ML20070Q788

Nuclear Power Plant Sys Sourcebook,Wolf Creek

ML20070Q788
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1988
From:	Lobner P, Saylor P SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY
To:	NRC
References
CON-FIN-D-1763, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-88-1996, NUDOCS 9103290178
Download: ML20070Q788 (133)

Text

{{#Wiki_filter:._ O ggaREGO 4 Ay 0 y i NUCLEAR POWER PLANT i SYSTEM SOURCEBOOK o . ~ff).'~^j g,' eh j 4 4**+ WOLF CREEK O so 482 S O M newCK 05on, p 1

SAIC 88/1996 8il(gRREGq b pf o NUCLEAR POWER PLANT e

• kh@M /',", np#

5 i SYSTEM SOURCEBOOK g L g 4, # c 41 WOLF CREEK l 50 482 Editor: Peter Lohner l Author: Patricia Saylor 1 Prepared for: U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Contract NRC 03 87 029 FIN D 1763 i y_. l

l 1 - Wol' Creek ) TAllt.E OF CONTENTS J Section Egg 1 S UM M A R Y D ATA ON PLANT................................................ 1 2 IDENTIFICATION OF SNILAR NUCLEAR POWER PLANTS........ 1 3 S Y STE M INFORM ATI ON..................................................... 3 3.1 Reactor Coolant S ystem (RCS ),........................,............... 8 3.2 Auxiliary Feedwater (AFW) System and Secondary l S t eam Relie f (S S R) S ystem............................................ 14 3.3 Emergency Core Cooling System (ECCS)........................... 20 3.4 C h arg in g S ys t e m..........,............................................ .28 3.5 Instnimentation and Control (I & C) Systems,........................ 34 3.6 E le c tri c Po we r S y s t e m.................................................. 38 3.7 Component Cooling Water System (CCWS).......................... 53 3.S Essential Service Water System (ESWS) 63 3.0 Post-accident Heat Removal System (PAHRS),..................... 70 i 4 P L A NT I N FOR M ATI O N.....,,,..,,,,...................................... ~ 'i 4.1 S ite and B uildin g S ummary............................................. ~5 4.2 Facility Layout Drawings. 75 5 BIB LIOG RA PH Y FOR WOLF CREEK...................................... I13 g l APPENDIX A Defmition of Symbols Used in System and Layout Drawings........................................................................ I14 APPENDIX B Definition of Terms Used in Data Tables..................... 121 i l i l l l l i i i \\j i. 12/88

Wolf Creek f LIST OF FIGURES \\ Fic ne has 3-1 Cooling Water Systems Functional Diagram for Wolf Creek........... 7 3.1-1 Isometric View of a 4 Loop Westinghouse RCS,........................ 10 3.1-2 Wolf Creek Reactor Coolant System...................................., 11 3.1-3 Wolf Creek Reactor Coolant System Showing Component Lo: a ti o n s.................................................,.................... 12 3.2-1 Wolf Cree k Au xiliary Feed wate r S yste m................................... 17 3.2-2 Wolf Creek Auxiliary Feedwater System Showing Component Locations..... 18 3.3-1 Wolf Creek S afe ty Inj ection Syste m........................................ 23 l 3.3 2 Wolf Creek Safety injection System Showing Component Locations... 24 3.3-3 Wolf Creek Residual Heat Removal System..................,,....... 25 A ) 3.3 4 Wolf Creek Residual Heat Removal System Showing \\d Coraponent Locations....................,.............................,,..., 26 l l 3.4-1 Woi f C re e k C h a rgin g _ S y s t e m................................................ 31 1 3.4-2 Wolf Creek Charging System Showing Component Locations......... 32 3.6-1 Wolf Creek 4160 and 480 VAC Electric Power Distribution System, 41 3.6-2 Wolf Creek 4160 and 600 VAC Electric Power Distribution System Showin g Componen t Loca tion s..................................,....... 42 3.6-3 Wolf Creek 125 VDC and 120 VAC Electric Power Distribution System.... 43 3.6-4 Wolf Creek 125 VDC and 120 VAC Electric Power D:stribution System Showing Component Locations............................. 44 3.7-1 Wolf Creek Component Cooling Water System...................... 56 3.7-2 Wolf Creek Component Cooling Water System Showirg Component Locations......................................_............. 59 3.8-1 Wolf Creek Essential Service Water System Train A................. 65 m(V Wolf Creek Essential Service Water System Train A Shweg i 3.8-2 Component L o,: a t i o n s..............................................., 66 ii, 12/88 ~

Wolf Creek O LIST OF FIGURES (continued) U Figure Eagt 3&3 Wolf Creek Essential Service Water System Train B..................... 67 3h4 Wolf Creek Essential Service Water System Train B Showing Componeni Locations....................................................... 68 3.9-1 Wolf Creek Containment Spray S ystem.................................... 72 3.9 2 Wolf Creek Containment Spray System Showing Component Loc a ti on s............................................ 73 4-1 General View of Wolf Creek Site and Vicinity...................... 76 4-2 Plot Plan of Wolf Creek Nuclear Generating Station............. 77 4A SNUPPS Reactor and Auxiliary Building Section Views............. 78 4-4 SNUPPS Auxiliary Building and Communication Corridor Section View 80 4-5 SNUPPS Diesel Generator Building, Control Building and p Communication Corridor S ection View................................... 81 4-6 S NU PPS Fuel Building Section Views................................... 82 47 Wolf Creek Reactor and Auxiliary Buildings, Elevation 1974'0"...... 84 48 Wolf Creek Reactor and Auxiliary Buildings, Elevation 1988'0"....... 85 49 Wolf Creek Reactor, Auxiliary and Fuel Buildings, Elevation 2000'0" 86 4-10 Wolf Creek Reactor, Auxiliary and Fuel Buildings, Elevation 2026'0" 87 4-11 Wolf Creek Reactor, Auxiliary and Fuel Build.ings, Elevation 2047'6" 88 12 Wolf Creek Control Building and Communication Corridor, E l e v a t i o n 1 9 7 4 '0 "............................................................. 89 Wolf Creek Control Building and Communication Corridor, E l e v a t i o n 19 8 4 '0 "........................................................... 90 .4 Wolf Creek Diesel Generator Building, Control Building and Communication Corridor, Elevation 2000'0"............................. 91 4-15 Wolf Creek Diesel Generator Building, Control Building and Communication Corridor, Elevation 2016'0"........................... 92 b 4-16 Wolf Creek Diesel Generator Building, Control Building and \\ Communicapon Corridor, Elevation 2032'0"........................... 93-i iii. 12/88

Wolf Creek O LIST OF FIGURES (continued) 'J Figure fue 4-17 Wolf Creek Diesel Generator Building, Control Building and Communication Corridor, Elevation 2047'6".............................. 94 4-18 Wolf Creek Diesel Generator Building, Control Building and Communication Corridor, Elevation 2073'6".............................. 95-4-19 Wolf Creek Essential Service Water Pumphouse Section View......... 96 4 20 Wolf Creek Essential Senice Water System Pumphouse, E l e v a t i o n 2 000 '0 "............................................................. -98 4-21 Wolf Creek ESWS Valve House Section Cews.......................... 99 4-22 Wolf Creek ESWS Valve House, Elevations 1885'5.5",1991'0" and 2000'0".... 101 A-1 Key to Symbols in Fluid System Drawings............................... 117 A-2 Key to Systems in Electrical System Drawings........................... 119 O A3 Key to Sym'cols in Facility Layout Drawings............................. 120 b i m (v) iv. 12/88

-Wolf Creek LIST OF TABLES Tahic })ggg 3-1 Sumn.try of Wolf Creek Systems Covered in this Report............... 4 3.1 1 Wolf Creek Reactor Coolant System Data Summary for Selected Components..................,,............................................... 13 3.2-1 Wolf Creek Auxiliary Feedwater System Data Summary for S e le c te d Compon e nt s......................................................... 19 3.3-I Wolf Creek Emergency Core Cooling System Data Summary for Sele c te d Compone nt s....................................................... 27 3.4-1 Wolf Creek Charging System Data Summary for Selected Components.,............................................................... 33 3.5-1 Wolf Creek Auxiliary Shutdown Panel Controls........................ 37 3.6 1 Wolf Creek Electric Power System Data Sun' mary for Selected Compone n ts..... 45 3.6 2 Partial Listing of Electrical Sources and Loads at Wolf Creek........... 48 b( 3.7 1 Wolf Creek Component Coo'ing Water System Data Summary for S e le c ted Com po ne n t s......................................................... 62 3.8-1 Wolf Creek Essential Service Water System Data Summary for Selected Components............ 69 3.9 1 Wolf Creek Post. Accident Heat Removal System Data Summary for S el e c t ed Com pon e n t s....................................................... 74 4-1 Definition of Wolf C eek Building and Location Codes.................. 102 l 4-2 Pardal Listing of Components by Location at Wolf Creek............... 107 B1 Compon e n t Type Cod e s..................................................... 123 O( v. 12/88

i i WolfCreek (~ i CAttrION l The information in this report has been developed over t n 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 cur j knowledge, it accurately reflects the plant configuration at the time the information was obtained, however, the information in this document has 4 not been independently verified by the licensee or the NRC. t EQIlCE Thir sourcebook will be periodically updated with new and/or replacement 4 pages as appropriate to incorporate additional information on this reactor plant. Technical errors in this report should be brought ta the attention of the following: Mr. Mark Rubin U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation y Division of Engineering and Systems Technology Mail stop 7E4 j Washington, D.C. 20555 With copy to: l Mr. Peter Lobner Mr. nager, Systems Engineering Division l Science Applications Intemational Corporation - 10210 Campus Point Drive 1 San Diego,CA 92131 (619)458 2673 j Correction and other recommended changes should be submitted in the form of marked up copies of the affected text, tables or figures. Supporting i documentation should be included if possible. 1 i l l i l-i l .I - vi. 12/88-

i WOLF CREEK 1 i RECORD OF REVISIONS REYlSION ISSUE COhlh1ENTS 0 12/88 Original report l l l l l l 1 l i i 1 \\ vii. 12/88 .___._._..____._.-._-..,2.....-,- . -. ~,. -.. _,..

Wolf Creek f's, WOLF CREER SYSTEM SOURCEBOOK V This sourcebook contains summary information on Wolf Creek. Summary data on this plant are presented in Section 1, and similar nuclear power plants are identif'ied in Section 2. Information on selected reactor plant systems is presented in Section 3, and the site and building layout is illustrated in Section 4. A bibliography of reports that describe featutes 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 in Appendh B. 1. SLMMARY DATA ON PLANT Basic informe. tion on the Wolf Creek nuclear power plant is listed below: Docket number 50 482 Operator Kansas Gas & Electric Company, and Kansas City Power and Light Company l_wation Burlington, Kansas Commercial operation date 9/85 Reactor type PWR NSSS vendor Westinghouse Number of loops 4 Pow er (MWt/MWe) 3425/1150 Architect engineer Bechtel(standard plant)/SNUPPS Group /Sargent & Lundy (site) Containment type Reintorced concrete cylinder with steel liner ' pb 2. IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS Wolf Creek is one of five nuclear power plants that were to be constructed as part of the Standardized Nuclear Unit Power Plant Systern (SNUPPS) project. The l SNUPPS plant design is based on a standard Westinghouse 4 loop PWR nuclear steam supply system. Originally the SNUPPS project included single unit plants at Wolf Creek, Tyrone (Northem States Powed, and Sterling (Rochester Gas and Electric), and a twin unit plant at Callaway (Union Electric). Only Wolf Creek and a single unit at Callaway were actually completed. Other four loop Westinghouse plants in the United States include: Braidwood I and 2 Byron 1 and 2 Catawba Comanche Peak 1 and 2 l Donald C. Cook 1 and 2 (ice condenser containment) Diablo Canyon 1 and 2 Haddam Neck Indian Point 2 and 3 McGuire 1 and 2 (ice condenser containment) Millstone 3 Salem 1 and 2 Seabrook1 Sequoyah and 2 (ice condenser containment) Shearon Harris 1 and 2 O South Texas 1 and 2 Trojan V Vogtle I and 2 Watts Bar 1 and 2 1 1/89 c

Wolf Creek Yankee Rowe 6; Zion 1 and 2 k Wolf Creek is generally similar to the other plants in the number and type of charging and high pressure iniection aumps. Differences tetween Wolf Creek and Callaway (the two completed SNUPPS p ants) are listed below: Ultimate IIcat Sink for the Essential Service Water System The ESWS at Wolf Creek draws water from a 6000 acre cooling lake on the Neosho River near the plant and returns it to the lake. The ESWS at Callaway draws water from a retention pond containing over 51 acre feet of water and returns water to the pond via inechanical draft UHS cooling towers. Heat Sink for the Service Water and Circulating Water Systems The 600() acre cooling lake is the normal water source and heat sink for the Wolf Creek Service Water and Circulating Water Systems. At Callaway, this funcuon is perfont.ed by a closed loop for heat rejection to the atmosphere. Makeup to this system is provided from the Missoun River which is five miles from the plant. I O oV 2 1/89

Wolf Creek O 3. SYSTEM INFORMATION This section contains descriptions of sel,ected systems at Wolf Creek in terms of general function, operation, system success enteria, major components, and support system requirements. A summary of major systems at Wolf Creek is presented in Table

31. In the " Report Section" column of this table, a section reference (i.e. 3.1,3.2, etc.)is provided for all systems that are described in this report. An entry of "X" in this colunm means that the system is not described in this report. In the "FSAR Section Reference" column, a cross reference is provided to the section of the Final Safety Analysis Report where additionalinformation on each system can be found. Other sources ofinformation on this plant are identified in the bibliography in Section 5.

Several cooling water systems are identified in Table 31. The functional relationshins that exist among cooling water systems required for safe shutdown are shown in Figure.i 1. Details on the individual cochng water systems are provided in the report sections identified in Table 31. \\ l r \\- i. l 3 12/88 l . ~ ~

i P Tabic 3-1. Summary of Wolf Creek Spfems Omered in this Report { Generic Plant-Specific Report I'SAR Section i System Name System Name Section Reference i Reactor Ifeat Removal Systems i Reactor Coolant System (RCS) Same 3.1 5 - Auxiliary Feedwater(AITV) and Same 3.2 6.5

• l Secondary Steam Relief (SSR) 1 Systems Emergency Core Cooling Systems f

(ECCS) - - Ifigh-Pressure Injection Safety injection System 3.3 6.3 j & Recirculation - Low. pressure Injection Residual IIcat Removal (RIIR) 3.3 - 6.3. 5.4.7 & Recirculation System A o - - Decaylleat Removal (DIIR) RIIR 3.3

6.3,5.4.7

[ System (Eesidual IIcat Removal (RIIR) System)' -, Main Steam and Power Conversion Circulating WaterSystem X 10.4.5 I Systems - OtherIIcat Removal Systems. None identified X Reactor Coolant Inventory Control. Systems Chemicalend Volume Control System 'Same 3.4 9.3.4

• i (CVCS)(Charging System)

.l ECCS See ECCS,above Reference is fmm Reference Safety Analysis Retort 3S, Westinghouse Nuclear Energy Systems. - 10

& ~

. n b ,0....- sa-~,, e.. e - --- -w2, ~ a

= l (.; [ Table 3-1. Summary of Wolf Creek Systems Cmcred in this Report iContinued) Generic ' Plant-Specific Report FSAR Section System Name System Name Section Referenes l Containment Sptems - Containment Same X 6.2.1 ? Containment IIcat Rennval Systems - Containment Spray System Same 3.9 6.2.2.1 l { i -- Containment Fan Cooler System Contaimnent Cooling System 3.9 6.2.2.1 Containment Normal Ventilation Systems See Containment Cooling System. -I above i Ilydmgen Control System X 6.2.5 t i j - Combustible Gas Contml Systems- . Reactor. and Reactivity Control Systems j u l Reactor Core Same X 4* d' - Control Rod System Control Rod Drive Mechanism X 4.2.* f t [ Boration Systems See CVCS,above l l-Instrumentation & Control (I&C) Systems 3 Reactor Protection System (RPS) Reactor Trip System 3.5 7.2 i Engineered Safety Feature Actuation Engineered Safety Ftature System 3.5 7.3. } System (ESFAS) - { -- ' Remote Shutdown System _ Auxiliary Shutdown Control Panels 3.5 7.4.3 [ t Ig

• Reference is from Reference Safety Analysis Retort 3S, Westinghouse Nuclear Energy Systems.

D I k r i h i

c; I Talite 3-1. - Summary.of Wolf Creek Systems Corcreef in tfvis Report (Continuc<f t [ Generie. Piant. Specific Report FSAR Section System Name System Name Section Referent e Instrumentation & Control (I&C) Systems (continued; I - Other I&C Systems Various Systems X 7.6. 7.7 I Support Systems Class 1E Electric Power System Same 3.6 8.2 K.3 1 Non Class IE Electric Power System Same 3.6 8.2.3.3 l Diesel Generator Auxiliary Systems Same 3.6 [ - Component Cooling Water (CCW) Same 3.7 9.2.2 * . System ~ cs - Service Water System (SWS) Same X 9.2. L 1 i -- Other Cooling Water Systems Essential Service Water System X 9.2.1.2 i -. Fire Protection Systems Same X 9.5.1 l . Room Ifeating. Ventilating, and Air-Air Conditioning. IIcating. Cooling X 9.4* Conditioning (HVAC) Systems and Ventilation Systems 't - Instrument and Service AirSystems Coupessed AirSystem X 9.3.1

• f t

- ' Refueling and Spent Fuel Systems Same X

9. l

• I i

- Radioactive Waste Systems Same X 11.0' ( Radiation Protection Systems Same. X 12.0. t m . Reference is from Reference Safety Analysis Retut 3S. Westinghouse Nuclear Energy Systems. j I i s t i

( tx w <x e

• i 2 C

P 05 Q<i f 3 f 3 gn b* o M c OW OO e s <w HI sc U. L h!$ IL db h h o eV xo w L J V J 4 4 O O N m 2 r 3 r m r rm E p om a .- c <W to w M WG JO gg< m n I" WE woo C 8 B E E5 E8d 5 oW o s e5 3 o w a w-c

• h k

( ) ( ) ( ,,/ 4 6 6 JS s u l ( 5 u. l to Eo EAM f ^ C3 y ~~m M M n n a W (f) C W

=00 5

L J L J 4 A E i w<3 w I$ b 6ht o ef t B 1m1 e a u N 7h p l g$. N O

• =

/ \\ 0 gx ) bW 85 Eg 880 sw o 7 12/88

! /D Wolf Creek 1 b 3.1 RI: ACTOR COOLANT SYSTEM (RCS) i 3.1.1 Ss stem Function 'T he RCS transf ers heat from the reactor core to the secondary coolant system via the steam generators. The RCS pressure boundary also establishes a boundary against l the uncontrolled release of radioactive material from the reactor core and primary coolant. 3.1.2 System Definition 'I he RCS includes: (a) the reactor vessel, (b) reactor coolant loops, (c) reactor coolant pumps, (d) the primarv side of the steam generators, (c) pressurizer, and (f) connected piping out to a suitable isolation valve boundary. An isometric drawing of a 4-loop Westinghouse RCS is shown in Figure 3.1 1. A simalified diagram of the RCS and important system interfaces is shown in Figures 3.12 and 3.13. A summary of data on selected RCS components is presented ir Table 3.1 1. 3.1.3 Ssstem Ooeration Dunng power operation, ciret.'ation in the RCS is maintained by one reactor coolant pump in each of the four reactor coo' ant loops. RCS pressure is maintained within l a present>ed band by the combined action of pressurizer heaters a..d pressurizer spray. RCS coolant invento'ry is measured by pressurizer water level which is maintained within a t prescribed band by the chemical and volume contwl system (charging system). At power, core heat is transferred to secondary coolant (feedwater)in the steam generators. The heat transfer path to the ultimate heat sink is completed by the main steam and power conversion system and the circulating water system, p Following a transient or smLil LOCA (if RC$ inventory is maintained), reactor Q core heat is still transferred to secondan coolant in the steam generators. Flow in the RCS is maintained by the reactor coolant pumps or by natural circulation. The heat transfer path to the ultimate heat sink can be established by using the secondary steam relief system (see Section 3.2) to vent main steam to atmosphere when the power conversion and circulating water systems are not available. If reactor core heat removal by this alternate path is not adequate. the RCS pressure will increase and a heat balance will be established in the RCS by venting steam or reactor coolant to the containment through the pressurizer relief valves. There are two power-operated relief valves (each in series with 1. motor operated block valve), and three safety valves on the pressurizer. A continued inability to establish adequate heat transfer to the steam generators will result in a LOCA like condition (i.e. continuing loss of reactor coolant through the pressurizer relief valves). Repeated cycling of these relief valves has resulted in valve failure (i.e. relief vah c stuck open). i Following a large LOCA, reactor core heat is dumped to the containment as reactor ecolant and ECCS makeup water spills from the break. For a short-temi period, the containment can act as a heat sink: however, the containment cooling systems must operate in order to complete a heat transfer path to the ultimate heat sink (see Section 3.9). 3.1.4 System Success Criterin The RCS success criteria can be described in terms of LOCA and transient mitigation, as follows: An unmitigatible LOCA is not initiated. If a mitigatible LOCA is initiated, then LOCA mitigating systems are successful. If a transient is initiated, then either: (A RCS integrity is maintained and transient mitigating systems ire successful, or d RCS integrity is not maintained, leading to a LOCA likt condition (i.e. 8 12/88

Wolf Creek stuck open safety or relief valve, reactor coolant pump seal failure), and LOCA mitigating systems are successful. 3.1.5 Comoonent Information A. RCS 3

1. Total system volume: 12,135 ft, including pressurizer

2. Nominal operating pressure: 2235 psig B. Pressurizer

1. Nomial water volume: 1080 ft3

2. Normal steam volume: 720 ft3 C. Safety Valves (3)

1. Set pressure: 2485 psig

2. Rehef capacity: 420,(XK)lb/hr each D. Power Operated Relief Yalves (3)

1. Design pressure: 2335 psig

2. Relief capacity: 210,(KK)lb/hr each E Steam Generator s

1. Type: Vertical shell and U-Tube

'n

2. hiodel: Westinghouse Model F

\\ V F Pressurizer lleaters

1. Capacity: 1800 kW G. Reactor Coolant Pumps (4)

1. Type: venical. single stage. centrifugal

2. Capacity: 100,600 gpm @ 288 ft head (125 psid) 3.1.6 Suonort Systems and Interfaces A. Motive Power

1. The reactor coolant pumps are supplied from Non Class IE switchgear.

2. Two banks of pressurizer backup heaters can be supplied from the Class 1E power system via 480 VAC buses PG21 and PG22. The supply circuit breakers for these buses are automatically tripped by the load shedder /

sequencer foliowing an SI AS or essential bus undervoltage signal. B. Reactor Coolant Pump Seal Injection Water System The chemical volume and control system supplies seal water to cool the reactor coolant pump shaft seals and to maintain a controlled inleakage of seal water into the RCS. Loss of seal water flow may result in RCS leakage through the pump shaft seals which will resemble a small LOCA. v\\ I 9 12/88

t 1 O Glhi ATOR v 8S M v v ND \\Vf 6 LA N T PUNP Q <?S Od 3 V JJ ( 8 u / J / k-- [' I a Wi g PRE $$URl2(A l RCACTOR i l Figure 3.1 1. Isometric View of a 4 Loop Westinghouse RCS. 10. 12/8S

O I

• If Mi hi hl i.

