ML20070Q775: Difference between revisions
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| number = ML20070Q775 | | number = ML20070Q775 | ||
| issue date = 12/31/1988 | | issue date = 12/31/1988 | ||
| title = Nuclear Power Plant Sys Sourcebook,Palo Verde 1 & 2 | | title = Nuclear Power Plant Sys Sourcebook,Palo Verde 1 & 2 | ||
| author name = Lobner P, Saylor P | | author name = Lobner P, Saylor P | ||
| author affiliation = SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY | | author affiliation = SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY | ||
Latest revision as of 22:18, 23 May 2020
| ML20070Q775 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/31/1988 |
| From: | Lobner P, Saylor P SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
| To: | NRC |
| References | |
| CON-FIN-D-1763, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-88-1017, NUDOCS 9103290175 | |
| Download: ML20070Q775 (106) | |
Text
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l PALO VERDE 1, 2 and 3 50 528, 5o.529, ana 30 53o l 4 li i M u p r m = PDRu,
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PALO VERDE 1, 2 and 3 50 528, 50 529, and 50 530 Editor: Peter Lobner Author: Patricia Saylor O Prepared for: U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Contract NRC 03 87 029 FIN D 1763 O M , c .. _ ______ _ _-__ _____ __ __- ___ _ - _ _ -_ _
Palo Verda 1,2 & 3 I . TAlli.E OF CONTENTS (Q. Sminq g I 1 S U h th tA R Y DATA ON PLANT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1.
.! IDENTIFICATION OF S!h11LAR NUCLEAR POWER PLANTS ..., 1 3 S Y STEM I NFORhi ATI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .2. . . . .
3.1 Reactor Coolant Syste m (RCS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3.2 Auxiliary Fcedwater System (AIAVS) and Secondary S te am R elief S yste m (S S R S)..... ........ ...................... 13 , 3.3 Emergency Core Cooling System (ECCS) ................... 19 3.4 Charging System (CVCS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 3.5 Instrumentation and Control (I & C) Systems................ 36 3.6 Electrie Powe r Syste m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 3,7 Essential Cooling Water System (ECWS) .................... 54 3.8 Essential Spray Pond System (ESPS)......................... 58 4 PLA NT IN FOR h1ATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 ......... 4.I Site and B uildin g S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 4.2 Facility Layout Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 O 5 BIB LIOG RAPHY FOR PA LO VERDE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .88 .... V APPENDIX A Definition of S and Layout Drawings..........ymbols Ur:d in the System
.......................................... ... 89 APPENDIX B Definition of Terms Used in the Data Tabl:s ............ 96 l
i I l
,n 1
1- t,
- i. 12/88
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Palo Verde 1,2 & 3 i LIST OF FIGURES Fiture P. age
.1 Cooling Water Systema Functioma Diagram for Palo Verde 1, 2, and3....................................................................... 6 3.1 1 Elevation View of the RCS of a Typical Ct dustion Engineering P1 ant.......................................................................... 9 3.1-2 Palo Verde 1, 2 and 3 Reactor Coolant System...................... ...... 10 3.1-3 Palo Verde 1,2 and 3 Reactor Coolant System Showing Compuxnt Loca ti on s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 3.2 1 Palo Verde 1, 2 and 3 Auxiliary Fe,;dwater System........................ 16 3.2 2 Palo Verde 1,2 and 3 Auxiliary Feedwater System Showing Component Locations.......................................................,.. 17 3.3-1 Palo Wrde 1,2 and 3 High Pressure Safety Injection System .. ........ 22 3.3-2 Pak Verde 1,2 and 3 High Pressure Safety Injection System i
Showing Component Locatic u ............................................ 23 h
%/
3.3 3 Palo Verde 1. 2 and 3 Low Pressure Safet Spray Systems...............................y injection and Containment
.................. ................ 24 3.3-4 Palo Verde 1,2 and 3 Low Pressu e Enfety Injection and Containment Spray Systems Showing Component Locations............................ 2$
3.4 1 Palo Verde 1,2 and 3 Chemical and Volume Control System....,....... 29 3.4 2 Palo Verde 1,2 and 3 Chemical and Volume Control System Showing Component Locations.......................................................... 32 341 Palo Verde 1, 2 and 3 Electric Power System .............................. 43 ( 3.6-2 Palo Verde 1,2 and 3 Electric Power System Showing Component Loc a ti on s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.7 1 Pulo Verac 2 and 3 Essential Cooling Water System (Train A) ....... 56 3.7-2 Palo Verde 1,2 and 3 Essential Cooling Water System (Train B) ....... 57 3.8 1 Palo Verde 1,2 and 3 Essential S Train B) . . . . . . . . . .. . . . . . . . . . . . . . . . . . pray Pond System (Train A and
.......................s.................. 60 3.8-2 Palo Verde 1,2 and 3 Essential Spray Pond System (Train A and Train B) Showing Component Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 4-1 Plot Plan for Palo Verde Nuclear Generating System..................... 64 ii. 12/88
Palo Verde l,2 & 31 LIST OF FIGURES (continuM) 1 Figure P.agg 44 Palo Verde Site Generat Arrangement (Power Block Site Plan)......... 65 43 .,i .fified Arrangement Drawing for a Single 'Jnit at the Palo Verde S ite iTs ical for U nits I , 2 and 3) . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . 66 44 Elevai. B uiluin g at Palo . . Verde View . . . .of
. . . .the
. . . . . Containment,
. . . . . . . . . . . . . . . . . . . . . Auxiliary
. . . . . . . . . . . . . .Building
........ and Radwaste- . 67 45 Elevation View of the Containment and Fuel Buildin Turbine Building at Palo Verde.........................gs and Partial
..'................... 68 46 Elevation View of the Control and Diesel Generator Buildings at Palo Verde..................................................................... 69 4-7 Palo Verde Power Block (Except Turbine Building),40 ft. Elevation.. 70' 4-8 Palo Verde Power Block (Exce Elevatton.........................pt Turbine Building),51 ft ,6 in.
............................................... -71 49 Palo Verde Power Block (Except Turbine Building),80 ft, Elevation., _72 4 10 Palo Verde Power Block (Except Turbine Building),88 ft, Elevation.. 73 4-11 Palo Verde Power Block (Except Turbine Building),100 ft. Elevation (G rad e Le vel) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .74- .....................
-4 12- Palo Verde Power Block (Except Turbine Building),l120 ft.~
Eleyatton........................................................................ 75 _ 4-13 Palo Verde Poo:r Block (Except Turbine Building),140 ft. t Eleyat10n.......................,................................................ 176- , 4 14 Palo Verde Power Block (Except Turbine Building),-160 ft. Eleyatton........................................................................ :77-4-15 Palo Verde Power Block (Except Turbine Building), Roof............... c 78 - l A-1 Key to -Symbols - in Fluid ' System Drawings..... ........................... 92~ . A-2 - Key to Symbols in Electrical System Drawings.......... .......... ...... 94 ~ . . A-3 h.ey to Symbol's in Facility Layout Drawings............'................... , 95
.w iii. _12/88
Palo Verde 1,2 & 3 LIST OF TAllLES J Iabh Eau 3-1 Summary of Palo Verde 1,2, & 3 Systems Covered in this Report..... 3 3.1 1 Palo Verde Reactor Coolant System Data Summary for Summary Components.................................................................... 12 3.2-1 Nlo Verde Auxiliary Feedwater System Data Summary for Selected Components..................................................................... I8 3.3 1 Palo Verde Emergency Core Cooling System Data Summary for S ele c te d Com po ne n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 3.4-1 Fuio Verde Charging System Data Summary for Selected Components, 35 3.5 1 Controls Available on the Palo Verde Remote Shutdown Panels......... 39
?.6 i Palo Verde Elecuic Power System Data Summary for Selected Components..................................................................... 47 3.6 2 Partial Listing of Electrical Sources and Loads at Palo Verde 1,2 & 3. . 50 3.8 1 Palo Verde Essential Spray Pond System Data Summary for S e le c t ed Com po ne n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 d 4-1 Definition of Palo Verde 1,2 and 3 Building and Location Codes....... 79 42 Partial Listing of Components by Location at Palo Verde 1,2 & 3...... ' 83 B-1 Compone nt Type Codes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 97
{ iv. 12/88
~ - _ _ _ - _ _ . . . _. - -
Palo Verde 1,2 & 3 C\ CA L"" ION The information in this report has 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 knowledge, it accurately reflects the plant configuration at the time the information was obtained, however, the information in this document has not been ind:: pendently verified by the licensee or the NRC. NOTICE This sourcebook will be periodically updated with new and/or replacement pages as appropriate to incorporate additionalinformation on this reactor plant. Techmcal errors in this report should be brought to the attention of the following: Mr. Mark Rubin U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation O Division of Engineering and Systems Technology Mail stop 7E4 Washington, D.C. 20555 With copy to: Mr. Peter Lobner Manager, Systems Engineering Division Science Applintions International Corporation 10210 Campus Point Drive San Diego,CA 92131 (619)458 2673 Correction and other recommended changes should be submitted in the form of marked up copies of the affected text, tables or figures. Supporting documentation should be included if possible.
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- v. 12/88 i
PALO VERDE RECORD OF REVISIONS < REVISION ISSUE COMMENTS 0 12/88 Original report O . N O vi. 12/88
I Palo Verde 1,2, & 3 p PALO VERDE 1, 2, & 3 SYSTEM SOURCEllOOK
\v)
This sourcebook contains summary infom1ation on Palo Verde. Summary data on this plant are presented in Section 1, and similar nuclear power plants are identified in Section 2. Information on selected reactor plant systems is presented in Section 3, and the site and building layout is illustrated ia Section 4. A bibliography of reports that describe features of this plant or site is presented in Section 5. Symbol used in the system and layout drawings are defined in Appendix A. Teiins use(in :he data tables are defined in Appendix B. I,
SUMMARY
DATA ON PLANT Basic information on the Palo Verde 1,2, and 3 nuclear power plants are listed below: Docket number 50-528 (1),50 529 (2),50 530 (3) Operator Arizona Public Service Company Location Wintersburg, Arizona Commercial operation aate 1/86 (Unit 1),9/86 (Unit 2),1/88 (Unit 3) Reactor type PWR NSSS vendor Combustion Engineering, Inc. Number of loops 2 Power (MWt/MWe) 3800/1270 Architect engineer Bechtel Containment type Reinforced concrete cylinder with steel g hner 2, IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS Palo Ve 1 1,2, and 3 are the only pressurized water reactor plants to utilize Combustion Engi > ring's System 80 steam supply system. Other Combustion Engineering tyy P R plants in the United States include: Fort Calhoun Maine Yankee Palisades Millstone 2 Calvert Cliffs 1 & 2 St. Lucie 1 & 2 ANO 2 San Onofre2 & 3 Waterford 3 WNP3 Palo Verde differs from other Combustion Engineering plants in that it uses two independent Seismic Category I essential spray ponds (ESP) per, unit as the ultimate heat sink. These ponds are part of the Essential Spray Pond System (ESPS) which is used dt ring normal shutdown or during accident conditions. A) v i 12/88
l Palo Verde 1,2, & 3 p 3. SYSTI'.M INFORM ATION This section contair,s descriptions of selected systems at Palo Verde in terms of general function, operation, sptem success criteria, major components, and support system requirements. A summary or c ajor systems at the Palo Verde is presentea in Table 3-1. In the " Report Section" column cf this table a section reference (i.e. 3.1,3.2, etc.) is provided for all systems that are described in this report, An entry of "X" in this column means that the system is not described in this report. In the "FSAR Section Reference" column, a cross reference is provided to the section of the Final Safety Analysis Report where additional information on each system can be found. Other sources ofinformation on this plant are identified in the bibliography in Section 5. Several cooling water systems are identified in Table 31. The functional relationships that exist among cooling water systems required for safe shutdown are shown in Figure 31. Details on the individual cooling water systems are provided in the report sections identified in Table 31, ~ G l V) (~s O
- 2. 12/88
Table 3-1. Summary of Palo Verde I, 2, & 3 Systems Covered in this Report Generic Plant-Specific Report FSAR Section System Name System Name Section Reference Reactor lleat Removal Systems
- ReactorCoolant System (RCS) - Same 3.I 5
- Auxiliary Feedwater(AFW) and Same 3.2 10.4.9 Secondary Steam Relief (SSR)
Systems Emergency Core Cooling Systems I (ECCS)
- IIigh-Pressure Injection Same 3.3 6.3
& Recirculation
- - Low-pressure Injection Same 3.3 6.3
& Recirculation u
Decay IIeat Removal (DIIR) Same 3.3 5.4.7. 5.5.7* f- . System (ResidualIIeat Removal (RI1R) System)
- Main Steam and Power Conversion Main Steam Supply System, 'X 10 Systems Circulating Water System.
