ML20070Q767
| ML20070Q767 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1988 |
| From: | Finn S, Lobner P SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
| To: | NRC |
| References | |
| CON-FIN-D-1763, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-88-1019, NUDOCS 9103290172 | |
| Download: ML20070Q767 (106) | |
Text
_. . ______ - ___ __ ____ ______-____- __ _ _ _ _
l l l l
I
- O %
l %,
l 8 o NUCLEAR POWER PLANT 5
- c "5 E
g SYSTEM SOURCEBOOK
/ ( 'T 4 4 _- --
MILLSTONE 3 50 423 i
O ..
b 9103290172 910327 DR 9 ADGCK 0500]
... - .. _ .. .._, .. .. . - ...., .._.. _ ....-. _ ... _. - . .~..__.. ._ -... ,...._. . _ -_..__._. .
S AIC 89/1019 00 lq 8 o NUCLEAR POWER PLANT 5 $ SYSTEM SOURCEBOOK
- i e
% 4
% me r MILLSTONE 3 50 423 c
Editor: Peter Lobner Author: Stephen Finn Prepared for:
U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Contract NRC 03 87-029 l FIN D 1763 i
i
(
N!illstone 3 TAIILE OF CONTENTS r
h Section (G 1 SUhthlARY DATA ON PLANT .
Eags
.... ..... ...................... .... . . I 2
IDENTIFICATIO'NOF SlhilLAR NUCLEAR POWER PLANTS ....... 1 3
S YS TE h ! I N FOR h tATI ON . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.1 Reac tor Coolant System (RCS) , . . . . . . . . . . . . . . . ..... ........... .. S 3,2 Auxiliary Feedwater (AFW) System and Secondary S team Relief (S S R) System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 3.3 Emergency Core Cooling System (ECCS) .. .... .......... .... 20 3.4 C h arg i n g S ys te m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 3.5 Containment Heat Removal System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33 '
3.6 Instrumentation and Con trol (I & C) System. . . . . . . . . . . . . . . , . . . . . . . . . 39 3.7 Electric Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 3.8 Service Water (S W) System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61
.1 PLANT INFORhtATION ... .. . . . . ........... ............. ,, . .... .... . 68 4.1 Site and Building Summary ... .. .,... .. ..................... ...... 68 4.2 Facility Layout Drawings ........ .. . . ..
........ ... ............ 68 5 BIB LIOG R AP HY FOR N11LLSTONE 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . 88 APPEhDIX A Definition of Symbols Used in the S Layout Drawings. . . . . . . . . . . . ..,. ....... ... . . .......
. .ystem 89 and O
t APPENDIX B
'Y Definition of Terms Used in the Data Tables .......... 96 s
i e
1 i 1/89
Millstone 3 LIST OF FIGURES 4
/7 O fin!m Em .
31 Cooling Water Systems Functional Diagram for Millstone 3.. ....... . 7 3.1 1 Isometric View of a 4. Loop Westinghouse RCS . . .... .. . ... . .. . .. . 10-3.12 Millstone 3 Reactor Coolant System ............................... I1 3.1 3 Niillstone 3 Reactor Coolant System Showing Component Locations . . . . . . . . . . . . . ....... .. ................ .... . . . ... .... . 12 1
- 3. .' . ! Millstone 3 A uxiliary Feed wa ter Sys tem . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 17 3.22 Millstone 3 Auxiliary Feedwater System Showing Component-Locations . . . . . . ............ ....... .................. . .............. .. 18 3,3 1 Millstone 3 High Pressure Safety injection System......... ......., ... 23 4
3.3 2 Millstone 3 High Pressure Safety Injection System Showing Component Locations.. .. .......................... ............. ..... 24 3.3 3 Millstone 3 Residual Heat Removal System . . . . . . . ..- . . . . . . . . . . . . . . . . . . . 25
, 3.3 4 Millstone 3 Residual Heat Removal S N Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . .ys tem S ho wing Compc,ne nt
.......... ... ...... ........ ... .. 26 3.4 1 Millstone 3 Charging S ystem . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 3.42 Millstone 3 Charging System Showing Componer.t Locations....... ... 31-3.5-1 Millstone 3 Containment Recirculation System ... ... ... .. ...... ..... . ..
35
- 3.5-2 Millstone 3 Containment Recirculation System Showing Component j Loc a ti oris . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .36 ....................
i i 3.7 1 Millstone 3 4160 and 480 VAC Electric Power Distribution System . .
i 49 f
! 3.7-2 Millstone 3 4160 and 480 VAC Electric Power Distribution S l
S howing Component L.ocatior.s . . . . . . . . . . . . . . . . . . . . .......... . . . . . . . . 50
. . . . .ystem
- 3.7-3 Millstone 3125 VDC and 120 VAC Electric Power Distribution l System....................................................................... 51 3.7 4 .;fillstone 3125 VDC tind 120 VAC Electric Power Dis ribo
- ion S y sum Showing Component Locations.................... . .......... . 52 3.8 1 Millstone 3 Service Water Sys tem Loop A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
i 63 3.8 2 Millstone 3 Service Water S i
Locations . ........ ....... ..ystem Loop A Showing Component
...... .......... ........... ........... ... . 64
\
. il 1/89 i
4 I
. - ,e~ .r . .> ,, , , - - - ~ , , 4, .,
hlillstone 3 LIST OF FIGURES (continued) fhm M 383 hiillstone 3 Service Water System Lcop B. .... , ........... . ...... 65 3.8 4 Stillstone 3 Service Water System Loop B Showing Component
' oc a ti o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .............
.. ...... 66 41 General View of hiillstone 3 Nuclear Station and Vicinity . , . .. . . 70 4-2 h1illstone 3 P1ot P1an .. . .......... . ....... . ..... .............. . 71-43 Stillstone 3 General Arrangement, ESF, Fuel, and Auxiliary B uildi n g s , Ele va tion 3' - 6" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 72 4-4 hlillstone 3 General Arrangement, ESF, Fuel, and Auxiliary B u ildin g s, Ele vation 24' - 6" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73 45 htillstone 3 General Arrangement, ESF and Fuel Buildings Eleyation 5l'-4"................................. ...... . ....... .... 74 46 hiillstone 3 General Arraagement, Control Building and Diesel Generator Enclosur,:, Elevation 4' 4 6"..................,............... 75 47 htillstone 3 Contnl Building and Diesel Generator Enclosure, O
. N'./
Elevation 47' -
6",............................................................ 76 4-8 htillstone 3 General Anangement, Circuladng and Service Water Pump House, Elevation 14' - 6" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 A-1 Key to Symbols dsed in Fluid System Drawings., ......... ............ 92 A2 Key to Symbols Used in Electrical System Drawings .................... 94 A3 Key to Symbols Used in Facility Layout Drawings...... .......... ..... 95
/
v'-
m ,/89
Stillstone 3 LIST OF TAl;LES
\ TaNe Pags 31 Summary of Millstone 3 Systems Cover *d in this Report.... .... . 3 3.1-1 Stillstone 3 Reactor Coolant System Data Summary for S e lec ted Com po ne nt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 3.2-1 5!illstone 3 Auxiliary Feedwater System Data Summary for S e lec ted Com pone nt s . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 3.3-1 h!illstone 3 Emergency Core Cooling System Data Summary fo r S elec ted Com pon en ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 3.4 1 51illstone 3 Charging System Data Summary for S elec ted Compone n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 3.5 1 hiillstone 3 Containment Heat Remov.d S stem Data Summary
, for Selected Components... .............. ............... ,,....... . 37 3.7-1 hiillstone 3 Electric Power System Data Summary for S e le c ted Co m po ne n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 53 3.7 2 Partial Listing of Electrical Sources and Loads at Millstone 3......... . 56 O 3.8 1 Millstone 3 Service Water System Data Summary for Q. S e le c te d Com pone n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .67 .....
4-1 Definition of Millstone 3 Building and .acatior. Codes ... .............. 78 42 Partial Listing of Components by Location at Millstone 3........ ....... 82 B.1 Co m po n e n t Type Cod e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .9' .
i a
b a
e
\
t -'
iv 1/89
Milhtone 3 g
)
d C-\ UTION The infomwtion in this repo .ias been developed over an extended period 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 knowleJge, it accurately reflects the plant configuration at th e time the information was obtained, however, the information in this do.ument 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 it. corporate additional information on this reactor plant. Technical rtrors in this report should be brought to the attention of the folloaing:
hlr. Mark Rubin U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Engineerir.g and Systems Technology Mail stop 7E4 Washington D.C. 20555
,fm, ;
' .j With copy to:
Mr. Peter Lobner Manager, Systems Engineering Division
- Science Applications Intemational Corporation 10'.10 Campus Point Drive
' San Diego, CA 92131 1
(619) 458 2673 j
Correction and other recornmended changes should be submitted in the form of marked up copas of the affected text, tables or figures. Supporting documentatic.n should be included if possible.
i f
B I
(- 2 l
v [fgg
4 MILLSTONE 3 RECORD OF REVISIONS l
! REVISION ISSUE COMM ENTS l 0 1/89 Original report t
i J
i e
f i
. s j
)
l i
4 f
I e
i i-4 i
r 4
i a
e 4
n*
1 N
3 s
-'/ vi 1/89-4
-. . . .. , , . . . . - . . - , _ , . . - - . . . , _ . , . . , . . . . . . , . . . . . . . . . . - . . _ . _ . . ..- . ., . . . . . _ . . . . - . , , . . ~ . . ~ . . . .
Md!s one MILLSTONE 3 SYSTEM SOURCEBOOK
(~T This sourcebook contains summary information on Millstone 3. Sununarv data t
O') 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 preunted in Section 3, and the sue and building layout is illustrated in Section 1. A bibliography of ret rts that deenbe features of this plant or site is presented in Section 5. Symbols used in the sptern and layout draw;ngs are defined in Appendix A. Terms used in data tables are defined in Appendix B.
I
SUMMARY
DATA ON PLANT Basic information on the Millstone 3 nuclear power piant is listed below:
Docket number 50 423 Operator Northeast Utilitie .
Location New London CT Commercial operation date 4/86 Reactor type PWR NSSS vendor Westinghouse Number of loops 4 Power (MWt/MWe) 3411/1150 Architect-engineer Stone and Webster Containment type Reinforced concrete cylinder with steel 4
liner, subatmospheric
- 2. IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS b
Nj Millstone 3 unit has a Westinghouse PWR four-loop nuclear steam supply system (NSSS). Other founloop Westi-4.ouse plants in the United States includt Braidwood 1 and 2 Byron 1 and 2 Ca!!away Cat wba 1 and 2 Comanche Peak 1 and 2 Donald C. Cook 1 and . (ice condenser containment)
Diablo Canyon 1 and 2 Haddam Neck Indian Point 2 and 3 McGuire 1 and 2 Oce condenser containment)
Salem i and 2 Seabrook 1 Sequoyah I and 2 (ice condenser containment)
Shearon Harris 1 and 2 South Texas 1 and 2 Trojan Vogtle I and 2 Watts Bar I and ?
Wolf Creek Yar:kee Rowe Zion 1 and 2
/m (JI L
l 1/89 i ~ -
Millstone 3 Millstone 1 differs from the triajority of Westinghouse plants in that it contains three
,Cg t
centrifagal charging pumps whereas most other plants contain at least one positive V
j displacement charging pump. Millstone 3 is similar to other plants in the number and type ef auxiliary feedwater and high pressure injecnon pump.s.
3, SYSTEM INFORMATION This section contains descriptions of selected systems at Millstone 3 in terms of ,
general function, operation, system success criteria, major comr>onents, and n ; port system requirements. A summary of major systems at the Millstone 3 is preserc.;d 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 encry 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 additional information or, each system can be fout d, Other sources of infonnation on this plant are identified in the bibliography in Section 5.
Several coolinr , vater systems are identified in Table 31. The functional relationships that exist att og cooling water systems requi ed for safe shutdown are shown in Figure 31. Details on ine individual coolmg water sy stems are provided in the report
>ections identified in Table 3-1.
l C
i 1
l 1
\
l l
l l
l
/%
, (m) 2 1/89
.-.. .~ ~ . - . . - . . - - - . - . . - - . - - - . . - -.- .- . - - . - . . - . .- . -- . .. .
s e t
, i v7 :
i Table 3-1. Summary of Millstone 3 Systems Covered in this um . .r t Generic Plaut-Specific Report 1SAR Sergion Svstem Name System Name Secli,gi ][e t crenet- <
Rescler lleat Removal Systems t Reactor Coolant System (RCS) Same 3.I :5 t
-- Auxiliary Feedwater(AFW)and Sane 3.2 m.4.9 Secondary Steam Re!ier'(SSR) c Systems ' i
.t l-Emergency Core Cooling Systems 1 (ECCS) .
} .- iligh-hessure Injection ' Safety injxtion System 3.3 ' 6.3 1& Recirculadon 1 . - Low-pressure Injection' -
1 . & kccirculation - '
u k -
Decay IIcat Removal (DI1R)L . ResidualIleat Removal (RI1R): -3.3 ' 6.3 i- System (Residual IIcat Removal System " ,
I (RHR) System) -
Main Steam and I$wer Couversion ~ ' Main Steam System, Ctedensate - X 10.3, 10.4 Systems arxi Feedwater System, Circulating -
Cooling Water System
- -- Other Ifeat Removal Systems None identified X k -Reaclor Coolant . Inventory Control Systems i- - 'ChemicchM Volone Comrol System ' Charging System 3.4 6.3 (CYCS) (C.iarging System) . .
g 4
f'.
r t-- g# g 7 ,. , ., m - . , ....,% . , _ _
.% , y
k; ! ' ; i{ci !! !' r (.: - 3 '! , ,
n i
o t
c ec e
Sne
)
d Rr c 3
_. e Ar 2; 7 5 1
. u Se 2 2 4 2 6 2 3 n Fh 6 6
'4 i
t
- 9 6 4 4 - 7 7 7 n
o
. . C
(
t n
_ t r ro o oi p pt c
_ e ee 5 6 6 6 RS X
, R 3 - X X X X - 3 3 3 i
s
. h t m n m
_ e o c ;
. i n t p
i t
a g i s
S l
ri n y f it er n n S
- ar o e no i t m e l V bi e r e
_ e ,it n o n m ml a e mo o
t s
y n. ' P a
eu r u cM S c O sr c n
_ F t
t e m s e
- yi c c u Re n e v v e e t
y o
w Se r ng- i s fe t
m e k'm n
a ca yR S' t
e or D r
b o
S y
a dt u
at t gd a o y -- p S
. t s eN r n n d h
- - y p pr e r l o S
.ir de S S S-m
- S n hn m'
n d
y I R C T r y ,
t ci a im l
mm l o V r e r a
3 nt e o e I
e e a e e . s n nt en n t Atee 'e t r C t c n i l
_ n I y a uo o nt s oy Bss yy t
m a
n.
- o. e a e
i' g
i x
u t
R E r
A
_ l s
l i
s M r m e
f s m t
_ o
. m e
t s
e s'-
y y
r s t
y- S s
- a m y s
S . ) n
- m e m S l C~ o' t
e n m o it ~
m s y t s o e r 4)S a
_ u y it t
s t 1
(P u' S Sm S a y n o' R t
c l
ae vt s r e
l i
t n
S l
C l
o(
rm A
e
_ 1 3
s oy mS ey l
o' o V e
t o
r n
y t
ni c os r
u t
a t
e m
s C
_ t
_ l o i y y e m e
Ra r n a
n C i v'
m - CS F e
S l
t s' ap t
a n s t
c e s - n y) n b
a y eS F o a a t
s &o t w
T S l
l t
n t
n N G e' S y m e nce i
t f
eS aA o
. g t n t e n e t e Rer t s o't SF dt n
i.
t n e em n m~
n en l b do d
o S y i t o r deES u
i
_ a emn mi na i
a m
i t
s nC R. n t aP r(
l S
N mi n u aro l o o nr e e eo it em t
c nt a an n i a b t n e o i
_ r n o o rc t t t t im r in ao oC C n m oa t
n a r mtc i gs uea t
- ee o o t e o o ny m e
nt e s y t
nC o'
C.' - C C cR a C. B t rR ES R e s GS C- n
_ p R-L I -
- [: i
,ii;~:.}^ i!!i <'i' , i;t 15l ,ll . i ,t - !
t Table 3-1. Summary of Millstone 3 Systerns Covered in this Report (Continued) '
Generic , Plant-Specific Report FSAR Section System Name System Name Section Reference t Instrumentation & Control (I&C) Systems (continued)
- Other1&CSystems .Various Systems - 3.6 7.4. 7.5. 7.6, 7.7 '
Support Systems Class IE EIectric Power System Same 3.7 8.1.5,83 i Non-Class IE Electric Power System Same 3.7 8.2,8.3 Diesel Generator Auxiliary. Systems Same 3.7 8.3.1.1.3, 9.4.6 t 9.5.5, 9.5.6 l
- Component Cooling Water (CCW) Same 9.2.2..1 i System -
L.
-- Service Water System (SWS) Same 9.2.1 -
- Other Cooling Water Systems Turbine Plant Component Cooling -X 9.2.2.3 to 9.2.2.6,
- Water System, Neutron Shield 9.2.7 !
Tank Cooling System, Charging ;
Poinps Cooling System, Safety (
Injeuion Pumps Cooling System, Condensate Demineralizer . l
- Componem Cooling Water System
-l' e ~ Fire Protection Systems Same X 9.5.1 Roon:1Icating, Ventilating, and Air- Sane X 9.4 Conditiening (1IVAC) Systems
.g. - Instrumem and Service Air Systems- Same X 9.3.1 m
i i
..u_ _ _ . . _ _ . _ _ , _ . . _
_ _ . ~._u..- _- ._. _ ,,
> !: 1I; ,I ;l;>li>Ij,:= ' . \i: ! - .h1 , a - l!ili! , , ; r [! ihf!! l!! ; fI:! i*:i; a1a 1 4
. n i
o t
c e e c Sne
. )
- d Rr e e Af u Se I n FR
. 1 2
- i t
9 1 1 n
o C(
. t n t
r ro oi
- R o
p e
pt c ee RS X X X
. i s s
. h m w t
t e t n s n
. i y e
. S m d g e e n g r i a
e i l
n v m a o a M
.. C l l
e e
- s iec d t s
m f n a
a g e i m W
- ca e .,
r e t
s y pN g e v
a r
S S o i
t c s
- m t am -
3 t nt e S o e e j l i
. e as e ds t
m n l y u ay a o PS F RS S l
t s
l i
M f .
- o -
y i.
'g
- r ,
a s S
m m
u t
e s
y m
s' s
- S m
- l m e t
. e e s 1 u t s y 3
F y 'S
- S n t
e n o l e p t e' i b s t c
- a S a e
-. T e d
n W t o
r a e P
- m g v n
a n i
t c o
- N i l a i
'c e u i o i t
a
- imr ee f
e d a d a
.-. nt s R R~ R
- e y
. GS .
i.
. C Cc
~
Il1l!c
- . 1- i it sl
- ;; j.ii{ :'f j4 {!I 3ij! .