/ / f. l! ( 9 11il qi$ l p* * & L $ 4i l'444 t M~ i E v gg g sf 'h l!si - r& 11 l! 5 O l! V I j f r olf it It 2 l ' 'l 'l ( ,l 5 it ll h2 &If 411 'I f y l' I 5 2 1 !k l! l! M / s si$ ub 14 cd!$1 t$i tf-t cdj oEl cd i! 'C l! I! C ?! i}T >f $ $ [( -4 8 li' li If 3 g lI { 3 l!

t!

9g 4 s tXl r i !hf [ I Y .t 4 4 'jj;. t 13 12/88- ,,ns re,- ~ ' * =

suopesol guauodusoa 6uimoys maisAs turioo3 Jopeau MaaJ3 it?/A 'C-FC aanSg3 -b 4 I4 b -y =e -p -sp .t e= g -o ~ v v u G ] D u h d-. v.. m.. s 3 e_.. o e --_.v = a q.y m _.~ e- _ ~t -xt V - 'it -t _.T W -_. _o 3_ weses G.es. pg g gg g W $dM) 6 J m.. V a. os. -'.e Eam 2 4 g,,,, y,gg i y, ~ ~ h, w.2..

• • f.,b. ~y r

% "'l,"; ...h U.. o .m + + an* /~% v '-- y-

=-g g-g y-=

g__ .= -y ~ W ,y gm . ~... - . ~ ~ ' 6 - ~ .ve m . f.. ' ['. +[ J8 P4W JBS D p p r r G O ...s.- q.. p u. .v. m. a O O O

h N d _) J Table 3.1-1. Wolf Creek Reactor CoOrant System Data Summary for Selected Components COMPONENT ID COMP. LO C ATIOff POWER SOURCE VOLT A GE I'??, ER SOURCE EMERG. TYPE LOCATIOff LOAD GRP. PZH-H T H-A HTH HC BUS PG21 480 ESfHM1 AC/A PZH411H B HIH HC BUS PG22 480 ESF HM2 AC/B HC-455A TJV HC HC-456A TJV HC HC-P%OA MOV HC MCC18 480 tJELECPHM ACIA HC-d'0000 MOV HC MCC 2B 480 SELECPRM AC/B HH4701A MOV HC MCC1B 480 rJELECPHM AC/A HH E7018 MOV HC MCC1B 480 TJELECPHM AC/A HH E702A MOV HC MCC ZB 480 SELECPRM AC/B HH E702B MOV HC MCC2B 480 SELECPHM AC/B 4 C i' 6 h i E 4

Wo f Creek ( 3.2 Al'XILI ARY FEEDWATER (AFW) SYSTEM AND SECONDARY STEAM RELIEF (SSR) SYSTEM 3.2.1 Ssstem runction 'Ihe AlW system provides a source of feedwater to the steam generators to remove heat from the reactor coolant system (RCS) whem (a) the main feedwater system is not available, and (b) RCS 1ressure is too high to permit heat removal by the residual heat removal (RHR) system. "he SSR system provides a steas.1 vent path from the steam generators to the atmosphere, thereby completing the heat trusfer path to an ultimate heat sint when the main steam and power conversion systems are not available. Together, the AFW and SSR systems constitute an open loop fluld systern that provides for heat transfer from the RCS following transients and small break LOCAs. 3.2.2 System Definition The AFW system consists of two motor-driven pumps and one turbine driven pump. Water is supplied to the AFW pumps from the condensate storage tank (CST). The Essential Service Water System (ESWS)is the backup water source for the AFW pumps. 1 The turbine driven AFW pump can supply all four steam generators. Each motor dnven pump nonnally is aligned to sup? y two steam generators. l The SSR system ine udes five safety valves and one power operated pressure i relief valve on each of'the four main steam lines. Simplified drawings of the AFW and SSR systems are show n in Figures 3.21 and 3.2 2. A summary of data on selected AFW system components is presented in Table 3.2 1. 3.2.3 System Ooeration i Dunng nonnal operation the AFW system is in standby, a id is automatically actuated on either a low low level in any two of four steam generators, a safety injection signal, a loss of both main feedwater pumps, or a loss of offsite and station nonnal auxiliary power. The system can also be manually started from the control room. AFW system success criteria are defined as delivery of 470 gpm to a minimum of two steam generators before they boil dry (about 25 minutest Ordinarily, the AFW system is required to operate for about 2 hours to maintain the reactor at hot standby followed by cooldown of the Reactor Coolant System to aparoximately 350*F and 40U psig. The residual heat removal (RHR) system may then je initiated to continue the cooldown (Ref.1). The turbine driven AFW pump is capable of providing 1145 gpm, which is more than twice the capacity required for AFW system success. This pump is ca 3able of supplying its own cooling and lubrication independently of AC power, but wien AC power is available backup The two motor-driven AF% pumps are provid 3 for oil pressure and water jacket cooling. pumps are capable of providing 575 gpm each.' The CST is the nonnal water source for all AFW pumps. The backup source for motor driven AFW pump A is ESW train A. Motor dnven AFW pump B can be supplied from ESW train B, and the turbine driven AFW pump can be supplied from either ESW train. Motor driven AFW pump A normally su AFW pump B supplies steam generators A and D.pplies steam generators B and C, w Two normally closed valves may be opened manually to allow the motor driven pumps to feed any of the steam generators. The turbine-driven pump can supply all of the steam generators, but only steam generators B and C can supply steam to drive the AFW pump's turbine. O V 14 12/88

l Wolf Creek b 3.2.4 Ssstem Success Crlferla For the decay heat removal function to be successful, both the ARY system and the SSR system must operate successfully. The ARY success criteria are the following (Ref.1): hiakeup to any two steam generators provides adequate decay heat removal i from the Reactor Coolant System. Any one AFW pump can provide adequate flow to supply two steam generators. Either the CST or the ESWS can serve as an adequate water source for the ARY system as follows: ARV Pumns Water Source Turbine driven pump CST or ESWS A or B 1 hiotor driven pump PI A CSTor ESWS A j hiotor driven pump P1B CST or ESWS B j 3.2,5 Comoonent Information A. 510 tor driven ARY pumps P1 A and PIB

1. Rated flow: 575 gpm @ 3200 ft. head (1387 psid)

2. Rated capacity: 100% each (Ref. 2) j

3. Type: Cvntrifugal, horimntal I

B. Turbine driven ARY pump

1. Rated flow: 1145 rpm @ 3450 ft head (1496 psid)

2. Rated capacity: 100W (Ref. 2)

3. Type: Centrifugal. horimntal C. Condensate grade sources

1. hiasimum capacity: 297,500 gallons D. Secondary steam relief valves

1. Five safety valves per main steam line

2. One power operated relief valve per main steam line 3.2.6 Suonort Systems and Interfaces A. Control Signals

1. Automatic

a. The motor driven ARY pumps are automatically actuated based on any one of the following signals:

two out of four low low water level signals in any one steam generator safety injection signal loss of offsia power and station normal auxiliary power .sss of both matn feedwater pumps v

~>

12/88 l

i Wolf Creek

b. The turbine driven AFW pump stans automatically based on any one of the following signals:

two out of four low low water levels in any two of four steam

enerators oss of offsite power and station normal auxiliary power

c. The water source for the AFW pumps is automatically switched to the Essential Service Water System on low pump suction pressure.

2. Remote manual The AFW system can be actuated by remote manual means from the main control room, from the auxiliary shutdown control panels, and locally at the pumps. See Section 3,5 for a discussion of the relationship between the control room and the auxiliary shutdown control panel.

B. Motive power

1. The AFW turbine driven pump is driven by steam from steam gtnerators B and C.

2, The motor operated steam admittance valve (AFW 312) for the turbine. driven AFW pump is a 125 VDC load powered from DC load group B.

3. The AFW motor driven pumps and other motor o?erated valves are Class lE AC loads that can be supplied from the stanciby diesel generators as l

described in Section 3.6. Redundant loads are supplied from separate load groups. O C. Other i

1. Room cooling for the motor driven AFW pumps is provided by the Essential Service Water System (See Section 3.8). The source of room cooling for the turbine driven AFW pump is not known.

2. Lubrication is provided locally for all pumps, 3,2,7 Section M References

1. Rosco, J., "SNUPPS Auxiliary Feedwater System Reliability Study Evaluation," NUREG/CR 2458, S AND812596, Sandia National Laboratories, January 1982.

1 l

2. Wolf Creek FSAR, Section 10.4.9 l

( 4 16 12/88 y 3, 4 c, y ,_r_,,w-

k G 4L 4L 4L 4L U it; 4L 4L 4L I td I 4L 4L 4L i 40 4L e 4L t 4L [ de/ay-@4Lditc7-6o t 4L k .I 4Ll t i,jo+-@4L y oa-@ c h+ j t*rY-6 E-C' Ji C, ); C )i C 21 d, 6 12 5 12 s tAs tA5 d E 126 t25 tp 45 q ~ oj $ =$ i c y E ,e cy cy $= i a l tp t2,= [ ji ie tZi li iti li a- ,= i i-O i oE. i e a [3 C 3 4 It g 2 l O 4.- 4 i c>If sgo 8 sga e OE1 tEs, tZe tki l -6: K 2 s 9 S. h tl* ,g m Di Di Di I t2

• ti =

ti-if- ,4, 9 ,4 ,I. r. i oII cxI i c>Ri c>Il .I cmi c#,i il il 11 11 (o> l DIE 17 12/88 l ,.... = - , -... ~ -. .. ~. -. - -

0 %L kL l %L %L hi 4L i 4L 4L 4L l 4L l~ 41. l 4L r 41 I 4L 4L e 4L S- ,d , 41 th e,. 'e, 4L k,1,4L ko>d,4L h l of f

k-of,t, 4 oe ct A-Y A-6

=k-so = s %Vi a. +f 41-7 C, li C Ji C )i C li j tb tSs tEs tE$ [ r1 Y, 3 t tit tb t%s tb 7 oy {c 7 oy oy q j i .,i .= 2 te t* t: 's -li t rt a t=t* a i d, i h j i i ici l i tt 3 j .z. I .v. e ~ Olf s 's - ',o { h .e 'a oSie . t, .:= I 3 4 54 t 2 S-O o e ew 4 50-w

o__

= 8 5-t y 3 L DI I (1 D! .,s q a t t- ) = 7 s. s s . ~. ~ s. i d j ,i t i ,j! oj .j-Ik I 7 f O l ii l i! I li i ll i SG t X r ,l!!!B r,-% 5 i 18 12/88

Table 3.2-1. Wolf Creek Auxiliary Feedwater System Data Summary for Selected Components t COMPOMENT ID COMP. LOCATION POWER SOURCE YOLTAGE POWER SOURCE EMERG. f TYPE LOCATION LOAD GRP. i AFW MOV AF WVLVC MCC18 460 NLLECPHM AC/A f AF W-30 MOV AFWPPCHSE UCC 4C 480 NGodC AC/U ' l AFW-31. MOV AFWPPGIISE fACC 3C 480 NG03C AC/A AFW-312 MOV TDAFW. OP-fJK02 125 SUDin.t2 DC/2 AFW-32 MOV AlWPPCHSE MCC3G 480 NG03C AC/A AFW-33 MOV AFWPPCHSE MCC 4C 480 NG04C AC/B AFW-34.- MOV AFWPPCHEE FACC4C 480 NG04C AC/B AFW-35 MOV AF WPPCHSE MCC3C 460 NG03C AC/A AFW-36 MOV AFWPPCHSE MCC3C 480 NG03C AC/A AFW-5 MOV AFWVLVD MCC4C 480-NG04C. AC/B AFW-7 MOV AFWVLVA MCC4C 480 NG04C AC/B i M AFW-9 MOV AFWVLVB MCC18 480 NELECPHM AC/A. AFW-CST IK CSTHM [ f AFW-CST TK' CST AFW-FMA MDP-MDAFWA BUS NB01 L 4160 ESFRM1 ACIA AFW-PMB MDP MDAFWB BUS NUO2 4160 ESFHM2 AC/A AFW-IDP TDP TDAFW - l SG-1A SG EC ' i f SG-1B SG EC - SG-1C SG HC lt SG-1D SG HC-l N]. e. u -.,.._..y.

Wolf Creek 3.3 EMERGENCY CORE COOLING SYSTEM (ECrS) 3.3.1 Ss stem Function The LCCS ts an integrated set of subsystems that perfonn emergency coolant injection and recirculation functions to maintain reactor core coolant inventory and adequate decay heat removal following a LOCA. The coolant injection function is performed during a relatively short term period after LOCA initiation, followed by realignment to a recirculation male of operation to maintain long term, post LOCA core cooling. llent from the reactor core is transferred to the containment. The heat transfer path to the ultimate heat sink is completed by the RHR system operating in the recirculation mode and the containment cooling system (see Section 3.9). 3.3.2 System 1)crinition The emergency coolant injection (ECI) function is performed by the following ECCS subsystems: Passive cold leg accumulators Safety injection (SI) system Charging system (CVCS) Residual heat removal (RilR) system The safety in high pressure coolant in,iection (SI) pumps and the centrifugal chargiru pumps perform tection function and RHR pumps perform the ow pressure coolant injection function. The kefueling Water Storage Tank (RWST)is the water source for both the high and low pressure injection systems. Both systems normally are aligned to inject coolant into all four RCS cold legs. the SlS can be aligned to inject into all four hot legs, w hile the RHR system can be aligned to inject into two hot legs. After the injection phase is completed, low pressure recirculation is perfonned by the RHR pumps drawing suction from the containment recirculation sumps and dis:hr %ng into the RCS cold legs. Heat is transferred to the component cooling water system ty the RHR heat exchangers. The RHR pumps can also deliver water to the suctions of the Si pumps and the centrifugal charging pumps for high pressure recirculanon. Long-term core decay heat removal is perfomied by the RHR system and the containment cooling system (see Section 3.9). Simplined drawings of the safety injection system (SIS) are shown in Figures 3.31 and 3.3 2 _ The RHR system is shown in Figures 3,3 3 and 3.3 4. The charging system is described in Section 3.4. Interfaces between the accumulators, the ECCS injection and recirculation subsystems, and the RCS are shown in Section 3.1. A summary of data on selected ECCS components is presented in Table 3.31. 3,3,3 System Ooeration During normal operation, the ECCS is in standby, Following a LOCA, the four cold leg injection accumulators (one for each loop) supply borated water to the RCS as soon as RCS pressure drops below accumulator pressure (approximately 650 psig). A safety injection signal (SIS) automatically starts the centrifugal charging pumps, the safety injection pumps, and the RHR, pumps, and aiigns & centrifugal charging pumps for injection. The centrifugal charg ng pumps inject througn the boron injection tank (BIT) into the four RCS cold legs. The Si and RHR pumps normally inject into the cold legs, but also can be aligned for hot leg injection. All pumps nomially are aligned to take suction on O the RWST. \\ / For small breaks, operator action can be taken to augment the RCS-depressurization by utilizing the secondary steam dump capability and the auxiliary feedwater (AFW) system (i.e., depressurization due to rapid heat transfer from the RCS).. 20 12/88

Wolf Creek [ When the RWST water level drops to a prescribed low level serpoint, the RHR pump 3 are realigned to draw a suction from the containment sumps and deliver water to the RCS. If depressuriration of the RCS proceeds slowlv, high pressure recirculation can be accomphthed by manually aligning the discharge of the RHR pumps to the suction of the centrifugal charging and Si pumpi 3.3.4 System Success Criteria LOCA mitigation requires that both the emergency coolant injection and emergency coolant recirculation functions be accomplished. The ECl success criteria for 1.OCAs are not clear in the FS AR, however, the following is noted: A.365 inch diameter break is the maximum break size for which the normal makeup system can maintain the pressurizer level and the nonnal reactor coolant system pressure of 2250 psia. For a break of this size, one centrifugal charging ) ump is adequate to sustain pressurizer level at an RCS pressure of 2250 psia. 11is break results in a loss of approximately 17.5 lb/sec (127 gpm at 130^F and 2: 50 psia) (Ref.1 ). Fe a small break LOCA the high head portion of the ECCS, together with the act umulators, provide suf0cient core flooding (Ref.1) For a large break LOCA in which the break is in one injection path, three accumulators, one charging pump, one safety injection pump, and one residual heat removal pump provide sufficient core flooding (Ref. 2). p 3,3,5 Comoonent Information A. Safety injection (SI) pumps l A and 1B

1. Rated now: 425 gpm @' 2680 ft head (1162 psid)

2. Rated capacity: 100%

3. Discharge pressure at shutoff head: 3M5 ft (1580 psid)

4. Type: horizontal centrifugal B. Residual heat removal (RIIR) pumps l A and IB

1. Rated flow: 3800 gpm @ 350 ft, head (152 psid)

2. Rated capacity: 10(F7c

3. Type: verticalcentrifugal C. Cold leg injection accumulators (4)

1. Accumulator volume: 1350 ft3

2. Minimum water volume: 850 ft3

3. Normal operating pressure: 650 psig

4. Nominal boric acid concentration: 2000 ppm D. Refueling water storage tank

1. Capacity: 407,000 gallons

2. Design pressure: Atmospheric

3. Minimum boron concentration: 2000 ppm E. RHR heat exchangers 1 A and IB Q

l Design duty: 39.0 x 10 Btu /hr 6 Q .. Type: Shell and U-tube type 21 12/88 i

Wolf Creek Oi 3.3.6 Suonort Systems nnd Interfaces gD A. Control signals

1. Automatic

a. The ECCS injection subsystems are automatically actuated by a safety injection signal (SIS). Conditions initiating an sis trip are:

lew pressurizer pressure Low steam line pressure High cantainment pressure Manual actuation

b. The SlS automaticallyinitiates the following actions:

starts the diesel genervors starts the centrifugal cha ging, SI, and RHR pumps aligns the centrifugal charging pumps for injection via the boron injection task tnps the main feedwater pumps isolates the CYCS letdown line

c. Switchover to the recirculation mode occurs automatically on low-low level in the RWST.

2. Remote manual

a. An SIS signal can be initiated by remote manual means from the main

/ control room.

b. The transition from the injection to the recirculation phase of ECCS operation can be initiated by remote manual means, Remote manual action is required to realign the charging and safety c.

injection pumps for high pressure recirculation. B. Motive Power

1. The ECCS motor driven aumps and motor-operated valves are Class lE AC loads that can be seppliec from the standby diesel generators as described in Section 3.6.

C Other

1. The SI, RHR, and charging pumps and the RHR heat exchangers are cooled by the Component Cooling Water system (See Section 3.7).

2, The SI, RHR and charging pump room coolers are cooled by the Essential Service Water System (See Section 3.8).

3. Lubrication is assumed to be provided locally for the SI, RHR, and charging pumps and motors.

i 3.3.7 Section 3.3. Refereng.g3

1. Wolf Creek FSAR, Sec: ion 6.3,1984,

2. Reference Safety Analysis Report 3S, Westinghouse Nuclear Energy Systems, Section 6.3.3.2.

l 10 U 22 12/88

- _ -.~ I r e o e, : x.. R. . %... - J '::, t,Et ~ .. m.m -m. 1 ..... l... om... .. ~ a~ 4 o . -.go go - H...

u9 g

4..., c,, a. l o = g .en O O

• im:"....H...

6e

%..g,e I

i L_a...z.... a m...m. = c-s.. ~~ I. ...1 g.o ' ,,,_ W , ~..... t ':'J ,~. _4. I I c- "Ei ~u ,,;u, u 'a+W l g m. "E ht t ,w- ..1, . M.. 10 o ~~ r ,2,

1. ..e..,n,

.k# b .~..,.c U +- 4..e f s~c. Z.. '. b.. W. ' *. '. ' O ~~ K.d n-t v.i,1. .. = M t. 0 U ,". +.4o o I i 9,' a, }o..... go a i i R . 4.a.. e* a* s o - H--..n ee, ...g, i CC8-IIII d . M.. .-. c%, ~ TO c4 "e ...e .. m4.A m * '. .r. .'Old , j*.bi. 70 CC, F1K a i _. Ph.C,ne. t Figure 3.31. Wolf Creek Safety injection System 23' 12/88-

l l i .e-a, .s.- a . ~a s-; e:4 a, a q eg et u:n e t., eg eg a u, t f A A 1 H t2 3 : 1l,. I : tI! t i

t.. !

t <., A e L 4 j ! OI.f t ! OIf w j i. 1 2- }J. 4. id.: y., l., fi,^ *g,. lgi fd,- j i J 1 t., g. j E _ t,i, g fi.' g q.t{.t.,j: td : i i gi i i i i i

• b d

a ,e 'e 33- ,I. ,e g$..) 1-3 s! a,e l, I .c ,I. jej f-l gf las dj 1 l .a C O j !f l C.L i f 2 3 i. o 1 i ol.i oi of? i i ca o C i a I I I a I i i x c = i i. i = .e I . i a ? .x u __ y _. l y r ~ _a .- i o n. s w-s-[1-l. el l y 2 -C t .x. i i o e n W a = -. 9, m i i o i ai ov: x o*;/3 -A-v j os,;a .e e .g 1 O } 3 1 I __o

• e 3:

,u Es is qs: v3 e s <3 tls 2 va 17 ; 2 n n - i= l o l_ 1 o,1 ;: i n-o,j oI[ oXi oVi ox; /e; 0I.2 '.jl .i /. 010 { __g i. i. it-i {c ;,)_ i 1.- ia _. - _jy. _ _ __ _ _ _. _ m a i a L'- 4 ,.A-h $ ~ h2k 0 0 0

,_-_._,...-._._..,,___._._m. _..-.m- ._._._,-.m........_-..... ...m. m. .s._.---......_-~.,-y..._,.. . f. ..? IE ji! Ili Ili E!! thi th! thi thf thi thi til tz: thi t$! fit tjl tzi tf til f$ tXI tja t$1tXIt$it$1 l!! li l lI il 11 l! lI lI a d! s! L 4 y __g p uy t}i tf! til t21 i ,_j - Il, ec-f i 5 :: ql l cI,l aj_i <c : w f" 9 I! Ifi l3 = l 2 v, e 9, s m., i t s%! s'! { bl )! a n tzt txt [ e oxl ~ OKj, %[j Ci[ g. OK! OK 4 a _7_ili Ili. il .,i h. 4 k,i @$ t; u 0 cecElox'i ox5 oX'I cdioxici[! = i o4 xx 25 12/88

ili thi tk tI tI tI ffl '~ t?! ife thi t$s! the tfl til tf ts[ ff ti:(- ffs. i l di thi tfl li P ,ii il lI il j! il lI n! l 1 r 3.y l od OI!- Ok I g = l' i l i "D .t. <a=== t$ litI r E 4 i, al iI;g) 8 s t 9 ii j' =:O v--- y' i g - [d. t2l O + o t Y, t1 t l-e g C OIf.,id'i i. f tC[t r&K! O i i j ..-.g_,__ o x. ~ ~ e-A e 5 g hr i ,i] _ _ g. 2 i E = i 7 Og 3., C, La s i e _i8 s a: 1 2b"! ST[ 5 ~ j g (\\)g 9 %3 13 g gg-( [,,jj [ l g Aq tk 1 i a y l = t MN Q J( 7[! Ol! i t 3 i 1 ~ 1 9 l O l O h t 1 1 fa e l4 11 tg. ,,'lli e et, ej 81 5 tu e ts y 9 s t - lh-ll p 3 g 31

