ML20070Q433

Nuclear Power Plant Sys Sourcebook,Millstone 3

ML20070Q433
Person / Time
Site:	Millstone
Issue date:	01/31/1989
From:	Finn S, Lobner P SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY
To:	NRC
References
CON-FIN-D-1763, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-89-1019, NUDOCS 9103290080
Download: ML20070Q433 (111)

Text

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1 SAIC 88/1019 stS REGO eyT NUCLEAR POWER PLANT B SYSTEM SOURCEBOOK 21 <n# .. e ; o% @.~ $e me WATERFORD 3 50 382 Editor: l'eter Lohner Author: Stephen Finn Prepared for: U.S. Nuclear Regulator,v Commission Washington, D.C. 205E5 Contract NRC 03 87 029 FIN D. 763 0 L i. -s_- ....--...,rm,-. .x-_,

i i i Waterford 3 j TAllLE OF CONTENTS l Section PaEs 1 S U h t h 1 A R Y D ATA ON PL A NT............................................ 1 i 2 IDENTil'! CATION OF SIMILAR NUCLEAR POWER PLANTS.... 1 3 S Y S TE M I NFOR h 1 ATI ON.................................................. 2 3.I Reactor Coolant S ystem (RCS)................................ S 3.2 Emergency Feedwater System (EFS) and Secondary S te am Relie f S yste m (S SRS)................................... 14 3.3 Emergency Core Cooling System (ECCS)................... 20 3.4 Charging System................................................. 29 3.5 Instrumentation and Control (I & C) Systems................ 36 3.6 Elee tric Powe r Sy ste m.......................................... 39 3.7 Com sonent Cooling Water System (CCWS)................. 51 3.8 Auxi inry Component Cooling Water System (ACCWS)... 60 4 PL A NT I N FOR h1 ATI ON....................................................65 4.1 S ite and B uildin g S ummary..................................... 65 l 4.2 Facility Layou t Dra wings....................................... 65 'p 4.3 Sec ti on 4 R e ference s............................................65 ( 5 BIBLIOGR APilY FOR WATERFORD 3 POWER STATION......... 93 APPENDIX A Definition of Symbols Used in the System and Layout Drawin gs.............. 94 APPENDIX B Definition of Terms Used in the Data Base Tables..... 101 1 O v i 12/88-

_ _ _ _ _. _ _ _ ~ _ ~.. _ _ i Waterford 3 I LIST OF FIGURES Figure Pags 31 Cooling Water Systems Functional Diagram for Waterford 3............ 7 3.1 1 Elevation View of the RCS of a Typical Combustion Engineering P1 ant.............................................................................. 10 3.1 2 Wat e rford 3 Reactor Coolan t S ystem........................................ I1 3.1 3 Waterford 3 Reactor Coolant System Showing Component Locations........................................................................ 12 3.2 1 Waterford 3 Emergency Feedwater System................................. 17 3.2 2 Waterford 3 Emergency Feedwater System Showing Component laations........................................................................ I8 3.3 1 Waterford 3 High Pressure Safety Injection System....................... 24 3,3-2 Waterford 3 Hi;h Pressure Safety injection Sy.9em Showing Component Locations.......................................................... 25 3.3-3 Waterford 3 Low Pressure Safety injection System....................... 26 3.3-4 Waterford 3 Low Pressure Safety injection System Showing Component Locattons.......................................................... 27 3.4 1 Waterford 3 Chargin g Sys tem............................................... 31 3.4-2 Waterford 3 Charging System Showing Component Locations.......,,, 32 3.4 3 Waterford 3 Boric Acid Makeup System................................... 33 3.4 4 Waterford 3 Boric Acid Makeup System Showing Component Loc a t i o n s....................................................................... 34 2 3.6 1 Waterford 3 4160 and 480 VAC Electric Power System................. 42 3.6 2 Waterford 3 4160 and 480 VAC Electric Power System Showing Component Locations.......................................................... 43-3.6 3 Waterford 3125 VDC and 120 VAC Electric Power System............. 44 3 3.6 4 Waterford 3125 VDC and 120 VAC Electric Power S S howin g Compone nt Location s..........................ystem. 45 3.71 Waterford 3 Component Cooling Water System........................... 53 p) Waterford 3 Component Cooling Water System Showing 3.7 2 Component Locations.......................................................-56 i il 12/88