I$ ! t l'!!!i":?t[:ifiI !ti!II:1i+ :
,n~ (-- -~
-~
) ( ) ,
xj 'v/ '\,,)
i r %
--* COOLERS V -)
HPSI P CHARGitJG PUMP COOLERS j r 3 CRS 11 EAT
"
- EXCHAtJGERS NIAtJTIC ( J CIRCULATitJG BAY P SWS P WATER DISCHARGE --
r 'S TUtJtJEL
' J ' J RHR llEAT EXCHAf4GERS L. J r 3 AFWS SUPPLY L J r 3 ESSEtJTIAL
-* LOADS AFWS = AuxAary Feedwater System q j CRS Concairurces HecucuLstson System y sws - serwce was system o
Figure 3-1. Cooling Water Systems Functional Diagram for Millstone 3
hlillstone 3 3.1 REACTOR COOLANT SYSTESI (RCS) a 3.1.I System Function The RCS transters 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) reactor coolant loops, (c) reactor coolant pumps, (d) the primary side of the steam generators, (e) pressurizer, and (f) connected piping out to a suitable isolation valve boundary. An isometric drawing of a &
j loop Westinghouse RCS is shown in Figure 3.1 1 Simplified diagrams of the RCS and
)
important system interfaces are shown in Figures 3.12 and 3.13; A summary of data on selected RCS components is presented in Table 3.1-1, 3.1.3 Ststem Omrntion During power operation, circulation'in the RCS is maintained by one reactor coolant pump in each of the four reactor coolant loop RCS pressure is maintained within
' a prescritx d 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 pcescribed band by the chemical and volume control system (charging system).
i At power, core heat is transferred to sccondary con! ant (feedwater) in the steam -
generators. The heat transfer path to the ultimate heat sink i: completed by the main steam and powe* conversion system and the circulating water system.
Following a transient or small LOCA (if RCS inventory is maintained), reactor i core heat is still transferred to secondary coolant in the steam generators.- Flow in tne RCS -
' is maintained by the reac:ar coolant pumps or bv natural circulation. The heat transfer path to the ultimate her, sink can be established by u' sing the secondary steam relief system (see Section 3.2) to vent main steam to atmosphere when the power conversion and circulating water systems are not available. If reactor core heat removal by this alternate path is not adequate, the RCS pressure will increase and a heat balance will be established in the RCS by venting steam or reactor coolant to the cor.minment through the pressurizer relief valves.
There are two power operated relief valves and three safety valves on the pressurizer A t continued inability to establish adeguate heat transfer to the steam generators will result in a LOCvlike condition (i.e., continuing loss of reactor coolant through the pressurizer relief valves). Repeated cycling of these relief valves Ms re<ulted in valve failure (i.e., relief valve stuck open).
Following a 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 cooling systems must operate in order to complete a heat transfer path to the ultimate heat sink (see Section 3.5).
3,1,4 System Success Criteria 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 IJX'A is initiated, then LOCA mitigating systems are successful.
If a transient is irulated, then either:
8 1/89
hlillstone 3 p) b RCS integrity is maintained and transient mitigating systems are successful, or RCS integrity is not maintained, leading to a LOCA-like condition (i.e.
stuck open safety or relief valve, reactor coo'am pump seal failure), and LOCA mitigating systems are successful.
3.1.5 Comoonent Information A. RCS
- 1. Volume' 12,240 ft ,3 including pressurizer
- 2. Normal operating pressure: 2250 psia B. Pressurizer
- 1. Volume: 1400 ft3 C. Safety Valves (3)
- 1. Set pressure: 2485 psig j 2. Relief capacity: 420,000 lb/hr each D. Power Operated Relief Valves (2)
- 1. Set pressure: 2335 psig
- 2. Relief capacity: 210,000 lb/hr each E. Steam Generators l . Type: Vertical shell and U Tube c 2. Model: Westinghouse 51 Series
(
, V) F. Pressurizer Heaters
- 1. Capacity: 1800 kW 3.1.6 Suonort Systems and Interfaces A. Motive Power
- 1. The pressurizer heaters are Class IE AC loads that can be supplied from the standby diesel generators as described in Section 3.7.
- 2. The reactor coolant pumps are supplied from Non-Class IE switchgear.
B. Reactor Coolant Pump SealInjection Water System The chemical and volume control system supplies seal water to cool the reactor coolan: pump shaft seals and to maintain a controlled inleakage of seal water into the RCS, Loss of seal water flow may result in RCS leakage through the pump shaft seals which will resemble a small LOCA.
1 m
T)
L# 9 1/89 1
CEdt ATOR
<W V
R v
J s (h MAIN Q v .
CY"'
J D
'I 6 C M v
/> l I t !
w PRES $URilER REACTOR Figure 3.1 1. Isometric ylew of a 4 Loop Westinghouse RCS.
f)
(/
10 1/89
1
- U O I _
J+>i -
i i
4p.3 s; oh.l s p.3 -
y g' ', .
i Dr di $c e di L
+Il' q! o-I!
C >-s E '
C >W W sv 1' 1- se .i 1
[ )]
A 3j I *k! d.!oxi qi oXl . oxl i 3- +ft lim! e!
Lt.
s gi ,v 1 aa, s
.e 2
aid &
a a
- 9. 8 18 .L o i! !!! !!1 s t
! i i ,t i-g- .e.
, -+I! It +I1 In i i i ery
-i .g-r n g
- i. ;
. 2
{g E
, ,- 2
! !j i
[
- v4 y i$ l !!-E di zi-- , )
I - 13 -1 i A
- i "bg! oK!
, 31--c< & it i
. y
-c , a til-e
> ,s-l
/ oXi oI! 'ag3g! oXi 4 4 i i I!- :s
-) 1 83' jo'{,l _).]
2
-] ~j- Is; -lg; -j i ( % _W l(- M -W M' 4!
l -J +xt mti
- f. 2 -
f 1.. i 2 - 1
! ! 8 .i -S i
I j_ _
8!
lf!l !' o l f ---e{J(: 5l -
[ j f 11: t/89
,.,,,.:,,,-.,...-c+~--- - - - ~ - - - + - - - - - ~ - - * - ~ ~ ^ ~
' In A !E R ;
lc) E
, rota.: n L
t
!. og1 -
itt! El itti 1; rog! !. i i 4
$ )! 4\f k ! f fli cfIl
' ey! o-Il
( >w & '
( >-r e se
] ] se ] i d) l i
!,! l 8 2
OI,i li,! si 3
- gjoM oxl ", !
ffi li-m &
8.
+hl I' Alj l
h e
.s
- g n ,
8 to ... .I ,
si 11! 111 a
-t t l f O
\j
- &I!
l EioKi L_
XI oEl 1
>I- !
- 3 da, l e 1:
s ,
u elg- - =
, ! b !
ltfi~ 2 aft, e
. lia i i
s 4 a r
! .og!L 4t1 v i l' "
s j
/ ' oli LoKIIl!oli- $
,si! e 3
i rr a d Li 8
Q ) as-i 5
OE*.I *oxi. ,- 1; 1. -
1 1
>w e -( 15 e bX3bX[
0-Il j (.):(
,o
- fp oMis i
) ;-
fp ign i a g i of.I 'gu!
t E- ,, i t-b g j.'
i ; a,-
12 1/89
fs -es
( O U Table 3.1-1. Millstone 3 Reactor Coolant System Data Summary for Selected Components COMPOlaENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
RC-455A NV HC RC-456 NV RC RC-8000A MOV flC MCC-3A2 480 ABS AC/A RC-00008 MOV RC MCC-3B2 480 AB6 AC/B RC-8701A MOV HC MCC-3A2 480 ABS AC/A RC-8701C MOV RC MCC-3A2 480 ABS AC/A RC-87028 MOV RC MCC-382 480 AB6 AC/B RC-8702C - MOV RC MCC-382 480 ABS AC/B RCS-VESSEL RV RC l
c i
J r
4 i
u
\
j-1 i
4 4
Atillstone 3 3,2 AUXILIARY FEEDWATER (AFW) SYSTEM AND SECONDARY RELIEF (SSR) SYSTEM 3 3.2.1 System Function l The AFW system provides a supply of high pressure feedwater to the. ,
secondary side of the steam gene.ators to remove heat from the reactor coolant system (RCS) w hen: (a) the main feedwater system is not available, and (b) RC5 pressure is too 4
high to permit heat moval by the residual heater removal (RHR) system. The SSR system provides a om vent path from the steam generators to the atmosphere, thereby completing the heat transfer path t_o an ultimate heat sink when the main steam and power ,
i conversion systems are not available. Together, the ARV and SSR systems constitute an
! open loop fluid system that provides for heat transfer from the RCS following transients l and a small-break LOCAs.
l 3,2,2 System Definition The ARV system consists of two motor-driven pumps and one turbine driven
- pump. The normal water sources for the pumps is the demineralized water storage tank
- (DWST). An alternate source of wateris the condensate storage tank (CST). The turbine-driven pump can supply all four steam generators while each motor-driven pump can supply two steam generators. The turbine driven pump can be supplied with steam from
", three of the four main steam lines.
- _ The SSR system includes five safety valves and one power-operated pressure
, control valve on each of the four 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 ARV system components is presented in Table j 3.21.
j 3,2,3 System Ooeration i During normal operation the AFW system is in standby. Ordinarily, the ARV l system is required to operate for about 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to cool the unit down to 350 F, below I
which temperature the low pressure residual heat removal system operates.
! Motor-driven pump 1B is automatically actuated on either two of four low-low level signals in any steam generator, a safety injection signal (SIS), loss of power, or a i containment depressurization actuation (CDA) signal. Motor driven pumpl A--is
, autematically actuated whenever any of the above conditions occur and control is not in LOCAL. The turbine driven pump is automatically actuated on loss of power or two of
! fotr low low water level signals in any two of four steam generators, The system can also -
, be manually started from the control room.
The primary suction source is the demineralized water storage tank. The DWST is designed to-support the plant for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> in a hot standby condition; An additional source of water is the condensate storage tank;- However, this source is not-i safety related and is not considered available-for safety related purposes. The normally j closed air operated valves connecting the CST to the motor driven ARV pumps are closed -
automatically on receipt of an SIS, CDA, AFW pump auto start, or loss of electrical power
!- (LOP) signal. The turbine driven pump is isolated from the CST by an administratively l locked closed valve. The service water system can also provide water to the AFW pumps.
! Howeve , spool pieces must be installed to connect the two systems. _
Flow from each pump goes to all four steam generators through independent i: paths. Flow is regulated by control valves which are manually adjusted from the control L room or the auxiliary shutdown panel.
l 4
f.
i 14 1/89 4
1
- . . - ..- - - - - . - - - . - . , .... - . . ..~ .. - . . . _ - . . - - - . - . . . . - . . .
Stilistone 3 3.2.4 Svstem Success Criteria
, For the decay heat removal function to be successful, both the ARY system and-
\
the SSR system must operate successfully. The ARV success criteria are the following (Ref.1. Section 10.4.9):
Two motor-driven pumps or the turbine driven pump can provide adequate flow.
Water must be provided from the demineralized water storage tank or the CST to the ARV punm suctions . Note that the CST is not a safety telated source.
Makeup to any two steam generators provide adequate decay heat removal from the reactor coolant system.
In NUREG/CR 4142 (Ref. 2), different system success criteria is described as follows:
l_
Deliver 235 gpm to at least 3 of 4 steam generators Conflicting references are made in NUREG/CR 4142 (Ref. 2) and in NUREG ll52
- (Ref. 3) that any one ARV pump can 3rovide adequate makeup to the steam generators,-
even thcugh each motor-drive pump on y supplies two steam generators.
The SSR system must operate to complete the heat transfer path to the environment. The l numter of safety valves or secondary steam relief valves that must open for the decay heat t removal function is not known.
3,2,5 Comoonent Information A. Motor-driven ARV pumps l'A and IB
- 1. Rated flow: 575 gpm @ 2975 ft, head (1290 psid)
- 2. Rated capacity: 100% each
- 3. Type: Centrifugal ,
B. Turbine 1. Rated flow: driven 1150 ARVgpm pump 2975@2.
ft, head (1290 psid)
- 2. Ratedcapacity: 200%
- 3. Type: Centrifugal C. Demineralized water storage tank -
- 1. Capacity: 340,000 gallons
- 2. Design pressure: Atmospheric -
- D. Condensate storage tank l 1. Capacity
- 300,000 gallons
- 2. Design pressure: Atmospheric -
E. Secondary steam relief valves
, 1. Five safety valves per main steam line .
j 2. One power-operated pressure control valve per main steam line 3.2.6 Suonort Systems and Interfaces A. Control Signals
- 1. A utomatic
'g motor driven ARV pumps IB is automatically actuated based on the.
following signals:
15 1/89 j
d
, , - , . - .,. . - - . . . , - - - .wan,,,,, r,,,,,a,m,w,,,,-n.,.,,,,,cy..w,.,,,.mr- , . , ~ , .-9
Niillstone 3 two of four low low water level in any one steam generator
[h
( -
safety injection signal (SIS) loss of power (LOP) containment depressurization actuation (CDA)
Slotor-driven pump 1 A is automatically actuated on the above signals when control is not in LOCAL. The turbine-driven pump is automatically actuated on LOP or two of four low-low water level in two of four steam generators.
- 2. Remote manual The AFW system can be actuated by remote manual means from the main control room and from the auxiliary shutdown panel.
B. .\fotive power
- 1. The AFW motor-driven pumps and motor operated valves are Class lE AC loads that can be supplied from the standby diesel generators as described in Section 3.7. Redundant loads are supplied from separate load groups.
- 2. The AFW turbine-driven pump is supplied with steam from three of four main steam lines C. Other
- 1. Lubrication, cooling, and ventilation are provided locally for the pumps, 3.2.7 Sittled 2 References q 1. Niillstone 3 Final Safety Analysis Report.
b 2. NUREG/CR-4142, "A Review of the hiillstone 3 Probabilistic Safety Study," Lawrence Livermore National Laboratory, April 1986.
- 3. NUREG-1152, "hlillstone 3 Risk Evaluation Report," USNRC, June 1986.
l l f'%.
t I b' 16 1/89 i
l l
i 1
1 m ,!!. !! !!
7 i
s a o !.!2
'v; . . .
i
&Z OE &Z i 0E t o4- l t A 10 4 - ! , ( 04-c{f' i;%
CE!
15 4 cq;l_, c{
1i4Sm tigq l
- C ' Ji C ] C; ) ;C, ) ei:er:er:
tk: tZ- tZ'- tk: i! @ %!
CEI oZl o$l Okt OZ: o$l ok,IDXW i l I I I i e
tZ: tZ: tZ- tZ: t2a tZ: tX* tZx s a i 08: 08: O3 0sa! eXx DXx l i I I I I i Ze Z:
2- 2 Ex Ze p Xa j m
-a (v,) .
a
- 40 L0 n 2 Z-
, j l I X=b -
i t2- tZ: tb i ! ; 5 i i a =
bl d! ! ]
I ;
E II 2: E: E= (I I I I o-I o-I: &Ia I l
-i IE X- Is I I=
t t t I &XI I5!!.
a IE!!.
a X= Ra
.t I -X t
4 1
I -X gm1 1_J 51
< 1
'v' M
"} ., p flyd 'i N
[7 1/89 g,. _ m. - -
Jam-..4AJEA -, L.4AB -aM. 4 .s .A 6u-= .s.k.- M iMAe. -.,_ -e m.,a- -we ..w.a -
a ._. ..-__..-ya,_-. - ,-.------------..y O
18 a 11 25 li as .li5 4 4 4 "
t k i j g C 1 tA , 10 4 , tA-, rc j i 0$! qt ! -
t_
!$ I! I$ 15 --
~
C l 3C'] l i >
C] 1 e 4g m ;
a I a
a tp .
tf- ,
tf= ge + i ge: .;
I i th ti: tI- tD tD tD tl'= tZ I
s
! O I cn i 059 OE! OE! ,5 DES DE! S
. - DEX CEN _
e
- o
- =
< I
< i 7 'T _ $
.== -
a $
g m . t o 3 y,
7,.
- 7. ., r.[,, .
]
u, e
t "a - . t ": f"al,. #.l :l -
y i
i !
~
ll i$W i s
.a If u . ,8 3
_ _ _ s l -- -
- i- 2
- 1r F 3
I,t ;L y e , 3 m -
. - !! OEI -
2 3l!.
3 .
I. "
-; .7,; : .7,,; -
l s_ -
I w .
$} :
- 3 x} ,
{ -
ll]i Q g. -
s =
e - ,
l 30
! l-18 1/89
Table 3.2-1. Millstone 3 Auxiliary Feedwater System Data Summary for Selected Components
' COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
AFW-35A MOV HSSAC MCC-184 480 ESFSE36 AC/B AFW-358 MOV IISSBD MCC-1 A4 480 ESFE36 AC/A AFW-35C MOV flSSBD MCC-1A4 480 SFE36 AC/A AFW-350 MOV HSSAC MCC-1 B4 480 ESFSE36 AC/B AFW-CST T ANK ..- CST AFW-DWST - TANK DWST AFW-P1A MDP AFWA BUS-34C 4160 CB2 AC/A AFW-P1B MDP AFWB BUS-34D 4160 CB1 AC/B AFW-P2 TDP. AFWID SG-1 A SG- HC SG-18 SG flC
- ' SG-1C SG HC-SG-1D SG- HC r
\
c
.\lillstone 3 3.3 E.\1ERGENCY CORE COOLING SYSTE.\1 (ECCS)
O 3.3.1 Svstem Function The ECCS is an integrated set 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 coolant injection function is performed during a relatively short-term period after LOCA initiation, followed by realignment to a recirculation mode of operation to maintain long term, post LOCA core cooling. Heat from the reactor core is transferred to the containment. The heat transfer path to the ultimate heat sink is completed by the containment cooling systems (see Section 3.5).
3.3.2 Svstem Definition The emergency coolant injection (ECI) function is performed by the following ECCS subsystems:
Passive cold leg accumulators Charging system (CVCS)
High pressure safety injection (HPSI) system Residual heat removal (RHR) system The charging function of the CVCS is described in Section 3.4 i
The HPSI system provides high pressure coolant injection capability. The RHR pumps perform the low pressure injection function. The Refueling Water Storage Tank (RWST) is the water source for both the high and low pressure injection systems.
Both systems inject coolant into all four RCS cold legs. The HPSI system can also inject into all four hot legs, while the RHR system can inject into two hot legs.
l After the injection phase is completed, recirculation (ECR) is performed by the h
U RHR pumps drawing suction from the containment sump and discharging into the RCS cold legs. Heat is transferred to the component cooling water system by the RHR heat exchangers. The RHR pumps can also deliver water to the suction of the HPSI and charging pumps during recirculation.
Long term containment and core decay heat removal is performed by the containment recirculation system (see Sec' ion 3.5).
Simplified drawings of the hid pressure safety injection system are shown in Figures 3.31 and 3.3 2. The low pt,ssure safety injection (RHR) 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 selec:ed ECCS components is presented in Table 3.3-1, 3.3.3 Svstem Ooeration During normal operation, the ECCS is in standby. Following a LOCA, the four cold leg injection accumulators (one for each loop) supply borated water to the RCS as soon a. RCS pressure drops below accumulator pressure (approximately 650 psig). A safety injection signal (SIS) automatically starts the charging pumps, the safety injection pumps, and the RHR pumps, and aligns the charging pumps for injection. The charging pumps inject through the boron injection tank (BIT)into the four RCS cold legs. The HPSI and RHR pumps can inject into either the cold legs or the hot legs. All pumps are aligned to take suction on the RWST.