)

h s_ >h!dl OI! oKi ql >XioXl 31l g Q j 4 I I -l I-EEi- [ ak I E ~. E 'f j t 26 12/88

v u Table 3.3-1. Wolf Creck Emergency Core Cooling System Data Summary for Selected Components i COMPONENT ID COMP. LOCATION POWER SOURCE VO LT A GE POWER' SOURCE EMERG. TYPE LOCATION LOAD GRP. HH-8716A MOV HHHHXA MCC1B 480 NELECPRM AC/A. HH-8716B MOV HHHHXB MCC2B 480 SELECPHM AC/B HH-8804A MOV HHHHXA IGCC 3C 480 NGC3C AC/A HH-88048 MOV SIB MCC 2A 480 ESiRM2 AC/B HH-8811 A MOV HC MCC1B 480 NELECPRM AC/A RH-88118 MOV HC. MCC2B 480 SELECPRM AC/B HH-HX1A HX HHHHXA ~ j HH-HX1B HX HHHHXB HH-P1d MDP HHHA BUS NB01 4160 ESFRM1 AC/A HH-P1B MDP - RHHB BUS NB02 4160 ESFHM2 AC/B S;-2802A MOV NPLNRM MCC 18 - 480 NELECPRM AC/A O Si-8002B MOV SPENRM MCC2B 480 SELECPRM AC/B 8:-8806A MOV-SIA. MCC1A 480 ESFRM1 AC/A ' Si-8806B MOV SIB MCC 2A 480 ESFRM2 AC/B i. I SI-8807A MOV StA MCC1A 480 ESFRM1 AC/A SI-88078 MOV. SIA MCC 2A 480 ESFRM2 AC/B SI-8821A MOV SIA MCC 1 A 480 ESFRM1 AC/A Si-Ba21/ MOV S!A MCC1A 480 ESFRM1 AC/A - SI-8321b MOV SIB MCC 2A 480 ESFRM2 AC/8 - SI-88218 MOV SIB MCC 2A 480 ESFHM2 AC/B. SI-8835 MOV SPENRM MCC2B 480 SELECPRM AC/B SI-8923A MOV SIA MCC 1 A 480 ESFHM1 AC/A SI-89238 MOV SIB MCC 2A 480 ESFHM2 AC/B y SI-8924 MOV SIA MCC 2A 480 ESFRM2 AC/B St-P1 A. MDP SIA BUS NB01 - 4160 ESFHM1 AC/A SI-P1B MDP SIB BUS NB02.- 4160 ESF RM2 AC/B I I' l t, ~ u - y m. p ..._._..,-y._ r , ~

Wolf Creek 3.4 CllARGING SYSTEM 3.4.1 System Function The charging system is part of the Chemical and Volume Control System' r 'CYCS) and the Emergency Core Cooling System (ECCS). The CVCS is responsible for maintaining the proper water inventory in the Reactor Coolant System and maintaining water purity and the proper concentration of neutron absorbing and corrosion inhibiting chemicals in the reactor coolant. The normal makeup function of the CVCS is required to ,l maintain the plant in a long-term hot shutdown condition following a transient. As part of the ECCS, the charging system performs high pressure emergency coolant injection and recirculation functions to maintain reactor coolant inventory and' adequate decay heat removal following a LOCA. 3.4.2 System Definition - The CVCS consist 3 of several subsystems: the charging, letdown, seal. water collection system, the reactor coolant puri0 cation and chemistry control system, the reactor makeup control system, and the baron thermal regeneration system. The CVCS includes the following: three charging pumps (one positive displacement and two centrifugal pumps) three independent charging now paths to the RCS (normal charging reactor-coolant pump seal injection end boron injection tank paths) two letdown flow paths from the RCS (normal and excess letdown paths). two borated water sources for the charging pumps (volume control tank and refueling water storage tank) s various demineralizers, filters, and.other subsystems -for maintaining coolant purity, pH, and chemical concentration Simplified drawings of the CVCS, focusing on the charging portion of the system, are shown in Figures 3.41 and 3,4-2. A summary of data on selected CVCS 3 components is presented in Table 3 A.I. 1 3.4,3 Svstem Oneration During normal operation, CVCS letdown flow is 75 gpm and the positive - displacement charging pump is operating to provide RCS makeup. Pump speed is-controlled to maintain pressurizer level in the prescribed range.During normal operation with maximum purification, letdown flow is 120 gpm, and makeup is provided by one centrifugal charging pump. Charging flow is modulated by flow control valve 121 to maintain pressurizer level in the prescribed range. The letdown flow from the reactor _ coolant system is cooled by the regenerative heat exchanger and the letdown heat exchanger, and pressure is reduced along the letdown flow; path to the mixed bed - demineralizer. Boron concentration is adjusted before the letdown flow is directed to the-Volume Control Tank (VCT). All charging pump; normally are aligned to take suction on the VCT, The charging pamps are aligned to take a suction on the Refueling. Water Storage Tank (RWST) when the VCT water level cannot be adequately maintained or when a Safety Injection Signal (SIS) is present. When an SIS occurs, normal operation of the CVCS is terminated (letdown line is isolated) and makeup to the RCS is provided by both centrifugal charging pumps injecting via the boron injection tank into all four RCS colo 3 legs. When needed, an ECCS high pressure recirculation flow path can be established with the RHR pumps taking a suctica on the containment sumps and delivering water to the suctions of the cenMf+1 charging pumps for makeup to the RCS.~ See Section 3,3 for a further discussic,n of the ECCE 28 1238

t Wolf Crcek - ,C 3.4.4 Svstem Success Criteria

1. The charging system can maintain pressurizer level at the normal operating level and pressure for an RCS equivalent pipe break opening up to 3/8 inch (0.375 in, liquid senice) or 3/4 inch -(0.75 in,- steam sen' ice) (Ref,1.

Section 9,3.4.2). The charging system is capable of making up for leakoff from such small breaks (up to approximately 120 gpm) with one centrifagal' 1 charging pump while still maintaining sealinjection flow to the reactor coolant pumps, ar.d allowing for a mimmum of reactor coolant contraction during cooldown. This is accomplished with the CVCS letdown line isolated (Ref.1, Section 9.3.4.3). i

2. Post shutdown boration of the reactor coolant can be accomplished with any

. one charging pump taking a suction on the RWST and injecting via any one of the following mdependent flow paths: .the normal charging line via the regenerative heat exchanger to RCS-loops 1 and 4 the reactor coolani pump seal injection lines the boron injection tank to all four RCS cold legs. 3,4,5 Comoon ent - Information A. Centrifugal Charging Pumps l A and IB

l. Rated flow: 150 gpm @ 5800 ft head (2514 psid)

2. Rated capacity: 100 %

3. Discharge pressure at shutoff headi 6200 ft ~

B. Positive Displacement Charging Pump

1. Rated flow: 98 gpm -

2. Design head: 5800 ft head (2514 psid)

C. Refueling Water Storage Tank

1. Volume: 407,000 gallons

2. Design pressure: atmospheric

3. Minimum boron concentration:- 2000 ppm D.' Volume Control Tank 1, ' Volume: 400 ft3 (est)

2. Design pressure: 75 psig E. Boron Injection Tank

1. Volume: 900 gallons

2. Design pressure: 2735 psig L

3. Minimum boron concentration: 20,000 ppm l

3,4,6. Suonort Systems and Interfaces. .i A. Control Signals n -1. Automatic

a. The reactor makeup control system avoma !cally maintains reactor coolant boron concentration and volume conuel tank (VCT) level.

b. Low level in the VCT initiates makeup with re tetor makeup water and boric acid.-

i 29 12/88 L .,. u.. a. ..=. .. = = - - =-

Wolf Creek (

c. A low low level from both VCT level channels transfers the suction of

\\ the '.harging pumps to the RWST and closes the VCT outlet isolation

vilves,

d. A safety injection signal (SIS) automatically initiates the following actions in the charging system:

starts the centrifugal charging pumps aligns the centrifugal charging pumps for injection via the bcron injection tank isolates the letdown line

2. Remote Manual The charging pumps and power-operated valves can be actuated by remote

. tans from the control room. B. Motive Power

1. The centrifugal charging pumps and motor operated valves associated with

.ae ECCS function are Class IE AC loads that can be supplied from the standby diesel generators as described in Section 3.6.

2. The positive displacement charging pump power source is not known, but it appears to be powered from a non-Class lE source.

C. O'ber

1. The centrifugal charging jumps are ' cooled by essential loops of the Component Cooling Water System (CCWS) and the positive displaceme nt chargmg pump is cooled by the nonessentialloop of the CCWS (see Sectian O

3.7), C/

2. Charging pump room cooling in provided by the Essential Service Water System (ESWS, see Section 3.8).

3. Pump lubrication is assumed to be provided locally, at the pumps.

3.4,7 Section 3.4 References 1 Wolf Creek FSAR. Section 9.3.4 m(J ) 30 12/88

..-a e ~ a.

una,

. sa.w._ u a O !!! ii! l ii! >ck!edi edi thithithithi f, 8El gr Eoeo E s;!r M~ 'l a li! 5 'i - i 6 ~ E oKai oXai ct'!

c. !

' ~ 1 n l l 75 a.18! 'iI ^LJa Zi es-O E e n g m

1. !I 3

O 93 $l 5 ace t ear a 8 n aU o. 4# s -g ry e s I 9 f - W O I

• l *E W

== -0,< X X-8l8 it o 5 c og. 3 ~I 3 ex; 1 3 6 4 s. .i l E,.I fa fi

llI f l.

si stia e -!!!j -. I t- . 2 1;r; _a a a o B-5 oK.s OK.s. y SXi SX! oEi [ [ SVi Xi = = il si-El li il si si d.i d;. ofi.-

ox! di da d.i:

oK i. X O qa yi lini Ill 31 .12/88

ri! ej;i i e!r-i ji r!g Vji i 3m; sg 3 e.g e e_; h h 1 h h eoE! s eIt roI,! ff s t, ! i g A> s III

by %,

f ji! 1 i h ,i . olti oIBi E ili e ai = s OE! I 3 I Oa 6: E ll e ~ 8 j _k O Q = 10y - -r-g ll EE! $j- .. B ] I gg Ele 2 t i m E I i 2 s 4, _.A g e 2 e i 9 I-s 2 v en -y x w . g,e s 3 ~ o r-a e ' S,M,! g. K .t 2 g - 2,,! g m. l 5 5 i t ((

u ti 12 5

l;i fE!'

b a

p H

=

• !;i -f,

-= N. i N.i D o f _)'B na-u- e Je b5

t. ::

oKi 011 W i i. i s2; s y-i n i 5 a e J,, I g g -d: 7-k E O t; B y e I ! !l _ El I-I ! .!l El I! I2! 3 - li

di. i op - di ob

.i d,,! cVi D a 8 i I I i il { \\ 8 v t. i o "A t z I } ilj [

l!!l I

i 32 12/88 l_

Table 3.4-1. Wolf Creek Charging System Data Summary for Selected ucmponents COMPONENT ID COMP. LOCATION POWER SOURCE VO LT AG E POWER SOURCE EMERG. TYPE LOOATION LOAD GRP. CCP-112D MOV CCPA MCC1A 480 ESF ItM1 AC/A CCP-112E MOV CCPB MCC 2A 480 EST flM2 AC/B CCP-8801A "MOV NPENRM MCC1B 480 TJELECPRM AC/A CCP-8801 B MOV NPLNFIM MCC4C 480 NG04C AC/B CCP-8803A MOV BIIRM MCC18 480 NELECPflM AC/A CCP-88038 MOV BIIRM MCC4C 480 NG04C AC/8 GCP-Bil TK BliRM - CCP-P1 A MDP CCPA BUS NB01 4160 ESFHM1 AC/A MDP CCPB BUS NB02 4160 ESFilM2 AC/B CCP P1B - l l is sa .-~

o l Wolf Creek \\ 3.5 INSTRUMENTATION AND CONTROL (1 & C) SYSTEMS 3.5.1 System Function The instrumentation and control systems consist of the Reactor Protection System (RPS), the Engineered Safety Features Actuation System (ESFAS), and systems for the display of plant information to the operate:s. The RPS and ESFAS monitor the reactor plant, and alert 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. The ESFAS will automatically actuate selected safety systems based on the specific limits or combinations of - limits that are exceeded. A remote shaidown capability is provided to ensu e that the reactor can be placed in a safe condition in the event that the main control room must be evacuated. 3.5.2 System Definition The.RPS includes sensor and transnutter units, logic units, and output trip - relays that operate reactor trip circuit breakers to cause a reactor scram. The ESFAS includes independent sensor and transmitter units, logic units and relays that interface with the control circuits for the many different sets of components titat can be actuated by the ESFAS. Operator instrumentation display systems consist of display anels in the control room and other locations that are powered by the 120 VAC electric power system (see Section 3.6). Instrumentation and controls for hot shutdown from outside the control room are located in the Auxiliary Building on the Auxiliary Shutdown Control Panels (ASDCPs). h 3.5.3 System Ooeration v A. RPS The Westinghouse RPS (or Reactor Trip System,. RTS) has two to four-redundant input instrument channels for each sensed parameter and two output actuation trains (A and B). The A and B logic trains mdependently generate a reactor trip command when prescribed parameters are outside the safe operating - range. Either RPS train is capable of opening a separate and independent reactor trip circuit breaker to cause a scram. The manual scram A and B circuits - bypass the RPS logic trains and send a reactor trip command directly_to shunt trip circuitry in the reactor trip circuit breakers. B. ESFAS The ESFAS -has three or four input instrument ektnnels for each ~ sensed parameter, and two output actuation trains-(A and B)J In general, each train controls equipment powered from different Class 1E AC electrical buses.- An individual component usually receives an actuation signal from only one ESFAS train. The ESFAS generates the following signals:--(1) reactor trip, provided one has not already been generated by the RPS, (2) safety injection - signal (SIS), (3) containment isolation, (4) main steam line isolation, (5) main feedwater line isolation, (6) emergency diesel start, (7) containment spray actuation, and (8) ventilation systems for the auxiliary building, control room, - and diesel building. The control room operators can manually trip the various ESFAS logic subsystems. Details regarding ESFAS -actuation logic are included in the system description for the actuated system. C. Remote Shutdown There are two distinct auxiliary shutdown panels; one panel is associated with instrumentation and control circuits used for controlling safe shutdown 34 12/88:

,1 j i I WolfCreek i equipment in Train A,'and the other panelis associated with instrumentation and s' control circuits used for controlling safe shutdown equipment in Train B. Both - panels are electrically separated and are associated wit:1 the same safety grade circuits that serve their respective trains; Train A control can be accomplished from either the auxiliary shutdown control panel or the control room without the use of a transfer switch; the equipment responds to the last signal from either location. Switches are provided on the Train B ASDCP to isolate and remove control from the control room for the Train B safe shutdown equipment necessary to take the plant to and maintain the alant in a safe hot shutdown condition independent of the control room. Not a 1 components on panel B can be isolated in this manner, Transfer of control to the Train B shutdown panel is alarmed in the control room. The electrical power that supplies al: of the devices controlled from these panels is avallaale following a loss of offsite - power. De controls on the auxiliary shutdown panels provide the capabilities _ of achieving and maintaining hot shutdown when the control room is - inaccessible. The controls provide a means of sustainin; the capabilities for boration, supplying steam generator feedwater and R TR, and. continuing ) reactor coolant pump seal injection and/or thermal barrier cooling water flow. Cold shutdown conditions can also be met outside the cc'itrol room with some temporary instrumentation and control modifications, it should be noted that - for the AFW valves, only valve 5 is included in auxiliary shutdown-control-panel B. Controls available in the ASDCPs are identified in Table 3.51, 3.5,4 System Success criteria O A. RPS The RPS uses hindrance logic (normal = 1, trip =;0) in both the input and output-- logic. Therefore, a channel will be in a trip state when input signals are lost, when control power is lost, or when the channel is temporarily removed from senice for testing or maintenance (i.e. the channel has a fail safe failure mode). A reactor scram will occur upon loss of control power tc, the RPS. A reactor scram usually is implemented by the scram circuit breakers which must open in response to'a scram signal. Typically, there are two series scram circuit breakers in the power path to the scram rods,. In this case, one of two circuit - breakers must open. Details of the scram system for Wolf Creek have not been determined. B. ESFAS - A single component usually receives a signal from only one ESFAS output train. ESFAS Trains A and B must be available Jn order to automatically actuate - their respective components. ESFAS typically uses hindrance input logic (normal = 1, trip = 0) and transmission output. logic >(normal _= 0, trip = 1). In this case, an input channel will be in a trip state when input signals are lost, when control power is lost, or when the channel is temporarily removed from: F service for testing or maintenance (i.e. the channel has a fail safe failure mode).- Control power is needed for the ESFAS output channels to send an actuation signal. Note that there may be some ESFAS actuation subsystems that utilize hindrance output logic. For these subsystems, loss of control power will cause system or component actuation, as is the-case with the RPS. Details of the ESFAS system for Wolf Creek have not been determined. 1 C. Manuallv. Initiated Protective Actions When re'asonable time is available, certain protective actions may be performed-manually by plant personnel. The control room operators are capable of 35 12/88 -i

Wolf Creek O' d operating individual components using normal control circuitry, or operating groups of components by manually tripping the RPS or an ESFAS subsystem, The control room operators also may send qualified persons into the plant to operate components locally or from some other remote control location (i.e., the remote shutdown panel or a motor control center). To make these judgments, data on key plant parameters must be available to the operators. 3,5,5 Suonort Systems and Interfaces A. Control Power

1. RPS The RPS input instrument channels are powered from the 120 VAC instrument buses (see Section 3.6). It is assumed that the RPS A and B output logic trains are powered from separa'e 125 VDC distribution panels.

2. ESFAS The ESFAS input instrument channels are powered from 120 VAC instrument buses, it is assumed that the ESFAS A and B output logic trains are powered from separate 125 VDC distribution panels.

3. OperatorInstrumentation Operator instrumentation displays are powered from the 120 VAC instrument buses.

3.5.6 Section M References

1. Wolf Creek FSAR, Section 7.4.

b oV 36 12/88

/% ( I Table 3.51. Wolf Creek Auxiliary Shutdown Panel Controls, u./ The following remote controls are available on the Auxiliary Shutdown Panel: START /STOP control for each motor-driven auxiliary feedwater pump (1) (4) (5) START /STOP controls for the turbine driven auxiliary feedwater pump (steam supply and trip and throttle valve controls)(4) (5) hiANU AL control for all auxiliary feedwater flow control valves (2) (4) OPEN/CLOSE control for essential service water to the auxillary feedwater pump suction valves and condensate storage tank to the auxiliary feedwater pump suction valves (1) (4)(5) Auxiliary feedwater pump turbine speed control (2) (4) AUTOhl ATIC/h1 ANUAL control for each power-operated atmospheric dump valve (2) (4) -ON!OFF/Al'TO control for two pressurizer backup heater groups (3) (5) OPEN/CLOSE control for the containment isolation valves in the letdown line (1)( O (5) U Note:

1. Train A paralleled with the control switch in the control room (control can be accomplished from either location without use of a transfer switch; the equipment responds to the last command from either location)

2. Transfer of the control circuit with switch at the auxiliary shutdown panel is provided for the analog instrument controlloop.

3. " AUTO" mode is not operable after transfer.

4. Essential monitoring indicator or control.

5. Train B controls in the main-control room ban be isolated from the auxiliary shutdown panel controls. Control is transferred through a transfer switch

'ocated at the auxiliary shutdown panel. i t \\ () 37 12/88

Wolf Creek C\\ ' \\ 3.6 ELECTRIC POWER SYSTEM w 3.6.1 Svstem Function The electric power system supplies power to various equipment and systems needed for normal operation and/or response to accidents. The onsite Class 1E 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 or when the nomial electric power sources are not available. 3.6.2 Ssstem Definition The onsite Class lE electric power system consists of two AC load groups. Diesel generator A is connected to 4160 VAC bus NBCl, and diesel generator B is connected to 4160 VAC bus NB02. There are four emergency 480 VAC buses designated buses NG01, NG02, NG03, and NG04. Buses NG01 and NG03 are connected to bus NB01 throuch transfomlers XNG01 and XNG03. Buses NG02 and NG04 are connected to bus NB05 through transformers XNG02 and XNG04, 480 VAC motor control centers NG01 A, NG01B, and NG0lT receive their power from bus NG01,480 VAC motor control centers NG02A, NG02B, and NG02T receive their power from bus NG02,480 VAC motor control centers NG03C, NG03D, and NG03T receive their power from bus NG03, and 480 VAC motor control centers NG04C, NG04D, and NG04T receive their power from bus NG04 Emergency power for vital instrumentation, control, and emergency lighting is supplied by four 125 VDC/120 VAC load groups. Four station batteries energize four DC distribution panels, designated NK01, NK02, NK03, and NK04. Four 120 VAC p instrument panels (NN01, NN02, NNO3, and NN04) are supplied from the DC l (d distribution panels through inverters, or, as a backup, from 480 VAC MCC NG01 A or MCC NG02A through transformers. Simplified one-line diagrams of the electric power system are shown in Figures 3.6-1 and 3.6-2. Simplified one line diagrams of the 125 VDC and 120 VAC electri: Power systems are shown in Figures 3.6 3 and 3.6-4. A summary of data on selected electric power system components is presented in Table 3.61, 3.6.3 System Ooeration l During normal operation, the Class 1E electric power system is supplied from two independent sources within the power block: 13.8 kV bus PA01 and bus PA02. The emergency sources of AC power are the diesel generato.. The transfer from the preferred power source to the diesel generators is accomplished automatically by opening the normal source :ircuit breakers and then reenergizing the Class 1E portion of the electric power system from the diesel generators. The DC power system normally is supplied through the battery chargers, with the batteries " floating" on the system, maintaining a full charge. Upon loss of AC power, the entire DC load draws from the batteries. The batteries are sized to supply power to design loads for up to 6 hours without recharging (Ref.1). The 120 VAC vital buses normally receive power from the DC buses through their respective inverters. Redundant safeguards equipment such as motor driven pumps and motor operated valves are supplied by different VAC buses. For the purpose of discussion, this equipment has been grouped into " load groups". Load group AC/A contains components powered either directly or indirectly from 4160 bus NB01. Load group AC/B contains components powered either directly or indirectly from 4160 bus NB02. Componems O receiving DC power are assigned to load groups DC/1, DC/2, DC/3, or DC/4, based on the Ny battery power source. 38 12/88

j g Wolf Creek ( 3.6.4 Svstem Success Criterin Basic system success criteria for mitigating transients and loss of coolant accidents are defined by front line systems,.which then create demands on support - systems. Electric power system success criteria are defm' ed as_ follows, without taking credit for cross ties that may exist between independent load groups: 1 Each Class IE DC ioad group is supplied initially from its respective battery. (also needed for diesel starting) i - Each Class IE AC load group is isolated from the non Class IE system and is j supplied from its respective emergency power source (i.e. diesel generator) Power distribution paths to essennal loads are intact Power to the battery chargers is restored before the batteries are exhausted 3.6.5 Comnonent Informction A, Standby diesel generators (2)

1. Maximum continuous rating: '6201 kW

2. 168 hour rating: 6821 kW

3. Rated voltage: 4160 VAC

4. Manufacturer: Unknown B. Batteries (2)

1. Rated voltage: 125 VDC

2. Rating with design load: 6 hours per battery h

3.6.6 Suncort Systems and Interfaces A. Control Signals

1. Automatic The standby diesel generators are automatically started based on:

Undervoltan on the nonnal bus,' loss of offsite power (LOSPW) Safety injection actuation signal (SIAS)

2. Remote manual The diesel generators can be started, and many distribution circuit breakers -

can be operated, from the main control room or the diesel generator room at their local control panels B. Diese! Generator Auxiliary Systems

1. Diesel Cooling Water System i

Heat from both diesel generators is transferred from a jacket water system to the Essential Service Water System (ESWS, see Section 3.8). i

2. Diesel Starting System Each diesel has an independent air starting system.

3. Diesel Fuel Oil Transfer and Storage System Fuel for each diesel is supplied from an independent " day tank" which' contains enough fuel for 1.5 hours of diesel generator operation. ' Each day tank can be replenished from a storage. tank during engine operation. The capacity of each storage tank is based on the fuel consumption by one diesel engine for operation at continuous rating for seven days. Each storage tank O

is located underground. D

4. Diesel Lubrication System Each diesel generator has its own lubrication system.

39 12/88 L ~. ... ~

Wolf Creek

5. Diesel Room Ventilation System This system consists of supply and exhaust fans which maintain the environmental conditions in the diesel room within limits for which the diesel generator and switchgear have been qualified. This system may be needed for long-term operation of the diesel generator, C. Switchgear and Battery Room Ventilation System Details on systems providing switchgear and battery room ventilation have not been identified. These systems may be needed for the long term operation of the electric power system.