Condensate and Feedwater System ..
- Otherlleat Removal Systems - None identified X l
Reactor Coolant Inventory Control. Systems !
- Chemicaland Volume ControlSystem Same 3.4 9.3.4
-(CVCS)(Charging System)
See ECCS,above
.ECCS - -
12
$ .
- Reference is from System 80 PSAR CESSAR, Combustion Engineering.
.m. - :-.- . . - - --
g' ,. t--- Table 3-I. Summary of Palo Verde 1, 2, & 3 Systems Covered in this Report (Continued) Generic Plant-Specific Report FSAR Section System Name System Name Section Reference Containment Systems
- Containment Sane' X 6.2 Containment Ileat Removal Systems.
- Containment Spray System Same X 6.2.2.1, 6.5.2.
- Containment Fan CoolerSystem . None identified X X
- Containment Nonnal Ventilation Systems , Noneidentified X X l -
Combustible Gas Control Systems Containment flydrogen Control '- X 6.2.5 l System 4 Reactor and ~. Reactivity Control Systems
- Reactor Core Same '- X 4
- Control Rod System Control Element Drive X 4
. Mechanisms (CEDMs)
Boration Systems - . See CVCS, above - -- Instrumentatiori & Control (I&C) Systems . .
- ' Reactor Protection System (RPS) -' 'Same:
3.5 7.2
- . Engineered Safety Feature Actuation - Same- 3.5 7.3 System (ESFAS)
-' Remote Shutdown System . Local Control Panels - 3.5 - 7.4 u
CC 00
._ . _ _ . . .~.- --. .-
TN O Table 3-1. Summary of Palo Verde 1, 2, & 3 Systems Covered in this Report (Continued) Generic - Plant-Specific Report FSAR Section System Name = System Name Section ILeference Instrumentation & Control (I&C) Systems (continued)
-- OtherI&C Systems Various Systems X 7.6,7.7 Support Systems Class IE Electric PowerSystem 'Same 3.6 8.2,8.3 Non-Class IE Electric Power System Sane. 3.6 8.2,8.3
- . Diesel Generator Auxiliary Systems Same- 3.6 8.3, 9.5.4. 9.5.5, 9.5.6, 9.5.7. 9.5.8
- Component Cooling Water (CCW) Essential Cooling WaterSystem 3.7 9.2.2 System u
Service Water System (SWS) Essential Spray Pond System 3.8 9.2.1
- Other Cooling Water Systems Nuclear Cooling WaterSystem, . X 9 2.2
' Turbine Cooling Water System, Chilled Water System,-
Plant Cooling Water System Fire Protection Systems . Same X 9.5.1 Room IIcating, Ventilating, and Air- Air Conditioning Ileating, Cooling X 9.4 Conditioning (IIVAC) Systems and Ventilation System
- Instmment and Service AirSystems -- Compressed AirSystem X 9.3 I Refueling and Spent Fuel Systems Same ' X .. 9.1 t'
88 - Radioactive Waste Systems Same X 11 Radiation Protection Systems - Same X :2
i i ESSENTIAL
--> CHILLED WATER ,
i SYSTEM ! L J t
- i.
I SHUTDOWN -
---> ECWS > COOLING HEAT EXCHANGER i w J t J A l r 3 V
- r 3L r 3
- ECWS HEAT ESSENTIAL
[ --> ESPS & EXCHANGERS- > SPRAY f ( j q. j POND l l . r . 3 L J DIESEL i
, GENERATORS t J
.i ECWS - Essental Chi!!ed water System
_ ESPS -. Emeigency Spray Pond System ; M' i E . 1 Figure 3-1. ' Cooling Water Systems Functional Diagram for Palo Verde 1,2 and 3 s
. . , . _ .._.e., _
- . - - - - ~ . . - - -.-. - -. _ . . . . - - - - . . . - - . -.
1 Palo Verde 1,2, & 3 - 3.1 REACTOR COOLANT SYSTEM (RCS) 3.1.1 System Function The RCS transt'ers heat from the reactor core to the secondary coolant system via the steam generators. The RCS pressure boundary also establishes a boundary a' gainst ! the uncontrolled release of radioacuve material from the reactor core and priman coolant. i 1 3,1,2 System Definition The RCS includes: (a) the reactor vessel, (b) two parallel reactor coolant loops, each containing one steam generator and two reactor coolant pumps, (c) a pressurizer connected to one of the reactor vessel outlet pipes. and (d) associated piping out to a-suitable isolation valve boundary. An elevation view of a two;1oop Combustion Engineering RCS is shown in Figure 3.1 1. Simplified diagrams of the RCS and important system interfaces are shown in Figures 3.1-2 and 3.13. A summary of data on selected RCS components is presented in Table 3.1-1. 3.1.3 System Oneration
- During power operation, circulation in the RCS is maintained by two reactor 1 coolant pumps in each of the two reactor coolant loops. RCS pressure is maintained within a prescribed band by the combined action of pressurizer heaters and pressurizer spray, RCS coolant inventory is measured by pressurizer water level which is maintained within a prescribed band by the chemical and volume control system (CVCS).
At power, core heat is transferred to secondary coolant (feedwater) in the steam generators. The heat transfer path to the ultimate heat sink is completed by the main steam and pown conversion system and the circulating water system. i Following a transient or small LOCA (if RCS inventory is maintained), reactor core heat is still transferred to secondary coolant in the steam generators. Flow in the RCS ( is maintained by the reactor coolant pumps or by natural circulation. The heat transfer path to the ultimate heat sink can be established by using the secondary steam relief system 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 reactor drain tank through the pressurizer relief valves. There , are four simple spring loaded safety valves on the pressurizer. , Following a large LOCA, reactor core he t is dumped to the containment'as reactor coolant and ECCS makeup water spills from the break. For a short 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. 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 LOCA-is initiated, then LOCA mitigating systems are successful. If a transient is initiated, then either: RCS integrity is maintained and transient mitigating systems are successful, . or . RCS integrity is not maintained, leading to a LOCA like condition-(i.e. stuck open safety or relief valve, reactor coolant pump seal failure), and . LOCA mitigating systems are successful. 7 12/88
Palo Verde 1. 2, & 3 - 3.1.5 Comnonent Information A. RCS
- 1. Volume: 11,643 ft3 (without pressurizer)
- 2. Normal operating pressure: 2235 psig B. Pressurizer
- 1. Volume: 1800 ft3 C. Reactor Coolant Pumps (4)-
'l. Rated flow 111.400 gpm
- 2. Type: Vertical Centrifugal D. Safety Valves (4)
- 1. Set pressure: 2485.2510 and 2535 psig
- 2. Relief capacity: 190,000lb/hr each E. Steam Generators
- 1. Type: U Tube with Integral Economizer -
F. Pressurizer Heaters
- 1. Capacity: Unknown
- 2. Type: Immersion-3.1.6 Sunnort Systems and intu toff,4 A. Motive Power - -
- 1. The reactor coolant pumps are supplied from Non-Class IE switchgear.
- 2. The pressurizer heaters are Ciass 1B ACloads that can be supplied from the standby diesel generators as describect in Section 3.7.
B. Reactor Coolant Pump Seal Injection Water System The chemical and volume contml system supplies seal water to cool the reactorL coolant pump shaft seals and to maintain a controlled inleakage of seal water into the RCS. Loss of seal water finw muy result in RCS leakage through the - pump shaft seals which will reser.ible n small LOCA. 4 8 -12/88
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RE ACTOR VESSEL a 4 is ~ s Figure 3.1-1. Elevation View of the RCS of a Typical Combustion
- Engineering Piant.
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i;L*J W 6 hth t P TO WI $vMo $v2C1 S V202 SV233 f i&J .P FHI M L P hJFCT4A M CTON M CT(m nJECTsDN IM M
X m := d:,, i' M32 FC TO TO $6eJTDOwM e ; swuToowg Caxao Comma LOOP 1A V240 ac ac \ LOOPHI C-X c,is gp ,4 V23? TOPZR RCP 29 W2 J! uvm vns v22s A uvu. WI V , , , x.m i . TO CVC 5 V134 Vt33 V123 V124 55eDM LP THOfJ ee FFsUnd er FRrm1P m,1CTON thuECTON M CTOs kJECTION Figure 3.1-2. Palo Verde 1, 2, & 3 Fleactor Coolant System l .A4 -,u ga _Js u4m e *, m a e a O se 3, s . Y Y = a I O E l 2 s h- - $- U h .tr e 3 0 ${ t g s5 E l E NE 0 D- ))} s Y F !$~ M--W OE! c % , i $! i is i i le $ WW1 ! g !j M- g = *e!l ! okj v fi ~ i . *g ! s e -- g fi en ,- a w $I$ - d G [ l\ : : $ 4 M !!! - - 3
- r. x x<>
~ o e. R \ 2 $.-se h i 1 '. y elj ,i $Y : !; ; 1; '9 ? . *a " s o ; a - !" 3 3 0-S6 s 5 -i ' g' !j ' M M- t2E H .M ok! = m 4 m %d , y" - 4 8 lj M- fi0 - 115 ji 3 .C v l l 11 12/88 s f% 0 % Table 3.1-1. Palo Verde Reactor Coolant System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VO LTAG E POWER SOURCE EMERG. TYPE LOCATION LOAD GRP CH515 NCV RC CHS16. NCV RC RCS-VESSEL RV RC RHR651 MOV HC MCC35 480 WELPENRM120 ' AC/A RHR652 MOV RC MCC36 480 EELPENRM100 AC/B RHR653 MOV. RC LC43 125 DCC DCC ! RHR654 MOV RC- LC44 125 DCD DC1) C R OC I . , . . . . .. . . . . . . . . . . . . . . t_ _ Palo Verde 1,2, & 3 3.2 AUXILIARY FEEDWATER SYSTESI -( A FWS) AND SECONDARY STEAM RELIEF SYSTEM (SSRS)
- 3. 2.1 - System Function The ARVS provides an independent means of supplying feedwater to the steam generators in addition to the main feedwater system. The AFWS is intended to provide a t sufficient supply of feedwater to permit the plant to operate at hot standby after a transient or small break LOCA for eight hours followed by an orderly plant cooldown to the point where the shutdown cooling system may be initiated. The Secondary Steam Relief System (SSRS) provides a steam vent path from the steam generators to the atmosphere, thereby completing the heat transfer path to an ultimate heat sink when the main steam and power conversion systems are not available. The ARVS and SSRS constitute an open loop fluid system that provides for heat transfer from the RCS following transients and small break LOCAs, 3.2.2 System Definition The AFWS consists of one safety related Seismic Category I motor driven .
pump, one safety related Seismic Category I steam turbine driven pump , one non safety related, non Seismic Category I motor-driven startup feedwater pump, associated piping, , controls and instrumentation. Each pump can supply both steam generators, The primary source of auxiliary feedwater is the Seismic Category I condensate storage tank (CST). The secondary or backup source of auxiliary feedwater is the reactor makeup water tank (RMWT). The SSRS consists of five safety valves and one pneumatically operated atmospheric dump valve on each of four main steam lines (two per steam generator). Simplified drawings of the AFWS and the~SSRS are shown in Figures 3.21 ' and 3.2-2. A summary of data on selected ARVS components is presented in Table 3.21. F 3.2.3 System Ooerallan During normal operation the ARVS is in standby until the system pumps are actuated by an Automatic Feedwater Actuation Sirnal (AFAS). This actuation signal automatically starts the motor and turbine driven ARVS pumps and pump room cooling . units, opens the ARVS feed regulating valves to the intact steam generator (s), and closes the steam generator blowdown isolation valves. Steam generator level is maintained automatically after inidation of the ARVS, After conditions stabilize, the operator has the capability of manually controlling the auxiliary feedwater flow. The primary source of auxiliary feedwater is the condensate storage tank. A minimum capacity of 195,000 the AFWS during emergency shutdown conditions. This provides gallons is required an orderly RCS coo by ldown to the shutdown cooling initiation conditions. An additional 105,000 gallons of condensate storage capacity-provides sufficient feedwater to maintain the plant at hot standby for eight hours, The startup feedwater pump is used for startup, hot standby, and normal shu down operations. This pum operated from the control room. p is manually started and associated valves are manua 3.2.4 System Success Criteria-For the decay heat removal function to be successful, both the ARV system and the SSR system must operate successfully. The AFW success criteria are me following (Ref. 1, Section 10.4.9): s, 13 12/88 -l" Palo Verde 1,2, & 3-I Any one AFW pump can provide adequate flow. - Water must be provided from the CST or RMWT to the AIAV pump suctions Q - Makeup to any one steam generator provides adequate decay heat removal from the reactor coolant system. The SSR system must operate to. complete the heat transfer path to the environment. The number of safety valves that must open for the decay heat removal function is not known. 1 3.2.5 Comnonent Information A. Motor-driven AFW pump
- 1. Rated flow: 750 gpm @ 3280 ft. head (1422 psid)
- 2. - Type: Centrifugal B. Turbine driven AFW pump
- 1. Rated flo.v: 875 gpm @ 3280 ft, head (1422 psid):
- 2. Type: Centrifugal-C. Motor-driven startup feedwater pump
- i. Rated flow: 875 gpm @ 2960 ft, head (1283 psid)
- 2. -Type: Centrifugal D. Condensate storage tank 1, Capacity: 300,000 gallons E. Reactor makeup water storage tank q 1. Capacity: 480,000 gallons k/
v 3.2,6 S.uggprt Systems and Interfaces A. Control Signals -- 1 Automatic The AFWS pumps are automatically actuated upon receipt of an . Auxiliary Feedwater Actuation Signal (AFAS) under the following conditions: Main steam line break Loss of main feedwater - Loss of offsite power Loss of all offsite/onsite AC power (TDP only) The AFAS appears to be capable of detecting conditions indicative of 4 main feedwater or main steam line breaks and isolating AFWS flow to ? - the affected steam generator.
