Text

Nuclear Power Plant Sys Sourcebook,Cooper
	ML20070Q778
Person / Time
Site:	Cooper
Issue date:	12/31/1988
From:	Goldman L, Lobner P; SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY
To:	; NRC
References
	CON-FIN-D-1763, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-88-1994, NUDOCS 9103290176
	Download: ML20070Q778 (99)
	v • d • e

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4 4**M COOPER 50 298 Editor: Peter Lohner Author: Lewis Goldman 1 i Prepared for: U.S. Nuclear Regulatory Ccmmission Wsshington, D.C. 20555 Contract NRC 03 87 029 FIN D 1763 O diiliitfE: i m .-m. ,o-- ,,,,.y y r-

Cooper h TABLE OF CONTENTS \\ Section Put 1 S UM M ARY DATA ON PLANT........................................... 1 2 IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS... 1 3 S YSTE M INFORMATI ON................................................. 2 3.1 Reactor Coolant S ystem (RCS)................................ 8 3.2 Reactor Core Isolation Cooling (RCIC) System............. 13 3.3 Emergency Core Cooling System (ECCS)................... 18 3.4 Instrumentation and Control (l&C) Systems................. 33 3.5 Ele etric Power S yste m.......................................... 36 3.6 Control Rod Drive Hydraulle System (CRDliS)............ 46 3.7 Reactor Building Closed Ce , Water (RBCCW) System.......................................................... 49 3.8 Service Water (SW) S ystem.................................... 53 4 P L A NT I N FO RMATI ON.................................................... 58 4.I S ite and B uildin g S ummary.................................... 58 4.2 Facility Layout Drawin gs...................................... 58 5 BIBLIOORAPITY FOR COOPER NUCLEAR STATION.............. 81 APPENDIX A, Dennition of Symbols used on the System and Layout Drawings..................................................................... 82 APPENDIX B, Dennition of Terms used in the Data Tables............ 89 ( i. 12/83

Cooper O LIST OF FIGURES Eigmr Past 31 Cooling Water Systems Functional Diagram for Cooper................. 7 3.1 1 Cooper N uclear Boller S ysiem.............................................. 10 3.1 2 Coop;r Nuclear Boiler System Showing Component Locations........ I1 3.2 1 Cooper Reactor Core Isolation Cooling (RCIC) System................ 15 3.2 2 Cooper Reactor Core Isolation Cooling (RCIC) Syctem Showin g Compone nt Locations............................................. 16 3.3 1 Cooper High Pressure Coolant Injection (HPCI) System................ 22 3.3 2 Cooper High Pressure Coolant injection (HPCI) System Showin g Compone nt Locations............................................. 23 i 3.3 3 Cooper Low Pressure Coolant Injection System A..................... 24 3.3 4 Cooper Low Pressure Coolant Injection System A Showing Component Loeations........................................................ 25 i 3.3 5 Cooper Low Pressure Coolant Injection System B...................... 26 3.3 6 Cooper Low Pressure Coolant injection - System B Showing Component Locations......................................................... 27 3.3-7 Cooper Core S pray S ystem (CSS).......................................... 28 3.3 8 Cooper Core Spray System (CSS) Showing Component Locations.... 29 3.5 1 Cooper 4160. 480, and 120 VAC Electric Power Distribution System......................................................................... 38 3.5 2 Cooper 250 and 125 VDC Electric Power Distribution System......... 39 3.6 1 Simplified Diagram of Portions of the Control Rod Drive Hydraulic System that are Related to the Scram Function............... 48 3.7-1 Cooper Reactor Building Closed Cooling Water System................. 51 3.7 2 Cooper Reactor Building Closed Cooling Water System Showing Component Locations......................................................... 52 3.8 1 Cooper Service Water (SW) and RHR Service Water Booster System.......................................................................... 55 (3 ty 3.8 2 Cooper Service Water (SW) and RHR Service Water Booster S y stem S howing Compone nt Loc ations................................... 56 11. 12/88

Cooper LIST OF FIGURES (continued) Figure h j 41 General View of Cooper Nuclear Station and Vicinity.................. 59 4 42 Cooper Nuclear Station She plan........................................... 60 43 Cooper Nuclear Station Reactor Building Section........................ 61 4 44 Cooper Nuclear Station Reactor Building, Elevation 859' 9"........... 62 45 Cooper Nuclear Station Reactor Building, Elevation 881' 9"........... 63 1 46 Cooper Nuclear Station Reactor P:lilding, Elevation 903' 6"........... 64 47 Cooper Nuclear Station Reactor Building, Elevation 931' 6"........... 65 e 48 Cooper Nuclear Station Reactor Building, Elevation 958' 3"........... 66 49 Cooper Nuclear Station Reactor Btflding, Elevation 976' 0"........... 67 i j 4 10 Cooper Nuclear Station Reactor Building, Elevation 1001' 0".......... 68 i i 4 11 Cooper Nuclear Station Turbine Building, Elevation 882' 6"........... 69 4 4 12 Cooper Nuclear Station Turbine Building, Elevation 903' 6"........... 70 l 1 4 13 Cooper Nuclear Station Turbine Building, Elevation 918' 0"........... 71 4 14 Cooper Nuclear Station Turbine Building, Elevation 932' 6"..........._ ~72 4 15 Coope r Nuclear S tation In take S tructure.................................., 73 A1 Key To Symbols In Fluid System Drawings............................. 85 A2 Key To Symbols In Electrical System Drawings.........................- 87 A3 Key To Symbols In Facility Layout Drawings............................ 88 (v l 4 111. 12/88-

Cooper LIST OF TABLES IIbk Page 31 Summary of Cooper Systems Covered in this Repon.................... 3 3.1 1 Cooper Reactor Coolant System Data Summary for Selected Components.................................................................... 12 3.2 1 Cooper Reactor Core Isolation Cooling System Data Summary for S e lected Compone nt s......................................................... 17 3.3 1 Cooper Emergency Core Cooling System Data Se nvy for S e lec ted Compone nt s......................................................... 30 3.4 1 Matrix of Cooper Control Power Sources................................. 35 3.5 1 Cooper Electric Power System Data Summary for Selected Components.............-...................................................... 40 3.5 2 Partial Listing of Electrical Sources and Loads at Cooper................ 42 3.8 1 Cooper Service Water System Data Summary for Selected Components.................................................................... 57 [ 41 Definition of Cooper Building and Location Codes....................... 74 ( 42 Partial Listing of Components by Location at Cooper.................... 76 B1 Compon e n t Type Cod e s...................................................... 90 r~ kv iv. 12/88

m e Cooper \\ 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 ref ects 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 u pdated with new and/or replacement p ges as appropriate to incorporate additional information on this reactor P ant. Technical errors in this report should be brought to the attention of the following: Mr. hiark Rubin U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Engineering and Systems Technclogy Mail stop 7E4 Washington, D.C. 20555 i Mr. Peter Imbner Manager, Systems Engineering Division Science Applicationsinternationa Corporation 10210 Campus Point Drive San Diego,CA 92131 (619)458 2673 Correction and other recommended changes should be submitted in the form of marked up copies of the affected text, tables or figures. _ Supporting documentation should be included if possible, l l t 1 l v. 12/88-I _._,-._,-.._,_...m_. ..._....._.-,,.4.__....

1 4 4 C COOPEP. RECORD OF REVISIONS i f HEYlS10N ISSUE C0515fENTS 0 12/88 Original report I r l I l i f i i l s l. a ] VI. 12/88 .~,.--,,~.--.._.. - -,.. ~,. _. .-..-~...,----- -.,-.,,,- -.--,,~..

Cooper COOPER SYSTEM SOURCEHOOK This sourcebook contains summary information on Cooper. Summary data on this plant are presented in Section 1, and similar nuclear power plants are identified in .Sectfon 2. Infonnation 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 data tables are defined i.. Appendix B. 1.

SUMMARY

DATA ON PLANT Basic information on the Cooper Nuclear Station is listed below: Docket number 50 298 Operator Nebraska Public Power District Location Nebraska 21/2 miles South of Brownville Commercial operation date 1974 1 Reactor type - BWR/4 NSSS vendor General Electric. Power (MWt/MWe) 2381/801 Architect-engineer Burns and Roe Containment type Steel drywell and wetwell(Mark 1) 2. IDENTIFICATION OF SIMILAR NUCLEAR POMTR PLANTS The Cooper Nuclear Station contains a General Electric BWR/4 nuclear stearn supply system with a IWark I BWR containment imorporating the drywellhressure !y suppres: ion concept. The plant has a secondary containment structure of te nforced L concrete Other BWR/4 plants in the United States are as follows: e Browns Ferry 1,2 and 3 Verinont Yankee 4 Peach Bottom 2 and 3 4 j Hatch I and 2 i Duane Arnold Fitzpatrick Brunswick 1 and 2 Ferm12 Hope Creek 1 Limerick 1 and 2 (Mark II Camalnment) Shoreham (Mark 11 Containment) Susquehanna 1 & 2 (Mark Il Containment) 1 12/88 1

Cooper 3. SYSTEM INFORMATION This secticn contains descriptions of selected systems at Cooper in terms of general function, operation, system success criteria, major components, ated support system requirements. A summary of major systems at Cooper is presented in Table 31. In t e " Report Section" column of this table, a section reference (i.e. 3.1,3.2, etc.) is h provided for all systems that are described in this report. An entry of "X" in this columri means that the system is not described in this report. In th' "FS AR Section Reference" column, a cross reference is provided to the section of the Final Safety Analysis Report where additional information on each system can be found. Other sources ofinformation on this plant are identified in the bibliography in Section 5. Several cooling water systeins are identified in Table 31. The functional relationships that exist among cooling water systems required for safe shutdoven are shown in Figure 31. Details on th individual coohng water systems are provided in the report sections identified in Table 31. p $\\j v 2 12/88 i ...o

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.{ ) x. Table 3-1. Summary of Ccaper Systems Covered it..this Report e Generic Plant-Specific Report USAR

tiion System Name System Name

- Section Referetur Reactor Heat Removal Systems - Reactor Coolant Syston (RCS) Same 3.1 IV-2 to IV-6, IV-10 - Reactor Core Isoiation Cooling Same 3.2 IV-7 (RCIC) Systemt - Fmergency Core Cooling Systems Core Standby Cooling Systems (dCCS). - Iligh-Pressure Injection High-Pressure Coolant Iniecdon ?3 VI-4.1, VI-5 & Recirculation (HPCI) System - Low-pmure Injection. Core Spray (CS) System, 3.3 VI-43, VI-5 & Recirculatioa low-Pressure Coolant Injection 3.3. IV-8.5.4 (12CI) System (an operating mode VI-4.4, VI-5 a of the RIIR system) - Automatic Depressurization Same 3.3 VI-4.2, VI-5 . System (ADS) .i f - Decay Heat Removal (DHR)L Residual Heat Removal 3.3 IV-8 ' System (Residual lieat Removal. (RIIR) System (a m* ' % node - (RilR) System) system) - IWain Steam and Power Conversion Main Steam System, X IV-11, XI-5

Systems Condensate System, X

XI-7 to XI-9 ^ Feedwater System, X IV-11, XI-8 Circulating Water System X XI-6 l - Other Heat Removal Systems Steam-condensing RIIR/RCIC 3.2 - IV ' 5.5 operation j [. t 6 m ~ _..,....

I-O C O Table 3-1. Summary of Cooper Systems Covered in this Report (Continued) Generic l@nt-Specific Report USAR Section Systes Name System Name Section Reference Reactor. Coolrut Inventory Control Systems ReactorWaterCleanup(RWCU) Same X IV-9 System - - ECCS .See Core Standby Cooling Systems - above Contml Rod Drive Ilydraulic System (CRDIIS) Same 3.6 111-5.5.2 - Containment Systems Primary Centainment - Same(drywell and pressure X V-2 suppression chamber) o a Secondary Conninment Same X V-3 - Standby Gas Treatment System (SGTS) Same' X V-3.3.4 - ContainmentIIcat Re noval Systems - Suppression Pool Cooling System - Same (an operating mode of the 3.3 IV-8.5.3.2 RIIR system) - Containment Spmy 5,, tem Same (an operating mode of the 3.3 IV-8.5.3.1 RIIR system) - Containment Fan Coola stem P6uary Contdnment (Drywell) X V-2.3.7 Cooling System (fan coolers) ' -- Containment Normal Vc,tilation Systems Primary Containment (Drywell) X V-2.3.7 Cooling System (fan coolers) - Combt.stible Gas Control Systems Nitrogen Inerting System, X V-2.3.8.2 Atmospheric Containment X V-2.3.8.3 e Atmosphere Dilution (ACAD) =