3.6.7 Section 3.6 References

1. Wolf Creek FSAR Sections 8.3, 9.4, 9.5.

bG 40 12/88

aW. l To a se sa WAN SWITCtWAftD rev ma f.w! tf ev Affrs (2 PK r(AT(#1 ,L e.;w,vr 4,y gng) .r h ' sE w MANTi(AN r pW Ast1 A X r ^,;- % ^,X $[ XY = "$7 FuAft? ym v., I Ir ir is 918 8tV la FS Pact 13 a *V fBIS PAG 7 wj.w II !#4 'O 8'Y F3 %d 'S #fV s ~- r sr mAu n, m JtW? paggog [G A Or: 8 CSS ji Cat gg 4190 VAC Btf3 N9of 4:40 VAC EW35 fWtu I I 1I 11 Id t 1B a wvaso y . e uvaso v tt 4 xvaso y gy YFIAN XPG21 M TNGot TRAN RMM e uvasoy a wvenso v

== == == == = cx

== Tsvut rWM . wy, y trapt OGtxt Traps esm --c il a-11 15 12 in 4.o vAc sus ecz, q, ve sus e, vAc us. ...C ous. . Ac,,us. .,,, vAc P2R BACXtP HTRS l i ll il 11 IE IB 18 F28% BACRt.P 84TRS 15 II 13 11 3r 1r l l i I a te en cn taOC1A 1aCC 17 aKC sa amCG 3C 48CC 37 gr'C 30 a80C 4D taCC 47 tace 4C trOC 79 nsCX 77 aar C 7A Figure 3.6-1. Wolf Creek 4160 VAC and 480 VAC Electric Power Distribution System

m .m - o f try r se es e s, w eenes iwen savce + ertt, won r, weit,um CFNFRAH64 iL ,i p m.- emnne mass I masAc3 4 4 w8' ' TIE" xmm "N5T n - ~- vaane? wt* ww I ie Ir g 1<,m....... 1,.__ t.._ f TJ 1TWs isrTRAM m,e NWQ yogRpg r 1 OGA DG8 .5,... i..... Cse 11, 087 ? qg 4seo WAC SL5 N509 etto WAC 9tn NROP A tO I l 1l~ ll il .Il Il 11 4 stvasao y 4 avumo y a sneeso w - i . TRAM 3PC79 ;. TIMf6 NPG01 TRAM NNG05 . 4 are480 w a snpano y a swege v ~ TSMM NNGee TRAMENQo2 TRAM NPG27 .I N m" ', N N _ NN . Nm 'NN. 'Nm 1 W ll 11s. l 11 11 1R . Il de0 VAC BLS PG75 4eo WAC SUS NGot eto VAC SUS NGO3 400 VAC fpJs 900s ano VAC Stp5 perjor eso vaC St25 P922

P1RSACatLP HTR$

~ l.. P7R BACatuP offR$ i

ll-

'llis 'f tl ll <ll( ll ~ll

ll 11~

Il 11' ll i. v. = i l ~ 1 eaCC lA ascC T adCC 18 8800 3G eacc $7 6er4 3D aer4 40 eacC 47 esCC aC tacC 29 escC 27 14 2A { l NELECPRm l 8808 3C NE t t CPMW DG4 003 SELECPRdB seG6eC l SyggcPam l ] DCTE LesES taAv NOT RIPRESFNT TTUT CA9tf ROtfflNG BETWEf M Rricams ~ Figure 3.6-2. Wolf Creek 4160 VAC and 480 VAC Electric Power Distribution System Showing Component Locations 1 1 4 4

._.._...__,_.___..._.._...m. _m_ s .6 t 't 1 480 VAC BLIS HG01 480 VAC BltS t*103 4N) V AC i48 IS tK/$4 din VrC Utri ttW I l ll "11 '15 II IB-11 480 VAC MCC 1 A 480 VAC MCC ?A IB II d l BC 21 BC 23 BC 24 BC 22 l BT-11 BT-13 - BT,14 BT-12 Z sz Z sz Z sz Z sz

i 1'

j l 101 1'02 301 302 401' 402 201 202 I ( A Ua i 125 VOC PANEL .125 VOC PANEL - 125 VDC PANEL ]'. 125 VDC PANEL j (OP NK01) (DP NK03) (DP NK04) - (DP-NK02) 1 i 'l 111 311 431 211 . 4 son 2ev 4 eon 2cv i .TRAN. TR W XNN05 XNN06 [ MM INV 11 iPN 13' INV 14 MM INV 12 f ' f j [ ] - - - - -11 . i l- - - - - l l II----ll [ ]-. - - - - El s I' 120 VAC PANEL-120 VAC PANEL 120 VAC PANEL 120 VAC PANEL n. tJ (%NN01) (PNL-NNO3)

(PN'. NNO4)

(PNL-NNO2) s 's m L1 4 i . Figure 3.6-3.- Wolf Creek 125 VDC and 120 VAC Electric Power Distribution System i 1 1

,.n.- [ l E. S F H M t l l E st nu2 480 VAC Ot)S NGO1 4HOVAC H171NGO3 l 4M VV 8tritrend 4% V AC Ht F, PFW I I I 11 If II IR 1R AN VAC MCC 2A 480 VAC MCC 1 A I { ( II-1 BATRM1 BATPM3 D Ainue BATRM2 B T-18 Hl.13 HT 14 OT.32 2 2 2 2 2 I i 101 102 301 302 401 402 201 202 2 I I I I I I i 125 VDC PANTL 125 VDC PANEL 125 VDC PANEt 125 VDC PANI t. (DP NM01) (DP NK03) (DP NK04) (DP NM02) til 311 411 211 4A0/120V 480/120V ' IRAN-TilAN - XNN06 XNN05 MM ~/ NV 11. ~ NV 13 NV14 MN ~ NV 12 [% l I J- - - - -Il (1----il II----II t}----II 120 VAC PANEL 120 VAC l'ANE L 120 VAC PANEL 120 VAC PMd L (PNL41N01) (FWL NNO3) (PNL NN04) (FWL NN02) SUDRM4 l l SBDPM2 l l SBDRMt l l SBDRM3 l l _ cn NOTE: t NES uAY NOT III!Uf SE N T THUE CAIR E nOUltNG BF.IWf f M ROOMS Figure 3.6-4. Wolf Creek 125 VDC and 120 VAC Electric Power Distribution System Showing Component Locations

b o x Table 3.6-1. Wolf Creek Electric Power System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. . TYPE LOCATION LOAD GRP._ BC-21 BC SBORM1 BUS NG01 480 FSF HM1 AC/A BC-22 BC SBORM2 BUS NGOP 480 ESf-RM2 AC/B BC-23 BC SBDRM3 BUS NG03 480 ESf HM1 AC/A BC-24 BC SBDRM4 BUS NG04 480 ESf flM2 AC/B Bi-11 BATT BATRM1 125 DC/1 BT-12 BATT BATRM2 125 DC/2 8I-13 BAIT BA IllM3 125 DC/3 - B F-14 BAIT BAIRM4 125 DC/4 BUS NB01 BUS-ESFHM1. DG-A 4160 DGA AC/A ( BUS NB02 BUS ESIRM2. DGB 4160 DGB AC/B BUS NG01 BUS ESfRM1 IHAN-XNG01 480 ESFHM1 AC/A N BUS NG02 BUS ESFHM2 1RAN-XNG02 - 480 ESFHM2 AC/B - BUS NG03 BUS ESFHM1-TRAN-XNG03 480 ESFHM1 AC/A BUS NG04 BUS ESFHM2 1RAN XNG04 480 ESFHM2 AC/B BUS PG21 BUS ESFRM1 TRAN-XPG21 480 ESFRM1 AC/A BUS PG22 BUS ESFHM2 T RAN-XPG22 480 ESFHM2 AC/B CB-1 CB ESFRM1 AC/A CB-2 CB ESFHM2 AC/B DG-A DG DGA AC/A DG-B DG. DGB AC/B DP-NK01 PNL SBDRM1 BT-11 125 BATRM1 DC/1 DP-NK01 PNL-SBDRM1 BC 125 SBDRM1 DC/1 DP-NK02 PNL SBDRM2 B T-12. 125. BATRM2 DC/2 DP-NK02 PNL SBDRM2 BC-22 125 SBDRM2.. DC/2 DP-NK03 PNL. SBORM3 BI.13 125 BATRM3 DC/3 DP-NK03 PNL SBDRM3 BC-23 125 SBDRM3 DC/3 DP-NK04 PNL. SBDRM4 B T-14 125 BATRM4 DC/4 ~~

h..,_.. ( u) V) (~% v Table 3.6-1. Wolf Creek Electric Power System Data Summary for Selected Components (Continued) COMPONENT ID COMP. LOCATION POWER SOURCE VOLTA GE POWER SOURCE EMERG. TYPE LOCAT;ON LOAD GRP. DP-NK04 PNL SBDHM4 BC-24 125 SBUHM4 DC/4 INV11 INV SBORM1 DP-NK01 125 SBDHM1 DC/1 INV 12 INV SBDRM2 DP-NK02 125 SUDHM2 DC/2 INV 13 INV SBDRM3 DP-NK03 125 SBDHM3 DC/3 INV 14 INV SBDHM4 DP-NK04 125 SBDHM4 DC/4 MCC 1 A MCC ESFHM1 BUS NG01 480 ESFHM1 AC/A MCC18 MCC NELECPRM BUS NG01 480 ESFHM1 AC/A MCCIT MCC NELECPHM BUS NG01 480 ESFHM1 AC/A MCC 2A 'MCC ESFHM2 BUS NG02 480 ESFRM2 AC/B MCC 2B - MCC SELECPRM BUS NG02 480 ESFHM2 AC/B MCC2T MCC SELECPHM BUS NG02 480 ESFHM2 AC/B N MCC3C MCC NG03C BUS NG03 480 ESFHM1 AC/A MCC3D MCC DGA BUS NG03 480 ESFHM1 AC/A MCC3T MCC NELECPRM BUS NG03 480 ESFHM1 AC/A MCC4C MCC NG04C BUS NG04 480 ESFRM2 AC/B MCC4D MCC; DGB. BUS NG04 - 480 ESFRM2. AC/B MCC4T MCC-SELECPRM BUS NG04 480 ESFHM2 AC/B PNL-NN01 PNL SBDRM1 TRAN-XNN05 120 SBDHM1 AC/A PNL-NN01 PNL: SBDRM1 INV 11 120 SBDRM1 AC/A PNL-NN02 PNL SBDHM2 THAN-XNN06 120 SBDRM4 AC/B PNL-NN02 - PNL-SBDRM2 INV 12 120 SBDRM2 AC/B PNL-NNO3 PNL-SBDRM3 TRAN-XNN05 120 SBDRM1 AC/A PNL-UNO3 PNL SBDHM3 INV 13 120 SBDRM3 AC/A PNL-NN04 PNL SBDRM4 TRAN-XNN06 120 SBDRM4 AC/B 00 PNL-NN04 PNL SBDHM4 INV 14 120 SBDRM4 AC/B TRAN-XNG01 1RAN ESFHM1 BUS NB01 4160 ESFHM1 AC/A T RAN-XNG02 1RAN ESFHM2 BUS NB02 4160 ESFHM2 AC/B

. t LJ ' Table 3.6-1. Wolf Creek. Electric Power System Data Summary l for Selected Components (Continued) f -I COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. i TYPE' LOCATION LOAD GRF. .i IHAN-XNG03 IHAN EGFitM1 BUS NB01 4100 ESi llM1 - AC/A r T HAfJ-XNG04 - lHAN ESFHM2 BUS TJB02 47tio ESfHM2 AC/B f T HAN-XNN05 THAN SBORM1 MCC 1 A 480 EST HM1 AG/A i T HAN-XNN06 - THAN SBORM4 MCC 2A 480 EST HM2 AC/B i T HAN-XPG21 THAN EST-HM1 BUS NB01 4160 EST HM1 AC/A } THAN-XPG22 THAN ESFHM2 BUS NB02 4160 ESF HM2. AC/B < i ?

.t I

4 i I .i { s.- 4- .i I 1 i' . j 1[ g. l -i 5 h h i 75 5 s s m 'f I f '. T ,..a~, '. + - :~ --~v i r- - ~~ +

TABLE 3.6 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT WOLF CREEK \\% I POWER VO.T A G E EMERG POWER SOURCE LOAD LOAD COMP COMPONENT SOURCE LOAD GRo LOCATION SYSTEM COMPONENT 10 TYPE LOCATION BC41 125 DC/1 SBDRM1 EP DP NK01 PNL SBDRMI BC 22 125 DC/2 SBDRM2 EP DP-NK02 PNL SBDRM2 B043 125 00/3 SBDRM3 EP DP-NK03 PNL SBORM3 8044 125 DC/4 SBDRM4 EP DP NK04 PNL SBDRM4 BT 11 125 DC/1 BATAM1 EP DP NN01 PNL SBDRM) E l 12 125 DC/2 BATRM2 EP DP NK02 PNL SBDRM2 BT 13 125 DC/3 BATAM3 EP DP NKO3 PNL SBDRM3 E T 14 125 004 BATRM4 EP DP NK04 PNL SBORM4 BJS NB01 4160 ACcA ESFRM) AFW AFW PA% MDP MDAFWA "6JS NbO1 4160 AC A ESFAM) CCP GCP PIA MDP CCPA bJS Nb21 4163 AC/A ESFAM) CCW CCW P1 A MOP CCWA EJf NE0' 4160 AC A ESFRM) CCW CCW PIC MOP CCWA BUS NB01 4160 AC/A ESFRM1 ECCS RH-P1A MDP RHRA [ BJS N601 4160 AC/A CrRM) ECCS ShP1A MDP SIA BUS NB01 4160 AC/A ESFRM) EP TRAN XNG01 TRAN ESFRM) BJS N501 4160 AC/A ESFRY1 EP TRAN XNG03 TRAN ESFRMI BUS NSD1 41(0 ACeA ESFRM) EP TRAN XPG21 TMN ESFRM1 BUS NB01 4160 AC. A ESFRM1 ESW ESW PIA MDP ESFPMMSEA BUS NB01 4160 AC/A ESFRMI PAHR CS P1 A MDP SM BJS NB02 4160 AC/A ESFAM2 AFW AFW PMB MOP MDAFWB BJS N602 AC/B ESFRM2 CCP CCP P1B MOP CCPB s BUS NB02 416v AC/B ESFRM2 CCW CCW PIB MOP CCWB BUS NB02 4160 AC/B ESFRM2 CCW CCW P1D MOP CCWB BUS NBC2 4160 AC/B ESFRM2 ECCS RH P1B MOP RHRB BUS NB02 4160 AC/B ESFRM2 ECCS SbP1B MDP SIB BUS NB02 4160 AC/B ESFRM2 EP TF%N XNG02 TRAN ESFRM2 BUS NBC2 4160 AC/B ESFRM2 EP TRAN XNGod - TRAN ESFRM2 BUS NB02 4160 AC/B ESFRM2 EP TRAN XPG22 TMN ESFRM2 BUS NB02 4160 AC/B ESFRM2 ESW ESW P1B MDP ESFPMHSEB l, 15 NBC2 4160 AC/B ESFRM2 PAHR CS PIB MDP sib BJS NG01 460 AC/A ESFRM1 EP BC 21 BC SBDRM1 48 12/88

TABLE 3.6 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT WOLF -CREEK (CONTINUED) POWER VO,, T A G E EMERG POWER SouACE LOAD LOAD COMP COMPONENT SOUROE LOAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION Bss NG01 450 AC/A ESFRM1 EP MCC1A WC ESFRM1 BsS NGO) 480 AC/A ESFRM1 EP MCC18 MCC NELECPRM BsbNG01 460 AC/A ESFRM1 EP MCCIT WC NELECPRM BUS NG02 480 AC/B ESFRM2 EP BC 22 BC SBDhM2 Bss NG02 460 AC/B ESFAM2 EP MCC 2A MCC ESFAM2 BJS NG02 480 AC/B ESFRM2 EP-MCC2B WC SELECPRM BJS NG02 400 AC;B - ESFRM2 EP MCO 2T MCC SELECPRM BJS NG03 450 AC A ESF AMI EP BC 23 BC SSDRM3 BUS NG03 490 AC:A ESFRM) EP MCC3C MCC NG03C BUS NGO,! 460 ACIA ESFAMI EF MCC 3D WC DGA BUS NG03 460 AC A ESFRM1 EP McC 3T MCC NELECPRV BUS NG04 4SO AC'S ESFRM2 EP BC 24 BC SBORM4 BUS NG34 460 AC!B ESFRM2 EP MCC4C MCC NG04C BUS NG04 460 AC/B ESERM2 EP MCC4D MCC DGB BUS NGod 480 AC/B ESFRM2 EP McC 4T MCC SELECPRM BUS FG21 480 AC' A ESFRM1 RCS PZR HTR-A HTR RC BUS PG22 480 AC/B ESFRM2 RCS PZR HTR-B HTR RC DG-A 4160 AC/A DCA EP BUS NB01 - DUS ESFRM1 DG-B 4160 A C< B DGB EP BUS NB02 BUS ESFRM2 DP NN01 125 DC/1 $80RM1 EP INV 11 INV SBORM1 DP Ns02 125 DC/2 SBDRM2 AFW AFW 312 MOV TDAFW DP NN02 125 DC/2 SBDRM2 EP-INV 12 INV SBORM2 04 NNO3 125 DC/3 SBDRM3 EP. INV 13 INV - SBORM3 OP NnO4 125 DC/4 SBORM4 EP INV 14 INV - SBORM4 INV 11 120 ACIA SBDRM1 EP: PNL NN01 PNL SBORM1-INV 12 120 AC/B SBDRM2 EP PNL NN02 PNL SBDRM2 IN v 13 - 120 AC/A SBORM3 EP PNL NNO3 PNL SBORM3 INv 14 120 AC/B SBDRM4 EP-PNL NN04 PNL-SBORM4 MCC1A 480 AC/A ESFRM1 CCP CCP 1120 MOV CCPA MCC1A 480 AC/A ESFRM1 ECCS SI-6806A MOV SIA t MCC 1 A 480 AC/A ESFRM1 ECCS-SI-6807A MOV SIA J 49 12/88

I TABLE 3.6 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS p AT WOLF CREEK (CONTINUED) t s %) PQAER VOLT AGE EMER3 POWER SOVRCE LOAD LOAD COMP COMPON E NT SOURCE LOAD GRP LOCATION SYSTE M COMPONENT ID TYPE LOCATION f.L O 1 A 4t; AC,A ESFRM) ECCS Sb8821A MOV SIA M;C1A 460 AC/A ESFRM1 ECCS SI-8821 A MOV SIA MCC 1A 460 AC A ESFRM) ECCS SI-8923A MOV SIA M001 A 420 AC A ESERM) EP TRAN XNN05 TRAN SADRM) MOC 1 A 460 ACIA ESFRM1 ESW ESW 23 MOV 1974CB MOC1A 460 AC/A ESFRM) ESW ESW-25 MOV 1974C B l MOO 1 A 460 AC, A ESFRM1 ESW ESW 37 MOV 19 74CB MOO 1A 46; AC A ESFRM1 ESW ESW23 MOV 1974CB U.C 1 A 460 AO:A ESFRM) ESW ESW 41 MOV 19 74 C B M;; 1 A 450 AC. A ESFRM1 PAHR .S-4 MOV SIA M. ; 16 49; AO. A NELECPRM AFW AFW 11 MOV AFWVLVC Mw is 46, AC A NELECPRV AFW AFW 9 MOV AFWVLVB MCC18 4SO AC'A NELECPRM CCP CCP 8801 A MOV NPENRM b, MOO 18 460 AO/A NELECPAM CCP CCP-8803A MOV B4TRM a Y MCC 16 480 AC< A NELECPRM ECCS RH 8716A MOV RHRH.xA MOC 1E 460 ACr A NELECPRM ECCS RK 8811A MOV RC MOC lb 450 AC, A NELECPRM ECCS Sb8802A MOV NPENRM MOC 15 480 AC, A NELECPRM PAHR CC 31 MOV NPENRM MOC 16 460 AC/A NELECPRM PAHR CC-33 MOV RC MCC19 460 ACs A NELECPRM PAHR CC 45 MOV RC MCC18 460 AC/A NELECPRM PAHR CC 47 MOV NPENRM MOC 1e 4SO AC/A NELECPRM PAHR CC-49 MOV NPENRM MCC1B 460 AC/A NELECPRM PAHR CS 1 MOV RC MCClb 450 AC/A NELECPRM PAHR CS-6 MOV NPENRM MCC 18 480 AC/A NELECPRM RCS RC-6000A MOV RC 3 MOC 1B 460 AC/A NELECPRM RCS RH 8701A MOV RC MCC16 460 AC/A NELECPRM RCS RH-8701 B MOV RC MCCIT 480 ace A NELECPRM PAHR FANA FAN RC MCC2A 480 AC/B ESFRM2 CCP CCP 112E MOV CCPB [m) MCCEA 480 AC/B ESFRM2 ECCS RH 88048 MOV stb \\'~j MOC2A 460 AC/B ESFRM2 ECCS SI8806B MOV SIB 50 12/88