- 2. Remote manual'-
The AFWS can be -operated- from the control room _or a remote shutdown station.
- 3. Manual The AFWS can be manually aligned to the alternate water source, the RMWT.
O 14 12/88'. 4 Palo Verde 1. 2. & 3 IL Motive power
- 1. The safety related motor driven AFWS pump and ARYS motor operated
,V valves receive Class lE loads that can be supplied from the standby diesel generators as described in Section 3.6.
- 2. The turbine driven pump is supplied with steam from the main steam lines of either steam generator upstream of the main stcam line isolation valves. The power and controls for the valves associated with this pump receive power from the Class IE DC buses A _nd C.
C. Other
- 1. Lubrication, coo!!ng and ventilation are provided locally for the pumps.
3.2.7 Section 3.2 References
- 1. Palo Verde Final Safety Analysis Report, Arizona Public Service Company, Phoenix, Arizona.
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O < O Table 3.2-1. Palo Verde Auxiliary Feedwater System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. 4 AFW-A-B TDP 80MSSSA AFW-B-B MDP 80MSSSB BUSSO4 4160 ESFB AC/B AFW134 MOV 100MSSSA LC41 125 DCA DC/A AFW138 MOV 100MSSSB LC41 125 DCA DC/A AFW30 MOV 80MSSSB MCC34 480 EELPENRM100 AC/B AFW30 MOV 80MSSSB MCC34 - 480 EELPENFU100 AC/B s AFW31 MOV SOMSSSB MCC34 480 EELPENRM100 AC/B AFW32 MOV 80MSSSA LC41 125 DCA DC/A - AFW33 MOV 80MSSSA LC43 125 DCC DC/A AFW33 MOV BOMSSSA LC43 125 DCC DC/A AFW34 MOV 80MSSSA MCC38 480 EELPENRM100 AC/B G- AFW34 MOV- 80MSSSA MCC38 480- EELPENRM100 AC/B AFW35 MOV 80MSSSB MCC38 480 EELPENRM100 AC/B AFW36 MOV 80MSSSA LC43 125 DCC CC/A AFW37 MOV 80MSSSB LC41 125 DCA DC/A AFW37 MOV- 80MSSSB LC41 125 DCA DC/A AFW54 MOV 80MSSSA LC41 125 DCA DC/A - CST TANK CST RMWT TANK RMWT ' SG-1 SG RC SG-2 SG RC T3 OC - '- -- - - ^ - - - ' - ' ~ - ' - " ' -,. ~ .- Palo Verde 1. 2. & 3 [] 3.3 EhlERGENCY CORE COOLING SYSTE51 (ECCS) U 3.3.1 System 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 j recirculation mode of operation to maintain long temt post LOCA core cooling. Heat from 1 the reactor core is transferred to the containment. The heat transfer path to the ultimate heat sink is completed by the containment spray system. 3.3.2 System Definition c The emergency coolant injection (ECI) function is performed by the following ECCS subsystems: Safety Injection Tanks High Pressure Safety Injection (HPSI) system (Train A and Train B) , Low Pressure Safety injection (LPSI) sysicm (Train A and Train B) The HPSI system provides the high pressure coolant injection capability, and the LPSI system perform the low pressure injection function. The Refueling Water Tank (RWT) is the water source for both the high and low pressure injection pumps. Simplified drawings of the HPSI system are shown in Figures 3.3-1 and 3.3 2. The LPSI system is shown in Figures 3.3 3 and 3.3 4. A summary f data on selected ECCS components is presented in Table 3.3-1. [ ( 3.3.3 System Goeration Dunng normal operation, the ECCS is in standby. Following a large LOCA, the ECCS meets short term cooling requirements nrimarily in two ways. Initially, the passive safety injection tanks discharge into the cold legs of the RCS to provide core cooling and refill when the reactor pressure falls below the tank pressure. Adequate fluid is contained in the safety injection tanks to accomplish this function with one tank discharging through the LOCA break. Secondly, each train containing one high pressure injection pump and one low pressure injection pump delivers borated makeup water from the RWT to the RCS. One ECCS train is capable of performing this short term cooling function with one of the injection flow paths discharging through the LOCA break. Long term core cooling is accomplished by recirculating water in the containment sump. The switchover from injection to recirculation occurs automatically upon reaching a preset level in the RWT, approximately 20 minutes following LOCA initiation. The ECCS is manu tlly realigned for long-term core cooling within 90 minutes following a LOCA by the initir. tion of hot leg injection. The ECCS may be aligned for simultaneous hot leg / cold leg injection which provides effective long-term core cooling independent of the large LOCA break locasion. This type of injection is accomplished by opening connections between the high pressure safety injection discharge headers and the two shutdown cooling suction lines. Decay heat is rejected to the containment atmosphere. Heat removal from the containment atmosphere is accomplished by the Containment Spray System and the shutdown cooling heat exchangers. For long term cooling of small breaks, the high pressure safety injection pumps provide make-up while the RCS is cooled down and depressurized to shutdown ecoling initiation conditions utilizing the steam generator atmospheric dump valves and the auxiliary (a G/ I feedwater system. This is followed by a normal shutdown cooling operation. 19 12/88 Palo Verde 1. 2, & 3 The shutdown cooling (residual heat removal) system operates when the RCS temperature and pressure are below 350 F and 40 psia espectively. This " system" is an operating mode of the LPSI system in which the pump suedons ete aligned to the RCS hot legs via the shutdown cooling suction lines, Reactor coclant is circulated through the shutdown cooling heat exchangers and is returned to the RCS through the four cold leg injection paths. Decay heat is transferred from the RCS to the essential cooling water system in the shutdown cooling heat exchangers. When the RCS temperature is below 200*F, the containment spray pumps can ! be realigned to provide additional shutdown cooling flow. 2 3.3,4 System Succeu Criteria LOCA mitigation requires that both the emergency coolant injection and emergency coolant rectreulation functions be accomplished. The ECl success criteria for a ' ; large LOCA are: Three of four safety injection tanks discharge their contents into the RCS cold legs - At least one low pressure safety injection pump takes suction on the RWT and : injects into the cold legs, If the ECI success criteria is met, then the following large LOCA ECR success criteria will. apply (Ref.1, Section 6.3): 1 At least one high pressure safety injection pump is realigned for recirculation and takes a suction on the containment sump and injects into the RCS cold legs. . The success criterion for a small LOCA is: \ - At least one high pressure safety injection pump takes suction on the RWT and' injects into the RCS cold legs. ; It should be noted that: H 1 The HPSI pump shutoff head is less than RCS normal operating pressure, therefore, a small LOCA must be of sufficient size to cause some RCS -depressurization, or the RCS must be depressurized by other means if the HPSI . pumps are to provide makeup. The'RCS may be cooled with operation of the . auxiliary feedwater system (see Section 3.2); Note that there are no_ power . operated relief valves on the pressurizer (see Section 3.1).- The combined capacity of the three positive displacement charging pumps (not part of the SIS) is 132 gpm (i.e. 44 gpm each). 3.3.S ' Comnonent Information + 4 A. High Pressure Safety injection pumps 1 and 2 -
- 1. Rated flow: 1130 gpm @ '1580 ft head (685 psid)
- 2. Rated capacity: 100 %
- 3. Type: multistage, horizontal, centrifugal B. Low Pressure Safety Injection pumps l'and 2
- 1. Rated flow: 5000 gpm @ 290 ft. head (126'psid)
- 2. Rated ca acity: 100 % ,
- 3. Type: S gle stage, vertical, centrifugal-v 20 12/88
Palo Verde 1,2, & 3 C. Containment Spray Pumps 1 and 2
- 1. Rated flow: 37'40 cpm O'Q 2. Rated Capacity:-ho?c D. Safety injectica Tanks (4)
- 1. Volume: 1927 ft3
- 2. Normal operating pressure: 610 psig E. Refueling water tank 1, Capacity: 600,000 gallons F. Shutdown cooling heat exchangers 1 and 2
- 1. Design duty: 43.8 x 106Btu /hr
- 2. Rated flow (gpm): 3890 (primary side),14,400 (ECWS side)
- 3. Type: shell and tube 3.3.6 Suncort Systems nnd Interfnces A. Control signals
- 1. Automatic The ECCS subsystems are automatically actuated by a saf.., injection actuation signal (SIAS) Conditio".s initiating an SIAS trip are:
Low pressurizer pressure High containment pressure Manual actuation O The SIAS automatically initiates the following actions: stans the HPSI and LPSI pumps aligns the pumps for injection aligns the pump suction to the RWT Switch over to the low pressure recirculation mode occurs automatically on low levelin the RWT.
- 2. Remote manual An SIAS signal can be initiated by remote manual means from the main control room. ECCS operation can be initiated by remote manualmeans.
B. Motive Power
- 1. All ECCS motor driven p amps and motor operated valves are Class iE AC loads that can be supplied from the standby diesel generators as described in Section 3.6.
C. Other ! . The shutdown cooling heat exchangers are cooled by the Essential Cooling Water System (see Section 3.7).
- 2. Lubrication is provided locally for the ECCS pumps and motors.
- 3. Pump rooin cooling is provided by the Essential Chilled Water System.
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i l 0 E z x i M H p - ~ ~ ~ l l oEl 0El l i a oEl 0El Ei f f:] I o l tj:t tf! tf! tIl j bi. _s 5 _ 8 bi. i !g tkB t+ i itki ! tii t+! ? til' ; . et . et i n. g3g i - >>s . [ t* _ ,,,, o,p:1 Et '8- - i E! J! off - ! 1 d:8 _ X. ~ q 1, I I u, i . .._,......, . ~ _ f--j=,,8I!y! *g== .. > ..... i s, 25 12/88 .~_ _m _ . _ - _ _ . ..-m. ._. __ _ _ _ _ _. - .- _ _ . . . . - _ . _ _ N Table 3.3-1. Palo Verde Emergency Core Cooling System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. l TYPE LOCATION LOAD GRP. ! HPI321 MOV WPPENRM LC43 125 DCC DOA HP1331 MOV EPPENRM LC44 125 DCD DGB HP!530 MOV 80A8 MCC36 480 EELPENRM100 AC/B HP1531 MOV 80A8 MCC35 480 WELPENRM120 AC/A i i HPl604 MOV WPPENRM MCC33 480 WELPENRM120 AC/A ~ HPE* 09 MOV EPPENRM MCC34 480 EELPENRM100 ACB HP1616 MOV EPPENHM MCC34 480 EELPENRM100 AQB HP1617 MOV EPPENRM MCC33 480 WELPENRM120 AQA HP1626 MOV EPPENRM MCC34 480 EELPENRM100 AQB HP1627 MOV EPPENRM MCC33 480 WELPENRrJ120 ACA HP1637 MOV WPPENRM MCC37- 480 WELPENRM120 AC/A HP1646 :MOV WPPENRM MCC36 480 EELPENRM100 AOB HP1647 MOV WPPENRM MCC33 480 WELPENRM120 AC/A HP1698 MOV HPSIA MCC37 480 WELPENRM120 AC/A HPl699 - MOV HPS18 MCC38 480 EELPENRM100 AC/B HPSIP1 MDP HPSIA BUSSO3 4160 ESFA AC/A ! HPSIP2 MDP HPSIB BUSSO4 4160 ESFB AGB I .G cc ' -. ~L.~_-_ . . _ - . - - - - - . - ~ _. ~ . - . . . - - - . -. _ Palo Verde 1. 2 & 3 3.4 Cil Al(GING SYSTE.it (CYCS) g 3.4.I System Function The charging system is part of the Chemical and Volume Control System (CVCSL The CVCS is responsible for maintaining the proper water inventory in the Reactor Coolant System and maintaining water purity and the proper concentration of neutron absorbing and corrosion inhibiting chemicals in the reactor coolant. The makeup function of the CVCS is required to maintain the plant in a long te m hot standby condition following a transient. 3,4,2 System Definition The CVCS provides a means for injection of control poison in the fami of boric acid solution, chemic tl additions for corrosion control, and reactor coolant cleanup and degasification. The system also maintains the required water inventory in the RCS, reprocesses water tha: is let down from the RCS, provides seal water injection to the reactor coolant putt.p seals, and performs an emergency core cooling function. The CVCS consists of several subsystems: the charging, letdown, and seal water system, the reactor coolant purification and chemistry control system, the reactor makeup control system, and the boron thermal regeneration system. The functions of the CVCS are performed by the followin ; components: (a) the charging pumps, (b) boric acid transfer pumps, (c) volume contro. 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 Oneration During normal plant operation, two charging pumps are running with suction s ' aligned to the Volume Control Tank (VCT). The letdown flow from the RCS cold leg is cooled in the tube side of the regenerative heat exchanger, then directed to the VCT. The bulk of the charging flow is pumped back to the RCS through the shell side of the regenerative heat exchanger via one charging line. Portions of the charging flow are directed to the reactor coolant pumps through a sealinjection system. The chargin;; pumps can be aligned to take a suction on ht e Refueling Water l Tank (RWT) and provice long term makeup to the RCS following a unsient. The CVCS
- letdown line is automatically isolated upon detection of a LOCA.