System, l' urge to atmosphere or to X

V-2.3.8.4 SGTS

v,y -~ O C O Table 3-1.. Summary of Cooper Systems Covered in this Report (Continued) ^ Generic Plant-Specific Report USAR Section System Name System Name Section Reference Reactor and Reactivity. Control Systems - Reactor Core Same' X III - Control Rod System Control Rod Drive Mechanisms X III - Chemical Poison System Standby Liquid ContmlSystem X III-9 (SLCS) Instrumentation & Control (I&C) Systems - ' Reactor Protection System (RPS) Same 3.4 VII-2 - Engincem! Safety Feature Actuation Primary Cr tiinment and Reactor X VII-3 System (ESFAS) Vessel P.ition Contml System, r .dby Cooling System 3.3 VII-4 u L.arol and Instrumentation, Standby Gas Treatment System -X VII-17 Actuation - Remote Shutdown System local control panels 3.4 VII - Other I&C Systems Various other systems X VII-5 to VII-16 Support Systems - Class IE Electric PowerSystem: Same 3.5 VIII -- Non-Class IE Electric Power System. Same X VIII - DiesciGenerator Auxiliary Systems Same 3.5 VIII Q Component Cooling Water (CCW) Reactor Building Closed 3.7 X-6 Sysicm Cooling Water (RBCCW) System oo L L ___

i D O*f U Table 3-1. Summary of Cooper Systems Covered in this Report (Continued) l Generic l': ant-Specific Report USAR Section System Name. System Name Section Reference i Support Systems (continued) - Service Water System (SWS) Service Water and RIIR 3.8 X-8 Service Water Booster System Residual IIcat Removal Service Water Service Waterand RIIR 3.8 X-8 (RifRSW) System Service Water Booster System l -.Other Cooling Water Systems Turbi,e Building Closed X X-7 Cooling Water (TBCCW) System - Fire Pmtection Systems Same X X-9 l Same X X-10 l - Foom iIcating, Ventilating, and Air-1 m Conditioning (lIVAC) Systems ' l Instrument and Service AirSys.tems. Same X X-12 i - Refueling and FuelSheaxSystems Same' X X-2 to X-5 - - Radicxtive Waste Swt:ms. Same X IX - Radiation Prtxection Systems. Same X XII i 4 h h,, q 4 co i 00 I's-1 3 t i

h' O m ECCS = EssentialComponent Cooring System RBCCWS = Reactor Eksidng Closed Coosng Water System sws - service water system l uissouR R r DIESEL GENERATOR r, 7 COOLING.J t -p .. S WS - r C J RHR HEAT. m.- EXCHANGERS C Y r 3 f? RBCCWS HEAT EXCHANGERS C J d r 3 y ECCS PUMPS - 0 AND AREA COOLING j p. y .=. Figure 3-1.- Cooling' Water Systems Functional Diagram for Cooper.- r

Cooper ( 3.1 REACTOR COOLANT SYSTEM (RCS) l 3.1.1 System Function - The RCS, also called the Nuclear Steam Supply System (NSSS), is responsible for directing the steam aroduced in the reactor to the turbine where it is used to rotate a generator and produce e ectricity. The RCS pressure boundary also establishes a boundary against the uncontrolled release of radioactive material from the reactor core and primary coolant. 3.1.2 System Definition The RCS includes: (a) the reactor vessel, (b) two recirculation loops,-(c) recirculation pumps, (d) 3 safety valves, (c) 8 safety / relief valves and (f) connected piping out to a suitable isolation valve boundary. A sim alified diagram of the RCS and important system interfaces is shown in Figures 3.1-1 anc. 3.12.- A summary of data on selected RCS components is presented in Table 3.1-1, 3.1.3 System Oneration During power operation, circulatica in the RCS is maintained by one recirculation pump in each of the two recirculation loops and the associated jet pumps internal to the reactor vessel. The steam water mixture flows upward in the core to the steam dryers and separators where the entrained liquid is removed. The steam is piped through the main steam lines to the turuine. The separated liquid returns to the core, mixed with the feedwater and is recycled again. .About 1/3 of the liquid in the downcomer region of the reactor vesselis drawn off by the recirculation pumps. The discharge of these pumps is returned to the inlet - fs (v) nozzles of the jet sumps at high velocity. As the liquid enters the jet pumps the slow moving liquid m tie upper region of the downcomer is induced to flow through the jet pumps, producing reactor coolant cin:ulation. The steam that is produced by the reactor is piped to the turbine m. the main steam line. There are two main steam isolation valves (MSIVs)in each main steam line. Condensate from the turbine is retumed to the RCS as feedwater -- Following a transient that involves the loss of the main condenser or loss of feedwater, heat from the RCS is dumped to the suppressicm chamber via safety /relbf valves on the main steam lines. A LOCA inside contamment or operation of the Automatic Depressurization Systems (ADS) also dumps heat to the suppression chamber. Makeup to the RCS is provided by the Reactor Core Isolation Cooling (RCIC) system (see Section 3.2) or by the Emergency Core Cooling System (ECCS, see Section 3.3). Heat is transferred from the containment to the ultimate heat sink by the Residual Heat Removal (RHR) system operating in the suppression pool cooling moc'N Actuation systems provide for automatic closure of the MSIVs and isolanon of other Fnes connected to the RCS, 3.1.4= System Success Criteria - The RCS success criteria can be descrited in terms of LOCA and transient-mitigation, as follows: An unmitigatible LOCA is not inihted. If a mitigatible LOCA'is initiated, tNn LOCA mitigating systems are - successful. If a transient is initiated, then eithv A S 12/2R r ~

l Cooper RCS integrity is maintained and transient mitigating systems are successful, or RCS integrity is not maintained, leading to a LOCA like condition (i.e. stuck open safety or relief valve, reactor coolant pump seal failure), and LOCA mitigating systems are successful. 3.1.5 Comnonent Information A. RCS

1. Total volume: 14,302 ft3

2. Water volume: 8,199 ft3 (including recirculation loops).

3. Steam volume: 6,103 ft3 6

l

4. Steam flow: 9.56 x 10 lb/hr.

5. Normal operating pressure: 1020 psia t

l' B. Safety /ReliefValves(8)

1. Set pressure: 1080 to 1100 psig

2. Relief capacity: 870,000 lb/hr each C. Safety valves (3)

1. Set Pressure: 1240 asig

2. Capacity: 642,000 : h/hr each D. Recirculation Pumps (2) l

1. Rated flow: 45,200 gpm @ 500 ft. head (217 psid)

2. Type: Verticalcentrifugal E. Jet Pumps (20) 6

1. Total flow: 73.4 x 10 lb/hr@ 76.4 ft. head 3.1.6 Sunnort Systems and Interfaces A. Motive Power

1. The recirculation pumps are supplied with Nonclass 1E powet from an AC motor generator set.

B.- MSIV Operating Power l The instrument air system supprts normal operation of the'MSIVs. Valve operation is controlled by an AC and a DC solenoic' pilot valve. Both solenoid valves must be deenergized to cause MSIV closure. This Jeign prevents - spurious closun of an MSIV if a single scienoid valve should idl. MSIVs are designed to fail closed ifinstrument air is lost or if both AC and DC control-power is lost to the so'inoid pilot valves. This is achieved by a local dedicated - air accumulator for each MSIV and an independent valve closing spring. C. Recirculation Pump Cooling The reactor building coo ing water system provides cooling _ water to the-recirculation pump coolers. OO l l 9 12/88 a

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$YSTE M ]S03 A CC SMt OR es l l CE (__ l 903aCC5MtDRe l Hgure 3.1-2. Cooper Nuclear Boiler System Showing Component Locations l J p s V J Table 3.1-1. Cooper Reactor Coolant System Data Summary for Selected Components ' COMPONENT ID . COMP. LOct. TION POWER SOURCE VO LTAG E POWER SOURCE EMERG. TYPE-LOCATION LOAD GRP. RCIC-MOIS. MOV CX MCC-Y 480 903RB AC/G RCIC-MO16 MOV STM 9)N RC'C-RK 125 903RB DC/A RCS-V74 MOV CX MCC-H 480 903RB AC/G RCS-VESSEL RV CX RHR-M17 MOV 903ACCSHLDR HPCI-RK 250 HPCIRM DC/B - t RHR-M18 MOV CX MCC-R 480 903RB ACIF RV-70A - SV CX i RV-708 SV CX 4 RV-70C SV CX RV-71 A SRV CX L RV-718 SRV CX- .g RV-71C SRV CX-RV-71D SRV CX RV-71 E. SRV-CX RV-71 F SRV. CX-RV-71G. SRV CX [ RV-71H SRV CX. RWCU-V15 MOV CX. MCC-R. 480 903RB AC/F RWCU-V18 MOV RWCUHXRM-SIRT-RK 125 958RB DC/B i Po ce + 1 Cooper 3.2 REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.2.1 System Function The reactor core isolation cooling system provides adequate core cooling in the event that reactor isolation is accompanied by loss of feedwater flow. This system provides makeup at reactor operating pressure and does not require RCS depressurization. The RCIC system is not considered to be part of the Emergency Core Cooling System (ECCS, see Section 3.3) and does not have a LOCA mitigating function. 3.2.2 System Definition The reactor core isolation cooling system consists of a steam driven turbine pump and associated valves and piping for delivering makeup water from the condensate storage tank or the suppression poo: to the reactor pressure vessel. The RCIC can also operate in conjunction with the RHR system in the steam condensing mode, in which condensed steam is delivered from the RHR heat exchanger outlets to the RCIC pump suction for return to the RCS. Simplified drawings of the reactor core isolation cooling system are shown in Figures 3.21 and 3.2 2. A summary of data on selected RCIC system components is presented in Table 3.2 1. 3.2.3 System Oneration During normal opera' tion the RCIC is in standby with the steam supply valves to the RCIC turbine driven pump closed 7.ad the pump suction aligned to the condensate storage tank. Upon receipt of a reactor pressure vessel (RPV) low water level signal, the turbine-pump steam supply valves are o?cned and makeup water is supplied to the RPV. / The primary water supply for the RC)C is the condensate storage water tank which contains an 8-hour supply of makeup water, The suppression pool is used as a backup water supply. _ Reactor core heat is dumped to the suppression pool via the safety / relief valves which cycle as needed to limit RCS pressure. The RCIC turbine also exkusts to the suppression pool. The RCIC can also operate in conjunction with the RHR system in the steam condensing mode, iri which condensed steam is delivered from the RHR heat er. changer outlets to the RCIC pump suction, for return to the RCS, In this mode of operation, reactor core heat is transferred to the RHR system rather than to the suppression pool. The RCIC turbine still exhausts to the suppression pool. 3.2.4 System Success Criterin For the RCIC system to be successful there must be at least one water source and supply path to the turbme-driven pump, an opea steam supply path to the turbine, an : open pump discharge path to the RCS, and an open turbine exhaust path to the suppression pool. 3.2.5 Comnonent Information A. Steam turbine-driven RCIC pump:-

1. Rated Flow: 416 gpm @ 2800 ft. head (1,214 psid)-

3

2. Rated Capacity: 100 %

3. Type: centrifugal

)_ B. Condensatt Storage Tanku2)

1. Capacity: 100,00G gal teserved for RCIC and HPCI eperation so 13 12/88 1

1 m 1 Cooper. 1 3.2.6 Sunnort System and Interfaces A. Cuntrol Si tials

1. The Rb!C pump is automatically actuated on a reactor vessel low water level signal and automatically tripped on a reactor vessel high water level signal.

2. Remote Manu" i,

The RCIC pump can be actuated by remote manual means from the - 1 Main Control Room. - B.- Motive Power

1. The RCIC turbine ~ driven pump is supplied with steam from main steam -

loop C, upstream of the main steam isolation valves.

2. The steam supply valves to the turbine pump, RCIC MOIS, and the other MOVs required for RCIC operation are Class IE DC A loadsJ j

supplied by station batteries as described in Section 3.5. - The RCIC : -system is designed to be operable on DC power orJy. C. - Other

1. Lubrication and cooling for the turbine-driven pump is supplied loca;1y.

It should be noted that the pump lube oil cooler is cooled by water-diverted from the RCIC putr,, discharge and retumed to the barometric condenser. Design maximum I'ibe oil cooling water temperature isL 140 F.

2. A room _ ventilation system ccnted by reactor building closed cooling ;

water system (see Section 3.7' provides RCIC room cooling. ~ 3. RCIC pump gland seal leak >ff is collected, condensed and returned to-the pump suction. ;A vacuum pump maintains condenser vacuum. eY_. 14 - -12/88 m_______2.__i-- - - - - - - - - - - - - - - - - - - - - - - - - ~ ^ - - - - ^ ' ' - - - - - - - ' - - - A -1 s 7G L. 'A "'Ts*E" '= 4 roo. S e l ROW TEST LDC acs*Ssu ,.cv .com ,cc o 30f0ENSATE STORAGE. Toum '. TAA*S m AO90C STE AM O F,.. n c CST-? 4 CST-tB - SYSTEM I bd/ acc = 'cc "" acc o,s . acc moi. _ ioev .kia nn ncy acevn. .,o, ,,c . 5 N ,o ION am g 11CV ACc MOst acc o,3, ace.e. W ' .g. m Figure 3.2-1. Cooper Reactor Core isolation Cooling (RCIC) Sysiem I . -.., ~. --.. - -..~., -.-~ m a I f l SIMfUN l g I j l 4m '"isv R -V s i ( FLOW IIS T itP( ' 14CV ACC v31 ACC V10 RCS vtSSTL { CONDENSATE j STORAGE TANM3