. ~. _ ~ _ ___ _ _-_ - _ - _ _ ~. _ -._.y TABLE 3.0 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LCADS AT WOLF CREEK (CONTINUED) J POWE4 VO.,TAGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT ID WPE LOCATION V,.0 2A 460 AC/B ESFAM2 ECCS SI-8807B MOV SIA MLC 2A 460 AC/B ESFRM2 ECCS St88210 MOV stb MJC 2A 460 ACzB ESFRM2 ECCS S R8210 MOV SIB MCC 2A 480 AC/B ESFRM2 ECCS SI-89230 MOV SIB M;C 2A 460 AC/B ESFRM2 ECCS S68924 MOV SiA MCC2A 460 ACIB ESFRM2 EP TRAN XNN06 TRAN-SBDRM4 MOC i.A 460 AciB ESFRv2 ESW ESW 24 MOV-1974CB EC 2A 482 AC/B ESFRM2 ESW ESW 26 MOV 1974CB MCC LA 480 AC/B ESFRM2 ESW ESW 38 MQV 1974CB M00 2A at0 AC/B ESFRM2 ESW ESW 40 MOV 1974CB M; cia 460 ACiB ESFRM2 ESW ESW 42 MOV 1974 C B MuG 2A 460 Acro ESFRM2 PAHR CS 3 MOV sib MCC 2B 460 AC;B, SELECPRM ECCS RM 8716B MOV RHRHXB MOC 20 460 AC/B SELECPRM ECCS RH 88118 MOV-RC MCC2B 460 AGiB l SELECPRM ECCS S688028 MOV SPENRM MCC ;b 480 AC/B SELECPRM ECCS SI-8835 MOV SPEtRM MCC 20 480 AC< B SELECPRM PAHR CC 32 MOV $PENR.4 MCC 2B 480 AC/B SELECPRM PAHR CC-34 MOV RC MCC 28 4B0 AC/ B SELECPRM PAHR CC 36 MOV-AC-MCC 2B 460 AC/B SELECPRM PAHR-CC-48 MOV SPENRM MCC2B 480 AC/B SELEOPRM PAHR CC 50 MOV SPENRM-MCC2B 460 AC/B - SELECPRM PAHR CS 12 MOV SPENRM MCC2B 480 ActB SELECPRM PAHA CS 7 MOV RC MCC25 480 AC/B SELECPRM RCS AC-60000 MOV RC MCC 2B - 460 AC/B SELECPRM RCS - RH-8702A MOV RC MCC 2B 480 AC/D SELECPRM RCS RH-8702B FOV RC MCC2T 460 AC/B SELECPRM PAHR-FANB FAN RC MCC3C-480 A?iA NG03C AFW AFW 31 MOV AFWPPCHSE MGC 3C. 480 AC/A NG030 AFW AF W-32 MOV AFWPPCHSE. i ( MCC 3C 400 AC/A NG03C AFW AFW 35 MOV AFWPPCHSE \\. 1 MCC3C 480 AC/A NG03C AFW AFW 36 - MOV AFWPPCHSE 51 12/88

.... _. -. ~.. - ... ~., TABLE 3 6 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT WOLF CREEK (CONTINUED) FOWER VOLTAGE EMERG POWER SOURCE LOAD LOAD COMPONENT ID[ COMP [ COMPONENT SOURCE LOAD GRP LOCATION SYSTEM TYPE LOCAh0N MvC 3G 460 AC/A NG03C CCW CCW 15 - MOV 2026AB MvC3C 4eo AC/A NGQ3C CCW CCW43 MOV 2026AB MOC 30 480 AC/A NG03C ECCS-RM 6804A MOV ~ RHRMXA MOC 30 460-AC/A NGoac ESW ESW 51. MOV 6 CWA MCC 31 460 A C/A NELECPRM PAHR FANC FAN RC MOC 40 460 AC/B. NG04C AFW AFW40 MOV ' AFWPPCMSE i MCC 4C 480 AC/B NG04C AF W AFW 33 MOV AFWPPCHSE MGQ 40 480 ACJB NG340 - AE', AFW 34 MOV AFWPPCHSE '- i MGC 40 480 AC/B NG04C ACW AF W 5 MOV-AFWyLVQ ~ MLC40 450 AC/B NG04C AF W AFW 7 MOV AFWVLVA ) M;C 4C 460 AC-B NG04C CCP GCP-60018 MCV NPENAM - J l MCC 40 460 AC B NG34C CCP CCP 8803B MOV BWRM MCC 40 460 AC/S NG04C CCW ' CC W 16 MOV 202f AB MOC4; 460 AC< B NG04C CCW CCW.54 MOV-2126AB l MeC 4C 480 AC/B - NG04C ESW ESW 52 MOV CCWB } MCC4T 480 AC)B SELECPRM - PAHR MNO. FAh RC ~ f TRAN ANG01 480 AC/A ESFRM1 EP-BUS NG01 SUS ESFRM) 1 j TRAN ANdO2. 430 AC/B ESFRM2 EP-BUS NG02 BUS E~ ESFRMi i ] TRAN.XNG0J 480 ACiA ESFRM1 EP BUS N G03 BUS. ESFRMI TRAN AfG4 460 A C/B.: ESFRM2 EP euS NGO4 - bus E.SF RM2. TRAN XNN05 120 ACIA SBDRM1 EP PNL NN01. PNL SBORU) l TRAN XNNOS 120 AC/A SBDRM1 E P_ PNL NNV3 PhL SBORMS -TRAN XNN06 120 AC/B SBORM4 EP PNL NN02 PNL'- SBORM2 i 1. TRAN XNN06 120 AC/b SBDRM4-EP-TNL.NNO4 - PNL-E80RM4 ~~ TRAN XPG21 480 ACsA ESFRM1 EP BUS PG21 BUS-ESFRM1 TRAN XPG22 460 AC/B ESFRM2 - EP BUS PG22 - BUS ESFRM2 - \\ 52 12/88

D Wolf Creek 3.7 COMPONENT COOLING WATER SYS'IEM (CCWS) J 3.7.I Svstem Function The CCWS provides cooling water to various plant components during normal operation, plant shutdown, and after an accident. This system is a closed loop intermedtate cooling system between the components being cooled and the Essential Service Wat:r System (ESWS). Separation is required to minimize the possible releas4: of radioactive material. The CCWS serves to renwve residuti and sensible heat from ihe RCS during plant shutdown by cooling the RHR heat exchangers. 3.7.2 Svstem Definition The Component Cooling Water System (CCWG) consists of two se aarate 100% capacity trains which serve engineered safety features. The CCWS also inc udes a loop which serves non-essential equipment and is common to both trains. The non-essential loop can be isolated from the essential 3 cops during accident ec,nditions. Each safety-related CCWS train hat two 100% capa:ity pumps, one heat exchLnger, one surge tank, and associated piping and valves. The CCWS heat exchangers transfer heat to the Essential Service Water System. The surge tanks accommodate expansion, contraction, and in-leakage of water. Simplified drawings of tne CCW syttem are shown in Figures 33-1 and 3]C. [ A summary oi data on selected CCW components is presented in Table 3.71. 3.7.3 Svstem Ooeratin During nomial operation, one CCWS loop is in operation with one CCW pump supplying cooling water to the non-essentialloop and to any operating comoonents in the /G associated essential loop (i.e., spent fuel cooling heat exchanger or a centrifugal charging () pump). Heat is transferred from the CCWS to the Essential Sr. nice Water Sistem (ESWS) w hi;h is being supplied from pumps in the Service Water System (SWS). Heat loads supported by the essential loops of the CCW system include the following: RHR heat exchangers Si containment spray and centrifugal charging pumps and RHR pumps Fuel p(x>l cooling heat exchauger Heat loads supported by the non essentialloop nf the CCW system include the Letdown heat exchanger Excess letdown heat exchanger Positive displacement charging pump Seal water heat exchanger Reactor coolant pumps Makeup from the demineralized water storage tank to the CCWS is provided automatically to maintain the levelin the respective surge tanks in the proper range. The Essential Service Water System is an emergency source of water for CCWS makeup. A radiation detection system is provided in each CCWS train to detect abnormally high radioactivity that would be indicative of inleakage from one of the components served by the CCWS. (O offsite power, one CCWS pump in each loop is placed in operation. Following receipt of a Safety Injection Signal (SIS) or following a loss of '--) During a normal plant cooldown, both CCWS loops are in operation since flow through both RHR heat exchangers is required. An additional CCWS pump is staned in 53 12/88 I mhm.

I Wolf Creek O) the,oop supplying the newessential heat loads. At least one CCWS pump and one RHR lV heat nehanger are required to be in operation during cold shutdown 3.7,4 Svstem Success Criteria or the CCW svstem is expressed in terms of the The success criteria c requirements for minimum unit cooldawn (Ref.1): I v. 2 CCW ptimps per train 1 CCW h(at exchanger per train 3.7,5 Comnonent Inf,qrmation (Per Unit) A. Component Cooling Water Pumps 1 A,1B, IC, and ID

1. Design flow: Unknown

2. dated c.9aci'y per pump: 1007c

3. Type: h(vri-ntal centrifugal G. Component Couling Heat Exchanpers l A and IB 6

1. Design duty: 6.82 x 10 Nu/hr

2. Type: shtll and straight tube 3.7.6 Sunnort 5,ultnn_ add Interfnces A. Cc.itrol Signals

1. Automatie O)-

a. If an operating CC\\\\ pump shaidd tail, the standby pump in the same

\\. loop is automatically started after a 4 second delay, based on a low pump discharge.

b. A CCWS pump is automatically started (if one is not already running) when the centrifugal charging pump in the same train is started.

One CCW pump per train is automaticaUy started and the CCW non-c. essential loop is isolated by an SIS synal,

d. Makeup to the CCW surge tanks is provided automatically from the demineralized waer totary and tra,1sfer system.

Isclation vah es in,the CCW r,onesential loop supply and return lines e. to componems inside contninmern are automatically closed by a i contairme at isciation signal. (C7S/8). l f, High mdiation in e CCWS loep iso!.ites the surge tank vent.

2. Remote Manuai

a. The CCW pumps can tr: actuated by remote manual means from the coatrol room.

b. He CCW inlet isolaton valves for the RHR heat exchangers (valves

'101 and 102; muu b.: opened manually when placing these heat i exchangers in servic - Cooling Ac the renctor coolant pumps and the excess letdown heat c. exenanger can be t'ianually restored following isolation. B. Motive Powe7 l. The CCW motor-driven pumps and motor operated valves are Class lE AC V ]> loads that can be supplied from the sttz.dby diesel generators as described in [ Section 3.6. v 54 12/88 ~.

Wolf Creek C. Other d

1. The CCW heat exchangers are cooled by t..e Essential Service Water System (See Section 3.8).

2. 1,ubrication and cooling are provided locally for the CCW pumps.

3. Nonnal makeup to the CC% surge tanks is provided by the demir.eralization water storage and transfer system,

4. Emergency makeup to the CCW surge tanks is provided by the ESWS (See Section 3.8).

5. ".he CCW pump room coolers are cooled by the ESWS (S. Section 3.8).

3.7.7 Section 3.7 Reference

1. Wolf Creek FSAR, Section 0.2.2.

/ k t l O l -IQ 55 12/88

( 7_. __._.. _.. il 1 tv X5 th: {> sht @ft ll (11! II:li tki Nu sE ( t I I a g-I EX: OIsi A l = t l 'O k k '*k - l 'i!, p /'~'s y t't kn 3 8 I.- 1 l o i v 0-X t-e i _g e. g sk+ I"t lff! I o y - j t I = >< -~ t f 5 9a t- ? I y 5 e a f e e s l l = ~ 3 $b 'I!{ sys 5 5: s 9 F (V r[J);jil oI&: et i l( !r! y oIn: i 11' 1 Nr i e s.t! $6 l uS3

-~..-,,.~.---n. ..__...+...--n~.a..-_..-.-..~~-..--~.._,..s. -_.c,,.~._....--,.,,.n.,.~.n._ v i i i i i i 4 1 i i I I $ I $ Z I .c lE,.l jf ff kh !I I '1-II .e is fg h I I I

h k t

I I e-i oI, ;r sX: co t jijf-h --R @ k l h p i, a la. s :- t 1 i i, 9 3 I' i y i I j 1 ? ---w w 5-l e .n 9 t d' l .t : 't-6 l n ' t t l t i f hi- [ .s s f (k-h: . se i.. exI q lb. A A:1.e - 1

l!

gg + il x n/ssi i ._.. -.... _, __ J. !

_ =- _. - i tiTt.sngpe Mg ~ ~ X- + ---{x; N i n - zy n n =,0 s,s,E., -- g a, f 04am'Aer; dL mM .i 3 TO W R s serW OD8 4 coerow=r ~* u nsec=e wr _ UMM N3 UwM os; MAIEU M f.4 AT LOA')S g StpPLY ~ f 83048 CCW, STysefewt 10 N 1559e . rux,083 9. DFSPt ACE est NT TfMYw tonP A l 04MWWI Ifw F a fSt 9 l cen .i Ptwan en n, ru a, cu., o ?

• p i

'i X SEAL WATER Hz N [ .p 2 2 m m

4 4

><1- -C<l b g ,a in .= e-r3 o s O O 1 VA P

Q; lxi--DR

Dk: j =- l-n s. = ..w in 73 -OC W ^

u...

1 i E Figure 3.7-1.. Wolf Creek Component Cooling Water System (page 3 of 3) l r i I . - -. _.. _.. ~ -..k.....-.. _ _ _ = -... -., -. ., _. ~_.

i g g g... g esApS e p 6 75 eye [ n==., r - = :. ~

=

= = - - t i i i s 1L 1, t0 _ f J_. I W ,n f . T_'- o I 1 I i J,. x 4 j I

" +h.hM

,29Q, M O g g b b _.- 3.t M ,",~';-',;", M:

$h g'~"

• e n

i u.. "" 10 -bc >4-10' -- c s w w u -N OT h i e se os avun "?f , h* ~~ f I -.. I WEN q- - -. - -. c _ m._- i . 1 f wa.

=

r 4 / pI., t ar,menr= e a= -M mes..e s g u.. f l mu,= ic -== _y w a cr> a <*=ca m j CC i 3 .o. owin... I -.. l g u.. g i Figure 3.7-2. Wolf Creek Component Cooling Water System Showing Component Locations (page 1 cf 3) I

i n m 0 MAs sX: i o i l h \\ R lll s31 e f e e 3 i n g lI Iti

• i

'ji ti ~ P _".' 1!i 'lk8 + I8 l{I E 8 ~ I 3 e be as I 15 ~ a j [ l i l 7r o i g s%: sK' s sE: s.,i = I g F: ll !( 'I E. I n 8- 'a g g oI:t s#: e e g l P. + 8::!( M *!: 7 . J. 1 2 J g m E i e 's $n 0 t E W S t -*O-. e g ,o != = cli 8 s t i"l s6 3 uk U 1 E $.-.-->g 9 -- A e g s,: s : a OO f2 2 a -j! I a 1 - i

== O N g gR' gg. I l' W Nn e h .h. j

1. E*i - m +=.

4 t w. E. o 24 11 a g* y 5 s){ !- e i.f,! I gI h

1. E' s

i n m.9 i: [I .p-i BI a-e.I 60 12/88

g m.. l l u n.m sn =bC = & - D<h M 4 7-n m 7, ,m o ro 04AWiPO ~ ~ SY $ rF af = g l I r .o.. roorw a l 'a==== N NT gmg gr - axx => g g a...n $4ATLOADS w at t pat 6 I St#Tt V FY7stTrifF-10 N TLA TOCCW FROM O W Dr9PtACF.nd MT g, D* tocaean ma=2 c tenvAone .25,- FM # 09 0 rut t on a. er ll PlasPCOOt F A a l se.ta= I S N srAt wmn un -M es art metas l l RC l _h_. _h_ ,w .n ,n ,2r m a s, ,n ,n F7; he;

7EO, h_

_h_ s.' b

• • • "S r,

w ,w

1. 4>

A,a ,a .n l m Figure 3.7-2. Wolf Creek Component Cooling Water System Showing Component Locations (page 3 of 3) m

fm\\ ( ,J\\ 'J L 1 i Table 3.7-1. Wolf Creek Component Cooling Water System Data Summary for Selected Components COMPONENT ID COMP. LOCATIOff POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCATIOf3 LOAD GRP. CCW-15 MOV 2026AB MCC 3C 480 FFJ03C AC/A CCW-16 MOV 2026AB MCC4C 480 f1G04C AC/B CCW-53 MOV 2026AB MCC3C 480 FJG03C AC/A CCW-54 MOV 2026AB MGC4G 480 rJG04C AC< B CCW-PTA MDP GCWA BUS NB01 4160 EST HM1 AC/A CCW-P1B MDP CCWB BUS NB02 4160 ESF HM2 AC/B CCW-P1C MDP CGWA BUS NB01 4160 ESF HM1 AC/A CCW-P1D MDP CGWB BUS NB02 4100 ESF HM2 AC/B t t-I C 4 d& =

i Wolf Creek 3.8 ESSENTIAL SERVICE WATER SYSTEM (ESWS) 3.8.1 System Functi s t The Essential Service Water System provides the heat transfer path from essential equipment and systems to the ultimate heat i!nk (a 6000 acre cooling lake). The system also serves as a bac kup water source for the.'.uxiliar>4cedwater System. 3.8.2 Svstem Definition The ESWS consists of two 100 mercent capacity independent trains. Each train includes one centrifugal ESWS pump, a se f cleaning strainer, a supply cross tle from the _ Service Water System (SWS), supply headers to the various heat ioads and equipment served by the ESWS, return headers, and discharge paths to the SWS or to a cooling lake. There are no cross ties between the ESWS trains. ~ Simplified drawings of the ESWS are shown in Fi;ures 3.81 through 3.8 4 - A summary of data on selectec ESWS components is presented in Table 3.81. 3,8.3 System Oneration During normal operation, the ESWS pumps are not operating, however, heat loads in the two ESWS trains are supplied with cooling water via cross tic lines between the ESWS and the Service Water System (SWS). Equipment cooled by the ESWS includes the following: Diesel pencrators CCW heat exchangers Spent fuel pool cooling heat exchangers O pump room coolers for the SI, RHR, CS, centrifugal charging, AFW, and CCW pumps Class 1E switchgear room coolers Control room air conditioners Containment fan cooler units penetration room coolers Air compressor after coolers The ESWS is the backup source of water for the AFW System (see Section 3.2). ESWS train A can supply the turbine driven AFW pump and motor driven pump A, while ESWS train B can supply the turbine driven AFW ? ump and motor-driven pump B, In addition, the ESWS is the source of emergency maceup for the CCW System (see Section 3.7) and the fuel pool cooling and cleanup system. I The ESWS pumps are automatically started and the ESWS is isolated from the - SWS following a loss of offsite power, a Safety injection Signal (SIS), or an AFW pump - low suction pressure signal. The ESWS pumps draw water from the cooling lake to supply essennal heat loac;s. The ESWS discharge is returned back to the cooling!ake. A radiation detection system is provided in each ESWS train to detect high radioactivity that would be indicative ofinleakage from an interfacing system.' 3,8.4 System Success Criterin Either train of the ESWS is sufficient to maintaln' the plant at an extended hot - shutdown. The success criteria for each train is as followst Coolant from the pumphouse forebay must be available. O The respective ESW pump must operate. Q Piping and valves from the respective ESW pamp to the heat sources and ultimate heat sink must remain intact. -63i 12/88 1-

l i Wolf Creek 3.8.5 Comnonent Information V A. Service Water Pumps l A and til 4

1. Rated flow: 15,(XX1 gpm @ 361 ft head (156 psid)

2. Rated capacity: 1 ( 0 71

3. Type: verticalcentrifugal

11. Ultimate Heat Sink - Essential cooling pond

1. Volume: 442 acre feet 3.8.6 Euonort Systems and Interfaces A. Control Signals 1

Automatic The ESWS pumps are automatically started and isolation valves in the cross ties between the SWS and the IISWS are automatically closed by one of the following signals: SIS loss of offsite power auxiliary feedwater pump low suction pressure

2. Remote Manual The ESWS pumps can be actuated by remote manual means from the control room, as well as locally in the respective pump rooms.

11. Motive Power The ESWS motor driven pumps and motor o>erated valves are Class IE AC loads that can be supplied from the standby clesel generators as described in i

Section 3.6. l l C. Other

1. Each ESWS pump ig provided with a prelube s;orage tank that supplies the pump lineshaft beanngs with water to prevent the bearings above the pit water level from running dry during pump startup, The tanks are sized to

2. provide a five minute supply of water to the bearings.

When the ESWS pumps are operating, the bearings are lubricated by the pumped fluid.

3. Two traveling water screens are provided, one per train of the ESWS. The screens are designed for continuous operation to protect the ESWS pump suction from large debris.

4. Provisions for ESWS pump room eocling sre not known.

3.8.7 Section 3.8 References

1. Wolf Creek FS AR, Sections 7.4,9.

i 61 12/88

.,a -m ___m a tfi !l c.I ',, 70-c.I,is, 12, i, i. C h] E l*I x-, $1b E O i oIj cIj sZe E ot'ioli ,E L i gX g g ._cl i ! j! +illlili. !!111 hi'l' 1 Iri OIl Xl SXL p O 2, e f.,1

f. i f 9

O V ce; ,73. t .a c t syn sZs s e a e a e a r i,Is ojl t n n n.I iI.eI; 19 9 t-m s a s s s a e a sI s%: g ? A - b gil i e i t, i e s

• x lf.

u e i{!SI 65 12/88

i i it f f I', i! y T-a ^ f b or,- t2, S ta is_ lb 'I i i 1! t. w:i

• t t!

em oI[ cJ .g ll h, h oI! onj i M l sv, l l( l l e oI; or' ! ii' s4;i-l .ir i u est i-- 7 op sp sp c > >Isp ) i y,, i! !!! t. It (- 1 I e i s; i E 8 {E t l [ ji 8 4

• Of S 4 o'

S,'I' [ ! ' E,I $.4 2 1 T m t l t l IL. li .g i t sfa _ 1"' s '_ e 's k ~ t s a e a s _A g ! !l!i !il

lii, I lil

! ill i lI i i $ A R, h' 3 I' 9 ,I 1 l l 5 I I t .s.. s

• +~

y .N,i.. c ? 8 { [ S I \\ I i I .I 66 12/88

,64 4 4 J-h M u e.s. -- m .,4 M ph erm -p 6Eh4 41AW,,J.,-.hach. w Jz 4 e-4W.3m, gg A,w s.pe 4A.r__W A W6.a,a5h+es.&4-.+4b45 6

4. dW_ De

&_14G,*=-.54mk-e.4&#4-.y 3,.kma, A A eee..d. efe-L**#W:em-4-A' 0 1 o ,o q i 1 olIn n -i, cEi e$i t$i H i i l# E t iL1 i,ois g igl.I i a a l I' cEl oIj i cEb oli tyi A cdj,Ill]I!il'lli syi egi syn syi ip { i '!'l lall ill i i i 1 e s i ;* i f i e f. i f s, e f. ext g O si ~ c4: ice:i i i e n Lde .w { 2 8 2 8 9$s. 0 B s S 8 .2 3 e 3: 8 Oli Li ll( lli g,,f,4 m S s 9 s' S 9 2

k

% b llil!

e r la la i l Q ~ 0 4 I 8[f'. I .67 12/88

-au e.J _J4.uaum-._.4e et.a d es,y=a*.Ms.m__4 am W .a,-h--.- -.s ._sm.

• As.

aa. L.aAz.--emAm__4. ,,wa_ -.mmaa-4e w_ ..m ea.%.mm ,i_,s,_s. se in i.<-ha,..mi is__._A_.2 I t I <r i. I I I U I. C ss a s,e L r8 i e i.e i r s 1 .. ! :: OI,L i; i $i I i r .L-- l il r i I, I aOI,: 1 - 11, or; s(t p i 12 = ce; ! u p j o.jj, sys syi syn syi 3*"'. ] i! !i !!!!! llel l I !gj ll.l i y r s. 1 I l i o .s ti !!Pj r el 3 1 I sks . i_ t i-e I of ' ekt 2X eXe s - {' sit y 8 a s [ o]QoIl c = p Z. -[ I t 2, - ss e _4': _ ; i _ sgs. s : ,c 4 3 111' 8 E i 115 i !is!w lir ps s la so- .a w

m.,.