3.4.4 System Success Criteria The following success criterion is assumed for CVCS makeup (Ref.1, Section 9.3.4): 1 of 3 positive displacement charging pumps (CHP 1, CHP 2, or CIIP 3) is required for adequate post transient makeup to the 'lCS. For post-transient makeup to the RCS the following charging system success criteria is assumed: l A long-term water source must be available to th: charging pumps. One of three charging pumps is available. A makeup path to the RCS is available. v 27 12/88 l Palo Verde 1,2 & 3 i l l 3.4.5 Comnonent Information A. Charging Pumps (3) l 1. Rated capacity: 44 gpm l 2. Normal discharge pressure: 2300 psig .
- 3. Type: Positive Displacement i
B. Refueling WaterTank(1)
- 1. Volume: 590,000 gallons C. Regenerative lleat Exchanger (1)
- 1. Flow: 84 g pm (letdown). 48 gpm (charging)
- 2. Type: Shel) and tube, vertical (charging: shell; letdown: tube) 3.4.6 Sunnort Ststems and Interfaces ,
A. Control Signals
- 1. Remote Manual The charging pumps and motor operated valves can be actuated by remote means from the control room.
2 Manual j Manual valves can be actuated by hand at their specific locations. B. Motive Power
- 1. The positive displacement charging pumps and motor opemted valves of the -
CVCS are Class lE AC loads that can be supplied from the standby dierel generators as described in Section 3.6, i C. Other i
- 1. No external cooling water or lubrication systems for the charging pumps --
i have been identified. l 2. Pump room cooling systems ha'e not been identified. l 3.4.7 Section 3.4 References 1, Palo Verde Final-Safety Analysis Report, Arizona Public Service Company,- Phoenix, Arizona. i i i !h 4 V i 28 12/88 ..._,,s. .._., . . , , ,,,,,...m.--,__.,..- .,._,___,u_ .. , ,,%.,.y., ..o,....,y ,e_,_,, ,w,.,_,.,,.~,,w, .,,,,,my,--_v,- as !O E! li tk! . a d' v i thi SXirodl ll lll<4191tXie+yiedi si - ..ir 5 5 Il1 8 8 !8 J, e:. !1 kI II E A _! c. m i 8 s 9 5 ti el 8 { 0-k I XI XI i ti > ! 1 O
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~* 04EMICAL ADO T/J4M % TO 01MR G CVCS USERS 4 5 Figure 3.4-2. Palo Verde 1,2 and 3 Chemical and Volume Control System Showing Component Location (Page 3 of 3) 1 p Table 3.4-1. Palo Verde Charging System Data Summary , IOr Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG. TYPE L OC ATION LOAD GRP. CH524 MOV 100AB MCC35 480 WELPENRM120 AQA CH530 MOV 80AB MCC36 480 EELPENRM100 AQU CH532 NV 80AB CH536 MOV 100Ab' MCC35 480 WELPENHM120 AC/A CHP-1 MDP OIGA BUSL31 480 ESFA AQA CHP-2 MSP CHGB BUSL32 480 ESFB ACiB CHP-3 MDP OiGC BUSL36 480 ESFB AC/B d 1 ) -m & m __ _ _ . ~ _ . _ _ _ _ _ _ . _ _ __. _, Palo Verde 1. 2 & 3 3.5 INSTRUMENTATION AND CONTROL. (I & C) SYSTEMS 3.5.1 System Function The instrumentation and control systems consist of the Reactor Protection System (RPS), the Engineered Safety Features Actuation System (ESFAS), and systems for the display of plant information to the operators. The RPS and the Engineered Safety Features Actuation System monitor the reactor plant, and alert the operator to take corrective action before specined limits are exceeded. The RPS will initiate an automat i c reactor trip (scram) to rapidly shutdown the reactor when plant conditions exceed one or more specined limits. The Engineered Safety Features Actuation System will automatically actuate selected safety systems based on the specific limits or combinations oflimits 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. 3.5.2 System Definition The RPS includes sensor and transmitter units, logic units, and output trip relays that operate reactor trip circuit breakers to cause a remor scram. The Engineered Safety Features Actuation System includes independent su . and transmitter umts, logic units and relays that interface with the control circuits the many different sets of components that can be actuated by this system. Operator instrumentation display systems consist of display panels in the control room that are powered by the 120 VAC electric power system (see Section 3.6). The remote shutdown capability is provided by the Remote Shutdown Panel in conjunction with normal automatic systems and local equipment controls (Ref 1), g 3.5.3 System Goeration lk A. RPS The RPS has four redundant input instrument channels for each sensed parameter and two output actuation trains (A and B). The A and B logic trains ~ mdependently generate a reactor tri outside the safe operating range. p command when prescribed param separate and independent reactor trip circuit breaker to cause a scram. The manual scram A and B circuits bypass the RPS logic trains and send a reactor trip command directly to shunt trip circuitry in the reactor trip circuit breakers. B. ESFAS The initiation of the Engineered Safety Features Actuation System has three or four input instrument channels for each sensed parameter, and two output actuation trains (A and B), in general, each train controls equi) ment powered from different Class 1E AC electricalload groups, An indivic ual component usually receives an actuation _ signal from only one train. The initiation of the Engineered Safety Features Actuation System generates the following signals: (a) safety injection actuation signal (SIAS), (b) containment isolation, and (c) containment spray actuation. The control room operators can manually trip the various logic subsystems. Details regarding actuation logic are included in the system description for the actuated system. C. Remote Shutdown Instrumentation and controls are provided external to the control room to i achieve and maintain hot shutdown of the reactor should the control room O become inaccessible and under the assumption that: (1) the operator trips the ' t reactor prior to evacuation from the control room, and (2) that no other adverse 36 12/88 ! Palo Verde 1,2 & 3 - i' 1 available at the remote shutdown station. The atmospheric dump valve manual loading stations and the auxiliary feedwater turbine speed controller are provided with control transfer from the main control room to the remote i shutdown panel, j 3,5,4 System Success Criterin A. RPS l The RPS uses hindrance logic (normal = 1, trip = 0) in both the input and , output logic Therefore, a channel will be in a trip state when inp.it signals are ' i 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 breakers in the power path to the scram rods. In this case, one of two circuit breakers must open. Details of the scram system for Palo Verde have not been ' determined. , 4 l B.ESFAS A single component usually receives a signal from only one ESFAS output-train. ESFAS Trains A and B must be available in order to automatically actuate their respective components. ESFAS typically uses hindrance input logic (normal = 1, trip = 0) and transmission output logic (normat = 0, trip = 1), in this case, an input channel will be in a trip state when input signals are lost, l when control power is lost, or when the channel is temporarily removed from l service for testing or maintenance (i.e. the channel has a fall safe failure mode). ! Control power is needed for the ESFAS output channels to send an actuation signal. Note that there may be sorne ESFAS actuation subsystems that utilize hindrance output logic For these subsystems, loss of control power will cause i system or component actuation, as is the case with the RPS. Details of the ' ESFAS system for Palo Verde have not been determined. C. Manually-Initiated Protective Actions. . ; When reasonable time is available, certain protective actions may be performed manually by plant personnel. The controi toom operators are capable of operating individual components using normal control circuitry, or operating groups M 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 locally or from some other remote control location (i.e., the remote shutdown panel or a motor control center). To make these judgments, data on key plant parameters must be available to the operators. 3.5.5 Sunnort Systems and Interfaces j . A. Control Power
- 1. RPS The RPS input instrument channels are powered from the 120 VAC instrument buses (see Section 3.6). It is assumed that the RPS A and B output logic trains are powered from separate 125 VDC distribution panels, j 4
37- 12/88 : Palo Verde 1,2 & 3
- 2. Initiation of Engineered Safety Features Actuation System
, The input instrument channels are pow. red from 120 VAC instrument buses. It is assumed that the A and D output logic trains are powered from separate 125 VDC distribution panels.
- 3. Operator Instnimentation Operator instrumentation displays are powered from the 120 VAC instrument buses.
3.5.6 Section 3.5 References
- 1. Palo Verde Final Safety Analysis Report, Arizona Public Service Company, Phoenix, Arizona, Section 7.4.1,1984 a
I t l i i \ 38: 12/88 _ _ _ _ . _ . . _ . . _ . _ . _ - _ ~._ _ _ Table 3.51. Controls Available on the Palo Verde Remote Shutdown Panels The following controls are available at remote shutdown panels:
- 1. Steam Generator (SG) Atmospheric Dump Vahe Permissive Controls
- 2. Auxiliary Feedwater (RV) Regulating Valve Controls
- 3. Auxiliary RV isolation Vale Controls 4 SG Atmospheric Steam Dump Modulating Controllers
- 5. Auxiliary RV Turbine Steam Supply Valve Lontml
- 6. Auxiliary RV Turbine Speed Control Transfer Switch
- 7. Auxiliary RV Turbine Speed Control Potentiometer
- 8. Auxiliary RV Turbine Trip Valve Control
- 9. Auxiliary RV Turbine Trip Pushbutton
- 10. All Channels of Main Steam Isolation System (MSIS) Actuation Pushbuttons 11, Channel A and B Auxiliary Pressurizer Spray Valve Controls s- 12. Reactor Coolant Pum; (RCP) Controlled Bleedoff Conta!nment isolation Valve Controls 13, Shutdown Cooling Pump (SCP) Controlled and Bleedoff ReliefIsolation Valve Control 14 Letdown Isolation Valve Controls
- 15. Backup Ileater Groups 1 and 2 Controls
- 16. Safety injection Tank Vent Valve Control and Power Disconnect Switch
- 17. Shutdown Cooling Pumps Recirculation Valve Controls
- 18. Steam Generatur Pressure Variable Serpoint Reset -
- 19. Pressurizer Pressure Variable Serpoint Reset
- 20. Low Pressurizer Pressure Bypass O
V 39 a/88 - Palo Verde 1,2 & 3 3,6 ELECTRIC POWER SYSTEN! 3.6.1 System Function d The electric power system supplies power to various equipment and systems needed for normal operation and/or response to accidents. The onsite Class lE electric power system supports the operation of safety class systems and instrumentation needed to establish and maintain a safe shutdown plant condition following an accident, when the normal electric power sources are not available. 3.6,2 System Definition The onsite Class lE electric power system consists of two AC load groups. Diesel generator A is connected to 4160 VAC bus PBA503, and diesel generator B is connected to 4160 VAC bus PBBSO4. There are six 480 VAC switchgear buses, designated PGAL31,33,35 and PGBL32,34 and 36. Buses PGAL31,33 and 35 are connected to 4160 bus PBAS03 through transformers TR 31,33 and 35 respectively. Buses PGBL32,34 and 36 are connected to 4160 bus PDBSO4 through transformers TR-32,34 and 36 respectively. Various motor control centers receive their power from the 480 VAC buses. , Emergency power for vital instruments, control, and emergency lighting is supplied by four 125 VDC/120 VAC load groups. Four station batteries energize four DC buses, designated Load Centers PKAht41 PKBh142, PKCht43, and PKDh144. Four 120 VAC instrument panel buses (panels D25, D26, D27, and D28) are connected to the DC buses through inverters. Simplified one line diagrams of the electric power system are shown in Figures 3.61 and 3.6 2. A summary of data on selected electric power system components is presented in Table 3.61. A partial listing of electrical sources and loads is presented in Table 3.5 2. p l t 3.6.3 System Oncration l Dunng nonnal operation, the Class lE electric power system is supplied from the 525 kV switchyard through two system auxiliary transformers. The emergency sources of AC power are the diesel generators. The transfer from the preferred power source to the i diesel generators is accomplished automatically by opening the normal source circuit breakers and then reenerglung the Class lE poruon of the electric power system from the diesel generators. The DC power system normally 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 power for up to 2 hours (Ref.1). , ,The 120 VAC vital buses normally receive power from the DC buses through respeenve :nvates. Redundant safegads equipment such as motor driven pumps and motor operatid valves are supplied by differect VAC buses. For the purpose of discussion, this equipment has been grouped into " load groups". Load group AC/A contains components powered either directly or indirectly from 4160 bus PBAS03. Load group AC/B contains I components powered either directly or indirectly by bus PBBS 04. Components receiving DC power are assigned to load groups DC/A, DC/B, DC/C, or DC/D, based on the battery power source. 3.6.4 System Success Criterin Basic system success criteria for mitigating transients and loss-of coolant accidents are defined by front line systems, which then create demands on support n systems. Electric power system success criteria are defined as follows, without taking ( credit for cross ties that may exist between independent load groups: Y 40 12/88 Palo Verde 1. 2 & 3 Each Class IE DC load group is supplied initially from its respective battery (also needed for diesel staning) Each Class IE AC load group is isolated from the non Class 1E system and is supplied from its respective emergency power source (i.e. diesel generator) Power distribution paths to essential loads are intact Power to the battery chargers is restored before the batteries are exhausted 3.6.5 comoonent Information A. Standby diesel generators (2)
- 1. Maximum continuous rating: 5500 kW .
