MCC LVSGAMI BC-IP 125 A
LVSGRMI EP OC-MCC1 MCC LYSGAM1 BCIPN 125 A
LVSGRMI EP OC MCC1 MCC LVSGRM1 BC-2N 125 8
LVSGRM2 EP OC MCC2 MCC Lv5GRM2 BC 2P 125 8
LVSGRM2 EP OCMCC2 MCC LYSGRM2 BC 2PN 125 B
LVSGRM2 E f' DCr/CC2 MCC LVSGAM2 BUS-C 1 4160 A
HVSGRM1 CCW bub-CD OUS ASOPNL BU S-C )
4160 A
HVSGRM1 CCW CCW11 MOP CCHARM BU S-C 1 4160 A
HVSGRM1 ECCS OH 1 1 MOP ECCSRM1 BUS C1 4160 m
HVSGRM1 ECCS HPil 1 MOP ECCSRM1
/\\
BU S-C 1 4160 A
HVSGRM1 EP EP CE11 TRAN LVSGRM1 BUS C1 4160 A
HVSGRM1 MKUP MU11 MOP MAUPRM BUS-C 1 4160 A
HVSGRM1 SW BUS-CD BUS ASOPNL BUSC1 4160 A
HVSGRM1 SW SW11 MOP INIKPMP BUS CD 4160 A/B ASOPNL CCW CCW13 MOP CCHXRM BUS-CD 4160 A/B ASOPNL SW SW10 MOP INTKPMP BUS 01 4160 8
HVSGRM2 CCW BUS-CD BUS ASOPNL BU S-01 4160 8
HVSGRM2 CCW CCW12 MOP CCHXRM BUS 01 4160 8
HVSGAM2 ECCS OH12 MOP ECCSRM2 BUS-01 4160 0
MVSGRM2 ECCS HPil-2 MOP ECCSRM2 BUS 01 4160 0
HvSGAM2 EP EP OF12 TRAN LVSGRM2 BUS-01 4160 8
HVSGAM2 MKUP MU12 MOP MKUPRM BUS 01
. 4160 8
HVSGRM2 SW BUS-CD BUS ASOPNL BUS-01 4160 0
HVSGRM2 SW SW12 MOP IN IKPMP BUS El 480 A
LVSGRM t EP MCC EllA MCC 565ABHALL O[
B%$ El 480 A
LVSGRM 1 EP MCC E12A MCC LVSGRM1 53 1/39
TABLE 3,6 2.
PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT DAVIS BESSE (CONTINUED)
(h POWER VOLTAGE EMERG POWER SOURCE LOAO LOAO COMP COMPONENT lV 1
SOURCE LOAO GRP LOCATION SYSTEM COMPONENT 10 TYPE LOCATION BUS El 480 A
LVSGRMI EP MCC E14 MCC LVSGRM1 BUS El 460 A
LVSGRMI EP MCC E15 MCC LVSGRMt BUS El 480 A
LVdGRM t EP 1CC F13 MCC T8603 BUS-F 1 480 8
LVSGRM2 EP MUTF11A MCC ELECTPENRM2 BUS-F 1 480 8
LVSGAM2 EP MCC-FIM MCC LVSGRM2 BUS F1 480 8
LVSGRM2 EP MCC F13 MCC T8603 B US-F 1 480 8
LVSGRM2 EP MCC F14 MCC LVSGRM2 BUS F1 480 8
LVSGRM2 EP MCC4-15 MCC LVSGRM2 OC-MCC1 125 A
LVSGRM)
AFW AFW106 MOV 623A8HVACAR EA OC MCC) 125 A
LV5GRM1 AFW AFW360 MOV AFPRM1 DC-MCC1 125 A
LVSGAMt AFW AF W3870 MOV AFPRM)
OC MCC1 125 A
LVSGRM1 AFW AFW3870 MOV AFP RM1 OC MGC1 125 3
LVSGRMI EP PNL 01N PNL LVSGRMI OC-MCCl 125 1
LYSGRM)
EP PNL 01P PNL LVSGRM1 OC MCC2 125 4
LVSGRM2 EP PNL 02N PNL LVSGRM2 OC MCC2 -
125 2
LYSGRM2 EP PNL 02P PNL LVSGAM2 EP CE11 480-A LVSGRM1 EP BUS El BUS LvsGRM1 EP OF12 480 8
LVSGRM2 EP BU S-F i BUS LVSGRM2 EP OG1 4160 A
OGRM1 EP BU S-C1 BUS-HvSGAMI EP-OG2 4160 8
OGRM2 EP BUS 01 BUS HVSGRM2 ICS A/8 AFW MS11 A NV MNS TMRM I ICS A/8 AFW MS t 18 NV MNSTMAM2 INV YVi 120 1
LVSGRMI EP PNL ESS Y1 PNL LVsGRM t INV YVt 120 A
LVSGRM1 EP PNL Y1 A PNL bNKNOWN
~
INV YV2 120 2
LVSGAM2 EP PNL ESS Y2 PNL LVSGRM2 (NV YV2 120 8
LVSGAM2 EP PNL Y2A PNL UNKNOWN INV YV3 120 3
LVSGRM1 EP PN L-ESS-Y3 PNL LVSGRM1 MCC 12C 480 B
INTKPMP EP MCC-F 120 MCC INIKPMP MCC EllA 480 A
565ABHALL ECCS OH18 MOV PENRMt MCC EllA 480 A
565ASHALL ECCS OH2733 MOV ECCSRM2 MCC EllA 480 A
565ABHALL ECCS OH78 MOV BWSTVPIT C/
1 54 1/89
\\
TABLE 3,6 2.
PARTIAL LISTING OF ELECTRICAL SOURCES AND LOALS AT DAVIS BESSE (CONTINUED)
\\
POWER VOLTAGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT 10 TYPE LOCATION s
MCC EllA 480 A
565A8 HALL ECCS DH98 MOV MKUPRM MCC Ell A 480 A
565A8 HALL ECCS HP2C MOV PENRMI
~
MCC E11 A 480 A
$65A8 HALL ECCS HP20 MOV PENRM1 MCC Ell A 480 A
565ABHALL EP MCC E118 MCC 585A8H Al.L MCC Ell A 480 A
565A8 HALL EP MCC E11C MCC 585A8 HALL MCC EllA 480 A
565A8 HALL EP MCC E11D MCC MKUPCOR MCC EllA 480 A
565ABHALL MKUP OH78 MOV BWSTVPli MCC-Ell A 480 A
565A8 HALL MKUP MU40 MOV UNKNOWN MCC E118 480 A
CRORM Af W AF W608 MOV PENRMJ.
MCC E116 480 A
585A8 HALL
^ Td DH12 MOV RC F4 MCC E118 480 A
$85ABHALL RCS MU2A MOV RC MCC E118 480 A
585ABVALL RCS MU2B MOV RC MCC E11C 480 A
$85ABHALL EP MCC E11E MCC CRORM MCC E11C 480 A
585A2 HALL MKUP PWAl1 MOP 585A8Hr.L O,
MCC E11C 480 A
585A8 HALL VENT CCW FAN 1 FAN CCHXRM l
MCC-E 110 480 A
MKUPCOR AFW AFW786 MOV AFPRMt MCC E110 480 A
MKUPCOR EP BC1PN BC LVSGRMI MCC-E110 480 A
MKUPCOR MKUP BA1 1 MOP BATN> 9M MCC-E 110 480 A
MKUPCOR MKUP MU3971 MOV MKUPRM MCC-E 110 480 A
MKUPCOR MKUP MU3971 MOV MKUPRM MCC EllE 480 A
CRORM AFW AFW3869 MOV AFPRM1-MCC E11E 400 A
CRORM ECCS OH64 MOV ECCSRM1 MCC E11E 480 A
CRDRM EP MCC-E12E MCC PPTUN MCC E12A 480 A
LVSGRM1 AFW SW1382 MOV AFPRM1 MCC E12A 480 A
LVSGRM1 CCW CCW5095 MOV CCHX1M MCC E12A 480 A
LVSGRM t EP BC1N BC LVSGAMI MCC-E 12A 480 A
LVSGRM1 EP BC1P BC LVSGRMt MCC-E 12A 480 A
LVSGRM1 EP MCC-E 128 MCC DGRM1 MCC E12A 480 A
LVSGRM)
EP 1-E 12C MCC INTKPMP MCC-E12A 480 A
LVSGRM1 EP MCC E12E MCC PPTUN MCC E12A 480 A
LVSGRM1 EP MCC EF120 MCC LVSGRM1 v
55 1/89
TABLE 3.6 2.
PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT DAVIS BESSE (CONTINUED)
^[h POWER VOLTAGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT i,
)
SOURCE LOAD GRP LOCATlON SYSTEM COMPONENT 10 TYPE LOCATION MCC E12A 480 1
LVSGRMI EP RECT YRFt RECT LVSGRM1 MCC E12A 480 3
LV.SGAMI EP RECT-YHF3 RECT LVSGRMt MCC E12A 480 A
LVSGRM1 RCS P2R HTR A HTR RC MCC E12A 480 A
LVSGRM1 VENT AFW-FAN 1 FAN AFORM1 MCC E12A 480 A
LVSGRM1 VENT CR COND 1 CONO CR MCC El?^
480 A
LVSGRM1 VENT
- CR-FAN I FAN CR MCC E12A 480 A
LYSGAM1 VENT LV+AN 1 FAN LVSGAMI MCC E12A 480 A
LVSGRM1 VENT LV FAN El FAN LVSGRM1 MCC E120 480 A
OGRMI AFW AF W106A MOV 623ABHVACAR EA MCC E128 480 A
DGRM)
AFW AF W106A MOV 623ABHVACAR EA MCC E128 480 A
OGRMt EP MCC-E l2F MCC DGRM1 MCC-E 128 480 A
OGRM1 VENT BATT FAN 1 FAN BATTRMA MCC.E 128 480 A
OGRM1 VENT OG FAN 1 FAN OGRMI MCC-E t 2 B 480 A
OGRM)
VENT OG-FAN 2 FAN OGRM1 MCC E12C 480 A
LVSGRM1 EP MCC E120 MCC IN TKPMP p\\
iG MCC E12C 480 A
INIKPMP EP MCC EF12C MCC INIKPMP MCC-E12C 480 A
INIKPMP SW SW1399 MOV SWPPTNL MCC E12C 480 A
IN TKPMP SW SW2929 MQ/
SWPPTNL MCC E12C 480 A
INTKPMP SW SW2931 MOV SWPPTNL MCC E12E 480 A
PPTUN AFW AFW608 MOV PENRM3 MCC E12E 480 A
PPTUN VENT CR CONO-SBY CONO CR MCC-E 12 E 480 A
PPTUN VENT ECCS-FCU-4 FCU ECCSRMt MCC E12E 480 A
PPTUN VENT ECCS-FCU-5 FCU ECCSRM1 MCC-E 14 480 A
UNKNOWN VENT RC-FCU 1 1 FCU RC MCC E15 480 A
LVSGRM1 EP MCC EFIS MCC LVSGRM1 MCC EF15 480 A/B UNKNOWN VENT RC FCU-13 FCU RC MCCfi1A 480 B
ELECTPENRM2 AFW AF W 107 MOV 623ABHVACAR EA MCC F11A 480 0
ELECTPENRM2 AFW AFW599 MOV PENRM4 MCC-F 11 A 480 B
ELEC TPENRM2 AFW AFW599 MOV PENRM4 MCC F11A 480 B
ELECTPENRM2 CCW C CW5096 MOV CCHXRM
/
MCC Fila 480 B
LVSGRM2 EP MCC Fi tB MCC MCCF11BRM
'J 56 1/S9
TABLE 3.642.
