ML20070Q519
| ML20070Q519 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/31/1988 |
| From: | Lobner P, Ryan D SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
| To: | NRC |
| References | |
| CON-FIN-D-1763, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-88-1995, NUDOCS 9103290105 | |
| Download: ML20070Q519 (132) | |
Text
{{#Wiki_filter:1 l 2 f*" *"% f g NUCLEAR POWER PLANT : rn 4j SYSTEM SOURCEBOOK l
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J i 1 i J CATAWBA 1 & 2 50 413 and 50 414 i i i l 1 .I j !O - . . . _ _.
= 9103290105 910327 -
PDR ADOCK 05000029 P PDR }I
SAIC 88/1995 l O' ga REG 9 A+ g g' , n NUCLEAR POWER PLANT
;I SYSTEM SOURCEBOOK
, . ..,. ,i
- %;**@**+,/ i i i CATAWBA 1 & 2 50 413 and 50 414 Editor: Peter Lobner Author: Deborah Ryan i Prepared for: ! U.S. Nuclear R2gulatory Commission-Washington, D.C. 20555 i Contract NRC 03 87 029 ! FIN D 1763 l l lO I M
l l 4 i Catawba 1 & 2
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TABLE OF CONTENTS O Sectinn Eags 1 S USINiAR Y DATA ON PLANT . . . . . . . . . . . . . . . . . . . , , . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 IDENTIFICATION OF SIhilLAR NUCLEAR POWUR PLANTS ........ 1 3 S Y STEh1 INFORhi ATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 3 3.1 Reactor Coolant System (RCS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 3.2 Auxiliary Feedwater (AFW) System and Seconcary S team Relief (S S R) System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 14 3.3 Emerg ency Core Cooling S ystem (ECCS) . , . . . . . . . . . . . . . . . .. . . . . . . . . . 21 3.4 Ch arging System (CVCS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 3.5 In strumentation and Con trol (I & C) System . . . . . . . . . . . . . . . . . . . . . . . . . . 35 3.6 Ele c tric Po we r Sy ste m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 3.7 Componen t Cooling Water (CCW) System . . . . . . . . . . . . . . . . . . . . . . . . . . . 59 3.8 Nu e1 ear S ervic e Water (NS W) S ystem............................. .... 68 4 PL ANT IN FORh 1 ATION . . . . . . . . . . . . . . . . . . . . . ., . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 4.1 S ite and B uildin g S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 4.2 Fa cili ty Layou t Drawing s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 4.3 S ee tion 4 R e ference s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77 ...... p 5 BIBLIOGRAPHY FOR CATAWBA NUCLEAR STATION ............... I14 "i APPENDIX A, Def'mition of Symbols Used in the System and Layout Drawings ........ . .............................................................. I15 APPENDIX B, Definition of Terms Used in the Data Tables................ 122 ) 1, 4 v i t
- i. 12/88
Catawba 1 & 2 LIST OF FIGURES l i Ficure g l 31 Cooling Water Systems Function Diagram for Catawba l Units 4 and2,................................................................. 7 3.1 1 Isometric View of a 4 Ioop Westinghouse RCS........... . .............. 10 l 3.1 2 Catawba Unit 1 Reactor Coolant System . . . . . . , . . . . . . . . . . . . . . . . . . . . . .. . . . I1 3,1 3 Catawba Unit 1 Reactor Coolant System Showing Component ! Loca ti o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .12 ........ 3.2 1 Catawba Unit 1 Auxiliary Feed water System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 17 3.2 2 Catawba Unit 1 Auxiliary Feedwater System Showing Component ' Loc a ti o n s . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 18 3.3 1-Catawba Unit 1 Safety injec tion Syste m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25-3.3 2 Catawba Unit 1 Safety Injection System Showing Component Loc a ti o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .26 .................. 4 3.3 3 Catawba Unit 1 Residual Heat Removal System.......................... 27 i V 3.3 4 Catawba Unit 1 Residual Heat Removal System Showing ; Component Locations..................,,,................................... 28 3.4- 1 Catawba Unit 1 Charging System . . . . . . . . . . . . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . 32 3.4 2 Catawba Unit 1 Charging System Showing Component locations..... 33 . 3.6 1 Catawba 14160 and 600 VAC Electric Power Distribution System ,.. 42 F 3,6 2_ Catawba 14160 and 600 VAC Electric Power Distribution System - Showing Component Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l 4 45 ! 3.6-3 Catawba 1 125 VDC and 120 VAC Electric Power Distribudon _ j System......................................................................... [ . 48: 1 3.6 4 Catawba 1 125 VDC and 120 VAC Electric Power Distribution System Showing Component Locations............ .... .................. 49 3.6 5_ Catawba 1 125 VDC Diesel Essential Auxiliary Power System......... - -50 3,6I6 Catawba 1 125 VDC Diesel Essential Auxiliary Power System Showing Component Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 3.6 Catawba 250/125 VDC Auxiliary Power Distribution System........... 52
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G 3.7-1 Catawba Unit 1 Component Cooling Water System ..................... 61 ii. -12/88.
1 Catawba 1 & 2 LIST OF FIGURES (continued) Eigure Eags' 3.72 Catawba Unit 1 Component Cooling Water System Showing Component Locattons,........................................................ 64 3.8 1 Catawba Unit .1 Nuclear Service Water System ..........................._- 70_ , 3.8 2 Catawba Unit 1 Nuclear Service Water System Showing Component Locations......................................................... 73 . 4-1 General View of Catawba Site and Vicinity. . .. ..... . . . ......... . .. . . ...... 78 42 Ca ta w ba S i t e M ap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . 79 3 43 Simplified Catawba S ite Plan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 80 44 Elevation View of Catawba Nuclear S tation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 81 l 4-5 Elevation View of Catawba Reactor Building.......,,..........., ,. .... 82 46 Elevation View of Catawba Refuelin j Pool . . . . . . . . . . . . . . . . . . . . . ........................................
. . . . .. . . . . . . . . . .g Canal and 83 Spent Fuel Storage ,
47 Catawba 1 Reactor, Auxiliary, and Fuel Buildings, Elevation 522 ft... 84-4S Catawba 1 Reactor, Auxiliary, and Fuel Buildings, Elevation 543 ft... -85
- 49 Catawba 1 Reactx Auxiliary and Fuel Buildings, Elevations 554 and .
l 560 ft.........................................................,................ 86 [ 4-10 Catawba 1 Reactor, Auxiliary and Fuel Buildings, Elevation'577 ft.... 87 4 11 Catawba 1 Reactor, Auxiliary and Fuel Buildings, Elevation 594 ft.'... 88 4 12 . Catawba 1 Reactor, Auxiliary and Fuel Buildings, Elevations 605 and 619 ft.....................................,.....................................,. 89 4 13 Catawba 1 Reactor, Auxiliary and Fuel Buildings, Roof... .............. :90 4 14 Catawba 1 Reactor and Diesel Generator Buildings, Elevations 556 and 594 ft....................................................................... 91 4 15 Catawba 2 Reactor, Auxiliary, and Fuel Buildings, Elevation 522 ft... 92-4 Catawba 2 Reactor, Auxiliary, and Fuel Buildings, Elevation 543 ft... - 93 4-17 Catawba 2 Reactor, Auxiliary and Fuel Buildings, Elevations 554 and 560 ft.......................................................................... 94 iii. 12/88'
- Camwba l & 2
/] LIST OF FIGURES (continued)
J Ficure P.ags , 4-1S Catawba 2 Reactor, Auxiliary and Fuel Buildings, Elevation 577 ft.... 95 4 19 Catawba 2 Reactor, Auxiliary and Fuel Buildings, Elevation 594 ft.... 96 4 20 Catawba 2 Reactor, Auxiliary and Fuel Buildings, Elevations 605 arid 619 ft........................................................................... 97 4-21 Catawba 2 Reactor, Auxiliary and Fuel Buildings, Roof................. 98 4 22 Catawba 2 Reac:or and Diesel Generator Buildings, Elevations 556 and 594 ft.................................................................... 99 4-23 Catawba 1 & 2 Service Water Pump Structure, Elevation 545 ft........ 100 4-24 Catawba 1 & 2 Service Water Pump Structure, Elevation 600 ft......., 101 4-25 Catawba 1 & 2 Service Water Pump Structure, Elevation 620 ft (Roof). ... ..... ... . ... ...... ..................................... 102 4-26 Elevation View of Catawba 1 & 2 Safe Shutdown Facility .............. 103 m
/
r 4-27 Catawba 1 & 2 Safe Shutdown Facilit
\ (Grade Level) . . . . . . . . . . . . . . .... ...................................
. . . . . . . . . .y, Elevation 594 ft 104 4-28 Catawba 1 & 2 Safe Shutdown Facility, Elevation 611 ft............, .. 105 4-29 Catawba 1 & 2 Safe Shutdown Facility, Elevation 623 ft................ 106 A-1 Key To Symbols In Fluid System Drawings . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . I18 A-2 Key to Symbols In Electrical System Drawings. ... .. .. . ... . .... ... .... . . 120 A-3 Key to Symbols in Facility Layout Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 121
( iv. 12/88
Catawba 1 & 2 n LIST OF TABLES i ( t
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TaNe Eagt 31 Summary of Catawba Systems Covered in this Report................. . 4 3.1 1 Catawba 1 & 2 Reactor Coolant System Data Summary for Selected Components.................................................................... 13 3.2 1 Catawba 1 & 2 Feedwater System Data Summary for Selected Components....,.............................................................. 19 3.2 2 Catawba Auxiliary Feedwater System Water Sources.................... 20 3.3-1 Catawba 1 & 2 Emergency Core Cooling System Data Summary for S e l e c t e d Compon e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 3.4 1 Catawba 1 & 2 Charging System Data Summary for Selected Companents.,................................................................. 34 3.5-1 Listing of Components Controlled by Auxiliary Shutdown Panels..... 38 3.6 1 Catawba 1 & 2 Electric Power System Data Summary for Selected Components.................................................................. 53 O 3.6-2 Listing of Electrical Sources and Loads at Catawba 1 & 2............... 55 V 3.7-1 Catawba 1 & 2 Component Cooling Water System Data Summary for S elec ted Compon e n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67 3.8-1 Catawba 1 & 2 Nuclear Service Water System Data Summary for Selected Components . . . . . . . . . . . . . . . . . . . . ................................ ~76 41 Definition of Catawba 1 Building and to .aon Codes................... 107 4 4-2 Partial Listing of Components by Location at Catawba 1 & 2........... I10 B-1 Co m pon e n t Typ e Cod e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 123 p% b
- v. 12/88
I Catawba 1 & 2 1 O CAUTION 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 renects the plant configuration at the time the information was obtained, however, the information in this document has not been independently verified by the licensee or the NRC. NOTICE This sourcebook will be periodically updated with new and/or replacement pages as appropriate to incorporate additional information on this reactor ', plant. Technical errors in this report should be brought to the attention of the following: Mr. Mark Rubin U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation - Division of Engineering and Systems Technology-Mail stop 7E4 b d Washington, D.C. 20555 - With copy to: Mr. Peter Lobner Manager, Systems Engineering Division Science ApplicationsIntemationalCorporation 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. f~ i r 4 vi. 12/88 _ . _ - , _ .;._...;.._.- , , . . , - . , , . .. a ,
E. CATAWBA 1 & 2 RECORD OF REVISIONS l REVISION ISSUE COMMENTS 0 12/88 Original report O O s ji. 13fgg
Catawba 1 & 2 CATAWBA 1 & 2 SYSTEM SOURCEBOOK O This sourcebook contains summary information on the Catawba nuclear power plant. Summarv data on this plant are presented in Section 1, and similar nuclear power plants are iden'tified in Section 2. Information on selected reactor plant systems is presented in Section 3, and the site and building layout is illustrated in Section 4. A bibliography of reports that describe features of this plant or site is presented in Section 5. Symbols used in the system and layout drawings are defined in Appendix A. Terms used in the data tables are defined in Appendix B.
- 1.
SUMMARY
DATA ON PLANT Basic information on the Catawba 1 & 2 nuclear power plant is listed below: Docket number 50-413 (Unit 1),50-414 (Unit 2) Operator Duke Power Company Location Clovcr, South Carolina Commercial operation date 6/85 ' Unit 1),8/86 (Unit 2) Reactor type PWR NSSS vendor Westinghouse Number of loops 4 Power (MWt/MWe) 3411/1180 Architect engineer Duke Power Company Containment type Reinforced concrete cylinder with steel liner, ice condenser
- 2. IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS Each Catawba unit has a Westinghouse PWR four loop nuclear steam supply system (NSSS) with an ice condenser containment. Other four loop Westinghouse plants in the United States include:
Braidwood 1 and 2
- Byron 1 and 2 Callaway Comanche Peak I and 2 Donald C, Cook 1 and 2 (ice condenser containment)
Diablo Canyon 1 and 2 l - Haddam Neck 1 - Indian Point 2 and 3 McGuire 1 and 2 (ice condenser containment) Millstone 3 Salem 1 and 2 Seabiook 1 Sequoyah I and 2 (ice condenser containment) - Shearon Harris 1 and 2 South Texas 1 and 2 Trojan Vogtle I and 2 Watts Bar 1 and 2 WolfCreek Yankee Rowe 4 - Zion 1 and 2 - i /3 V Catawba differs from the majority of Westinghouse plants in that its containment is an ice condenser, rather than the more common dry containment. Catawba is similar to other
- 1 12/88 I
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[ - Catawba 1 & 2 plants in the number and type of charging and high pressure injection ? umps. The nuclear j senice water and component cooling water system is shared between tae two units. l 4 I I 1 t i i 4 1 l 4 1 i 1 1 a 1 1 li 1 i 1 k-i a i t i i i i i )- 3 I 5 i I l , 2 12/88 i i. 4 __ _ _-. _ . _ , . . _ - - - . . , _ , . _ _ . . . - . . . , - _ _ . . _ . . _ . . - . _ _ - , _ . _ . . _ , _ _ - , _ . . - - . - . _ - . . . _ . _ , _ , . ~ . . .
o r Catawba 1 & 2 ' <
- 3. SYSTEM INFORMATION This section contains descriptions of-selected systems at Catawba in terms of.
general function, operation, system success criteria, major components, and support , system requirements. A summary of major systems at Catawba is presented in Table 31, In the " Report Section" column of this table, a section reference (i.e,3.1, 3.2, etc.) is l, 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 referer.ce is provided to the section of the Final Safety Analysis Report where additional information on each system can be found. Other sources of mformation 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 coolinj; water systems required for safe shutdown are shown in Figure 31. Details on the indivic ual coohng water syster.1s are provided in the report sections identified in Table 31, i i 3 '12/88
O > 9 Table 3-1. Summary of Catawha Systems Covered in this Report . Generic Plant-Specific Report FSAR Section System Name System Name Section Reference i Reactor IIcat Removal Systems Reactor Coolant System (RCS) Same 3.1 5
- Auxiliary Feedwater(AFW)and Same 3.2 10.4.9 Secondary Steam Relief (SSR) !