TOMAM w anumi AO90C STE AM I

- O- [ 1 i L- .-CST-tB. m g_- CSftA WSE ( 1 RCCM RCC W 1 6 kK 10CV. ~ ~., MO,, \\ t-h ,A l RC'NR' i 13CV ACC V27 _#6 ?. a sscV i + ss CHAMBE R f (StPO a 8 1 ICV RCC UO41 R L% L 1 ? i C..A. o m m ....N.C_., i ..M... ( t i l ~ M m 4 m 2 } Figure 3.2-2. Cooper Reactor Core Isolation Cooling (aCIC) System i Showing Component Locations I a Table 3.2-1. Cooper Reactor Core isolation Cooling System Data Summary j for Selected Components l .) COMPONENT 80 COMP. LOCATION POWER SOURCE VOLTAG E POWER sot >RCE EMERG. TYPE LOCATION LOAD GRP. I CST-1B TANK' CSTAB RCGM0115 - MOV CX MCC-Y 480 903RB AGG RCIC-M0131 - MOV-159NECHNRM RCCRK 125 903RB DOA HCC-M016 MOV SIMTUN RCC RK 125 903HB DOA RCC-MO18 MOV 859NECRNRM RCGRK 125 903HB DOA RCCMO20 MOV-859NECHNRM RCC-RK 125 903RB DOA RCGMO21 MOV SIMIUN RCGRK 125 903RB j DC'A f RCGMO41 MOV 859NECRNRM RGGRK 125 903RB DOA 'l RCO-TURB TDP 859NECHNRM l 1 RCIC-V27 MOV-859NECRNRM RCIC-RK 125 903RB DOA. RCIC-V30 MOV-859NECRNRM RCCRK 125 903RB' DOA i g RCIC-V33 MOV. 859NECRNRM HCIC-RK 125 903RB DOA SUPP PP 859NECRNRM I l .i A . j .. g ) i ( ? .3s oc f I N-, ~. ~ l i Cooper 3.3 EMERGENCY CORE COOLING SYSTEM (ECCS) 3.3.1 System Function The ECCS is an integrated set of subsystems that perform emergency coolant injection and recirculation functions to maintain reactor core coolant inventory and adequate decay heat removal following r. LOCA. For Cooper this system is called the Core Standby Cooling (CSC) system. The ECCS also performs suppiession pool cooling and containment cn"ty functions and has a capability for mitigating transients. 3.3.2 System Definition The emergency coolant injection (ECI) function is performed by the following ECCS subsystems: High pressure Coolant Injection (HPCI) System Autoinatic Depressurization System (ADS) Core Spray System (CSS) Low pressure Coolant injection (LPCI) System The HPCI system is provided to supply make-up water to the reactor pressure vessel (RPV) in the event of a small break LOCA which does not result in a rapid depressurization of the reactor vessel. The HPCI system consists of a steam-turbine driven pump, system piping, valves and controls. The automatic depressurization-system (ADS) provides automatic RPV depressurization for small breaks so that the low pressurr systems (LPCI and CSS) can provide makeup to the RCS. The ADS utilize 6 of the 8 safety / relief valves that discharge n the high pressure steam to the suppression pool. ( ) The core spray system supplies ruke up water tc the reactor vessel at low U pressure. The system consists of two mdependent loon, et a of which has an electric driven pump to supply water from the suppression poo. to c spray sparger in the reactor vessel above the core. The low-pressure coolant injection system is an operating mode' of the RHR system and provides make up water to the reactor vessel at low pressure. The LPCI system consists of two loops designated LPCIA and LPCIB. Each loop consists of two motor driven pumps which supply water for the suppression pool into one of the two rc:irculation loops. Simplified drawings of the HPCI system are shown in Figures 3.31 and 3.3 2. A flow diagram of LPCIA is shown in Figures 3.3 3 and 3.3-4, and LPCIB is shown in 4 Figures 3.3 5 and 3.3 6. The core spray sy tem is shown in Figures 3.3-7 and 3.3-8. Interfaces between these systems-and tne RCS are shown in Section 3.1. A summary of data on selected ECCS components is presented in Table 3.3 1. 3.3.3 System Oneration - All ECCS systems normally are in standby.- The manner in which the ECCS operates to protect the reactor core is a function of the rate at which coolant is being lost from the RCS, The HPCI system is normally aligned to take a suction on the emergency condensate storage tarde (CST). The HPCI system is automatically started in response to decreasing RPV water level, and will serve as the primary source of makeup if RCS pressure remains high. Operation of the HPCI system is not directly dependent on AC - electric pnwer. If the break is of such a size that the coolant loss exceeds the HPCI system capacity or if reactor pressure is too low to operate the steam turbine-driven HPCI pump, then the CSS and LPCI systems can provide higher capacity makeup to the reactor vessel.- - O Autom ttic depressurization is provided to reduce RCS pressure if a break has V occurred m6 RPV water level is not maintained by7he HPCI system. Rapid 18 1248 I a Cooper /N depressurization permits flow frr m the CSS or LPCI systems to enter the vessel. Water (j can be taken from the suppretsion pool by each of these system for injection into the core. 3,3.4 hstem Success Criteria LOCA mitigation requires that both the emergency coolant injection (ECI) and emergency coolant reciculation (ECR) functions be accomplished. The ECl system success enteria for a large LOCA are the following (Ref.1): 1 of 2 core spray loops (CS A or CSB) with a suction on the suppression pool, or 3 of the 4 low 3ressure coolant injection pumps with a suction on the suppression poo.. The ECI system success criteria for a small LOCA are the following (Ref.1): The high-pressure coolant injection (HPCI) pump with a suction on the suppression pool or the condensate storage tank, or The automanc depressurization system (ADS) and 3 of 4 LPCI pumps with a suction on the suppression pool, or The automatic depressurization system and either of the core spray loops (CS A or CSB) with a suction on the suppression pool. The success criterion for the ADS is the use of any 1 of 2 ADS trains. All injection systems essentially are operating in a recirculation mode when drawing water from the suppression pool. A For transients, the success criteria for reactor coolant inventory control involve the following: Either the reactor core isolation cooling (RCIC) system (not part of the ECCS, see Section 3.2), or Small LOCA mitigating systems It is possible that the coolant inventory control function for some small LOCAs can be satisfied by low-capacity high pressure injection systems such as thfcontrol rod drive hydraulic system (see Section 3.6). For the suppression pool cooling function to be successful one of two RHR trains must be aligned for containment heat removal and the associated service water and RHR servis water train must be o exchangers to the ultimate heat sink perating to complete the heat transfer from the RHR 3.3.5 Comnonent Information A. Steam turbine-driven HPCl pump (HPCI TDP)

1. Rated flow: 4250 gpm @ 2580 ft head (1,118 psid)

2. Rated capacity: 100 %

3. Type: centrifugal B. Low-pressure Ccolant Injection Pumps (PE, B, C, and D) (4)

1. Rated flow: 7700 gpm @ 46 ft. head C0 psid)

2. Rated capacity: 331/3%

3. Type: centrifugal

,s [vl 19 12/88 L ~. _ Cooper C. Core spray pumps PMla and PM1B t

1. Rated flow: 4500 gpm @ 260 ft. head (113 psid)

2. Rated capacity: 100 %

3. Type: centrifugal D. Automatic depressurization valves (6)

1. Rated capacity: 20%

2. Rated flow: 3 @ 870,000 lb/hr @ 1090 sig 3 @ 877,000 lb/hr @ 1100 sig E. Pressure Suppression Chamber

1. Design pressure: 56 psig

2. Design temperature: 281 F

. j

3. Operating temperature: 90 F

4. Maximum water volume: 91,100 ft3

5. Minimum watervolume: 87,650 ft3 3.3.6 Sunnort Systems and Interfaces A. Contrc' signals

1. Au! matic a,

'IPCI pump, core spray pumps and the LPCI pumps and all their. i associ. ' s function upon receipt oflow water level in the reactor vessel or hig.. pressure in the drywell.

b. The ADS system is actuated-upon_ coincident signals of the reactor l

. O vessel low water level, drywell high pressure and discharge pressure V indication on any LPCI or CS pump but with a 2 min delay.

2. Remote manual
ECCS pumps and valves and the ADS can be actuated _ by remote manual 4

means from the main control room. B. Motive Power i

1. The ECCS motor-driven pumps and motor operated vahes are Class IE AC nd DC loads that can be supplied from the emergency diesel generator or station battery, as described in Section 3.5.

2. The steam supply valves to the HPCI turbine are Class 1E DC-B loads.

3. The HPCI turbme-driven pump is supplied with steam from main steam loop C, upstream of the main steam isolation valves.

C. Other

1. Lubrication and cooling for the turbine driven pump are supplied lo: ally. It

'l should be noted that the pump lube oil cooler is cooled by water diverted - from the HPCI pump discharge and retumed to the pump suction. Design - maximum cooling water temperature for the HPCI pump is not knowm. For the turbine driven RCIC pump, the limit is 140 F (see Section 3.2)c

2. The LPCI (RHR) pump are cooled by the reactor building cooling water (RBCCW) system (see Section 3.7).

3. Room ventilation systems cooled by reactor building closed cooling water system (see Section 3.7) are provided as follows:

O 20 12/88 [ i- ^ Cooper

4. HPCI pump gland seal leakoffis collected, condensed, and returned to the pomp suction. A vacuum pump maintains condenser vacuum.

3.3,7 Section 3.3 References

1. Cooper FS AR, Section 6.

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FvCHAperga tesi vue tes o.e - n '9' LPsl V268 (PSs V318 ORYVVEtt TO srRAr mAotR 4 g tes, SYSTEM A 9 i su wssamCOou,c ,Q invus t,s,,,s, ge;9; 9; "8 Toaus sneev N ess rsureREss.o STEAM (* 1 CHAMBER I toSI-PMB >G-17CV <r ir trsom (PS8-V130 9 m, Giso n. + s *nw. COOUPCs SUCT m 51b X tPS8V138 L Figure 3.3-5. Cooper Low Pressure Coolant Injection - System B i I J I

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- rn2 mv 71fi 22CV MOg RCIC N l 903ACCSHL DRM {

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1 "2 gge. T j l J SorenESsou,mcom a 3 - a.., i 191 a t _,w,, 'l 9318HXRM l W N-) = jestSWCRNRW) l TORR t h M tesiv,30 0, a,a i + s><noown o com m (Ts SUCTON une MO158 b M C I asoswcnnsu I l Figure 3.3-6. Cooper Low Pressure Coolant !njection - System B Showing Component Locations i i

l j 4 I r g9 O. CONDENSATE M1B CS-MO128 ' + 14B RCS SUPPLY 11CV CS-FMIB A0138 VESSE9 Ld v F' ( 10CV CS-M011A CS M012A + 14A L J ^ l CS-PM1A l wa m F' ' SUPPRESSION ' CS-M y CHAMBER 3 00 suPPnESSO4 ' kJ m TO own) V' ' SUPPRESSsON i CS V26A / CHAMBER X j CS-MO7A i cs uOrs ~ i 1 f -w s m = i !~ Fgure 33-7. Cooper Core Spray System (CSS) l i i i i ~. c,...-..- . ---.. ~ -...,. r,,-~ , -.. -.,. -. - -,.,,,..,. -. ~ - - - -. - -, _..-. _.

-.... -. -. -... -..- _ _ _.... ~.. ~... - ~.... _.. ~. _.... _. l 931 Rl; l l 903RB CX l l I +b EJ [ i ( I CONDENSATE y 8 F' SUPPLY 11CV l CS MO118 CS-M0128 148 ncS l CS PM1B A0138 VESSEL ^ ( =2 j .F' ~ 0CV-CS-M011A CS-M012A '+ 14A .L 1 l AO13A CS-PM1 A '. j1 i ~' PPRESSION f . CS-V268 CHAMBER g l 'O I SUPPfESSION l 'LJ c TO i cnAusta F ' ' SUPPRESSION j .: CS-V26A : CHAMBER i I i '. CS-MO7A : l l 859NECRNRM l - f !Xj ' CS-MO78 - i 'l SECHNRM l l TORR l-U s cc Figure 3.3-8. Cooper Core Spray System (CSS) Showing Component Locations i i a

JL i g / ) ( C/ G) V Table 3.3-1. Cooper Emergency Core Cooling System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. CS-M3118 MOV 931RB MCC-Y 480 903HB . AC/G CS-M0128 MOV 931RB MCC-Y 480 903RD AC/E CS-M07A MOV 859NECRNRM MCCO 480 903RB AC/F CS-M078 MOV SECHNRM MCC-Y 480 903HB AC/G CS-M011 A MOV 931RB MCCO 480 903RB AC/F CS-M012A MOV 931 RB MCCO 480 903RB AC/F CS-FM1A MDP 859NECRNRM BUS-1 F 4160 81F ACIF CS-FM1 B MDP SECHNRM BUS-1G 4160 81G AC/G CS-V26A MOV 859NECHNRM MCCO 480 903RB AC/F CS-V268 MOV SECHNRM MCC-Y 480 903RB AC/G CST-1A TANK CSTAB w CST-1B TANK CSTAB HPCI-MO14 MOV HPCIRM HPCI-RK 250 HPCIRM DC/B HPCI-M015 MOV CX MCC-R 480 903RB AC/F HPCI-M015 MOV CX MCC-R 480 903RB AC/F HPCI-M016 MOV 903ACCSHLDR HPCI-RK 125 HPCIRM DC/B HPCI-MO16 MOV 903ACCSHLDR HPCI-RK 125 HPCIRM DC/D ^ HPCI-M017 MOV HPCIRM HPCI-RK 125 HPC1FDA DC/B HPCI-M019 MOV STMTUN HPCI-RK 250 HPCIRM DC/B HPCI-MO20 MOV HPCIRM HPCI-RK 250 HPCIRM DC/B HPCI-MO58 MOV HPCIRM HPCI-RK 125 HPCIRM DC/B HPCI-TURB TDP HPCIRM HPCI-V21 MOV HPCIRM HPCI-RK 250 HPCIRM DC/B HPCI-V24 MOV HPCIRM - HPCI-RK 250 HPCIRM DC/B g g HPCI-V25 MOV HPCIRM HPCI-RK 250 HPCIRM DC/B LPSI-MO27A MOV 903ACCSHLDR MCC-R 480 903RB ACIF LPSI-MO278 MOV 903ACCSHLDR MCC-RB 480 903RB AC/G