PARTIAL LISTING OF ELECTRit m. SOURCES AND LOADS AT DAVIS DESSE (CONTINUED)
POWER VOLTAGE EMERG POWER SOURCE LOAO LOAD COMP COMPONENT g
SOURCE LOAD GRP LOCATION SYSTEM COMPONENT 10 TYPE LOCATION MCC F11A 480 B
LVSGRM2 EP MCC F11C MCC PENRM2 MCC Fil A 480 B
LBSGRM2 EP MCC-F 110 MCC MKUPCOR MCC Fila 480 B
ELECTPENRM2 RCS DH11 MOV RC MCC Fi1A 480 B
LVSGRM2 RP MCC Fi1E MCC PPTUN MCC F11A 480 8
ELECIPENRM2 VENT CCW FAN 2 FAN CCHXRM MCC-F 11 A 480 8
ELECTPENRM2 VENT CR COND 2 CONO CR MCC F118 480 B
MCCF t 1BRM AFW AF W107 A MOV 623ABHVACAR EA MCC-F 11B 480 B
MCCF 11BRM ECCS OH7A MOV BWSTVPIT MCC F118 480 B
MCCF11BRM MNUP DH 7A MOV BWSTVPti MCC Fi1B 480 8
MCCF t 1BRM MKUP PWX12 MOP 585A BH ALL MCC F116 480 B
MCCF i t BRM VENT CRFAN2 FAN CR MCC F1 t C 480 B
PENAM2 AFW SW1383 MOV PENRM2 MCC F t 1C 480 B
PENRM2 ECCS DH1A MOV PENAM2 MCC FitC 480 B
PENRM2 ECCS DH2734 MOV OHARM MCC F11C 480 B
g MCC-F 11C 480 8
PENAM2 ECCS HP2A MOV PENRM2 MCC Ft1C 480 8
MCC Fit 0 480 B
MKVPCOR EP BC 2PN BC LVSGRM2 MCC F t10 400 6
MAUPCOR MKUP BA12 MOP BATN KRM MCC-F t 10 480 B
MKUPCOR VENT ECCS-FCU 3 FCU ECCSRM2 MCC-F 116 480 B
MCC Fi1E 480 0
PPTUN EP MCC F11F MCC PPTUN MCC F11E 480 B
PPTUN VENT ECCS FCU l FCU ECCSAM2 MCC F11E 480 B
PPTUN VENT ECCS-FCU 2 FCU ECCSRM2 M CC F12.\\
480 B
LVSGRM2 AFW AFW3871 MOV AFPRM2 MCC F12A 480 B
LVSGAM2 AFW AF W38 71 MOV AFPRM2 MCC F12A 480 B
@CCF12A 480 B
LVSGRM2 AFW AF W790 MOV AFPRM2 MCC F12A 480 B
LVSGRM2 EP BC-2N BC LVSGRM2 MCC-F 12A 480 B
MCC F t2A 480 B
LVSGRM2 EP MCC-EF 120 MCC LVSGRMI N
57 1/S9
TA.iL E 3.6 2.
PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT DAVIS BESSE (CONTINUED) 9 P WER VOL TAGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT l SOURCE LOAD GRP LOCATION SYSTEM COMPONENT 10 TYPE LOCATION MCCF12.A 480 8
~
MCC-F 12A 480 8
LVSGRM2 EP MCC-F 12C MCC INIKPMP MCC FICA 480 2
LVSGRM2 EP RECT YRF2 RECT LVSGRM2 MCC F12A 480 4
LVSGAM2 EP RECT YRF4 RELT LVEGRM2 MCC Ft2A 480 8
LVSGRM2 RCS MUI A MOV RC MCC F12A 480 0
LVSGAM2 RCS MU18 MOV RC MCC-F 12A 480 0
LVSGRM2 RCS P2R+1TR 8 HTR RC MCC F12A 480 8
LVSGRM2 RCS RC11 MOV RC MCG F12A 480 8
LVSGRM2 VENT AFW FAN 2 FAN AFPRM2 MCC F12A 480 8
LVSGRM2 VENT LV FAN-2 FAN LVSGRM2 MCC F12A 480 8
LYSGRM2 VENT LV FAN-E2 FAN LVSGAM2 aCC-F 12 B 480 8
MOV AFPRM2 MCC-F128 460 8
OGAM2 VENT BATT FAN 2 FAN BA TT AM8 MCC F128 480 8
OGhM2 VENT OG-F AN-3 FAN OGRM2 (x
MCC F128 480 8
OGRM2 VENT OG-FAN-4 FAN OGRM2 MCC F12C 400 8
INIKPMP EP MCC EF t2C MCC INIKP:AP l
MCC F12C 480 8
INIKPMP SW SW1305 MOV SWPPTNL MCC-F 12C 460 8
INTKPMP
INIKPMP SW SW2932 MOV SWPPTNL MCC F14 480 8
UNKNOWN VENT RC-FCU-t 2 FCU RC MCC-F 15 480 8
LVSGRM2 EP MCC-EF IS MCC LVSGRMI PNLDIN 125 3'
LVSGRM I EP INV W3 INV LVSGRM1 PNL 01N 125 3
LVSGRM 3 EP PNL OAN PNu LVSGRM)
PNL 01P 125 1
LVSGRM1 EP INV WI INV LYSGRM1 PNL 01P 125 1
LVSGRM I EP PNL DAP PNL LVSGRM1 PNL 02N 125 4
LVSGRM2 EP INV W4 INV LVSGAM2 PNL 02N 125 4
LVSGRM2 EP PNL OBN PNL LVSGRM2 I
PNL 02P 125 2
LVSGRM2 EP INV W2 INV LVSGRM2 PNL 02P 125 2
LVSGRM2 EP PNLOBP PNL LVSGRM2 PNLOBP 125 2
/
)
RECT YRF1 125 1
LVSGAMI EP IN V-YV I INV LVSGRMI i
\\,j 58 1/89
~~
TABLE 3.6 2.
PARTIAL LISTitlG OF ELECTRICAL SOURCES AND LOADS AT DAVIS BESSE (CONTINUED)
}
POWER VOLTAGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT k
SOURCE LOAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION RECT YRF2 125 2
Lv5 GAM 2 EP INV YV2 INV LVSGRM2 RE 0T-) RF3 125 3
LVSGAMI EP INV YV3 INV LVSGRMt RECT YRF4 125 4
LVSGAM2 EP iNV YV4 (NV LVSGRM2 UNsNOWN CCW CCW 1460 NV CCHXRM UN6NOWN CCW SW 1424 NV CCHXRM UNNNOWN CCW SW1429 NV CCHXRM UNNNOWN CCW SW1429 NV CCMXRM UNNNOWN CCW SW 1434 NV CCHXRM UNANOWN ECCS OHl4A NV OHXRM UNANOWN ECCS OH148 NV OhxRM UNNNOWN MKUP OWX1 1 MOP UNKNOWN UNANOWN MAUP OWX12 MOP UNANOWN
~
UNNNOWN MKUP OWX13 MDP UNKNOWN UNNNOWN MKUP MU32 NV MKUPRM UN6NOWN MAUP MU33 NV PENRM2 V
1 i
l l
l O
U 59 1/89
Davis Besse 3.7 COMPONENT COOLING WATER (CCW) SYSTEM 3.7.1 System Function The CCW system is designed to provide cooling for various components and remove residual and sensible heat from the RCS during plant shutdown by cooling the
-DHR heat exchangers. The CCW system is an intermediate cooling loop between the heat loads and the service water system.
3.7.2 Svetem Definition The CCW system is a closed loop cooling system consisting of two essential cooling loops and a nonessential loop. Each essential loop consists of one pump and o_ne CCW heat exchanger. The cooling loads are divided between the two essential loops in such a manner to ensure that each loop serves a redundant set of components needed to establish and maintain a safe shutdown condition following a design basis accident. The nonessential loop is supplied from one of the essential loops. A thir'd CCW pump and heat exchanger serves as an installed spare, The CCW heat exchangers transfer beat to the Service Water System. A surge tank accommodates expansion, contraction, and inleakage of water, Simplified drawings of the essential loops of the CCW system are shown in-Figures 3.7-1 und 3.7 2. The nonessential loop is shown in Figures 3.7-3 and 3,7-4. A summary of data on selected CCW components is presented in Table 3.7 1.
3.7.3 Sntem Oneration_
One component cooling water loop (i.e. one CCW pump and heat exchanger) arovide the necessary cooling requirements during normal operation. The second CCW
- oop is in standby. Failure of the primary CCW pump initiates an automatic switchover to the standby CCW loop. The third CCW pump and heat exchanger can be aligned to take.
A the place of the normal aump and heat exchanger in either CCW loop. The third pump -
-Q normally is electrically c.isconnected, therefore, manual operations are needed in order to place this pump m service.
Major heat loads supported by the CCW system include the following:
Essential Essential Nonessential Loon A-Loon A
- Loop Diesel generatorheat exchanger CGI DG2 DHR coolers 11 1-2 DHR pump seals 1 1-2 HPI pump seals 1-1 1-2
- Contamment gas analyzer
_A B
Makeup pump oilcoolers Letdown coolers -
X Seal return cooler-X X'
-Primary water transfer pumps X
Emergency mstrument air compressor X
Spent fuel pool heat exchangers Other nones' entialloads X
s X
Makeup water for the CCW system is provided from the primary water storage tank (PWST). Backup water sources include the demineralized water storage tank (DWST) and the service water system.
60 1/89
Davis Besse 3.7.4 System Success Criteria A CCW loop can successfully perform its cooling function if flow is maintained to essential heat loads with one CCW pump, a heat transfer path to the service water system 4
is available, and water inventory in the CCW is maintained.
3.7.5=
Comnonent inrormntion-A. Component Cooling Water Pumps 1-lil 2 and 13 -
- 1. Rated flow: 7860 gpm @ 150 ft head (65 psid)
- 2. Rated capacity: 100%
- 3. Type: horizontalcenmfugal
.B. Component Cooling Heat Exchangers 1 1,1-2 'and 13 -
6
- 1. Design duty: 57 x 10 Btu /hr
- 2. Type: shell and tube 3.7.6 Sunnnrt Systems and interfaces A. Cor: trol Signals
- 1. Automatic
- a. An SFAS' signal (see Section 3.5) will start a CCW pump in the standby loop and will close valves to isolate the nonessential loop.
- b. Loss of flow in the.normally. operating CCW loop will initiate an:
automatic switchover to the standby CCW loop.
- 2. ' Remote Manual.
The CCW pumps can be actuated by remote manual means from the control room.
- 3. Manual Manual actions are required to place CCW pump'l-3 and its associated CCW heat exchanger in service.
B. Motive Power i
.1. The CCW motor driven pumps and motor operated valves are Class IE AC loads that can be supplied from the standby ciesel generators as described in Section 3.6.