_ ~. _ _ _ _ Waterford 3 1 lST OF FIGUIRES (continued) Figure Pagg 3.8 1 Waterford 3 Auxiliary Component Cooling Water System................ 62 3.S 2 Waterford 3 Auxiliary Component Cooling Water System S howing Componen t Locations.............................................. 63 41 General View of Waterford Site and Vicinity......................../..... 66 4-2 Waterford 3 Sim plified Flot Flan............................................ 67 43 Wat erford 3 Reactor B uilding Section Views.............................. 68 44 Waterford 3 Reactor Auxiliary Building Section Views.................. 70 45 Waterford 3 Fuel liandling Building Secdon Views...................... 73 46 Waterford 3 Turbine Building Secdon Views.............................. 75 4-7 Waterford 3 Reactor, Reactor Auxiliary, and Fuelllandling B tilding s. Ele vation 35' 0"................................................. 77 48 Waierford 3 Reactor and Reactor Auxiliary Buildings, Elevation C 4' 0", and Fuel liandling Building. Elevation l' O..................... 78 \\ 4-9 Waterford 3 Reactor, Reactor Auxiliary, and Fuel Handling B uildin gs, Eleva tion 2 l ' 0".................................................. 79 4-10 Waterford 3 Reactor Reactor Auxiliary, and Fuel Handling B uildin g s. Ele vation 35' 0".................................................. 80 4 11 Waterford 3 Reactor, Reactor Auxiliary, and Fuel Handling B uildings. Ele v ation 4 6' 0"..............................................,.. 81 4 12 Waterford 3 Reactor, Reactor Auxiliary, and Fuel Handling B u ildin gs, Ele varion 69' 0"................................................. 82 l 4 13 Waterford 3 Reactor, Reactor Auxiliary, and Fuel llandling B uildin gs, Ele vation 91' 0"................................................. 83 A1 Key to Symbols in Fluid Sys te m Drawings................................ m A2 L Key to Symbols in Electrical System Drawings........................... 99 A-3 Key to Symbois in Facility Layout Drawings.............................. 101- \\ iii 12/88 a. 7 ~

Waterford 3 LIST OF TAllLES lO V Tahh-P.agt 31 Summary for Waterford 3 Systems Covered in this Report.............. 3 3.1-1 Waterford 3 Reactor Coolant System Data Summary for S e l e c t ed Com po n e n t s......................................................... 13 i 3.2 1 Waterford 3 Emergency Feedwater System Data Summary for S e l e c t e d Com po n e n t s......................................................... 19 1 3.3 1 Waterford 3 Emergency Core Cooling System Data Summary for S e l e c t e d Co m po n e n t s........................................................ 28 l 3.4 1 Waterford 3 Charging System Data Summary for 2 S e l e c t e d Com po n e n t s....................................................... 35 3.6 1 Wnterford 3 Electric Power System Data Sununary for Selected Components.................................................................... 46 3.6 2 Partial Listing of Electrical Sources and Loads at Waterford 3.......... 48 3.7 1 Waterford 3 Component Cooling System Data Summary for Se le c te d Com po ne nt s......................................................... 59 3,8 1 Waterford 3 Auxiliary Component Cooling Water System Data 1 S u m m ary for S e iee t ed Com po ne n t s,........................................ 64-41 Definition of Waterford 3 Building and Location Codes................. 84 42 Partial Listing of Components by 1.ceation at Waterford 3............... 88 B1 Compon e n t Type Cod e s...................................................... 102 ) 4 t iv 12/88

f l\\ CAUTION The information in this report has been developed over an extended period of time baed on a site visit, the Final Safety Analysis Report, system and layout drawings, and other published infonnation. To the best of our i i knowledge, it accurately reflects the plant configuration at the time the information was obtained, however, the information in this document has not been independently verified by the licensee or the NRC. NOTICf! This sourcebook will be periodically updated with new and/or replacement pages as appropriate to incorporate additionalinfonnation on this reactor plant. Technical errors in this report should be brought to the attention of the following: hir, h1 ark Rubin U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation - Division of Engineering and Systems Technology hiail stop 7E4 Washington, D.C. 20555 With copy to: - hir Peter Lobner hinnager, Systems Engineering Division Science ApplicationsInternationalCorporation 10210 Campus Point Drive San Diego,CA 92131 (619)458 2673 Correction und other recommendea changes should be submitted in the femi-of marked up copies of the affected text, tables or figures. Supporting documentation should be included if possible. O v. 12/88

i WATERFORD 3 RECORD OF REVISIONS l I ilEVISION ISSUC COhthtENTS 0 12/88 Original tepon O vi. -12/88 .} . -,. ~ ~.... - - -. - ~. - - -....