Table 3.3-1. Cooper Emergency Core Cooling System Data Summary I for Selected Components (Continued) s k COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. CS-M0118 MOV 931RB MCC-Y 480 903RB AC/G CS-M0128 MOV 931RB MCC-Y 480 903RB AC/E CS-M07A MOV 859NECHNRM MCC-O 480 903RB AC/F CS-M078 MOV SECHNRM MCC-Y 480 903RB AC/G CS-MO11 A MOV 931RB MCCO 480 903RB AC/F CS-MO12A MOV 931RB MCC-O 480 903RB ' AC/F CS-FM1A MDP 859NECHNRM BUS-1F 4160 B1F AC/F CS-PM1B MDP SECRNRM BUS-1G 4160 81G AC/G CS-V26A MOV 859NECHNRM MCCO 480 903RB AC/F CS-V268 MOV SECRNRM MCC-Y 480 903RB . AC/G CST-1A TANK-CSTAB w CST-1B TANK CSTAB HPCI-MO14 MOV HPCIRM HPCI-RK 250 HPCIRM DC/B HPCI-M015 MOV CX MCC-R 480 903RB AC/F HPCI-MOIS MOV CX MCC R 480 903RB AC/F HPCI-MOl6 MOV 903ACCSHLDR HPCI-RK 125 HPCIRM DC/B HPCI-M016 MOV 903ACCSHLDR HPCI-RK 125 HPCIRM DC/B HPCI-MO17 MOV HPCIRM HPCI-RK 125 HPCIRM DC/B HPCI-M019 MOV STMTUN HPCI-RK 250 HPCIRM DC/B HPCI-MO20 MOV HPCIRM HPCI-RK 250 HPC1RM DC/B HPCI-MO58 - MOV HPCIFW HPCI-RK 125 HPCIRM DC/B HPCI-TURB TDP HPCIRM HPCI-V21 MOV HPCIRM HPCI-RK 250 HPCIRM DC/B HPCI-V24 MOV HPCIRM HPCI-RK 250 HPCIFW DC/B 1:' gg HPCI-V25 MOV HPCIRM HPCI-RK 250 HPCIRM DC/B LPSI-MO27A MOV 903ACCSHLDR MCC-R 480 903RB AC/F LPSI-MO27B MOV 903ACCSHLDR MCC-RB 480 903RB AC/G 1 ,,.....,...,,.4 ,o<,.., .r -..,e ,m. .m, u-st . -....w. ,.i-,.,,-r -..,..rm m

1 O O Table 3.3-1. Cooper Emergency Core Cooling System Data Summary for Selected Components (Continued) J-COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. 't LPSI-PMA MDP 859NWCRNRM BUS-1F 4160 B1F AC/F i LPSI-PMB MDP 859SVJCHNRM BUS-1 F 4160 B1F AC/F LPSI-PMC MDP 859NWCRNRM BUS-1G 4160 B1G AC/G LPSI-PMD MDP 859SWCHNRM BUS-1G 4160 B1G AQG LPSI-V12A MOV: 903AHXRM MCCO 480 903RB AC/F LPSI-V128 MOV. 903BHXRM MCC-Y 480 903RB AC/G i LPSI-V13A MOV E59NWCRNRM MCCO 480 903RB AC/F LPSI-V138 MOV 859SWCRNRM MCC-Y 480 903RB AGG LPSI-V13C MOV 859NWCHNRM MCC-O 480 903RB AC/F 1 1 LPSI-V13D MOV 859SWCRNRM MCC-Y 480 903RB AC/G ? LPSI-V25A MOV 903ACCSHLDR RHRA-RK 250 903RB DQA i g LPSI-V25A MOV 903ACCSHLDR - RHRB-RK 250 903RB DC/B LPSI-V26A MOV. 903AHXRM MCC-O 480 903RB AC/F j LPSI-V26B MOV 903BHXRM - MCC-Y 480 903RB AC/G LPSI-V31 A MOV 931 RB MCCO 480 903RB ~ AC/F l LPSI-V318 MOV.. 903RB MCC-Y 480 903RB AQG l LPSI-V34A MOV-881NWCRNRM MCCO-480 903RB AC/F i LPSI-V34B MOV 881SWCRNRM MCC-Y 480 903RB AC/G LPSI-V39A - MOV-881NWCRNRM MCCO 480 903RB > AC/F i LPSI-V39B - MOV 881SWCRNRM MCC-Y 480 903RB AC/G LPSI-VSSA MOV 931AHXRM MCCO 480 903RB AC/F LPSI-V658 - MOV 931BHXRM MCC-Y 480 903RB AQG LPSI-V66A - MOV 903AHXRM MCC-O 480 903RB AC/F f .h LPSI-V668 MOV 903BHXRM - MCC-Y 480 903RB AQG 4 co t

Caper 3.4 INSTRUh1ENTATION AND CONTROL (I&C) SYSTEhtS 3.4.1 System Function The instrumentation and control systems consist of the Reactor Protection System (RPS) and systems for the display of plant information to the operators. The RPS monitors the reactor plant, and alerts the operator to take corrective action before specified limits are exceeded. The RPS will initiate an automatic reactor trip (scram) to rapidly shutdown the reactor when plant conditions exceed one or more specified limits. It will also automatically cause actuation of selected safety systems based on the specific limits or combinations oflimits that are exceeded. 3.4.2 System Definition The RPS includes sensor and transmitter units, logic units, and output trip relays that interface with the control circuits for components in the Control Rod Drive Hydraulic System (see Section 3.6) Under certain circumstances components in other safety s: stems will also be actuated. Operator instrumentation display systems consist of display panels that are powered by 120 VAC power (see Section 3.5), 3.4,3 System Ooeration A. RPS The RPS has four in put instrument channels and two output actuation trains, RPS inputs are listed & low: Neutron monitoring system Reactor pressure Low water levelin reactor vessel Turbine stop valve closure Turbine control valve fast closure 5 hiain steam line isolation signal Scram discharge header high water level Drywell high, pressure I hiain steam ime radiation hianual Both output channels must be de-energized to initiate a scram. The failure of a - single component or power supply does not prevent a desired scram or cause an unwanted scram. B. Other Safety Systems l Other actuation systems include the following: Primary containment and reactor vessel isolation system - Core standby cooling system control and instrumentation system C. Remote Shutdown-No information was found in the FSAR rea,arding a remote shutdown capability. Such a capability is expected to exist. 3.4.4 System Success Criteria A, RPS p The RPS uses hindrance logic (normal = 1, trip = 0) in both the input and' output logic. Therefore, a channel will be in a trip state when input signals are lost, when control power is lost, or when the channel is temporarily removed '33 12/88

Cooper from service for testing or maintenance (i.e. the channel has a fail safe failure (n\\ mode). A reactor scram will occur upon loss of control power to the RPS A V reactor scram is implemented by the scram pilot valves in the control rod drive l hydraulic system (see Section 3.6). Details of the RPS for Cooper have not been determined. B. Other Actuation Systems A single component usually receives a signal from only one actuation system outaut train. Trains A and B must be available in order to automatically actuate the r respective camponents. Actuation systems other than the RPS 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 removed from serv'ce foi testing or maintenance (i.e. the channel has a fail safe failure mode). Control power is needed for the actuation system output channels to send an actuation signal. Note that there may be some 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 other actuation systems for Cooper have not been dctermined. C. Manually-Initiated Protective Actions When reasonable time is available, certain protective actions may be perfonned manually by plant personnel. The control room operators are capable of operating individual components using normal control circuitry, or operating groups of components by manually tripping the RPS or an ESFAS subsystem. O The control room operators also may send qualified persons into the plant to Q 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. 3.4.5 Suncort Systeme and Interfaces A. Control Power

1. RPS The RPS is powered from two 120 VAC buses (see Section 3.5).

2. Other Actuation Systems Control power sources for the actuation logic of various safety systems are summarized in Table 3.4 1,

3. OperatorInstrumentation Operator instrumentation displays are powered from instrumentation power sources as described in Section 3.5.

l l ~ v) i 34 12/88

O Table 3.4-1. Matrix of Cooper Control Power Sources 125 VDC SYSTEM Division ( A l B i% ADS A ~.31 +p - ADSB ven. RHR(LPCI) A uggVy41$) RHR (LPCI) B l WMli)k CS A g $fd cS B DIESEL 1A& AUXILIARIES TESEL 1B & AUXILIARIES % ^tg SWA P SWB ..g( O L 35 12/88

Cooper (~~'N 3.5 ELECTRIC POWER SYSTEM 3.5.1 System Function The electric power system supplies power to various equipment and systems needed for normal operation and/or response to accidents. The onsite Class IE electric power system supports the operation of safety class systems and instrumentation needed to establish and maintain a safe shutdown plant condition following an accident, when the nomial electric power sources are not available. 3.5.2 System Definition The onsite Class 1E electric power system consists of two diesel generators and 4160 VAC buses. The Class 1E electric power system consists of two 4160 VAC trains, two 480 VAC trains, a 125/250 VDC subsystem, and a 120 VAC subsystem. Two sets of station batteries supply power to the 125/250 VDC system for normal switchgear control, turbine control, annunciators, and various emergency functions. These batteries have adequate capacity for eight hours of operation without recharging (Ref.1). The 120 VAC system supplies power to the reactor instrumentation and protection circuits. Simplified one line diagrams of the electric power system are shown in Figures 3.51 and 3.5-2. A summary of data on selected electric power system components is presented in Table 3.51. A partial listing of electrical sources and loads is presented in Table 3.5-2. 3.5.3 Sntem Ooeration The normal power system supplies AC power to all station auxiliaries and is the normal source of power when the main generator is operating. The start up station offsite AC power source provides power when the main generator is off line. s [V T Upon loss of both normal and start up (offsite) power, each emergency diesel generator is automatically started and is aligned to supply power to the respective AC power load groups. The 480 VAC buses IF and IG constitute the two separate 480 VAC trains distributing power to the rest of the 480 VAC motor control centers electrical system. The normal source of power for the 125/250 VDC system are the battery chargers. The station batteries l A and 1B float on their respective buses. These DC buses supply 125/250 VDC to the essential cabinets l A and IB which supply Division I engineered safeguard system (ESS) and Division II ESS loads. 120/240 VAC instrument power is supplied from the 480V buses (lF and IG) as are the RPS motor-generator (MG) sets. Redundant safeguards equipment such as motor driven pumps and motor operated valves are supplied by different 4160 VAC buses. For the purpose of discussion, this equipment has been grouped into " load groups". Load group IF contains components receiving electric power from Bus IF. Load group IG contains components powered by bus 1G. Load groups DCA and DCB contains components receiving DC power from DC bus l A and IB respectively. 3.5.4 System Success Criteria Basic system success criteria for mitigating transients and loss-of coolant accidents are defined by front line systems, which then create demands on support systems. Electric power system success criteria are defmed as follows, without taking credit for cross ties that may exist between independent load groups: / 'i V 36 1248 1 I

Cooper ( Each Class IE DC load gro p is supplied initially from its respective battery (also needed for diesel starting) Each Class IE AC load group is isolated from the non Class lE system and is supplied frem its respective emergency power source (i.e. diesel generator) Power distribution paths to essential loads are intact Power to the battery chargers is restored before the batteries are exhausted. 3.5.5 Comnonent Information A. Standby diesel generators l A,1B

1. Power rating: 4000 kW continuous

2. Rated voltage: 4160 VAC

3. Manufacturer: Cooper Bessemer 4 Day tank capacity: 2500 gals (8 hours operation @ full load).

B. Station batteries

1. Type: Lead acid

2. Rated voltage: 125/250

3. Cells: 60

4. Design Capacity: 8 hours with design load.

3.5.6 Sunnort Systems and Interfaces A. Control Signals O

1. Automatic V

The standby diesel generator is automatically started based on loss of start-up power, low reactor water level, or high drywell pressure. l

2. Remote manual The diesel generators can be started, and many distribution circuit breakers can be operated from the main control room.

B. Diesel Generator Auxiliary Systems

1. ' Cooling The service water system (see Section 3.8) provides diesel cooling.

2. Fueling An independent day tank is provided for each diesel. A day tank will support eight hours of diesel operation with design loads.

3. Lubrication Each diesel generator has a self contained lubrication system.

l

4. Starting An independent starting air accumulator is provided for each diesel generator

5. Ventilation

- Deta!!s on diesel room ventilation are not known. 1 C. Swit::hgear and Battery Room Ventilation System. Details on switchgear and battery room ventilation are not known. 3.5.7 SMon 3.5 References O . (

l. Cooper FSAR, Section 8.6.4.

37 12/88 l t, .v

N A s 'J i DG1P DG1B rnou Fncu 4160 DOS 1A FROu STATION EME AGENCY 4*60 SUS 18 7 'P TTIANSIOPME R 'F 1r -l 4160 DOS F l l 4160 BUS 1G l lI II STATION STATION

^ ".:^,"
SERVICE g SERVICE

= - -- TRIF TR1G l 480 SWGR DUS 1F l l 480 SWGR BUS 1G l II II II II II II I ucc u II acca l I acct i I uccx - 1 I acc-s I l uccTx I II II Il II II II II },", [ t - 4a0vn2cv 4eovnrov i l ucco - l l ucca l l uccY l l ucc4e l l 12cv stST PANEL 1 A l. l 12DV WST PANEL 18 l -Q Figure 3.5-1. Cooper 4160,480, and 120 VAC Electric Power Distribution System E i s 1

\\ s j FROM 480 VAC McCtX FROM 4e0 VAC REC 4.X FROM 4eCVAC MCCTX FROM WO VAC Mr4 TX 1r 1r <r 1r ll' ll Il ll g SATTERY g SATTTRY SATTERY g BATTEMY g C"*"*" C""*" C"""#" rscv mv mv nov 8AT-1 A SAT-1A BAT tB SAY 18 E E E C ll -ll Il El ll ll ll ll l 790WDC BUS 1A l l 125V DC SUS 1A l l 1MW DC BUS 18 l l Mov DC EkA5 98 l ll ll-ll El Illl ll ll ll FROM FR0ha F10s FROM OUS 18 SUS 18 BUS 1A BUS tA N urs N urs L.I L.I J J urs urs \\ l ta l l I aocs=Taaac=mo l I DCD5f PA6 A MS l l W SNE ara mS l l DC DST NL 8 pv g l l RC.C sTAmR Ra pv,1 l m sTA m RRACx l l m sTA=R ao l 1 - sTAmR m. l l % sT R RAc. co. l i l Figure 3.5-2. Cooper 250 and 125 VDC Electric Power Distribution System _y 00 00

m s Table 3.5-1. Cooper Electric Power System Data Summary for Selected Components l 4 COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. BAT-1A BATT BTRMA 125 DC/A BAT-1 B BATT BTRMB 125 DC/B BC-1A BC DCSGRMA MCC-LX 480 ARLY AC/F BC-1B BC' DCSGRMB MCC-TX 480 ARLY AC/G BUS-1A BUS DCSGRMA BT-1 A 125 BIRMA DC/A BUS-1A BUS-DCSGRMA BC-1 A 125/250 DCSGRMA DC/A BUS-18 BUS DCSGHMB B I-1 8 125 BTRMB DC/B BUS-1B BUS-DCSGRMB BC-18 125/250 DCSGRMB DC/B BUS-10. BUS B1F DG-1A 4160 DG1A AC/F BUS-1G BUS B1G DG-1B 4160 DG1B AC/G ,l CB-1F CL' B1F DG-1 A 4160 DG1A AC/F g CB-1G CB B1G DG-1B 4160 DG1B AC/G DC-PNL-A PNL DCSGRMA BUS-1A 125 DCSGRMA DC/A i DC-PNL-B - PNL DCSGRMB BUS-1B 125 DCSGRMB DC/B DG-1 A - DG DG1A 4160' DG1A AC/F DG-1B DG DG1B 4160 DG1B AC/G HPCI-RK MCC HPCIRM BUS-1B 125 DCSGRMB DC/B HPCI-RK MCC HPCIRM BUS-1B 250 DCSG.WB DC/B IDBUS-1F BUS B1F T R-1F 480 81F AC/F IDBUS-1G BUS B1G TR-1G 480 B1G - AC/G INSPNL-1 A PNL

CSR.