C. Other
- 1. The CCW heat exchangers are cooled by the Service Water System (see Section 3.8).
- 2. Lubrication and cooling are provided locally for the CCW pumps _.
- 3. CCW pump room ventilation is discussed in Section 3.9.
' 61 -
1/89
. -... -.. -.. -... ~. -....... -.
Xs En Ia Xs
. Xs-Xs-e Xs yt3yt.
y t! y t
& I t' H:s H:!
&I!
u 1
qtsSte Stsqfe g".
Xi Xe Xe Xs 3
L A.
A 5-i s
~
a ai a
i 5:-
i g
2:
.a o
y<
r<
dt,dts dt e Eti Xe Xe i
F 5
eEts d,ta dts
.5 4
Xs Xs Xs Is Is a
l C M U$
23 a
c2 Oc oW Q.=
Eo
[
h g
V g!!
ei
'l g3
-!i
-9 ht
=E
&Rg
!i es ulg 1
i-gig
-3
- ns -
m g-l I
a g
JS
-g 3
i=
8 b
- U f_
i 4s a
II II b
e w
Cn -
Xa X:
Xt E
i t..
t.
t.
,5 la 1!
, n!.
. as
. as li 11
!n s
-c<
s x,
- x. - ><
-9
~
a
-E L
v 2 62 1/89-
___-.--_.,_..-.._....._...u._,....._.......-.
~
.y
=
t (ks T
qe u
v_.
ww vw Mr.
o 4
n r.3.'
I Fy hr is.
s 9.
a 8
4g a
I 1
C.,.,ww l
l r
2'.
,e5 m
e
+S s
2 vw yn.
l i
3 a
1 c
w a
e I
C t
Il l
s a
g
.s I'
uO C
R p
D J,
5',
a h
L h
A 6
E P
M S2 H
l g
- a. T O
L O
9
("
l C
E' g
l A
i R
f l
r.E
(
oH
!l
?a M
m
'2i i.]
e s
O1
+F.
+ t 7
t9 s
z.
8 t
s v,s ye, t
o a
ss yn So 62
+
-l i
3 I'
e*
g l
-l e a 3
rt 3
s 1
=
[
t c l
ao t
uw ww WL t
a n
t u
gn l
'3
+
M's 4
ne 1
)
2
=
i p
loo 1
n i
6 4'
- =.
o op o
Cm 6
]
t o ng nC e
l on 3
L oA I
B pi w
t h
v
)N mpd mo w
a5' t s C
uEA A
sam 5 oh 0
PE, S
CS wMu D
F' laNL COu A
W o, 4 es Af O
HfSA OA
_- +.
H sp PM T
lN MUL l
sA so F
F R.E e o UPA N H EPii O
'C T
ut wE1 C
EPTt BL 7
UPA L
AUN T
R5 4uN 9
sg 4
F CA1 9
Ca(
0 a
wE(
y i
u$
n 1 's EM[
v i N
S S
O W
N C
2 c"
u O
Do N
al C
C s
fb o
C f'
'O R
R E
E D
.l
-D A
A a
(
(
2i t
f
- 7. n Y
v m
3e LPP 3
u s
t
.s es
.A rE u
g
'u wn u
F i
F t
3 a
2 N
=
x x
w w
C C
C C
.C C
T s
.p:'.
,A i
E.
n J"
CR 6
R ev Tt "A
Rn Mf
.A
>A A
f.
R NwM t
yt F
gC 2
t W
, n op ra t
A R
W E.
MutP C
D OG C
f C
R C
A CO E
M C
D A
N 4
5i L
g N
ft t )
R l
h 6
u A
l T
A E
T a
a d
R.
E m
s' c
m a
a z
6 m
t S(
e g
mmm a
j
_gx i
/
/
i 123 124 a...,.
.1 o
On(R
~
HEATLOADS CouPOt4 NT COOL NG W ATER N
M PS g
A SUPPLY HEADE R E $$E NYlAL I
E A
HEATL CCW1t 35 532 LOADS SERvrE
- 4 WATER A X-oXcc--
Per... 4
'X:
S$ 4
==
-r to 33 12S CCW taso PUuP s 2
+
3y CCWn3 II 00 " 0000 WAIL A S
CCW HX3 t323 g
,9y OTFEM db II
$33 inAT
~
3e
.J L 70 X
- t 8
H 34 S SUPPtV tEADER 6(
3 Sofie 5.s CCW t 2 M
SERvsCE *
-e, 82 WATTRB a
CCW HX2
'C 7.53 8 RETURN t( AT4R
- Figure 3.7-3. Davis Besse Component Cooling Water System, Nonessential Cooling Loops f
b 4
.~.
r CCHERM
(
- FROM ESSE NTIAL A RE RJFYe HEADE R LOOP AHf AT LOADS l 823 Als l-SURGEYANN l
123 124 unn m.
f 41 149%
42 :
HEATLOADS c==
u NA*O A,
c
' A SUPPtV HEADER ESSENTIAL OTHE R
[
M u
- I I
35[
5 32 CCW1-1
- M
~P SERvCE 4
+'
PEMRM4
'Mt R T NM Ran WATER A lMMUPRMl
_L
}
3e.'
CCW 5095 f
~
g.,
l
,2, o
3 ris p
s
- ,, g
+..
~
~
is 33 125 CCW-1460 gpg 4
CCW 1-3
~
b U
a R
E*
+
' CCW-5096 -
CCW Hx3 1328 a
'3, ;
~'533 AT
+
ES$f NTIAL 8338 LOADS 8SUPPLYHEADER 509 549 N-CCW t 2 SERVCE 4
+
WATER S
. CCW HX2 N%
8 RE TUFFuE ADE R C
- FfKas ESSENTtAL LOOP S H AT TOADS Figure 3.7-4.
Davis Be:se Component Cooling Water System, Nonessential Cooling Loops Showing Component Locations 4
(
p0 Table' 3.7-1.
Davis Besse Component Cooling Water System Data Summary I
for Selected Components COMPONENT ID COMP.
LOCATION POWER SOURCE VO LTAG E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
BUS-CD BUS ASDPNL.
BUS-C1 4160 HVSGRM1 A
4 BUS-CD BUS.
ASDFNL BUS-D1 4160 HVSGRM2 B
CCW1-1 MDP.
CCliXRM -
BUS-C1 4160 fiVSGRM1 A
CCW1-2 MDP CCHXRM-BUS-D1 4160 HVSGRM2 B
CCW1-3 MDP CCHXRM BUS-CD 4160 ASDPNL A/B CCW1460 -
NV CQlXRM UNKNOWN CCW50S5 MOV CCHXRM MCC-E12A -
480 LVSGRM1 A
I CCW5096 MOV CCHXRM MCC-F11 A 480 ELECTPENRM2 B
}
SURGE-TANK TK 623AB' SW1424 NV CCHXRM UNKNOWri i
SW1429 NV-CCHXRM UtJKNOWrJ SW1434 NV CCHXRM UNKfJOWrJ
,I 1
I 3
i l.
4 I
l i
t i
. k
{'
b^
t I
1
.i
. i-e
(
Davis Besse 3.8 SERVICE WATER (SW) SYSTEM (7
3.8.1 Svetem Function
(')
The Service Water System supplies cooling water from the ultimate heat sink, Lake Erie, to various heat loads in both the primary and secondary portions of the plant.
The system is designed to provide a continuous flow of cooling water to these systems and components necessary for plant safety either during normal operation or under abnormal and accident conditions. The system also serves as a backup source of water for the Auxiliary Feedwater System (see Section 3.2),
3.8.2 System Definition The Service Water System contains two independent headers, each supplied by a single motor driven pump. A third service water pump serves as an installed spare and can take the place of the normal pump in either SW header. Strainers are provided to remove foreign material from the raw water before it er,ters the SW pumps.
Simplified drawings of the service water system are shown in Figures 3.81 and 3.8 2. A summary of data on selected SW components is presented in Table 3.81, 3.8.3 Svetem Onerntion During normai o water to essential and non peration, two SW pumps are in operation providing cooling essential loads. The normal source of water is Lake Erie through the intake forebay. If the supply of water from Lake Erie via the intake structure is lost, the forebay will serve as a reservoir and cooling pond to ensure that an adequate heat sink is available for reactor core and component cooling. Essential loads are those required for safe shutdown, and are therefore redundant and are served by separate loops of the SW system. Heat loads and services supported by the SW system include the following:
{}
Heat Load or Service Normal Ernercencv CCW heat exchangers X
X CCW emergency makeup X
AFW backup water supply X
ECCS room coolers X
X Containment air coolers X
X Control room emergency coolers X
i Hydrogen dilution blower coolers X
l.
Cooling water (CW) hea: exchangers X
i Cooling tower makeup X
Other secondary systems X
The SW system provides a backup supply of water to the Auxiliary Feedwater System, with SW header A suppling AFW pump 1-1 and SW header B suppling AFW pump 1-2.
l 3.8.4 Svstem Success Criterin The SW system water source is either Lake Erie or the intake structure forebay.
Equipment supported by a particular SW loop are dependent on that loop having one pump operating. For component cooling, a complete flow path must exist from the SW pump suction to the point of discharge to the ultimate heat sink.
The SW system can serve as a backup supply of AFW even with the normal SW discharge paths closed (i.e. valve SW2929 to SW2932 closed).
67 1/89
Davis Besse 3.8.5 Comnonent Information
- A. Service Water Pumps 1-1,12 and 13
- 1. Rated flow: 10,250 gpm @ 160 ft head (69 psid)
- 2. Rated capacity: 100 %
- 3. Type: verticalturbine B. Ultimate Heat Sink
- 1. Lake Ede (normal) -
- 2. Intake forebay (when intake from Lake Ede is unavailable) 3.8.6 Sunnort Svstem's and interfaces A. Control Signals
- 1. Automatic An SFAS signal (see Section 3.5) causes the following: -
- a. CCW heat exchanger outlet valves open fully.
b., Flow to cooling water (CW) heat exchangers is isolated (valves SW1395 and SW1399 close),
- c. Containment fan cooler outlet valves open wide and fans shift to fast.
- 2. Remote Manual The SW pumps can be actuated by remote manual means from the control -
room.
B. Motive Power The SW 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
{
3.6.
C. ' Other
- 1. Lubrication and cooling are provided locally for the SW pumps.
- 2. The method of SW pump room ventilation has not been determined.
i
]
i 4I i
68
. Ifgo 1
..,...N--n., -, ~N < Nn n.-**n-
.~ws~'
++ + ~*" ' ~ *
..;_.._...a..
..,mm..
~.~.._.m__.._m.
~4m... -.
_v_
.s
. ~. _ _ _. - _....
t.,4 H-43 X*
tO n
f,
N+cw n&w e
J Ia-Ia 1
I Ia I-4..
r...., 'l i
- x
.n io i.
=
cew
- I
- x. 0x X,
ME c=u i i g
sj s n
n un-in - - n.
yx j
aa =A, ko y,o ax m_
x
==
x 2n cap o in un =
in in
,8 n
D I
.T., D D
D-o-
I"
- + a=;L cr y ggy
' a-g MD
-w Q 6 e j,, x A.
4..
x g;,,
2, 4.... i _
s a
4-u g
P X "'
g iu..
m l[m o.
Ia
..S m 1
- g
.h g
.nu - cguuo.