Systems
]
Emergency Core Cooling Systems (ECCS)
- High-Pressure Injection L Safety injection System 3.3 - 6.3
& Recirculation
- Low-pressure Injection
&. Recirculation >
^
- Decay IIcat Removal (DIIR) Same '3.3 6.3 'i System (ResidualIIcat Removal (RHR) System)
- . Main Steam and Power Conversion Main Steam Supply System,' X 10- ,
Systems
. Condensate and Feedwater System, Circulating Water System -
- OtherIIcat Removal Systems - None identified X Reactor Coolant Inventory Control Systems .
- ' Chemical and Volume Control System. Same 3.4 9.3.4
'(CVCS)(Charging System)
- . - ECCS See ECCS, above - -
.$=
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. - -. . - - --- : -~. - L. .. . . _ . .-_.; -
O O O Table 3-1. Summary of.Catawha Systems Covered in Ihis Report (Continued) Generie Plant-Specifie Report FSAR Section System Name System Name Section Reference Containment Systems Containment Same X 6.2 Containment IIcat Removal Systems
- Containment Spray System Same X 6.2.2, 6.5.2
- Containment Fan Cooler System Containment Air Retum Fan System X 6.2.2
- Containment Nomul Ventilation Systems Containment Purge Ventilation X.. 9.4.5, 9.4.6 System, Containment Ventilation System
- ' Combustible Gas Control Systems flydrogen Sample and Purge System X 6.2.5
- v. .
Other Containment Systems . Ice Condenser System X 6.7 Reactor and Reactivity Control Systems Reactor Core Same X .4
- Control Rod System Control Rod Drive System X 4.6 i ration Systems See CVCS,above - -
Instrumentation & : Control (I&C) Systems
-- Reactor Protection System (RPS)' ReactorTrip System (RTS) 3.5 . 7.2 Engineered Safety Feature Actuation - Same- 3.5 7.3 Svstem (ESFAS)
- Remote Shutdown System ' Auxiliary Shutdown Panels, 3.5 7.4.7
, Auxiliary Feedwater Panel,
- Turbine Control Fanel i
m . _ . . . , _ . . _ ._ .-_ - ---
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b
, Table 3-1. Summary of Catawha Systems Covered in this Report (Continteed)
Generic Plant-Specific Report FSAR Section 2 System Name System Name Section Reference Instrumentation & Control (f&C) Systems (continued)
- Other I&C Systems X 7.6, 7.7 Various systems Support Systems
- Class 1E Electric Power System same 3.6 8.2,8.3 1
Non-Class IE Electric Power System .Same 3.6 3.2,8.3 Diesel Generator Auxiliary Systems ' -Same 3.5 8.3,9.4.4,9.5.4 to 9.5.8 .
- Component Cooling Water'(CCW) Same 3.7 9.2.2
. System cs .. .
. Service Water System (SWS) Nuclear Service Water System 3.8 9.2.1 i - Other Cooling WaterSystems ' Conventual Imw Preer- X 9.2.8 Service WaterSystem .;
- - Fire Protection Systems- Same' X 9.5.1 L i --
, - - : Room Heating, Ventilating, and Air- < Air Conditioning, Heating, X . 9.4 '!
Conditioning (HVAC) Systems Cooling and Ventilation Systems + - Instrument and Service AirSystems Compressed AirSystem' 'X 9.3.1 g . Refueling and Spent Fuel Systems Same' X 9.1 Radioactive Waste Systems . 'Same X 11 1 t . . . . .
'I 1 s' Radiation Protection Systems Same- X- 12 r -
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-4 CCWS HEAT ) i EXCHANGERS i
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b Figure 3k1. Cooling Water Systerns Functional Diagram for Catawba Units 1 and 2 i-
i Catawba 1 & 2 3.1 REACTOR COOLANT SYSTEM (RCS) ' 0 ' 3,1.I System Function The RCS transfers heat from the mctor core to the secondta coolant system via the steam generators. The RCS pressure 1 - andary also establishes a b'arrier against the i uncontrolled release of radioactive material fnar the reactor core and primary coolant. 3.1,2 System Definition 4 The RCS includes: (a) the reactor vessel, (b) reactorloolant loc os, (c) reactor coolant pumps, (d) the primary side of the steam generators, (e) pressurizer, and (f) l connected piping out to a suitable isolation valve boundary. An isometric drawing of a 4e loop Westinghouse RCS is shown in Figure 3.1-1. Simplified diagams of the RCS and l ' important system interfaces are shown in Figures 3.12 and 3.1-3. A eummary of data on selected RCS components is presented in Table 3.1 1. 3.1.3 System Oneration - r, e During power operation, circulation in the P.L'S is maintained by one reactor- i coolant pump m each of the four reactor coolant loops. RCS pressure is maintained within a prescribed band by the combined action of pressurizer heaters and pressurizer spray. i RCS coolant inventory is measured by pressurizer water levei which is maintained within a presenbed band by the chemical and volume control system (charging system). At power, core heat is transferred to secondary coolant (feedwater) in the steam - generators. The heat transfer path to the ultimate heat sink is completed by the main steam and power conversion system and the circulating water system. Following a transient or small LOCA (if RCS inventory is maintained), reacter 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 uhimate heat sink can be established by using the secondary steam relief system (see Section 3.2) to vent main steam to atmosphere when the power conversion and circulating water systems are not available. If reactor core heat removal by this alternate path is not - adequate, the RCS pressure will increase and a heat balance will be established in the RCS by venting steam or reactor coolant to the containment'through the pressurizer rdief valves. There are three power-operated relief valves (each in series with a motor operated block ! valve), and three safety valves on the pressurizer. A continued inability tc establish.- adequate heat transfer to the steam generators will result in a LOCA like condition (i.e. ' continuing loss of reactor coolant thro':2h the pressurizer relief valves).qRe of these relief valves has resulted in valve failure (i.e. relief valve stuck open)peated cycling - Following a large LOCA, reactor core heat is di' .iped to the containment as reaetor coolant ai,d ECCS makeup water spills from the bres.LFor a short term period, the : containment can act as a heat sink; however, the containmc.nt cooling sy:tems must operate in order to complete a heat transfer path to the ultimate heat sink. 3.1.4 Svstem Success Crlierta mitigation, The RCS success criteria can be described in terms of LOCA and transient - as follows:
. a 8 -12/88'
-l l
4 b
w u - Catav,b 1 & 2 An unmitigatible LOCA i not initiated. 1 if a mitigatible LOCA is initiate.4, 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 emition (i.e. stuck open safety or relief valve, reactor cwlant pump seal failure), and ; LOCA mitigating systems are successful. 3.1.5 C2mponent Informntion A.RC5
!, Volume: 12,516 ft3,includin
- 2. Nominal opersting pressure: g pressurizer ant s@c t',ne 2,235 psia B. Pressurizer
- 1. Nomtal water volume: 1,350 ft3
- 2. Normal as F volume: 450 ft3 C. Safety Valver (3)
- 1. Set pressute: 2,485 psig
- 2. Relief canacity: 420,000lb/hr each D. Power Operated Relief Valves (3)
- 1. Design pressure: 2,485 ps
- 2. Reli capacity: 210,000 reach E. Steam Generators
, 1. Type: Vertical Shell and U Tube
- 2. hiodel: Westinghouse $1 Series F. Pressurizer Heaters
- 1. Capacity: 1,800 kW 3.1.6 Ouocort Systems and Interfaces A, Motive Power
- 1. The pressurizer heaters are Non Class IE AC loads that are supplied from blackout switchgear groups IFTA and IFTB via pressurizer heater panels PHPl A and PHPlD, respectively, As described in Section 3.6, the blackout buses are not automatically reenergized by the diesel generators when normal power is lost.
2 The reactor coolant pumps are supplied from Non Class IE switchgear, B . Reactor Coolant Pump Sr.1 Injection Water System The chemical and volume control system supplies seal water to cool the reactor coolant pump shaft seals and to maintain a controlled inleakage of seal water I into the RCS. Loss of seal water flow may result in RCS leakage through the pump shaft seals which will resemble a small LOCA. I O V 9 12/88
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\ AUXILIARY FEEDWATER (AFW) FYSTEM AND SECONDARY l STEAM RELIEF (SSR) SYSTEM l
3.2.1 System Function The AFW system provides a source of feedwater to the steam generators to remove heat from the reactor coolant system (RCS) whem (a) the main feedwater system is not available, and (b) RCS pressure is too high to pennit heat removal by the residual heat removal (RHR) system. The SSR system provides a steam vent path from the steam generators to the atmosphere, thereby completing the heat transfer path to an ultimate heat sink when the main steam and power conversion systems are not available. Together, the AFW and SSR systems constitute an open loop fluid system that provides for heat transfer from the RCS following transients and small break LOCAs. 3.2.2 System Definition The AFW system consists of two motor driven pumps and one turbine driven pump. Water is supplied from several sources on a priority based on water quality. These sources melude Upper Surge Tanks, Condensate Storage Tank, Condenser Hot Well, Nucleai Service Water Systems A and B and a Condenser Circulating Water System. Each AFW pump can supply all four steam generators. The SSR system includes five safet relief valve on each of the four main steam lines.y valves and one power operated pressure Simplified drawings of the ARY and SSR systems are shown in Figures 3.21 and 3.2 2. A summary of data on selected AFW system components is , resented in Table 3.21. A summary of information on potential water sources for t1e AFW symm is presented in Table 3.2 2. O 3.2.3 System Oneration During normal operation the ARV system is in standby, and is automatically actuated on either a low low level in any two of four steam generators, a safety injection signal, a loss of both main feedwater pumps, or a loss of offsite and station normal auxiliary power. The system also can be manually started from the control room. The motor drivt n AFW pumps are 600 brake horsepower units, and the turbine driven AFW pump is 1160 a brake horsepower unit. The turbine driven AFW pump is capable of providing 1000 gpm at 3217 feet head, which is nearl twice the capacity required for ARV system success. This pum + cooling and lubrication independently of AC aut power when?AC is capable of supply ng its own power s available backup pumps are provided fer oil is available for room air cooling. pressure and waterjacket cooling, and a fa ptoviding 500 gpm at 3210 feet of head each. They require nuclear service wi.ter for j cooling (Ref.1). The preferred suction sources include the condensate storage tank, upper surge tank, and condenser hotwell. Redundant flow paths from these sources meet at a common i header which supplies all three pump; No single valve can block the flow path, in the i event of low suction pressure, there is automatic switchover to the Condenser Circulating j Water S,upply, if desired, nuclear sersice water valves may be manually opened to supply
- the turbine driven pu,mp.
- Motor dnven nump 1 A normally supplies Steam Generators 1 and 2, while pump 2A supplies Steam benerators 3 and 4. Two normally closed valves may be opened manually to allow the motor driven pumps to feed any of the steam generators. The turbine uriven pump may supply any of the steam generators, but norma ly would supply
, B and C which return steam to drive the pump turbine, i. 14 12/88 i e i
l l Cataw ba 1 & 2 3.2.4 System Success Criteria AFW system success enteria are defined as delivery of 470 ppm to a minimum of two steam generators before the provided by any on ARY pump. y boil The SSR dry (about system 25 minutes). must operate to complete This flow rate the heat can be transfer path to the environment. The number of safety valves that must open for the decay heat removal function is not known. Ordinarily, the AFW system is nquired to operate for about 2 hours to maintain the RCS at hot standby followed by cooldown to approximately 350*F and 415 psia, at which time the residual heat removal (RHR) system may be operated (Ref.1). 3.2,5 Comnonent Information A. Motor driven ARV pumps PI A and PIB
- 1. Rated now: 500 ppm @ 3210 ft, head (1,392 psid)
- 2. Rated capacity: 1007c (Ref. 2)
- 3. Type: Centrifugal, horizontal B. Turbine driven AFW pump
- 1. Rated flow: 1000 gpm @ 3217 ft. head (1,395 psid)
- 2. Rated capacity: 1007c (Ref. 2)
- 3. Type: Centritupal, horizontal C. Condensate grade sources
- 1. Maximum capacity: 297,500 gallons (combined, See Table 3.2 2)
D. Secondary steam relief valves ( t
- l. Five s'afety valves per main steam line
- 2. One power eperated relief valve per main steam line 3.2.6 Sunnort Systems and Interfaces A. Control Signals
- 1. Automatic The motor driven AFW pumps are automatically actuated based on the following signals:
low low water level in any two of four steam generators safety in.}ection signal loss of offsite power and station normal auxiliary power loss of both main feedwater pumps The turbine driven AFW pump starts automatically with the following signals: low low water levels in any two of four steam generators loss of offsite power and station normal auxiliary power i The water source for the ARV pumps is automatically switched to the Nuclear Service Water system on low pump suction pressure.
- 2. Remote manual The ARY system can be actuated by remote manut1 means from the main control room, from the auxiliary shutdown panels, as well as locally at the pumps.
15 12/88 4
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1 Catawba 1 & 2 g B. Motive power .N . The AFW motor driven pumps and motor operated valves are Class lE AC loads that can be supplied from the standby diesel generators as l described in Section 3.6. Redundant loads are supplied from separate load groups. 1
- 2. The AFW turbine driven pump is driven by steam from steam generators 1B and IC.
! C. Other
- 1. Cooling for the motor-driven AFW pumps is provided by motor coolers supplied with 30 ppm of nuclear service water (see Section 3.8).