- 2. 2 hour rating: 6050 kW
- 3. Rated voltage: 4160 VAC-
- 4. Manufacturer: unknown B. Batteries (4)
- 1. Rated voltage: 125 VDC
- 2. Rating with 6: sign load: 2 hours per battery 3.6.6 Sunnort Systems and Interfaces A. Control Signals
- 1. Automatic '
The standby diesel generators are automatically started based on: Undervoltage on the normal bus, loss of offsite power (LOSPW) Safety injection actuation signal (SIAS)
- g -
Auxillery feedwater actuation signal (AFAS)
- 2. Remote manual The diesel generators can be started, and many distribution circuit breakers can be operated, from the main control room.
B. Diesel Generator Auxillary Systems
- 1. Diesel Cooling Water System-Heat from both diesel generators is transferred from a jacket water system to the Essential Spray Pond System (ESPS, see Section 3.8). An alternate cooling source is the fire system.
- 2. Diesel Starting System Each diesel has an air starting system.
- 3. Diesel Fuel Oil Transfer and Storage System A " day tank" supplies short term (approximately 7 hours) fuel' needs of each i
. diesel. Each day tank can be replenished from two storage tanks during engine operacon.
- 4. Diesel Lubrication System.
Each diesel generator has its own lubrication system, 5, Diesel Room Ventilation System. This s,vstem consists of exhaust fans which maintain the environmental conditions in the diesel room within limits for which the diesel generator and switchgear have been qualified, This system may be needed for long-term operation of the diesel generator. .41 ~12/88. (..._.. 1 I i , 2, Palo Verde 1,2 & 3 3.6.7 Section 3.6 References ; I 1. Palo Verde Final Safety Analysis Report, Arizona Public Service Company. - ! Phoenix, Arizona. I i i t a {
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- n CC Figure 3.6-1. Palo Verde 1,2, and 3 Electric Power System (Page 2 of 2)
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- ce
. . . - . - . _ - . . . _ - .-. . _ - . - ~ - _ - - . - .- _ _ . . - - . . . d TABLE 3.6 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT PALO VERDE 1,2 & 3 C PCWhR Y OLT AG E EMERG PCWER bOURI;E LCAD ' CAD , COVP COMPOhENT SOURCE LCAD GRP LOCATION SYSTEM COMPONENT 1D TYPE LOCATICN t.51 A 120 AC. A DCA EP PhL25 PNL DCA AS1B 120 AC<B DC9 EP PNL26 PNL DCB ~ AbiC tio ACiA DCC EP PN L2 7 Pk; DCC ASTD 120 AC/B OCD E P- PN L28 PNL GCQ t$ AT T A 125 DC/A B'T, EP LC41 BUS DCA M 125 DC/B BATB EP LC42 BUS DCB -@ 125 DGC BATC EP LC43 BUS DCC BATT CwGRA 125 DC/A DCA EP LC41 BUS DCA BATT CHGRAC 125 DC/A DCA EP LC41 BUS DCA BATT CHGRAC 125 DC/C DCC EP LC43 BUS DCC BATT CHGRB 125 DC/B DCB EP LC42 BUS DCB BATT CHGRBD 125 DCe8 DCB EP LC42 BUS DCB BATT CHGRBD 125 DC/D DCD EP LC44 BUS DCD BATT CHGRC 325 00, JDW EP LC43 BUS DCC BATT CHGRO 125 DC/D DCD EP LC44 BUS DCD , DATTD 125 OGO BATO EP LC44 BUS DCD BUSL31 -460 AC/A ESFA CVCS CHP 1 MDP CMGA BUSL31 480 AC/A ESFA EP MCC31 Bud ESFA BUSL32 480 AC/B ESFB CVCS CHP 2 MSP CHGB BVSL32 480 AC/B ESFB EP MCC32 BUS ESFB-BUSL32 480 ACs 0 E'SF B EP MCC38 1 BUS EELPENRM100 BUSL33 480 AC/A ESFA EP MCC33 BUS WELPENRM120 BUSL34 480 AC/B E$fB EP MCC34 BUS E ELPE NRM 100 . BUSL35 480 AC/A ESFA EP MCC35 BUS WELPENRM120 ~ j BUSL36 480 AC/8 ESFB CVCS CHP 3 MDP CHGC ~ l BUSL36 480 AC/B ESFB EP ' MCC36 P' ILPEN RM100 BUSS 03 ~ 4160 ACIA ESFA- ECCS HPSlft MDP HPSIA BUSS 03 4160 AC/A ESFA EP TR31 TRAN ESTA BUS $03 4160 AC/A ESFA E'P TR33 TRAN ESFA BU6S03 4160 AC/A ESFA EP TR35 TRAN ESFA l BUSS 03 4160 AC/A b ESFA ESPS SPA P01- MDP UMSPMPHSEA 50 12/88 .. .. . . - -_- - - . . . . - - -_. ~ . . - . . - TABLE 3.6 2, PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT PALO VERDE 1, 2 & 3 (CONTINUED) C ( POAE4 SOURCE VOLTAbE LMERG POM.R SOURCE LOAD (OAD COMP GOMPONENT LOAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION BU$b04 4140 AC. B EbEB AF WS AFW 8 6 MDP 80MSSSB BUSSO4 4160 AC< B 4 SFB ECCS NPSiP2 MDP NFS,8 CUSSO4 4160 AciB ESFB EP TRQ2 IRAN LSF B DVbSO4 4160 AC, B ESFB EP 1R34 TRAN E$FB BUSSO4 4i60 ACeB ESFB EP TR36 TRAN ESFB Bub 504 4160 AC/B ESFB ESPS SP B.P01 MDP UMS S ESEB DGA 4160 AC/A FSFA EP BUSS 03 oVS ESFA DGB 4160 AC/B ESFD tP BUS 604 bus ESFB INVA 120 AC/A DCA EP AISA ATS DCA INVB 120 ACs0 DCB EP ASTB~ ~ ATS DCB INVC 120 AC<A DCC EP 'ATSC ATS DCC INVD 120 ACiB DCD EP ATSD ATS DCD LC41 125 DC/A DCA AF WS AFWIN MOV 100PiiSA LC41 125 DCiA DCA AFWS AFW138 MOV- 100MSSSB LC41 125 DC,A DCA AF WS AFW32 MOV BOMSSSA LC41 125 DC/A DCA AFWS AF W37 MOV SOMSSSB 1 LC41 125 DC. A DCA AFWG AFW37 MOV 80MSSSB -; LC41 125 DC/A DCA AFVVS AF W54 MOV 60MSSSA LC41 125 DC/A DCA EP INVA INV DCA i LC41 125 DC/A DCA EP PNL21 PNL DCA LC42 125 DC/B DGB EP INVB INV DGB LC42 125 DC/B - DCB EP ~ PNL22 PNL DCB LC43 125 DC/A DCC AF WS AF W33 MOV 80MS$$A LC43 125 DDI DCC AF WS AF W33 MOV SOMSSSA LC43 125 DC/A DCC AF WS AF W36 MOV SOMSSSA LC43 125 .DC/A DCC ECCS HPl327 MOV WPPENRM LC43 125 DC/A DCC EP (NVC INV DCC LC43 125 DOC DCC RCS RHR653 MOV RC - LC44 125 DC/B DCD LCCS HPl331 MOV EPPENRM LC44 125 DC/B DCD EP INv0 INV DCD 6 (s .LC44 11f DC/D DCD ACS RHR654 MOV RC ~ ( l 51 I?/Rg i T A B L E 3.0 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT PALO VE3DE 1, 2 & 3 (CONTINUED) O\j POWER VOLTAGE EMER3 ~ POWER dOURCE LOAD LOAO COMP COMPONENT - SOURCE LCAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION MCC31 480 AC/A ESFA EP BATT-CMG4C BC OCC i VCC31 480 ACiA ESFA EP TRC TRAN OCC MCC31 480 AC/A EUA ESPS ESP 49A MOV SPONOVPTA MCC31 480 ACTA ESFA ESPS ESP 49B MOV SPONOVPTA MCC32 480 AC/B ESFB EP BATT CHGRO BC 000 MCC32 400 AC/B ESFB EP TRD TRAN OCO MCCd 480 AC/B ESFB ESPS ESP 50A MOV SPONOVPTB MCC32 480 AC/P ESFB ESPL ESP 508 SPONDVPTB MCC33 480 AC/A WELPENRM120 ECCS HP1604 MOV WPPENRM-MCC33 480 AC/A WELP ENRM120 ECCS HP1617 MOV EPPENRM MCC33 480 AC/A WELPENRM120 ECCS HP1627 MOV EPPENRM MCC33 480 AC/A WELP ENRM120 ECCS HPi64 7 MOV WPPENRM MCC33 480 AC/A WELP E N RM120 EP BATT CHGRAC SC DCA MCC34 4L O AC/B EE LPEN AM100 AFWS AF W30 MOV 80MSSSB \ MCC34 48 I AC/B E ELP ENRM100 AFWS AFW30 MOV 80MSSSB MCC34 480 AC/B EELPENRM100 AFWS AFW31 MOV 80MSSSB MCC34 480 AC/B EELPENRM100 ECCS HPn609 MOV EPPENRM MCC34 480 AC/B EELPENRM100 ECCS HPt616 MOV EPPENRM MCC3d 480 AC/B EELPENRM100 ECCS HPl626 MOV EPPENRM MCC I 480 AC/B EELPENRM100 ECCS HPl636 AUX WPPENRM MCC34 480 AC/B E ELPENRM100 EP BATT CHGRBO BC 0C0 MCC35 480 AC/A WELPENRM120 CVCS CH524 MOV 100AB MCC35 48C AC/A WELPENRM120 CVCS CH536 MOV 100AB ' ,;35 480 AO/A - WF.LPEN AM120 ECCS HP1531 MOV 80AB MCC35 480 AC/A WELPENRM120 EP BATT CHGRA BC OCA MCC35 480 AC/A WELPENRM120 EP TAA TRAN OCA MCC35 480 AC/A WELPENRM120 RCS RHR651 MOV RC MCC36 480 AC/8 EELPEN RM100 CVCS CH530 MOV 80AB 'MCC36 480 AC/B EELPENRM100 ECCS HPl530 MOV 60AB MCC36 480 AC/B E LLPENRM100 ECCS HP1646 MOV WPPENRM MCC36 4ri AC/B EELPENRMID0 EP L)\ -- BATT CHGRB BC DCB 52 12/88 p _ , _ , _ , , _ . a . _ . . . = = 'u' TABLE 3.6 2, PARTIAL LISTING OF EL<.TRICAL SOURCES AND LOADS AT PALO VERDE 1, 2 & 3 (CONTINUED) C 5 \ POWER VOLTAGE EMERG POWER SOURCE LOAD LOAD SOURCE COMP COMPONENT LOAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION MCC36 480 A C, B E E LPE N RM100 EP IRB 3 RAN DCB MCC36 480 A C, B EE LF E NRM 100 RCS RHR652 k,)V RC MCC37 480 ACIA WELPE NRM 120 ECCS HP1637 MOV WPPENRM MCC37 480 AC/A WELP E N AM120 ECCS HP1698 MOV HPSIA MCC38 480 ACiB E ELPEN RM100 AF WS AF W34 MOV 80MS$$A MCC38 480 AciB EELPENRM100 AFWS AF W34 MOV 80MSSSA MCC38 400 AC/B EELP ENRM100 AFWS AF W35 MOV 80MSSSB MCC38 480 AC/B EELP ENRM100 ECCS HPl699 ~ MOV HP$lB TR31 480 AC/A ESFA EP BUSL 31 BUS ESFA TR32 480 AC/B ESFB EP BUSL32 BUS ESFB TR33 480 AC/A ESFA EP BUSL33 BUS ESFA TR34 480 AC/B ESFB EP BUSL34 BUS ESFB TR35 480 AC/A ESFA EP BUSL35 BUS ESFA TR36 480 ACiB ESFB EP BUSL36 BUS ESFB \ V s s 7 53 12/88 Palo Verde 1,2 & 3 3,7 A ESSENTIAL COOLING WATER SWTEM (l:CWS) h 3.7.1 System Function The essential cooling water system (ECWS) forms an intermediate cooling. i water loop for transferring heat from various safety related heat loads, including the i shutdown cooling heat exchanger, to the Essential Spray Pond System (ESPS) which serves as an ultimate heat sink. The ECWS provides indirect cooling, through heat i exchangers, of those reactor auxiliaries that carry radioactive or potentially radicactive- i fluids, j 3.7,2 System Definition i The ECWS consists of two separate, independent, closed loop, safety related q trains. Each train of the ECWS consists of a heat exchanger, surge tank, pump, chemical i addition tank, piping, valves, controls, and instrumentation Simplified drawing of the ECWS are shown in Figures 3.7-1 and 3,7 2, 3,7,3 System Oneration During nomial operation, the ECWS is in standby,- Although either train has a i 100% heat dissipation capacity, an emergency reactor shutdown is normally accomplished - ; by initial operation of both trains of the ECWS and ESPS. For shutdown and cooldown-over an extended period of time, use of a single train is 3ossible. . Each train of the ECWS provides cool ng for the following redundant components: L Shutdown cooling heat exchangers (one per train) - Essential chillers (one per train) . Fuel pool heat exchangers (one per train) if NCWS is unavailable Normal chiller ( - Reactor coolant pumps (seals and motor) ' . Control element drive mechanism (CEDM) air coolers In the; event the Nuclear Cooling Water System (NCWS) is unavailable the operator can align train A or train B of the ECWS (never both) to supply cooling water to-the NCWS and act as a heat sink for NCWS heat loads. 3,7.4 System- Success Criterin + The system success criteria can be defined on a per train basis. Either train can j maintain an extended hot shutdown. The success criteria for each train requires that the ECW pump operates, the associated Essential Spray Pond System removes heat from the ECW heat exchanger, and the piping and valves provide an adequate flow path in the-- specific train (Ref,1, Section 9.2.2.1). 3.7.5 Comnonent - Information A - ECWS pumps 1 and 2 1, Design flow: 14,500 gpm@ 154 ft head (68 psid)