- u., -
hx 4
x
-x
!=*s7. -pq-n l
mean N
x
. M-
-.x
' k x--
Z x
- =..
[
g_J 3
v.
S, r
.m
..uu uw m.,
l
><--.m 0
.. uu uw = i 4
Figure 3.81. Davis Besse Service Water System i
l 69 1/89
.. - ~
?
i i
I e
6 2 *3 2
-3 t
3 5
's 73 3*
eis ess esti en t
t
+
t l
oloi 01:,
o*ft:
ol,
=
i I
s c
1 I
l l
O c
i
)
.,O Cl3 tX5 a tXE tE-3 l
n i
1 t25 tXe s
s a
a X
E X
a C
Zs g=
m
- >o- -x---x -
g x-l l
oX oX o
s 1=
oli oli E:
X:
E:
X:
X:
l I
i
- L.:
1 1
X X
el Ei OE!
oli i X5 X 2 0-X5 o K 5 &X 3 G K !
ei!
oXi i
s 4
e.
a
,g, f
a a g_ :
c,
i
- t, a c
c, c,
1__
5-r 3
e e
/{
Ig
/ l
/ l ag:3 g3l 5
+5
+5 85 EEE
-f gg s
s 1
e a
J
=
Ed i
ai i'
- l
[3 ei
+
+
+
+
1 J
J
_J L._J L.J L1 um g
g oX S
~
X:
X:
X=
E
=
=
-A-A-i oXi oX!
oKi 5
m X:
X:
XB X5
~
X:
X:
X: tX tX tX tX oK!
i.
I;S ohj 8
l O
- >o--H-H-2 2
=
2 B
pc-** ww-..... - t 3
g u
to 8
q A:
A3 A;
g, E
Ust l%-
$i!V5 5
't
p l
(v) x/
V l
Table 3.8-1.
Davis Besse Service Water System Data Summary for Selected Components COr.1POtJEtJT ID C O t.1P.
LOCATIOti POWER SOURCE VOLTA G E POWER SOURCE E L1E R G.
TYPE L O C ATIOf1 LOAD GRP.
BUS CD BUS ASDPNL BUS-C1 4160 flVSGHM1 A
BUS-CD BUS ASDPNL BUS-D1 4160 HVSGHM2 B
SW1-1 MDP INTKPMP BUS-C1 4160 HVSGHut A
SW1-2 MDP INIKPMP BUS-D1 4160 HVSGHM2 B
S'N1 -3 MDP IfJIKPMP BUS-CD 4160 ASDPNL A/B SW1395 MOV SWPPINL MCC-F12C 480 ifJI K P M P B
SW1399 MOV SWPPINL MCC-E12C 480 if1TKPMP A
SW2929 MOV SWPPINL MCC-E12C 480 ifJ1KPMP A
~SW2930 MOV SWPPINL MCC-F12C 480 ifJI K P M P B
SW2931 MOV SWPPirJL MCC-E12C 480 INIKPMP A
SW2932 MOV SWPPTf1L MCC-F12C 480 if1TKPMP O
d i
E I
u
Davis Besse 3.9 EQUIPh1ENT AND CONTROL-ROOh!
EMERGENCY VENTILATION SYSTEMS T
3.9.1 System Funcilon The equipment and control room emergency ventilation systems maintain environmental conditions in various areas of the plant within limits based on equipment qualification and/or human habitability requirements. These systems transfer heat from the room air to the ultimate heat sink (i.e. to atmosphere) or to a secondary heat transport system.
3.9.2 Svstem Definition The equipment and control room emergency ventilation systems include a variety of fans, fan coil cooling units at d condensing units that usually serve limited areas --
of the plant and operate when the norma. heating, ventilating and air-conditioning (HVAC) systems are unavailable. Some emergency ventilation systems aim may provide for normal room cooling and/or ventilation. A summary of data on selected er.1ergency ventilation -
system components is presented in Table ;.9 1, 3.9.3 Svetem Oneration Emergency room vantildon systems for the following plant areas are described in this sectiom Auxiliary feedwater pump rooms ECCS pump rooms Makeup pump room Component cooling water heat exchangst and pump room Service water pump room Electrical switchgear rooms
.. Battery rooms-
- _ Diesel generator rooms L
Main control room Containment A. Auxiliary Feedwater Pump Rooms AFW pump room ventilation is provided by two Class lE fans.
B. ECCS Pump Rooms-The two ECCS pump rooms are ventilated by a total of five fan-cooling units.
Units 1,2 and 3 normally are supplied with cooling water from the service water B header. Units 4 and 5 normally are supplied from the S_W A header.
All units can be supplied from the opposite SW header if needed. Each fan cooling unit is rated at 50 percent capacity.
C. Makeup Pump Room-None identified.-
D. Component Cooling Water Heat Exchanger and Pump Room -
i
[
The CCW pump room appears to be ventilated by two Class IE fans.
E. Service Water Pump Room None ibntified.
O 72 1/89
Davis Besse F. Electrical Switchgear Rooms g
- 1. Each low voltage switchgear room is ventilated by a Class lE fan, with a t
i full-capacity emergency ventilation fan as backup.
V
- 2. No emergency ventilation system has been identified for the high voltage switchgear rooms.
G. Battery Rooms Each battery room is ventilated by an independent Class lE fan that exhausts through the auxiliary building roof.
H. Diesel Generator Rooms Each diesel generator room is ventilated by two 50 percent capacity fans that are interlocked with the diesel generator. The fans operate any time the diesel is runmng.
I.
Control Room Emergency control room ventilation and cooling is provided by two emergency vent fans and two emergency condensing units. A third standby condensing unit is available. All are powered from the Class IE AC system. Condensing unit i normally is supplied with cooling water from SW header A and condensing unit 2 is supplied from SW header B. A supply side cross connect allows each condensing un,t to be aligned to the opposite SW header.
i J. Containment Three fan coolet units are provided for normal containment cooling and for emergency cooling in conjunction with the containment spray system and ECCS systems. The FCUs are cooled by the' Service Water System (see Section 3.8).
[sT Upon receipt of an SFaS si
()
from each unit is fully open.gnal, all fans shift to fast and the SW outlet valve 3.9.4 System Ruccess Criteria Loss of a room ventilation subsystem eventually may cause the associated equipment in the room to fail due to extreme environmental conditions. An individual fan cooler unit will fail to perform its cooling function if motive power to the fan is lost, or if the heat sink is unavailable.
3.9.5 Comnonent Information A. Containment Fan Coo'ler Units 1 1,12 and 1-3
- 1. Type: forced air to-watercooler
- 2. Rated capacity: 75 x 106 Btu /hr each 3.9.6 Suonort Svstems and Trterfaces A. Control signals Various control features are noted in the descriptions of ventilation absy<tems operation, above.
B. Motive Power All emergency ventilation system components are Class 1E AC loads that can be supplied from the standby diesel generators as described in Section 3.6.
{}
\\
l v
73 1/89
1 l
Davis.Besse t
C. Service Water The E^CS pump room coolers, the control room emergency condensing units and the containment fan cooler units require cooling water supplied by the service water system (see Section 3.8).
S 1
l g
l 4
i e
i f
i i,
I 74-1/89 e
t
%)
Table 3.9-1.
Davis Besse Equipment and ' Control l loom Emergency Ventilation System Data Summary for Selected Components
.{
-i cot.1PONEtJT ID COMP.
LOCATION POWER SOURCE VOLTAGE POWER SOURCE E f.1 E R G.
t TYPE LOCATION LOAD GRP.
I AFW-FAN FAN AFPRM1 MCC-E12A 480 LVSGRM1 A
AFW-FAN-2 FAf1 AFPfiM2 MCC-F12A 480 LVSGHM2 8
BATT-FAN-1 FAN BATTilMA MCC-E128 480 DGRM1 A
BATT-FAtJ-2 FAN BATTRMB MCC-F12B 480 DGRM2 B-i CCW-FAtJ-1 FAN CCHXRM.
MCC-E11C 480 585ABilALL A
CCW FAfJ-2 FAN CCilXRM MCC-F11 A 480 ELECTPENRM2 B
CH COND-1 COND CR MCC-E12A 480 LVSGRM1 A-4 CR COND-2 COtJD CR' MCC-F11 A 480 ELECTPEf1RM2 B
j CR-COND-SBY COND CR MCC-E12E 480 PPTUt1 A
e CR-FAN 1 FAN CR MCC-E12A 480 LVSGHM1 A
Cfl-FAN 2 FAN CR MCC-F118 480 MCCF11BRM B
DG-FAN-1 FAN DGRM1 MCC-E128 480 DGHM1 A
DG-fat +2 FAN DGRM1 MCC-E128 480 DGRM1 44 DG-FAN-3 FAN.
DGRM2 MCC-F128 480 DGRM2 8
T DG-FAN FAN DGRM2 MCC-F128 -
480 DGRM2 B
L ECCS FCU-1 FCU ECCSHM2 MCC-F11E 480 PPIUN B
ECCS FCU 2 FCU ECCSRM2 MCC-F11E :
480 PPTUN B
ECCS-FCU-3 FCU ECCSRM2 MCC-F11D 480 MKUPCOR-B-
ECCS-FCU-4 FCU ECCSRM1-MCC-E12E '
480 PPIUN A.
ECCS FCU-5 FCU ECCSRM1 MCC-E12E 480 PPTUN A
LV-FA N-1 FAN LVSGRM1 MCC-E12A 480 LVSGRM1 A
3 LV-FAN-2 FAN LVSGRM2 MCC-F12A 480 LVSGRM2 B
i LV-FAN-E i -
FAN LVSGRMe MCC-E12A 480 1.VSGRM1 A
E LV-FAN-E2 FAN.
LVSGRM2 MCC-F12A 480 LVSGRM2 B
o j
HC-FCU-1-1 FCU RC MCC-E14 480-UNKNOWN A'
RC-FCU-1-2 '
FCU RC MCC-F14 -
480-UNKNOWN B
i HC-FCU 1-3 FCU HC MCC EF15 '
480 UNKNOWtJ jA/B.
s I
.m..
Dav;s Besse
- 4. PLANT 'INFORMATION 4.1 SITE AND BUILDING SUhlMARY The Davis Besse Nuclear Station is located on a site of a? proximately 954 acres of land in Ottawa County, in northwestern Ohio. The city of Sancusky Ohio is about 20 miles ESE of the site, and the Toledo incorperated limits are about 20 miles WNW. The site is bounded on the north and cast by Lake Erie. Figare 41 (from Ref 1)is a general view of the plant and vicinity.
The major structures at this unit include the containment building, turbine V
building, auxiliary building, a service building, the intake <tructure and the cooling tor a.
A site plot plan is shown in Figure +2 and more detalis of station arrar.gement are shown in Figure 4-3.
The containment structure is a freestanding cylindrical steel containment vessel enclosed by a separate reinforced concrete shield building. The conta! ament houses the reactor vessel, reactor coolant pumps, steam generators, and pressurizer. Pumps, piping, and valving for the reactor coolant system is completely contamed within the contamment structure. Access to the building is via an equipment hatch or a personnel air lock. Piping-and electrical penetration areas are on various levels of the auxiliary building, mainly on the southeast and southwest sides of the containment. The diesel generators are housed on the north side of the containment in the auxilivy building.