Cooling for the turbine driven pump is provided locally.
- 2. Lubrication is pavided locally for all pumps.
3.2.7 Section 3.2 References
- 1. Fresco. A., Youngblood, R. and Fapazaglou, l.A., " Review of the Catawba Units 1 and 2 Auxiliary Feedwater System Reliability Analysis," NUREG/CR.
3297. BNL'NUREG 51675, Brookhaven National Laboratory, October 1983.
- 2. Catawba Nuclear Station FS AR, Section 10.4.9.
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i i Table 3.2-1. Catawba 1 & 2 Auxiliary Feedwater System Data J aamary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCAMON LOAD GRP. ' AFW-116A - MOV AFWPMRM UNKtJOWN 600 ASWGHM 4 AC/A ) AFW-15A MOV AFWPMRM UNKNOWN 600 AMCCRM577 AC/A , AFW-174 MOV AFWPMPM MCC1SMXG 600 SSF SSF AFW-175 MOV AF WPMRM MCC1SMXG 600 SSF SSF AFW-178 MOV (G MCC1SMXG 600 SSF SSF . AFW-188 MOV AFWPMHM UNKNOWN 600 BMCCRM560 AC/B
- AFW-250A MOV AFWPMRM UNKNOWN 600 ASWGRM AC/A AFW-3108 MOV AFWFMRM UNKNOWN 600 BSWGW AC/B
, AFW-428 MOV ODH UNKNOWN 600 BSWGRM AC/B AFW-468 MOV IDH UNKNOWN 600 BMCCRM560 ACIB l 4 - AFW-50A MOV IDH UNKNOWN. 600 AMCCRM577 AC/A 2 m l AFW-548 MOV ICF UNKNOWN 600 BMCCRM560 AC/B * ] AFW-58A MOV IDH UNKNOWN 600 AMCCRM577 AC/A } AFW-62A . MOV ODH UNKNOWN 600 ASWGRM AC/A i AFW-858 MOV AFWPMRM UNKNOWN 600 BMCCRM560 AC/B t AFW-P1A MDP AFWPMRM BUS 1 ETA 4160 ASWGRM AC/A AFW-PIB MDP AFWPMRM BUS 1ETB 4160 BSWGRM AC/B AFW-TD1 TDP AFWPMRM + i i r M .
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gO Table 3.2 2. Catawba Auxiliary Feedwater System Water Sources G Capneities (Gallone Source Safety Grade Normal Maximum
- 1. Upper Surge Tanks No $5,000 85,000
- 2. Condensate Storage Tank No 42,500 42,500 (Sharec' intween both units)*
- 3. Condenser Ilot Well No 170,000 170,(X)0
- 4. Nuclear Senice Water System Yes Nuclear Service Water Pond (2,74x108 gal)
- 5. Condenser Circulating Water No 3 Day Supply System '
- An additional 30,000 gal. (maximum)is available from the condensate storage tank when the condensate tank pumps are available to fill the upper surge tankt.
Source: Reference 1. . V da
- )
Catawba 1 & 2 3,3 EMERGENCY CORE COOLING SYSTEM (ECCS) , 3.3.1 System FunctI D.D j The ECCS is an integrated set of subsystems that perform emergency coolant injection and recirculation functions to maintain reactor core coolant inventory and adequate decav heat removal following a LOCA. Th. coolant injection function is performed during a refatively short term period after LOCA initiation, followed by realignment to a recirculation moJe of oxration to maintain lonF term, post LOCA core cooling. Heat from the reactor core is transferred to the containment. The heat transfer path to the ultimate heat sink is completed by the containment cooling systems, t 3,3,2 System Defintilon ine emergency coolant injection (ECl) function is perforned by the following ECCS subsystems: Passive cold leg aceumulators Upper head injection accumulators Safety injection (SI) system
- Residual heat removal (RHR) system The emergency coolant recirculation (ECR) function is performed by the RHR system.
The Si system and the centrifugal charg ng pumps provide high pressure coolant injection capability. The RHR pumps perform the low pressure injection function. The Refueling Waar Storye Tank (RW ST)is the water source for both the high and low pressure injection systems. Both systems inject coolant into all four RCS cold legs as their 1 primary flow paths. The SI system can also inject into all four hot legs, while the RHR system can inject into two hot legs. After the injection phase is completed, recirculation (ECR) is performed by the RHR pum cold legs.Decay ps drawing st.etion from the containment sump and dischargmg heat is transferred to the component cooling water system by the RHR into the RC - heat exchangers. Th: RHR pumps can be aligned to deliver water to the suction of the SI
- and centrifugaler , jumps for high pressure recirculation. The RHR pumps can also i provide flow to the containment sprav system.
Simplified drawings of tiie safety injection system are shown in Figures 3.31 i and 3.3 2. The residual heat reinovel s stem is shown in Figures 3,3 3 and 3,3 4. Interfaces between the accumulators, the ecd"S injection and recirculation subsyste the RCS are shown in Section 3.1. A summary of data on selected ECCS cornponents is presented in Table 3.31. The charging sutem i described in Section 3.4.
. 3,3 Svstem Onernflon During nomial operation, the ECCS is in standby. Following a LOCA, the four - ,
borated water to the RCS as cold leg injection accumulators (one for each loop) supply (approx soon as RCS pressure drops below accumulator pressure . A safety injection signal (SIS) automatically starts the two centrtfugal charging pumps, the two safety injection pumps, and the two RHR pumps, and aligns the chargmg pumps for injection; The charging pump i j , i are normally pumps gned aretoab, take suction aligned into the cold to on the RWST.inject ,s n ect nto the four RCS col legs, but can be aligned for hot leg injection.- All For small breaks, operator action can be taken to augment the RCS depressurinSon by utilizing the secondary ste.m dump capability and the auxiliary feedwater (AFW) system (i.e., depressurization due to rapid heat transfer from the RCS). The changeover from injection to recirculation is initiated automatically by a low RWST level signal, and completed manually by the operator in the main control room. The 21 12/88 _m.,,,,%- .,--v ..-c .---#.-v ,.~,.m.e-4~ . , ..m r.e, - ~%.e- ., e , w y- ,v wn wm -o wo , e ,< w
I l Catawba 1 & 2 r~ 1 ( s automatic functions include opening the containment sump isolation valves and closing the l isolation valves for the RWST to the RHR pump suction so that the RiiR pumps draw on 1 the containmem sump. The Si as well as centrifugal charging pumps contmue to draw on the RWST, and all systems continue to inject directly to RCS cold legs. Manual action is required to establish a high pressure recirculation Dow path. This involves aligning the Si and centrifugal charging pum? suctions to the discharge of the RiiR pumps. Following reallpnment, now from the R FIR pumps can supply the two centrifugal charging pumps whten inject into the RCS cold legs; and the SI pumps which can inject into the RCS cold leps or hot legs. Approximate y 4 hours after the reactor shutdown, hot leg recirculation is initiated to ensure termination of telling and preclude excessive boron concentration in the reactor vessel. 3.3.4 System Success Criterin LOCA mitigation requires that both the emergency coolant injection and emergency coolant recirculation functions be accomplished. The EC1 success criteria for LOCAs are not clear in the Cataw ba FSAR, however, the following is noted: A .375 inch diameter break is the maximum break size for which the normal makeup system can maintain the pressurizer level and the normal reactor coolant system pressure of 2250 psia. For a break of this size, ona centrifugal charging pump is adequate to sustain pressure level at an RCS ,sressure of 2250 psia, This break results in a loss of approximately 17.5 lb/see (127 ppm at 130 F and 2250 psia) tref.1). For a small break LOCA the high head portion of the ECCS, together with the p accumulators, provide sufficient core Gooding (Ref.1). For a large break LOCA in which the break is in one injection path, three accumulators, one enarging pump, one safety injection pump, and one residual heat removal pump provide sufficient core flooding (Ref. 2). 3.3.5 Conmonent Information A. Safety injection (high pressure) pumps l A and 1B
- 1. Design Dow: 400 ppm @ 2,540 ft head (1,101 psid)
- 2. Rated capacities: 1009
- 3. Discharge pressure at shutoff head: 3,545 ft head (1,537 psid)
- 4. Type: honzontal centrifugal B. Residual heat remo.al (low pressure) pumps l A and IB
- 1. Design Dow: 3,000 ppm @ 375 ft. head (163 psid)
- 2. Rated capacities: 100%
- 3. Type: verticalcentrifugal C. Cold leg injection accumulators (4)
I. Accumulator volume: 1,350 ft3 each
- 2. Minimum water volume: 1,000 ft3 each
- 3. Design operating pressure: 700 psig
- 4. Nominal boric acid concentration: 2,000 ppm (G
22 12/88
1 i Catawba 1 & 2 D. Upper head injection accumulators
- 1. Number: 1 gas filled '
I water filled j 2. Operating pressure: 1250 psia ) 3. Accumulatorvolume:1800ft3 , 4. Boron concentration in liquid filled tank: 1900 to 2100 ppm , , E. Upper hecd injection surge tank (1) 1
- 1. Nominal pressure: 1000 psia
- 2. Useable volume: 35 ft3
- 3. Boron concentration: 2100 ppm max F. Refueling water storage tank
- 1. Capacity: 350,000 gallons (minimum volume)
- 2. Design pressure: Atmospheric -
- 3. Minimum boron concentration: 2,000 ppm G. RHR heat exchangers lA and lH 30.5 x 106 Btu /hr
- 1. Type:
- 2. Design capacity:U Shell and tube
] 3.3.6 Suonort Systems and Interfaces - A. Control signals i ' 1. Automatie
- a. The ECCS injection subsystems are automatically actuated by a safety injection signal (SIS). Conditions initiating an SIS trip are:
4 - 1.ow pressurizer pressure High comainment pressure Lov steam line pressure Manual actuation
- b. Te SIS automatically initiates the following actions:
starts the diesel generators i - starts the chargi,ng, SI, and RHR pumps aligns the charging pumps for injection L -- closes all feedwater control valves - trips main feedwater pumps
-closes main feedwater ? ump discharge valves aligns RHR heat exc1 anger bypass and valves to provide flow through the heat exchangers
- c. Switchover to the recirculation mode occurs automatically on low level in the RWST. -
- d. UHI injection following a large LOCA is terminated by a low level in-the UH1 accumulators.
- 2. Remote manual An SIS signal can be initiated by remote manual means from the main control room 1The transition from the injection to the recirculation phase of -
ECCS operation can be initiated by remote manual means. 23: 12/88 = ,
Catawba 1 & 2 f 3. hianual action is required to realign the charging and safety injection pumps for high pressure recirculation. B. hiotive Power
- 1. The ECCS motor-driven aumps and motor operated valves are Class 1E AC loads that can be suppliec from the standby diesel generators as described in Section 3.6.
C. O6er
- 1. Each Si, RiiR, and charging pump is cooled by the Component Cooling Water system (see Section 3.7),
- 2. The RHR heat exchangers are cooled by the Component Cooling Water system (see Section 3.7).
- 3. Lubrication is provided locally for the SI, RIIR, and charging pumps and motors.
- 4. Pump room coolers transfer hcat to the Nuclear Service Water System (see Section 3.8).
3.3,7 Section 3.3 R@rences ! 1. Catawba Nuclear Station FSAR, Section 6.3.
- 2. Reference Safety Analysis Report 3S, Westinghouse Nuclear Energy Systems, St ction 6.3.3.2.
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O O C Table 3.3-1. Catawba 1 & 2 Emergency Core Cooling System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. RH-136B MOV SIPMRMB UNKNOWN 600 BMCCRM560 AC/B RH-1848 MOV MPENRM543 UNKNOWN 600 AMCCRM577 AC/A RH-185A MOV MPENRM543 UNKNOWN 600 AMCCRM577 AC/A RH-28A MOV HXRMA UNKNOWil 600 AMCCRM577 ACIA RH-32A - MOV HXRMA UNKNOWPJ 600 AC/A RH-650 MOV HXRMB UNKNOWN 600 AC/B RH-PIA MDP RHRPMRMA BUS 1 ETA 4160 ASWGRM AC/A i RH-P1B MDP RHRPMRMB BUS 1ETB 4160 BSWGRM AC/B 5 -1008 MOV SIPMRMB UNKNOWN 600 BMCCRM560 AC/B SI-103A MOV SIPMRMA UNKNOWN 600 AMCCRM577 AC/A g SI-118A MOV S~PMRMA UNKNOWN 600 AMCCRM577 AC/A SI-121 A MOV MPENRMSA3 UNKNOWN 600 AMCCRM577 AC/A SI-1058 MOV SIPMRMB UNKNOWN 600 BMCCRM560 AC/B SI-150B MOV SIPMRMB UNKNOWN 600 BMCCRM560 AC/B SI-1528 MOV MPENRM543 UNKNOWN 600 . BMCCRM560 AC/B SI-162A MOV MPENRM553 UNKNOWN 600 AMCCRM577 AC/A SI-PTA MDP SIPMRMA BUS 1 ETA 4160 ASWGRM AC/A SI-P1B MDP SIPMRMB BUS 1ETB 4160 BSWGhli AC/B SI-RWST TK RWST W N b 03 [
Catawba 1 & 2 3.4 Cll ARGING SYSTEM (CYCS) 3.4.1 Ssstem Function The charging system is part of the Chemical and Volume Control System (CYCS). The CYCS 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 assumed to be required to maintain the plant in a long term hot shutdown condition. The centrifugal charging pumps also operate as part of the ECCS in the event of a LOCA. 3.4.2 System Definiflon The CYCS provides a means for injection of control poison in the form of teric acid solution, chemical additions for corrosion control, and reactor coolant cleanua and degasification. This system also adds mak:up water to the RCS, recycles water triat is letdown from the RCS, provides seal water injection to the reactor coolant pump sealc, and perfonns an emergency core cooling function. The CYCs consists of several subystems: the charging, ledown, 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 C\ CS are perfonned by the following components the charging pumps,(two centrifugal, one positive displacement), boric acid transfer pumps, volume control tank, boric acid tanks, and various heat exchangers and deminerahrers. 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 3A 1. y 3.4.3 System Oneration During nonnal plant operation, one charging pump (the positive displacement pump)is running with its suction aligned to the Volume Control Tank (VCT). The letdown now from a RCS cold leg is cooled in the shell side of the regenerative heat exchanger, then directed to the VCT. Part or all of the letdown now heading for the VCT may be directed to the Boron Recycle System. The reactor makeup control system maintains the desired inventory in the VCT The bulk of the charging flow is pumped back to the RCS through the tube side of the re;;:nerative heat exchanger via two chargmg lines. Portions af the charging flow are directec to the reactor coolant pumps through a seal water injection filter. The charging system can be aligned as an auxiliary source for pressurizer spray. The centrifugal charging pumps also provide hi;;h head injection as part of the ECCS (see Section 33). During a LOCA the CVCS is iso.ated except for the centrifugal I charging pumps and the piping in the safety injection path. The pumps take suction on the Refueling Water Storage Tank (RWST) and inject into all four cold legs. The reciprocating (positive displacement) charging pump is also used to perfomi hydrostatic tests which verify the integrity of the RCS. 3,4.4 System Success Criteria For post transient makeup to the RCS the following charging system success criteria is assumed: A long-tenn water source must be available to the charging pumps. One of three charging pumps is available. A makeup path to the RCS is available. O 30 12A18
i 3 a t
- Catawba 1 & 2 3.4.5 Comoonent Information 8
A. Centrifugal charging pumps 1A and IB
- 1. Design flow: 150 @ 5,800 ft head (2,514 psig)
- 2. Rated capacity: 100%
- 3. Type: centnfugal i
D. Reciprocating charging pump ,
- 1. Cesign flow: 98 gpm
- 2. Rated capacity: 100% (for nonnal charging funedon)
- 3. Type: positivedisplacement 3,4,6 Suonort Systems and Interfaces
?