- 2. Rated capacity: 100%
L
- 3. Type: centrifugal i
B. ECWS Heat Exchangers 1 and 2
- 1. Capacity: 100(7e .
- 2. Type
- Shell (ECWS) and Tube (ESPS) x 54 12/88
- .-- -.--..- - -~ - . - . - . _ - . . . . - . . . - - . - - - - Palo Verde 1,2 & 3 C. Surge Tanks 1 and 2
- 1. Capacity': 1000 gallons ,
- 2. Type: Vertical cylindrical i D. Chemical Addition Tanks I and 2
- 1. Capacity: 11 gallons
- 2. Type: Ball Feeder 3.7.6 Suncort Systems and Interfaces A. Control Signals
- 1. Automatic The ECWS is actuated automatically.
- 2. Remote manu.tl Control and instrumentation necessary for the operation of the ECWS pumps are located in the control room.
- 3. I.ocal Local instrumentation and controls are provided at the ECWS pumps.-
o' B. Motive power
- l. The ECWS motor driven pumps and motor operated valves (65 and 145) are Class lE AC loads that can be supplied from the-standby diesel generators as described in Section 3.6.
C. Other ' O
- 1. No extemal systems for ECWS pump lubrication and cooling water have-
- been identified.
- 3. 7. 7 - Section 3.7 References-
- 1. Palo Verde Final Safety Analysis Report, Arizona Public Service Company, Phoenix, Arizona.
i d
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- k
= Figure 3.7-2. Palo Verde 1,2, & 3 Essential Cooling Water System (Train B) _ _ _ _ _ _ _ _ .. .. .. . - . - . .. .:-. - . . . .. .- .. .. . . . - .. .. .-~-. ---=--~ . Palo Verde 1. 2, & 3 3.8 ESSENTIAL SPRAY POND SYSTEM (ESPS) 3 3.8.1 System Function . l The Essential Spray Pond System removes heat from the diesel generators and the Essential Cooling Water System and dissipates it to the atmosphere via the essential spray ponds. A separate essential spray pond system is provided for each unit. 3.8.2 System Definition The ESPS consists of two spray ponds and two separate, redundant cooling water trains. There are no interconnections between trains or cross connections with any other unit's ESPS. Each train is comprised of an ESPS pump, pump structure, piping, valves, instmmentation, and controls to provide cooling water to specific nuclear safety-related components. Simplified drawings of the ESPS are shown in Figures 3.81 and 3.8 2. A summary of data on selected ESPS components is presented in Table 3.8-1. 3.8.3 Ststem Oneration During normal operation, the ESPS is in standby. Each ESPS train is capable , of supporting 100% of the cooling functions required for a safe reactor shutdown or following a LOCA. During an emergency operation _a normal reactor shutdown, or each time the c.andby diesel generators are started and there is a loss of offsite power, the ESPS - provides cooling water directly to the cooling systems of the diesel generators and to the ECWS indirectly through the ECWS heat exchangers. Cooling water for the ESPS is supplied from the ultimate heat sink or essential spray onds. Each pond serves one train of the ESPS. Return flow from components serviced b the ESPS.is returned to the ESPS ' spray cooling subsystems and to the ultimate heat sink for reuse. Each heat sink holds water inventory to meet 15 days of operation without makeup. l t O 3.8.4 System Success Criteria l Dependencies of components on the ESPS are defined in other system models. For a specific ESPS loop, the respective ESPS pump must operate and one of two motor-operated valves in the return path to the respective spray pond must be open (Ref.1, Section 9.2.1). 3.8.5 Comnonent Information A. ESPS pumps A and B-
- l. Rated flow: 16,300 gpm @ 120 ft head (52 psid) 2 Type: vertical wet pit B. Ultimate Heat Sink - Spray Ponds A and B 3.8.6 Sunnort System and Interfaces l A. ControlSignals
- 1. Automatic-Both trains of the ESPS are automatically actuawl.
- 2. Remote Manual Manual start and stop actuation of the two ESPS trains from the control room overrides the automatic mode. Spray header isolation and bypass valves can be manually operated from the control room.
1 U ( 58 12/88 -l 1 l l Palo Verde 1,2, & 3
- 3. Manual
() Valves in supply lines from the ESPS pumps .nd in the return lines to the 'Q ESPS spray ponds or the ECWS heat exchan;,ers are locked open. B. Motive Power Each ESPS pump and motor operated valves are class lE loads that can be supplied from the standby diesel generators as described in Section 3.6. C. Other
- 1. No external systems for ESPS pump lubrication and cooling water have been identified.
- 2. The ESPS pump house coolers are supplied by the Essential Chilled Water System.
3.8.7 Section 3.8 References
- 1. Palo Verde Final Safety Analysis Report, Arizona Public Service Company, Phoenix, Atizona.
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qwpk.. ' I - 3 p 1ap q- k 3 d" > e.I 35"Pf 3d'If 3 6f 31j 31 f. :sd.l s l q-p elf q sa p w M V c m I _- e ! E g 3 O um mus.m b i 1 t:'i ii t7,i- # e m - A' 61 12/88 . . .. . . - . . . . . . . - . ~ . . ~ . - . . . , - . . . - . . . . - . . - . . . - . - . . . - - . . . . e < 4 Table 3.8-1. Palo Verde Essential Spray Pond System Data Summary ~ for Selected Components ' COMPONENT . lD COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG. TYPE' LOCATION LOAD GRP. ESP 49A MOV SPONDVPIA MCC31 480 ESFA AC/A ESP 498 MOV SPONDVPTA MCC31 480 ESFA AC/A ESP 50A MOV' SPONOVPIB . MCC32 480 ESFB AC/B ESP 508 MOV SPONDVPIB MCC32 480 ESFB AC/B l- SPA-P01 MDP UHSPMt)HSEA BUSS 03 4160 ESFA AC/A i SPB-P01 MDP UHSPMPHSEB BUSSO4 4160 ESFB AC/B t tJ ! j . . . ~. 4 , ~ t + .f i .i i 1 - ! ~ LJ 1 .x OC i + c- - . . _ Palo Verde 1,2 & 3 s
- 4. PLANT INFORMATION 4,I SITE AND BUILDING
SUMMARY
The Palo Verde site is located 34 miles west of the nearest boundary of the city of Phoenix, Arizona. The site contains three PWR plants. Figure 41 shows a general ' view of the site, with Figures 4 2 and 4 3 showing more details of the site buildings. The auxiliary building is located adjacent to the containment building. This building' primarily houses the ESF and CVCS equipment, and the power block controlled access facility. The control building is located adjacent to the radwaste and auxiliary buildings. This building primarily houses the control room, computer room, upper and lowei cable spreading rooms, battery rooms, electrical equipment rooms and ventilation equipment rooms. Two identical essential spray ponds are provided for each unit. Each pond removes heat from the Engineered Safety Features (ESP) and safety related components. Three cooling towers serving each unit are the heat sink for the power conversion system. The diesel generator building is located adjacent to the control building. This building primarily houses the two standby diesel generators. The condensate storage tank (CST), located northwest of the reactor building, primarily supplies water for the auxiliar, feedwater system.- It is also a redundant source of demineralized water for the essential cooling water system, essential chilled water system, diesel generator system and the fuel pool. It also is used for maintaining proper feedwater inventory in the secondary system during startup, shutdown, hot standby, and normal power operations. The refueling water storage tank (RWT), located southwest of the containment building, primarily services the safety injection pumps. The reactor makeup water storage tank (RMWT) is located southwest of the containment building and services the auxiliary feedwater system and the chemical volume and control system. 4.2 FACILITY. LAYOUT DRAWINGS Figures 4 4 through 415 are secth views and sim alified building layout-drawings for the Palo Verde containment, auxii y building anc. intake structure. The . turbine and service building, maintenance shop, a..u technical stoport building are not shown on these drawings Major rooms, stairways, elevators, and cloorways are shown in - the simplified layout drawings however, many interior walls have been omitted for clarity, Labels printed in uppercase cotrespond to the location codes listed in Table 41 and used in the component data listings and sy included for information andnted arein pn, stemtype. lowercase drawings in Section 3. Some additional labels are A listing of components by location is presentec. In Table 4 2, Components - included in Table 4-2 are those found in the system data tables in Sectior,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. U 63 12/88-
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- 73 12/88
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L h ! i i Table 41. Definition of Palo -Verde 1, 2 and 3 Building and t Location Codes Codes Descriotions 4
- 1. 40ABPPCHSA 40' elevation Auxiliary Building Pipe Chase A ?
- 2. 40ABPPCHSB 40' elevation Auxi .nf Building Pipe Chase B l
- 3. 80AB 51' 6" elevation of:re Auxiliary Building 4, !