ITR480/120 120 DCSGRMA AC/F INSPNL-1B PNL CSR ITR480/120 120 DCSGRMB AC/G ITR480/120 XFMR DCSGRMA MCC-LX 480 ARLY AC/F 4 IIR480/120 XFMR DCSGRMB MCC-TX 480 ARLY AC/G 4 ~ 1:3g MCC-K MCC 903RB IDBUS-1F 480 B1F ACIF MCC-L MCC. 882CB IDBUS-1F 480 B1F AC/F i MCC-u MCC ARLY IDBUS-1F 480 j B1F AC/F l

Table 3.5-1. Cooper Electric Power System Data Summary for Selected Components (Continued) COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. MCCrM MCC 958RB IDBUS-1F 480 81F AC/F MCCO MCC 903RB MCC-K 480 903RB AC/F MCC-H MCC 903RB MCC-K 480 903RB AC/F MCC-RB MCC 903RB MCC-S 480 903RB AC/G MCC-S MCC 903RB IDBUS-1G 480 81G AC/G l MCC-TX MCC ARLY IDBUS-1G 480 B1G AC/G MCC-Y MCC 903RB MCC-S 480 903RB AC/G RCIC-RK MCC 859NECHNRM BUS-1A 250 DCSGRMA DC/A l HCIC-RK MCC 903HB BUS-1A 125 DCSGRMA DC/A i HHRA-RK MCC 903RB BUS-1A 250 DCSGRMA DC/A RHRB-RK MCC 903RB BUS-18 250 DCSGRMB DC/B 3 STRT-RK MCC 958HB BUS-1B 125 DCSGRMB DC/B TR-1F XFMR B1F BUS-1F 4160 B1F AC/F TR-1G XFMR B1G BUS-1G 4160 B1G AC/G i A i

TABLE 3.5 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT COOPER \\ POWER VOLTAGE EMERG POWE R SOURCE LOAD LOAD COMP COMPONENT SOUACE LOAD GAP LOCATON SYSTE M COMPONENTID TYPE LOCATION BC1A 125/250 DC/A DCSGRMA EP BUS 1A BUS DCSGRMA BC 1B 125'250 DC/B DCSGRMB EP BUS 18 Bus DCSGRMB Bi 1 A 125 DC/A BTF4MA EP BUS 1A BUS DCSGRMA BT 1B 125 DC< B BIRMB EP BUS 1B BUS DCSGRMB BUS 1A 125 DC/A OCSORMA EP DC-PNL A PNL DCSGRMA bus 1A 250 DC, A DCSGRMA EP RCIC-RK MCC 859NECRNRM BUS 1 A 125 DC/A DCSGRMA EP RCIC-RK MCC 903RB BUS 1 A 250 DC/A DCSGRMA EP RHFWRK EC 903RB Bus 1B 125' DC< B DCSGRMB EP DC PNL B PNL DCSGRMB BUS 18 125 DC/B DCSGRMB EP HPCIRK WC HPCIRM BUS 18 250 DC/B DCSGRMB EP HPCIRK MCC HPCIRM bus-18 250 DC/B DCSGRMB EP RMRB-RK MCC 903RB BUS-18 125 DC/B DCSGRMB EP STRT RK MCC 958RB BUS-I F 4160 ACiF B1F ECCS CS PM1 A MOP 859NECRNRM BUS 1F 4160 AC/F B1F ECCS LPSi PMA MOP 839NWCRNRM I B US-1 F 4160 ACrF B1F ECCS LPSI PMB MOP 659SWCRNRM B US-1 F 4160 AC/F B1F EP TR1F XFMR 81F B U S-1 F 4160 AC,F B1F SW SW PMA MOP ISPUMPRM B U S-1 F 4160 AC/F BIF SW SW PMC MOP ISPUMPRM BVS-1G 4160 AC/G B1G ECCS CS-FM1 B MOP SECRNRM BUS-1G 4160 AC/G BIG ECCS LPSidMC MOP 959NWCRNRM BUS 1G 4160 AC/G BIG ECCS LPSiPMD MD5' 859SWCRNRM BU S-1G 4160 AC/G B1G EP TR-lG XFMP B1G BUS-1 G 4160 AC/G BIG SW SW PMB MOP iSPUMPRM bus-1G 4160 AC/G BIG SW SWPMO MOP iSPUMPRM DG-1A 4160 AC/F DGIA EP BUS-1F BUS B1F DG-1A 4160 AC/F DG1A EP CB1F CB B1F DG-18 4160 AC/G DGIB EP BUS-10 BUS BIG DG-1 B 4160 AC/G DG1B EP CB-1G CB BIG @Cl RK 250 DC/B HPCIRM ECCS HPCHiO14 MOV HPCARM g 'Cl RK 125 DC/B HPCIRM ECCS HPCI-MOl6 MOV 903ACCSNLDR v) z 42 12/88

TABLE 3.5 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT COOPER (CONTINUED) C POWER VOLT AGE. EMERG POWER SOURCE LOAD LOAD COMP COMPONENT SOUACE LOAD GAP LOCATION SYSTEM COMDONENT fD TYPE LOCATION - HPCbRK 125 DC/B HPCIRM ECCS HPCbMOl6 MOV 903ACCSHLDR M HPCFRN 125 DC/B HPC6RM ECCS HPCl4017 MOV HPC1RM HPCi-RK 250 DC/B HPCiRM ECCS HPC641019 MOV STMTUN HPCFRK 250 DC/B HPCIRM ECCS HPCl4020 MOV HPCIRM HPCbRK 125 DC/B. HPCIRM ECCS HPC64 0$8 MOV HPCIRM , I 'B HPCIRM ECCS HPCIV21 MOV HPCtRM HPCbRK 250 HPCbRK 250 '3 HPCiRM ECCS HPCIv24 MOV HPCIR68 i HPCbRK 250 DC/B HPCIRM ECCS HPCIV25 MOV hM.ilRM HPCI-RK 250 DC< B HPCIRM RCS RHR.M I T MOV 903ACCSHLCR M IDBus-1F 480 ACiF B1F EP MCC-K MCC 903RB (D BUS-1 F 480 AC,F B1F EP MCC-L MCC 882CB ID BUS-I F 480 AC/F B1F EP MCC LX MCC ARLY IDBus tF 480 ACtF B1F EP MCGM MCC 058AB IDBUS-1G 480 AC/G BIG EP MCCS MCC 903RB O IDBUS-1G 480 AC/G BIG EP MCC TX MCC ARLY INSPNL 1 A 120 AC/F CSR 18 0 PNL CR INSPNL 18 120 AC/G CSR IAC PNL CR 17R480/120 120 AC/F DCSGRA% EP INSPNL1A PNL CSR IT R480/120 120 AC/G DCSGRMB EP INSPNL1B . PNL CSR MCC-K 480 AC/F 903RB EP MCC-Q MCC 903RB MCC-K 480 AC/F 903PB EP MCC-R MCC 903RB MCC-LX 480 AC/F ARLY EP BC-1 A BC DCSGRN% - MCC LX 480 AC/F ARLY EP iTR480/120 XFMR DCSGAN% MCCC 480 AC/F 903RB ECCS CS4107A MOV 859NECRNRM MCC4 480 AC/F 903RB ECCS CS-M011 A MOV 931RB MCC-O 480 AC/F 903AB ECCS CS M012A MOV 931RB MCC O 480 AC/F 903RB ECCS CS V26A MOV 859NECRNRM MCC4 480 AC/F 903RB ECCS LPSI V12A-MOV 903AHXRM MCCO 480 AC/F 903AB ECCS LPSI Vl3A MOV. 85bNWCANRM MCC-O 480 AC/F 903RB ECCS LPSbV130 MOV 859NWCRNRM l [ MCC4 480 AC/F 903RB. ECCS. LPSIV26A-MOV 903AHXRM i U -43 12/88

TABLE 3.5 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT COOPER (CONTINUED) (nI (] POWER VOLTAGE EMERG POWER SOURCE LOAD LOAD l COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT IDI TYPE LOCAT'ON MCC4 480 AC/F 903RB ECCS LPShv31A MOV 931RB MCCO 480 ACsf 903RB ECCS LPSIV34A MOV 881NWCRNRM MCC4 480 AC/F 903RB ECCS LPSt V39A MOV 881NWCRN AM MCC4 480 AC/F 903RB ECCS LPSbV65A MOV 931 AHARM MCC4 480 AC/F 903RB ECCS LPSbV66A MOV 903AHARM MCC R 480 AC/F 903RB ECCS HPC64015 MOV CX ~!C R 460 ACiF 903RB ECCS HPCI MOIS MOV CX M MCGR 480 AC F 903RB ECCS LPSI MO27A MOV 903ACCSHLDR M MCC-R 480 AGO 903RB RCS RCS V74 MOV CX MCC-R 480 AC/F 903RB RCS RHR MIB MOV CX MCC-R 480 AC/F 903RB RCS RWCU V15 MOV CX MCC-RB 480 ACvG 903RB ECCS LPSbMC27B MOV 903ACCSHLDR M MCC-S 4e0 AC/G 903RB EP MCGRB MCC 903RB MC4$ 480 AC/G 903RB EP MCGY MCC 903RB [ MCC-TX 480 AC,G ARLY EP BC 1B BC DCCGRMB b MCCTX 480 AC/G ARLY EP ITR480/120 XFMR DCSGAMB 1 I MCGY 480 AC/G 903RB ECCS CS-M0118 MOV 931 HB MCGY 480 AC/E 903RB ECCS CS-M0128 MOV 931RB MCGY 480 AC/G 903RD ECCS CS-M07B MOV SECRNRM l ACC-Y 480 AC/G 903RB ECCS CS V26B MOV SECRNRM-MCC-Y 480 AC/G 903RB ECCS LPSIV128 MOV 903BHxRM MCCY 480 AC/G 903RB ECCS LPSbV13B MOV 859SWCRNRM 1 MCCY 480 AC/G 903R8 ECCS LPSbV13D MOV 859SWC AN RM MCC Y 480 AC/G 903RB ECCS LPSbv268 MOV 903BHxRM fEGY 480 ACiG 903AB ECCS LPSI V31B ' Mov 903RB MCC Y 480 AC/G 903AB ECCS LPSIV348 MOV 881SVvCRNRM MCC Y 480 AC/G 903RB ECCS LPSIV398 MOV 881SWCRNRM MCC-Y 480 AC/G 903RB ECCS LPSt-V658 MOV 931BHxRM MCC Y 480 AC/G 903RB ECCS LPSbV66B MOV 903BHxRM MCC Y 480 AC/G 903R8 RCIC RCIC-M0115 MOV CX [ MCC-Y 480 AC/G 903RB RCS RCIC M015 MOV CX V 44 12/88

TABLE 3.5 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT COOPER (CONTINUED) (" i POWER VOLTAGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT SOUACE LOAD GRP LOCATION SVSTEM COMPONENT 10 TYPE L OCATION RCiGRK 125 DCiA 903RB RCIC RCIC M0131 MOV 859NECRNRM RCiC-RK 125 DCsA 903RD RCIC RCic-M016 MOV STMTUN NiC RN 125 DGA 903i4B NiC RCiG M018 MOV 859NECRNRM RC44R6 125 DC/A 903RB NIC RCIC4 040 MOV 859NECRNRM NIGRN 125 DGA 903RB NiG RCIC4021 MOV STMTUN RC4GRA 125 DC,A 903RB RCiG RCIC MO41 MOV 859NECRNRM RCIGRN 125 DC/A 903RB mig RCIGV27 MOV 859NEC8 NRM RCiG RN 125 DC/A 903RB RCIC RCIGV30 MOV 859NECRNRM RGiG-RK 125 DCsA 903RB RCIC RC14V33 MOV 859NECRNRM RCIC-RK 125 DC/A 903RB RCS RCiG M016 MOV STMTUN l RM%RN 250 DC/A 903RB ECCS LPSIV25A MOV 903ACCSHLOR RmRB-RK 250 DGB 903RB ECCS LPSIV25A 8.VV 903AC4o. :' OR M STRT RK 125 DC/B 958AB RCS RWCU.V18 MOV RWCUHARM TR1F 480 AC/F B1F EP IDBUS1F BUS 81F [ \\ TR1G 480 AC/G BIG EP IDBUS-1G BUS B1G V i OV 45 12/88