A. Control Signals
- 1. Automatic
- a. The centrifugal charging pumps are automatically actuated by a safety e injection si;nal(SIS),
i 2. Remote Manua
- a. The charging pumps can be actuated by mmote manual means from the '-
contml room. B. Motive Power
- l. The centrifugal charging pumps and motor operated valves of the CVCS.
are Class lE AC loads that can be supplied from the standby diesel generators as described in Section 3.6
- C. Other
- 1. The centrifugal charging pumps are cooled by the Component Cooling Water system (see Secuon 3.7).
i 2. Pump
- 3. Pump roomlubrication coolers transfer isheat provided to t locally,he Nuclear Service Water S l Secuon 3.8).
l 3,4,7 Section 3.4' References '
- 1. Catawba Nuclear Station Final Safety Analysis Report, Sections 6.3 and 9.3.4. -
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U(-- b u Table 3.4-1. Catawba 1 & 2 Charging System Data Summary for Selected Components COMPONENT ID COMP. LOCATIOri POWER SOURCE VO LT A G E POWER SOURCE EMERG. TYPE LOC A TION LOAD GRP. CV-10B MOV FAPErJHM543 UNKtJOYni 600 BMCCHM560 AQB CV-19A MOV MPEtJHM543 UNKrJOVnJ 600 AMCCHM577 ADA CV-252B MOV S!ITAHMB UNKNOVnJ 600 AMCCIO.1577 AQA CV-253B MOV Sitt1HMB UNMNOVnJ 600 EMCCHM560 ACB CV-P1 A MDP CHPMHMA BUS 1EIA 4160 ASWGHM AQA CV-P1B MDP CHTMHMB BUS 1EIB 4160 B5WGIM AC/B s sa n
Catawba 1 & 2 3.5 INSTRUMENTATION AND CONTROL (1 & C) SYSTEMS i 3.5.1 System Fenetton The instrumentation and control systems consist of the Reactor Protection j S) stem (RPS), the Enginected Safety Features Actuation System (ESFAS), and systems for the display of plant information to the operators. The RPS and ESFAS monitor the
- reactor plant, and alert the operator to take corrective action before specified limits are exceeded. The RPS will initiitte an automatic reactor trip (scram) to rapidly shutdown the reactor when plant conditions exceed one or more specified limits, The ESFAS will automstically actuate selected safety systems based on the specific limits or combinations of limits that are exceeded. A remote shutdown capability is also provided te ensure that the reactor can be placed in a safe condition it; the event that the main control room must be evacuated.
- 3.5.2 Ststem Definition The RPS includes sensor and transmitter units, logie units, and output trip relaya that operate reactor trip circuit breaken 50 cause a reactor scram, The ESFAS includes independerit sensor and transmitter units, logic units and relays that interface with the control circuits for the many different sets of components that can be actuated by the
, ESFAS, Operator instrumentaton displav systems (onsist of display panels in the comrol i room that are powered by the 120 VAd electtic power system (sce Section 3.6), The remote shutdown capability is proved by the Auxiliary Shutdown Panel and the Auxillary , Feedwater Pump Turbine dontrol Panel, 3.5,3 S5 stem Oneration -
- d A. RPS ..
The Westinghouse RPS (or Reactor Tdp System, RTS) has two to four redundant input instrument channels for each sensed parameter and two output actuation trams (A and B). The A and B logic trains irdependently generate a reactor trip command when pre >cribed parameters are outside the safe operating range, Either RPS train is capable of opening a separate and independent reactor trip circuit breaker to cause a scram The manual scram A and B circuits bypass the RPS logic trains and send a reactor trip command directly to shunt - trip circuitry in the reactor trip circuit breakers. B. ESFAS The ESFAS has three or four input instrument channels for each sensed parameter, and two output actuation trains (A and B). In general, each train controls equipment powered from different Class lE AC electrical buses. An individual component usually receives an actuation signal from only one ESFAS train, The ESFAS generates the following si;nals: (1) reactor trip, provided one has not already been generated by the R?S, (2) safety injection signal (SIS), (3) containment isolation, (4) main steam line isolation, (5) main. , feedwater line isolation, (6) emergency diesel start, (7) annulus ventilation system actuation, (8) containment spray miation, and (9) ventilation systems ' for the auxiliary buildin , control room, ' diesel building. The control room operators can manuall tri? the varioua tiSFAS logic subsystemsc Details regarding ESFAS actuat on logic are included in the system description for the actuated system; 35- -12/88
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Catawba 1 & 2 h C. Remote Shutdown Instrumentation and controls for hot shutdown from outside the control room are lo:ated in the Auxiliary Building on the Auxiliary Shutdown Panels and the Auxiliary Feedwater Pump Turbine Control Panel. Selector switches on the auxiliary shutdown panels allow the op;rator to _ transfer control of the equipment required for shutdown from the control room to the shutdown panels. When equipment control is transferred to the auxiliary shutdown panels, all contro: room controls and all interlocks that ot4'riate in or pass through the control room and/or cable room are defeated (Ret.1). Transfer of control to the shutdown panels is alarmed in the control room. The electrical power that supplies all of the devices controlled from these panels is available following a loss of offsite power. The controls on the auxiliary shutdown panels provide the capabilities of achieving and maintaining hot shutdown when the control room is inaccessible. The controls provide a means of sustaining the capabilities for boration, supplying steam generator feedwater and RRR, and continuing reactor coolant pump seal injection and/or thermal barrier cooling water flow. Cold shutdown conditions can also be met outside the control room with some tem?orary instmmentation and control modifications. A list of instrumentation anc controls available for hot shutdown vlA the auxiliary shutdown panels is provided as Table 3.51 (Ref.1). 3.5.4 System Success Criteria A. RPS The RpS uses hindrance logic (normal = 1, trip = 0) in both the input and p/ s output Icgic. Therefore, a channel will be in a trip state whea input signals sre lost, when control power is lost, or when the channel is temprarily remoed from service for testing or maintenance (i.e. the channel has a fail safe fallu te mode). A reactor scram will occur upon loss of control power to the RPS. A reactor serain 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 Catawba have not been determined. B. ESFAS ' A single component usually receives a signal from only one ESFAS output train although all swing components and both AFW pumps receive signals from both trains. ESFAS Trains A and B must be available in order to automatically actuate their respective components. ESFAS typically uses hindrance input logic (normal = 1, trip = 0) and transmission output logic (normal = 0, trip = 1). In this case, an input channel will be in a trip state when input signals are lost, when control power is lost, or when the channel is temporarily remove <1 from service for testing or maintenance (i.e. the channel has a fail safe failure ! mode). Control power is needed for the ESFAS output channels to send an l actuation signal. Note that there may be some ESFAS actuation subsystems that utilize hindrance output logic. For these subsystems, loss of control power will cause system or component actuation, as is the case with the RPS. Details of the ESFAS system for Catawba have not been determined. C. Manually-Initiated Protective Actions i (O V) When reasonable time is available, certain protective actio..s may be performed manually by plant personnel. The control room operators are capable of 36 12/88
Catawba.l'& 2 :- ' O operating individual-components using normal control circuitry, or opcoting groups of components by manually tripping the RPS or an ESFAS subsystem.- The control room operators also may send qualified persons into the plant to - operate components locally or from some other remote control location (i.e., the - remote shutdown panel or a motor control center). To make these judgments; data on key plant parameters must be available to the operators. 3.5.5 Suonort Systems _and Interfaces 4 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.
- 2. ESFAS The ESFAS input instrument channels are powered from 120 VAC iastrument buses, it is assumed that the ESFAS A and B outpu'. logic trains are powered from separate 125 VDC distribution panels.
- 3. OperatorInstrumentation
-Operator: instrumentation displays' are powered from the 120 VAC instrument buses, i
3,5,6 Sectinn 33 References
- 1. Catawba Nuclear Station FS AR,-Sectica 7.4 O
i 4 t
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- 37 Ll2R j i
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( ( O(3 Taue 3.5-1. Listing of Components Controlled by Auxiliary Shutdown Panels Aux,itary Shutdowr, Aurehary Shutdown Auxshary Feedwate- Pump Panet 1A Panel 10 Pump Turbine Cm. ' Panet SDPf4L R M A ._ SDPtJL RMR AFWTCPE:s AFW Pump 1 A Start' Step AFW Pump 1P Start'Stop AFW TD Pump StartGtop AFW Sucten Valves AFW Suction Vafve AFW Suction Va!vas
?1A 90 7A 15/ 18 0 A2 (Hotwelfi 250A 3100 A4 (Upper Surge Tank)
.- AG (CST) p AFW Discharge Valves *FW Dech~-- Valves AFW TD Disdarge Valves ( ' ?A 460 Se8 58A 428 608 60 40 SOA [ 56 44 38A NSW Pump 1 A NSW Pump to PJ'W Supply Vafve Cetifegal Charging Pump 1 A Centrifugar Charg% Pump 18 116A CCW Pump 1 A CCW Pump 1B 858 CCW Pump 2A CCW Pump 28 Staam Gen Atmos Steam Dump Sept Cnt M Boric Acid Transfer Pump 1 A CVCS Valves Boric Add Transfer Pump 18 SV19 13 CVCS VrJves 1A 1228 7 2A 123B 1 13A 1248 Steam Gen Atmos S'.eam Dump Trans Switch 37A 1250 Train A Auto-Start Discharge Vafve Argn Reset 186A 2368 Train B Auto-Start Discaree Va!ve ATsn Reset 172A 294 7
~~
238A 309 148 ld 309 CCW Valves CCW Va!ves 1A 28 7' 18B 5* A 53 8 51A 228B 230A 548 Pressurizer PORV Valve 33A Pressurizer PORV Valve 328 Pressurizer Bbck Vafve 34 A Pressurizer D!ock Valve 319 d Pressurizer Heaters Pressurizer Heaters
$ Steam Generator isolation Vafves Steam Generator Isolation Valves 1SM7 1SMt 1SMS 1SM3 ,
w
I Catawba 1 & 2 (] 3.6 ELECTRIC POWER SYSTEM 3.6.1 Svstem Function The electne 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 cundition following an accident, when the nom al electric power sources are nci available. 3.6.2 Svstem Defib'flon
- The onsite Class lE electric power system is divided into two redundant and independent trains designated A and B, each consisting of two 4160 VAC buses, four 416"'600 VAC transformers, three 600 VAC load centers and associated loads. Each train of the 4160 VAC enential auxiliary power system is also provided with a se 3arate and independent emergency diesel generatrr Various motor contro! centers receive t1eir power from the 600 VAC buses.