80MSSSA Main Steam Support 'tructure A on the 80' elevation
- 5. 80MSSSB Main Steam Support Structure B on the 80' elevation
- 6. 100MSSSA Main Steam Support Stmeture A on the ICO'c!cvation
- 7. 100MSSSB Main Steam Support Structure B on the 80' elevation l 8, BATA Battery Room A, located on the 100' elevation of the Control Building Central Area E 9. BATB Battery Room B, located on th: !00' elevation of the Control-Building-Central Area
- 10. BATC Battery Room C, located on the 100' elevation of the Control u Building-Central Area
- 11. BATD Battery Room D, located on the 100' elevation of the Control Building-Central Area -{
- 12. CR Control Room, located on the 140' elevation of the Control-Building j
- 13. CSA Containment Spray- Pump Room A, located on the -140' l
elevation of the Auxiliary Building .i
- 14. CSB Containment Spray Pump Room B, located on the 40' of the .
Auxiliary Building -
- 15. CST. Condensate Storage Tank, located northwest of Containment Building-
- 15. CSTPMRM Condensate Storage Tank Purrp Room, located next to the.
Condensate Storage Tank
- 17. CSTUNN Condensate Storage Tunnel, t .nnel between Condensate Storage Tank and Turbine Building -
- 18. DCA- D.C. Equipment Room Channel A, located on the 100' elevation of the Control Building - Central Area 79 12/88
Table 41. Definition of Palo Verde 1, 2 and 3 Building and i Location Codes (Continued) l Codes Ilescrjntions ; I
- 19. DCil D.C. Equipment Room Channel B, located on the 100' elevation of the Control Building at elevation 10(T Central Area
- 20. DCC D.C. Equipment Room Chann L acated on the 100' elevation !
of the Control Building at eles -e XT i
- 21. DCD D.C. Equipment Room Channe J kcated on the 100' elevation of the Control Building Central Area
- 22. DGA Diesel Generator A, located on the 100' elevation of the Diesel Generator Building southwest side
- 23. DGACPA Diesel Generator Air Compressor Room A, located on the 100' elevation of the Diesel Generator Building west side
- 24. DGACPB Diesel Generator Air Compressor Room B,le ated on the 100' elevation of the Diesel Generator Building east side
- 25. DGACR Diesel Generator A Control Room, located on the 100' elevation of the Diesel Generator Building northwest side
't '
- 26. DGAIRA Diesel Generator A Air Intake Filter Room, located in the Diesel
- Generator Building nonhwest side
- 27. DGAIRB Diesel Generator B Air Intake Filter Room, located in the Diesel Generator Building northeast side
- 28. I'GB Diesel Generator B, located on the 100' elevation of the Diesel Generator Building southeast side
- 29. DGBCR Diesel Generator B Control Room, located on the 100' of the the Diesel Generator Bcilding northeast side
- 30. DGDTA Diesel Generator A Fuel Oil Day Tank, located on the 100' of the Diesel Generator Building central area -
- 31. DGDTB Diesel Generator B Fuel Oil Day Tank, located in the Diesel Generatcc Building - central area 4
- 32. DGEXA Diesel Generator A Exhaust Room, located in the Diesel Generator Building northwest side I
- 33. DGEXB Diesel Generator B Exhaust Room', located in the Diesel l Generator Building northeast side l 34. EELPENRM100 East Electrical Penetration Room, located on the 100' elevation b]
/ of the Auxiliary Building northeast side 80 12/88 )
Iq Table 41. Definition of Palo Verde 1, 'e and 3 Building and Location Codes (Continued) Cndes Descriotions
- 35. EPPENRM East Pipe Penetration Room, located in the Auxiliary Building -
northeast side
- 36. ESFA ESF Switchgear Room A, located on the 100' of the Control Building west side
- 37. ESFB ESF Switchgear Room B, located on the 100' of the Control Building east side
- 38. EWIIXA ECW licat Exchan ger Room A, located on the 100' of the Auxiliary Building e evation 100' west side
- 39. EWiiXB ECW 11 eat Exchanger Room B, located on the 100' of the Auxiliary Building west side 40, llPSIA liigh Pressure Safety injection Pump Room A, located on the 40' elevation of the Auxiliary Building
- 41. IIPSIB liigh Pressure Safety injection Pump Room B, located on the 40' elevation in the Auxiliary Building b
d 42. LOCSR Lower Cable S ) reading Room, located on the 120' elevation of the Control Bui ding
- 43. LPSIA Low Pressure Safety injection Pump Roo:.) A, located on the 40' elevation of the Auxiliary Building
- 44. LPSIB Low Pressure Safety injection Pump Room B, located on the 40' elevation in the Auxiliary Building
- 45. RC Reactor Containment
- 46. RM%T Reactor Makeup Water Tank, located west of Fuel Building ,
- 47. RPS1 Reactor Protection System Panel 1, located in the Auxiliary Building southeast corner
- 48. RPS2 Reactor Frotection System Panel 2, located in the Auxiliary Building southeast comer
- 49. RSDPNLBD Remora Shutdown Panel BD, located on the 100' elevation of the Control Building - south side
- 50. RSDPNLAC Remote Shutdown Panel AC, located on the 100' elevation of the Control Building - south side
'A 1 52. RWT Refueling Water Tank, located south of Puel Building \J 81 12/88
- ~
n Table 41. Definition of Palo Verde 1,2 and 3 Building and Location Codes (Continued) Codes Descriotions I
$3. RWTUNN Refueling Water Tunnel, located south of Fuel Building 54 SPONDVirrA Spray Pond Valve Pit A, located next to Spray Pond A i
- 55. SE NDVPTB Spray Pond Valve Pit B, located next to Spray Pond B
$ 6. TLSF Spent Fuel operating floor, located in the Fuel Building
- 57. UliSA Ultimate lleat Sink A (Spray Pond A)
- 58. UllSB Ultimate IIcat Sink B (Spray Pond B)
- 59. UliSPhiPliSEA Ultimate IIcat Sink Pump flouse A, located next to Spray Pond A
- 60. UllSPhiP11 SED Ultimate liest Sink Pump 11ouse B, lodated next to. Spray Pond B 6' UPCSR Upper Cable Spreading Room, located on the 160' ekvation of the Control Building O)
( U 62. WELPENRhil20 West Electrical Penetration Room, located on the 120' elevation of the Auxiliary Building - northwest side , 63. WPPWNRhi West Pipe Penetration Room, located in the Auxiliary Building - nonhwest side i j b
'J 82 12/38
TABLE 4 2. PARTIAL LISTif40 OF COMPOt4Et4TS BY LOO?,T'OM AT PALO VERDE 1,2 & 3 LOC A TION bYS1LM COMPONENT ID COMP TYPE 100 A B cvC5 CH536 MOV 100AB CVCS chb 24 MOV 100MSSSA AF WS AF W 134 MOV 100M5SbB AF n S AF W I S8 MOV 60AB CVCS Cn632 NV 60A0 CVCS CH630 MOV BOAB ECCS HPib31 MOV 80AB ECCS HPl530 MOV 60MSSSA AFWS AF W33 MOV 80MSSSA AF WS AFW34 MOV 60MSSSA AF WS AF W32 MOV 80MSSSA AFWS AFW36 MOV BOMSSSA AFWS AF W33 MOV r 80MSSSA AF WS AF W34 MOV 80MSSSA AFWS AFW-A B TOP 60MSSSA ANS AFW54 MOV BOMSSSB AFWS AF W30 MOV 80MSSSB AF WS AFW31 MOV 80MSSSB AFWS AFW36 MOV 80M OSB AF WS AFW37 MOV 80MSSSB AF WS AFW B B MOP 80MSSSB AFWS AFW30 MOV. 80MSSSB AF WS AFW37 MOV BATA EP BATT A BATT BATB EP BATTB BATT SATC EP SATT C BATT BATO EP BATT D BATT CHGA CVCS CHP1 MDP CHGB CVCS CHP 2 MSP
~
CHGC CVCS CHP 3 MDP 83 12/88 1
TABLE 4 2. PARTIAL LISTINO OF COMPONENTS BY LOCATION AT PALO VERDE 1, 2 & 3 (CONTINUED) LOC ATION SYSTEM COMP',NENT ID COMP TYPE CST AhvS CSi' TANN DCA EP PNL25 PNL DCA EP LC41 bus DCA EP (N V A INV DCA EP DATT CNGRA BC DCA EP BATT CHCRAC BC DCA EP TRA TRAN DCA EP P N L21 PNL DCA EP ATSA ATS DCA EP LC41 BUS DCA EP LC41 DVS DCB EP PNL26 PNL DCB EP LC42 BUS DGB EP iNVB IN / D ( DCB EP BATT CHGRB DC D00 EP BATT+Cm alBD BC W^ EP TRB TRAN DCD EP PNL22 PNL DCB EP ASTD ATS DCD EP LC44 DVS DCD EP LC42 SUS DCC EP P NL27 PNL DCC EP LC43 BUS DCC EP INYC INV [ DCC EP OATT CHGRC DC i I DCC EP TRC TRAN DCC EP ATSC ATS DCC EP LC43 BUS DCC EP LC43 BUS l DCD EP PNL28 PNL b-lO l 84 12/d8 l i o
TABLE-42. PARTIAL LISTING OF COMPONENTS BY. LOCATION AT PALO VERDE 1, 2 & 3 (CONTINUED) LOCA140N SYSTEM COMPONENT 10 COMP TYPE DCD EP LC44 BUS DCD EP INVD INV DCD EP BATT CNGRD BC DCD EP IRD TRAN DCD EP ATSD ATS 000 EP LC44 BUS-DCD EP LCd4 BUS DCA EP DGA DG i DGB EP DGB DG EELPENRM100 EP MCC36 BUS EELPENRM100 EP MCC34 BUS EELPENRM100 EP MCC38 BUS EPPENRM ECCS HPl617 MOV EPPENRM ECCS HP1627 MOV EPPENRM ECCS HPI331 MOV EPPENRM ECCS HP4609 MOV EPPENRM ECCS HPl616 MOV _, EPPENRM ECCS HPl626 MOV ESFA EP MCC31 BUS - ESFA EP BUS 503 BUS ESFA EP CBA CB-ESFA EP BUSL33 ,Ph~ - ESFA EP- TR33 TWN~ ESFA iP BUSL31 BUS ESFA EP TR31 TRAN ESFA EP BUSL35 . BUS ESFA EP- TR35 TRAN ESFB- EP MCC32 BUS ESFB EP. BU SSO4 -- BUS ESFB EP CBB CB 85- 12/88-
TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION AT PALO VEEE 1, 2 & 3 (CONTINUED) \ LOCAllON SYSTEM COMPONENilo COMP TYPE ESAB eP BUSL34 BUS ESFB EP TR34 T FMN ESFB EP GUSL36 DVS ESFB EP TR36 TRAN ESFB EP BUSL32 BUS TSio EP TR32 IFMN HPSIA ECCS HPSIPI MOP HPSiA ECCS HPl698 MOV HPSiB ECCS HPSIP2 MI HPSiB ECCS HPl699 MOV N AFWS SG 1 SG RC AFWS SG 2 SG N RCS RCS VESSEL RV N RCS CH515 NOV N ACS CH516 NCV N RCS RHR652 MOV RC RCS RHR654 MOV N RCS RHR653 MOV N RCS RHR651 MOV RMWT AFWS RMWT TANK SPONovPTA ESPS ESP 49A MOV SPONOvPTA ESPS ESP 498 MOV . SPONOvPTB ESPS ESP 50A MOV SPONOvPTB ESPS ESP 500 MOV UHSP MPHSEA ESPS SPA P01 MOP UHSPMPHSEB ESPS SPB P01 MOP WELPEN AM120 EP MCC35 BUS WELPENRM120 EP MCC33 BUS WPPENRM ECCS HPG21 MOV WPPENRM ECCS HP1604 MOV O ' b 86 12/88
. - . . .. _ - .. . . . - . - ~ .-
i TABLE 4 2. PARTIAL LISTitio OF Col /. pot 4Et1TS BY LOCATIOt1 i AT PALO VERDE 1, 2 & 3 (LOl1Tlf4UED) l N LOCATION SYSTEM COMPONENTi0 COMP TYPE WPPENRM ECCS M Pi637 MOV - WPPENRM ~~ ECCS HPl54 7 MOV WPPENRM ECCS MPib46 MOV i e i 1 lO s l 87 12/88
=
Palo Verde 1,2 & 3
!*. DIBLIOGRAPilY FOR PALO VERDE
(
- l. NUREG 0857, " Safety Evaluation Report Related to the Operation of Palo Verde Nuclear Generating Station, Units 1,2 and 3", USNRC
- 2. NUREG 1133, " Technical Specification for Palo Verde Nuclear Generating Station, Unit 1", USNRC, May 1985
- 3. NUREG 1181, " Technical Specification for Pe' i Verde Nuclear Generating Station, Unit 2", USNRC
- 4. NUREG 1287, " Technical Specification for Palo Verde Nuclear Generating S ation, Unit 3", USNRC
- 5. Roscoe, B.J., "Palo Verde Nuclear Generating Station Units 1, 2 and 3 Auxiliary Feedwater System Reliability Study Evalution". NUREG/CR 2322, Sandia National Laboratories, December 1981 O
c ( 88 12/88
_ _ _ _ __ _ _ _ _ ~ _ _ _ _. . . _ __ ._. Palo Verde 1,2, & 3 APPENDIX A DEFINITION OF SYMBOLS USED IN TIIE SYSTEM AND LAYOUT DRAWINGS A 1, SYSTEM DRAWINGS A 1,1 Fluid System Drawings The simplided system drawings are accurate representations of the major now paths in a system and the important interfaces with other fluid systems. As a general rule, small Guld lines that are not essential to the basic operation of the system are not shown in these drawings. Lines of this type include instrumentation lines, vent lines, drain lines, 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 drawin comparable drawing showing component The locations. gt a simplified drawing conventions used insystem the drawing, a fluid system drawings are the following: Flow generally is left to right. Water sources are located on the left and water " users" (i.e., heat loads) or discharge paths are located on the right. One exception is the return Gow path in closed loop systems which is right to left. Another exception is the Reactor Coolant System (RCS) drawing which is
" vessel centered", with the primary loops on both sides of the vessel. >
Horizontal lines always dominate and break vertical lines. Component symbols used in the fluid system drawings are defined in Figure ( A-1. Most valve and pump symbols are designed to allow the reader to distinguish among similar components based on their support system requirements (l.c., electric power for a motor or solenoid, steam to drive a turbine, pneumatic or hydraulic source for valve operation etc.) Valve symbols allow the reader to distinguish among val-;s 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 t of valve)ype. of valve (i.e., as a globe, gate, butterfly, or other specific type Pump symbols distinguish between centrifugal and positive displacement pumps and between types of pump drives (l.c. motor, turbine, or engine). Locations are identified in terms of plant location codes defined in Section 4 of this Sourcebook. Location is indicated by shaded " zones"_ that are not intended to represent the actual room 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. The primary flow path in the system is highlighted (i.e., bold white line) in
) the location version of the fluid system drawings.