For small breaks, operator action can be taken to augment the RCS i depressurization by utilizing the secondary steam dump capability and the auxiliary i
feedwater (AFW) system (i.e., depressurization due to rapid heat transfer from the RCS).
! When the RWST water level drops to a prescribed low level setpoint, the RHR A
pumps are realigned to draw a suction from the containment sump and deliver water to the RCS. If depressurization of the RCS proceeds slowly, high pressure recirculation can be 20 1/89
Millstone 3 accomplished by manually aligning the discharge of the RHR pumps to the suction of the charging and HPSI pumps.
(~~N
\ ) 3.3.4 System Success Criteria LOCA mitigation requires that both the emergency coolant injection and emergency coolant recirculation functions be accomplished. The ECl success criteria for LOCAs are not clear in the Millstone 3 FS AR, however, the following is noted:
A .375 inch diameter break is the maximum break size for which the normal makeup system can maintain the pressurizer level and the normal reactor coolant system pressure of 2250 psia. For a break of this size, one charging pump is adequate to sustain pressure level at an RCS pressure of 2250 psia. This break results in a loss of approximately 17.5 lb/sec (127 gpm at 130 F and 2250 psia)
(Ref.1).
For a small break LOCA (less than 1.0 ft2) the high head portion of the ECCS, together with the accumulators, provide sufficient core Gooding (Ref.1).
For a large break LOCA (greater than 1.0 ft2 ) in which the break is in one injection path, three accumulators, one charging pump, one safety injection pump, and one residual heat removal pump provide sufficient core flooding (Ref. 2).
3,3,5 Comoonent Information A. High pressure safety injection pumps l A and IB
- 1. Rated flow: 425 gpm @ 2850 ft head (1235 psid)
O 2. Rated capacity: 1007o
(") 3. Discharge pressure at shutoff head: 4037 ft head (1750 psig)
- 4. Type: horizontal centrifugal B . Low pressure safety injection (RHR) pumps I A and 1B
- 1. Rated flow: 4000 gpm @ 350 ft. head (152 psid)
- 2. Rated capacity: 1009c
- 3. Type: vertical centrifugal C. Cold leg injection accumulators (4)
- 1. Accumulator volume: 1350 ft3
- 2. Minimum water volume: 950 ft3 3, Normal operating pressure: 650 psig
- 4. Nominal botic acid concentration
- 2000 ppm D. Refueling water storage tank
!. Capacity: 1,166,000 gallons
- 2. Design pressure: Atmospheric
- l. Design duty: 35.27 x 106 Bru/hr l 2. Type: Vertical, shell and U-tube O)
D' 21 1/89
.\li!ktone 3 3.3,6 Suonort Systems and Interfaces
/^N V)
( A. Control signals
- 1. Automatic The ECCS injection subsystems are automatically actuated by a safety injection signal (SIS). Conditions initiating an SIS trip are:
- a. Low pressurizer pressure
- b. Low steam line pressure
- c. liigh containment pressure
- d. Manualactuation The SIS automatically initiates the following actions:
starts the diesel generators starts the charging, SI, and RHR pumps aligns the charging pumps for injection trips the main feedwater pumps Switchover to the recirculation mode occurs automatically on low low level in the RWST.
- 2. Remca manual An SIS signal can be initiated by remote manual means from the main control room. The transition from the injection to the recirculation phase of ECCS operation can be initiated by remote manual means. Manual action is 7_, required to realign the charging and safety injection pumps for recirculation, k '
- 3. Motive Power l . lne ECCS motor-driven aumps and motor-operated valves are Class 1E AC loads that can be suppliec. from the standby diesel generators as described in Section 3.7.
C. Other
- 1. Each HPSI and charging pump is cooled by the Service Water system (see Section 3.8).
- 2. The RHR pumps and heat exchangers are cooled by the Component Cooling Water system.
- 3. Lubrication and ventilation are provided locally for the HPSI, RHR, and charging pumps and motors.
3.3.7 Section 3.3 References
- 1. Millstone 3 Nuclear Station FS AR, Section 6.3.
- 2. Reference Safety Analysis Report 3S, Westinghouse Nuclear Energy Systems, Section 6.3.3.2.
A 5
(/
22 1/89 l
l
l O O Q O
.n i 2; s a:; s sa s3 is is 2: : a:a a: 2: a: a:
4 o -4
-4 o o til til t21 t21 tzi t2i t21t2st$1t2st$1t2st$!t2it$1t21:
l X! Xi Xi I f.. Xi'Ej' XI Xi XI Xi-I 3 e
3 i i !*i ![i 1 s 3 :V "D l D E C.
i2! t2l t2! i ! i2! t! t2! i ! i2! t ! t2!. t2l 133 'E 3 es: . 2 r1!=2 3 3 rE: o 1, ?. . i s.
- g.e$e-13 g -
!- 1, 3 s ,
,=
. .E o
t Oil OK!a OXIa Oll-a-J-
9 a 1 e
- m ?:3
' a g :s 8 a a $
Xi Xi 3
- c i2l . . i21- I s i- 1- .a c' E' h c
l- 3 e h D-c-
=
a y e --
-- - 3 :.
a o -2 2 2' I
s a
2 4 :
I d>
ORIa T %l *
-lgg. .OXia- :5 g-V5
, gp gg W
, 225 see z OXI j- ~tgi C
I,i-am3 t
ISE"
, f!
31 a
$ -b 23- 1/89- ;
I 4
a.. .-..~--~-m.e
, r u U . .~, , . . . .. , *..,.,.3L.-mm,,...mrc, -.%. .-m.--,,_, mm.,,,w.,w.wv,-,- ,,y,..,-, y,,y,,.,.,-,-%,, ,,~
x, . 9 e e =
h -
n
==
p a
x:
ca se 2;3 gg gg I
iki tk! tkl tki tXI tZjtZit$lthit$1tZE tk,itII tE,ltZ]tZj .!.
_ t t =
~ ., 3!! ,-, age a ano o i 3 E,,S 33 2,i 35 ZE 3;5 v "
2 .
I g g li fi'- X{ Xi -
i ! g c g 3 5
,3 I g-
- e a.
tZi tZitZitkitZitIltZ1tkitZitEltZitZi t t t t b
a f!
I i
fi!!EI!!El I 55! fl !!! {i I
{i f*
I 1. E j
OII OIS ! OII i an . e
- ~3* S h ,o
- l y;'
, m. -
tg
-,, c, <3 amb
< >l 3
=
0 U iZ-re] 9
- l --
3
~
D D. $ i i^ (_y' i- x.
W c E
b.
U, e eli i O
,3
.I } M i
..ori' ,
$$* Y t ge g'g '
a e E
D E- 3 N
- q
- t - "
g
- g!!
5 ehe b, l l $
ll e
o
- b- c o
og'ai
_ a _ s as
_ g , _
a a o i-
- =
i i .e
(
\
- =
2.lt p,
7
- l. 5e.
24 )
i i !. !, x ,. , 9 ., ;,
l Es !! $8 is, !! 1g tki tki tki .tkl e
l ti fl tl . t l.
- tZi ,3, tXI 3, tZi tXl tXE , tXd ,3, e q s2 a3, !
i I I i
1=i Xs y Xi v Xe Xs Xr v l XI -
ogp
$ ksE E.
3 thi t$i t$1 t$1 t$i t$i $
l- it: tis 2 01:1 tXi :t: s tXi !s: t{,:a:
i t}ei it:3t{r!!s!
g i-tf2i g
.{
o1:1 ;
l i
5 m
l --
T ,
u)
- tw X X -ru T T a 4 Ih !I O
'us -irs I!
3 I
fli i
q8i 'Il,!$
sE j-8
=
s
, i E. <
- e wn
,d w, n okri.
IS E ; e 2
x o e o] [d - ,
5 a
~
l { g g-i :l i . i .i tv-5 p=
[ s3 3y lig a
l
~f 5 ale if l al!
l1 ! - "
l g-
'jh =
3 j$ X IE
\
25= -1/g9
.a.e -M--md,.A 4 a awaa dde a - a . mM.-. a.ma.4.Mewe- h4na4.-ans,-4me- 4.a .. mJ Aes-a m ma ei. m2A.4.;_ v ---M. J EMJo == <:s ed4W 4.M du 4-4d.d4.4*hMef1-hA+E--WJa_-sg. 4 4wa ,Jh---w.. -.L-_; 3,.J I
! l 1 l h
i
)
i l
$ i 0 2 x n 4: . .% .i i
ii at es: es: 2:: 2::
4 4 o i
( 4 l t21 t2! t21 t21 ,
1 li J C O
L
! +
= t2. . ) ... +21 3, tz! . t21 tZs .n tzi .p S
a l $ I! II ll I*
ll $3 l ' I' E-
- i D D D
! 1: : i l
=
Xs X: 1 D !
1 8.
2JU
=
e gs o
,z, i (*5 , " , , f,i
.z.
l OI] l -
llI - t{j8'Efja,j- {fl a,j ff) a,j p
q i 8 l.
j e
u i n oil !
l- - 2 R
.. I- _.
t i 8 8 I I tZ= Z E f'n E t u a as l l.
i a M
f 23 a a
, - E i D : +-
ifs e "ils o 't 5 e
' Ei
$f I -. N5 I -. .$ $
wi I
a - -.
w {l5 g-e o,
. I-g z
I . =
o a' n- a
{ i
$ .. m r-- 4 >4 nyi ->o -
o o- g i 01L1 ~- s lo =
ge-Oli ti 's x- c- : . OI) q_
a=-
i
'i f7i -!
y t*'
4 j;g e 2 -
e '
3' c, -
eH 1 - 25 i- :!
l' 3 a
26 1/S9
Table 3.3-1. Millstone 3 Emergency Core Cooling System Data Summary ;
for Selected Components
, COMPONENT ID ' C O M P. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. ..
TYPE LOCATION LOAD GRP. -!
HWST TANK. HWST SI-8802A MOV SlHA MCC-1 A4 480 ESFE36 AC/A SI-88028 MOV S!HB MCC-183 480 ESFN36 AC/B SI-8806 MOV ESFNE MCC-183 480 ESF N36 AC/B SI-8821 A MOV SlHA MCC-1A4 480 ESFE36 AC/A ;
SI-8821 A . MOV StHA MCC-1 A4 - 480 ESFE36 AC/A .
SI-88210 MOV SlHB MCC-183 480 ESFN36 AC/B .
SI-88218 MOV SlHB MCC-183 480 ESF N36 AC/B SI-8835 ' MOV SIHA MCC-1 A4 480 ESFE36 AC/A .
SI-8923A - MOV SlHA MCC-1 A4 480 ESFE36 AC/A i SI-89238 -- MOV StHB . MCC-183 480 ESE N36 AC/A i U SI-P1 A MDP SlHA - BUS-34C 4160 AC/A SI-P1B S!HB BUS-34D 4160 CBI - AC/B lbDP 1 4
d i
i ,
l '$
1
.\lillstone 3 3.4 CilARGING SYSTEM C
r 3.4.1 Svstem Function
\
The charging system is part of the Chemical and Volume Control System i C YCS ). The CVCS is responsible for maintaining the proper water inventory in the Reactor Coolant System and maintaining water punty and the proper concentration of neutron absorbing and corrosion inhibiting chemicals in the reactor coolant. The makeup function of the CVCS is assumed to be required to maintain the plant in a long term t8 hours) hot shutdown condition. The charging pumps also operate as part of the ECCS in the event of a LOCA.
3.4.2 System Definition The CVCS provides a means for injection of control poison in the form of boric acid solution, chemical additions for corrosion control, and reactor coolant cleanup and degasification. This system also maintains the required water inventory in the RCS.
reprocesses water that is letdown from the RCS, provides seal water injection to the reactor coolant pump seals, and performs an emergency core cooling function.
The CVCS consists of several subsystems: the charging, letdown, and seal water system, the reactor coolan purification and chemistry control system, the reactor makeup control system, and the boron thermal regeneration system. The functions of the CVCS are perfermed by the following components: (a) the charging pumps, (b) borie acid transfer pumps, (c) volume control tank, (d) boric acid tanks, and (e) various heat exchangers and demineralizers.
Simplified drawings of the CVCS, focusing on the charging portion of the system, are shown in Figures 3.41 and 3.4 2. A summary of data on selected charging system components is presented in Table 3.41.
3.4.3 System Occration
( Dunng normal plant operation, one charging pump is rtmning with its suction aligned to the Volume Control Tank (VCT). The letdown flow from a RCS cold leg is cooled in the shell side of the regenerative heat exchanger, then directed to the VCT. The reactor makeup control system maintains the desired inventory in the VCT. The bulk of the charging flow is pumped back to the RCS through the tube side of the regenerative heat exchanger via two charging lines. Portions of the charging flow are directed to the reactor coolant pumps through a seal water injection filter, and to pressurizer spray.
Two of the three centrifugal charging pumps also provide high head injection as part of the ECCS (see Section 3.3). During o LOCA the CVCS is isolated except for the charging pumps and the piping in the safety injection path. The pumps take suction on the Refueling Water Storage Tank (RWST) and inject via the Boron Injection Tank mtu all four cold legs.
3.4.4 System Success Criteria For post transient makeup to the RCS the following charging system success criteria are assumed:
A long term water source must be availab.e to the charging pumps. Available water sources include (insert actual sources)
One of three charging pumps is available.
A makeup path to the RCS is available.
s "J 28 1/89
.\lillstone 3 3.4.5 Comooncat Information rO)
(./
A. Centrifugal charging pumps 3A,3B,3C
- 1. Rated flow: 150 @ 5800 ft head (2514 psid)
- 2. Rated capacity: 1(XFc for RCS makeup
- 3. Type: centrifugal 3,4.6 Snooort %tems and Interfaces A. Control Sicnals
- 1. Automatic
- a. The charging pumps are automatically actuated by a safety injection signal (SIS).
- b. The charging - ips are automatically aligned for safety injection by a SIS.
- 2. Remote hianual The charging pumps can be actuated by remote manual means from the control room.
B. N1otive Power
- 1. The centrifugal charging pumps and motor operated valves of the CVCS are Class IE AC loads that can be supplied from the standby diesel generators as described in Section 3.7.
C. Other f 1. The centrifugal charging pumps are cooled by the Service Water System
( (see Section 3.8).
- 2. Pump lubrication and ventilation are provided locally.
~.
29 1/89
,, . " :m.
c
_o
,v" ': ,, <
/ n -
r(L % ._ x-s_
g mx, s
e ro 4 m_ X
,s a
._ x -
~a _ et o
% Q"-- .s A ' _9 t
f o e b
C m
, ur )
e C T se
,Ca U T
,a
,rf m
X
- m o o t
e s
. t e
. y
<- .s S y
- I^ X- m g
n g W s i
,. gg R . g gg sa
. .C
. L r nu ev
.F
. C h
a J
_ - gC. .%mI 3 e
~ m n
- r e o W,,, W,,,,c-e
( % C" l
t l
s i
M O
7' ~ .
4
- 1 A X A 3
^ 8 s
er s #e ~
6 u
w_s g. " M g e s3 C i c ug F M a ts ng s
X' -
u sa p
o, x .
9 ,uc w.,
eA ,
m S, s e-P n 0L 7
o s
m sM S
A 2,
M E
F7
- 5 f> O7
'W T$
R EK 4W 4 v, - - -
A A T
N S =
M Vsf e B S Mde WI n CJ K NI C 4l O l
d2 , s vs s
,, ~~ EA I V C 9f Cf tJ GH 8 a
fjM RG 85D L
fUL FIS r nB n
i M
t S
J R
F ft A
& I F
)/, e p I F
,.( Q Q~, A
,sM m ,< EY
,S Y
e' Qmo
!;i!:..! , ; ' i ;; !!tI}
_ , I i 1l 1l i
!I?;[iE I; :f: ! !{ '{i! ,f 'I)-
- o. osa .. D-Suu c e _
' u ,om e. C" 4 . f, g
c
.e c
. 3 c.. -
. y .
W. '
.L ml.
)
_ ow., d.: s s
x s. n c i o 0 s it 1
. C v
C a
c u=
c 0 c.
o
- .=' 1 c L t
_ . . i n e
,. n o
.c ,
p m
. 0 c a. o 5
ee-s
.- . C s-i, s g
. i n
g 4 . _
w
" r s=
8 88=
il . M
.M da I
h o
2 I
S g
I
~
I 4 $m.
- c *- ;
e a
.a i
t m
e
~
a
- - sy c ,= S mu'""
I
~
I I
f u* =
c c
i g
n
_ ;, ig Mv
_g - p .l c
r a
i P. r.e - h
. .- C f"
3 e
.a .- n o
. + .
.m
.- t s
c m ,. .u a- l s
y a s
c c l i
- c. e, n
a, s
. M su .
t 2
4 l I 3 o
- a. e
- Q ,. .
=
%= r QH_c.
u c
",,. ~
g
. c.
i l F 3
L'- .
i o .
, G .,. l a-o r
8.
5 Ptr
. oN . =
+
. i a ,.
Ms c i Oe p.
?
s Ts
- w o s
a .
A. + -
. +
E L s .
, $ =
. fAsA YW s .
. AI . n C sE c v a" Ce p G s
- ,as
, es sI f
GM REK I
- c. cM g
L K .ne a. m .D i
td fI E S
.f -
i GE t
d
,= mA g=
S E J
E 5
4 i g
+
e .
a
=
u u=
, s e
s h .%$
- ; i , i . i i .
\ J Table 3.4-1. Millstone 3 Charging System Data Summary for Selected Components COMPONENT ID COMP. LOCATION . POWER SOURCE VOLTAGE POWER SOURCE EMERG.
TYPE LOC ATION LOAD GFIP.
Cit-1120 . MOV BASAB MCC-3A1 480 ABS AC/A CH-112E MOV BASAB MCC-381 480 AB6 AC/B CH-8438A MOV CHA MCC-3A1 480 ABS AC/A 1 CH-84388 MOV CilB , MCC-381 480 AB6 AC/B CH-8438C MOV CHA 1ACC-3A1 480 ABS AC/A CH-8468A MOV CHA MCC-3A1 480 ABS AC/A CH-84698 MOV CitB MCC-381 480 AB6 AC/B CH-P3A MDP CHA BUS-34C 4160 CB2 AC/A CH-P3B MDP, CHB BUS-34D 4160 CB1- ~ ' AC/B SI-8801 A MOV BASAB MCC-3A1 480 ABS AC/A SI-8801B MOV BASAB- MCC-381 480 l AB6 AC/B g
i c
i L.
Millstone 3 3,5 CONTAINMENT llEAT RE.MOVAL SYSTEM 3.5.1 Svstem Function The contamment heat removal system is an integrated set of subsystems that provide the functions of containment heat removal and containment pressure control' following a loss of coolant accident. In conjunction with the ECCS, the containment heat -
removal system completes the post LOCA heat transfer path from the reactor core to the ultimat; heat sink.