J g .w - _s e,. 3' 2 3 -2 5 g u = o o l I i.'C> l[ i ' s ; it la e a 2,E c mmmer - M i unu t-1 i r i - - 3, r -1 68 12/88

O O,,m ~ v Table 3.8-1. Wolf Creek Essential Service Water System Data Summary for Selected Components COMPONENT ID COMP. LOC A.llON POWER SOURCE VOLTA G E POWER SOURCE EMERG. TYPE LOC ATION LOAD GRP. ESW-23 MOV 1974CB MCC 1 A 480 ESF IU.11 AC/A ESW-24 MOV 1974CB MCC 2A 480 ESFHM7 AC/B ESW-25 MOV 1974CB MCC1A 480 EST HM1 AC/A ESW-26 MOV 1974CB MCC 2A 480 ESF HM2 AC/B ESW-37 MOV 1974CB MCC 1 A 480 ESF HM1 AC/A ESW-38 MOV 1974CB MCC 2A 480 ESFHM2 AC/B l ESW-39 MOV 1974CB MCC1A 480 ESIHM1 AC/A ESW-40 MOV 1974CB MCC2A 480 ESF HM2 AC/B ESW-41 MOV 1974CB MCC 1 A 480 ESFHM1 AC/A ESW-42 MOV 1974CB MCC 2A 480 LSFHM2 ACIB ESW-51 MOV CCWA MCC 3C 480 NG03C ACiA b ESW-52 MOV CCWB MCC4C 480 NGO4C AC/B ESW-PTA MDP ESFPMHSEA BUS NB01 4160 ESFHM1 AC/A ESW-P1 B MDP ESF PMHSEB BUS NB02 4160 ESF HM2 AC/B

l Wolf Creek 3.9 POST. ACCIDENT llEAT REMOVAL SYSTEMS (pal!RS) 3.9.1 Ssstem Function 'ihe PAHRS is an integrated set of subsystems that 3rovide the functions of containment heat removal and containment aressure control foi owing a loss of coolant accident. In conjunction with the ECCS, tie PAHRS completes the post LOCA heat transfer path from the reactor core to the ultimate heat Link 1 3.9.2 Sutem Definitir,a The PAlIRS cont.sts of two separate subsystems (Ref.1): Containment Spray System (CSS) Containment Cooling System (CCS) The CSS consists of two parallel redundant subsystems, each feeding one 360 degree spray header. Each CSS subsystem consists of one vertical centrifugal pump drawing suction from the Refueling Water Storage Tank (RWST) or the containment sump. The CSS does not include heat exchangers for containment cooling. The CCS consists of four fan cooler units divided into two independent trains. This system transfers heat from the containment to the Essential Service Water System (ESWS). Simplified drawings of the Containment Spray System (CSS) are shown in Figures 3S 1 and 3.9 2. The interface between the Contalnment Cooling System (CCS) and the Essential Service Water System is shown in Section 3.8. A summary of data on selected PAllRS components is presented in Table 3.91. Q 3.9 3. Sutem Oncration Q Dunng normal operation, the CSS and CCS are in standby Following a LOCA the CSS is actuated by a two out of four containment high pressure sigual. Each CSS pump draws water from the RWST and delivers water to independent spray headers in the containment dome. The CSS pump suctions are automatically realigned to the respective containment sump when a low level in the RWST is reached. The system continues to operate in a recirculation mode to maintain containment sprays. The CCS is actuated about 45 seconds after the safety injection signal (SIS). The ESW system should already be operating when the CCS fans are started (see Section 3.83 3,9,4 Ssstem Success Criteria Both the CSS and CCS have sufficient cooling capacity to independently perfoim the containment heat removal function. The success criteria for the CSS and the CCS are as follows:

1. One of two containment spray pumps (1 A or IB) must operate for CSS success. In the injection mode the RWST is the water source, and in the recirculation mode, the res,ective containment sump is the water source.

2. Any two of four fan coo er units must cperate with heat removal by the ESWS for CCS success.

3.9,S Comoonent Information A. Containment Spray Pumps 1 A and IB n

1. Rated flow per train: 3900 ppm @ unknown head j

j

2. Rated capacity: 100 %

v

3. Type: verticalcentrifugal 70 12/88

Wolf Creek O B, Containment Air Cooler Fans (4)

1. Duty per fan cooler unit: 100 x 106 Btu /hr (under design post.LOCA conditions)

2. Rued capacity: 50%

3. Fan type: vaneaxial 3.9.6 Sunoort Systems and Interfaces A. Control Signals

1. Automatic

a. The CSS pumps are automatically actuated upon the coincident two-out-of four containment high pressure signal.

b. The CSS pump suction is automatically realigned to the respective containment sump when the RWST reaches a low level,

c. The CCS fans are automatically actuated 45 seconds after an SIS.

2. Remote Manual

n. The CSS can be actuated by remote manual means from the control room.

b. The CCS fans can be actuated by remote manual means from the control room.

B. Mouve Power

1. The CSS pumps. CCS fans, and motor-operated valves are Class 1E AC loads that can be supplied from the standby diesel generators as described in Section 3.6. Redundant loads are supplied from separate load groups.

ID Q C Cooling Water

1. No emling water requirements for the CSS pumps have been identified.

2. The CCS fan coo er units A and C are supplied with cooling water from ESW train A. Fan cooler units B and D are supplied from ESW train B (see Section 3.8).

D. Other

1. Lubrication is assumed to be provided locally for the CSS pumps and the CCS fans.

l

2. The CSS pump A/C toom cooler is supplied with cooling water from ESW train A. The CSS pump B/D toom cooler is supplied from ESW train B t

l (see Section 3.8). l l 3.9.7 Section 3.4 References

1. Wolf Creek FSAR. Sections 6.2.2.1 and 6.2.2.2.

(O 71 12/88

i i i t .b. m .C.3., f far e. .X-2, = m. eer..a so. O CePaen.s.ac. ,h R.. ]-N 4 e+ i >4 N N a.. _a Q nfe w t b 2, 2 =-.][O _. ~ .,m,., .i na*. i 'e Q tJ O t - pTc =][.e { = ve m aurus te w-n _ +* 0 m = io s. R,. +N N ). .m a a. a

c..

s omstas.m.s.

c-c= =

Q i

==. j i. [o _ 2, 2,. .e. u 4 t-- f i l - seen.am.s.e. u 4 t g t i Q =..- cc.... ( 1' t Figure 3.9-1. Wolf Creek Containment Spray System t . _....~

a i. l. i:: il :: l i e c e, sp - sa : 1 m 8 fL tit i 8a E& ole k 01; gl i E i i i I se i 6 f _h h_ f i r 8 .c !l t2 e tI. 1 C b! h! g 9 4-a 3 E E 7 i oIB i; oli it u e o c- .x -) h j e a ~ Q lk. cQ L" g [1 f2_,,- . fe., - je) p ,o ). e of i i 3 I I r ~3-4 c) { .oX I- .OK !} .l-e s-i i a1 i o r g e OX !' f2] OK !!: tX{ E. s' g c t E n n. e e u m t R n 2 2 ( O h .I ih Ilf OI ) t t r.e r t ,,e i. 1 a 2l 5: 1 e I sXi i P [! 73 12/88 . _. _ _.... - -. _. _ _ _ _ _. _ _. - _... _. _, _.. _ _. _.. _. ~ _... _.. _.... _ - _, _,. _. _..

=. -. i ? Table 3.9-1. WOff Creek Post-accident Heat Removal System Data Summary ) fOr Sciected Components COMPONENT ID COMP. LOCATION POWER r.JECE VOLTAGE POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. CC-31 MOV NPENRM MCC18 480 NFLLCPRM AC/A CC-32 MOV SPENRM MCC28 SO SELECPRM AC/D CC-33 MOV FC MCC18 0430 NELECPRM AC/A i CC-34 MOV RC MCC2B 487t SELECPRM AC/B ~ CC-36 MOV RC MCC2B 480 SELECPRM AC/B CC-45 MOV RC MCC1B '480 NELECPRM AC/A CC MOV NPENRM MCC1B 480 NELEGPRM AC/A CC-48 MOV SPENRM MCC 2B 480 SELECPHM AC/B CC-49 MOV NPENRM MCC1B 480 NELECPRM AC/A CC-50 MOV SPENRM MCC2B 480 SELECPRM AC/B I CS-1 MOV RC MCC18 480 NELECPRM AC/A w h CS-12 MOV SPENRM MCC2B 480 SELECPRM AC/B CS-3 MOV SIB MCC2A 480 ESFHM2 AC/B CS-4 tMOV. SIA MCC1A 480 ESFRM1 4C/A CS-6 MOV NPENRM MCC18 480 NEEECPRM AC/A i CS-7 MOV RC MCC2B 480 SELECPRM AC/B CS-PI A MDP SIA - BUS NB01 4160 ESFHM1 AC/A CS-Pt B MDP SIB DUS NB02 4160 ESFRM2 AC/B FANA FAN RC MCCIT 480 NELECPRM AC/A l FANB FAN RC MCC2T-480 SELECPRM AC/B i i FANC' FAN RC MCC3T 480 NELECPRM AC/A i FAND FAN RC MCC 4T 480 SELECPRM AC/B t I G' i n l ~

Wolf Creek

4. PLANT INFORM ATION t

4,1 SITE AND BUILDING

SUMMARY

The Wolf Creek plant is located in Coffey County, Kansas,28 miles cast southenst of Emporia, Kansas. The site contains one operating Westinghouse PWR. A general view of the Wolf Creek site and vicinity is shown in Figure 41 (from Ref.1) and a plot plan of the Wolf Creek nuclear generating station is shown in Figure 4 2. The Wolf Creek Power Block consists of the reactor building, auxiliary building, fuel builc.ing, radwaste building, turbine building, control building, communication corridor, diesel generator building, and transformer vaults. The containment structure is a reinforced concrete cylinder with a steelliner. This structure contains the reactor vessel, reactor coolant pumps, steam generators, and pressurizer. Access to the containment is via an equipment hatch or personnel airlocks. Tae auxiliary building, west of the reactor building, houses pumps' piping and valves for the AFWS, ECCS, CYCS. and CCWS. The fuel building, which ts south of the reactor building, contains the spent fuel pool and new fuel storope. The control building, located northwest of the reactor building, houses the control room, the upper and lower cable spreading rooms the majorit,v of the Class lE power distribution equipment (4160 VAC buses. 480 V AC buses. 480 \\ AC motor control centers,125 VDC distribution p nels, the 120 VAC instrumentation power panels, batteries). The diesel generator building, located west of the reactor buildin; and south of the control building, houses the emercency diesel generators and their auxiinry systems. The condensate storage tank which serves the AFWS is located nonheast of the reactor building. The refuelln; water storage tank which serves the ECCS ana the CVCS is located nonh of the radwaste suilding. The essential service water pumphouse is lceated to the west of the control building and houses the pumps, piping and

• O valves at the ESWS which cools emergency components and their respective working spaces.

4.2 FACILITY LAYOUT DRAWINGS Fi;ures 4 3 through 4 22 include section views and simplified t uilding layout drawings of tie Wolf Creek reactor building, diesel generator building. control building, fuel building. communications corridor, ESW pumphouse, and ESW valvehouse. Details of the turbine building and many of the outlying buildings are not shown on these drawings. Major stairways, elevators, and doorway: are shown, Labels printed in uppercase correspond to the location codes listed in Table 41 and used in the component data listing in Section 3. Some additional labels are included for information and are printed in lower case type. A listing of components by location is presented in Table 4 2. Components included in Tab:: 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 lccated 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.," ORhL NSIC 55, Volume IV. Oak Ridge National Laboratory, Nuct:m Safety Information Center, August,1975.

75 12/88

i. lI

!!:i [: 7; .i 1 t t> O N N_x ,/ Q) t

\\p /y_,~

/,sf" y' ~ s u ,s / . ?- -x ., / , :, f y s ~ 4 <L t e,,,, x\\g s ~ ./ / i l n i c \\ 'L /s - y i ,y V o1 s.s j ly c9.m .,.. \\( l / d f n 'r: /, a n m_ ., o, u pV' k;,y(,,J . Q ss. t,, = n -h t e, x o i ~ t s /,\\' a t o 4 (Y -s S s l g )/p k r, w% - . g.,e'z, y-pe e i /,,,' e r \\,s ~\\ O ,e C j- '91 s' f Q,%g, >_' \\%s(, lo / 4 6

• p,(,, Lr.f' W

\\ _c_ _c f e o D-m \\ N

~\\

e w ,%qbr c v e e' \\ m, 3 i \\ g\\ o o* V 'f w V /'r. re s l ,(* /,s;, ,/ a ~, r e n c _._ 'o e ~ G x v. ~ .\\ , cv a T- ~v s' r sf y~. .a 1 ,v ' \\x.A 1 8 cou< 4 i oc z ,. M oo ny ~ e K cc r ~ u p g g' . F s i c ),' ,.,v s s s a y 9 ,\\<\\ e, 1 + s O j,d , ~ ~ s ao -e= =. t

h I [ 't Cn M erw Wiw I V r*w 1 m j C*#" ** t w ro.404 Eswsv:ew.t w j "N "" soprog.,rc+< (Eswvvwsa, 1 (Uad-wouaro Eswvvnse; tw .~

2 Hoe wr %

Ce* Coatrei }} Bud +ag Nwag A1% N****C f l 3 jf ~ G..-

E-g i,--

r C-Bud 6ng C l / on,m. N g s l g Er ;7 55 A' 2 Turbw e a e fia=*>r eu dmo 8m'6ao 4 3 .e: -- l) U EE .:E 8 2 M { ggl-- Storey TM W V8h* - Wa>r / } { Storage }} (CST) Fbom(CSTRM)% Tw ] s Tar

• g,,,,

(RWST) ' W veive iI N'* p 4 (RWSTYLVRW) Cneutetag Wome ./- so, % NS ND NORTH /- 9 Tm t f g we [ t t s-w,, csws m - t ~ i V(ESFPtfMSEA. ESFPtfMSES) I G Esws w ec w . g Y + w Figure. 4-2. Plot Plan of Wolf Creek Nuclear Generating Station s h ... - ~.. ~ _ - - _ - - _. _ _ _... ~...

T J m ...a. m m. w., 4 'j,fM-r. - d ..m liu p n=~ g /. / ss)\\ - f.. ,m. .a- _, ,- % p u_ v 6.,we.-o _ e, =uom.s.s.== - _...i _.-.. _.ast es-e-h 5 itLC \\ kh Il l 90 !:".:Y'-r-. a = %p[,~= = m =. - m. j.-- ,.r o ~ nw t.3' ene i A

7. n."

!~ a1 C , 3....-- - _-_ , Q,[7 '. + su een 4 i X1 T T L m - c. =i-A.,......' 3,.,,,- 9 ..,, ~_3 I9 & r' 1, , il l lI

r., -

.r: -1 J, - %> _um. Tp:..'- - s "u r .~- =, p o.,.nw'p-,i -C 7 ... c. X r j.. f y !'. A'

ii f-c

~, i g uei a --a- . ~.. 1 "a- ,Z J j ]1;j ,tu,,3 A 'a" O. i; e. i i .... w. b) lI d , t.sA I, M, - ! l uu e! e t I ~P '" ~..... M 1_rs; gl** - +n .~e g1,..- Q. ri, f L n:h i I I 4u c Ng e :.- n r.: n [,' ei q EM l +3 g g;,]T

• r

.1 ur-l a.y.u 4 y! -

, j i vaa# j hig M p;

. u-=. e 'I 7 .-- L n/* fr.~p t iuu .n ei q, yr mg.,.., lg.el ~e h.,..=._.-4 i _=. % b.<. . u..- f n g F~.

==p C i ....t.

1. ,u-. ((

g :.r ( [ wA: - M.- ar.sii y ,) m. = i W i i u Ty_,.,, mg4.,""'

m. o. I r['c'. 4 '

! (w. I /1.a L A.n t e.- n. ,. = . i n-- o .g u ar v.c,i ..... a _, g. g, h,,7

s-

..h.ama.. o ...q; '.$u, sI ,a - =g. m,y _ '"4 (**'O l y n -.I "= .. ~ 4},/ N -9 3: i ' rg)r-i ,/ D<j $o ty] 2""'Q.. 3.e w x - :..c.u..v.,.y - i (y-o w mMsJ wm _.iCQ.s.,..nWh.-j LF "n (;.. 7 j a s- .m, h ew - m' d M R11'" [3 w.=r.ut.- l l Section Lookina V/gsj-A l .i Figure 4 3. SNUPPS Reactor-and Auxiliary Building _Section Views (Sheet 1 of 2) 78 12/88

N a J.meLA _w q. ,,, x..: = p m m ~ - mKr- / a .?'

t=

:

/i'^ b \\ t, \\ \\;t? m-.,_ q\\ iu ...u-_. t 8 / e t l. l!

t..y i j

72%_... a,~.g_ i o. Awm -.a ~ m..._ s c-n. 7.g8= F;;Pr ] g 7 +a -.63..-- 1 r. % !,- G-A, n r.-- ,_ v i i J R-T Mws. !.m:, - c iC.. . !w, .= ' i, O t e,, _.., i.!- -hi t i +- 1 M. t ed. Ah.l ,ei.i?.E.". I. 9.k l I *~E 4.'T gr ,M /q E i,.,, ,s.e.a.. \\ jT ha 9ok o, L 3 / L. ,_w{ af, l - g ..H.m _*- M

,g,_-e::q t.

L'rE$-

r. ~...

p:o. j ... m.. c i-4 .t r g,.. .c. -2, w,, ,4,, p%m w. u..; ruw-a.c. 5 g. i n_- ,.,_,7 . s. mm 1. m up u - .J., a< _o i r ..;h d ,"._~ i ,'/S-m -a m ,e- = a ~ s-g 1Js =w r-[' ~ m, l ar.=, 2 -- y 22 -i ",,~ kll j d ji,s E I_, %% d' D5:.hTh, _....,. =.. ,' ? ~re_j. - s a, C e._~:' E. -BE%,F.j~1L G - 2." r tc3 E.n ~ r i y u a> .o_ l nx r .E s QQ j f...'i J;u.1 ...... m m } si-g .x u es s% _ . e.f f. k Section Lookino South ( Figure 4 3. SNUPPS Reactor and Auxillary Building _Section Views (Sheet 2 of 2) iF 79 1248- ____----_-_-------0

1 l .u 9 r i .{ j.-i91 1 I a f , lf .t h; ... g a (' l 8-o 1 0.t:iih.f' ll1,.1 [.l' l l"'. { b, te .e 4,._ ! d. ' N '.-dL g...J %7M ~ a=$d .2 Jh i-q.p. i in t P l' 'y I, di p.l f-ll-s 10 s i r7 c 1= -a .-}:.. t m. v m, .9 p v.. - - e ; 6.,, .. i. s , s4@r'% y

4. Ijf

M'.$r r&.-#'@.

.t. , ci l;t - ! v.,N i I T td ). c _I @g..l)J'j!)j.: iif,Ld.(I'l [77 i. hs l i w i 8 lr-d;;I . pl1 lr .. i, 1 t ,llh e n 2.~ o. t: + w s 1 T P! al ! ? h) ly)i o b

.' 8;' : 1 y ]1 d i l,t 0

t ij l 1; h l

w..

m s, \\ 7- -) o r- . +gi g g ;3g. 1 m lij [ lm/ p. i s e j-Is :ia s ',j i--. e .c i h. 1 J ir; I _ _ m, 3,; .g...,,L l if l : .'i j 3- '- 1Os i i ,1 3 .E i;

1. W,

~ IE sQH E E q.a : h 6: m .e:._N5_.._I! .. !!} lW' l !! U-S o* w l:j., ;d[ N '!. j 'D .j e d. li!) c :-d l C ll ! 3 4' ! - ' lit -@y. 8 E r '-- -~ ~-M 1 1 P ~

.. b;. '

e c c w n.l . _ l l___

t

' l' 1m ' uq S s I p -.. - ..a 4 - 1,j 0;; 3%.t,p E- -R ji 5 l.:,3;.a - M k-l 1pt i: r q u _J - m i I. v II f.- ...p;0 j x h 5, Md . Ei '! j ! l ! [n ;1;...!,'di.i i! h.) N .? l i5 u x L,u i ln.:..lll,, dD N! I 3 l ' j! s, } } O O4 1-l I 1.- i {;li1(*:i,, u) h.

i. Dr< i I

.J l i ti c. s.-z.

}7 W*il.uwd.,,

1-p _s ;A a. ji c c{ -i od-,i8

D p-iri' l;,._L i hj]$k:. :uldg'IA.'_.,

i u 2 u) idu ~ y i G~ t 'l J

• 4 i

!i il i...d L 3f.qs.I* &.t 4 {i! 'l t w___.' t i p.. t -g g f f

1. . E h,i-l/h'%li g}l.p.U!di

--\\. b .!! Ij===! , Lie,.: !

r L ! <.t y-M(Mi!b cr.

L 4 f ij ;0 !/ _5.__J 8 4

iL

. -{ 3 .h t )f, gile. .( ~ s s } -- - - -- [ e ., i o .t, 80: 12/SS

.-J---ess a. 4.A4--e-nl44 e <ia e 462M.a W 4JA4 m 5m Jh 4 gMA..=44-h Je6 4mM W45.qM e3.M4.-hd.SM .mDA dAEn.JF5 e-s-h*S-s-@.6.5 e es .J 4A.a..g..4M44 .**eOam lh4.-4 7 4,-r&@ 3_.e>niAh.EJ,W a-a8. Ja s e, J.Eb e eed-64Ja ..J t i l t 4' e t s u'k11?

• i j; ;,

s 4 u IFl.,9} I' 'l 1 i A jj I, 1 f, . j' i t' i 4.,1 4: sj * }l it I e .s 4* Q.. & r W 4h*'? l' fu.Y }]s [i.]. *. ] j t g % ti jf Nl'.W h gi.- 8' L,t,] 4dj ' c...,g

81. - 4 1

, ~. 4 kI h " N.*, m_.,'a _ .. u;._.t_ f;;.m 9,t % pit"PR.fij,dpyp; .__v

v. g;$*f c-

[' J'. ~ 7, 8.;.m.a.y - - ,4, - d, a i _ r ~ :- 3 :-.q,.J.:. ,,.y l !" ly ",t'O 3,wi q y [', e - l*l f th, I e e a o... r.. t . _w.a ...: i m I~,..a:. ,5 _. 1 h j.j. p.. qtj g, - i, 3 .g ' i.= y $ h, g ;, 5 C*-*""" ,I Q.i.__!.i 3 t ;' !d b4 5 gD m ' m.. o. Ii j f-~~ ] I! _~ l .q- , 6 _' L w)d ' 4 .%slii', E d i, e e.u.dh:wlpd;s.m i t

t

, _t C th L. e-I t* g a , )7 :

o

.u. i._ d,: N H F. g..M. 6,g,x.dl. r o. '8 3 o-P ~

• R-i f p jj j.