Emergency power for vital instrument ontroi, and emergency lighting is supplied by four 125 VDC station batteries. Associe'ed battery chargers receive power from various MCCs sunplied by the 600 VAC buses. The batteries supply four DC divisions. Four 120 \ AC instrument buses are connected to the DC buses through mverters. The Safe Shutdown Facility contains a 600 VAC diesel generator and 125 VDC batteries. These power sources are capable of supporting a minimum of equipment for maintaining a hot shutdown condition. Simplified one line diagrams of the electric power system are shown in Figures 3.6-1 through 3.6-7. A summary of data on selected electric power system components is fs) ' pre sented in T91e 3.6-1. A partial listing of electrical sources and loads ir presented in C/ Ta u 3.0-2. 3.6.3 Svstem Oneration During normal operation, the Class lE electric power system is supplied from the 230 kV switchyard which supplies two power trains of the 6900 VAC norrcal auxiliary power sy, tem. Two independent 6.9 kV buses and 6.9/4.16 kV tranJormers energize the two 4160 kV buses of each power train. The emergency sources of AC power are the diesel generators which hase dedicated starting batteries located in respective diesel genuator rooms. The transfer from the preferred power source to the diesel generators is accomplished automatically upon detect?on of an undervoltage on an essential bus by tripping the appropriate incoming breaker and closing the diesel output breaker, in addition, tne diesels may be manually started from the control room or from the local diesel contml panel. 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 duws from the batteries. The station batteries r Ted to supply DC loads and the instrument inverters for up to one'..our (Ref.1). The 125 VDC and 120 VAC vitalinstrument and control pov er system consists of four inde pendent load groups that supply instrumentation and control channels A, B, C, and D. Eac;1 load g up meludes a battery, a batte.ry charger, a DC d!stribution center and associated panalboard, an inverter, and an AC panetboard. The bittery charger of load groups A and C and load groups B and D are powered by 600 V buses of trains A and B respectively, of the essential auxiliary power system. Each battery charger has sufficient p) s V capacity to supply the bus load requirements of its own load group while maintaining float charge on its associated battery. The 120 VAC vital buses normally receive power from the DC buses thraugh an inverter. A regulated 120 VAC power supply is provided to serve as an alternate source of power. 39 12/88
Catawba 1 & 2 The Safe Shutdown Facility diesel generator supplies 600 VAC buses ISLXG and ISMXG in the Safe Shutdown Facility and one MCC in Unit I and Unit 2. Bus ISLXG is the normal power source for the 250/125 VDC auxiliary power distribution system. The 250/125 VDC auxiliary power system energizes 125 VDC and 120 VAC , panels in the Safe Shutdown Facility which supply Safe Shutdown Facility instrument , i power and controls. Redundant safeguards equipment such as motor driven pumps and motor se of discussion, this operated equipment has valves are supplied been grouped into " load by different groups". VAC,A buses. For the purp' Load group - contains receiving electric power irom Train A of the essential auxiliary power system. Load group "B" contains components powered from Train B. Components receiving DC mwer are assigned to load groups A, B, C, or D. Lead groups A and C are powered from " rain A of th Essential Auxiliary Power System. l.oad groups B and D are powered from Train B.- 3.6.4 Svstem Success Criterin Basic system success criteria for mitigating transients and loss of coolant accidents are defined 'oy front line _ systems, which then create demands on support systems. Electric power system success criteria are defined as follows, without taking credit for cross ties that may exist between independent load groups: Each Class IE DC load group is supplied from its respective station battery or - battey charger. Note that the diesel generators are not dependent on the station batteries for starting power. Separate diesel starting batteries are provided for this function. Each Class lE AC load group is isolated from the non Class 1E system and is supplied from its respective emergency power source (i.e. diesel generator). s - Power distribution paths to essential loads are intact. j - Power to the battery chargers is restored before the station batteries are exhausted. 3.6.5 Comoonent Information I ' A. Standby diesel generators (2 per unit
- l. Maximum continuous ratmg: 70v .W
- 2. 2 hour rating
- 7700 kW
- 3. Rated voltage: 4160 VAC j 4. Manufacturer: unknown l B. Station Batteries (4)
,_ l . Rated voltage: 125 VDC i
- 2. Rated capacity : l_ hour with design loads C. Diesel Starting Batteries (2 per unit)-
- 1. Rated voltage: 125 VDC
- 2. Rated capacity: 2 hours with design loads D. SSF diesel generator (1)=
- 1. Rated voltage: 600 VAC ,
E. SSF batteries (3)
- 1. Rated voltage: 125 VDC i
l 40 12/88~
1 Catawba 1 & 2-3.6.6_ Sponort Systems and Interfaces . A, Control Signals
- 1. Automatic The standby diesel generators are automatically started based on:
Undervoltage on the associated 4160 VAC essential bus
- Safety injection signal (SIS, see Section 3.3)
- 2. Remote manual The diesel generators can be started,'and many distribution circuit breakers -
can be operated, from the main control room and from the local daesel panel. B. Diesel Generator Auxiliary Systems
- 1. Diesel Cmling Wate+ System Heat is transferred from a jacket. water system tc Ae Nuclear Service Water system. Each desel receives redundant cooling water supplies from the NSW "A" and "B h-aders (see Section 3.8).
- 2. - Diesel Starting Syst,m Each diesel has two independent air starting systems and starting batteries
~'*at are independent from the station batteries.
- 3. Diesel Fuel Oil Transfer and Storage System A 550 gallon " day tank" su 3 plies the relatively short term (approximately 60 -
minutes) fuel needs of eac 1 diesel. Each day tank is reptem,shed from two - 90,000 gallon storage tanks during engine operation.
- 4. Diesel Lubrication System-Each diesel generator has its own lubrication system which utilizes a " dry sump" lube oil system. The supply of lubricating oil for each engine is O stored in separate 700 gallon capacity tube oil sump tanks.
- 5. Combustion Air Intake and Exhaust System .
This system supplies fresh air to the dieselintake, and. directs the diesel. exhaust outside of the diesel building.
- 6. Diesel Room Ventilation System This system maintains the environmental conditions in the diesel room
' within limits for which the diesel generator and switchycar have Nen qualified. This system snay be needed for long-term operation of the desel
- . generator.
C. Switchgear and Battery Room Ventilation System > Details on systems providing switchgear and battery room ventilation have not - c been identified. These systems may be needed for long term operation of thei electric power system. 3.6.7 . Section 3.6 References h 1. Catawba Nuclear Station, FSAR, Section 83 s 41 12/88i l
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- Figure 3.6-2. Catawba 14160 and 600 VAC Electric Power Distribution System Showing Component Locations l (Sheet 3 of 3, Train 8) 1 4
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Figure 3.6-3. . Catawba 1 125 VDC and 120 VAC Electric Power Distribution System
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Table 1.6-1. Catawba 1 & .2 Electric Power System Data Summary i for Selected Components ' 1 COMPONENT ID COMP. LOCATION POWER SOURCE VOLT AG E POWER SOURCE EMERG. .I TYPE LOCATION LOAD G*1P. BAITIDGBA BAI I~ DGA 125 BA T11DGBB SAIT DGB 125 BA T T 1 EBA BATT BATHMA BATT1 EBB BATI BAIRMB i r BAII1EBC BAIT BATRMC BATI1EBD BATI BAT RMD
\
BCTECA - BC DCSWGRM MCC1EMXA 600 AMCCRM57/ DC/A- ' BC1ECB BC. DCSWGRM MCC1EMXJ 600 BMCCRMS77 DCIB BC1ECC - BC DCSWGRM MCC1EMXI 600 AMCCRMS77 DC/C BC1 ECD BC DCSWGRM MCC1EMXB 600 BMMCRMS77 DC/D l BUS 1ECA BUS DCSWGRM . BATI1EBA 125 BATRMA DC/A BUS 1EDB BUS DCSWGRM BATT1Een 125 BATRMB DC/B BUS 1EDC BUS OCSWGRM BA I T1EBC 125 t3ATRMC DC/C BUS 1EDD. BL'S DCSWGRM . BAT 71EDD~ 125 BATRMD DClO BUS 1ELXA BUS AbWGRM TRANIEIX.! 600 ASWGRM AC/A BUS 1ELXB BUS BSWGRM TRAN;iiXF 600 BSWGRM - AC/B BUS 1ELXC- BUS ASWGRM E N10IXE 600: ASWGRM AC/A BUS 1ELXD BUS' BSWGRM - TRAN1ETXF G00 BSWGRM . AC/B BUS 1 ET/.- BUS _ ASWGRM DG1A 4160 ASWGRM AC/A BUS 1ETU BUS BSWGRM DG1B l4160 BSWGRM AC/B CB-ETA- CB ASWGRM DG/A CB-ETB CB. BSWGRM DG/B DG1A DG DGA-
.b - DG18. DG DGB "cr> 1RANIETXA. 1RAN ASWGRM -
BUS 1 ETA- 4160 ASWGRM AC/A TRAN1ETXB- IRAN BSVW.3HM BUS 1EIB 4160 BSWGRM AC/B , TRAN1ETXC.~ IRAN- ASWGRM BUS 1EI A 4160 AEWGRM AC/A TRAN1EIXD TRAN BSWGRM BUS 1EIB 4160 BSVKiRM AC/B i i u _
- - -- - - - - - - ~
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p Table 3.6-1. Catawba 1 '& 2 Electric Power System Data Summary 3 - for Selected Components -(Continued) ,i i ) . COMPONENT ID - COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. l TYPE LOC A TION LOAD GRP. 1RANIEIXE IllAN A3WGHM BUS 1 ETA 4160 ASWGliM AC/A i TRAN1EIXf 1HAN GSWGHM BUS 1Eiu 4100 USWGHM AC/B t f t e~- ~
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T ABLE 3.6 2. LISTING OF ELECTRICAL SOURCES AND LOADS AT CATAWBA 1 & 2 PonEA VOLTAGE EVERG POWER SOVRCE LOAD LOAD COMP COMPONENT SOU A'. E LOAD GRP LOCATION SYSTEM COMPONENTID TYPE LOCATION BATT1L3A 125 DC/A BATRMA EP BUSIECA bus DCSWGRM BATT1 EBB 125 DC B BAlRMB EP BUS 1EDB BUS DCSWGRM BATT1EE0 125 DCcC BATRMC EV BUS 1EDC BUS DCSWGAM BATT1EBD 125 DC/D BATRMD EP BUSIEDD BUS DCSWGRM sus 1ELxA 600 AC/A ASWGRM EP MCCIEMXA AUX AMCCRM577 bus 1ELx8 600 AC/B BSWGRM EP MCCIEMXB AUX BMCCRMS60
~
BUS 1ELXC 600 A Ci A ASWGRM EP MCC1EMxt AUX AMCCRM577 BssikLAD ECO ACiB BSWGRM EP MCCI EMxJ AUX BMCCRMS60 BsS1 ETA 4160 A C/ A ASWGRM AFW AFW PIA MDP AFWPMRM
-~
B s S li. i A 4 0 AC. A ASWGRM CCW CCW P1A MDP 660AB bsS1 ETA 4160 ASWGRM CCW CCW P2A MDP 560AB BsS1 ETA 4160 AC/A ASWGRM CVCS CV PIA MDP CHPMRMA Bu51 ETA 4160 AC A ASWGRM ECCS RH P1A MDP RHRPMAMA bus 1 ETA 4160 A L,!A ASWGRM ECCS St-P I A MDP SIPMRA% "\ BUS 1 ETA 4160 AC/A ASWGRM EP TRANIE TAA TRAN ASWGRM BUS 1 ETA 4160 AC/A ASWGRM EP TRANIETxC TRAN ASWGRM BUSIETA 4160 ACTA ASWGRM EP TRANIETxE TRAN ASWGRM SUS 1 ETA 4160 AC,A ASWGRM SW NSW P1A MDP NSWA BUS 1EiB 4160 AC!B BSWGRM AFW AFW-PIB MDP AFWPMRM BUS 1ETB 4160 AC/B BSWGRM CCW CCW P1B MDP 560AB bus 1ETO 4160 ACiB BSWGRM CCW CCW P2B MDP 560AB BUS 1ETB 4160 AC/B BSWGRM CVCS CV PIB MDP CHPMRMB BUS 1EIB 4160 AC/B BSWGRM ECCS RM P1B - MDP RHRPMRMB BUS 1ETB 4160 AC/B BSWGRM ECCS SIP 1B MDP SIPMRMS EUS1ETB 4160 AC/B BSWGRM EP TRANIETxB TRAN BSWGAM BUS 1ETO 4160 AC/B BSWGAM EP TRAN1ETxD TRAN BSWGRM Bus 1ETB 4160 AC'B BSWGRN. EP TRAN1ETxF TRAN BSWGRM BUSIETB 4160 AC/B BSWGRM SW NSW-PIB MDP NSWB DG A 4160 AC/A ASWGAM EP BUS 1 ETA BUS ASWGAM Q DG1B 4160 A C 'D BSWGRM EP BUS 1ETB BUS BSWGAM MCC1EVAA 600 DC, A AMCCRM577 EP BCIECA BC DCSWGRM 55 12/8S
TABLE 3.6 2. LISTING OF ELECTRICAL SOURCES AND LOADS AT CATAWBA 1 & 2 (CONTINUED) k POWER VOLTAGE EMERG POWE R SOUR 0E LOAD LOAD COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION MCC1EMAD 600 DC D BMMCRM577 EP BCIECD BC DOSWGAM MCC I E NO.G 600 AC/A WCAG $W NSW43A MOV $77AB MCC t EMAi 600 DC'C AMCCRM,77 EP BCIECC BC DCSWGRM MCCI EMxs 600 DC B BMcCRM577 EP BCIECB BC DCSWGRM MCC1EMAQ 600 AC. A N$WA SW NSW 26A MOV NSWA McC t E MAR 600 AC/B NSWB SW NSW 38B MOV NSWB MCCISMAS 600 SSF $$F AFW AFW 174 MOV AFWPMRM MCC1SMAG 600 SSF SSF AFW AFW 175 MOV AFWPMRM MCC1SMAG 600 SSF SSF AFW AFW-178 MOV UG Y;C2EMAn bW AC 6 MCC2AH SW NSW 56B MOV $77AB TR AN)E T AE '600 AGA ASWGRM EP BUSIELxA BUS ASWGRM TRANiETAE 600 ACiA ASWGRM EP BUSIELxc BUS ASWGRM TRAN1ETAA 600 AC B BSWGRM EP BUSIELAB BUS BSWGRM TRANtETAF 600 AC,b BSWGRM EP BUSIELXD BUS BSWGRM
) UNsNOWN 600 AC A ASWGRM AFW AFW 116A MOV AFWPMAM UNKNOWN 600 AC/A AMCCRM577 AFW AFW 15A MOV AF WPMRM UNsNOWN 600 ACt BMCCRM560 AFW AFW 18B MOV AFWPMRM UNsNOW N 600 AC/4 ASWGAM AFW AFW 250A MOV AFWPMRM UN%NOWN 600 AC/B BSWGRM AFW AFW 3108 MOV AFWPMRM UN ANOW N 600 AC/b BSWGRM AFW AFW 428 MOV ODH UNKNOWN 600 AC/B BMCCRM560 AFW AFW 468 MOV IDH UNKNOW N 600 AC/A AMCCRM577 AFW hFW 50A MOV (DH UNKNOWN 600 AC/B BMCCRM560 AFW AF W-549 MOV IDH UNNNOWN 600 AC/A AMCCRM577 AFW AFW 58A- MOV IDH UN*.NOWN 600 AC/A ASWGRM AFW AF W-62A MOV ODH UN6NOWN 600 AC/B BMCCRM560 AFW AFW 858 MOV AFWPMRM UNKNOWN 600 AC/A AMCCRM577 CCW CCW 56A MOV 577AB UNKNOWN 600 AC/B EMCCRM560 CCW CCW41B MOV $77AB UNKNOW N 600 AC/B BMCCRM560 CVCS CV-108 MOV MPENRM543 UNsNOWN 600 AC/A AMCCRM577 CVCS /eN CV 19A MOV MPENRM543 UNKNOWN 600 AC/A AMCCRM577 CVCS CV-2528 MOV SIPMAMis 56 12/88
- . . . . - - -. . ~ . , - .