Waterford 3 WATERFORD 3 SYSTEM SOURCEBOOK This sourcebook contains summary information on Waterford 3 Summary data on this plant are presented in Section 1, and similar nuclear power plants are identified in Section 2. Information on selected reactor plant systems is presented in Section 3, and the site and building layout is illustrated in Section 4. A bibliography of re ports that describe features of this plant or site is presented in Section 5. Symbols used in (1e system and layout drawings are defined in Appendix A. Tenns used in data tables are defined in Appendix B. 1.

SUMMARY

DATA ON PLANT Basic information on the Waterford 3 nuc! car power plants are listed below: Docket number 50 382 Operator leuisiana Power and Light Company Location Taft, Louisiana Commercial operation date 9/85 Reactor type PWR NSSS vendor Combustion Engineering, Inc, t Number of loops 2 "~ - _ Power (MWt/MWe) 3410/1104 Architect engineer Ebasco Containment type Steel cylinder with trinfon:ed concrete shield building 2, IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS Waterford 3 utilizes a Combustion Engineering nuclear steam supply system and a steel containment vessel surrounded b_ y a concrete shield buildLng. Other Combustion Engineering type PWR plants in the United States include: Fort Calhoun l Maine Yankee Palisades Millstone 2 Calvert Cliffs 1 & 2 St. Lucie 1 & 2 ANO2 San Onofre 2 & 3 Palo Verde 1,2, & 3 WNP3 Waterford 3 has a similar number of auxiliary feedwater, charging, and high-pressure injection pumps as most other C E plants, 1 1/89

Waterford 3 3. SYSTEM INFORMATION This section contains descriptions of selected systems at Waterford 3 in terms of general function, operation, system success criteria, major components, and support systeni requirements. A summary of major systems at Waterford 3 is presented in Table 3-

1. In the " Report Section" column of this table, a section reference (i.e. 3.1, 3.2, etc.) is provided for all systems that are described in this report. An entry of "X" in this column mer.ns that the s column, a cross ystem is not described in this report. in the "FSAR Section Reference" reference is provided to the section of the Final Sdety 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 relationships that exist among cooling water systems required for safe shutdown are shown in Figure 31. Details on the individual cooling water systems are provided in the report sections identified in Table 31. O r J 2 -12/88 4 a I,. r y,y., c' y,, r-- - - +,

.m 3 [ j \\ 1 Table 3-I. Summary of Waterford 3 Systems Covered in this Report Generic Plant-Specific Report FSAR Section System Name System Name Section Reference Reactor IIcat Removal Systems l Reactor Coolant System (RCS) Same .t 1 5 Auxiliary Feedwater (AlW) and Emergency Feedwater 32 10.4.9 Secondary Steam Relief (SSR) System (EFS). Systems Same Emergency Core Cooling Systems Safety injection System (SIS) (ECCS) - Ifigh-lYessure Injection Iligh Pressure Safety 3.3 6.3 j & Recirculation Injection System (IIPSI) - Low-pressure Injection Iew Pressure Safety 3.3 6.3 & Recirculation Injection Systerr (LPSI) 1 Decay IIeat Removal (DilR) Shutdown Cooling System 3.3 9.3.6 System (Residual Ileat Removal (RilR) System) Main Steam and Power Conversion Main Steam Supply System. X 10 Systems Condensate and Feedwater System. Circulating Water System i OtherIIcat Removal Systems. None identified X Reactor Coolant Inventory Control Systems - ' Chemical and Volume Control System Same 3.4 9.3.4 i (CVCS) (Charging System) ECCS See ECCS, above eT E x t ..)