89 12/88 1
Palo Verde 1,2, & 3 A1.2 Electrical System Drawings The electric power system drawings focus on the Class IE portions of the plant's t electric power system. Separate drawings are provided for the AC and DC portions of the Class IB system. There often are two versions of each electrical system drawine; a simplified system drawing, and a comparable drawing showing component locations. *The drawing conventions used in the electneal system drawings are the following: Flow generally is top to bottom In the AC power drawings, the interface with the switchyard and/or offsite Trid is shown at the top of the drawing, _
,n the DC power drawings, the batteries and the interface with the AC -
power system are shown at the top of the drawir.g. Vertical lines dominate and break horizontal lines. Component symbols used in the electrical system drawings are defined in Figure A 2. Locations are identified in terms of plant location codes defined in Section 4 of this Sourcebook. Locations are indicated by shaded " zones" that are not intendsd 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 tht actual O cable routing in the plant. Component locations that are not known are indicated by placing the V discrete components in an unshaded (white) zone. A2. SITE AND LAYOUT DRAWINGS i l A2.1 Site Drawings A general view of each reactor site and vicinity is presented along with a simpilfied site plan slowing the arrangement of the major buildings, tanks, and ot aer features of the site. The general view of the reactor site Js obtained from ORNL-NSIC 55 (Ref.1). The site drawings are ap 3roximately to scale, but should not be used to estimate distances on the site. As built sea e drawings should be consulted for this purpose. Labels printed in bold uppercase conespond to the locauon codes defined in Section 4 and used in the component data listings and system drawings in Section 3. Some - additional labels are included for information and are printed in lowercase type. A2.2 Layout Drawings Simplified building layout drawings are developed for the portions of the plant that contain components and systems that are described in Section 3 of this Sourcebook. Generally, the following buildings are included: reactor building, auxiliary building, fuel building, diesel building, and the intake structure or pumphouse. Layout drawings generally are not developed for other buildings. Symbols used in the simplified layout drawings are defined in Figure A 3. Major rooms, stairways, elevators, and doorways are shown in the simplified layout drawings however, many interior walls have been omitted for clarity. The building layout drawings, 90 12/88
Palo Verde 1,2 & 3 are approximately to scale, should not be used to estimate roorn size or distances. As built scale drawin p for should be consulted his purpose, l Labe s printed in uppercase bolded also correspond to the location codes defined in Section 4 and used in the component data listings and system drawings in Section 3. Some ! additional labels a c included for information 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),
January 1972 (Vol. 2), April 1974 (Vol. 3), and March 1975 (Vol. 4) i V 91 12/88 4
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(OPEN CLC D) ALVE ICV (OPEN CSE D) l O _ _ MOTOR CPER ATED Y ALVE . MOV MOTOR CPENATED (OPEN/ CLOSED) 3 WAY V ALVE . MOV (CLOSED PORT MAY VARY) l W , '> SOLEN 0lD OPERATED VALVE
- SOV SOLENCID OPER ATED F'
(O P E N /C L O S E D) 3 WAY VALVE 80V (CLMSED PORT MAY VARY)
' HYDR AVLIC VAIVE e HV L HYDR AULIC NON RETURN r7 (O P E N /C f.0 S L D) 4 V ALVE
- HCV (OPEN' CLOSED) .
' PNEUMATIC VALVE e NV F'
PNEUMATIC NON RETURN
- (O P E NIC L O S E D) V ALVE . NCV (OPENICLOSED)
CHECK VALVE
- CV M S AFETY VALVE . SV O
(CLOSED) W* Ch M POWER OPER ATED RTLIEP VALVE, SOLENCID PtLOT TYSE PORY dr b . POWER OPERATED RELIEF V ALVE. PNEUMATICALLY CPERATED PORV tED) OR DUAL FUNCTION SAFETYtRELIEF VALVE SRV (CLOSED) CENTRIFUC AL CEN'RIFLO AL MOTOR DRIVEN PUMP + MDP TURdlNE ORIVEN PUMP
- TDP
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, POSITIVE DIS PL ACEMENT _ positivt otspLACEMENT MOTOR ORIVEN PUMP = MDP .
TURDINE DRIVEN PUMP
- TOP 1
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I Figure A 1e- Key To Symbols in Fluid System Drawings. 92 12/88 i
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l I l i ' l pwnggwg MAIN CONDEN$tR . COND
- I REACTOR VitEEL.RV i
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- . HEAT EXCHANotR MX MECH ANICAL DR AFT 1
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.i Figure A 1. Key To Symbols ~ln Fluid System Drawings
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(Continued) 93 12/88-- 1
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I A C. DIEltL CtNER ATOR
- D0 2- B ATTERf . B ATT OR A.C. TURDINE ctNER ATOR . TO 4
g) OR g; CIRCUlf BRt Akth . C8 INTERLOCKt0 {0PENtCL0$tD) [3 ...l g l ... g ) ' CIRCulf ORE AktR$ CB OR O ( ~ SWITCH . $W > p AUTOMATIC OR OTHER TYPE OF TR ANSFER SWITCH a ATS DitCONNECT OtvlCE OR (08' 4/CLottD) MANUAL TRANSFER SWITCH . MTS SWITCHQt AR SUS BU$ I-(BUS N AME) l MOTOR CONTROL CENTER
- MCC M M OR Mf- - ?j TRANSFORMER . TR AN
' ] OR I DISTR 18U710N P ANil e PNL I B ATTERY CHAR 0ER (Rf CTIFitR) . BC 5Z INVERTER e INV j i T { l 1 f
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,- gR RELAY CONTACTS pygg , gg
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M ELECTRIC WTOR
- MTR MOTOR CENERATOR* MO w 1 Figure A 2. Key To: Symbols.In Electrical System Drawings l
-94 12/88
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i STAIRS E g SPIRAL STAIRCASE D .Down LADDER (- u . Up D e Down l= N ELEVATOR g HATCH OR OPEN AREA-GRATING DECK (NO FLOOR) 1
-O- PERSONNEL DOOR + *EQUlPMENT DOOR 55 RAILROAD TRACKS :< FENCE LINE EE
, TANK / WATER j AREA i Figure A-3. Key To Symbols in Facility Layout Drawings 95 12/83
1 Palo Verde 1,2, & 3 APPENDIX 11 DEFikiO' OF TERMS USED IN Tile DATA TAllLES l Tenns a denned as follows: ppearing in the data tables in Sections 3 and 4 of this Sourcebook are SYSTEM (also LOAD SYSTEM) . All components associated with a particular system description in the Sourcebook have the same system code in the data base. System codes used in this Sourcebook are the following: Cedg Defm' ition RCS Reactor Coolant System AFWS Auxiliary Feedwater System ECCS Emergencv Core Cooling System CVCS - Charging system EP Electric Power System ESPS Essential Spray Pond System COMPONENT ID (also LOAD COMPONENT 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 followed by a component number. The system preface is not necessarily the same as the system code described above. For component ids, the system preface corresponds to what the plant calls the component (e.g. IIPI, RI-IR). An example is IIPI 730, denoting valve number
(~ g 730 in the high pressure injection system, which is part of the ECCS. The component number is a contraction of the cornsonent number appearing in the plant piping and O' instrumentation drawings (P&lDs) anc electrical one line system drawings. LOCATION (also COMPONENT LOCATION and POWER SOURCE LOCATION) - L Refer to the location codes defined in Section 4.- COMPONENT TYPE (COMP TYPE)- Refer to Table' B 1 for a lisi of component type I codes. POWER SOURCE The component ID of the power source is listed in this field (see COMPONENT ID, above). In this data base, a " power source" for a particular component (i.e a load or a distribution component) is the next higher electrical distribution or i generating component in a distribution system. A single corr e ' t may have more than one power source (i.e. a DC bus powered from a battery and a W uy charger). POWER SOURCE VOLTAGE (also VOLTAGE)- The voltage "seen" by a load of a power source is entered in this field. The downstream (output) voltage of a transformer,
. inverter, or battery charger is used.
EMERGENCY LOAD GROUP (EMERG LOAD GROUP)i AC and DC load groups (or electrical divisions) are defined as appropriate to the 31 ant; 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 be powered from either of two AC load groups would be identified as AC/AB. DC load group follows similar naming conventions. T 96 12/88
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i TAllLE 111. COMPONENT TYPE CODES CO 51PONENT CO\1P TYPE VALVES: hiotor operated valve hiOV Pneumrtic (air operated) valve NV or AOV Hydraulic valve IIV Solenoid operated valve SOV hianual valve XV Check valve CV Pneumatic non retum valve NCV Hydraulic non return valve HCV Safety valve SV Dual function safety / relief valve SRV-Power operated relief valve PORY (pneumatic or solenold operated) PUhtPS: hiotor-driven pump (centrifugal or PD) hiDP Turbine-driven pump (centrifugal of PD) TDP Diesel driven pump (centrifugal of PD) DDP OTHER FLUID SYSTEM COMPONENTS: Reactor vessel RV Steam generator (U tube or once through) SG
, ' Heat exchanger (water to water HX, HX L
or water to air HX) Cooling tower CI' Tank TANK or TK Sump SUMP Rupture disk RD Orifice ORIF Filter or strainer FLT Spray nozzle SN Heaters (l.c. pressurizer heaters) HTR VENTILATION SYSTEM COMPONENTS: Fan (motor driven, any type) FAN Air cooling unit (air-to-water HX, usually ACU or FCU - including a t'an) Condensing (air conditioning) unit COND EMERGENCY POWER SOURCES: Diesel generator DG Gas turbine generator GT L Battery . BNIT . O 97- 12/88
i TABLE 111. COMPONENT TYPE CODES (Continued) I O CO MPONENT CO\1P TYPE ELECTRIC POWER DISTRIBUTION EQUIPMENT: Bus or switchgear BUS Motor control center MCC Distribution panel or cabinet PNL or CAB Transformer TRAN or XFMR Battery charger (rectifier) BC or RECT Invener INV Uninterruptible power supply (a unit that may UPS include battery, battery charger, and inverter) Motor generator MO Circuit breaker CD Switch SW Automatic transfer switch ATS Manual transfer switch MTS s s 9-. l l l l l l i i I 98 12/88-
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