Cooper 3.6 CONTROL ROD DRIVE HYDRAULIC WSTEM (CRDHS) I 3.6.1 System Function The CRDHS supplies pressurized water to operate and cool the control rod drive mechanisms during normal operation. This system implements a scram command from the reactor protection system (RPS) and drives control rods rapidly into the reactor. The CRDHS also can provide makeup water to the RCS. 3.6.2 System DefinDB The CRDHS vonsists of two high head, low-flow, pumps, piping, filters, control valves, one hydraulic control unit for each control rod dnve mechanism, and instrumentation. Water is supplied from condensate and from the condensate storage tank. The CRDHS also includes scram va'ves, scram accumulators, and a scram discharge volume (dump tank). Details of the scram porti~.en of typical BWR CRDHS is shown in Figure 3.61 (adapted from Ref 1). 3,6,3 System Oneration During normal operatioa the CRDHS pumps provide a constant flow for drive mechanism cooling and system pressure stabilization, Excess water not used for cooling is - discharged to the RCS. Control rods are driven in or out by the coordinated operation of the direction control valves. Insertion speed is controlled by flow through the insert speed control valve, Rod motion may be either stepped or continuous. A reactor scram is implemented by pneumatic scram valves in the CRDHS. An inlet scram valve opens to align the insert side of each control rod drive mechanism (CRDM) to the scram accumulator. An outlet scram valve opens to vent the o?posite side of each CRDM to the dtmp tank. This coordinated action results in rapid unsertion of control rods into the reactor. 1 A!: hough not intended as a makeup system, the CRDHS can provide a source of cooling water to the RCS during vessel isolanon, It is noted in NUREG 0626 (Ref,2), that this function is particularly important for some BWR;" and B NR/2 plants for which the CRDHS is the pnmary source of makeup on vessel i.'olation. In later model BWR alants, RCS makeup at high pressure is performed by the RCIC (see Section 3.2) and FIPCI (see Section 3.3) systems. The maximum RCS makeup rate of the CRDHS is about 200 gpm with both pumps operating (Ref. 3). l 3.6,4 System Success Criterin i For the scram function to be accomplished, the following actions must occur in the CRDHS: A scram signal must be transmitted by the RPS to the actuated devices (i~e., pilot valves)in the CRDHS. The pneumatic inlet scram valve and outlet scram valve must open in the i. hydraulic control units (HCUs) for the individual control rod drives. This is accomplished by venting the instrument air supply to each valve as follows: l Both scram pilot valves in each HCU must be deenergized, or Either backup scram pilot valve must be energized. A high pressure water source must be available from the scram accumulator in each HCU. A hydraulic vent path to the scram discharge volume must be available and sufficient collection volume must exist in the scram discharge volume. A specified number of control rods must responds and insert into the reactor - O core (specific number needed is not known). V 46 12k8

Cooper 3.6,5 Comnongnt Information A. Control rod drive pumps (2)

1. Rated capacity: 1007c (for control rod drive function)

2. Flow rate: about 120 gpm @ 1500 psig

3. Type: centrifugal B. Condensate Storage Tank

1. Capa:;ity: 500,000 gal 3.6.6 Sunnort Systems and Interfaces A. Control Signals

1. Automatic The RPS transmits scram commands to solenoid pilot valves which control the pneumatic scram valves

2. Remote Manual

a. A reactor scram can be initiated manually from the control room

b. The CRDHS can be operated manually from the control room to insert and withdraw rods, or to inject water into the RCS -

I B. Motive Power

1. The control rod drive pumps are Class 1E AC loads that can be supplied from the emergency diesel generator as described in Section 3.5.

3,6,7 Section 3.6 References Q

1. NEDO 24708A, " Additional Information Required for NRC Staff Generic Report on Boiling Water Reactors," General Electric Company, December 1980.

2. NUREG-0626, " Generic Evaluation of Feedwater Transients and Small Break Loss of-Coolant Accidents in GE designed Operating Plants and Near term -

Operating License Applications," USNRC, January 1980. I

3. Harrington, R.M., and Ott, L.J., "The Effect of Small-Capacity, High Pressure Injection Systems on TQUV Sequences at Browns Ferry Unit One,"

NUREG/CR-31' 9, Oak Ridge National Laboratory, September 1983, l U 47 1248-

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IN Y

w Sf Ca ,C iC O E C V yF rF r L C e c ) A C V g U 3 hS t , L T S 0 s A Tf n i D f yE g R e V ,C C Y t N X rF rF H O h A ) v T ( TC l E o sn P 8 oT 9, iO rF i - T d t E E V r e 'A ot L V Pa l f e T OR N S R r E$ E t r G C Dt mre RS R H OC Er AR R OH DC H t arA E OH CT T SA I gt + DW r r aa 3 R R ih D T I R E E E T T A A T T AE E W W W d M N A RV V G G e E N CL I N 1 f i V SA U G V R L AT D O R i L l NE C H p O A UO i C m AP F i i C S i 1 T ~ g N E C) W 1-MD E 6 A( 0 G RS R 3 EE gg T V RN M N A C PLA E n e F U V V C r X S T I A u CAO BR g g E P i T ' N F W A 8 / ^2 T N / EM C R UI i F RA T S h TN EV -tE

I Cooper i n 3.7 REACTOR BUILDING CLOSED COOLING WATER (RBCCW) { SYSTEM 3,7,1 Sistem Function The reactor building closed cooling water system provides cooling to the core I standby cooling system areas and the RHR pumps. Heat is transferred from the system to the service water system via the RBCCW heat exchangers. 3.7.2 System Definition The RBCCW system consists of two independent closed loops. Each loop contains two pumps and one heat exchanger for cooling of essential equipment and a non- ? essential header which is isolated during accident conditions. Simplified drawings of the RBCCW are shown in Figures 3.71 and 3.7 2. 3,7.3 System Oneration ? The RBCCW is normally operating, su pplying heat loads in the essential and non essential loops. One pump in each RBCCW loop is capable of supplying sufficient water to transfer the essential service design cooling load to the service water system. These pumps operate normally with the essential coohng service valved off. Upon receipt of signals indicating operation of the core standby cooling function following a LOCA, the non essential loads are isolated and two motor operated valves (one on each loop) are opened to supply cooling for the essentialloads. The equipment supplied by the RBCCW are as follows: Loon A Loon B Two RHR pump seal coolers X X HPCI pump area cooling X O RHR pump area cooling X X V Core spray pump area cooling X X 3,7.4 System Success Criteria i Following a design basis accident (DB A), the following success criteria applies to the RBCCW system (Ref.1). One out-of four RBCCW pumps operate successfully The appropriate RBCCW heat exchanger is available The appropriate train of the service water system is successful (see Section 3.8) Note that the Service Water System is a redundant cooling water source for most of the components served by the RBUCW system, therefore the SW system can perform the same function as the RBCCW. Since RBCCW success is dependent on SW success, the RBCCW pumps and heat exchangers is actually unnecessary under emergency conditions. ~ 3.7.5 Comnonent Information A. RBCCW Pumps (I A, IB, IC, and ID)

1. Rated flow: 1350 gpm @ 150 ft. head (65 psid)

2. Rated capacity: 100 %

3. - Type: centrifugal B. RBCCW Heat Exchar.gers (l A and IB) 6 O.

1. Design heat transfer: 33 x 10 Bru/hr

2. Rated capacity: 100 %

i 49 12 88

.~. _ _ _ _. _. Cooper 3.7.6 Suonort Systems and Interfaces A. Contml Signals

1. Automatic Upon receipt of the following signals the pumps are started and the essential-supply valves are opened.

Staning of any RHR pump motor Staning of any core spray pump motor Opening of HPCI turbine steam supply valve Opening of RCIC turbine steam supply valve Drywellisolation

2. Remote manual The pumps and valves can be actuated by remote manual means from the control room.

'B. Motive Power

1. The RBCCW pumps are Class lE AC loads supplied by the-480V emergency buses. Pumps I A and IB are supplied by Bus IF and pumps IC and ID are supplied by Bus 10.

3.7.7 Section 3.7 References

1. Cooper FSAR, Section 10.6.

i O 50 12/88-

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i Cooper 3.8 SERVICE WATER (SW) AND RIIR SERVICE WATER BOOSTER O SYSTEM V 3.0.1 itg[em Funetion The Service Water anc' RHR Service Water Booster System provides cooling water frcu ultimate heat siak, the Missouri River, to the secondary side of the RBCCW heat exck t and the RHR service water booster pumps. This system also can perform a core fboa . unction in an emergency. 3.8.2 System Definition The system contains four motor driven service water pumps which take suction through strainers at the intake structure. The pumps supply two headers from which the RBCCW heat exchangers, diesel heat exchangers, and RHR Service Water Booster Pumps are supplied. Simplified drawings of the SW system are shown in Figures 3.81 and 3.8-2. A summary of data on selected SW components is presented in Table 3.8 1 3.8.3 System Ooeration During normal operation three service water pumps ne required to cool the operating heat loads. One pump per SW train is sufficient fu. the emergency loads ,upported by that train as follows: Diesel generator RBCCW heat exchangers RHR service water pumps (Q 'N The, diesel generator and the RBCCW heat exchangers can be supplied by either loop of semce water 3.8.4 System Success Criterin One pump per SW train will support the heat loads served by that train. 3.8.5 Comnonent Information A. Service Water Pumps (A, B, C and D)

1. Rated flow: 8000 gpm @ 125 ft, head (54 psid)

2. Rated capacity: 100% (accident loads)

3. Type: vertical turbine B. RHR Service Water Booster Pumps

1. Rated flow 4000 gpm @ 800 ft. head (347 psid)

2. Rated Capa:ity: 50%

3.8.6 Sunnort Sv,tems and Interfaces A. Control Sigrals

1. Automatic Upon receipt of a LOCA or LOSP signal, one pump in each division is started.

2. Remote manual The SW pumps can be actuated by remote manual means from the control -

room. a 53 12/88

i Cmgr B. Motive Power

1. The SW pumps are Class lE AC loads that can be supplied from the 4

emergency diesel generator as described in Section 3.5. 4 i 1 1 i I l l [ 54 12/88

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=__ _ _ l [ l e i i i-Table 3.8-1. Cooper Service Water Systera Data Summary for Selected Componerts j COGBPONENT BD COtp P. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. SW-FMA MDP ISPUMPRM BUS-1F 4160 81F AC/F .( SW-FMB MDP ISPUMPRM BUS-1G 4160 B1G AC/G i SW-FMG MDP ISPUMPRM BUS-1F 4160 81F AC/F l t SW-FMO gJDP ISPUMPRM BUS-1G 4160 81G AC/G l t i I t I i t I h k { l-l I i t I i i 4 M i i 2 l ..l = [

..~.--P.- Cooper

4. PLANT INFORh1ATION 4

4.1 SITE AND HUILDING SUhth1ARY The Cooper Nuclear Sta: loc is located on a 1351 acre site on the west bank of the hilssouri River near the towns v Drownville and Nemaha, Nebraska in Nemaha County. The plant is at river mile 532.5 in an area of the river know as the Lower Brownville Bend. Figure 41 (from Ref.1) shows a general view of the site and the surrounding area. The major structures at this facility include the reactor building, the turbine building, the control buildin;;, the diesel generator building, the intake structure, the radioactive waste building and various support structures. The site general arrangement is shown in Figure 4 2. The reactor building is located on the west side of the turbine building. The building contains the primary containment drywell and torus housing, the reactor vessel, and recirculation pip ng, the fuel pool and the emergency core cooling system. An elevation drawing of the Coo,per reactor building is shown in Figure 4 3. The control building, located to the west of the turbine building and north of the reactor building contains the control roorn, cornputer room, cable spreading rooms, the DC batteries and switchgear, the auxillary relay room and the emergency condensate storage tanks. The diesel generator building is located on the cast side of the turbine building. This structure houses both emergency diesel generator and their associated fuel day tanks. The intake structure is to the cast of the diesel generator building and is located on the west bank o%he hiissouri River. The hiissouri River is the normal heat sink during power operation ara lho is the ultimate heat sink for safety related heat loads, t l 4.2 FACILITY LAYOUT DRAWINGS Figures 4 4 thru 415 are simplified building la out drawings for the Cooper reactor and turbine buildings and intake structure, Some ou ing buildings a.' not shown on these drawings, hiajor rooms, stairways, elevators, an doorways are shown in the simplified layout drawings however many interior walls have been omitted for clarity. Labels printed in uppercase correspon,d to the location codes listed in Table 41 and used m the component data listings and system drawings in Section 3. Some additional labels are included for information and are pnnted in lowercase type. A listing of components by location is presented in Table 4 2. Components included in Table 4 2 are those found in the system data tables in Section 3, therefore this table is only a partial listing of the components and equipment that are located in a particular room or area of the plant. 4.3 SECTION 4 REFERENCES

1. Heddleson, F.A., " Design Data and Safety Features of Commercial Nuclear Power Plants," ORNL NSIC 55 Volume 2, Oak Ridge National Laboratory, Nuclear Safety Information Center, January 1972.

O 58-1248-

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1 NORTH n v l U TORR U {l 869NECRNRM SECRNRM p, ROIC RK Suppression chamter / Oi \\ O = U= s 869NWCRNRM 869SWCRNRM v HPCIRM 125 250 HPCI-RK HPCI-AK I I I I Figure 4 4. Cooper Nuclear Station Reactor Building, Elevation 859'.9" 'Q 62 12/88 l

l NORTH \\ m...fO U u _gj A u \\ / Access Prestu's Hatch Suppresalon :. Chamber [ ]' O Access uO Hatch UD 5_e_ = SE M) sSINWCRNRM esisWCRNRM g l Figure 4 5. Cooper Nuclear Station Reactor Bullci,ng, Elevation 881'.9"- i O 63 12/88 ,-,._-.a..:....,-...