3.5.2 dvstem Definition The contatnmen: heat removal system consists of two separate subsystems:
Quench Spray System (QSS)
Containment Recirculation System (CRS)
The QSS consists of two parallel redundant subsystems, each feeding one 360 degree spray header. Each QSS subsystem consists of one horizontal centrifugal pump drawing suction from the Refueling Water Storage Tank (RWST). The CRS consists of two parallel redundant subsystems, each feeding two 360 degree spray headers. Each CRS subsystem consists of two vertical centrifugal pumps and two heat exchangers, which transfer heat to the service water system, The four CRS pumps take suction from a common containment sump. In each subsystem the two spray headers are shared between the two pumps.
Simplified drawings of the Containment Recirculation System are shown in Figures 3.5-1 and 3.5 2. The interface between the CRS heat exchanger and the service water system is shown on the SW system drawings in'Section 3.8. The interfaces are through motor operated valves CRS 54A through CRS 54D, and CRS 57A through CRS-
, 57D. A summary of data on selected contairment heat removal system components is-presented in Table 3.5 1.
3.3.3 System Ooeration During normal operation, the QSS and CRS are in standby. Fenlowing a LOCA the QSS is activated imrnediately upon receipt of a Containment Depressurization Actuation (CDA) signal. This signal is initiated when containment pressure reaches 24.7 psia. Each QSS pump d~s water independently from the RWST, Sodium hydroxide is added to the water by direct gravity feed from the chemical addition tank, if both pumps operate the system fill time (time for water to reach the spray headers)is 33 seconds. If one pump operates system fill time is 64 seconds (Ref.1).
The CRS pumps are started approximately 670 seconds after the CDA synalc The four CRS pumps take suctica from a common containment sump and pump water through the CRS heat exchanget to the four s? ray headers,-~At the heat exchangers CRS water flows through the shell where it is coo,ed by service water flowing in the tubes.
Each CRS spray header is fed by two risers, each riser running from one of the two CRS heat exchangers in each subsystem.
Heat is transferred from the containment: atmosphere to the quench and containment recirculation system spray water. Heat is transferred from the containment to the service water system through the CRS heat exchangers.
3.5,4 System Success Criteria One of two pumps must operate for QSS success. It is stated in Ref, I (Table 6.2.61) that two of four pumps must operate for CRS success. However, Section 6.3.2 of Pef. I states one pump and one heat exchanger must operate for CRS success. It could not-be determined whether both the QSS and CRS must operate for the containment heat O, removal function to be successful following a large LOCA.
33 1/89
l l
l Millstone 3
, 3.5.5 Comoonent Information J
l A, Containment Recirculation Pumps I A,1B,1C and ID j 1. Rated flow: 3950 gpm @ 342 ft head (148 psid)
- 2. Rated capacity:.1007c
- 3. Type: verticalcentrifugal l B. Containment Recirculation Heat Exchangers (4)
- 1. Design duty: 3J/9 x 106 Btu /hr j 2. Type: shell and tube
! C. Quench Spray Pumps (2)
- 1. Rated flow: 4000 gpm @ 291 ft. head (126 psid)
- 2. Rated capacity: 100?c i 3. Type: honzontalcentrifugal
- 3.5.6 - Suonort Systems and Interfaces .
4
- A. Contro! Signals
- 1. Automatic The QSS pumps are automatically actuated by a CDA signal. The CRS pumps are automatically actuated approximately 670 seconds after a CDA .
, signal.
1
- 2. Remote manual
- control room.
[ B. Motive Power
loads that can be suppliect from the standby diesel generators, as described '
i in Section 3.7. Redundant loads are supplied from separate load groups.
l- C. Cooling Water
! 1. The CRS heat exchangers are cooled by the Service Water System-(see
- Section 3.8).
i i D. Other ~
- 1. Lubrication, ventilation, and pump cooling are provided locally for th'e QSS ,
and CRS pumpsi 3.5.7 Section 3.5 References -
- 1. Millstone Nuclear Power Station, Unit No.' 3 Final-Safety Analysis Report, Northeast Utilities Service Co., Hartford Ct..
[
l l
l 34~ 1/89 l
l- - . . _ . ._ _ . _ . - . - _ . _ . - - - . . _ . _ _ _ . . . . _ . . , _ , , _ . _ .
,a e \
(,
w ) 1 ,
s < I I s
< e s}e l k <
k i
< k NO
'i
< w
~< <
k k k N k
- * [ E
- s a
_ C E i Ci ECEi
. .a C&if t2* t2- t2- t2:
E e
3 A 3
M s!! d!
+ .!
g u
4 C
c 0
. e s (7
i <
I i i
i .5
'w] s e
" a a $
w"2 w,
- e w4 U C 0 0 o "
O c
O E
3 E
I 3 3 i R R 3 a a
Tg_ 5 m2
'r , r, 's~ ='s a
!j s,
o i ~ 'd 8
" J
'6 i 'd L ,1 "
g e
%] i yFua 3
"2y!gF t ea" s
p
=
i 5
i 1
e :
R A
. o u
( <
E $ 5 h b h
/,
/ ')
\ .
\,._ '
35 1/89
. _ . _ _ . ._ _ - . _ _ _ _ _ . . . _ . _ . . _ . . _ _ _ . . - _ . _ . . . . _ . _ . = _ _ _ . . . _ _ - . . _
l i
I i
l l
n
< e e e .. I1 I W e k e s' !
Ic k
e p r.
eu I e - ,k -
..,A
_ l.
k s .E e a
s s e m
= -
N - - . ,
- U
_ o.
a
?o i2* tl- il- fle 8 c.
E o
g - - - - - o i 3 3 l ~ m
. ofE
-.. .o f.. E , .5, OE! M t* OE!v OE!e ta- ! OE! $
u E
o
- ' 3>
m e
. . .9
. a g a
- n
- a. i- l 3U w
v .g-g -'
'a v u .:
's 's u
- U B B -6 E
- - - g o
i ! : : : E
- : := : .5
= n
~1 -
3- y -
3.- - -
5 A
- '5- 3 3- o
,y %. 'r-
,! r, 'm 5 -- r n 3- '
! 0- 1
! J 3 i o L _;'_,3 g
LJ -
c.a t_a .
Q.;
- e. . e. . e. . .,
- E 1 A A; l~ !_ W 9
n 1 ..
.. . o , o I
k_.! _h h h -. ,h
- u. -
M 3
1 36 1/89 J
. . - - . . - , . . _ _ . ., . . . . . . , . . . , . , . . . . . . . . . . . . _ _ , . . . . . . . _ _ _ . _ . . _ _ _ _ . . . . _ . . , . . . . _ _ _ _ . . . . _ . . , - . . - . . ~ . . . _
O b t
d Table 3.5-1. Millstone 3 Containment Heat Removal System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VO LTA G E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
CRS-20A MOV RSSAC MCC-1 A4 480 ESFE36' AC/#,
CRS-208 MOV RSSBD MCC-184 480 ESFSE36 AC/B CRS-20C MOV. IISSAC MCC-1 A4 480 ESFE3G AC/A CllS-200 MOV flSSBD MCC-184 480 ESFSE3G ACJB CflS-23A MOV HSSAC MCC-1 A4 480 ESFE36 AC/A
! CilS-238 MOV RSSBD MCC-184 .480 ESFSE36 AC/B 4 CHS-23C MOV RSSAC MCC-1 A4 480 ESFE36 AC/A CllS-23D MOV RSSBD MCC-184 480 ESFSE36 AC/B CRS-8837A MOV ESFE MCC-1A4 480 ESFE3G AC/A CflS-88378 MOV ESFSE MCC-184 480 ESFSE36 AC/B ,
CRS-8838A MOV ESFE MCC-1 A4 480 ESFE36 AC/A "!
U CRS-88388 MOV ESFSE MCC-1B4 480 ESFSE36 AC/B CRS-E1 A HX RSSAC '
} CRS-E1B- HX: RSSBD CRS-E1C HX RSSAC I CflS-E1 D HX. flSSBD CflS-P1A. MDP RSSAC BUS-34C 4160 CB2 AC/A CRS-P1B MDP RSSBD BUS-34D 4160 CB1 AC/B
- CHS-PIC . MDP IlSSAC BUS-34D 4160 CB2 AC/A CRS-P1 D MDP RSSBD BUS-34D 4160 CB1 i
AC/B SW-54A MOV ESFE MCC-1 A4 480 ESFE36 AC/A SW-548 MOV ESFSE MCC-104 480 ESFSE3G AC/B '
SW-54C MOV ESFE MCC-1 A4 480 ESFE36 AC/A g SW-54D MOV ESFSE MCC-184 480 ESFSE36 AC/B
< C SW-57A ' MOV. RSSAC MCC-1 A4 480 ESFE3G ACIA i SW-57B MOV RSSBD MCC-184 480 ESFSE3G ACIB SW-57C MOV HSSAC MCC-1 A4 480 ESFE3G AC/A
s Table 3.5-1.. . Millstone 3 Containment Heat Removal System Data Summary for Selected Components (Continued)
COMPONENT ID COMP. LOCATION POWER SOURCE VO LTA G E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
SW-57D MOV HSSBD MCC-184 480 ESFSE36 AC/B i
i
- w I @
- i I
i l 't
.( '
4 ,
i
~
l '.
1 --
h s o E
i' i' ,
1 i
i
-i
- 1. - . . - . ._ _. -
, , . _ _ . _ _ . _= _
Millstone 3 3,6 INSTRUMENTATION AND LONTROL (I &- C) SYSTEMS 3,6.I Snigm Function The in, rumentation and control systems consist of the Reactor Protection System (RIS), the Engineered Safety Features Actuation System (ESFAS), and systems ,
for the display of plant information to the operators. The RPS and ESFAS monitor the I reactor plant, an' +
the op<.rator to take corrective action before specified limits are exceeded. The R. t ' ir,itiate an automatic reactor trip (scram) to rapidly shutdown the reactor when plant iditions exceed one or more specified limits. The ESFAS will automatically actuate selected safety systems based on the specific limits or combinations of limits that are exceeded. A remote shutdown capability is provided to ensure that the reactor can be placed in a safe condition in the event that the main control room must be evacuated.
i 3,6,2 System - Dermition l
The RPS includes sensor and transmitter units, logic units, and output tnp relays that operate reactor trip circuit breakers to cause a reactor scram. The ESFAS includes independent sensor and transmitter units, logic units and relays that interface with-the control circuits for the many different sets of components that can be actuated by the-ESFAS. Operator instrumentation display systems consist of display pane 4 in the control-room that are powered by the 120 VAC electric power system (see Secuon 3.7). The remote - hutdown capability is provided by the auxiliary. shutdown- 3anel-(ASP) in conjunction with normal automatic systems and local controls outside tie main control room.
3,6,3 System Goeration l
- A. RPS
\ The Westinghouse RPS (or Reactor Trip System, RTS) has two to four redundant input instrument channels for each sensed parameter and two output actuation trains (A and B). The A and B logic trains independently generate a reactor trip command when prescribed parameters are outside the safe operating range. Either RPS train is capable of opening a separate and independent reactor trip circuit breaker to cause a scram. The manual scram A and B civaits -
bypass the RPS logic trains and send a reactor trip command directly to shunt tnp circuitry in the recctor trip circuit breakers.-
B. ESFAS The ESFAS has three or four input instrument channels for each sensed, pa ameter, and two catput actuation trains (A and B). In general, each train controls equipment poviered from different Class 1E AC electrical buses. An individual component usually receives an actuation' signal from only one:
ESFAS train. - The ESF AS generates the following signals: (a) reactor trip, i
provided one has not : tready been generated by the RPS,(b) safety injection signal (SIS), (c) conta nment isolation, (d) main steam line isolation, (e) main .-
feedwater line isolatic n, (O emergency diesel start, (g) control room isolation, and (h) containment 6 pressurization actuation (CDA) signal. The control room -
operators can manually trip the various ESFAS ~ logic subsystems, Details-regarding ESFAS actuation ;ogic are included in the system description for.the actuated system.
39 1/89
l i-
) Millstone 3 1
C. Remote Shutdown The remote shutdown system provides redundant safety grade capability to achieve and maintain a safe shutdow n condition from location (s) remote from the control room. The controls available on the ASP provide the capabilities of >
achieving and maintaining a safe shutdown when the main control room is in accessible. the controls necessary for immediate operator action to establish a stable plant condition anc r.vailable m the ASP or the adjacent emergency switchgear rooms. The controls prov.ce a means of sustaining the capability .
for boration, letdown, residual heat removal, natural circulation, continuing e
- reactor coolant pump seal injection and for thermal barrier cooling water flow, '
i and depressurization.
Panels and associated equipment used in the event of control room evacuation are located at elevation 4 feet 6 inches in the control building. Also at this location are the emergency switchgear for each train, along with two tr:insfer ;
switch panels (TSP) and the ASP, Safety related equipment with controls 1
located on the TSP and ASP are listed in Table 3.61. Most controls located at their respective emergency switchgear. Two rooms arepumps have the provided to separate the redundant emergency switchgear and the transfer switch panels. The ASP panel is located in the purple switchgear room (Train B) and the two trains (A and B) of the ASP r e separated by a non. train sanel.
All controls and instrumentation tequired for the reactor hot and cold sht idown from ASP are decoupled from those normally used in the main control ' >om in 4
order to ensure that the control room evacuation event does not deunt the-operation of equipment and controls necessary for remote shutdown in case of failure of equipment in the main control room.
[ Controls located outside the control room are provided with REMOTE / LOCAL selector switches. An annunciator is alarmed in the main control room and the indicator lights in the main control room are turned off when LOCAL CONTROL is selected. There are no cases in which transfer from the main control room to the auxiliary shutdown panel requires a jumper or other special equipment. The design is such that transfer of equipment frcm the main control room to the attemate shutdown area will not change the status of the equipment.
! Loss of offsite power will not negate f.hutdown capability from the remote shutdown area. The design is such that access to the remote shutdown stations at the ASP, the TSPs and the 4 kV switchgear requires keys for operation of equipment. Access to these areas are under administrative control.
3.6,4 Sntem Succen Criteria A. RPS The RPS uses hindrance logic (normal s 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 fail safe failure mode).
A reactor scram will occur upon loss of control power to the RPS. A reactor scram usually is implemented by the scram circuit breakers which must open in response to a scram signal. Typically, there are two series scram circuit-
.\
40- 1/89-i'
-..i.,_,-.ia,___..,L... e , _.,L,, . . - , , , . - , . _~.mm,., .. -- - . - _ , , , , - - - - ,
l l
Millstone 3 breakers in the power path to the scram rods. In this case,' one of two circuit _ ;
l breakers must open. Details of the scram system for Millstone 3 have not been determined.
B. ESFAS A single component usually receives a signal from only one ESFAS output train. ESF AS Trains A and il must be available in order to aut,matically actuate 1 their respective components. ESFAS typically uses hindrance input logic
- (rormal = 1, trip = 0) and transmission output logic (normal = 0, trip = 1). In this case, an input 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 fail. safe failure mode). -
Control power is needed for the ESFAS output channels to send an actuation i signal. Note that there may be some ESFAS actuation subsystems that utilize i hindrance output logic. For these subsystems, loss of control power will cause system or component actuation, as is the case with the RPS. Details of the ESFAS system for Millstone 3 have not been determined.
C. Manually Initiated Protective Actions .
When reasonable time is available, certain protective actions may be performed
. manually l operriting ,by plant individual personnel.
components usingThe control normal controlroom circuitry, operators are or operating capable of groups of components by manually tripping the RPS or an ESFAS subsystem.
The control room operators also may send qualified persons into the plant to.
operate components le ly or from some other remote control location (i.e., the remote shutdown pans. ar a motor control center).- To make these judgments, data on key plant parameters must be available to the operators.
()
3,6,5 Sunnort Systems and,Jnterfaces A. Control Power
- 1. RPS The RPS input instrument channels are powered from the 120 VAC vital buses (see Section 3,7). It is assumed that the RPS A and B output logic trains are powered from separate 125 VDC distribution panels.
- 2. ESFAS The ESFAS input instrument channels are powered from 120 VAC vital buses. It is assumed that the ESFAS A and B output logic trains are powered from separate 125 VDC distribution panels.
- 3. OperatorInstrumentation Operator instrumentation displays are powered from th'c 120 VAC .
Instrument buses. -
3,6.6 Section 3.6 References
- 1. Millstone 3 Final Safety Analysis Report, Section 7M.l.
l l
i i
r 41 -
1/89 s :-
-- - . , . _ _ , _;_,..,....,,.,,._..__,._,,..m,G.,.--._.,,w_,__._ ,,,._._,.._._.._,_..__._:_...
l Table 3.61. Millstone 3 Safety Related Equipment With Control Switches on ASP ASP Section 1 ASP Section 3 Decerlotion Electrical Train A flectrien! Train 11 h Auxiliary Feedwater Control 31A.31D 31B, 31C Yah es (Throttling) 32A,32D 32B,32C 4
36B,36C 36A 36B Auxiliary Feedwater 35B. 35C 35A,35D isolation Valves Auxiliary Feedwater Pump 23A 23B Altemate Suction Valve Auxil!ary Feedwater/DWST 61 A - 61B lsolation Vahe Auxillary Feedwater Motor Driven 62A 62B INmp Cross Connect Valve Turbine Driven Auxiliary Feedwater 31A 31B,31D Note 1 i: .
Pump Stes;n Supply Valves Main Steam Pressure Relieving 16A,18C 188,ISD 4
Valve isolation Valves I
Main Steam Pressure Relieving 748,74D 74A, 74C Valve Bypass Valves Pressurizer Power-Operated Relief 445A 456 Vahe Pressurizer ReliefIsolation Valve 8000B 8000A Pressurizer Auxiliary Spray Valve 8145 Nott. 2
. Reactor Vessel Head Vent 8095 A,8096A 8095B,80968 1 solation Valves Reactor Vessel to Excess 8098 Note 3 Letdown Valve Reactor Vessel to Pressurizer 442A 442B:
Relief Tank Letdown Valve "ressurizer Level Control Valves 459,460- Note 4 Letdown Orifice Isolation Valves 8149A,81498, Note 5 -
-8149C.
i l
- 42_ '1/89 I
,_-,--,..._,.,_c.,_,. , , . . , . . _ - - . . . , ~ . . . - . , _ _ - , _ , , . _ , . , . , - ~ , _ _ , _ , . -_. _..___,_,..-.,.,-.m...,-..,,.. _ . . _ , , . , - . - - ,
n I
l l
Table 3.61. Millstone 3 Safety Related Equipment With Control Switches on ASP (Continued)
ASP Section 1 ASP Section 3 Descriotion Flectrical Train A Electrical Train H h LetJown to CVT/CWS Diven Va!'e 112A Note 6 i Volume Control Tank Outlet 112B 112C l Isolation Yahe RWST to Charging Pump Suction 112D ll2E Vah e Charging System to RCS isolation 8147 8146 Vahe Boric Acid Gravity Feed Valve 8507A 8507B Charging lleader Isolation Valves 8438 A, 8438C 8438B Note 7 Charging Pump A Recirculation Valve 8111 A Note 8 Charging Pump B Recirculation Valve 8111B Note 8 Charging Pump C Recirculation Valve 8111C Note 8 f LPSI to Charging Pumps Suction 8468A 8468B
\ Vahe Charging fleader Flow Control Valve In0A 1908 Charging lleader Isolation Bypass 8116 Valve Note 9 Charging Pump to RCS isolation 8105 8106 Valve Charging Pump Miniflow Control 8511A 851IB Valve RilS lleat Exchanger Component 66A 66B Cooling Water Outlet Valve RilS to Cold Leg Isolation Valve 8809A 8809B RWST to RHR Pump Suetiu. 8812A 8812B Valve Safetyinjection Accumulator 8808A,8808 C 8808B,8808D Tank Isolation Valves 43 1/89
Table 3.61. Millstone 3 Safety Related Equipment With Control Switches on ASP (Continued)
ASP Section 1 ASP Section 3 Descriotion riectrical Train A Electrical Train il Notes
' Safety injection Accumulator SS75A 8875E Tank i Nitrogen Supply
... Safety injection Accumulator 88758 8875F Tank 2 Nitrogen Supply f Safetyinjection Accumulator SS75C 8875G Tank 3 Nitrogen Supply Safetyinjection Accumulator 8875D 887511 Tank 4 Nitrogen Supply Safety Injection Accumulator 943A 9438 Vent Control RHS Inlet isolation Valves 8701 A, 8701 C, 87018, 8702B, 8702A 8702C Charging Pump Cooling Pump 1A IB Pressurizer Heater Backup 4
1 A (Group A) IB (Group B)
Cold Shutdown Air Compressor 2A 2B a Air Conditioning Unit for S t. QS, lA IB and Ri!R Pump Area Slain Steam Line Safety injection Train A Train B Block / Reset Pressurizer Pressure Safety Train A Train D Injection Block / Reset l Sequencer LOP Reset Train A Train B l
RCS Cold Overpressure htitigating Train A Train B Arm / Block O
O
- 44 1/89
Table 3.61. Mllistone 3 Safety Related Equipment With Control Switches on ASP (Continued)
G NOTES:
- 1. There are three steam supply valves for the turbine driven auxiliary feed rater pump, one is Train A and two are Train B.