The turbine building, located eau of the containments houses the turbine generator and the asscciated power generating auxiliaries. The adjacent office building contains the condensate storagt tanks. The circ @ ting nter pump house contains Ne circulating water pumps for main condenser cooling.
The auxiliary building is located around three quarters of.the reactor containment. The auxiliary building contains much of the plant's safety related equipment, including the auxiliary feedwater pumps, high pressure injection pumps, DHR pumps and heat exchangers, containment spray pumps, makeup pumps, component cooling water pumps and heat exchangers, and motor control centers supplying power to safety _ system components.
The intake structure is located east of the reactor complex, on the intake mnal which connects to Lake Erie. The intake pump house on the intake canal hcuses the service water pumps.
4.2 FACILITY LAYOUT DRAWINGS-Figures 4-4 through 4 11 are simplified building layout drawings for Davis -
Besse. Some outlying buildings are not shown on these drawings. A section drawing of
{
the Auxiliary Building is shown in Figur 412.
Major rooms, stairways, elevators, and -
doorways are shown in the simplified layout drawings, however, many interior walls ht;ve -
been omitted for clarity. Labels pnnted in uppercase correspond to the location codes listed in Table 41 and used-in the component data listings and system drawings in Section 3.
- Some additional labels are included for information and are printed in lowcecase type.
A listing of components by location is presented in Table 4 2. Comconents-included in Table 4-2 are those found in the system data tables in Section 3, therefore thir 5
table is only a partial listing of the components and equipment that are located in a particular room or area of the plant.
4.3 Section 4 ' References
- 1. Heddleson, F.A., " Design Data and Safety Features 'of Commercial Nuclear Power Plants" ORNL NSIC-55, Volume II, Oak Ridgt National Laborntory, _
January 1972.
\\
76 1/89
g-
.s-a.~.
a
+m-.
a m
..ae sa_-s-a M
6g, o'e e. i.=
7 1 e e'-
-?
0+'3O g
s f.; :
9 i
!, y# 0 4,
- /
05 s
o s
o 94 4l L
5 j
9
)
il g
- a o II
?
l
<n
- q g
//
l/
E v
'J 2 7' /
g v
g W
th (
,j 2
%m
,?
i 1
h f
i p
b
\\ P l
3 4
i@ '.LC *e li s
Y 2'
E O
,y,
/
- =
ca 4
L l
'5
\\{# ?
R m
x
/
o O
C iQ
.C f
(I A k
,\\ I
\\
h
' 4 %,
,,fY h
/
r.v a
o %g 04 vf s
5 e:
lin F
t e
q$
'\\m,
\\
!s b
\\
y
~
i r
y e
!! #;i i
4
/
14s
,x p
,b o
e Qu 4'A i
r i$if[i.'j'.,.
r..d f
_E s,1,[0>
v'>#.
i
.t O
g f
77 1/89
--,.a-i s
_s AAdh..)4 4
,J sala,4 m-p=-
4 h
5 a4_
Ja.
4.s,h,-Ahgh 4
,a au-, i s w
.n
...a4 N
s
\\
\\
\\
- f'h, s,
\\
ag s
\\
\\
\\
g
\\
\\-!.
1
.'p/ I
\\
p... ilN.'s,
l G
C '
a: L h i
= /g. q m g
col
(
A u
Mi22
.- n i 1 m
=rr M
3 l
& si;oi
[
'/
m
+...+-
n n
a
~
,....__,.i 2 2 E
Q Df
. y
. h Q
i
' l y
gn ss y
v m
0.l.
3 M
d i
a i
O "4
9 m
./
l/ ('
E ls
-l l
m f
) i.
V
-~~.--
s,~
p 5
s o
e
- f. '
/k j
I Q
/ju, r
j
.e If_
__ji._!q
-,gE e.
- ___=
- nae
't l
i
. : p.
y
%=h p o
3 o_
~
w x El.
2 l
k
>A y
e 4==.
y
,i, s
o 4
2 l
m i,
h
!k 1
., b N}..-+\\
y\\
g uu 3
b
=
-t l
s\\
/
\\ - N
-o z-4'd g g -l j
A n
\\
--7 i
~
5, f,
q --
l W/o9 -)
h,d t h
,g 8 a
_2
... kN, g.[f,'i. gIL\\. )b
-o S
'Q- -
i y
e.
j g
_ ' '$8 UY! & El V.S
- s-1 78
-1/89 w
w g-w
,e
,,.v m
,,.n.v..
...w,e
~-a,n,n
.,.r.
-, +,,,,,
,,~,&,,
wam,-.ya-..,,,
,,w--,
t t
tJORTH
[
sL
[
A
.m--
e scoun, anu un.
l M
)b v
v v_
y
.y y
l Nog-v v
j ac pearu patung sor
)
Coohng(
[
Tower b>
1 w as
- c Canal save house storage rank 1
p
~
'a g(
2 s
7.
t 3-Service 5
toesor No.1
==tary
,,,,,,',',,g,
" *'s'acy rnans n
2c om nous.
.p generator
[
$torage Rans
)[
g 7
Y ir
^
^
^
A l
tarms 3c 3:
ac start-w#
3c rans 01
]
E X
')C tws tej,
- ans stre w 4
- !1 "
W aer.
t t
t 3c C
Circ Water Treat.nent I
W I
' pnmary wE House 3
W
'I storage tank -
3(
Can.1
[
(PWS }
l Turbine
. sNTxanf P l
2
]
CN i
y, tr i Building 4
,, ac***
{
1 Ndg
]
f^
^
- e o
man
' 'ptanng -
[
h entrance M
J
- c I
9
).
l M% Bid -
d
[
ou 2C y
v t
]t borawd water c:c
.)C storage tank -
i
' (8 WST) 7
- c;<
i 3
i N
cn j
c'-
Figure 4-3.
Davis-Besse General Station Arrangement i
i t
4 l
Y_
?
I t
'i t
_,r..,
e a
4-
_...-..__,._.-_.~_.1_
..-m.___
NORTH i
l d
i I
RC l
U U Ei.
J P
i (
0 E
t.s :
ECCRM2 g$gggg'h R-
~
v A
DHXRM gggjp ECCSRM1 3
~"
u areaq
. waste e ast, aea ares.
waste ~
I gas area i
lu[E"Cl,.
i i
i Figure 4 4. Davis Besse Contalnment and Auxillary Buildings, Elevation 545 feet j
1 80'
'/89 i
.....c.
.., _. ~
......_,1 1~..r.
~
NORTH d
I
\\
i f
I
(
\\
]
g I
U fs waste PENRM2 tanks hPENRM1 l~ l BAEVAPpjRT!
N_
+
9 9
B MKUPRM RM1
~
u u
565A8 HALL y
,,,y
~;
dg purifica$on -
, j j ;qg
'gggRT2 i__
ecivipment
,.gt;7,. ;gy;"g);ey;c; I
%U
. g g!' seen sl;;i' E lm!'!!Tmu W
d 5;
4..
Yhyr.w su.it.:jk,g gj,Q bl -
s e,
MKUTKRM l
BATNKRM PURVRM igya "
MKUFLTRM ppjff;Y';jfkiM$ gh[
way lug PP NL
%gqq, 9:07 4
l i
5 i
Figt..e 4 5.
Davis Besse ' Containment and Auxillary Buildings, Elevation 565 fest
-- 81 1/89-
NORTH d
$95 ft. elevaton above SWGRAWNTRM g-m DGRM2 ewt 2
l Cle$el Qen. l SWGR cay gA3yyny tank 0 e, w DGRM1 I
,1 l diesel gen j HVSGRM2 HVSGRM1 o
esy C
tank u
g oom ASDPNL EhtERGENCY
- AIR LOCK N. {
k RC turbine bidg.
heater bay
(
area i
o PENRM3 k
stairs F to A A V pump rooms PENRM4 I
585ABHALL h!b; e N G Ni MIXTNKRM
=>x - t xx m u 1.a; <wAM%$9k$;
.Ao h; 4'y n.gyggspent & new }h(N'h r
- rg; fuel is 9
railroad spur.
.. j$w;h l
l u r; i
g...................p p,,,,,,,,;
- q; lu M CCHXRM-e 7
m,
.p.
,o w v
l Figure 4 6.
Davls Besse Containment and Auxillary Buildings, Elevation 585 to 595 feet 82 1/89:
i
. - ~.... -.
i NORTH l
l I
i e
c 5
-o-LYSGRM2 LVSGAMI toof
$95 ft i
I
\\'\\_
~
s i
E h
. tuttine bldg.
w heator bay
- area '
O personnel CRORM air kxA eQulpment l
hatch t
1 MCCF11 HAM I
1 603A8 l-X) nm m
Au
~YpTnf tuoi h buo
!(*,1 l.[ K iabs and hp 7 o~
pool <c area u
m Agra ywn -
a
- t fyj g
I
" c:q 1 0-1
!V Figure 4 7. Davis Besse Contalnment and Auxillary Buildings, sevatlon 603 feet 83:
1/89 1
NORTH
.-a v.
- h-I il.s c 3
s t
..m u w.
o.
-n e,
1 ggnq 610 ft 7,"
. ~ -
..(.{
.,i' ',ca,
,,,;Eb'_
.st-l s
g
,y.~
a-m
.. s :c.;
r s ;; -ctJ.
[
RC 4
turbine bldg.
heater bay O
area i
'D M
"""'ml u i l-hJ ol CSR E
. g
'e t
i I
1 Figure 44. Davls Besse Containment and Auxlilary Buildings, Elevation'613 feet N
l/89-t 9
- +
,w,...e-g, van wi gw.,
v+,
+ a-s e
- re w e-e- te re-w v - aM-< v e5
-4..:e--.wy,v,3-.%,--y 9
-g y
r y,e
,,,..,ww,.
--r.
+,.y.-,,-,ww,-.nwy
,,,-.y-ww..-
v-.
.,,,y-wey y-
(~'N, NORTH
\\v/
A
{
l s
eI
<o 5
\\5 RC b
U turbine bldg.
heater bay area (r/
I Q,J
\\
A computer room N cabinet 7; n '
g room
=
CR
-O--
O
,n
\\ )
m Figure 4 9.
Davls Beste Containment and Auxillury Buildings, Elevation 623 feet 85 j/gg
{%
)
NORTH A
-7
.a.
M 3 ft. '
~ Yit$ti
.c%:
Rc
'd turbine bldg.
heater bay area b
s
)
'% /
MNSTMAM2 MNSTMRMI i
1 E3 control 70 l
rool room 7e I
,Mid!.
.g hvac e,
main stearn piping
(
/
%/
Figure 410. Davls Besse Containment and Auxillary Buildings, Elevation 638 to 643 feet 86 1/39
-ma
A D)
(
NORTH A
auxiliary bldg.
circulahng water pump house i
U l
5
- =
piping from CSTs to AFWpumps
- .a _...a. _
(565ft. elevation)
{ main turbino i
+ge.n,erator n
heater bay area t
r**..