1 NORTH RCIC 125 V AC SCRAM Discharge Stader Ra* To Volume Tank / Turbine Building g "h hM MCC-K N e,,.. EEEE3 g STMTUN 6 %Il Hatch for Equipment g3 N m a CRD Hyd. , CRD Hyd. Control Control Units Units Nw CX f Drywell _ 9 I_ MCC Y /03DHXRM 903 AHXRM% MCCC l [ l Personnel 33 O Access toex o li l 4 m o k () uo I E_ 4 903RB RHR 35 94" MCC R MCC RB Start Rad 33 53 =- g e i i i / e l 1 903ACCSHLDRM 33 9 33:: 1 Figure 4 6. Cooper Nuclear Station Reactor Building, Elevation 903' 6" l 64 12/88 = -.

I h NORTH N h O Roof 4160V Swgr *1F' 4160V Swgr '1G' y I I I I B1F B10 Ro;f 490V Swor *1F' 480 V Swgr 't G* I I I I O I U llIII:!Illll D 'e 931 R B mm RWCUHXRM O 2 n CX { 931 AHXRM% p 931 B H X R M g O o o RWCUPMPA w RWCUPMPB uo oy E _E = EE

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l f 1 ' O 1 1 NORTH l l 988RB UIIIITTII] O O ^ O 9 (7~~ 6 00 00 = =_ 55 EE 35 f $y 4 Figure 4 8. Cooper Nuclear Station Reactor Building, Elevstion 958' 3" i l l i l lO j 66 12/88

- - - - -. -..... - - - ~. - - -. -.. -.. - -.. -. -. - 4 NORTH [ l Stora e Va p O I Fuel Dryer and Separator g

giorag, l

Storage Pool ponl l l Motor Ger.arator Set #18 O F i yD Motor Generator Set # 1 A DS E !5 55 = = 5 $5 t 1 \\ l i Figure 4 9. Cooper Nuclear Station Reactor Building, Elevation 976'.0" { l l 1 f i 6 f 67 12/88 l

1 tCRTH \\ iv r D sl New Fuel m 1 Storage Vavit - (Below) f TW Dryer and Segrator Sto, age Storage pooi 1000RB \\. l 5 E = Y L J Figure 410. Cooper Nuclear Station Reactor Building, Elevation 1001' 0" s V 68 12/88

1 NORTH 'N Turbine Generator Area C O Q y = 0 O n o \\ se2co CSTA Figure 411. Cooper Nuclear Station Turbine Building, Elevation 882" 6"- I f% l \\ / 69 12/88

i l 1 1 NORTH -) OO" 001A D018 g g g I I I I yevenA n D,e..n o O oo o g ugg g I w N h D (J d E OO O ~ T ^m Turbine U u 4 DN Generator ARLY 3 Atoa I = () U ^ wu 'l STMTUN BTRMB .g f', - DCSORMB Pipo Tunnel Fmm Reactor f4._ Building -- DCSORM A i w BTRMA i l r l Figure 412. Cooper Nuclear Station Turbine Building, Elevation 903"-6" i \\ 70-12/88 ._ _. _.._..,.-_ _.,_,. _. ~.,

1 NOATH / /\\ / i ur g = \\ Z 2 o b E" (~)) \\ 'u CSR Figure 413. Cooper Nuclear Station Turbine Building, Elevation 918" 0" 0\\ Nj 71 12/88

1 NORTH O O O LMw o Turbine Generator Area ri m D > --C 0 6 computer jg O Room Q --c O 6 v CH l l Figure 414. Cooper Nuclear Station Turbine Building, Elevation 932" 6" IA) \\. J 72 12/88

= 1 NORTH l l 1 -C c / ssee 1 ISPUMPRM s I l O Figure 4 15. Cooper Nuclear Station intake Structure - / k 73 12/S8 i $wgr T- -4 w w y e -'-=+z-a-.-,-.ger -re-r-TP'""" M 'TP-'T"&P'8 T T1'+"9P""*N"f's'""W*'

Table 41. Definition of Cooper Building and Location Codes podes Descrintions 85')NECRNRhi 859' elevation northeast cornerroom S. 859NWCRNRhi 859' elevation northwest corner room 3. 859SWCRNRh1 859' elevation southwest cornerroom 4, 881NECRNRhi 881' elevation northwest corner room 5. 881SWCRNRhi 881' elevation southwest corner room - 6. 882CB 882' elevation ControlBuilding 7. 903ACCSHLDRhi Personnel Access Shield Room, located on the 903' elevation of the Reactor Building 8, 903AHXRht 903' elevation of the Reactor Bailding RHR A Heat-Exchanger Room 9. 903BHXRhi 903' elevation of the Reactor Building RHR B Heat Exchanger Room

10. 90RB 903' elevation of the Reactor Buildinb tart rack htCCR, htCCRB, hiCCY, hiCCQ, RHR Start rack, RCi S

11. 931AHXRhi 931' elevation of the Reactor Building RHR A Heat Exchanger Room 12, 931BHXRhi 931' elevation of the-Reactor Building RHR B Heat Exchanger Room 1

13, 931RB 931' elevation of the Reactor Building 14, 958RB 958' elevation of the Reactor Building htCCRA

15. 1000RB 1000' elevation of the Reactor Building Spent Fuel Pool Operating Floor -

16. ARLY Auxiliary Relay Room, located on the 903' elevation of the Turbine Building

17. B1F IF Switchgear Roo.m located on the 931' elevation of the Reactor Butiding

18. BlO 10 Switchgear Room, located on the 931' elevation of the Reactor Building

19. BTRhiA Battery Room A - hiezzanine Level of Turbine Building 74 12/88

Table 41. Definition of Cooper Building and Location Codes (Continued) Codes Descrintions

20. BTRhiB Battery Room B - Mezzanine Level of Turbine Building

21. CR Control Room, heated on the 932' elevation of the Turbine Building

22. CSR Cable Spreading Rrom, located on the 918' elevation of the Turbine Building 23, CSTAB Condensate Storage Tanks A and B

24. CX Reactor Containmerit

25. DCSGRMA DC Switchgear Room A - hiezzanine Level of Turbine Building

26. DCSGRMB DC Switchgear Room B - hiezzanine Level of Turbine Building

27. DGIA Diesel Generator Room 1 A Mezzanine Level of Turbine Building

28. DG1B Diesel Ge6.erator Room IB Mezzanine Level of Turbine Building

29. HPCIRM High Pressure Coolant Injection System Pump Room, located on the 859' elevation adjacent southwest corner room -

30. ISPMPRM Intake Structure Pump Room

31. RWCUHXRM

- Reactor Water Cleanup Heat Exchanger Room, located on the 931' elevation of the Reactor Buildmg

32. RWCUPMPA Reactor Water Cleanup Pump A Room, located on the 931' elevation of the Reactor Building

33. RWCUPMPB Reactor Water Cleanup Pump B Room, located on the 931' elevation of the Reactor Building 34 SECRNRM Located on the 859' elevation southeast comer room 1

35. STMTUN Steam Tunnel u

36. TORR Torus Area -

Ob 75 12/88

TABLE 4 2. PARTIAL LISTING OF COMPONTENTS BY LOCATION AT COOPER LOCATION SYSTEM COMPONENT 10 COMP TYPE 869NECRNRM ECCS CS M07A MOV 859NECRNRM ECCS CS-PM1 A MDP 4 659NECRNRM ECCS CS V26A MOV t$9NECRNRM EP RCC-RK MCC 869NECRNRM KC RCIC-M0131 MOV 669NECRNRM NC RC6C MD10 MOV 659NECRNRM RCC RCIC-MO20 MOV 859NECRNRM NC RCC MO41 MOV 659NECHNRM NC SUPP PE 669NECRNRM NC RCIC-TURB TDP 659NECRNRM RCC RCIC V27 MOV 66DNECRNRM KC RCIC V30 MOV 869NECRNRM NC RCIC V33 MOV B59NWCRNRM ECCS LPSiFMA MDP 669NWCRNRM ECCS LPSI-FMC MDP 659NWCRNRM ECCS LPSIV13A MOV 659NWCRNRM EC;S LPSI V13C MOV 859SWCRNRM ECCS LPS4 PMB MDP 9595WCRNRM ECCS LPSI-PMD MDP W WCRNRM ECCS LPSI V13B MOV 859SWCRNRM ECCS LPSLV13D MOV 681NWCRNRM ECCS LPSI V34A MOV 681NWCRNRM ECCS LPSIV39A MOV 681SWCRNRM ECCS LPSIV34B-MOV 861SWCRNRM ECCS LPSIV39B MOV 6820B EP MCC L ) MCC i-903ACCSHLDRM ECCS HPCI-mot 6 MOV 903ACCSHLDRM ECCS HPCLM016 MOV 903ACCSHLORM ECCS LPSI-MO27A MOV n 903ACCSHLDRM ECCS LPSIV25A MOV ( \\ 903ACCSHLORM ECCS LPSi-MO27B MOV 76 12/88

j-l i TABLE 4 2. PARTIAL LIST!WG OF COMPONTENTS SY LOCATION AT COOPER (CONTINUED) LOCATION SYSTEM COMPONENT ID COMP i TYPE j 903ACCSHLDRM ECCS LPSIV26A MOV 933ACCSHLDRM RCS RMR Mt? MOV l 903AHARM ECCS LPSIV12A MOV 903AHARM ECCS LPSIV26A MOV l 903AHARM ECCS LPS6 V66A MOV j-903BHARM ECCS LPSI V128 MOV 933BHARM ECCS LPSI V26B MOV 903BHARM ECCS LPSI V66B MOV 903RB ECCS LPSIV31B MOV 903RB EP MCC-C MCC l 903RB EP MCGM MCC 903RB EP MC48 MCC E RB EP RHRA RK MCC-903RB EP RCIC-RK MCC 903RB EP MCC S MCC 903RB EP MCC RB MCC 903RB EP MC4Y-MCC 903RB EP RHAB RK MCC 93 t AHARM ECCS LPS6 V65A MOV 93 t BHARM ECCS LPSIV658 MOV 931RB ECCS CS-Mo t 1 A MOV 931RB ECCS CS MC118 MOV 931RB ECCS CS-M012A MOV 93188 ECCS CS Mol2B MVV 931RB ECCS LPS! V31 A MOV l 958RB = EP MCC-M MCC 958RB EP STRT RK MCC l ARLY EP MCC-LX - MCC l ARLY EP MCO TX MCC-BtF EP CB1F CB I BlF EP BUS 1F BUS-i 77 12/88 1E

TABLE 4 2. PARTIAL LISTING OF COMPONTENTS BY LOCATICN AT COOPER (CONTINUED) LOCAT60N SYb1EM COMPONENT 6D COMP TYDE B1F EP IDBVS1F BVS B1F EP 1R1F AFMR - BIG EP CBl-O CB BIG EP BV41G BUS B10 EP IDDV41G BVW B10 EP TF&1G XFMR BTRMA EP BAT 1A BATT DTRMB EP BAT 1B BA l'T CSR EP INSPNL1A PNL CSR EP INSPNL.1 B FNL ~~ CSTAB ~5(CS CST 1 A TANK CSTAB ECCS CST 1B TANK CSTAB FCC CST.1 A TANK CSTAB FCC CST.10 TAN 6 CX ECCS RCS VESSEL RV CX ECCS RCS VESSEL RV CX ECCS HPCIM016 MOV CX ECCS RCS VESSEL RV CX ECCS HPClMOt$ MOV CX ECCS ACS-VESSEL RV CX ECCS RCS VESSEL RV CX FCC RCIC-Ac t i6 MOV CX RCC RCS VESSEL RV CX RCS RHR M18 MOV CX FtCS RCS-V74 MOV CX RCS RV 71A SRV CX RCS RCS VESSEL RV CX RCS RCIC-M015 MOV CX RCS RV 71A SRV CX RCS RWCUV15 ACV m _g ) CX RCS RV.70A SV %d 78 12/88

-._..__._.___.m..___ i TABLE 42. PARTIAL LISTING OF COMPONTENTS BY LOCATION AT COOPER (CONTINUED) LOCATlON SYSTEM COMPONENT ID COMP TYPE Cx RCS RV 70B SV Cx RCS RV 70C SV CX RCS RV 70B SV CX RCS RV 70A SV CX RCS RV 700 SV CX RCS RV 71B SRV. W RCS RV 71C SRV CX RCS RV 710 SRV CX RCS RV 71E SRV CX RCS RV 71F SRV 1 CX RCS RV 7*G SRV CX RCS RV 71H SRV CX RCS RV 71B SRV CX RCS RV 71C SRV k CX RCS RV 710 SRV CX RCS RV 71E SRV CX RCS RV 71F SRV CX RCS RV 71G SRV CX RCS RV 71H SRV DCSGRMA EP BC1A BC DCSGRMA EP BUS 1A BUS DCSGRMA EP BUS 1A BUS DCSGRMA EP ITR480/120 XFMR DCSGRMA EP DC-PNL A PNL DCSGRMB EP BC1B BC DCSGRMB EP BUS 1B BUS DCSGRMB EP BUS 1B BUS DCSGAMB-EP ITR460/120 XFW) DCSGRMB FP DC-PNL B PNL 1 DGIA EP DG-1 A DG 1: V E1B EP DG-1B DG 79 12/88

TABLE 4 2. PARTIAL LISTING CF CCMPONTENTS BY LOCATION AT COOPER (CONTINUED) LOCdTION 5YS!EM C.CMPONE NT ID COMP (N TYPE HPCIRM ECCS HPC6 Mold MOV HPCRM ECCS HPCI M017 MOV HPCiRM ECCS HPC6-MO20 Mov iPCiRM ECCS HPC6MO58 MOV HPCIRM ECCS HPC6 TURB TDP HPCi4M ECCS HPC6 v21 MOV HPC1RM ECCS HPClV24 @V HPCIRM ECCS HPC6 V25 MOV HPCIRM EP HPCI-RK MCC HPCIRM EP HPCIRK MCC ISP MPRM SW SW FMA MDP U 6SPVMPRM SW SWPMD MDP ISPUMPRM SW SW PMC MDP iSPUMPRM SW SW4PMD MDP RWCUmRM RCS RWCU VtB MOV SECRNRM ECCS CS M078 MOV SECRNRM ECCS CS-PM t B MDP ~ SECRNRM ECCS CS V26B MGV STMTUN ECCS HPClM019 MOV ~ STMTUN NIC RCIC dot 6 ^ MO' / ~ $!MTUN NC RCIC-V021 MOV SIMTUN RCS RCIC-lot 6 MOV O i V 80 12/88

Cooper 5. BIBLIOGRAPilY FOR COOPER NUCLEAR STATION

1. Hatch, S.W., et al., " Shutdown Decay Heat Removal Analysis of a General Electric BWR4/ Mark 1; Case Study," NUREG/CR 4767, Sandia National Laboratories, July 1987.