TABLE 3.6 2. LISTING OF ELECTRICAL SOURCES AND LOADS AT CATAWBA 1 & 2 (CONTINUED) (' POWER VOLT AGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT SOURCE LOAD GRP LCCATION SYSTEM COMPONENT 10 TYPE LOCATION UNNNOWN 600 ACeB BMCCRM560 CVCS CV 253B MOV SIPMRMB UNNNOWN 600 ACeB BMCCRMb60 ECCS RM 136B MOV SIPMRMB UNNNOWN 600 Acta AMCC AM577 ECCS RH 164B MOV MPENRM543 UNNNOWN 600 AC/A AMCCRM577 ECCS RM 185A MOV MPENRM543 UNNNOWN 600 ACsA AMCCAM577 ECCS RM 26A MOV HXRN% UNNNOWN 600 AC/A ECCS RM32A MOV HXRN% UNNNOWN 600 AC 8 ECCS RH-6bB MOV HARMB UNsNOWt, 600 AC B TMCCRM560 ECCS Si100B MOV S1PMRMB UN%NOWN 600 AC/A AMCCRM577 ECCS SI-103A L I40V SIPMRN% g UN%CWN . 600 , AC'A AMCCRM577 ECCS Sb 1184. OV SlPMRMA UNNNOW N t00 AC A AMCCRM577 ECCS Si-121/, Mdv MPENRM543 UNNNOW N 600 AC/B EMCCRM560 ECCS Sb135B MOV SiPMAMB UNNNOWN 600 AC/B BMCCRM560 ECCS Sl-150B MOV SIPMRMB U N NNOW N 600 AC, B BMCCRM560 ECCS Sb152B MOV MPENAM543
\ UNNNOW N 600 A Ci A AMCCRMA77 ECCS Sb102A MOV MPENRM543 UNNNOWN 600 AC/B BSWGRM RCS AC+31 B MOV RC UNNNOW N 600 AC/B RCS RC 328 NV RC U NNN '.;W' 600 AC/A ASWGRM RCS l
RC 33A MOV RC E OWN 600 ACiA RCS RC-34 A NV RC UNNNOWN 600 AC/B BSWGRM RCS RC-350 MOV RC UN6NOWN 600 AC/B RCS RC 36B NY RC v UNKNOWN 600 AC/A ASWGRM RCS RH 1B MOV RC UNNNOWN 600 A C e A. ASWGRM RCS 4H-2A MOV RC UNNNOW N 600 AC/B BSWGRM RCS RM-36B NV RC UNNNOWN 600 AC/A ASWGRM RCS RH.37A MOV RC UNANOWN 600 AC/A AVCCRM577 SW NSW 144A MOV 577AB UNKNOWN 600 ACr8 BMCCRM577 SW NSW 225B MOV 577AB UNNNOWN 600 AC/A SW NSW 232A MOV DGA UNKNO A N 600 AC/A AMOCRM577 SW NSW 28'A MOV 577AB
~ ; O UNNNOWN 600 AC/B SW NSW-2928 MOV DGB ?
(j UNKNOWN 600 AC/B BMCCRM577 SW NSW 347B MOV 577AB 57 12/M
]
TABLE 3.6 2, LISTING OF ELECTRICAL SOURCES AND LOADS l AT CATAWBA 1 & 2 (CONTINUED) j O PonER SOURCE vo.1. AGE EMERG LOAD GRP POWER SOURCE LOCATION LOAD LOAD SYSTEM COMPONENT 10 COMP TYPE COMPONENT LOCATION v f.e,N O W N 600 AC/A AMCCRM577 SW NSW47A MOV $77AB Vt,sNOWN 600 A CeB BMCCRM560 SW NSW49B MOV $77AB Utt%NOWN 600 AC/A SW NSW 846A MOV DGA vh*A Ou N 600 AC/B SW N SW.6480 MOV DGB i O V l C k SS 12/88
Catawba 1 & 2 3,7 COMPONENT COOLING WATER (CCW) SYSTEM V 3.7,1 S.ptem Function The CCW system provides cooling water to various plant components in both units during normal operation, plant shutdown, and after an accident to act as an
- intermediate system b' tween the components being cooled and the Nuclear Service Water system. Separation is required to minimize the possible release of radioactive material.
The CCW serves to remove residual and sensible heat from the RCS during plant shutdown by cooling the RHR heat exchangers. 3,7,2 Svstem Definition The CCWS normally functions as two independent closed loop systems, one subsystem for Unit I and one subsystem for Unit 2. Each subsystem is further divided mto two trains. Cooling water su) plied to shared equipment is contained in the Unit 1 subsystem. Cross-ties are providec between the two subsystems so that cooling water can be stipplied to shared equipmen' from either unit. The CCWS consists of eight (four per unio component cooling pumps, four (two per unit) component cooling heat exchangers, foa'r (two per unit) surge tanks, two (one per unit) drain sumps, four (two per unit) drain sump pumps, and associated valves, piping, and instrumentation. The CCW heat exchangers transfer heat to the Nuclear Service Water system. The surge tanks accommodate expansion, contraction, and in leakage of water. Simplified drawings of:he CCW system are shown in Figures 3.71 and 3.7 2. A summary of the data on selected CCW system compt aents is presented in Table 3.71. 3,7,3 System Oneration Three component cooling putaps, two component cooling heat exchangers, and O tae two surge tanks are sufficient for nomial operation of the two units. Cooling water is Q nrculated by the pumps through the shell side of the CCW heat exchangers to the components being cooled, then back to the pump suction. Demineralized makeup water is supplied to the system into the surge tank. A backup source of makeup water is the supplied by the Nuclear Service Water system. Heat loads supported by the CCW system include the following: RHR heat exchangers and pumps CCW, SI, AFW, containment spray and centrifugal charging pumps Letdown heat exchanger Excess letdown heat exchanger Component cociing is also provided for additional components, such as the reactor coolant pumps and other emponents of the Chemical and Volume Control System. 3,7,4 Svstem Success Criterin The system success criteria can be defined on a per train basis. Either -in can maintain an extended hot shutdown. The success criteria for et;h train requires that an unspecified number of CCW pumps operate, the associated n, : lear service water system removes heat from the CCW heat excht age ir d the piping and valves provide an adequate flow path in the specific train (Ref.1, Section 9.2.2). 3,7,S Comoonent Information (Per Unit) l l A. Component Cooling Wate- Pumps I A, IB,2A, and 2B
- 1. Design flow: 3703 gpm @ 200 ft head (qv) 2. Type: horizontal centrifugal 59 12/88
Catawba 1 & 2 B Component Cooling Heat Exchangers l A and IB q , 1. Design duty: 6.82 x 106Btu /hr -
- 2. Type: shell and straight tube q
3.7.6 Suonort Systems and -Interfaces -J A. Control Signals- -
- 1. Automatic .
All four CCW pumps for each unit are automatically actuated by an SIS- , signal,
- 2. Remote Manual The CCW pumps can be actuated by remote manual means from the control--
room and from the remote shutdown control panel ' q B. Motive Power -
- 1. The CCW motor-driven pumps and motor operated valves are Class'lE AC loads that can be supplied from the standby desel generaton as described in Section 3.6. 3 C. Other -
l ~ The CCW heat exchangers are cooled by the Nuclear Service Water system.
- 2. Lubrication and cooling are provided locally for the CCW pumps. ,
3.7.7 Section 3.7 Reference -
) 1. Catawba Nuclear System, Final Safety. Analysis' Report, Section 9.2,2. .-
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n= . , ( e; c: ( 8 Table 3.7-1. Catawba 1 & 2 Component Cooling Water System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VO LT AG E POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. 1 CCW-56A MOV 577AB UfJKNOWN 600 AMCCRM57/ AC/A CCW-818 MOV 577AB UNKNOWN 600 BMCCHM560 AC/D CCW-fiX1 A IIX 577AB CCW-P1A MDP 560AB BUS 1E1 A 4160 ASWGHM AC/A
~CCW P1B MDP 560AB BUS 1EIB 4160 BSWLHM AC/B CCW-P2A MDP 560AB BUS 1 ETA 4160 ASWGHM AC/A CCW-P2B MDP 560AB BUS 1ETB 4160 BSWGHM AC/B CCWB HX1B HX 577AB C
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Catawba 1 & 2 3.8 NUCLEAR SERVICE WATER (NSW) SYSTEM-D 3.8.1 System Function The Nuclear Service Water System supplies cooling water from the ultimate heat sink to various heat loads in both the primary and secondary portions of the plant. The system is designed to provide a continuous flow of cooling water to those loads which are safety related or essential to the safe shutdown of the reactor. 3.8.2 System Definition The Nuclear Service Water System consists of two trains with two pumps in each train. The discharge of the two pumps in each train form a header that supplies coolant to both units. These trains can be cross connected. The normal source of water for the system is either Lake Wylie or the Standby Nuclear Service Water Pond (SNSWP), formed by a Class I seismically designed dam, which is available for use if utke Wylie is unavailable. The SNSWP contains sufficient water to achieve cold ',nutdown following a-LOCA. Strainers are provided to remove impurities from the. 'w water before it enters the - NSW pumps. Simplified drawings of the NSW system are shown in Figures 3.81 and 3.8 2. These drawings show some components from Unit 2. Unit I component ids begin with "l", Unit 2 component ids begin with "2". A summary of data on selected NSW system components is presented in Table 3.81. 3.8,3 Sutem Ooeration During normal operation, two of the NSW pumps are in continuous operation providing cooling water to essentialloads of the two unit plant. Essentialloads are those required for safe shutdown, and are therefore redundant and served by the corresponding channels of the NSW system. Heat loads supported by the NSW system include the V following: Diesel generator coolers Containment s? ray heat exchanger CCW heat exc aangers AFW, NSW, SI, and centrifugal charging pump lube oil coolers AFW, NSW, SI, RHR, CS, and centrifugal charging pump cubicle coolers Control Room area chillers Auxiliary Shutdown Panel air conditioning unit The NSW also provides an assured supply of water to the Auxiliary Feedwater and Component Cooling Systems. , 3.8.4 System Success Criteria The NSW trains can be cross connected so that any two NSW pumps are sufficient to maintain both plants at an extended hot shutdown and any one NSW pump is sufficient to maintain one plant at extended hot shutdown. In addition, either source of water, Lake Wylie or the Standby Nuclear Service Water Pond is required, along with an
- adequate flow path from the NSW pump discharge to the heat sources (Ref.1, Section 9.2.1 ) .
T 3.8.5 Comoonent Information A. Service Water Pumps 1 A and IB i p 1. Design flow: 20,900 gpm @ 174 ft head
- 2. Type: vertical, wet pit, mixed flow with above floor discharge 68 12/88
Catawba 1 & 2 B. Ultimate Heat Sink Lake Wylic and SNSWP 3.8.6 Suonort Systems and Interfaces - ' A. Control Signals
- 1. Automatic The NSW pum ps are automatically actuated.
- 2. Remote Manua)
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- 1. Lubrication and cooling are provided locally for the NSW pumps.
3.8.6 Section 3.8 Reference
- 1. Catawba Nuclear System FSAR, Section 9.2.1.
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a Table 3.8-1.- Catawba 1 & 2 Nuclear Service Water System Data Summary for Selected ' Components t i COMPONENT ID COMP. LOCATION POWER SOURCE VO LT AG E POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. NSW-144 A MOV 577AB UNKNOWN 600 AMCCHM577 AC/A NSW-2250 MOV 577AB UNKNOWN 600 BMCCHM577 AC/B NSW-232A MOV DGA UNKNOWN 600 AC/A NSW-287A MOV 577AB UNKNOWN 600 AMCCHM577 AC/A - NSW-28A MOV NSWA MCC1EMXO 600 NSWA AC/A NSW-2928 MOV DGB UNKNOWN 600 AC/B TJSW-347B MOV 577AB UNKNOWN 600 BMCCHM577 AC/B ' NSW-38B MOV NSWB MCC1EMXH 600 NSWB AC/B
-r NSW-38B MOV 577AB MCC2EMXH 600 MCC2XH AC/B -
NSW-63A .MOV 577AB MCC1EMXG 600 MCCXG AC/A NSW-67A MOV 577AB UNKNOWN 000 AMCCRM577 AC/A wJ cs - NSW-698 MOV- 577AB UNKNOWN 600 BMCCRM560 AC/B NSW-846A MOV DGA UNKNOWN 600 AC/A NSW-848B MOV DGB UNKNOWN 600 AC/B NSW-P1A MDP NSWA BUS 1 ETA 4160 ASWGRM AC/A NSW-PI B MDP- NSWB BUS 1ElB 4160 USWGHM ' AC/B i C
'JJ
~
Catawba 1 & 2
- 4. PLANT INFORMATION ~
4.1 SITE AND BUILDING
SUMMARY
The Catawba Station, Units 1 and 2, is located in the north central portion of South Carolina, approximately six miles north of the town of Rock Hill and ten miles southwest of Charlotte, North Carolina. The site is in the northeastern portion of York County arid occupies approximately 391 acres of land. - Figure 41-(from Ref.1) is a-general view of the plant and vicinity. - The major structures at this unit include the two containment buildings, two : turbine buildings, a shared auxiliary building, two fuel buildings, two diesel buildings, and a safe shutdown facility. A site map and plot plan are shown in Figure 4 2 and 4 3. An elevation view of the Catawba nuclear station is shown in Figure 4-4. Each containment structure is a reinforced concrete cylinder with a steelliner. The containment houses the reactor vessel, reactor coolant pumps, steam generators, and pressurizer. Pumps, piping, and valving for the reactor coolant system is ccmpletely - contained within the containment structure. Access to the building is via an equipment hatch or a personnel airlock. Piping and electrical penetration areas are on various levels of
- the auxiliary building. An elevation view of the containment is shown in Figure 4 5; The turbine buildings, located west of the containments, house the turbine generator and the associated power generating auxiliaries.