E
........................o.............
t 5
y :,
off!ce bldg.
l l
control room
- h l.,l'[
(623 ft elevation) l l
p)
' (J
\\
Figure 411. Davis.Besse Turbina Building, Elevation 565 to 623 feet (typical) 87 1/89
i ij j
-!i
. !y l
{l{
l LZ I
i we o
ei
_e i
f 8
l 1
i t c, i
- 7
~~
i T
!. I i 14 Uj 1 !l f
j}
1lf b's, i
a' Il
.;)
55' l
gi t
)#
l e;:)
[
s.
i 4
I i
a l.
i 1
L e'
G l
l l) o 1 I-
-Q l.E t !
- n.5 on; b.
[
+1 w"c.
u 0
i t
C ]f y/ ; /,
l~&,
g
- m. ; C C3
~
e.
' *q "_. 1 1 t
e I
't.T3 l
L_'i -
rg ij i"' 7 'j
,oc u
s i
"+
=
1, l>
5 12.h: l IE/
8
=J
- sq m
I
,m (if !)
i Hq11 I n,n n, ggLIg
.,m.
- f, * ~
I.;
a
- i i
e r *-
+e 3-5 g<fnl+ah' i l di t=
lje J5 s$i
=-
ijf
=
4 I tfd M
il
=4i i
i
} n e.
L (pG 7
b
.;t ut-3 m
t'. dn?i
- !j t-i
}
..J.
[ 1 1 (H s
g
=
(
L
's t
l' 1
s I
~
Si!}j,j I
N
- C j !;
o l
l'
. M i ;
ij i
4 m
- I h!h C?
'I
,I
! SE w
.!s.'
h !d Lr I
rvsf n
.e f.:
-- i 1
e I"S
.-i a!a m
9I
(
tuh O
4 e
h.
"b il kl s{u -
1 **
i i
i n
.i "
N_
. f v.
d
'h g
_l&
- o.
c fl
,5-K
{
__J _i I
i 1
w 1r 1
l
$m i
l3,I i
7 II u.
!si
!i-8
, r i te!
b__- [I h
-l..-
l y-l,}NI f; u$,,,-i, m'il-i
- l
- t, t
-*%y% m,1 s
L.,__; I - - L._
(
1._~.6 i
b g
l b
b
.b b
b dI
' I S
f,..
=
e
- e e
1
-hI 4
j!
g.
a.
.g
-.88 1/89 n-w
-=mvr.-y--g-y.
9
.,,w c.
.w,.,qve..p,._.,f,,
..y..,,,,3a..,+.w.,,.,e~,,
,..,-..~,.,,,w,n..#,.
p.r,....-w,rm=..,-_
.+ww.,
,,.c.,,,.r.,%,,,,,,.w
,v,
,.c,,.,-
Tablo 41.
Definition of Davis Besse 3ullding and Location Codes
\\
Codes Descrintions t
1.
565ABHALL 565' elevation of the Auxiliary Building hallway 2.
565TB CST PP 565' elevation area in the Turbine Building where the Piping from the Condensate Storage Tank to the Auxiliary Feedwater Pumps is accessib!c 3.
575TB
$75' elevation of the Turbine Building 4.
585ABHALL 585' elevation of the Auxillary Building hallway 5.
603AB 603' elevation of the Auxiliary Building 6.
623ABHVACAREA 623' elevation of the Auxiliary Building Heating Vantilation Air Conditioning Area 7.
AFPRM1 Auxiliary Feedwater Pump Room No.1, located on the 565' elevation of the Auxiliary Building 8.
AFPRM2 Auxiliary Feedwater Pump Room No. 2, located on the $65' elevation of the Auxiliary Building 9.
.ASDPNL Auxili Shutdown Panel, located on the 585' elevation of the Aubary Building
- 10. BAEVAPRM1 Boric Acid Evaporator Room No.1, located on the 565' elevation of the Auxiliary Building
- 11. BATNKRM Boric Acid Tank and Pump Room, located on the 565' elevation of the Auxiliary Building
- 12. BATTRMA Battery Room A in Low Voltage Switchgear Room No. I
- 13. BATTRMB Battery Room B in Low Voltage Switchgear Room No. 2
- 14. BWST Borated Water Storage Tank, located outside west of the Auxilhry Building
- 15. BWSTVPIT Borated Water Storage Tank Valve Pit, located between BWST and Pipe Tunnelin the Auxiliary Building
- 16. CCHXRM Component Cooling Heat Exchanget Room, located on the 585' elevation of the Auxiliary Building
- 17. CR Control Room, located on the 623' elevation of the Auxiliary Building 4
89 1/89
Table 41.
Definition of Davis Bosse Building and Location Codes (Continued)
Codes Descrintions
- 18. CRDRM Control Rod Drive Equipment Room, located on the 603' elevation of the Auxiliary Building i
- 19. CSR Cable Spreading Room, located on the 613' elevation of the Auxiliary Building
- 20. CSTRM Condensate Storage Tank Room, located on the 585' to 638' elevation of the Turbine Building
- 21. CWRTl Clean Waste Receiver Tank Room No.1, located on the 565' elevation of the Auxiliary Building
- 22. CWRT2 Clean Waste Receiver Tank RNr: No. 2, located on the 565' elevation of the Auxiliary 0.iilcing
- 23. DGHALL Hallway to Diesel Generators, located on the 585' elevation of the Auxiliary Building
- 24. DGRM1 Diesel Generator No.1, located on the 585' elevation of the Auxiliary Building O
25.
DGRM2 Diesel Generator No. 2, located on the 585' elevation of the Auxiliary Building 26, DHXRM Decav Heat Exchanger Room, located on the 545' elevation ofit luxillary Building 27, ECCSRMI Emergency Core Cooling Equipment Rrom No.1, located on the 545 elevation of the Auxillary Building 1
- 28. ECCSRM2 Emergency Core Cooling Equipment Room No.
located on the 545 elevation of the Auxiliary Building
- 29. ELECTPENRM2 Electrical Penetration Room No. 2, located on the 603' elevation of the Auxiliary Building i
- 30. HVSGRM1 High Voltage Switchgear Room No.1, located on the 585' elevation of the Auxiliary Building
- 31. HVSGRM1 High Voltage Switchgear Room No. 2, located on the 585' elevation of the Auxiliary Building
- 32. INTKPMP Water intake Structure east of Turbine Building
- 33. LVSGRM1 Low Voltage Switchgear Room No.1, located on the 603' elevation of the Auxiliary Building v
90 1/89
.i
Tablo 4-1.
Definition of Davis Bosse Building and Location Codes (Continued)
O Codes Descrintions
- 34. LVSGRM2 Low Voltage Switchgear Room No. 2, located on the 603' elevation of the Auxiliary Building
- 35. MCCFlIBRM Motor Control Center F118, located on the 603' elevation of the Auxillary Building
- 36. MIXTNKRM Mixing Tank Room, located on the 585' elevation of the Auxiliary Building
- 37. MKUPCOR Hallway leading to Makeup Pump Room, located on the 565' elevation of the Auxiliary Building
- 38. MKUPRM Makeup Pump Room, located on the 565' elevation of the Auxiliary Building
- 39. MNSTMRM1 Main Stream Room No.1,locatea on the 643' elevation of the Auxiliary Building
- 40. MNSTMRM2 hiain Stream Room No. 2,)ocated on the 643' elevation of the Auxiliary Building 41, PENRM1 Penetration Room No.1, located on the 565' elevation of the s
Auxiliary Building
- 42. PENRM2 Penetration Room No. 2, located on the 565' elevation of the Auxiliary Building
- 43. PENRM3 Penetration Room No. 3, located on the 585' elevation of the Auxiliary Building 44 PENRM4 Penetration Room No,4, located on the 585' elevation of the -
Auxillary Building
- 45. PPTUN Pipe Tunnel located on the 545' elevation of the Auxiliary Building l
- 46. RC Reactor Containment
- 47. SWGRMAINTRM Switchgear Maintenance Room, located on the' 585' elevation of the Auxiliary Building 48._ SWPPTNL Service Water Pipe Tunnel, located on the 565' elevation between Intake Structure and Turbine Building
- 49. TB603 Turbine Building,603' elevation v
l 91 1/89
TABLE 4 2.
PA9TIAL LISTING OF COMPONEtiTS DY LOCATION AT OAVIS BESSE l
O ECAT6CN SYSTEM COMPONEN T ID COMP N
TYPE
$6$A0 HALL EP MCC;Eli A MCC 585ADHALL EP MCC E118 MCC 585ADHALL EP MCC.E 11C MCC T85ADMALL MAUP PWA11 MOP 585A6 HALL M6UP PWAl2 MOP 623Ab DCd SVAGE-TANK TK 623ABHVACAhE AFW AF W106 MOV A
b23 ASH V ACARE AFn AF W106A MQ7" 23ABHVAC RE ' AF W AFWlC7A MQV A
62TAEVACARE AF W AFWlO6A MOV A
t AFPNM Wu AF W3870 MOV AFPRMI AF W AF W 786
~
MCV AFPRM)
AFPRMI AFW ~~3Wils2 f TOV AFPRMt A6Y nFW11 TCP ~
l
-AFPRM1 AFW AF W3870 MOV AF PRM t AFW MW3M MCV AFPRMI VENT AFW FAN 1 FIR ~
(
AFPRM2 AbY~
AFW12 TDP AFPRM2 AFW AF WJ872 MOV AFPRM2 FV[
AF WM71 MQV AFPRM2 ACW AFWN8 MOV ~
t AF DRM2 AF W AF W 730 AV AF PRM2 AFW AFW730 AV AFPRM2 AFW AFW720 AV l
~
AFPRM2 VENT AF vy FAN 2 FAN V
92 1/89 V
f y
r
- + -
ea'-e a
w-m--
e-eg ur a--
- e'
TABLE 4 2.
PARTIAL LISTit40 OF COMPOt4Et4TS BY LOCATIOt4 AT DAVIS BESSE (cot 4Tif4UED)
/
l LOCATION 5YSTEM COMPONEN T iD COMP
(
TYPE ASOPNL CCW BVS CQ SUS ASDPNL CCW DVS CD BUS AbOPNL SW BUS CD BUS t
ASDPNL SW BVS-CD BUS R ' #KRM MAUP BAl l MDP
~
BAT N ARM -
MNUP BAl 2 MDP E NP,RM M6UP BA lhi.
IK
~
BAisW MAUP BA TK12 '"
TA
_BArTRMA EP BAT 11P TAT ~
~
BAfiAMA EP BATi.tN~ ~~
SAT BATDfMA VENT
. 0ATT FAN 1 FAN 5ATTRMB Eb BA T T-2P TIT ~~
~*
1 EirlMB EP BATT 2N BAl WThMB VENT BATT FAN 2 FAN
{n')
bwST ECCS 6WST TK BWST
- T6DT~EiST TK TWST MAUP SWST TK
~~
BW5TVPil ECCS E 70
~
MO V~ ~
~
~ ~ "
EDVPiT MAUP DH7A MOV SWSTVP!T MWUP Dhh MOV MM~
CCW CCET
' MOP p
- CCHAau CCu CcwiE - ~
u@~
CC e u cCW CCwia uoP CCitxRt,I WW G7i424 tW CCHARM CCW
'Dwidas NV
~~
CCnx4M
, CCW
-3W ua4 tw CC8xRu cow Sw u2s Nv CCaxRu Ccw-~
Cciis3a uov CCHXRV NY CCW5096 MOV e
3
(.)
93 1/89 1
i
-i,-,
,,,~.,,-,,-e,
...., - - ~,.,,
,i ya e
TABLE 4 2.