1

i r

-e , -.4 o e ',/ ly, c ) gy ! t.; N*.'y? e.o 4., 'l w".. U I-

i. '* i

? 4 i + ". e pI f gQ q~/ }! t .? M* 11y

• 5 t%

-: f,p.1; pe ,i. alh i,,. u Q' p) el " m:hI n =* - *Ift i. . b. 5 g 6-t I 3 . f' -) %l * -- w.O 8 g

w..g -

3 -r9 o-1! -jI );.L< L, I~ hi)!' u. a, ,,p 'd !,, u., 3 c n. ,. O J'; 'M wo 1 I I N' p O..;.:-l. { iJ i! 8 EU '~ ii qr' pr i L-- ji r-s*c 99 9 a H 9 Z 4 6 ' '"""" 9L ~ i 6 p,hm.e Cf;.;iffby<---) U - } jQ 4 I' I! i ? -5 e e : m ^.. C-? $. cd. c4 %._c M 4.,3-s. fi

,1y; a __

1 f Iy mg-m'._.. h--ill ()f) $--. t,qa---e.dll;N.'d,#= ko ~' -i-m o r-d' ik

• 3 l j

l1, -A,/ 4 '.xrd,,.4 [ . Z *O 'i l ."I Me % }*i ]1'*1, k,g, $)L,.'y , iv t y : . a f f s +4 g*s th jI 4

s w v- -,i

. w.t,c- - o 3 m=,::r.:a,i _y g.,dD l }i - - e-1: -- ;j 4% g-. 'l ...U-h .k .1lI i m L %,..J4..,li.; ir m. 4 a.__ %d p p @ji. jqb Ly. p ii 4 g iij ) f _.w.2._.,, y ~ ,. 7 y gli. .Y 81. 12/88 i . c.. r ..=-..-~.,--.-m._,--_. m= ..- _,,_... ~.... _._._._.._ --. _ _.

T V

• u..:x.-

, -- n .n..- -= _ __ i ; __ _-. - f d ,c,..... y .h:f 'c %,ta 6 NL

t. i % 4 8'

.J. Ww I .. e..... m. i .. e. - - um 4

c. c....,. i l

22. ...c. / ,g h .....s..c,...... A? q a..A;M 4 8 4 5 m g N' 3 2 l, i s .. ::.r e- 'j ,..y. a ) j; l\\ a. f l \\ qn ~

i

[, p o. I l. l l;: j 1-L C,-- -- e.v., m.* * . e L e J - u. i__, ii t.

. 4

-y i,i e...  % W b ' !8.t. (' t yt. O g t,w(, ? s t ~ ~- g,pra w.- a n,.., m \\v,, .% A ,/ / LL te l..c ] l V , t.w. t. f! s' l'C2' a cxs. rw '-.3*... sm. .h----... ,/ \\ _. t. t u i.o .. ~..,

== _L 1 y 1 41 u, t on.~a ss,. EG.i.{ "~1 R aco.se s. 6L m yex. m w et i o h% se i, a nx at-- ~ ~ w.w wu w,,...,s y .)- . y c *a u naco.v .:,s aac / p . 3i_4

t..,,.

) --i n 4 n,,.v s l' / ruu w cxum + s kOU (W - ux e.m .L.A ( %,:tb - r-u... c.; m w es J t@ t,x Figure 4 6. SNUPPS Fuel Building Section Views (Sheet 1 of 2) 82 12/88

l 591 Es I.30* = ,-- m.,m==. = : m errw m - 7 7 5%4-*TUd4iLTJW"%'C W TJ~*" ~ ~ * "" ~**~"M+ e. g '*I / 4 4

• 7 of ha.At kA.5

( 4 = -- at L.1:Wi' 3 l

Tvt, t.,,3 4.a S.

..., *, a. s g n *;. ;tas; *, [

sA g

=; .,. ~ .3 e... 5 2 top or as.. casa;, = at a s.. 1?

t. ::... :

4- -., ...A 3 ,w

===,M. 7 7 7 w-t* l . 3. _ i! ') a_ ~ ; e \\ i 4 -.t, s

t. ta.>.*:4 RA.t m.it' k tcNCJL1L

• .,6-79 ct EA., a? E.1;M,*.

c t [ **'* ~.. u - n 1 w., > e.gw % s.ie.. a - t _.s :,,..; ,a.. eta com **> j i

w I

F I I' ' c%.( l i 4 I - [C.L I -- -+ l i f> } I - oeg a nt. o r aoa i g ..f3

t. toas *

-z =w r- - i x Q; e - Ltut,ak". e m6 - I ] {.l - 4 A*U $ 1 L.*A 4 ' Pi t. w wg, wy t 4 I m -.v m t. m -

== '} - [ ei. Len0CluTLA g 4 j M a tvt. , m g...g pa g e, t ,t.f..a*** mud y j p*gy. 1-3 sd l a a s n ,,y j PGu w - l mc - i-j /'~ Cab *4764 }r .-'f l ]'. WTIRvt.;nA?! NCR i e-t.- TL101 '.c" =* P h gI .mi i c:: :: ae i} lf '

-g

. is 1 ' J'a' \\ h, egu, sgu i en {t L AUD *s / N j h~ $a$. e E lt.I'64*a WAP) ' " # 4 "# f l WaF09A jMOS Cous*fJC' A N ~ _ pu,,g CCWtJ"T.N h I l l-CPU 4 644 f ' \\.,, -

1. y

- j g "J ' t g- - (pewho eu=% ) f e Puras e v.tco! { / 1 t,~ mc,e ./ ./- cexwo r m

: --- - s.

-f / ._t w tk 10&O W CkA%( ( [. PJ N*. Pit. I n g g _SECTION e-E '-_ .i LuJ Figure 4 6. SNUPPS Fuel Building Section Views (Sheet 2 of 2) k 83 12/88

-n...... n-an ..-.--..y.-- r i. to C<<dudf%ulocy Iledracal Chaw 4 4 e Nort radioactevo ,M Ps Tunnetand E Pe an.a uc.o N rrom nwao. s.,% O O O ) ^ I RHRB RF88t A Ih DORICRM CCP8 6C StA CCPA PDP o .38 I Radondeve D Illff3 f311M D O O. C b Poe Tunnel = k Foom Ihadwage 1 ND"9 - 74, cay I p 1974 A8 ME 2. u i ] i . } 81TRm 9 UQ f o co @J]U u } A i 9 LDHX -J i i AC 'C 4 AFWSWCMS i. E f i I t i U G i ? i h NORTH 5 M - m i. .m e l Figure 4-7. Wolf Creek Reactor and Auxiliary Buildings, Elevation 1974'0" { {- i g' i ' i

O 1 q h, ~n, l 8 l ~ Ib l 2 +\\

• % i

\\ i'

~

x N0/ "h 49 ? 9 /f\\ r g J f! a W i N 6 O' V i h e F .c b ?, e O D C t e e N. 'C k X \\~ ,q 9' is e li i, ~~ N n$e e 8

l. 5/ >N 1x

2 B ;e_ w.

e 85 jygg I - - ~ ~ ~ ~ - - - - - _ _ _

pf c-e em l l a <www ama b To Yard a h*N a l% :#*m 4 % s ~S L' ~ \\ 99999 SLFTRu HHRHXB AHRHIA ~ Hot II j M FJIlllll-c o" ~ 80*c"" unc% N l toc m w e m / yo O + Cw.v Stwage I"" tl O ()Q 2000 a 8 [ im peu n r+g a wJQ+ y, y f kb: m -C 4 i Te ves 4-J D [

M:

NPENRM M m I t) l N FPHX8 SPENRM I 5 I

()

l 33 C Yeved 4-() Q D I 33 FPHXA U i E! i m I adder To O Retroad 33 by 2: ku9 1 m a i 3 U 1 a a AFWVLVA -4 2 2 y l scear RC h 6 j 2000FB33 AFWVLVB -+ O--- g. l Pool O y TDAFW -[ ~ Ladder To 201 Y 6- ) Toved M** U"*' l FWWLVC h I Aou Do.ter Z / 5 [ --o i - Haxh to Personar -9 i Tendon Gariety y E m gency to Access $ haft Im1H3th F l g { To Ya d To Yard nogyg m { To Yard 4-I Figure 4-9. Wolf Creek Reactor, Auxillary and Fuci Buildings, Elevation 2000'O' l I i 4

.._.m....._.__ .. _. -..,........ _ ~ 1 l 6 1tf ELECRM A' " * 'g erd (ns5 rno n, 33 l *' ' re.~ es { C ( wm.v i N/\\/ 8 RHAHX9 RHAHXA gg gy un e cu.tN =

• * = = =

Shop Hoof e NF 1926 A B 3 ID ) 2026 AB l Cwt > '* IM y E M "D 1 D h SELECPRM NELECPRM M- !kh$c L_ UQ v "** 8 s PMW ASDCP WCCNos27 Et 20WF --O p /I< } WC CMG08 f + Z e UD %. N"* M uccw nr m-O hap (Dry) e,ctwmy D 2026FB "CC O'#8 M ~ l l M i l '"I*" MSTNLAD Pm spo,,e RC 2 w Fuse l L NSTNL9C s a n a / AHVAC Penthouse l %'To Turtana I

• "8 i

Au=*= y uo tw = i noom x_. i nor bEi l I

1. 4_N 9

i 1:3 = m j m

== NORTH t UD l Figure 4-10. Wolf Creek Reactor, Auxillary and Fuel Buildings, Elevation 2026*0" a i 4

~ m m b ( 's To Cwted Ibel*y Desed Generator floof 204T 2* F teva m W r A-f n %gy 4:J+ D "D l 1 m.. $?s. QV Eleva 'T2* g NGOeC NG03C ,,,?.;[;*.... i.h(- % ~-. Y 1 MCCMOO4C MC C hC O 3C O O () () Dy c--- , l; (*- ' uIIIIM . v. n IIM a o 2047AB i g D F

R c

0K ( h Personnet 4-l O A< lock ud E C___ '~~~: D .g' Caen Fans Temser W O f , c,,q ll i ._r 2est lg 70s y P' So** ' RC Y Y -y, A_. ~ e e:i ~ r Harded 8 To O --> Turtune Equepment ' o a>u,na use 5L NP,- Pfeform M E NORTH oo = D Figure 4-11. Wolf Creek Reactor, Auxiliary and Fuel Buildings, Elevation 20476~ xa

iII 1 > H T R ON '0 '479 1 no i tave lE g {j ro d irr m oC u no u it ) a ( N',w c inu m mo C dna 8 C gn 4 7 i 9 d 1 l iuB lo r tn . y o r - Tao C I i nn mu k io. A e e e T-r C. flo W 2 1-4_erug iF m 3Am i t llL

ll

.s_ m 'f i 'f NOFIT H e b i. N N h p 6 6 0 i d o o { O o .i 9 ~c 4 oo o D

o o

E 6 U o l @ 94 lNI f E .j w em ww i I i l } i; i i i i .Q m i t l Figure 4-13. Wolf. Creek Control Building and Communication Corridor, Elevation 1984 0" 4 + i i- ,.h.. 1

l l l t .Oo 8 N I ML! 4 5 $g 8 g f ~ f

gv -

ao

• .L-g n

i e o p=m tj unb c o S e f 4 g l -[ n 8 Y L get COON SnB k , LOON SnB V 2 M E 6. c e 40 L OON Soti c or-M- m 2 'S 200N SnB 900N sne 9 o 5mE 3 z e=N Sne g

q o

C enamen. O @0 V300N ODW I d f c U:e !; e DC 7.3 CD o m C e C O E o 3 $ ij Ie r g o 1 e

• g i

CO M i o 2 eo 2 3 h 03 n kl9 4 \\ 4 a 7 d b -o - l s e I C i 1 f 12/88

O ) C t E [fD$ ab hj w + D ocs. v v un[ "or o -6 t, ) soons. soone. U) (UP ~ bue E + sooner E snones 4-oca l I 1 e tJ 4 1 l uo I h Tistww nuibnD --+ NORTH I a f L' m m Figure 415. : Wolf Creek Diesel Generator Building, Control Building and Communication Corridor, Elevation 2016'0" 4 -[ 9 4 r

L;I 3 ! fi 1 !( O 0 '2302 H n T o R i t O a N ve lE g m r S d o ev d u l Ien O irr mo o 2 6 oa C T Q o n O oR%T o i ] o t ] a u c 4 o 0 I i n_ + u w0 rr m y* y a d e ae m i s 2 x2 u0 u0 o A2 A2 M C oI oTa T E d 0 0 u m = n u n d n d d a a t u ue g 3 c s f O n e i d t l i l i t Ir> u B lo M r tnoC o ,g Y] s n o id l iu B ro ta re n eG ^ h ? o e o se iD as, s. v k s. ee r y b/ C f lo Ex W 6 1 O -4 e rug iF TMo 3 o w m

-w---- - ~ - - - - ----,,,-- _ O e aa 3 5 5 2 W -ri "f! I a e g 0-w

== oc 4i ? Ej '3 e me 14 i i e e mc e Q g'/ p, a O m e ev 8 O .23 CD E 2 l p-a e e 2 1 = = 3 .'d la _X_K__X_E i ?! e n = 1 = D A 3 E -+ j ' h 'm as 4" D4 ,k. C "g ~ w 94 12/88

jil llIll{ O "6

• 3702 n

0HT o i R t O a N ve lE ]- o r g" - n* o d u i p:- a r 0 E r e N o 1 _r 1 C 1 u3 1 I T n \\wN 1 o ( lw,t t it 0 f a O c inu m moC dn i a c r g oR n sa i l p a d b t l a a i C C u U e B r gp l U o r tnoC gn T i 4 d l iu B ro ta re D n f D eG ooR7 0 o l E e r7 _mI e4 r s se0 0 e M2 r2 w n i n t D rea o n cta a p v k v tee le e sl E ef e iD rC f loW 8 1 -4 e rug iF 8 -t= llll ll l

4 \\ w) Mo rOn p[Mova t HArce z \\ y T R Avit speG WATER \\ S C RE t t4 Rt MOV A L H A 10 es ] noo u v o w a r ca \\-4_y p _. a 3. ___ L_ (sws, t ot AL CoedTROt. PAdE L t)MIT' Hf ATER(T Yf') --- _ _. Y pges5FORiet R ES*5 PU M P-- ce4LORissE DETECTOR 4* WA f( R 5(Rf f N . _. -3 8-kt - AITS-8 A T H AVE t s HG d l r N ~ ,I', LI \\; f t 20^4'9 ..g \\ I **'" "*'I \\,_. __ 'b d# # - kh' {; et zooo ou y' ., l f ,J~[k[, ' f _....__ _ I.. \\ f] M _r ,11 r, +..- j sta r-cti miu . e;'...,6R A DE a.y r sTop tos - i - y-

3. 31 Ramt sa -

$~ -<y L :; 1 WC /4. ( [.--- If Z Z [ 'Q' f f0RF1 f A - ~ ~ A g; . e t_mtE__ g-s- C-~ y' C \\ .-WARMING t tHL PST Stim P ] 1 . f Z i" T l l o-6 - tea ma) ~ h s p n y, PifL.& Et 49*>1*- x 'e L J Pf f il P f t 1958"O~ -r""" !*/)-' .{ v_,, r g ,955 9-y 'W * - ~ K 4 .g.- co Figure 4-19. Wolf Creek Essential Service Water Pumphouse Section View (Sheet 1 of 2)

(~h \\ s (# h5 8' r 4 MP A .F 1 Y,11J j

2. v..y n.. u o.

p $ " **4 'i F't fJ'T* O 6. { l $14% j-f d 4'4J A* >f ( Atlk i t e l-) / / / J / r- .- 3 / tr.. arm 5 me s o ru,3 8 "' O' M. tt 20?0 s-" .Ttf08A_. I! a s.s n-is.s swe[ -lp ::.4 ,trc.A .e int r o.. r-- <- j n. _I ___l-x' 47 . -,T 1:f a2,ww k ,..s'j 3 )mJl, pu rron s c r = w-r i, i r u .f !!; /,4 : :.

l

/ .-.a maum um o,s.> s .r - .s.. ,. j +E t t 9 91 *- C,' j - c s. e r r. a 8 a ,i .e ....i .i i.. ..l 8 r.e j e.i. .i : e ,- t,.s 4' l. : ~,i, 1 4 i .'+p... L. u. j 3-g r-s u.. L} +t .y t e x f = Figure 4-19. Wolf Creek Essential Service Water Pumphouse Section View (Sheet 2 of 2)

WL $U I}NnI p$i !k stv .?$~l G D .,e s h$:I. $$g N?$ 'w ESAPMHSEA ESRPMHSEB .+ 1 jfg e$ i I: U l El E l, E R tm I b E El NORTH s Figure 4 20. Wolf Creek Essential Service Water System Pumphouse, Elevation 2000'0" s 98 12/88

u T. d C. ' vy "*t .r ' W T: A Pt u*.- rg AJ*, >kLY a i s a b g_ \\t ..l ,I i 1 L f(*. #,, i s rt m, L, ',"?,,,,- j /.-' .__....__4 4 i l 1 . -.4, I l l 4 .j ' l ~ ' ' ~ vs o f / At t

1. , o.

L a t t%-- 4 90" E $ws [ Ot5(wA2GE .ppggigo pen M / - ELECTRICAL - 'f CuCT SAW84 - f-J t ( ../ } ( 1 \\> i ~ ,f, ~ .d Gn af tus I / F-

y.,,

27 nooni.e a ret-e s m t

I vy )

SLE f vE, 'ROCT. y. / . ue et asso-c }} L P E.L t980* *3* y m-i Figure-4-21., Wolf Creek ESWS Valve House Section _ Views (Sheet 1 of 2) ~ -.. - -. l _--t-iir +-. -- -. - -.. +. Lf--' 1 gj e

w a f. Covt R FOR 14 AN Dt B MG I ._..__l'~**,____..__ t s', t, goon'. o- <,...o. ,.n n,; i ~se .I ftfCTRtc UNIT MY Alf H (7.5KW) N f6DOSA -h~ . r, j-l-o.m. m m o.. ,,,,,.._o. .= [ ,], - l 1 ,a / -- 4 .. "\\ A g. ..i..,.. -4 m' / ..) a u -i x_ J vor or capr. c. .o..esv i fL e90 3'-3* 4

p-

~ r. . Y.30'E6WS 9dPtV Pt8T n t iw.'..e stove _ t. t l !d .m = Figure 4-21... Wolf Creek-ESWS Valve House Section.. Views (Sheet '2.of.2) .i

--ma.__-__ a .a-p..,. w.- - -. - - - w ..m. -i_ Jm. m 4, .A m aA..ip. ..,a_6. I 55 k c+ .J U) g b885g E 5 EE E50 jf[Cyi* $ % l ig ~5.[a$f f, topl 1 m re s ?;3.8 Y. g' a, ~ 6 ., d ' ! >>, g shj d k r wg a -*. . ggg g 3 r - Kj msnm t n 2">i m m U): 3 e

n -

8 8 $8 ?! / \\ t t" 0E Do odM$ $'s i

m i

i t 38 5 5 t /s NE 4e es P.r as s E m* SiD e e 6t c e Ed e 37 5 E o= i Do 0Q g e 5 5 6 O l 101 12788 I

i Table 41. Definition of Wolf Creek Building and Location Codes Codes Descriotions 1. 1974 AB 1974' elevation of the Auxiliary Building 2. 1974CB -1974' elevation of the Control Building-3. 1988AB 1988' elevation of the Auxiliary Building 4. 2000AB 2000' elevation of the Auxiliary Building 5. 2026AB 2026' elevation of the Auxiliary Building-6. 2026FB-2026' elevation of the Fuel Building 7. 2017AB 2047' elevation of the Auxiliary Buuding b. AFWPPCHSE Auxiliary Feedwater System Pipe Chase, located on the 1988' elevation of the Auxiliary Building-4 ARVVLVA Auxiliarv Feedwater System Loop A Valve Room,' located on the 2000'of'the Auxiliary Building (

10. AFWVLVB Auxiliary Feedwater System Loop B Valve Room, located on the

-20001 elevation of the Auxiliary Building

11. AFW RVC Auxiliary Feedwater System Loop C Valve Room, located on the

- 2000'of the Auxiliary Building

12. ARVVLVD Auxiliary Feedwater System Loop D Valve Room, located on the 2000'of the Auxiliary Building

13. ASDCP Auxil_iary Shutdown Control Panel, located on the 2026' elevation.

of the Auxiliary 1 Building

14. - BATRM1-Battery Room Noc 1, located on the 2026' elevation of the Control Building-

15. BATRM2 Battery Room No. 2, located on the 2026' elevation of the Control Building

16. BATRM3

- Battery Room No. 3, located on the 2026' elevation of the Control -- Building

17. BATRM4 Battery Room No. 4, located on the 2026' elevation of the Control' Building

18. BITRM

- Boric Acid Injection Tank Room, located 'on the 1974' elevation of - the Auxiliary Building s

102-12/88-

d ( i Table 41, Definition of Wolf Creek Building and Location Codes (Continued) Mu Descriotions

19. BORICRM Boric Acid Tank Room, located on the 2000' elevation of the Auxiliary Building

20. CBST Control Building Staircase

21. CCPA Centrifugal Chargir.g Pump A Room, located on the 1974' elevation of the Auxiliary Building

22. CCPB Centrifugal Charging Pump B Room located on the 1974' elevation of the Auxiliary Building

23. CCWA Component Cooling Water System Loop A Area, located on the 2026' elevation of the Auxiliary Building

24. CCWB Component Cooling Water System Loop B Area located on the 2026' elevation of the Auxiliary Building 2$. CR Control Room, located on the 2047' elevation of the Control p

Building

25. CST Condensate Storage Tank, located in the yard

26. CSTRhl Condensate Storage Tank Valve Room, located in the yard

27. DGA Diesel Generator A Room, located on the 2000' elevation of the Control Building

28. DGB Diesel Generator B Room, located on the 2000' elevation of the Control Building

29. ELECRh1 Room containing Rod Control CAB and RX Trip Switchgear, located on the 2026' elevation of the Auxiliary Building

30. ESFPh1HSEA ESF Pumphouse Room containing Loop A ESW Pump

31. ESFPMHSEB ESF Pumphouse Room containing Loop B ESW Pump

32. ESFRh11 ESF Switchgear Room No.1

33. ESFRh12 ESF Switchgear Room No. 2

34. ESWVVHSA ESWS Valve House containing Loop A ESW Piping, located in the yard

35. ESWVVHSB ESWS Valve House containing Loop B ESW Piping, located in the

\\v yard 103 12/88

j Table 41. Definillon of Wolf Creek Building and Location Codes (Continued) Codes DescrIntions

36. FPHXA-Fuel Pool Cooling Loop A Heat Exchanger Room, located _on the 2000' elevation of the Fuel Building

37. FPIIXB Fuel Pool Cooling Loop B Heat Exchanger Room located on the-2000' elevation of the Fuel Building _

i

38. LCBLRM Lower Cable. Spreading Room, located on the 2032' elevation of the Control Building

39. LDHX Letdown Heat Exchanger Room, located on the 1974' elevation of 9

the Auxiliary Building 40, MDAFWA Motor Driven Auxiliary Feedwater Pum 2000' elevation of the Auxiliary Building p A Room, located on the-

41. MDAFWB Motor Driven Auxiliary Feedwater Pump B Room, located on the 2000' elevation of the Auxiliary Building _

42 MSTNLAD Main Steam Tunnel containing Lines A & D, located on the 2026'- elevation of the Auxiliary Building - (

43. = MSTNLBC Main Steam Tunnel containing Lines B &-C located on the 2026' elevation of the Auxiliary Building

44. NELECPRM North Electrical Penetration L Room located on the 2026' elevation -

of the Auxiliary Building -

45. NG03C Room containing _480V-MCC NG03C, -located on"the 204T elevation of the-Auxiliary Building.

.i

46. NG04C Room containing 480V-MCC NG04C, located: on-the 2047' elevation of the Auxiliary Building

47. NPENRM North Piping Penetration Room, located _on the 2000' elevation of-the Auxiliary Building-

48. PDP Positive Displacement Charging Pump ~ Room, located on the 2000'.-

elevation of the Auxiliary Btulding

49. PPCHSEN North Pipe Chase, located on the 1988' elevation of the Auxiliary Building

-50. PPCHSES South Pipe Chase, located on thei1988_'_ elevation of the Auxiliary Building.