The auxiliary building is located between the containments and contains much of the plant's safety related equipment, specifically the auxiliary feedwater pumps, high pressure injection pumpa, RHR pumps and heat exchangers, containment spray pumps, charging pu ps, component coohng water pumps and heat exchangers, and motor control centers sup ying power to safety system components. e fuel buildings are located to the east of the two containments and house the spent fuel pools. An elevation view of the fuel building is shown in Figure 4 6. 4.2 FACILITY LAYOUT DRAWINGS - Simplified layout drawings for the Catawba i reactor, auxiliary, fuel and diesel i generator buildmgs are shown in Figures 4 7 to 4-14. Similar drawings for Catawba 2 are shown in Figures 415 to 4 22. The service water pump house layout is shown in Figures 4 23 to 4-25, and the Safe Shutdown Facility is shown m Figures 4 26 to 4 29, Details of-other outlying buildings are not shown on these drawings, ~ Major rooms, stairways, elevators, and doorways are shown in the simplified layout drawings, however, many interior walls have been omitted for clarity. Labels printed in uppercase correspond to the location codes listed in Table 4-1 and used'in the component data listings and system: drawings in Section 3. Some additional labels are included for information and are printed : o in lowercase typem A listing of components by location is presented in Table 4 2,1 Components included in Table 4 2 are those found m the system data tables in Section 3, therefore this table is only a partial listing of the components and equipment that are located in a l, articular
. room or area of the plant.
4.3 SECTION 4 REFERENCES- - L
- 1. Heddlesong, F.A., " Design Data and Safety Features of Commercial Nuclear-Power Plants," ORNL NSIC-55, Volume 3, Oak Ridge National Laboratory, April 1974. ,
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. 00 Figure 4-12. Catawba 1 Reactor, Auxillary and Fuel Buildings, Elevations 605* to 619*. 1
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t Figure 4-14. , Catawba 1 Reactor, Diesel Generator Buildings, Elevations 556* and 594* [. I e i -
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t 1 Figure 4-19. Catawba 2 fleactor, Auxiliary and Fuel Buildings, Elevation 594*.
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.0 0 9 . P-utwwn f-t' x .m. i Figure 4-22. Catawba 2 Reactor, Diesel Generator Buildings, Elevations 556* and 594*.
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t L 4 i i 1 i
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103 12/88
t I I l i 6 6 i t Wh comme h PW o ' O O-tame Crneur tSt Wa () - l (. o-.s c_ 3 h L J _, asoc sxasG n . , s n f. . . i
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I U i Pn i I f Figure 4-2/. Catawba 1 & 2 Safe Shutdown Facility, Elevation 594* (Grade Level) . [ i l
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4 a { i t Table 41. Definition of Catawba 1 Building and
- Location Codes i
h DescrIntions i , 1, 560AD 5& elevation Auxiliary Building Unit 1 and 2 2, 577AB $77' elevation . Auxiliary Building Unit I and 2
- 3. 594AB $94' elevation Auxl!!ary Building Unit I and 2
- 4. DATRhiA Battery A Room, located on the 554' elevation of the Auxiliary ,
Building
$. BATRhib Battery B Room, located on the 554' elevation of the Auxiliary Building
- 6. BATRh1C Battery C Room, located on the $54' elevation of the Auxiliary Building
- 7. DATRN1D Battery D Room, located on the $54' elevation of the Auxiliary Building
- 8. AFWPMRM Auxiliary Feedwater Pump Room, located on the 543' elevation -
of the. Adxiliary Building
- 9. AFWTCPkM Auxiliary Feedwater Turbine Control Panel Room, located on the $43' elevation of the Auxiliary Building
~
- 10. Ah1CCRM577 A MCC Room, located on the 577' elevation of the Auxiliary Building
- 11. ASWGRM A Switchgear Room located on the 577' elevation of the Auxiliary Building i
- 12. BMCCRM560 B MCC Room, located on the 560' elevation of the Auxiliary i
! Building ,
- l. 13. BSWGRM B Switchgear Room, located-on-the 560'- of the Auxiliary Building-t 14 CABLE RM Cable Spreading Room, located on the 577' of the Auxiliary Building 15.- CHPMRhiA- Charging Pump Room A, located on the 543' elevation of the Auxiliary Building
- 16. CHPMRMB Charging Pump R'oom B,' located on the 543f elevation of the
. Auxiliary Building O 17. CR' Contro) Ixta, loved on tne 594' elevaation of the Auxiliary
. .\j Building 1.
- m. _ m . - __. m __...-.._m__. _._... __ _ .a._,_ . , _.....#,_.~,_,-,,_.,
O Table 41. Definition of Catawba 1 Building and () Location Codes (Continued) Codes Descrintions
- 18. DCSWGRh1 DC Switchgear Room, located on the 560' eleveion of the Auxiliary Building
- 19. DGA Diesel Generator Room A, located in the Diesel Building
- 20. DGB Diesel Generator Room B, located in the Diesel Buuding
- 21. DGCORRA Diesel Generator A Corridor
- 22. DOCORRB Diesel Generator B Corridor
- 23. ELPENRh1594 Electrical Penetration Room, located on the 594' elevation of the Auxiliary Building 24 liXAPPTN licat Exchanger A Pipe Trench, located on the 522* elevation of the AuxiliaryBuilding
- 25. IlXBPPTN lient Exchanger B Pipe Trench, located on the 522' elevation of the Auxiliary Building it
- 26. IIXRMA fleat Exchanger Room A RiiR and Containment Spray, located on the 56(r to 577' elevations
- 27. IIXRMB l-leat Exchanger Room B RiiR and Containment Spray, located on the 560' to 577' elevations
- 28. IDII Inside Dog liouse, located on the 577' elevation of the Auxilituy Building
- 29. MCC2XII Motor Control Center 2EhiXH
- 30. MCCShiXG Motor Control Center ShiXG in area SSF l
- 31. MCCXE Motor Control Center EMXE in area DGA
- 32. MCCXF Motor Control Center EhiXF in area DGB
- 33. MCCXG Motor Control Center EMXG
- 34. MCCXQ Motor Control Center EMXQ in area NSWA !
- 35. MCCXR Motor Control Center EMXR in area NSWB
- 36. MPENRM543 Mechanical Penetration Room, located on the 543' to 560' elevations of the Auxiliary Building O
108 12/88
1 [ j
! Table 41, Definition of Catawba 1 Building and i Location Codes-(Continued)
Co.d es Descrintions
- 37. MPENRM577 Mechanical Penetration Room, located on the 577' elevation of q the Auxiliary Building
) 3L NSWA Nuclear Service Water Pump Structure A . ! 39. NSWD Nuclear Service Water Pump Structure B c 40. ODH -Ouside Dog House, located on the 577' elevation of the ! Auxiliary Building I 41. PPCll Pipe Chase, located on the 522' elevation of the Auxiliary 1, Building -
- 42. PPTN Pipe Trench, located on the 522' elevation of the . Auxiliary Building
- 43. RC Reactor Containment .
1 1 44, RECPMRM Reciprocating Charging Pump Room, located on the 543' elevation of the Auxit ary Building 1 l 45. RHRPMRMA RHR Pump Room A, located on the 522' elevation of the ? Auxiliary Building. i'
- 46. RHRPMRMD RHR Pump Room B, located on the 522' elevation of the j Auxiliary Building i
j 47. RWST Refueling Water Storage Tank ! 48, ' SIPMRMA Safety injection Pump Room A, located on the 543' elevation of ! the Auxiliary Building i i 49, SIPMRMB Safety injection Pump Room B, located on the $43' elevation of j- the Auxiliary Building 3 t' 50 .SSF Safe Shutdown Facility - ! $1. TSFP Spent fuel pool operating floor, located on the 605' elevation of the Fuel Building i- 52, SDPNLRMA Shutdown Panel Room A, located on the 543' elevation of the
- Auxiliary Building i $3. SDPNLRMB Shutdown Panel Room B, located on the 543' elevation of the Auxiliary Building - '
i- " )* p 109- 12/88T
TABLE 4 2. PAFlTIAL LISTING OF COMPONENTS BY LOCATION AT CATAWBA 1 & 2 b LOCAlON Sy5 TEM COMPONE N T ID COMP TYPE 4 % CAB CCW CCW PIB MDP T60AB CCW CCW P2A MDP
$60Ab CCW CCW P2B MDP 66 CAB CCW CCW P1 A MDP Tt7AB CCW CCW-61B MQ/ ~
677Ab CCW CCW 56A MOV
$77AB CCW CCW HAIA M 677AB CCW CCWB.HAlb $
577AB SW NSW58B MOV 677AB SW NSW GP MOV
$77AB SW NSW 226B i.iOV 677AB SW NSW 67A MOV 677AB SW NSW 144A MOV
$77AB SW NSW.3478 MOV 577AB SW NSW43A MOV 677AB SW NSW 287A MOV AF W PMRM AF W AF W 15A MOV AFWPMRI ~ AFW AFW 116A MOV AFWPMAM AFW AFW 66B MOV AF WPMRV AF W AFW 31CB MOV r
AFWPMAM AFW AFW TD1 TDP AFWPMAM AFW AFW PIB MDP 1 AF WPMRM AF W AFW P1A MDP AFWPMAM AFW AF W 16B MOV AF A PMAM AFW AFW 250A MOV AF WPMRM AF W AF W5175 MOV AF WPMRM AF W AFW 174 MOV ASWGRM EP BUSIELAA BUS ASWGRM EP TfMNIETAC TRAN g, ASWGRM EP BUSIETA BUS I \ 110 12/88
._ m.____ , - . _ . _ _ . . _ - . ._..m._. . - . ._..._m . . . _ - ._.._.__-......__m-.. . . _ . . . - _ . _
i TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION { AT CATAWBA 1 & 2 (CONTINUED) ' LOCATON SYSTEM COMPONENT C COMP TYPE EiY. 1 CB ETA CB ! ASWGRM EP 'sV51ELAC BUS a ASWGRM EP TRANit'TAE TRAN A6WGRM EP TRANIETAA TRAN BATRMA EP BATT1EBA BATT BATRMB EP BATT1 EBB BATT BAT RMC EP BATT1EBC BATT BAIRMD EP BATT1EBD BATT MWGRM EP BUS 1ELAD BUS MWGRM EP TRANIETAD TRAN MWGRM EP BUSIETB BUS BSWGRM EP CB-ET B CB MWGRM EP BUSIELXB BUS MWGRM EP TRANIETXB TRAN MWGRM EP . TRANIET AF TRAN CHPMRMA CVCS CV.P 1 A MDP CHPMRMB CVCS CV P1B MDP 3CSWGRM EP BUS 1ECA BUS DCSWGRM - EP BUS 1EDB BUS DCSWGRM EP BUS 1EDC BUS ! DCSWGRM EP BUS 1EDD BUS DCSWGRM EP BC1ECA BC DCSWGRM EP BC1ECB BC CCSWGRM EP BC1ECC BC DCSWGRM EP BCIECD BC-DCA - EP DG1A [X3 DM ~EP BATTIDGBA BATT DGA SW NSW.232A .. MOV DGA SW NSW 646A EdV. DGB EP DG1B DG ill- 12/88 a i i.
-.- ..- ,, , , . . ~ m. , - . - . , - - , - . . . . . . , , . , , ~ , - , _ - - . , _ . - , -.-.s * .
TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION AT CATAWBA 1 & 2 (CONTINUED)
\
LOCATION SYSTEM COMPONENT @ COMP TYPE DGb EP 6ATT 1DGBD BATT DSB SW NSW 2920 MOV DSB SW NSW4460 MOV NA R t.% ECC5 RH.26A MOV HARN% ECC5 RM 32A MOV HARMB ECCS RH460 NOV C*1 AFW AF W40A MOV 08 AF W AF W44B MOV OH AFW AFW 460 MOV O *4 AF W AFW46A MOV M; E N RM643 CVCS CV-10D MOV MkENRM643 CVCS CV 19A lAOV ME E N RM643 ECC5 RM 165A MOV MPENRM643 ECCS RH 164B MOV MF ENRM543 ECCS St162A MOV MPENRV543 ECCS 511620 MOV MPENRM643 ECCS GittA MOV N5AA SW NSW P1 A MDP N5WA SW NSW 26A MOV
'WLAB SW NSW PID MDP h5AB SW NSW 360 MOV ODH AFW AFW42A MOV ODN AF W AFW 428 MOV RC RCS RH 1B MOV RC RCS RH 2A MOV i
RC RCS RH 368 NV ) R0 RCS R+37A MOV RC RCS ACSVESSEL RV RC RCS RG 34A NV j] RC RCS RC 36B NV 112 12/88
.- - ~.. . - - . . . .
TABLE 4 2. PARTIAL LISTING OF OGMPONENTS BY LOCATION AT CATAWBA 1 & ' e(CONTINUED) k LOCAllON SYSTEM COMPONENT 10 COMP TYPE RC RCh RC 32B NV RC RC5 RG 33A MOV 4 RC 4C5 RC 3tB MOV RC RCS RC 31D MOV RNRPMRMA ECCS RH PIA MDP RNRPMRMB ECCS RH-PIB MDP Re bT CvCS Si-RWST TK R AST ECCS 6bRW6T 1h SiPM44% ECCS SIPIA MDP 4 SiPMRMA ECC5 Si103A MOy 5+ MR4% ECCS bi116A MOV 54MRMS CVC5 CV 252B MOV SiPMRMB CVC5 CV 2b38 MOV biPMRMB ECCS 51;1000 MOV V SWMRMB ECCS 54135B MOV 56PMRMB ECCS RH 136B MOV SiPMAMB ECCS StPIB MDP SiPMRVB ECCS Si 150B MOV Kh AF W AFW 176 MOV [ 1 113 12/88
Catawba 1 & 2
- 5. IIIBLIOGRAPIlY FOR CATAWBA NUCLEAR STATION
- 1. NUREG 0054, " Safety Evaluation Repon Related to the Operation of Catawba Nuclear Station, Units 1 and 2,' USNRC, May 1986.
- 2. NUREG 1191, " Technical Specifications for Catawba Nuclear Station, Units 1 and 2," USNRC.