2. Brice, J.R., " Aquatic Impacts from Operation of Three Mid Westem Nuclear Power Stationr' Cooper Nuclear Station Environmental Appraisal Report,"

NUREG/CR.2337, Volume 2, Environmental Sciences & Engineering, Inc., October 1981, w 81 12/88

Cooper [' APPENDIX A \\ DEFINITION OF SYMBOLS USED IN Tile SYSTEh! AND LAYOUT DRAWINGS A 1. SYSTEM DRAWINGS A 1.1 Fluid System Drawings The simplified system drawings are accurate representations of the major flow paths in a system and the important interfaces with other fluid systems. As a general rule, small fluid lines that are not essential to the basic operation of the s drawings. Lines of this type include instrumentation lines,ystem are not shown in these vent lines, drain lines, and other lines that are less than 1/3 the diameter of the connecting major flow path. There usually are two versions of each fluid system drawing; a simplified system drawing, and a comparable drawing showing component locations. The drawing conventions used in the - fluid system drawings are the following: Flow generally is left to right. Water sources are located on the left and water " users" (i.e., heat loads) or discharge paths are located on the right. One exception is the return flow path in closed loop systems which is right to left. Another exception is the Reactor Coolant System (RCS) drawing which is " vessel-centered", with the primary loops on both sides of the vessel. Horizontal lines always dominate and break vertical lines. OQ -- Component symbols used in the fluid system drawings are defined in Figure Most valve me pump symbols are designed to allow the reader to-distinguish among similar components based on their support system requirements (i.e., electric power for a motor or solenoid, steam to drive a turbine, pneumatic or hydraulic source for valve operation, etc.) Valve symbols allow the reader to distinguish among valves that allow flow in either direction, check (non return) valves, and valves that perform an - i overpressure protection function.L No attempt has been made to define the. specific t of valve).ype of valve (i.e., as a globe, gate, butterfly, or other specific type Pump symbols distinguish between centrifugal and positive displacement pumps and between types of pump drives (i.e., motor, turbine, or engine). Locations are identified in terms of plant location codes defined in Section 4 of this Sourcebook. Location is indicated by shaded " zones" that are not intended to represent the actual room 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 piping-passes (i.e. including pipe tunnels and urterground pipe runs). Compenant locatiors that are not known are indicated by placing the l ca.:ponents in an unshaded (white) zone. D) The primary flow path in the system is highlighted (i.e., bold whita line) in the locanon version of the fluid system drawings. 82 12/88

Cooper A1.2 Electrical System Drawings l (O 'j The electric power system drawings focus on the Class IE portions of the plant's l electric power system. Separate drawings are provided for the AC and DC portions of the Class 13 system. There often are two versions of each electrical system drawing; a simplified system drawing, and a comparable drawing showing component locations. The i 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 switchyard and/or offsite grid is shown at the top of the drawing. In the DC power drawings, the batteries and the interface with the AC power system are shown at the top of the drawing. l Vertical lines dominate and break horizontal lines, j Compor :nt symbols used in the electrical system drawings are defined in Figure A 2. i Locations are identified in terms of plant location codes defined in Section 4 of this Sourcebook. Locations are indicated by shaded " zones" that are not intended to represent the actual room geometry. Locations of discrete components represent the actual physical location of the component. l The eleenical connections (i.e., cable runs) between discrete components, I as shown on the electrical system drawings, DO NOT represent the actual l n cabk. outing in the plant. l I (V Component locations that are not known are indicated by placing the discrete compenents in an unshaded (white) zone. A2. SITE AND LAYOUT DRAWINGS i l A2.1 Site Drawings A general view of each reactor site and vicinity is presented along with a simplified i site plan slowing the arrangement of the major buildings, tanks, and other features of the site. The general view of the reactor site is obtained from ORNL-NSIC-55 (Ref.1). The site drawings are ap 3roximately to scale, but should not be used to estimate distances on the site. As-built sca e drawings should be consulted for this purpose. Labels printed in bold uppercase correspond to the locanon codes defined in Section 4 and used in the component data listings and system drawings in Section 3. Some additional labels are included for information and are printed in lowercase type. A2.2 Layout Drawings Simplified building layout drawings are developed for the portions of the plant a a contain components and systems that are described in Section 3 of this Sourcebook. Generally, the following buildings are included: reactor building, auxiliary building, fuel building, diesel building, and the intake structure or pumphouse. Layout drawings generally are not developed for other buildings. Symbols used in the simplified layout drawings aie defined in Figure A 3, Major p rooms, stairways, elevators, and doorways are shown in the simplified layout drawings 1 however, many interior walls have been omitted for clarity. The building layout drawings, r'%J 83 12/88

._. _ __._.-._._. _ ~ _._ _ _ _. _. ~.. _ _ _ Cooper are approximately to scale, should not be used'to estimate room size or distances, As built scale drawings for should be consulted his purpose. iO 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 t>w, i A3. APPENDIX A REFERENCES 1. Heddleson, F. A., " Design Data and Safety Features of Commercial Nuclear Power Plants.", ORNL NSIC-SS, Volumes I to 4 Oak Ridge National Laboratory, Nucleu Safety Information Center, December 1973 (Vol,1), January 1972 (Vol. 2), April 1974 (Vol. 3), and March 1975 (Vol. 4) l k 84 12/88 i -.w-

__.m. kJ MANUAL VALVE. XV MANUAL NON RETURN g F7 (O P E NIC L O S E D) VALVE 1CV (OPEN CLOSED) F Q O L2 MOTOR OPER ATED VALVE

WOV MOTOR OPER ATED r7 (OPEN' CLOSED) 5 WAY VALVE MOV (CLOSED PORT MAY V ARY)

W 'M SOLENOID 0PER ATED VALVE. SOV SOLENCID OPER ATED F' (CPe NICLOSED) 5 WAY V ALVE. 80V (CLOSED PORT MAY VARY) HYDR AULIC VALVE NV HYDR AULIC NON RETURN r7 - (O P E N /C L O S E D) 4 4 VALVE HCV (OPEN> CLOSED) 2 PNEUMATIC VALVE = NV PNEUMATIC NON RETURN (O P E N /CL O S E D) V ALVE NCY (OPEN' CLOSED) 7' CHECK YALVE CV d S AFETY V ALVE. SV \\ (CLO S E D) V Ch h POWER OPER ATED RELIEF VALVE, POWER CPER ATED RELIEF VALVE., MV SOLENOID PILCT TYPE PORY JC PNEUMATICALLY CPER ATED PORY (CLOSED) OR DUAL FUNCTION SAFETY / RELIEF V ALVE. SRV _(CLOSED) l I l l CENTRIFUG AL CENTRIFUQ AL WOTOR DRIVEN PUMP = MDP TURBINE DRIVEN PUMP. TDP l \\ / l l POSITIVE DISPLACEMENT POSITIVE DISPLACEMENT MOTOR DRIVEN PUMP

MOP TURBINE 0 RIVEN PUMP TDP 1

\\ / I 1

n

( l Figure A-1.- Key To Symbols in Fluid System Drawings 85 12/88 J

~, - -.... ~ ^ PWR'8WR. MAIN CONDENSER. COND - RE ACTOR VESSEL. AV c J f Q HE AT EXCH ANGER. HX MECHANIC AL DR AFT ,h COOLING TOWER h AIR COOLING UNIT. ACU STEAM TO WATER OR WATER.TO.5TE AM HEAT 4 EXCHANGER (l.E. FEE 0W ATER HEATER, DR AIN COOLER, ETC.). HX A o SMAY NOWS M OR TANK Tx aaaaaaaa Y v i ( J 4 RuRTuRE einx. Ao -Q-- ORinCE. OR O Figure A-1. Key To Symbols.In Fluid System Drawings-(Continued) 86 12/88

r A C. DIESEL OENER ATOR Do 8 ATTERY. 84TT OR A.C, TUR8tNE CENEP$'OR. 70 ON C RCUI BREAKER.C8 [] ll [].. 41 OR II...[3 INTERLOCKED ( I CIRCUIT BREAKERS C8 SWITCH SW o A UTO M ATIC OR O OR OTHER YYPE OF TR ANSFER SWITCH ATS DISCONNECT D E VIC E OR (C P E N rCL O S E D) MANUAL TRANSFER SWITCH MTS SWITCH 0E AR BV8 BUS [ (BUS NAME) l MOTOR CONTROL CENTER-. MCC M N OR.D.7--? ? TRANSFORMER

TR AN l

OR I OtSTRIBUTION PANEL

PNL l

l B ATTERY CHARGER (RECTIFIER)

BC 5Z INVERTER. INV l

l w/ 1 RELAY CONTACTS OR FUSE FS 7 (O P E N1CL O S E D) I ELECTRIC uoToR. uTR ooyo, o,,,,,10,,,o i\\ Figure A-2. Key To Symbols in Electrical System Drawings 87 12/88-

) STAIRS $",$P g SPIRAL STAIRCASE own 7 LADDER ( i u. Up ELEVATOR D= Down

M HATCH OR OPEN AREA GRATING DECK (NO FLOOR)

-O-PERSONNEL DOOR w

EQUlPMENT DOOR E

- RAILROAD TRACKS FENCE LINE E O TANK / WATER AREA Figure 'A-3. Key To Symbols-In Facility Layout Drawings i 88 12/88 4 ,e nw,-.-n ,--e .-mee s.w. .v,r.weo---- -n-wow,- -r-re--v wa w - m, -mmr m - w rw-- w r.c e we.- -+-m ,n

. - ~..... Cooper ( APPENDIX B DEFINITION OF TERMS USED IN THE DATA TABLES Terms appearing in the data tables in Sections 3 and 4 of this Sourcebook are defined as follows: SYSTEM (also LOAD SYSTEM)- All components associated with a particular system description in the Sourcebook have the same system code in the data base. System codes used in this Sourcebook are the following: .C.gde Definition RCS Reactor Coolant System RCIC Reactor Core Isolation System ECCS Emergency Core Cooling System (including HPCI, ADS, CSS and LPCI I&C Instrumentation and Control Systems EP Electric Power System SW Service Water System COMPONENT D (siso t.OAD COMPONENT ID) The component identification (ID) code in a data table matches the component ID that appears in the corresponding system drawing. The component ID generally,begins with a system preface followed by a component number. The system preface is not necessarily the same as the system code described above. For component ids, the system preface corresponds to what the plant calls the component (e.g. HPI, RHR). 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 com?onent number appearing in the plant piping and instrumentation drawings (P& ids) and electrical one-line system drawings. LOCATION (also COMPONENT LOCATION and POWER SOURCE LOCATION) - Refer to the location codes defined in Section 4. l I COMPONENT TYPE (COMP TYPE)- Refer to Table B 1 for a list of component type L 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 >onent may have more than one power source (i.e. a DC bus powered from a battery and a 3attery charger). POWER SOURCE VOLTAGE (also VOLTAGE) The voltage "seen" by a load of a >ower source is entered in this field. The downsuram (output) voltage of a transformer, unverter, or battery charger is used. EMERGENCY LOAD GROUP (EMERO LOAD GROUP)- AC and DC load groups (or electrical divisions) are defined as appropriate to the slant. Generally, AC load groups are identified as AC/A, AC/B, etc. The emergency loac group for a third of-a kind load (i.e. a " swing" load) that can be powered from ei+ '; of two AC load identified as AC/AB. DCload group follows sirr.a naming conventions. groups would be 89 12/88 l 1 sr-- emr ---+,= ns e.v.- e e-- ~nre-. 4 e_ a, eww ,-m-r, m es

TABLE B 1. COMPONENT TYPE CODES 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 return valve HCV Safety valve SV Dual function safety / relief valve SRV Power operated rehef valve ~ PORV (pneumatic or solenoid-operated) PUMPS: Motor driven pump (centrifugal or PD) MDP Turbine driven pump (centrifagal of PD) TDP Diesel driven pump (centrifugal of PD) DDP OTHER FLUID SYSTEM COMPONENTS: Reactor vessel RV Og Steam generator (U tube or once through) SG-l\\j Heat exchanger (waterno-water HX, HX-l or water to-air HX) l Cooling tower CT Tank TANK or TK Sump . SUMP Rupture disk RD i Orifice ORIF Filter or strainer FLT Spray nozzle SN Heaters (i.e. pressurizer heaters) HTR VENTILATION SYSTEM COMPONENTS: Fan (motor-driven, any type) FAN Air cooling unit (air-to water HX, usually - ACU or FCU including a fan) Condensing (air-conditioning) unit - COND EMERGENCY POWER SOURCES: l Diesel generator DG Gas turbine generator GT Battery BATT O m 90 12/88 a

TABLE B 1. COMPONENT TYPE CODES (Continued) CONTPONENT COMP TYPE ELECTRIC POWER DISTRIBUTION EQUIPMENT: Bus or switchgear BUS Motor control center MCC Distribution panel or cabinet PNL or CAB Transfonner TRAN or XFMR Battery charger (rectifier) BC or RECT Invener INV Uninterruptible power supply (a unit that may UPS include battery, battery charger, and inverter) l Motor generator MG l Circuit breaker CB i Switch SW Automatic transfer switch ATS Manual transfer switch MTS m i 1 D O 91 12/88 -A}}

ML20070Q778

Text

SUMMARY

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