- 2. The pressurizer auxiliary spray valve is Train A only.
- 3. There is no Train B reactor vessel to excess letdown valve.
- 4. Valves 459 and 460 are in series; both are Train A letdown valves.
5, The three letdown orifice isolation valves are all Train A.
- 6. Valve i12A is Train A; Valve up stream of 112A is non train and can be controlled from the main board or gaseous waste panel.
- 7. Valve 843SC is is Train A only; it is the charging header cross connect valve.
- 8. Valves 8111 A, B, and C (charging pump recirculation valves) are all Train B, Valve 8110 is the Train A common recirculation valve and can be operated from the main control board; it is normally OPEN.
9 The charging header isolation by pass valve is Train A only, O
o u
45 1/S9
Niillstone 3 3,7 ELECTRIC POWER SYSTEM 3,7,1 Sstem Function The electne power system supplies power to vanous equipment and systems needed for nonnal operation and/or response to accidents. The onsite Class IR electric power system supports the operation of safety class systems and instrumentation needed to establish and maintain a safe shutdown plant condition followine an accident, when the nomial electne power sources are not available.
3.7.2 Ssstem Definition The onsite Class lE electric power system consists of two 4160 switchgear buses, designated 34C and 34D. There are two standby diesel generators connected to the buses. Diesel generator I A is connected to bus 34C, and diesel generator 1B is connected to bus 34D. There are also six 480 VAC switchgear buses, designated 32R,32S,32T, 32U,32Y, and 32W. Buses 32R,32S, and 32T are connected to 4160 bus 34C through transformers, and buses 32U,32V, and 32W are connected to 4160 bus 34D through transfonners. Various motor control centers receive their power from the 480 VAC buses.
En;ergency power for vital instruments, control, and emergency lighting is supplied by four 125 VDC station batteries. The batteries energize four DC buses. Four 120 VAC vital buses are connected to the DC buses through inveners, and to 480 VAC buses through transformers and rectifiers.
Simplified one line diagrams of the electric power system are shown in Figures 3.71 and 3.7 2. A summary of data on selected electric power system components is presented in Table 3.51. A' partial listing of electrical sources and loads is presented in Table 3.5 2.
3.7,3 System Operation Dunng normal operation, the Class lE electric power system is supplied from Q the unit generator through normal station service transfonner A, via normal 4i60 volt buses 34A and 34B. An alternate source of power is also from the 345 kV switchyard (offsite '
power), The emergency sources of AC power are the diesel generators, The transfer from the nonnal power source to the diesel generators is accomplished automatically by opening the normal source circuit breakers and then teenergizing the Class 1E portion of the electric power system from the diesel generators.
The DC power system nor.tially is supplied 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 are sized to supply the connected safety related loads for a rainimum of two hours without the use of the battery chargers.
The 120 VAC vital buses normally receive power from an inverter, The normal source of power to each inverter is from a separate 480 VAC bus through a rectifier. The alternate source of power to the inverter is a 125 VDC bus, When the inverter is out of service an alternate source of power to the 120 V-\C vital bus is f rom the 4S0 VAC system through transformers.
Redundant safeguards equipment such as motor driven pumps and motor operated valves are supplied by different VAC buses. For the purpose of discussion, this equipment has been grouped into " load groups". Load group "AC/A" contains components receiving electric power either directly or indirectly from 4160 bus 34C, Load group "AC/B" conta!ns components powered either directly or indirectly from 4160 bus 34D.
Components receiving DC power are assigned to load groups "DC/l" to "DC/4", based on the battery power source.
\
46 1/89
Millstone 3 3,7.4 Sutem Success Criteria Basic system suxess criteria for mitigating transients and loss of coolant V accidents are defined by front line systems, which then create demands on support sptems. Electric power system success criteria are defined as follows, without taking ere for cross ties that may exist between independent load grour .
Each Class lE DC load group is supplied initially from its respective battery ialso needed for diesel staning)
Each Class 1E AC load group is isolated from the non Class IE system and is supplied from its respective emergency pow er source (i.e. diesel generator)
Pow er distribution paths to essential loads are intact Power to the battery chargers is restored before the batteries are exhausted 3,7,5 Comoonent Information A. Standby diesel generators (2)
- 1. Maximum continuous rating: 4986 kW
- 2. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating: 5335 kW
- 3. Rated voltage: 4160 VAC
- 4. Manufacturer: Fairbanks Morse B. Batteries (2)
- 1. Rated voltage: 125 VDC
- 2. Type: 60 cell
- 3. Capacity: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with design loads p 3.7.6 Sunoort Systems and Interfaces A. Control Signals
- 1. Automatic The standby diesel generators are automatically staned based on:
Undervoltage on the normal bus Safety injection signal (SIS, see Section 3.3) l Containment depressurization actuation signal (CDA, see Section 3.5)
- 2. Remote manual The diesel generators can be started, and many distribution circuit breakers can be operated, from the main control room.
B. DieselGenerator Auxiliary Systems l 1. Diesel Cooling Water System Heat is transferred through a shell and tube heat exchanger to the Service Water System. Each diesel receives redundant cooling water supplies from the SW "A" and "B" headers (see Section 3.8).
- 2. Diesel Starting System Each diesel has an air staning system.
- 3. Diesel Fuel Oil Transfer and Storage System A 550 gallon " day tank" su ) plies the relatively shon term (approximately 90 minutes) fuel needs of eac 1 diesel. Each day tank is replenished from two underground 35,000 gallon storage tanks during engine operation.
- 4. Diesel Lubrication System Each diesel generator has its own lubrication system.
- 5. Combustion Air Intake and Exhaust System l This system supplies fresh air to the diesel intake, and directs the diesel i
d exhaust outside of the diesel building.
47 1/89
l 1
1
\
, Millstone 3 '
- 6. Diesel Room Ventilation System j This system maintains the environmental conditicns in the diesel room
! within limits for which the diesel generator ano switchgear have been
! qualified. This system may be needed for long term operation of the diesel
! generator.
i l
l l
l i
i i
l
@ 48 1/89 1
1 l
l l_ . _ _ _ _ . _ _ _ _ . . . _ _ _ . . _ . _ _ _ _ . . _ - . _ _ _ _ _ _ - - . _ _ _ . ----~~~~-:
~ .
p-% ^
g
\ \
%J %d
,o a.e .wu su w, n.n.
t
- I :::L~~ >.s ta .
mm.:I:
i F
tv .= ,
__, L_
w mu . .,. . _.~~~a****
~'
-*;*g/g y a ;
I
. . ie . =
(49ER.19R or. .a 4 e o,4 i
l .= L.=Tsm7 [_ ,3 ., - J ..
o e csuc
,....em Y t i i I i' Y <s+
i i I #
a II II e 9 I
en ac2 = 6, en wc - - se ucs ,. .- ra wm = v. m ';;,..w.w v. >.. r; ;x .-,
g I c sus m i I c eos us iI ..c a re. 1 I .= en w 1 I . .v e w _j 1 -*e.-
T_j i
a o o o o o o o e o e n
l .,x . ] l =x ..s ] I em .aa u w a i I wx w I I=c =*I I m ensI1wc==I[=rinJ I *m.aa n g s _] [ fib Eial D
c Figure 3.7-1. Millstone 3 4160 and 480 VAC Electric Power Distnbution System h
l I
f r
.owrc e .o m .e t ,
- . L_. -.1= - .
_ i t w see -
.__.g oes as esen.t pats se sa w .. . -- - m ** ** =St.emrt
5'
pem a= _ _ _ _ m.
4 g . g u aana l mo ia ,
is l %.
l in i l c === eus w. 1 J [ .e = 1
.i l com 3 -
l s.. l 4 ,,
y . c. _ .
<. _ Y_ . . _ ._ .
. , = _ ._. _ .= ,
is it is it i ,
. -. _L_ .
T.
,.-, T . - 1
.. = , . - = !
~~I= F'
, $ I *= *acM v' I I * **C ""$ N' II * * * * * " I L_ *='ac** *> I I
...I.
~~**w*
=1= .
- Ii - - ~ ~ ~ ~ I qr is- ir te 16 i
in it is is it is
. 4 E
1 1
1_ i k
l xi I g =x .as l 1 ew.ea ee =,2 w . .,s m.
j ., I, 4 =, , u .
c ,, ,, ,,
f
.h j
4' 4- !
' I i t arttav .
marr,o,w u wu ,
wits =, e,,, u, aa, a vs. [;
1
- 1 [n] 4 **'
2 [u]"c' "[v] 2 u *c
- 2 - [u] *
- f 1
[ ,, ,,
}
{ {,,7 l
,,s a .us , m a .us > m a m,s =
l l l l l l m u m,s. -
l 1 ,
, . -aus-=, ,,
._ - e ses = a a,s m .
.,s . .
i r
e . _ _ _
- . . -@J . _ - -
.. - FX .
8
.,,, . . . f . . . ,_
insa
.,,, ---I-- , - .
TA & E
,,,, - f-- m ,
TR2 a
_,,1__ , ,ss4 m
~ ~
n 4
- .us --- ~s
, l l l l l l j _-_
l
.j . 2 I.
4 i- /
, .i k: {
- i i
- [
t t .I
. o 5 Figure 3.7-3. Millstone 3125 VDC and 120 VAC Electric Power Distribution System i j' i 9 I
)
I l
s t l
I i.
t' ~
f s \ -.
v -
! i
! i
- i i
t J
F&e me.m wmC $$st ma eau WAC &6e es.se WW. Sie es.se unc Gea esse. k AL 6seesem wae; sus M ? 215 M Y -ri 12 4 33512 U 25 m> esos s/ e i o ,,
) ...... ...... -
] - -
BA f fE RY GAfre RV SAT , BA TT6 3sv GAf 3 hp?TE,RW SAT 1
amt e sr ac ,
_-E=-
ac t u i u ac , ac 2 u -gi- 2 oc e v ..
y -- -- --
-3 y --
n a 6 o o o . 6 . .
I I I I I i
- j ,,,- ... ,,,-o,,, ,o m ..s ,
l l l l l l .m m .e .
l I ,
0 .. c " m vac "
=i sus a v
- m. c 87' . . -
Js n a sus n a
. _ ... . -g J -g I
- c m _. .,. . _ . ..
-,1 _ .._ _
-. ty lso.em i
! I;;;
,. b .sso a .=nm ==sro.ea wm -- f-- w=ssa.w m == 1_ mm.ceua q
1
.rn. . .
- . _ T ~' o__ I--._
j )
l l l
l l l
I i
g c., 3 I oce=. I l c.,
I I ix..- I lurJfE troE S edAv seO7 5E P9ESEnf ACTtaAL CARI se.m>TeeG 9b f aut 4 m RR A6 i
4 i-C Figure 3.7-4. Millstone 3125 VDC and 120 VAC Electric Power Distribution System i
E Showing Component Locations i
4 4
n a Table 3.7-1. Millstone 3 Electric Power System Data Summary for Selected Components COMPONENT ID COMP. LOCATIOt3 POWER SOURCE VO LTA G E POWER SOURCE EMERG.
TYPE LOC A TIOri LOAD GRP BA T-1 UATT BAIHM1 125 D01 BA I-2 BATT BAIRM2 125 002 BAT-3 BATT BAIHM3 125 003 BA T-4 BATT BAIRM4 125 DQ4 BC-1 BC CB2 BUS-32T 480 CB2 ADA BC-2 BC CB1 BUS-32U 480 CB1 AOB BC-3 BC DCEORM3 BUS-32H 480 AUS AC/A BC-4 BC DCLORM4 BUS-32W 480 AB6 AOB BC-7 BC CB2 BUS-32 T 480 CB2 AC/A BC-8 BC DCEOllM4 BUS-320 480 CB1 ACB BUS-1 BUS CB2 BA T-1 125 BATHM1 D01 O BUS-1 BUS CB2 BC-1 125 CB2 D01 BUS-1 BUS CB2 BC-7 125 CB2 001 BUS-2 BUS CB1 BA T-2 125 UATHM2 DC2 BUS-2 BUS Cat BC-2 125 CB1 D02 BUS-2 BUS CB1 BC-8 125 DCLOHM4 002 BUS-3 BUS DCEORM3 BA T-3 125 BATHM3 DC/3 BUS-3 BUS DCEORM3 BC-3 125 DCEORM3 DC3 BUS-3 BUS DCEOHM3 BC-7 125 CB2 DC3 BUS-32H BUS ABS T H 34C5 480 ABS ADA BUS-32T BUS CB2 TH-34C3 480 CB2 AQA BUS-320 BUS CB1 1 H-34D2 480 CB1 AC/B BUS-32W BUS AB6 IR-34D4 480 AB6 ACB BUS CO2 DG-1 A 4160 DGA AC/A BUS-34C BUS-34D BUS CB1 DG-1 B 4160 DGB AOB BUS-4 BUS DCLORM4 UAl-4 125 BAIHM4 DQ4 BUS-4 BUS DCEORM4 BC-4 125 DCEOfUA4 DC/4
~
O O O Table 3.7-1. Millstone 3 Electric Power System Data Summary for Selected Components (Continued)
COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE TYPE POWER SOURCE EMEEG.
BUS-4 LOCATION LOAD G R P.