PARTIAL LISTING OF COMPONENTS BY LOCATION AT DAVIS DESSE (CONTINUED)
LOCATION SYSTEM COMPONEN T 10 COMP TYPE CCHARM CCW CCW1460 NV CCHARM VENI CCW FAN 1 FAN CCHAPM VENT CCW FAN 2 FAN CR VENT CRFANI FAN
'"CR VENT CR-FAN 2 FAN GR VENI CR COND-l COND CH VENT CH COND-2 COND CR VENT GR COND-SBY COND CRORM EP MCC EllE MCC CSIRM AF W CSTi1 TK CSIRM AFW CST 12 TK DGRMt EP EP Od~
OG DGRM1 EP MCC E126 MCC DGRM)
~
DGRM1 VENT DG-FAN 1 FAN s
DGRMI VENT DG FAN 2 FAN
~0GRM2 EP EP DG2 DG DGRM2 EP MCC F120 MCC DORM 2 VENT DG-FANO FAN t
OGRM2 VENT DG-FAN 4 FAN DMARM ECCS DHxt 1 (tX DMARM ECCS DH 148 NV OHARM ECCS DHA 12 HK 3 HARM ECOS DH14A NV OMARM ECCS DH2734 MOV ECC5AM)
ERM1 ECCS DH11 MDP 1
ICCSRM)
~
ECCS HPil.1 MOP ECCbHM1 VENT ECCS-FCU 4 FCU 3CCSAMI VENT ECCS FCU4 FCU.
t 94 1/89
TABLE 4 2.
PAF1TIAL LISTING OF COMPONENTS BY LOCATION AT DAVIS BESSE (CONTINUED)
'I J
LOCATION SYSTEM COMPONENiiD COMP V
TYPE ECCSRM2 ECCS DH2733 MOV ECCSRM2 ECCS DH63 MOV ECCSRM2 ECCS OHi2 MOP ECCSRt't ECCS HPit 2 MDP ECCSRM2 VENT ECCS4 cut FCU ECCSRM2 VENT ECCS-FCU 2 FCU ECCSRM2 VENT ECCS-FCU-J FCU ELECIPENRM2 EP MCCFt1A MCC HV6GRM1 EP BUS Cl BUS HVSGRMt EP EP CD1 CD HV6GRM2 EP B US-01 BUS SVSGRM2 EP EP CB2 C8 IN I APMP EP MCC E120 MCC IN T APMP EP MCC-E120 MGC
/%
l
\\
IN T APMP EP MCC F t2C MCC INTAPMP EP MCC-F l2D MCC IN TAPMP EP MCC-EF12C MOC 6NTAPMP EP MCC-EF 120 MCC WTAPMP SW SWll MDP IN TKPMP SW SWi2 MDP INTKPMP SW SWt3 MDP LYSGRMt EP CUS E1 OUS LVSGRM t EP EP CEl)
TRAN LYSGAMI EP PNL DtP PNL LVSGRM t EP Pht OtN PNL LYSGRM t EP GC-MCC)
~LVSGAMI EP DC MCCI MCC LYSGRM1 EP DC-MCC )
~s LVSGRM1 EP DGMCCI MCC (x j) 95 1/h9
_.._.._=
TABLE 4 2.
PARTIAL LISTINO OF COMPONENTS BY LOCATION AT DAVIS BESSE (CONTINUED)
I
\\
LOCAlio 4 SYSTEM COMPONENT ID COMP TYPE LVSGRM1 EP OC 1P BC LV$GRM1 EP BCIN BC LV6GRM1 EP BCIPN BC LYSGRMI EP PNL CAP PNL Lv6GRM1 EP 1NV YV)
INV LVSGRM1 kP INV YVI INV LYSGRMI EP RECT YRF1 HECT LVdGRM1 EP PNL ESS Y1 PNL LV5GRM1 EP PNL DAN PNL LV6GRM1 EP (NV Yv3 LNV LVSGAMI EP INV YV3 (NV LV5GRMI EP RECT VRF3 RECT LV5GRM1 EP PNL ES$ Y;$
PNL LVSGRM1 EP MCC El2A MCC LVSGRM1 EP MCC-E 14 MCC LV6GRM)
EP MCC E15 MCC LV5GRM1 EP MCC EF120 MCC LV5GRM1 EP MCC-EF 120 MCC LV5GRMI EP MCC-EF 15 MCC LV5GRM t EP MCC EF16 MCC LVSGRM1 VENT LV FAN 1 FAN LVSGRM1 VENT LV FAN El FAN LV6 GAM 2 EP BUS Fi BUS LVSGRM2 EP E P-DF l2 TRAN LVSGRM2 EP PNL-D2P PNL i
LVSGRM2 EP PNLDIN PNL LVSGRM2 EP DC-MCC2 MCC LYSGHM2 EP DC-Mcc2 MCC LVSGRM2 EP DC MCC2 -
'\\
96 1/S9 l
~ - - - -
TABLE 4 2.
PARTIAL LISTitJG OF COMPOtJENTS BY LOCATIOt1 AT DAVIS BESSE (CONTINUED)
O I
LOCAllON SYSTEM COMPONENT 10 COMP TYPF LYSGRM2 EP DC-MCC2 MCC LVSGRM2 EP BC2P BC LVSGRM2 EP BC 2N BC LV6GRM2 EP BC2PN DC LVSGRM2 EP PNLObP PNL LVSGRM2 EP 6NV YV2 INV LvbGRM2 EP INV YV2 INV Lv5GRM2 EP RECT YRf 2 RECT LVSGRM2 EP PNL ESS Y2 PNL LVSGRM2 EP PNL DBN PNL LYSGRM2 EP INV YV4 INV LVSGRM2 EP 1NV YV4 INV LVSGRM2 EP RECT YRF4 RECT LVSGRM2 EP PNL ESS Y4 PNL Lv6GRM2 EP MCC F12A MCC TI5%9M2 EP MCC F t5 MCC LVSGRM2 EP MCC F14 MCC LVSGRM2 VENT LV FAN 2 FAN
'.VSGRM2 VENT LV FAN E2 FAN MCCF 11BRM EP MCC-F 110 MCC MKUFCOR EP MCC E110 MCC l
MnUPCOR EP MCC-F 110 MCC MKUPRM ECCS DH98 MOV MAUPRM ECCS DH9A MOV MAUPRM MnUP MV32 NV MAUPRM MnUP MU1 2 MDP MnUPRM M6UP MU1 1 MDP MAUPRM MAUP MU3971 MOV MKUPRM MAUP MU3971 MOV MNSIMRM)
AhV MS11A NV I-g) 1
- 'wJ i
97 1/89
TABLE 4 2.
PARTIAL LISTING OF COMPONENTS BY LOCATIOt1 AT DAVIS DESSE (CONTINUED)
LOCATION SYSTEM COMPONENilD l COMP d
TYPE MNSIMAM2 AFW MS118 NV PENRMI ECCS PP PENhM1 ECCS HP2C MOV PENhM1 ECGS HP20 MOV FENRM1 ECCS DHIB MOV E5Ei2 AF W SW1363 MOV PENRM2 ECCS HP2A MOV P.' N RM2 ECCS HP2B MOV PENRM2 ECCS DHIA MOV PENRM2 EP MCC F11C MCC PENRM2 MoUP MU33 NV PENRMJ AFW AFW608 MOV IENAMJ AFW AFW 608 MOV E 4RM4 AFW AFW599 MOV TdNRM4 AFW AFW599 MOV 1
PPTUN EP MCC Fi1F MCC PPTUN EP MCC E12E MCC PPTUN RP MCC F11E MCC PWST MKUP PWST 1K RC RCS RCS VESSEL RV RC RCS OH i t MOV AC RCS ACEA.
l RC RCS MU2A MOV-I N
RCS Mu1 A MOV RC RCS MU2B MOV RC RCS MU 18 MOV AC RCS OH12 MOV RC RCS P2R HTR A HIR
- (G 98 1/89 1
TADLE 4 2.
PAFITIAL LISTING OF COMPONENTS BY LOCATION AT DAVIS DESSE (CONTINUED)
LOCA TON SYSTEM COMPONENT 10 COMP TYPE N
ACS PZR HIR B HlR N
VENT HC FCU 11 FCU HC YENT RC FCUal.2 FCU l
N VENT HC FCU t 3 FCU l
SWPPINL bW SW1399 MOV l
SWPPINL bW SW293 8 MOV l
j 6WPPINL SW SW1396 MOV M INL SW SW2929 MOV SWPPINL SW SW2932 MOV TD603 EP MCC-F 13 MCC TB603 EP MCC F13 MCC UNKNOWN EP PNL.Y1 A PNL
~UNKNOWN EP PNL Y2A PNL UN6NOWN MAUP MU40 MOV UNNNOWN MAUP OWST TK UNKNOWN 4 XUP OWX11 MOP UNKNOWN MnUP OWX12 MDP UNKNOWN MAUP OWX13 MDP
[U 99 1/89 l
Davis Besse 5.
BIBLIOGRAPIIY FOR DAVIS.BESSE O.'
- l. NUREG 0720, " Power Plant Siting and Design: A Case Study of Minimal Entrainment and Impin ement Impacts at Davis Besse Nuclear Power Station".
USNRC, December 19J0.
- 2. NUREG ll54, " Loss of Main and Auxiliary Feedwater Event at the Davis-Besse Plant on June 9,1985", USNRC, July 1985.
- 3. NUREG 1177," Safety Evaluation Report Related to the Restart of Davis.Besse Nuclear Power Station, Unit 1, Following the Event of June 9, !?85",
USNRC, June 1986.
l
- 4. NUREG 1201," Report of the Independent Ad floc Greap for the Davis Besse l
Incident", USNRC, June 1986.
- 5. Youngblood, R.,, nd Papazoglou, I.A., " Review of the Davis Besse Unit No.
1 Auxiliary Feedwater System Reliability Analysis", NUREG/CR 3530, Brookhven National Laboratory, February 1984.
- 6. Davis, C.B., " Davis Besse Uncertainty Study", NURE3/CR 4946, EG&G Idaho, Inc., August 1987.
- 7. Lime, J.F., et al., " Rapid Response Analysis of the Davis Besse Loss of-Feedwater Event of June 9,1985," LA Uh 161782, Los Alamos National Laboratory,1986, i
l
.v
' 100-1/89 p--
7<-.e
Davis Besse APPENDIX A DEFINITION OF SYSillOLS USED IN iE SYSTEM AND LAYOUT DRA%'INW, A 1.
SYSTEM DR A%'INGS A1.1 Fluid System Drawings The simplined system drawings are accurate representations of the major now paths in a system and the important interfaces with other Duid systems. As a general rule, small Duld lines that are not essential to the basic operation of the s drawings. Linct 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 connecting major now path, There usually are two versions of each Guid system drawingt a simplified system drawing, and a con.prJable 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 loads) or discharge paths are located on the right.
One exception is the return flow path in closed loop systems which is right to left.
Another exception is the Reactor Coolant System (RCS) drawing which is
" vessel centered", with the primary loops on both sides of the vessel.
Horizontal lines always dominate and break vertical lines.
Component symbols used in the fluid system drawings are defined in Figure A 1.