51. - RC Reactor Containment 104-12/88

i b Table 41. Definition of Wolf Creek Building and -Locallon Codes (Continued) Cod (s

!).escriotions

52. RHRA RHR Pump A Room,1xated on the 1974' elevation of the Auxiliary _

Building 53, RHRB RHR Pump B Room, located on the 1974' elevation of the A r.iliary Building 54 RHRHXA RHR A Heat Ex.: hanger Room, located on the'2000' and 2026t ' . elevations of the Auxiliary Building

55. RHRHXB RHR B Heat Exchanger Room located on the 2000' and 2026' elevations of the Auxiliary Building

-l

56. RWST Refueling Water Storage Tank, located in the yard

57. RWSTVLVRM Refueling Water Storage Tank Valve Room, located in the yard

58. SBDRM1 DC Sv itchboard Room No.1, located on the 2026' elevation of the Control Building i O

59. SBDRM2 DC Switchboard Room No. 2, located on the 2026' elevation of the D

Control Building. 60, SBDRhi3 DC Switchboard Room No. 3, located on the 2026' elevation of the Control Building -

61. SBDRM4 DC Switchboard Room No. 4, located on the 2026' elevation of the Control Building

-j

62. SEALHX Reactor Coolant Pump Seal Heat Exchanger Room, located on the 2000' elevation of the Auxiliary Bu Jding

63. SELECPRM South Electrical Penetration Room, located on the'2026' elevation of the Auxiliary Building

64. SIA -

Safety Injection Pump A Room, located on the 1974' elevation of the Auxihary Building

65. SIB

- Safety _ Injection Pump B Room, located on the 1974' elevation off the Auxthary Building

66. SLFLTRM Seal Filter Room, located on the 2000' elevation of the Auxiliary Building.

67, -SPENRM South Piping Penetration Room, located on' the 2000' elevation of the Auxiliary Building 105 12/88

.1 l Table 41. Definition of Wolf Creek Building and Location Codes (Continued) Codes Descrintions

68. TDAFW Turbine Driven Auxiliary Feedwater Pump Room, located on the 2000' elevation of the Auxiliary Building-

69. TLSF Top Level of the Spent Fuel Pool, located on the 204T elevation of -

the Fuel Building

70. UCBLRM Upper Cable Spreading Room, located on the 2073' elevation of the v

Control Building .106, 12/88- = ___________=_--__:- __:__

TABLE 4 2. PARTIAL LISTING OF COkDONENTS BY LOCATION [ \\ AT WOLF CREEG (/ LOCATION SYSTEM COMPONENTn COf.1P TYPE Ys74 Cb ESW E5W 23 MOV 19 74 C B E5W F.SW 25 MOV 197400 ESW E5W 37 MOV 1974CB ESW E5W 39 MOV 1974 C B ESW E5W 41 MOV 1974C0 ESW ES W 24 MOV 19 74 CB E5W ESW 26 MOV is74GB E5W E b438 MOV 197400 E5W ESW 40 MOV 1974C6 ESW E 5W-42 MOV 2326 AL CCW CCW53 MOV 20a6AB CCW CCW 15 MOV 2026AB CCW CCW54 MOV 4 2026A6 CCW CCW 16 MOV v AFWPPCMSE AF W AFW 35 MOV AhnPPCM5E AFW A'::W 31 MOV A-WPPLM5E AFW AFW 34 MOV A-APPCM5E AFW AF W-30 MOV A A WPPCHSE AFW AFW 36 MOV AF W PP CHSE AFW AFW 32 MOV AFWPPCH5E AFW AFW 33 MOV AFWVLVA AFW AFW 7 MOV-Y NVLVB AFW AF W-9 MOV AFWVLVC AF W AFW 11 MOV AFWVLVD AFW AFW 5 MOV BATRM1 EP BT 11 BATT SATRM2 EP BT 12 BATT BATAM3 EP BT 13 BATT BATRM4 EP BT 14 BATT [ \\ ( BiiRM CCP GCP Bil TK 'w, 107 12/88

n l ,m TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION / T AT WOLF CREEK (CONTINUED) Q) \\' LOCAilON SYSTEM coMPONENf iD 1 COMP TYPE B. T RY CCP CCP 6603A MOV B4 T RM CCP CCP 0603B Mov CCEA CCP CCP P1A MDP CCFA CCP GCP-112D MvV CCFB CCP CCP P1B L1DP CCP6 CCP CCP 112E MOV l CC V, A CCW CCW PIA MDF GC V A -CCW CCW PIC MDP 'u CCVv A ESW ESW 51 MOV CCWe CCW CCW P1B MDP C C V, e CCW C C W.P1 D M'I C C Vi c EbW ESW 52 MOV CST AFW AFw CST TK fx f ) CSTRY AF W AF W.CS T TK w/ p DGA EP MCC 3D i MCC~ Daa EP DG-8 DG DGB EP MCC 4D MOC ESFPMHSEA ESW ESW P1A MDP ESFPMMSE6 ESW ESW PIB MDP k ESFRM1 EP BUS NG01 BUS ESFRM1 EP T RAN-AN Go t TRAN ESFRM1 EP BUS ND01 BUS ESFRM1 EP C B-1 CB ESFRM1 EP BUS NGO3 BUS ESERMI EP TRAN XNG03 TRAN i ESFRM1 EP MCC)A MCC ESFRM1 EP BUS PG21 BUS ESFRMI EP TRAN XPG21 TRAN ESFRM2 EP BUS NG02 BUS j 108 12/88 1

l TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATIOt1 ,.,s (V ) AT WOLF CREEK (CONTINUED) LOOAT 60N SYS10Y j COMPON.NT ID COMP l TYPE ESERM2 EP MN-XNGo2 TRAN 0 E6FRM! EP l US NB02 9US 4 ~ EdFRws EP C5. CB ESF RM2 EP BUS hGM ~ ~ DUS ~ ' ESFRM2 Tv ~ TRAtexNaK TRAN EbfRM2 N MCCEA MCC ESFRM2 EP ' BUS PG22 BUS ESFRMs EP TRAN APG22 TRAN MJAW A AF W AFW PMA MOP NOA; W b AFW AFW PMB Mi'I NELECPRM EP MCCiT MCC NE6ECPRM EP MCC 1B MCC NELECPRM EP MCC 3T MCC ~ (A i NGS3C EP MCC3G UCC NG04C EP MCC E MCC l NPENRM CCP CCP 6601 A MOV NPENRM CCP CCP 8801B MOV NFENRM ECCS SI8802A MOV NPENRM PAHR CC 31 MOV NPENAM PAHR CC-47 MOV i NPENRM PAHA CC 49 MOV NPENRM PAHR CS4 MOV N AFW SG 1C SG K AFW SG-1 B SG RC AFW SG-1 A SG W AFW SGID SG RC ECCS RM 6811A MOV N ECCS RH-8811 B MOV s RC PAHR FANA FAN / ) M PAHR CC43 MOV (V 109 12/88 l

TABLF 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION AT WOLF CREEK (CONTINUED) V LOCATION SYSTEM COMPONENilD i COMP ~ TYPE ~ R; PAHR CC45 MOV RO PAHR FANC FAN PAMR FANB FAN N PANR CC-34 MOV N PAMR CC 36 MOV I 4S PAHR FAND FAN N PAHR C S-1 MOV N PAHR CS-1 MOV N RCS SG-1 A SG RO RCS RH 8701 A MOV E RCS RM 8702A MOV T ROS RM 87018 MOV '87 RCS RH-8702B MOV ,IN R0 RCS RC-455A NV RCS AC-456A NV R0 ROS RC 8000A MOV K hCS RC-80000 MOV RO RCS P2R-HIR-A HIR N NS PZR-HTR-B HTR ) K RCS SG-1B SG RO RCS SG 1C SG ~ N RCS SG10 So RMM ECCS RM P1A MOP-EdB ECCS RM PIB MDP RnRnAA ECCS RM HX1A Hx knRHxA ECCS RH-8804A MOV 3 RMAMAA ECCS RH 8716A MOV RHRei AB ECCS RH-Hx1B HX RHRHAB ECCS RH 8716B MOV m. I \\ SBDRMI EP DP NK01 PNL k,/ 110 12/88

_- -.. ~.. - TADLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION AT WOLF CREEK (CONTINUED) , o LOCATION b r5 f E M COMPONENT ID COMP TYPE b li M il TV 60 2s BC ~ bbDRM) EP DP N A01 PNL bbD6Mt EP PNL NN01 PNL SbDhM1 EP INV 11 4HV bkD4VI EP PNL NNQ1 PNL SbD4M1 EP 1RAN ANN 05 1RAN bbDhMg EF DP NA02 PNL bbDRMt EP bC 12 BC 'WI EP DP N A02 PNL WP.'; EP PNL NNO2 PNL 78.KM2 EP PNL NNO2 PNL SED 4vi EP INV12 INV SbDRMJ EF DP N A03 PNL BC 23 BC SEDRM) EP ( W 4M3 EP DP N A03 PNL SbDhMS EP PNL NNO3 PNL SbDRMJ EP INV 13 INV SbDRM) EP PNL NNO3 PNL SBDRM4 EP DP NA04 PNL SbDRM4 EP BC 24 BC SBDRM4 EP DP N A04 PNL SBDRM4 EP PNL NN04 PNL SEDhM4 ~EP 6NV 14 INV SBDhM4 EP PNL NN04 PNL SBDRM4 EP TRAN XNN06 TRAN bELECPRM EP MCC 41 MCC SELECPAM $9 MCC2B MCC SELECPRM EP MCC 2T MCC-6;A ECC5 SI6923A MOV b SIA ECCb Si4806A MOV \\%J { 111 12/88 .. -. ~.. - _.,

--m__.. i 4 1 TABLE 4 2. PARTIAL, LISTING OF COMPONENTS BY LOCATION AT WOLF CREEK (CONTINUED) LUCATiON b t ST E M COMPONENT :D COMP TYPE 5,A ECC5 Sb6624 MOV s!A ECCh bl4607A W~ b,A ECCS 664607B MOV 5iA ECC5 StP1A MDP 5.A ECCS $l682tA MOV SiA ECC5 51'662tA MOV b.A FANR CS PtA MDP StA FAHR C54 MOV 5b ECCS 5469230 MOV ECCS 5166066 MOV 56 ECCS 5.46210 MOV $6 ECCS 56.PiD MDP bib ECC5 56462tb MOV S4B ECCS RH 8804D MOV + 5ts F/ xR CS PtB MDP 5b FAHR C53 MOV .j SPENRM ECC5 544635 MOV SPENRM ECC5 516602B MOV SPENRM FAHR C042 MOV SPENAM PAHR CC 48 MOV SPEARM FAHR CC40 MOV SPENRM PAMR C512 MOV TDAEW AF W AFW TOP TDP TDAFW AFW AF W.312 MOV ( 112 12/88

Wolf Creek I

5. IllllLIOGRAPIIY FOR WOLF CREEK

1. NUREG-(K)hl, " Safety Evaluation Report Related to the Operation of Wolf Creek Generating Station," USNRC, June 1985.

2, NUREG 1136 " Technical Specifications for Wolf Creek Generating Station, Unit 1," USNRC.

3. Rosco, J.. "SNUPPS Auxiliar ' Feedwater System Reliability Study Evaluation,"

NUREG/CR-2458, S AND81 2596, Sandia National Laboratories, January 1982. I a .113-12/88 l l' ,____-.__._._,_,_._,,_.m.,_

Wolf Creek APPENDIX A DEFINITION OF SYMilOLS USED IN Tile SYSTEM AND LAYOUT DRAWINGS A 1. SYSTEM DRAWINGS A 1.1 Fluid System Drawings The simplified system drawings are accurate representations of the majo'r now paths in a system and the important interfaces with other fluid systems. As a general rule, small Guid lines that are not essential to the basic operation of the system are not shown in these drawings. Lines of this type include instrumentation lines, vent lines, drain lines, and other lines that are less than 1/3 the diameter of the connecting major flow path. There usually are tw o versions of each Duid system drawing; a simplified system drawing, and a comparable drawing showing component locations. The drawing conventions used in the Guid 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 side; of the vessel. Horizontal lines always dominate and break vertical lines. ( ^1 Component symbols used in the fluid system drawings are defined in Figure A 1. Most valve and distinguish amon] pump symbols are designed a allow the reader to

, 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 overpressure protection function. Ne attempt has been made to define the specific type of valve (i.e., as a globe, gate, butterfly, or other specine type of valve). Pump symbols distinguish between cenairugal and positive displacement pumps and between types of pump drivts (i.e., motor, turbine, or engine). Locations are identined in terms of plant loct tion 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 underground pipe runs). Component locations that are n

• known are indicated by placing the (p) components in an unshaded (white) zone.

V The primary flow path in the system is highlighted (i.e., bold white line) in the location version of the Guid system drawings. I14 12/88

-.~.. A1.2 Electrical System Drawings The electric power system drawings focus on the Class IE portions of the plant's electric 3cwer system. Separate drawings are provided for the AC and DC portions of the Class 13 system. There often are two vers ons of each electrical system drawingt a simplified system drawing, and a comparable drawing showing component locations. The drawing conventions used in the electncal system drawings are the following: Flow penerally is top to bottom In the AC power drawings, the interface with the switchyard and/or offsite

rid is shown at the top of the drawing.

n the DC power drawings, the betteries and the interface with the AC power system are shown at the top of the drawing.

Vertical lines dominate and break horizontal lines. Component symbols used in the electrical system drawings are defined in Figure A 2. Locations are identified in terms or plant location codes defined in Section 4 of this Sourcebod. Locations are indicated by shaded " zones" that are not intended to reoresent the actual room geometry. Locations of discrete components represent the actual physical location of the component. ,O The electrical connections (i.e., cable runs) between discrete components, as shown on the electrical system drawings, DO NOT represent the actual cable routing in the plant. Component locations that are not known are indicated by placing the discrete components in an unshaded (white) zone. A 2. SITE AND LAYOUT DRAWINGS A 2.1 Site Drawir.gs A p.eral view of each reactor site and vicinity is presented along with a simplified site plan snowing 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 sea e drawings should be consulted for this purpose. Labels printed in bold uppercase correspond to the location codes defined in Section 4 and used in the component data listings and system drawings in Section 3. Some additional labels are included for information and are printed in lowercase type. A2.2 Layout Drawh:gs Simplified building layout drawings are developed for the portions of the plant that contain components and s./ stems 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. Liyout drawings generally are not develored for other buildings. O Symbols used ir. the simplified layout drawings are defined in Figure A 3. Major Q rooms, stairways, clevatois, and doorways are shown in the sim fied layout drawings however, many interior walle have been omitted for clarity. The b ilding layout drawings, 115 12/88

Wolf Creek are approximately to scale, should not be used to estimate room size or distances. As-built scale drawings for should be consulted his purpose. Labels printed in uppercase bolded also correspond to the location codes defined in Section 4 and used in the component data listings and system drawings in Section 3. Some aditional labels are included for infonnation and are pnnted in lowercase type. A3. APPENDIN A ItEFERENCES 1. Heddleson, F.A., " Design Data and Safety Features of Commercial Nuclear Power Plants.", ORNL NSIC 55, Volumes 1 to 4 Oak Ridge National Laboratorv. Nuclear Safety Infonnation Center, December 1973 (Vol.1), January 1972 (Vol. 2), April 1974 (Vol. 3), and March 1975 (Vol. 4) \\ a 116 12/88 l

• ~b- (Opt N CLC 5

~ D) VALVI RCV (CPIN CLC$tD) O O. MOTOR OPER&TtD WALVE. MOV WOTOR 0PERATED (OP E N 'C L O$ t D) 3 WAY V Alvt. MOV (CLO$tD PORT M AY V ART) N (b ... SOLfNDID OPER ATED VALYL $0V L > 30LIN0lD.0PtR Af tO y r7 -~ q c p g wir.(O g g g; 3.way yatyt, 30y 4 i (CL0ttD PORT MAY V ARY) Y HYDR AULIC VALVI. HV L L HYDR AULIC NON RETURN _ (OPEN CLO$t0) 4 9 VALVE. HCV (CPEN'CLO$tD) I c c _g, _ PNEUMATIC VALVE. NV PNtVMATIC NON RETURN (O P E N -C L O S I D) VALVE. NCY (OPEN' CLOSED)- i CHECK YALVE. CV M SAFtTY VALVE. SV l (CLO S E D) i 1 d i O* O th POWER OPER ATED RELitF W ALyt, h POWER.0PER ATED RWLIEF V ALVE, i dk' SOLENDID PlLOT TYPt. PORV dh PNEUM ATIC ALLY CPER ATED. PORV 'f 3 (CLOSED) OR DUAL FUNCTION S AFtTYiR E LIF F YALVE. $NV (CLottD) 4 r f CENTRIFUC AL CENTRIFUG AL MOTOR DRIVEN PUMP. MDP T7;9amt. DRIVEN PUMP TDP '\\ / / l i POSITIVE Di$PL ACE MENT MOTOR DRIVEN PUMP. MDP POSITIVE DISPL AC EME NT

== TUR8INE. DRIVEN PUMP TDP I \\ / I \\ Figure A 1. Key To Symbols in Fluid System Drawings l 117 12/88 ~-

~... / l RE ACTCR yt$$tL - RV UAIN CONDINSIA*COND PWR$WR Y J _[gp NtAT t CHANotR Mr WEC H ANaC AL DRAFT L: C00LINC TOWER t, I h $Tf AM TO WATEM AIR COOLINQ Unit + ACV l l OR w t.tt R f o Sit AM Ht At IRCHANGER (It i tIDW AiF R HE ATER, DR AIN COOLtR, f1C.)

• HX l

D w. lYl cp tahr. tx SPR AY N0llLE8

• SN aoaaaaaa v

i r-RUPfWRE DiSt RD p ORIFICE OR c ( Figure A 1. Key To Symbols in Fluid System Drawings (Continued) 118 12/88

C 8 ~ (- j CpAC TUR0iNE Ot ht R ATOR. TQ B ATTERY. D ATT j AC Dit St L Ot htR ATON DO l I I l on CiRCVIT OREArtR CD C 8 (CPIN CLOSID) g )..., y gp g,,,{3 INTER 10(KtD 1 CIRCylt (,RE AKtRS e CD 1 S WITCH. SW AUTOM ATIC ON ON OININ M I DI C~ TP ANSFER SWITCH ATS DIS C ONNE C T DI VIC f eq (OP t NICL O S E D) M ANU AL TR ANSFtR S WITCH

• MTS l

twlTCH0f AR BUS. BU$ Ch [ (P t/ 5 ha"Et ! woTOR CONTROL CENTER. MCC o n yo $.,* " TR ANSFORMER TR AN em CR OiSTR;JUTION P ANEL

• PNi S ATit RY CH ApotR (RECTIFitR). BC o

i r G 1 4 w-CR RELAY CONTt?TS FUSt. FS F (OPEN CLOSE D) I I ELECTRIC MOTCH. MTR y MOTOR OENER ATOR. MO o Figure A 2. Key To Symbols in Electrical System Drawings 119 12/88

. _. _.. _ _ _._.~__ _._ _ -- _. -... _ ~ _ i

O y

STAIRS g SPIRAL y STAIRCASE 0.Down LADDER (q g ELEVATOR u. up D e Down ] HATCH OR OPEN AREA GRATING DECK (NO FLOOR) + PERSONNEL DOOR --t

• EQUIPMENT DOOR O

EE Sh RAILROAD TRACKS x FENCE LINE x O TANK / WATER AREA ~ Figure A 3. Key To Symbols In Facility Layout Drawings -120 12/88

APPENDIX 11 DEFINITION OF TERMS USED IN Tile DATA TAllLES 'Iemas appearing in the data tables in Sections 3 and 4 of this Sourcebook are defir.,i as follov,s: SYSTEM (also LOAD SYSTEM) AP anociated with a particular system description in the Sourcebook have tha . ode in the data base. System codes used in this Sourcebook are the folle Co9 Definition RCS Reactor Coolant System FW Auxiliary Feedwater System 11P liigh pressure injection System (part of the Emergency Core Cooling System) CS Containment Spray LP Electric Power System AC Auxiliary Coolant Component Cochng Water System RW Raw Water System VA Containment Air Cooling System COMPONENT ID (also LOAD COMPONENT ID) - The component identi0 ration (!D) code in a data table matches the component ID that appears in the corresponding system (9 drawing. The component ID generally begins with a system preface followed by a (,) component number. The system prefacc 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 component number appearing in the plant piping and instrumentation drawings (P&lDs) and electrical one line system drawings. LOCATION (also COMPONENT LOCATION and POWER SOURCE LOCATION) - Refer to the location codes defined in Section 4. COMPONENT TYPE (COMP TYPE) Refer to Table B 1 for alist of component type codes. POWER SOURCE The component ID of the power source is listed in this field (see COMPONENT ID, ateve), 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 component may have more than one power source (i.e. a DC bus powered from a battery and a battery charger). POWER SOURCE VOLTAGE (also VOLTAGE) The voltage "seen" by a loarl of a power source is entered in this field. The downstream (output) voltage of a transformer, mverter, or battery charger is used. (~N !vI 121 12/88

i l Wolf Creen 1:\\1EltGl'.NCY LOAD GROUP (EMERG LOAD GROUP) AC and DC load groups r tot electneal divisions) are defined as appropriate to the slant. Generally,d of a kind loadAC load gro are identified as AC/A, AC/B, etc. The emergency loac group for a thir j (i.e. a ' swing" load) that can be powered from either of two AC load groups would be i identified as AC/All. DCload group follows similar naming conventions, f I i l i l l i i 9 122 ~ 12/88 l

TAllLE 11 1. COMPONEN'l TYPE CODES CON 1PONENT COMP TYPE VALVES. Motor operated valve MOV Pneumatie (air operated) valve NV or AOV Hvdraulie valve HV $61enoid-operated valve SOV Manual valve XV Check valve CV Pneumatic non retum valve NCV Hydraulle non return valve HCV Safetv valve SV Dual' function safety / relief valve SRV Power operated relief valve PORY (pneumatic or solenoid operated) PUMPS: Motor driven pump (centrifugal or PD) MDP Turbine-driven pump (centrifugal of PD) TDP Diesel-driven pump (centrifugal of PD) DDP OTHER FLUID SYSTEM COMPONENTS: O Reactor vessel RV 's Steam generator (U tube or once-through) SG Heat exchanger (water to water IL\\', HX or water to air HX) Cooling tower CT Tank TANK or TK Sump SUMP Rupture disk RD Onfice 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: Diesel generator DG Gas turbine generator GT Battery B A*. T i N. 123 12/88 a

TAllLE D.I. COMPONENT TYPE CODES (Continued) CON 1PONPNT 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 j Battery charger (rectifier) BC or RECT Invener INV Uninterruptible power supply (a unit that may UPS include battery, battery charger, and inverter) Motor generator MO Circuit breaker CB Switch SW Automatic transfer switch ATS Manual transfer switch MTS t .i 6 n i i I l i j 4 i I !ev 1 j 121 12/88' _ -}}