BUS DCEOFDA4 BC 8 125 DCEOnu4 004 BUS-VB1 BUS CB2 ItN-1 120 CB2 ADA BUS-VB1 BUS CB2 TH-1-X 120 CO2 ADA BUS-VB2 BUS CB1 itN-2 120 CB1 AC/B BUS-VB2 BUS CB1 TH-2-X 120 CB1 AC/B BUS-VB3 BUS DCEORM3 ItN-3 120 DCEOlu.t3 AC/A BUS-VB3 BUS DCEORM3 IH-3-X 120 DCEORM3 AQA BUS-VB4 BUS DCEORM4 nW4 120 DCEORM4 AQB BUS-VB4 BUS DCEORM4 IH4-X 120 DCEQHM4 ACB CB-34C CB CB2 DG-1 A 4160 DGA AQA CB-34D CB CB1 DG-1B 4160 DGB AQB U DG-1A DG DGA 4160 AQA DG-18 DG DGB 4160 AQB INV-1 ffN CB2 BUS-1 120 CB2 D01
!NV-1 Ir# CB2 BUS-32T 12'O CB2 001 INV-2 FN CB1 BUS-2 120 CB/1 002 ItN-2 IrN CB1 BUS-32U 120 Cut 002 INV-3 IPN DCEORM3 BUS-3 120 DCEORM3 003 INV-3 ITN DCEORM3 BUS-32H 120 ABS DC/3 frN-4 IPN DCEOHM4 BUS-4 <0 ,DCEOHM4 DO4 ItN-4 FN DCEORM4 BUS-32W 120 (496 D04 MCC-1A4 MCC ESFE36 BUS-32I 46(I ~ (CB2 AQA MCC-1A5 MCC SWPAC BUS-32I 480 CB2 AQA MCC-183 MCC ESFN36 BUS-320 480 CB1 AQB C MCC-184 MCC ESFSE36 BUS-32U 480 CB1 ACd5 MCC-t BS MCC SWPBD BUS 32U 480 CB1 ACiB MCC-3A1 MCC ABS BUS-32H g480 ABS AQA L_, -
s.q l
i Table 3.7-1. Millstone 3 Electric Power System Data Summary for Selected Components (Continued) i I
COMPONENT ID COMP. LOCATION POWER SOURCE VO LTAG E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
MCC-3A2 MCC ABS BUS-32H 480 ABS AQA i MCC-381 MCC AB6 BUS-32W 480 AB6 AC/B MCC-3B2 MCC ~ AB6 BUS-32W 480 AU6 ACH IR-1-X THAN CO2 BUS-32H 120 AUS AQA TH-2-X TIMN CB1 ' BUS-32W 120 AB6 AQB TH-3-X THAN DCEORM3 BUS-32T 120 DCEORM3 AQA TH-34C3 THAN CB2 BUS-34C 480 CB2 AQA TH-34C5 THAN ABS BUS-34C 480 CB2. AQA TH-34D2 THAN CB1 BUS-34D 480 CB1 ACB TH-34D4 THAN AB6 BUS 340 480 CB1 ACIB i
.t TH-4-X TIMN DCEORM4 BUS-32U 120 DCEORM4 AQU
- O' ,
I i
l 1
i i 1 t
i 1,
l ,
1 t
! i
. - - . - - . - . . _- - ._ - - _- - - _ - - . . _ - . . .~ .-
, Table 3.7 2. Partial Listing of Electrical Sources and Loads at Millstone 3 GOoEh ve5! AsE EVE 45 Pone 6 dOAE LQAD LvAR lOCVP CoWCMbi SOL :E LOAD CRD LOCAflON $YSTEM COUPONENT C TYPE LOO ATiCN EA' 12A DC t BAIRMI EP bus 1 Bv6 CEt lhA' 5eb DC 1 BATAM) EP B v S-1 Bv5 v62 i
rAi. 1.3 C0 4 OAT 4V2 ED bwS 2 Svp Chi
=Ai !.b DC 2 BAi4Y2 EP Bv6 2 sud VBt 7- J Id DC 3 BAi4M3 EP bub-3 Bus DCE.4V3 sA?i 145 DC 4 UAihM4 EP Ov5 4 Bys DCEQ4M4 I 125 041 002 EP Bus 1 bus Cb2 bei 145 04) cB2 EP Bus 1 bub CB2 cu-4 145 DC 2 CBI EP bus 2 Bus CBI EC-4 125 DC 2 GBt EP BUS-2 Bv5 CBI
~
BR3 iTS DC> 3 DCEORNO EP BUS 3 Bv5 DCEQRM3 BC 4 125 DG4 DC EORM4 EP BWi4 BUS DCEORM4 60 7 125 DC 1 Cb2 EP Ov51 BUS C B2 80- / 125 DC 1 CO2 EP BUS 1 BUS CB2 eC ? 125 DC 3 CB2 EP BUS 3 BUS DCEORM3
\ 6C +3 125 DC 2 DCEORM4 EP BUS 2 BUS CBI 6C e 125 DC. 2 DCEORM4 EP BUS 2 BV5 CB)
BC 8 125 00,4 DCEORM4 EP Bv5 4 BUS DCEORM4 Sv > 1 120 DC,1 CB2 EP iN V 1 INV CO2 bus-2 120 DG2 Cik t EP iNV 2 INV CBI Bv6-3 120 DC/3 DCEORMS EP INV 3 INV DCEORM3 Bus J48 480 A C, A AB5 EP BC 3 BC DCEQRM3 Ev5 32R 120 DC< 3 AB5 EP (NV 3 INV DCEORM3 sud 34R 480 AGA AB5 EP MCC 3At MCC AB5 Sws-Jaa 460 AGA AB5 EP MCC 3A2 i Mid ~ AB5 Ov>324 120 AGA AB5 EP TR 1 A TRAN CB2 Bv5 32T 480 AC A CB2 EP BC 1 BC CB2 Ev5 32T 480 AC. A CB2 EP BC 7 BC . CO2 Bus 32T 480 AC< A GB2 EP BC-7 BC CB2 Bus-Jii 120 DCi1 CB2 EP ANV 1 INV CB2 Sv5-32I 480 AC, A CB2 EP MCC 1 A4 MCC ESFE36 V
56 US9
Y Tablo 3.7 2. Partial Listing of Electrical Sourcom and Loads at Millstone 3 (Continued)
N Ab4 ', Qg f AuE i V E 4 's PCAE45Cy4CE LCAD LCAD COMG CQM&O*,E % i SL AC E LCAD G4P LOC A!!CN SYSTEV COMPONENTC TYPE LOCALCN cd47 460 40 A CB2 EF 7 e0 C t A 5 MCC sMAC e,5 32 7 sea AC A v;EGRVJ EP TA 3-A ';AN DCECAY3 c > Jiu de; AC B Gb1 Ek bC 2 BC 401 b >Jos 460 AC 0 0B1 EP bC 6 BC DCEUAV4 b.> JsV 400 AY B CB) EP BC 8 BC DwECAM4
> 34V 460 AC b CB) EP MCC 1B3 MCC E bF N36 T .5Jiv deg AC-b CBI EP MCC 104 MCC E5FbE36
- 1. > J s 460 A G. b CBI EP MCC 1bt MCC dM BD Esa sis 120 A C. B DC E C AM4 EP TR 4 A TRAN DCECAM4 ev >-J; W av0 A C, B AB6 EP BC.4 BC DCECRM4 b u s 3. W 120 DC,4 AB6 EP INV 4 <NV DCEGAM4 Bws 3sw 460 AC B ABb EP MCC381 MCC Ab6 Bv> 34W 460 A C48 AB6 EP MCC482 MCC AB6 Sv5 3;W 140 AC D AB6 EP TR 2 A TRAN CB1 Bv5 34C 416 AC A CD2 AFW AF W P 1 A MDP AF W A Bv 5-34 C 4160 A C,, ,, CB2 CVCS CM P3A MDP CMA Bv544C 4160 AC. A ECCS 5. P I A MDP 5iM A ev544C 460 AC. A CD2 EP TT3403 TRAN CB2 Bw544C 460 AC, A GB2 EP TR 44C6 TRAN AB5 Bv544C 4100 AC A CB2 PAMRS CRS.PI A MDP R5 SAC Bus 34C 4160 AC A CB2 SW SW.PI A MDP $WPAC l be5 34G 4160 ACr A CB2 SW 5W P1C MDP 5WPAC l
t Bv544D 4160 AC 8 CBI AFW AFW PiB MDP AF W B l Bv544D 4160 AC; b CE1 CVCS CH P3B MDP CNB bv544D 4160 AC,8 CB1 ECCS SiPIB MDP 5IMB Bus 34D 480 Ab8 CBI EF TR.3402 TRAN CBI I
Sv5440 ws3 A C< B CBI EP TR 3404 TRAN AB6 I
I oW>34D 4160 AC,8 CBI PAMR5 CRS PIB MDP A5SBD l
[ bus 44D 4160 AC, A CO2 PAMR3 CRS-PIC MDP R5 SAC Sv 5-34 D 4160 A C. B CB1 kkMRS ' RS-P t D MDP R$5BD 57 1/89
^
[ 1 7
Table 3.7 2. Partial Listing of Electrical Sources and Loads at Millstono 3 (Continued) m
. ; ,4 ; R i bi A ki. E Y E V.4 h AiRdO.4 L AD
.w ..Ak CwYD . f,4 d. i ', 7 SO C E LCAD C4P LOOATiCN SYSTEV COYPONENT O ME LOCASON t- - ~ ;- d i t- Q AC B vb1 du bahib YM 5AFOD E.5f I 41o., AC b Okt >A dW PID YP dAEED
..>i 9s sL 4 sCELAM4 EP A v .4 hv DCEuRY4
. ,2 tA .l it; AC A DUA EP bub 34C Oss Chi
.a'A 4% Av A USA EP Ovb J40 kvo CDs
'. v 1 1.0 AC- A ;B2 EP Bv5 v81 bus C02 h2 120 A C. B CD1 EP Bub v62 Bus Cbt A v .3 120 AC A DCEoRMJ EP Dv5-v8) BUS DCEGAM3 ava lia AC B DC EQ AM4 EP Bv5 v84 Bus DCEQRM4 MCC i A4 460 AC A ESFE36 AFW AFW stb MOV R$5BD MCC iA4 400 AC A ESFE36 AFW AFW450 MQv R55DO MCC 1A4 400 AC, A ESFE36 ECC5 Si e802A MOV SMA v
MCCa A4 460 AC A ESFE36 ECCS Si6621A MOV 5,M A MCC 1A4 480 AC A E CF E 36 ECCS 5F6021A MOV SlMA TJCC,1 A4 480 AC. A E6FE36 ECCS 566635 MQv SmA MCC 1 A4 400 AC A ESFE36 ECC3 Si-6923A MOV 5tM A
' MCC 1 A4 460 AC. A E 5F E 36 PAMRS CRS-20A MQv RSSAC MCC 1A4 400 AC. A ESFE36 PAMRS C RS-200 MOV RSSAC MCC t A4 460 AC. A ESFE36 PAMRS CRS43A MOV 455AC '
b>
MCC 1 A4 480 ACr A ESFL36 PAMR5 CR$ 23C MOV RSSAC MCC.1 A4 460 AC. A E5FE36 PAMR5 CAS 683?A MOV E5FE MCC 1A4 480 AC A E5FE36 PAMAS CAS 8835A MOV ESFE MCC 1A4 480 AC A E5FE36 PAMRS 5W 54A MOV ESFE MCC.1A4 460 A C. A ESFE36 PAMR5 5W-54C MOV E5FE MCC-1 A4 460 AC A E5FE36 PAMRS SW 57A MOV A55AC MCC.1 A4 460 A C4A E5FE36 PANAS $W 57C MQv RSSAC i
A % MCC tA5 480 AC A 5APAC EP SW502C MOV 5APAC 58 1/89
..-..- - - - - ._ ._ - - . . . . . . . --- . . ~ _ - - _ - - _ _ . - - _ - - _- _ .
Table 3.7 2. Partial Listing of Electrical Sources and Loads at Mllistone 3 (Continued)
-OnE4 .0LIAGE EMERS kO AE R 50vRCE LOAD .QAD CCMP v;N40%E%i SM4 E LOAD GAD LOCA?!ON SYSTE M COYPONENT T TYPE LOC A'ON M; tat 4e3 AC A 5APAC 5A SWa;eA MOV 5AFAC M;C 'At 450 AC A >AFAC SW SW 102C MQv 5APAC MC v 1DJ ab) AC D E M NJ6 ECCd 5bbh02B MOV $v6 L ' t: J 460 AC 0 E dF N36 ECC5 5.6806 MQv EbfNE Mv- 163 460 AC: B E 5F N36 ECC5 5b682iB MOV dmb Mvv lbJ 460 AC B E dG N 36 ECC5 dh6621B MOV 5+B h b3 460 AC A E 5F N36 ECCb SL6323B MOV 5NB M C 164 dey AC 6 E 5F bE 3b AF W AFW SbA MOV A55AC M;C 'i4 db0 A C. B E5G5E36 AF W AG W-350 MOV R$5AC V;C lb4 460 AC B E555E36 PAMR$ C AS-20B Mov RSSBD MCC 164 460 A C. B E 5F SE36 FAHR $ C AS 200 MOV RSSBD MCC 104 480 AC, B E5F5E36 PAMR5 CRS 238 MOV A55BD MC Cd B4 480 AC B E 5F SE 36 PAHR5 CR5 230 MOV RSSBD MC C- 164 480 AGB ESF5E36 PAHR5 CR5 6837B MOV E5F5E
\ MCC 1B4 480 AC. B E 5F 5E36 PAHRS CR5 88388 MOV ESFSE W Cd B a 480 AC B ESFSE36 FAHR $ SW 54B MOV E5FSE MC C d B4 480 A C, B ESF5E36 PAMR5 5W 540 MOV E5f5E MC C a B4 480 AC. B E5FSE36 PAH R5 SW 578 MOV R55BD MC C a B4 480 AC B ESF5E3f PAMR5 5 W.5 70 Mov RSSBD MC Cd 65 480 AC. B 5WPBD EP SW 102D MOV 5WPBD MC C- 185 480 AC, B $WPBD SW 5W 1028 MOV SWPBD MCC 185 480 AC,8 SWPBD SW SW 102D MOV SWFBD MCCJA1 480 AC, A A05 CvC5 CM 1120 MOV BA5AB MCC 3At 480 AC< A AB5 CvC5 ; CM 8438A MQv CnA MCC JAt 480 AC, A AB5 CVCS Cn 8438C MOV CNA MCC 3A I 480 AC, A AB5 CVC5 Cn 8468A MQv CMA MCC JA1 480 A C, A AB5 CVC5 Sb880tA MOV BASAB MCC 3A2 480 AC A ABS RC5 RC-6000A MOV AC MCC 3A2 460 AC. A AB5 RC5 RC 8701A MOV AC MCC 3A2 460 AC. A AB5 ACS AC 8701C MOV RC MCC-381 480 AC4 0 AB6 CvC5 CH.112E MOV BASAB i 59 1/89
Table 3.7 2. Partial Listing of Electrical Sources and Loads at Millstone 3 (Continued)
ACaEA vowiACs EMEAS PC ni;4 SQv4C .OAD a AO CCMP ,,JVPCNiN!
SOsACE LCAD G AD LOCAT:ON SYSTEM COMPONr.NT C TYPE LOCATION C.JB1 480 AC B AB6 CvCS CM-e4388 MQv C-B YO C -]s t 46S AC B AB6 CVCS GM 646)B MOV CS' h 3 61 de0 AC B Ab6 GVCS SbeS01B MOV BA$AB M .Jb2 466 A C, B AB6 NCS RC-60000 MOV NC WC aB2 ~W AC,8 AB6 ACS 40 87028 MQv AC M >b2 400 AC B AB6 RCS RC-6/02C MOV RC in i A 120 AC A CB2 EP Bus-vBI Bud CB2 74 2-A 120 AC B CB1 EP BvS.v82 Bv5 CBt IR J A liO AC. A DCEGAMJ EP Bv5 vb3 BUS DCECAM3 TA 34CJ 460 AC, A CBa EP BUS 42T Bus CO2 T A-34C5 480 AC, A ABS EP Bu S-32R BUS A%5 IA J402 480 A C. B CBI EP SUS 32V BUS CB1 T44404 480 A C. B AB6 EP BUS 32W BVS AB6 TA 4-A 120 AC< B DC E GRM4 EP Bus v84 Bus DCECAM4 f
1 l
60 1/89
i i
L
- Stillstone 3 3.8 SERVICE WATER ISW) SYSTEN!
l 3.8.1 System Function The semce Water System supplies cooling water from the ultimate heat sink to vanous heat loaas i n both the pritrary and secondary portions of the plant. The system is designed to provide c continuous flow of cooling v ater to those loads which are safety-related or essential to the safe shutdc i of the reacto..
i 3.8.2 Sntem Deflgliign I
The Semce W ater System contains two open. loop headers, each supplied by two motor driven pumps. The source of water for ti:e system is Niantie Bay. Strainers are p ovided to remove impurities from the raw water before it enters the SW pumps. After serving the various heat loads in the plant, service water is discharged to the circulating water discharge ti:nnel which returns to Niantic Bay.
' Simplified drawings of the SW system are shown in Figures 3.81 and 3.8 2.
A summary of data on selected Service Water System components is presented in Table 3.81.
3.8.3 System Oneration Dunng normal operation, one SW pump in each redundant header is in continuous operation providing cooling water to various heat loads. Heat loads supported by the SW system include the following:
Diesel generator coolers HPSI and charging pump coolers CRS heat exchangers Component Cooling Water heat exchangers, i
The SW system can also be aligned to supply water to the Auxiliary Feedwater System pumps. It also provides an emergency cource of makeup water to the fuel pool.
l 3.8.4 System Success Crlieria l The system success criteria for the Service Water System is defined on a per i
train basis. For each train of the SWS, the following must be available:
A source of coolant water from the Niantic Bay 1 of 2 pumps An adequate flow path from the pump discharge to the heat sources and to the circulating water discharge tunnel 3.8.5 comnonent Information A. Service Water Pumps I A,18.1C and ID
- 1. Rated flow: .15,000 gpm @ 120 ft head (52 psid)
- 2. Rated capacity: 50%
- 3. Type: verticalcentrifugal B. Ultimate Heat Sink Long Island Sound l
61 -1/89:
s' *-' w~yi guv- =p py w1,y gr y w v m,y yr-wyvig eewg -y y vw wwray=-r -* y-9--Wy r- yy9 ,wg % qe-- y ,w we w e w 1.a-Prywqggwwwgv wt,w w y$wm 4 , w9 y- g av y- w T4 W-9' k*-$pyrT*=-T-v rurM **t&ew'Dr-1r 9 y='P-rue N- WFY TW '7v M g vb'r y nr" VF'1
Alillstone 3 3.N.6 Suonort Systems and Interfaces A. Control Signals l
- 1. Automatic The SW pumps are not automatically actuated. l 3
- 2. Remote hianual The SW pumps can be actuated by remote manual means from the control room.
f3. Stotive Power 3 The SW motor driven pum as and motor operated valves are Class lE AC loads
- that can be supplied from t1e standby diesel generators as described in Section
! 3.7.
l i C. Other
- 1. Lubrication, ventilation, and cooling are provided locally for the SW pumps.
3.8.7 Section 3.8 References
- 1. Niillstone 3 Final Safety Analysis Report Section 9.2.1.
i 4
i
]
l
! 62 t/gg e - . - . .- -,_., ..-.,.. ,rw,,,, .. % . ,y. ,. ,.w , ,,,.-,..--.,%-w-, yy., % n...
i i
i
\
i ,
i .i-a!is!
. <.e J l'
< l
- c. I o i O t a
X: !c !
e, m t
(I. 3 s
O $>
x ext ex:
e, mt si si m x- !
n i
+5 +W .
(s c E
il TTl I'
l
--I r $
7 5 .
X2 X= oI!oI!
i i Ia I,s tZe $
n p-I .
s O
i 1
l< l o8.! oI.!
p -
t-b! !
63 1/89
l i <
i
- !
- I I eIj 1
- it i m umme o
mus. : C p o 1 0
- o a
- C o
g g g
- o
)_ e b j O
a
,, - - - - m i
. n . 4
- .a : a i
I
- 5
- o
)
. - 3
_ o, m _ _ _ _ _
. E Np 0-11 i
Ok-lOk5 3_ h y -
%=_ !
- c, is 4.1 'cV
. 3 ,
a
- s. < l r es j i
{g _ -
3 g t
, 1-v 9 ~@ ,
I - .
.y l t- ,
L D c5m! 1 a
_ _ c- - -
1 I I,,
aga tn :e e
. : El 2 i
- E e
I i 4 cJ l 4 n
i, i
m o
C
. i
- 9 I u 'I <!
i i
. t> L-
- j-g y 1 UR 4
64 1/89 d
f
---_,,.,.--_m_.-.._, .
, . . - . ._. . _,. - _,--_ --,-,.~....... . -. ,_-... ~ -._..- ..,----.., ,- ~. _, -
p .,
V i .i-esit!
I
' l l
l t
i a 1 3
E X- s c
- m t
IS Il a m
O e{5 e
x- ox .ox: il ii x- 1 1 ~
1 .
a +1 a <. ,,
n (n 4 9 8 o
J I
11 v
ri ri 3
=
I X: X: cIl crIj 1 i In D I,n i
tZn ri 4
n sta e t{ g en C
j e_s t- t-65 1/39
1 i
a .
2 s :i .i 4 4 6 4
- ne L_. _ O p =
c 3
C U
- g
,,,,, c.
E o
- g
.v,.. , g J:
, , - - - - - - m
=
,'1 Il i !
. i
!* a o
s . . - - - -
- a
. E C-l! X Okl Oi!_ y I
h -
}s- ! k
< m .
m r e
. g
, , ja .<_ t w 9 ;
- g 2
- I I I_I I 3
m v _ us y}, $ yF5~
.g o
i , 1 - -
D E: 01 ! Ia t
li' oI! ' I In tZe l
- - ._J i t _ .,_
aga .
- c Ej o t ~
m
- =
. lE t e
'D a
I I i
, 'l !
!. t& .:
jq7 j-, p V3 VA 66 1/89 i
1 e.
2 4
Table 3.8-1. Millstone 3 Service Water System Data Summary for Selected Components
+
COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
2 TYPE LOCATION LOAD GHP.
SW-102A MOV SWPAC MCC-1AS 480 SWPAC AC/A SW-1028 MOV SWPBD MCC-1BS 480 SWPBD ACM SW-102C MOV SWPAC MCC-1 AS ' 480 SWPAC ADA SW-1020 MOV SWPBD MCC-1BS 480 SWPBD AQB
!1 SW-P1 A MDP SWPAC BUS-34C 4160 CB2 AQA SW-P1B MDP SWPBD BUS-34D 4160 CB1 AC/B j SW-P1C MDP SWPAC BUS-34C 4160 CB2 AQA ,
j SW-P1D SWPBD BUS-34D 4160 CB1 ACB lMDP k o w-j d
,l I
l .
i i
t 4
k 4
(
1 i en C
i i
i' i
,+.,,y ,,.nq . , , ~ . , . < , - - ,..%,4 -r.--,.s, w-.-.-4. , ..r -
r, - w.,%v gv, e .y -w - q , .,-.,r- .,.i .,%- yo, .<.r=-,-,r ,,eg-..,.wr,.wy ,wie., , . . . , , - , - . . ,,,,e,-. ,..,.w_. ,,..,,%_my,-w.