Most valve and pump symbols are designed to allow the reader to distinguish among similar components based on their support system req uirements (i.e., electric power for a rnotor or solenoid, steam to drive a turbine, pneumatic or hydraulle source for valve operation, etc.)
Valve symbols allow the reader to distinguish 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 ty of valve). pe of valve (l.c., as a globe, gate, butter 0y, or other specific type 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 this Sourcebook.
Location is indicated by shaded " zones" that are not intended to represent the actual room ;'cometry.
Locations of discate components represent the actual physical location of the component.
Piping locations bet veen discrete components represent the plant areas j
through which the pi underground pipe runs). ping passes (i.e. including pipe tunnels and Component locations that am not known are indicated by placing the components in an unshaded (white) zone.
The primary flow path in the system is highlighted (i.e., bolc.. ste line) in Q
the location version of the Duid system drawings.
U 101 1/89
Davis Desse A1.2 Electrical System Drawings Q
The electric power system dr, wings focus on the Class lE portions of the plant's
, Q electric sower system. Separate drawings are provided for the AC and DC portions of the Class 13 system. There often are two versions of each electrical system drawin simplified system drawing, and a comparable drawing showing component locations. g: a Die 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.
n the DC power drawings, the batteries and the interface with the AC power system are shown at the top of the drawing.
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 discre.e components, as shown on the electrical system drawings, DO NOT represent the actual cable routing in the plant.
O Component locations that are not known are indicated by placing the i
discrete components in an unshaded (white) zone.
A2.
SITE AND LAVOUT DRAWINGS A2.1 Site Drawings A 1;eneral view of each reactor site and vicinity is presented along with a simplified site plan slowing the arrangement of the major buildings, tanks, and other features of the site. The general view of the reactor site is obtained from ORNL N3iG 5' fRef.1). The site drawings are ap 3roximately 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 location codes definee in Section 4 and used in the component data listings and system drawings in Section 1. Some additionallabels are included for 'nformation and are printed in lowercase type.
A2.2 Layout Drawings Simplified building layout drawings are developed for the portions of the platt that contain components and systems that are described in Section 3 of this Sourcebok.
Generally, the following buildings are included: reactor building, auxiliary building, nel building, diesel building, and the intake structure or pumphouse. Layout drawing generally are not developed for other buildings.
Symbols used in the simplified layout drawings are defined in Figure A 3. Major rooms, stairways, elevators, and doorways are shown in the simplified layout drawings however, many interior walls have been omitted for clarity. The building layout drawings,
(
102 1/89
Davis Besse are approximately to scale, should not be used to estimate room size or distances. As built 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 pnnted in lowercase type, A 3.
APPENDIX B 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 I
i t
i 103 1/89 4
-~y
~,..,,,.,_,.,,. -..-,r_
~.., -.
.w
.c,,.c m..,,y.,
...., -... _ - _. - - -. ~. _ _.... -. -
..., -.... ~. -... ~
l LJ MANUAL VALVE, XV MANUAL NON RETURN F'
(OPENiCLOSED)
VALVE
- ICV (OPEN/CLOSFO)
O MOTOR OPER ATED VALVE. MOV yh MOTOR OPERATED (OP ENICLOS ED)
M 3.WAY VALVE
- MOV (CLOSED PCRT MAY VARY)
W LJ.
SOLENCIC.0PER ATED VALVE * $0V (OPENICLOSED) 80LEN0lp.0PER AT!iD F'
S.WAV VALVE SQV (CLOSED PORT MAY V4 sty)
_._2 HYDR AULIC V ALVE HV HYDR AULiC NCN RETURN F'
(OPEN/ CLOSED)
VALVE
- HCV (OPEN/CLCSED) 4 PNEUMATIC VALVE e NV (OPENICloS E D)
PNEUMATIC NOURETURN F'
VAX.VE
- NCV (OPEN' CLOSED)
CHECK VALVE a CV M
S AFETY VALVE
- SV (CLOSED)
B N
O J
POWER OPERATED RELIEP VALVE.
SOLENotD PILOT TYPE. PORV J
POWER.0PER ATED RELIEF V ALVE.
(cLCSED)
PNEUMATICALLY CPERATED PORV OR DU AL.FU NCTIO N S AFE TYtR ELfEr VALVE.SRV (CLOSED)
CENTRIFUC AL MCTOR. DRIVEN PUMP MDP CENTRIFUCAL TURBINE. DRIVEN PUMP + TDP 1 /
l POSITIVE DISPL ACE MENT MOTOR DRIVEN PVMP
- WP POSITIVE DISPLACEMENT TUR81HE. DRIVEN PUMP = TDP 1
L /
I O-D Figure A 1. Key To Symbols in Fluid System Drawings-104 1/89.
_-____._.._.--._..___-..,____...._._-_..m._.-_......_.....
r
[h t.
PWR>9WR MAIN CONDENSER e CONO f
HEACTOR VESSEL
- RV l
L J
A HEAT EXCHANQER e HX MECH ANICAL DR AFT
=
L, C00 Lino TOWER t
l-
EXCHANGER (1.E. FEE 0 WATER g
HEATER. ORAIN COOLER. ETC.)
- HX f
r=
0 OR TANK + TM 8
OmES * $N aaaaoaoa Y
n RUPTURE DISM e AD-FILTER
- FLT ORIFICE o OR
~
r i
~
Figure A-1<
Key To Symbols In Fluid System Drawings
.(Continued) 105 1/89-
=.m.._
i T
A.C. DIE 8EL CENER ATOR. 00 OR A.C. TURDINE GENERATOR TO S ATTERY. BATT
\\
g (C PE NICLO8 ED) g).. g eq lp....[]
INTER 40CKED CIRCUlf BREAKERS
- C8 SWITCH. SW p
,WTC M ATIC OR OR OTNER TYPE OF TR ANSFEH SWITCH
MANUAL TRANSFER i
8 WITCH MTS j
l SWITCNCE AR 3V8
l On i
DISTRIBUTION P ANEL. PNL i
i l.
v i
B ATTERY CHAR 0ER (RECTIFIER). BC g SZ INVERTER. INV I
t
?
I M
RELAY CONTACT"4 og
~~
j 7
(O P E N/ CLOS E D) pysE. F3 i
I i
y tLECTmc uCToM. MTR woro, oEutnx,og. yo i
1 1
i i
i i
2
~
i i
Figure A-2. Key To Symbols In Electrical System Drawings
=
-106 1/89-
O STAIRS SPIRAL
"{
STAIRCASE D = Down
(-
LADDER M
ELEVATOR U. Up
- D = Down l
gw'-
if ATCH OR OPEN AREA GRATING DECK (NO FLOOR)-
-O-PERSONNEL DOOR
-i
- EQUIPMENT. DOOR.
EE 55 RAILROAD' TRACKS
- (
FENCE LINE
- g O ' TANK / WATER AREA l
Figure A-3.
Key To Symbols in Facility Layout Drawings j
107
.1/89 i
s.
_~
Davis Besse APPENDIX 11 DEFINITION OF ' PERMS USED IN Tile DATA TAllLES Terms appearing in the data tables in Sections 3 and 4 of this Sourcebook are s
l defined as follows:
l 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:
-l C.ch Definition RCS Reactor Coolant System i
AFW Aux!!iary Feedwater System ECCS
., nergency Core Cooltea System MKUP Makeup and Purification' System I&C Instrumentation and Control System EP 91ectric Power System CCW Qmponent Cooling Water S.vstem SW Service Water System VENT Equipment and Control Room Emergency Ventilation Systems COMFONENT ID (also LOAD COMPONENT ID) - The component identification (ID) code in a data tabic.natches the component ID that appears in the corresponding system drawing. The component ID generally beginsivith a system preface followed by a component number. The system preface is not necessarily the same as the system code L
described above. For component ids, the system preface corres 4
l calls the component (e.g. HPli RHR). An example is HPI-730, ponds to what the plaro denoting valve numFer 730 in the high pressure injection system, which is part of the ECCS. The compo.ent t
number is a contraction of the component number appearing in the plant piping and-instrumentation drawings (P&lDs) and electrical one line system drawings.
LOCATION (also COMPONENT LOCATION and POWER SOURCE LOCATION) -
Refer to the location codes defined in Section 4.
COMPONENT TYPE (COMP TYPE)- Refer to Tavle 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 partX lar component L
(i.e. a load or distribution component) is the next-higher electrical distribution or L
generat' ag compnent in a distribution system. A s.. ;le com ponent may have more than one power source (i.e. a DC bus powered from a battery and a battery charger).
POWER SOU_RCE VOLTAGE (also VOLTAGE)- The voltage "scen" by a load of a power source is entered in this field. The down3tream (output) volmge of a transformer, mverter, or battery charger is used.
L O
l LOS-1/89 Y
g l-Davis Besse l
EMERGENCY LOAD GROUP (EMERG LOAD GROUP)- AC and DC load groups
(
(or electrical divisions) are d: fined as appropriate to the plant. denerally, AC load groups
(
are identified as AC/A, AC/B, etc, The emergency load group for a third of a kind load (i.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.
l lo t
i l
i
'J 109-1/gg
TABLEB1.
COMPONENT TYP'E' CODES COMPONENT
. COMP TYPE VALVES:
- 1 Motor operated valve MOV Pneumatic (air operated) valve
- NV or AOV Hydraulic valve _
. HV-i
' Solenoid opera ;d valve SOV Manual valve XV Check valve CV Pneumatic non-return valve NCV Hydraulic non return Valve
Dual function safety / relief valve
'SRV-
. Power-operated relief valve PORV (pneumatic or scienoid-operated)
PUMPS:-
Motor-driven pump (centrifugal or PD)
MDP Turbine driven pump (centrifugal of PD)
TDP Diesel driven pump (centrifugal of PD)
DDP-OTHER FLUID SYSTEM COMPONENTS:
Reactor vessel:
RV' Steam generator (U tube oronce through)
.}- -
Heat exchanger (water to water HX, HX-or water to air HX)
Coolin CI' Tank g tower TANK or TK Sump S UMP --
Rupture disk -
RD Orifice ORIFL Filter or strainer FLT Spray norzle:
SN Heaters (i.e pressurizer heaters)
HTR VENTILATION SYSTEM COMPONENTS:
Fan (motor driven, any type)
FAN '
Air cooling unit (air-to water HX, usually ACU or FCU..
including a fan).
Condensing (air-conditioning) unit COND-EMERGENCY POWER SOURCES:
~ Diesel generatcr -
DG' Gas turbine generator
- GT Battery BA~IT 4
O 110-
.1/89 k
-... a
.x...a n ~=---
" " " - ~ " "
e TABLE B1.
COMPONENT TYPE CODES (Continued)
CO MPONENT COMP TYPE ELECTRIC POWER DISTRIBUTION EQUIPMENT:
Bus cr switchgear 9US Motor control center MCC Distribution panel or cabinet
- PNL or CAB Transformer
- TRAN or XFMR -
Battery charger (rectifier) '
BC or RECT Inverter
- INV Uninterruptible power supply (a unit that may I'PS include battery, battery charger, and inverter)
. Motor generator
~
MG C" -:t breaker CB i
Switch SW i
Automatic transfer switch ATS Manual transfer switch MTS i
1 1
j I.
l l,
l, p-i i
v
~111:
1/gg x
t
{
.-