- 3. Fresco, A., et al.," Review of Catawba, Units 1 and 2 Auxiliary Feedwater System Reliability Analysis," Brookhaven Nation Laboratory, October 1983.
i i \ O 111 12/88
Catawba 1 & 2 i } i APPENDIX A DEFINITION OF SYh1BOLS USED IN Tile SYSTEh! AND f LAYOUT DRAWINGS A1. SYSTEh! DRAWINGS A1,1 Fluid System Drawings The simplified system drawings are accurate representations of the major now paths L in a system and the important interfaces with other Guld systems. As a general mle, small [ fluid lines that are not essential to the basic operation of the s drawings. Lines of this type include instrumentation vent tines,ystem lines, drainare lines, notand shown
- in these other lines that are less than 1/3 the diameter of the connecting major flow path. There i usually are two versions of each nuld system drawin a simplified system drawing, and a 4
comparable drawing showing component locations. T g:he drawing conventions used in the i fluid system drawings are the fo' lowing: 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. 1 - One exception is the return flow path in closed loop systems which is right - ! to left. Another exception is the Reactor Coolant System (RCS) drawing which is
" vessel. centered", with the pr%ary loops on both sides of the vessel, i- -
Horizontal lines always dominate and break vertical lines. b\_/ Component symbols used in the fluid system drawings are defined in Figure A 1. hiost valve and pump symbols are designed to allow the reader-to distinguish among similar components based on their support system - 1 requirements (i.e., electric power for a motor or solenoid, steam to drive a ! turbine. pneumatic or hydraulic source for valve operation, etc.) Valve symbols allow the reader to distinguish among valves that allow flow 4 in either direction, check (non return) valves, and valves that pe form an overpressure protection function. No attempt has been made to d: fine 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 l _ pumps and between types of pump drives (i.e., motor, turbine, or engine). L - locations are identified in terms of plant location codes defined in Section 4 of ] this Sotircebook. lustion is indicated by shaded " zones" that are not intended to represent the actual mom 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. 115- 12/88 4 .
t i Catawba 1 & 2 , Al.2 Electrical S) stem Drawings i The electric power syrtem drawings focus on the Class lE portions of the plant's electrie sower sys'em. Separate drawings are provided for the AC and DC portions of the 1 Class 13 system. There often are two versions of each electr' cal system drawingt a
- simplified system drawing, and a comparable drawing showing component locations. The
{ drawing conventions used in the electncal system drawings are the following: Flow generally is top to bottom In the AC power drawings, the interface with the rwitchyard and/or offsite !. ; rid is shown at the top of the drawing.
.n the DC power drawings, the batteries and the intedsee with the AC i power system are shown at the top of the drawing. .
Vertical lines dominate and break horizontal lines. Component symbols used in the electrical system drawings are defined in Figure A 2. locations are identified in terms of plant location codes defined in Section 4 of this Sourcebook, Locations are indicated by shaded " zones" that are not intended to represent ' the actual room geometry. Locations of discrete components represent the acteal physical location of the component. The electrical connections (i.e., cable runs) between discrete components, as shown on the electrical system drawings, DO NOT represent the actual cable routing in the plant. Component locations that are not known are indicated by placing the discrete components in an unshaded (white) zone. l A2. SITE AND LAYOUT DRAWINGS i
- A 2.1 Slie Drawings i
A general view of each reactor site and vicinity is presented along with a simplified i site plan showing the arrangement of the inajor buildings, tanks and ot1er features of the - site. The general view of the reictor site is obtained from ORNL NSIC 55 (Ref.1).- The site drawings are ap ar( mdj to scale, but should not be used to estimate distances on-the site. As built sea e draJ.gs should be consulted for this purpose. Labels printh m bold uppercase correspond to the location codes defined in Section - 4 and used in the component data listings and system drawings in Section 3. Some - l additional labels are included for information and are printed in lowercase type. A2.2 Layout Drawings j-Simplified building layout drawings are developed for the portions of the plant that i contain components and systems that are described in Section 3 of this Sourcebook. Onnerally, the following buildings are included: reactor building, auxiliary building, fuel - t,uilding, 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,-
116 12/88 i 4
Catawba 1 & 2 are approximately to scale, should not be used to estimate room size or distances. As built scale drawings for should be consulted his purpose, s' Labels printed in uppercase bolded also correspond to the location codes defined in Section 4 and used in the component data listings and system drawings in Section 3. Some additional labels are included for information and are pnnted in lowercase type. A 3. APPENDIX A REFERENCES
- 1. lieddleson, F. A., " Design Data and Safety Features of Commercial Nuclear Power Plants.", ORNL NSIC 55, Volumes 1 to 4, Oak Ridge National Laturatory, Nuclear Safety information Center, December 1973 (Vol.1),
January 1(>72 (Vol. 2), April 1974 (Vol. 3), and March 1975 (Vol. 4) O V i 117 12/88 1 1 l
. . . . . . . . - _ . . . .. . .. ~- . . -. .--
1 I i h w.) (OPE CLC ) VALVE ECV (OP N CLOSED) O _ MOTOR.0PER ATED VALVE . MOV _ (O P E N /C LO S E D) p L MOTOR.0P E R A TED 8 WAY VALVE
- MOV (CLOSED PORT MAY VARY)
W L > SOLENotD.0PER ATED YALVE
- BOV 50L E NotD.0P E R ATED r' (O P E N 'C L0 s E D) s WAY VALVE . s0V (CLOSED PORT MAY YARY)
HYDR AULIC VALVE a HV
~ (OPEN CLo&ED)
L HYDR AULIC NON. RETURN 4 4 VALVE . HCV (OPENtLOSED)
% _ PNEUMATIC VALVE . NV PNEUMATIC NON. RETURN (O P E N >C LO $ E D)
VALVE . NCV (OPEN/ CLOSED)
,, CHECK VALVEa CV M SAFETY VALVE SV (CLO8ED)
\
& c1 ML POWER OPER ATED RELIEF VALVE, SOLEN 0lD PILOT TYPE , PORY J POWER 0PERATED RELIEF VALVE, (CL O S E D) PNEUMATICALLY OPER ATED . PORY
-OR DUAL. FUNCTION S A FE TYlR ELIE F VALVE
- SRV (CLOSED)
CENTRIFUC AL CENTRIFUG AL MOTOR. DRIVEN PUMP
- MDP TURRINE. DRIVEN PUMP e TDP i
\ /
l-l
, POSITIVE DISPL ACEMENT -
MOTO9 0 RIVEN PUMP MDP POSITIVE DISPLACEMENT TURBINE DRIVEN PUMP TOP l I
\ /
- j. I
/ \
l Figure A-1. Key To Symbols-in Fluid System Drawings 118 tyn i
. , , , , . . wyw y-- v -
.m. .._ . _ _ - . _ _ , _ _ _ _ _ _ _m._..___,_.._.. . . . . . . - . ._ _. .. _,.._ _ ..._,..... _ ~ .._ ___...,_~.. ._.m.___.._.. .
n 1 PWR DWR W AlH CONDENSER e COND REACTOR VESSEL
- RV !
i e > l I l Q -
- HE AT EXCH ANGER
- HX MECHANICAL DRAFT COOLING TOWER l
STE AM-TO.W ATER OR W ATER.TO STE AM HE AT h - AIR COOLING UNIT
- ACV g
ErCHANGER (LE FEEDW ATER HE ATER, DR AIN COOLER ETC.) . HX i O OR TANK +TK aaaaaaaa 8* ~ V
- RUPTURE DISK . RD FILTER . FLT-ORIFICE
- OR )
I \ Figure A-1. Key To Symbols-In Fluid System Drawings (Continued). 119 12/88 i 3.- 5___________ _ _ _ . _ _ _ . _ .. .. _ . . _ , . . , _ _ . , , , , , , _ _ _ _ _ . _ . _ , ,, _, ,,, ,, ,. ., , , , ,
,,,,r.,,,,,. ,.,.,
. . . . - - _ . . . - . . .. . - - , . - . . - . . , . - - . - . . . . . . . - , .- . . . . . - . - . . . ~ - . - . ~ - . - ~ , . . . .- -. . ~ .
s =
~
1 A.C. DIESEL OENER ATOR e DO _ ' S ATTERY
- S ATT -
CH A C. TURBINE GENERATOR . 70 CR l CIRCUtt BRE AKER . CB I.J U (oPEN/ CLOSED) - $ 3 ***-H OR II .!) IN TERLOCKED CIRCUIT BREAXERS
- CB SWITCH = SW p AUTOM ATIC OR OR CTHER TYPE OF TR ANSFER SWITCH . ATS DISCONNECT DEVICE OR (O P E NIC LO S E D)
MANU AL TR AN3FER j SWITCH . MTS , SWITCH 0E AR BUS . BUS i [ (Bus N AME l MOTOR C0llTdOL CENTER = MCC N @ OR W W- " W TRANSFORMER.'TRAN t CR .. DISTRIBUTION P AhEL = PNL l l { 5 ! B ATTERY CHARCER (RECTIFIER) . BC _ 1 2 . INVERTER
- INV g
! T 4 i l 1
~
i :: OR RELAY CONT ACTS pygg ,pg ,
- I (OP E N!CLO4 E D) ,,
! I 1 1 y ELECTRIC MOTOR MTR gg y , L 2 1 i r i. 1 i-Figure A-2. Key To Symbols in Electrical System. Drawings 12/88 120 _ _ . . . . . . . . . _ . . - _ . - ~ , . _ _ . . - - -
( A STAIRS o' Down g SPIRAL STAIRCASE LADDER U = Up (*! D= cown ELEVATOR
,g~
HATCH OR - OPEN AREA-GRATING DECK (NO FLOOR) 4
-O- PERSONNEL DOOR --I
- EQUIPMENT DOOR g :<
j 3 RAILROAD TRACKS :( FENCE LINE
- O TANK / WATER AREA e
4
; Figure A 3. Key To Symbols in Facility Layout Drawings I
121 12/8S E 1 - r -
,y , , ,rn--r----- .yfy-,-,-~, -r,, .,,m-w. e ,,yg-n-,. -,-,-a-f 7*-- "ar -V- v-i'
Catawba 1 & 2 i' APPENDIX B DEFINITION OF TER5fS USED IN TIIE DATA TABLES Terms appearing in the data tables in Sections 3 and 4 of this Sourcebook are defined as follows: j SYSTEM (also LOAD SYSTEM) All components associated with a particular system l description in the Sourcebook have the same system code in the data base. System codes used in this Sourcebook are the following: Cnk Definition ! RCS Reactor Coolant System AFW Auxiliary Feedwater System ECCS Emergency Core Cool System 4 CVCS Charging System I&C Instrumentation and Control System EP Electric Power System CCW Component Cooling Water System SW Nuclear Service Water System COMPONENT ID (also LOAD COMPONENT ID) - The component identification (ID) code in a data table matches the component ID that appears in the 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 prefau corresponds to what the plant U calls the component (e.g. HPI, R11R). An example is HPI 730, denoting valve number 730 in the high pressure injection system, which is part of the ECCS, The component number is a contraction of the comaonent number appearing in the plant piping and instrt.. ntation drawings (P& ids) anc electrical one line system drawings. LOCATION (also COMPONENT LOCATION and POWER SOURCE LOCATION)- Refer to the location codes defined in Section 4, COMPONENT TYPE (COMP TYPE)- Refer to Table B 1 for a list of component type codes. POWER SOURCE - The component ID of the power source is listed in this field (see COMPONENT ID, above). In this data base, a " power source" for a particular component (i.e. a load-or a distribution component) is the next higher electrical distribution or generating component in a distribution system. A single com ponent may have more than one power source (i.e. a DC bus powered from a battery and a battery charger). POWER SOURCE VOLTAGE (also VOLTAGE)- The voltage "seen" by a load of a power source is entered in this field.' The downstream (output) voltage of a transformer, i inverter, or battery charger is used. ' EMERGENCY LOAD GROUP (EMERG LOAD GROUP)- AC and DC load group:, (or electrical divisions) are defined as appropriate to the plant. Generally, AC load groups are identi6ed as AC/A, AC/B, etc. The emergency load group for a third of a-kind load (i.e. a " swing" load) that can be powered from either of two AC load groups would be-
\ identified as AC/AB. DC load group follows similar naming conventions.
122 12/88
^ TABLE B 1. COMPONENT TYPE CODES 1
COMPONENT COMP TYPE VALVES: Motor-operated valve MOV-Pneumatic (air-operated) valve NV or AOV Hydraulic valve - -HV- " Solenoid-operated valve SOV Manual valve XV Check valve CV Pneumatic non return valve NCV Hydraulic non-retum valve HCV l Safety valve SV Dual function safety / relief valve SRV Power-opera:ed relief valve 'PORV 7 (pneumatic or solenoid operated) PUMPS: Motor driven pump (centrifugal or PD)' MDP Turbine-driven pump (centrifugal of PD) TDP Diesel-driven pump (centrifugal of PD) DDP , 4 OTHER FLUID SYSTEM COMPONENTS: ! Reactor vessel RV-i( f Steam generator (U tube or once through) Heat exchanger (water to-water HX, SG HX or water to air HX) Cooling tovc;r CT-Tank TANK or TK - Sump SUMP i _ Rupture disk RD-Orifice ORIF - Filter or strainer FLT- - l Spray nozzle - SN l Heaters (i.e. pressurizer heaters) HTR VENTILATION SYSTEM COMPONESTS: 4
- - Fan (motor driven, any type) FAN 1 Air cooling unit (air to-water HX, usually . ACU or FCU j- including a fan)
Condensing (air conditioning) unit TCOND i-1 EMERGENCY POWER SOURCES: Diesel generator - _ DG' Gas turbine generator GT
- Battery BATT I
LO 123 12/88
,. -, , , , . , , - - . . , - - - - . . . . . . - ~ . . .-+ - .- .
TAllLE B.I. COMPONENT TYPE CODES (Continued)
-L COMPONENT - coup TYPE ELECTRIC POWER DISTRIBUTION EQUIPMENT:
! Bus or switchgear BUS-o Motor control center MCC l Distribution panel or cabinet PNL or CAB Transformer TRAN or XFMR - ; Battery charger (rectifier) BC or RECT Invener 'INV L Unintenuptible power supply (a unit that may UPS include battery, sattery charger, and inverter) Motor generator MG Circuit breaker CB Switch SW Automatic transfer switch ATS I Manual transfer switch MTS-t I a w J l i e p-f.- 4 s 124 f 12/88 ,
. . -- .- - . . - - - - _ . - -. - ..}}