- _ - - - _ ..~ - - . _.. _ - - .. . _ _ . - - - _ - _ _ _ __ - _ _ _
l Millstone 3 4, PLANT INFOR.\lATION l
\
t 4.1 SITE AND BUILDING SUS 1.\lARY' The Alillstone Nuclear Power Station is located in the Town of Waterford, New London County, Connecticut, on the north shore of Long Island Sound. The site occupies 500 acres on the tip of Millstone Point between Niantic Bay on the west and Jordon Cove on the east. The site is situated 3.2 miles west-southwest of New London and 40 miles southeast of Hartford.
The Millstone Station consists of three operating units. Unit 3 is located i immediately north of Units 1 and 2. No systems are shared between Unit 3 and the other
~
two units at the site. Figure 41 (from Ref,'l)is a general view of the plan: and vicinity.
The major structures at this unit include the containment building, turbine ,
ailding, auxiliary building, fuel building, main steam valve building, engineered safety-t'eatures building, control building, an.1 circulating and service water pump house. A site l plot plan i'; shown in Figure 4 2.
The containment structure is a reinforced concrete cylinder with a steel liner, The containment contains the reactor vessel, reactor coolant pumps, steam generators, and pressurizer. Pumps, piping, and vtiving for the reactor coolant system is completely contained within the containment structure. Piping and electrical penetration areas are on various levels of the auxiliary building and engineered safety features building, The _ turbine building, located west of the containment, houses the turbine generator and the associated power generating auxiliaries.
, The auxiliary building is located northwest of the containment and contains l components of the CVCS and electric power system.
l The fuel building is northeast of the comainment and houses the spent fuel pool.
The main steam valve building is located between the turbine building and y containment and contains the main steam lines and isolation valves.
The engineered safety features building is located east of the containment and contains much of the plant's safety related equipment, specifically components of the AFW, HPSI, RHR, CRS systems, and motor control centers supplying power to safety ~
system components. This building is divided into several areas.
The control building is ir ated north of the turbine building and contains the main control room, cable spreading room, and switchgear rocms.
The circulating and service water pump house is located southwest of the comainment on Long Island Sound and contains the service water pumps and intake structure.
4.2 FACILITY LAYOUT DRAWINGS Figures 4 3 through 4 8- are simplified _-building elevation drawings for Millstone 3.' Details of the turbine building and many of the oudying buildings are not shown on these drawings, Major rooms, stairways, elevators, and doorways are shown in the simplified layout drawings, however, many interior walls have been omitted for clarity, Labels printed in uppercase correspond to the location codes listed in Thble 4 1 and used in the component data listings and system drawings in Section 3, Some additional labels are included for information and are printed in lowercase type, A listing of components by location is presented in Table 4 2, Components included in Table 4 2 are those found in the system data tables in Section 3, therefore this table is only a partial listing of the components and equipment that are located in a particular room or area of the plant.
(
68 1G9
Millstone 3 4.3 SECTION 4 REFERENCES
i l
l.
l l
r i
t 1
l l
4 69 1/89 a
i .- . . . . - - ,.,---.---...-----.-.-,,-------.------,---,,-..v--n--n-,~--- - - , ~ - ,
a s. .w--a - a - 2. a n - - aw
/,Y .,.
p!- [f g) Iv .
3
,,a >
a <
r
,N l
f
- s s
- B~%+' '.. o a,y >
- e,
?m
. - - - . (/h,
/ g,h #' ~ } !' %s../" o
=
O l, m '$
'k 0
, D
'q $ u $ '
l
\
D ,
(& ~
s
~ o
\
' /
h p Gk ) \ ' q, e im i ';
o U
S ' s l': i ; c .s .
g i-f f 1
\ i, V
- s. __ -
j sr o 6p v ,
t d e',
- t. phk yg x
h .h-O 22 >
2 gE ' '. o o
f a5( \ w%
K 4
a
' 5 .
~,,,
'. w , .
/ $
C W- \ 0' /
J
'9 3 ('
O h
~[ t
,,F' ,
y . ,
O s 7 w
fg .
e u b
,.) s 8
} Nf' 4
Q m
\ r, N , '~~~ s,' . ,
+
p ;p ,
y Y
\/g i4 h _q s
' i 6
// /' A ,
f./2xx,n --
y y ;
v 70 US9
CALLED NORTH 3 f
Domin Water DWST RWST Refueling Water Storage Tank Storage Tank Engineered Safety C,r:Jx e ;
Features Budding Water Fuel D sena ;o RC Tunnel Building Unit 3 Containment Structure Condensate Auxiliary Storage Building Tank MacNne Main Steam
(
Sh3D Valve Building -)
Semco
% Building Turbine Building Control To Emergency Building Unit 2 4 Generator Enclosure Technical Support Center did aLak 4LaL Circulating Weter intake Lines From Circulatir,q a Service Wator Pump House bV Figure 4 2, Millstone 3 Plot Plan s
71 1/89
O x
C AL t E D NORIN
() O ESFE ESFSE ESFP PPCHFB RHRA RSSAC I CHS am 1 am
- ia na im o cw_3 m ic cas O sistma u eia O "" '" R S S e o i RHRa o cus Na*e "*' O an O Pi
% ,m
%w W ho N Sperti ha rod
( 31^- 3")
RC q EL 19 F iJ ruwws t
4 8 soum d' Inpmun Tne U u J BASAB e
gE__
! A U
l 1
-Y Es
$ 3e atur *"
O - -O- -
Figure 4-3. Millstone 3 General Arrangement, ESF, Fuel, and Auxiliary Buildings, Elevation 3'-8".
t
O O O
[ ~h p Skwy
- te d i ==% Cn.s)
N RIH U Ai S4 P tB SIP 1A AFWA y AF WD M w Pts
$1HB SlHA -
O AFWB CHs RSSAC
"'AO crO*
To Wave aa 8 *)
Ouess g) m ,, O nSSBo Svenn9 o u o " '
mmmn *'O
- a. O saa 2.
sp.ni ru. /
Sng 4wsg y u cma Siory U Stanma, se to Asea PJ4C barrt Spent a f w we Fued b" Pool ca.
u y RC d ! p, .
- 0 5747 ro.: 1,e T,
- 8 9o ~-
o Au==s Las AB24 o Equpanone hagge U N' Masde 4
sam" ABS CHA d
CHB AB6 d CHC ramiiwaa i oi eo 5 M1_ g sw u.. c.-
a 4 o ca o
% a u m a ,, ,
Figure 4-4. Millstone 3 General Arrangement, ESF, Fuel, and Auxiliary Buildings, Elevation 24*-6".
1 i
i
k
\
CALLED NORTH '
,,, 1111]D R11110 I
ESFE36 ESFSE36 O QuCCtA4 ESFN36 RHRA casO casO
- ,O
+= ia sa m csp, RSsoo
, , , , l
. RHRB cas ,
"" ' O an O ttX 18 I
t i em W o ~m -
t 144 */
Spent Fuel g ,,. 7 TLSF RC
^
o y :
. s. :
- i i
i
' A t
i
. 1 i
l i
1 C s .
i MNSTMAD
=
0 o
- 6 ot> B B o h ; MNSTMCD (-
O 9 i,
Figure 4-5. Millstone 3 General Arrangement, ESF and Fuel Buildings, Elevation 51*-4".
t
O O O x
CALLED
-o 0- +
NORTH Q BATRM1 BA M 3 ,
O-DCEORM3 0"5 co- -
't
( ' DG-1A FuelOf Tank )
CB2 i
( DG-1B FuelOilTank )
4160V BUS 34C DGA DGB MCC1 A2 - -
MCC182 ' '
d " ~
4160V BUS 34D 1A1 - 181 -
i CB1 i
Diesel Diesel DCEORM4 32 Room A Room G m !
BATRM2 BATRM4 b
O. #
C
- b Figure ' 4-6. Millstone 3 General Arrangement, Control Building and Emergency.
Diesel Generator Enclosure, Elevation 4' -6".
4
O O O
\
CALLED NORTH O
CSR Located Beneath This Elevation 6
CB66 Located Above This CR 1RR Elevation Control Room M
Q '
$ l D O-T n
- v w,
i l c
! $ Figure 4-7. Millstone 3 General Arrangement,. Control Building Elevation 47*-6" l
O e
i c
v r
e D S B
P d W n S a g
i n
t l a" cD I u6-s ev PO W
S 5
8 1
i i
C cr *4 1
n la C t ,o V B C nit d
1 P
M ea n
a g
n p
WO S
- I t
e r
u c
mv ele gE
_ u r n T P r
e S
t a
r e t
a C k e r s W a Au o
1 t P n e
ic v
r e
WO S
5 A
1 I i l aH r
ep S C n m A C e I
M GuP cS PO W
I 3r e
et na t
oW l
S l
C i A M P
W 8-S 4 -
e r
u g
O O i
F D
E H T
?
Table 41, Definition of: Millstone 3 Building and L Location Codes Codes Descriotions
- 1. AB24 Located on the 24'-6" el' e vation of the Auxiliary Buuding.
- 2. AB5 Auxiliary Building Switchgear Room 5, located on the 24' 6"-
! elevation of the Auxiliary Building i
- 3. AB6 Auxiliary Building Switchgear Room 6, located on the 24'-6" .
elevation of the Auxiliary Building
- 4. ARVA Auxiliary Feedwater Pump A', located on the 21' 6" elevation of j the Engineered Safety Features Building, east side i
- 5. ARVB Auxiliary Feedwater Pump B, located on'the 21' 6" elevation'of-the Enginected Safety Features Building east side :
i'
- 6. AF%TD Turbine Driven Auxiliary Feedwater Pump, located on the 21' -
6" elevation of the Engineered Safety Features Building -
! southeast side
! 7. BASAB Basement, located on the 4' 6" elevation of the Auxiliary--
Building i
- 8. BATRhll Battery Room 1, located on the 4' 6" elevation of the Control Building 3
- 9. BATRht2 - Battery Room 2, located on the 4' 6" elevation oflth'e Control
,. Building c
' 0.
. BATRM3 Battery Room 3, located on the 4'-6" elevation of the Control -
l= Building
- 11. BATRM4 Battery Room 4, located on the 4' 6" elevation of the Control-Building j 12. CBI Control Building Room 1,' located on the 4' 6" elevation of the -
Control Building - west side
- 13. CB2 I
' Control Building Room 2, located on' the 4' 6 elevation of the .
4-Control Building east side p 14. CB66 - Located on the 66' elvation of the Control Building
- - 15. CIIA Charging Pump Room A, located on the 24'-6" elevation of the
[ Auxiliary Building - southeast side 16i CHB Charging Pump Room B, located on the 24'-6" elevation of th'e i .
Auxiliary Building - south side
, 78 1/89 4
y , ., . - - - p- ewe.+ y--,.,+ r.--.- -.,we, , ,e, -,-.,.r,<- .,~y., , , - , . . , ,---e---..,,%,+,n..-o.v., ,,.,4ir .gy.o.w,,w-,,.o,.e- r w ,Wr-ve+.,*,-r,,-eve--
Table 41, Definition of Millstone 3 Building and pl
'w Location Codes (Continued)
Codes Descriotions
- 17. Ci!C Charging Pump Room C, located on the 24'-6" elevation of the Auxiliary Building southwest side
- 18. CR Control Room, located on the 4 6" elevation of the Control Building
- 19. CSR Cable Spreading Room, located beneath the Control Room on the 24'-6" elevation
- 20. CST Condensate Storage Tank, located south of the Containment Structure
- 21. DCEQRN13 DC Equipment Room 3, located on the 4' 6" elevation of the Control Building
- 22. DCEQRN14 DC Equipment Room 4, located on the 4' 6" elevation of the Control Building
- 23. DGA Diesel Generator A 24 DGB Diesel Generator B b
b 25. DWST Demineralized Water Storage Tank, located east of the Engineered Safety Features Building
- 26. ESFE East side of the Engineered Safety Features Building on the 4' 6" elevation
- 27. ESFE36 North side of the Engineered Safety Features Building on the 36'-6' elevation
- 23. ESFN36 North side of the Engineered Safety Features Building on the 36' 6" elevation
- 29. ESFNE Northeast s de of the Engineered Safety Features Building on the 4' 6" elevation
- 30. ESFNE36 Northeast side of the Engineered Safety Featu+ Building on the 36'-6" elevation
- 31. ESFSE Southeast side of the Engineered Safety Features Building on the 4'-6" elevation
- 32. ESFSE36 Southeast side of the Engineered Safety Features Building on the 36'-6" elevation
[
V 4 79 1/89
n Table 41. Definition of Millstone 3 Building and Location Codes (Continued)
Codes Descrintions
- 33. IRR instrument Rack Room, located on the 47 6" elevation in the Control Building south side 34 .\!NSTNIAB N!ain Steam Penetration Room AB, located in the Stain Steam Valve Building south side
- 35. NINSTNICD .N!ain Steam Penetration Room CD, located in the N!ain Steam Valve Building north side
- 36. PPCHFB Pipe Chase, located in the Fuel Building
- 37. RC Reactor Containment
- 38. RHRA Residual Heat Removal Heat Exchanger Room A, located on the 4'-6" elevation in the Engineered Safety Features Building -
north side
- 39. RHRB Residual Heat Removal Heat Exchanger Room B located on the 4'-6" elevation in the Engineered Safety Features Building -
north side
. (O l
') 40. RSSAC Reactor Spray System Room AC, located next to Containmnet in the Engineered Safety Features Building from elevation 4'-6" to 36*-6" (Contains RSS Heat Exchangers and RSS Pumps B and D)
l ud D)
- 42. RWST Refueling Water Storage Tank, located east of the Engineered Safety Features Building
- 43. SIHA High Pressure Safety Injection Pump Room A, located on the 21' 6"in the Engineered Safety Feature Building north side 44 SIMB High Pressure Safety Injection Pump Room B, located on the 21' 6" in the Engineered Safety Feature Building - north side l 45. SWPAC Service Water Pump Room A, located on the 14' 6" elevation in j the Pump House (Contains Service Water Pumps A and C)
- 46. SWPBD Service Water Pump Room B located on the 14'-6" elevation in the Pump House (Contains Service Water Pumps A and C)
/3 b
80 1/89
Table 41, Definition of Millstone 3 Building and O Location Codes (Continued)
Codes Descriotions 47, SWPES24 Sourthwest Pipe Penetration Area 24, located on the 21' elevation in the Engineered Safety Features Building southwest side
- 48. TLSF Spent fuel pool operating Door, located on the 52'-6" in the Fuel Building
- 49. TUNWB Pipe Tunnel, located underneath the Waste Disposal Building and the Fuel Building
- 50. UG Underground O
O l
81 1/89
Table 4 2. Partial Listing of Components by Location at Millstone 3 '
i f%
LOC A iiON SYSTEM COMPONENT Q COMP lj\
s TYPE AB$ EP BUS 324 BUS ABS EP TR 34C5 TRAN AB5 EP MCC 3A2 MCC ABS EP MCC-3A1 MCC AB6 EP BUSO2W BUS A B6 EP TR 3404 TRAN AB6 EP MCC 3B1 MCC AB6 EP MCC 382 MCC AFWA AFW AFW PI A MOP AFWB AFW AFW PIB MDP AFWTO AFW AFW P2 TOP BASAB CVCS CH 112D MOV BASAB CVCS CH 112E MOV BASAB CVCS SI8801A MOV y w~ BASAB CVCS St8801B MOV f
(j) BATAM1 EP BAT 1 BATT BATRM1 EP BAT-1 BATT BA TRM2 EP BAT 2 BATT BA TRM2 EP BAT 2 BATT BATRM3 EP BAT 3 BATT BATRM4 EP BAT 4 BATT l ~
CB1 EP BUS-340 BUS CBI EP CB 34D CB CB) EP DC 2 BC CBI EP BUS 2 BUS CB1 EP BUS 340 BUS CB) EP BUS 2 BUS CBI EP BUS 32U BUS l CBI EP TR-3402 TRAN
82 1/S9
Table 4 2. Partial Listing of Components by Location at Millstone 3 (Continued)
{G \
) LOCAT:ON SYSIEM COMPONENT lC COMP TYPE CB1 EP Bus 2 BUS CB1 EP BUS 2 BUS CB) EP Bus VB2 BUS CBt EP Bus VB2 Bus CB) EP INV 2 INV CB1 EP INV 2 INV CB1 EP TR 2 X TRAN CB2 EP BUS 34C BUS CB2 EP C B-34C CB CB2 EP 90" BC CB2 EP B G-7 BC CB2 EP BUS-1 BUS CB2 EP BUS 340 BUS CB2 EP Bus-1 BUS g CB2 EP BUS 32T BUS
'\"/ CB2 EP TR 34C3 TRAN CB2 EP BUS-1 BUS CO2 EP BUS 1 BUS CB2 EP BUSI BUS CO2 EP BUS-1 BUS
~
CO2 EP BUS-VOI BUS CB2 EP BUS VB1 BUS CB2 EP INV 1 INV CB2 EP INV-1 INV CB2 EP TR 1 X TRAN CB2 EP BC 7 BC CHA CVCS CH 8468A '. TOV CHA CVCS CH 8438A MOV CHA CVCS CH 8438C MOV CHA CVCS CH-P3A MDP
[h
'V 83 1/89
Table 4 2. Partial Listing of Components by Location at Millstone 3 (Continued) i / )
i ;
\v} LOC A TION SYSTEM COMPONENT!O COW TYPE Cms CvCS CH 84380 MQv CMB CVCS CH P3B MDP CST AFW AFW CST TANS DCECAM3 1EP %3 BC l
DCECAM3 EP BU S-3 BUS DCECAM3 EP BUS 3 BUS l
i DCEORM3 EP BUS 3 BUS l
l OCEORV3 EP BUS VB3 BUS OCEORM3 EP B U S-V B3 BUS OCEORM3 EP IN V-3 INV DCEORM3 EP INV3 INV l OCEORM3 EP TR4-X TRAN
~
OCECAM4 5. P BC-4 BC DCEORM4 EP BC-8 BC i
(N DCEORM4 EP BUS-4 BUS 5j!
DCEORM4 E F~ 6US-4 ~ WS DCEORM4 EP BU S-4 BUS j DCEORM4 EP BUS VB4 BUS-DCFCRM4 EP BUS VB4 BUS i
DCEQAM4 EP INV 4 INV l DCEORM4 EP INV-4 INV DCEORM4 EP TR+X TRAN OCEORM4 EP BC-8 BC DGA EP DG 1 A DG OGA EP CG-1A OG DGB EP OG-18 OG DGB EP OG-1 B OG OWST AFW AFW OWS1 TANK
~
ESFE PAHRS C AS 8837A MOV ESFE PAHRS C RS-8838 A MOV f ESFE PAHRS SW 54A MOV U]
84 1/89
Table 4 2, Partial Listing of Components by Location at Millstone 3 (Continued)
A
/ \
\
i.OC ATiON SYSTEM COMPONENT D COVP TYPE ESFE PAMRS SW54C MOV ESFE36 EP MCC1A4 MCC ESFN36 EP MCCAP: *CV ESFNE ECCS 51e806 MOV ESFSh PAHR$ C AS-86370 MOV ESFSE PAHRS CRS-883SB MOV ESFSE PAMRS SW 548 MOV ESFSE PAMRS WI440 lf C '. ,
E SF SE 36 EP MCC 184 MCC RC AFW SG<i B SG RC AFW SGIA SG RC AFW SG1A SG RC AFW SG 1B SG RC AFW SG 1C SG RC AFW SG 10 SG
'\ '"/ RC AFW SG 10 SG RC AFW SG-1C SG RC CVCS RCS VESSEL RV RC CVCS ACS VESSEL RV RC ECCS RCS VESSEL RV RC ECCS ACS VESSEL RV RC PAHRS RCS VESSEL RV RC PAHR$ RCS-VE SSEL RV RC PAHRS RCS VESSEL RV RC PAHRS RCS VESSEL RV RC RCS RC-8701A MOV RC RCS RC 8701C MOV RC RCS RC 87028 MOV RC RCS RC 8702C MOV RC RCS RCS VESSEL RV
{x \ RC RCS RC 455A NV l
85 1/89
Table 4 2, Partial Listing of Components by Location n at Millstone 3 (Continuec)
\ LOCATION SYS itiM CVMPONENT Q COMP TYPE RC RCS RC 456 NV RC RGS RC-8000A MOV RC RCS RC S0008 MOV RSSAC AFW AFW 35A MOV RSSAC AFW AFW 350 MOV RSSAC PAHRS CRS 20A MOV RSSAG PAHRS C RS-200 MOV RSSAC PAHRS CRS 23A MOV RSSAC PAHHS C RS-23C MOV RSSAC PAHRS CAS EI A MX RSSAC PAHRS CRS P1 A 'MvP RSSAC PAHRS SW 57A MOV RSSAC PAHRS CRS-E1C HX -
RSSAC PAHRS CRS P1C MOP T RSSAC PAHRS SW 57C MOV RSSBO AFW A F W-35B MOV RSS80 AFW AFW 35C MOV RSSBD PAHRS CAS 20B MOV RSSBO PAHRS CRS-200 MOV RSSBO PAHRS CRS 23B NOV RSSBO PAHRS CAS-230 MOV RSSBD PAHRS CRS EIB HX RSSBD PAHRS CRS PIB MOP RSSBD PAHRS SW 578 MOV RSSBO PAHRS CRS-E10 HX RSSBD PAHRS CRS-PIO MDP RSSBO PAMRS SW 570 ACV RWST CVCS S6.RWST TANK RWST CVCS St-RWST TANK RWST ECCS RWST TANK r
l%}
LJ RWST ECCS SI RWST TANK 86 1/89
.. .. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ -- J
.~ . - . . . - . - - _ . ~.. . - . - . . . _ , - . . . . . -. . . . - . . - .
4 1
Table 4 2.- Partial Listing of Components by Location at Millstone 3 (Cont!nued)
O I LOCAliCN SYSTEM COMPONENT 10 COMP TYPE
~
$;MA - ECCS SI6802A MOV SIMA ECCS Sb8821A MOV
.4 f 5.MA ECCS_ SI8821A. MOV t
] SMA ECCS Sb8835 MOV S!!<A - ECCS Sb8923A MOV
}
- SIMA ECCS SbPI A - MOP 2
SIMB ECCS Sb88028 MOV j SIMB ECCS Si8821B. MOV 4
SiHB ECCS- 6188210 MOV SlHB ECCS SI8923B MOV
! SlHB ECCS StPIB MOP SWPAC EP SW 102C MOV
]
4 j SWPAC EP MCC1A5. MCC SWPAC SW SW.102 A MOV 4
i' SWPAC SW SW 102C- MOV-I I \ SWPAC SW SW PI A MOP '
SWPAC SW SW PIC MOP SWPB0 EP- SW.1020 -- MOV SWPB0 EP MCC 185 MCC' I
SWPBO SW SW 1028 MOV SWPBD SW- SW.1020 MOV
i l
i i
l l
)
1 87 1/W
. . . . - _ _ . . - . . - . . . . . _ . , . . _ . . . _ . . , , _ . - . . . , _ , - . - ~ - . . . _ - . - - . . . . .
Niillstone 3 fs 5. BIBLIOGRAPilY FOR MILLSTONE 3
'()\'
l NUREG-1031, " Safety Evaluation Report Related to the Operation of Niillstone Nuclear Power Station, Unit No. 3," USNRC.
- 2. NUREG 1064, " Final Environmental Statement Related to the Operation of Niillstone Nuclear Power Station, Unit No. 3," USNRC, December 1984.
- 3. NUREG ll52, "htillstone 3 Risk Evaluation Report," USNRC, June 1986 4 NUREG 1176, " Technical Specifications for hiillstone Nuclear Power Station, Unit 3," USNRC.
- 5. NUREG/CR 4142, "A Review of the hiillstone 3 Probabilistic Safety Study," Lawrence Livermore National Laboratory, April 1986.
- 6. NUREG/CR-4143, " Review and Evaluation of the Stillstone Unit 3 Probabilistic Safety Study," Brookhaven National Laboratory, September 1985.
G o
V '
88 1/89
Millstone 3 APPENDIX A 4
O. DEFINITION OF SYMilOLS USED IN Tile SYSTEM AND LAYOUT DRAWINGS A 1. SYSTEM DRAWINGS A 1,1 Fluid System Drawings The simplified system drawings are accurate representations of the major now ,
paths in a system and the important interfaces with other Guid systems. As a general rule, small fluid lines that are not essential to the basic operation of the s these drawings. Lines of this type include instrumentation vent lines,ystem lines, drain arelines, not shown in and other lines that are less than 1/3 the diameter of the connecting major flow path. There usually are two versions of each fluid system drawing; a simplified system drawing, and a comparable drawing showing component locations. The drawing conventions used in the Guld 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.
Hodzontal lines always dominate and break venical lines,
~g Component symbols used in the fluid system drawings are defined in Figure l j A 1.
Most valve and pump symbols are designed to allow- the reader to distinguish among sim,ilar components based on.their support system.
requirements (i.e., electric power for a motor or solenoid, steam to drive a l turbine, pneumatic or hydraulic 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 (i.e., as a globe, gate, butterfly, or other specific type
. . 4 Pump symbols distinguish between centrifugal and positive displacement pumps and between types of pump drives (i.e., motor, turbine, or engine). a Locations are identified in terms of plant location codes defined in Section 4 of this Sourcebook.
l Location is 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.
Piping locations between discrete components represent the plant-areas-through which the pi underground pipe runs). ping passes- (i.e. including pipe tunnels and Component locations.that are not.known are indicated by, placing the components in an unshaded (white) zone, i i , -
The primary flogy path in the system is highlighted (i.e., bold white line) in the location version of the fluid system drawings.
. 89. 1/89 .
.,, . ,,,,_.m.,-, . , . . . . . , _ . . . . _ _ , . _ . . ,-_._,..,,,,m,_..,,_ + - ,,_, _ , ,
.~ . . . _ _ _ . _ _ _ . _ _ _ . . _ _ _ . . _ _ ___.. _ _ _ _
Millstone 3 A l.2 Electrical System Drawings The electric power system drawings focus on the Class lE portions of the plant's electric power system. Separate drawings are provided for the AC and DC portions of the Class 1E system. There of ten are two versions of each electrical system drawing; a simplified system drawing, and a comparable drawing showing component locations. The drawing conventions used in the electrical system drawings are the following:
Flow generally is top to bottom In the AC power drawings, the interface with the switchyard and/or offsite grid is shown at the top of the drawing.
In the DC power drawings, the batteries and the interface with 'the AC power system are shown at the top of the drawing.
Vertical lines dominate and break horizontal lines.
Component symbols used in the electrical system drawings are defined in Figure A 2.
Locations ae identified in terms of plant location codes defined in Section 4 of this Sourcebook.
Locations are indicated by shaded " zones" that are not intended to represent the actual room geometry.
Locations of discrete components represent the actual physical location of the component.
The electrical connections (i.e., cable runs) between discrete components, as shown on the electrical system drawings, DO NOT represent the actual cable routing in the plant.
Component locations that are not known-are indicated by placing the discrete components in an unshaded (white) zone.
A 2, SITE AND LAYOUT DRAWINGS A 2.1 Site Drawings A general view of each reactor site and vicinay is presented along with a simplified site plan showing the arrangement of the major buildings,- tanks, and other .
features of the site. The general view of the reactor site is obtained from ORNL NSIC 55 (Ref,1). The site drawings are approximately to scale, but should not be used to estimate:
distances on the site. As built scale drawings should be consulted for this purpose.
Labels printed in bold uppercase correspond to the location codes defined in- -
Section 4 and used in the component data listings and system drawings in Section 3. Some additionallabels are included for information and are pnnted in lowercase type.
A2,2 Layout Drawings Simplified building layout drawings are developed for the portions of the plant -
that contain components and systems that are described in Section 3 of this Sourcebook.
! Generally, the following buildings are included: reactor building, auxiliary building, fuel building, diesel building, and the intake structure or pumphouse. - Layout drawings generally are not developed for other buildings.
Symbols used in the simplified layout drawings are defined in Figure A-3.
[ Major rooms, stairways, elevators, and doorways are shown in the simplified _ layout.
drawings however, many interior walls have been omitted for clarity. The building layout 90 1/89 3
_ _ m. . _ , , , _ , . , _ _ _ . - _ , , ..,_..m_,_ -mm.,,__._,,,_y,_m,_,,-,,-,,m..-..-, .,,,...,
id j
.\lillstone 3 l drawings, are approximately to scale, should not be used to estimate room size or i distances. As-built scale drawings for should be consulted his purpose.
Labels printed in uppercase bolded also correspond to the location codes j
defined in Section 4 and used in the component data listings and system drawings in l Section 3. Some additionallabels are included for infom1ation and are printed in lowercase !
- type.
- A3, APPENDIX A REFERENCES
- 1. Heddleson, F.A., " Design Data and Safety Features of Commercial Nuclear Power Plants.", ORNL-NSIC 55, Volumes 1 to 4, Oak Ridge National Laboratory, Nuclear Safety Information Center, December 1973 (Vol.1), t
! January 1972 (Vol. 2), Apnl 1974 (Vol. 3), and March 1975 (Vol. 4) l t
I l
4 f
i l
l l
l t
91 1/89
.. - - - . ~ . . .. ...- - .. . . ..-- . . . - . . . . . _ . . . . . ... . . _ . . . . . .- .
l l
_ LJ MANUAL VALVE XV
__ __ F' - % L_ L MANUAL NON RETURN (O P E N IC LO S E D)
VALVE . XCV (OPEN CLOSED) o MOTOR CPER ATED YALVg . eACV -
Q MOTOR OPER ATED (OPEN 'LOSED) 3 WAY V ALVE . MOV (CLOSED PORT MAY V ARY)
L'J
[ .
_ SOLENOl0 CPER ATED VALVE . 80V -
SOLEN 0ID CPER ATED F'
(OPENICLOSED) - -
3 W AY V ALVE 50V l (CLOSED PORT MAY V ARY)
_ _ HYDR AULIC V ALVE HV HYDR AULIC NolJ. RETURN (OPEN+ CLOSED)
VALVE . HCV (OPEN. CLOSED) 2
- PNEUMATIC VALVE = NV L PN'EUMATIC NON RETURN F'
(OPENiCLOSED)
VALVE . NCV (OPEN CLOSED)
_ CHECK VALVE CV S AFETY VALVE SV (CLOSED)
U V O POWER OPER ATED RELIEF VALVE, M POWER.CPER ATED RELIEF VALVE, SQLEN0lD PILOT TYPE . PORY d (CLo SED)
PNEUMATICALLY OPERATED . PORV oR .
DUAL. FUNCTION -- S AFETY RELIEF VALVE =SRV-(CLO SED) -
b CENTRIFUGAL CENTRIFUG AL MOTOR ORIVEN PUMP . MDP TURBINE.ORIVEN PUMP . TOP -
\ /
I
~ POSITIVE DISPL ACEMENT .
MOTOR. DRIVEN PUMP . MDP - POSITIVE DISPLACEMENT TUSSINE. DRIVEN PVMP TDP l
\ /
I Figure A-1. Key To Symbols in Fiald System Drawings 92 1/89
,,--r, ,-p.- , -. , .-r.. y y .m-., ,,..-.v- . . ~ . - , , . - . ,_.a+,.m.-s, , , , , . ~ . , - - , ,.
I .
PWRBWR M AIN CONDENSER = COND RE ACTOR vtSSEL . RV O w J 1
- - HE AT EXCHANGER . HX MECH ANIC AL DR AFT
. a .
COOLING TOWER 9 l 1
STE AM.TO W ATER OR W ATER TO STE AM HEAT h
~ ~ "
AIR COQ (ING UNIT ACU EXCH ANGER (LE. FEEDW ATER
_g}__ oR,,,CE . R
. Figure A-1, Key To Symbols in Fluid System Drawings (Continued)
'93 t/89 e _ - _ __-____ _ - _.
--. . - . - . . . . ~ - - . . - . . . - - . , ~ . , _ . . - . . ~ , . . - - . . . . . . . . . . . - . . . - . . . . _ _ . - - . _ . ~ . . . - . , . . . - -- --..-. _
-j A C. DIESEL CENER ATOR , DO CR A C. TUR8lhE OENER ATCR ,10 [ D ATTERY + B ATT OR I CIRCUIT BRE AKER
- C8 I i g g l 3....g on- g...l) INTERLOCKED (OPEN CLOSED)
CIRCulf BREAKERS
MANUAL TR ANSFER SwifCH e MTS f SWITCH 0E AR BUS
- BUS
[IBUS NAME l M TOR CONTROL CENTER . MCC
" oR D ".- " " TR ANSFORMER TR AN .
l CR ,.,
I - DISTRIBUTION P ANEL
- PNL .~
l B ATTERY CH AROER (RECTIFIER) , BC -
SZ '( < ERTER
- INV I
1 l
l !
I OR ". RELAY CONTACTS FUSE =FS (OPEN' CLOSED) .
f.
, EtEcTRiC MoToa "ta
- motor cutR AToR . Ma Figure A-2. Key To Symbols in Electrical System Drawings 94~ .1/89 L
D I -1 STAIRS Y D = Down g SPIRAL STAIRCASE i
LADDER =r j
C' U = Up D = Down {=lll ELEVATOR
=
p HATCH OR OPEN AREA GRATING DECK (NO FLOOR)
-O- PERSONNEL DOOR H WEQUIPMENT DOOR F
$ RAILROAD TRACKS :<
FENCE LINE E
O TANK / WATER AREA Figure A-3. Key To Symbols in Facility Layout Drawings D
95 1/89 1
_ _ _ _ _ . . , . . . . . . . . '" ~ ~ ~ ~
Niillstone 3 APPENDIN 11 DLFINITION OF TER.\lS USED IN Tile DATA TOLES Terms appearing in the data tables in Sections 3 and 4 of this Sourcebook are denned as follows:
SYSTI31 olso LOAD SYSTEhD All components associated with a particular system dewription in the Sourcebook have the same system code in the data base. System codes used in thn Sourcebook are the following:
Gyk Dennition RCS Reactor Coolant System Alv .\uxiliary Feedwater System ECCS Emergelicy Core Cooling System (including HPSI and i
LPSD _
! PAllRS Containment lleat Remow 1 Systems
! CVCS Charging System
! EP Electric Power System i
SW Service Water System CO.\lPONENT ID (also LOAD COhlPONENT ID) The component identification (ID) code in a data table matches the component ID that appears in the corresponding system drawing. The component ID generally begins with a system preface fol! awed by a component number. The system preface is not necessarily the same as the system code desenbed above. For component ids, the system preface corresponds to what the plant calls the component (e.g. HP!, RHR), An example is HPI 730, derating valve number 730 in the high pressure injection system, which is part of the ECCS. The component number is a contraction of the com3onent number appearing in the plant piping and instrumentation drawings (P&lDs) anc electrical one line system drawings.
I LOCATION (also COhiPONENT LOCATION and POWER SOURCE LOCATION) -
Refer to the location codes defined in Section 4.
CO.\lPONENT TYPE (COhlP T'.PE) Refer to Table B 1 for a list of component type codes.
! POWER SOURCE The component ID of the power source is listed in this field (see COMPONENT ID, above). In this data base, a " power source" for a particular component ti.e. a load or a distribution component) is the next higher electrical distribution or generating component in a distribution system. A single component may have more than one power source (i.e. a DC bus powered from a battety and a battery charger).
POWER SOURCE VOLTAGE (also VOLTAGE) The voltage "seen" oy a load of a power source is entered in this field. The downstream (output) voltage of a transformer, mverter, or battery charger is used.
E.\lERGENCY LOAD GROUP (Eh1 ERG LOAD GROUP) AC and DC load groups (or electrical divisions) are defined as appropriate to the alant. Generally, AC load groups are identified as AC/A, AC/B, etc. The emergency loac group for a third-of a kind load (i.e. a " swing" load) that can bc ,,owered from either of two AC Inad groups would be identified as AC/AB. DCload group follows similar naming convenuons.
96 1/89
TAllLE 11 1. COhlPONENT TYPE CODES i
(fq)1PnNi?NT cn\1P TYPIC VALVES:
hiotor operated valve h10V Pneumatic (air operated) valve NV or AOV i
llydraulic valve fly Solenoid operated valve SOY hianual valve XV Check valve CV Pneumatic non return valve NCV liydraulic non return valve IICV Safety valve SV Dual' function safety / relief valve SRV Power operated relief v0 e PORV (pneumatic or solenoid operated)
PUh1PS:
hiotor driven pump (centrifugal er PD) \tDP Turbine driven pump (centrifugal of PD) SP Diesel driven pump (centrifugal of PD) GDP OTHER FLUID SYSTEN! COh1PONENTS:
Reactor vessel RV Steam generator (U tube oronce through) SG
' lhat exchanger (water to water llX, 11X or water to air IIX)
Cooling tower CT Tank TANK or TK Sump SUhiP Rupture disk RD Onfice ORIF Filter or strairer FLT Spray noz2le SN lleaters (i.e pressurizer heaters) IITR VENTILATION SYSTEh! COhiPONENTS:
Fan (motor driven, any type) FAN Air cooling unit (air-to water HX, usually ACU or FCU including a fan)
Condensing (air-conditioning) unie COND EhiERGENCY POWER SOURCES:
Diesel generator DG Gas turbine generator GT Battery BA'IT b
l 97 1/89 l
TAllLE B l. COMPONENT TYPE CODES it:ontinued)
C0 \lPO WENT Co\1PTYPE ELECTRIC POWER DISTRIBUTION EQUIP.\ LENT:
Bus or switchgear BUS Motor control center htCC Distribution panel or cabinet Transfonner PNLorCAB Battery charger (tectiner) TRAN or XFMR Inverter BC or RECT INV Uninterruptible power supply (a unit that c..'v UPS include battery, battery charger, and invenei s Motor generator Circuit breaker MG CB Switch SW Automatic transfer switch ATS Manual transfer switch MTS 98 liN9
___ _ - _ _ _ _ - _ _ - _ - - - - - -