Tat >Ie 3-1. Summary of Waterford 3 Systems Coserrel in this Report (Continued) Generi Plant Npecific Report FSAR Section System Name Ssstem Name Section Reference Containment Systems Containment Sane i 6 Containment IIcat Renx> val Systems - Containment Spray System danc X 6.2.2 l - Containment Fan Cooler System Containment Cmling System X 6.2.2 Containment Nmnal Ventilation Systems See Containment Cooling X 6.2.2 System above Combustible Gas Control Systems Same X 6.2.5 Reactor and Reactisity Control Systems u Reactor Core Sane X 4 - Control Rod System Control Element Drive X 4 Mechanisms (CEDM) t Boration Systems See CVCS,above Instrument'ation & Control (I&C) Systems Reactor Protection System (RPS) Reactor Pmtective Systems (RPS) 3.5 7.2 Engineered Safety Feature Actuation Sane 3.5 7.3 System (ESFAS) -. Remote Shutdown System Auxiliary Contml Panel 3.5 7.4 i3 M CC

Table 3-I. Summary of Waterford 3 Systems Cmcred in this Report (Contimiedi Generic Plant-Specific Report FSAR Section Ssstem Name System Name Sectiori Rcrerence Instrumentation & Control (I&C) Systems (continued) Other I&C Systems Reactor Regulating Systans X 7.6. 7.7 Support Systems Class IE Electric Power System Same 3.6 8.2. 8.3 Non Class 1E Electric Power System Same 3.6 S.2. X.3 Diesel Generator Auxiliary Systems Same 36 8.3.1. u,5 I - ' Component Cooling Water (CCW) Sane 3.7 9.2.2 System -- Service Water System (SWS) Not applicable - Other Cooling Water Systems Auxiliary Component Cooling 3.8 9.2.2 Water System (p.CCWS). i Essential Services Chilled Water X 9.2.9 ? System. l Turbine Closed Cooling Water X 9.2.7 System j Fire Protection Systems Same X 9.5.1 i Room IIeating. Ventilating, and Air-Control Room Air-Conditioning X 9.4 Conditioning (liVAC) Systems System, Fuel IIandling Building Ventilation System, Turbine Building Ventilation System, Reactor Building 4 Ventilation System Instrument and Service AirSystems Compressed AirSystem X 9.3.1 - - Refueling and Spent Fuel Systems Same X 9.1 i i l

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/ \\ l i \\ ( '\\ ] Q,) q) OTHER SAFEGUARD r T ( ) HEAT LOADS WET COOLITJG b TOWERS ACCWS I ( ) ( ) SHUTDOWrJ 4 COOll?JG HEAT EXCHArJGERS I ( / V r 3 r 3 r 3 f 3 DRY COOL!?JG ACCWS liEAT DIESEL e CCWS TOWERS EXCHATJGER E GETJERATORS P q ) J J J r h ~a e ESCWS ( ) A V ESSEPJTIAL ROOM COOLERS ( ) l ACCWS - Auxisary Component Codrg Water System G CCWS - Comt Cochng Water System M ESCWS - Esswial Services Chaed Wa'ar System m Figure 3-1. Cooling Water Systems Functional Diagram for Waterford 3

._ ~ Waterford 3 3.I REACTOR COOLANT SYSTEM (RCS) 3.1.1 Sntem Funcilon The RCS transfers heat from the reactor core to the secondary coolant system via the steam generators. The RCS pressure boundary also establishes a boundary against the uncontrolled release of radioactive material from the reactor core and primary coolant. 3,1.2 Sntem Definition The RCS meludes: (e) the reactor vessel, (b) two parallel reactor coolant loops, J each containing one steam generator and two reactor coolant pumps, (c) a pressurizer connected to one of the reactor vessel outlet pipes (hot legs), and (d) associated piping out to a suitable isolation valve boundary. An elevation view of a two loop Combustion Engineering RCS is shown in Figure 3.1 1. Simplified diagrams of the RCS and important system interfaces are shown in Figures 3.12 and 3.13. A summary of data on selected RCS components is presented in Table 3.1-1, 3.1,3 Sutem Goeratinn During power operation, circulation in the RCS is maintained by two reactor coolant pumps in each of the two reactor coolant loops. RCS pressure is maintained within a prescribed band by the combined action of pressurizer heaters and pressurizer spray. RCS coolant inventory is measured by pressurizer water level which is maintained within a prescribed band by the chemical and volume control system (CVCS). At power, core heat is transferred to secondary coolant (feedwater)in the steam generators. The heat transfer path to the ultimate heat cink is completed by the main steam and power conversion system and the circulating water system. Following a transient or small LOCA (if RCS inventory is maintained), reactor g core heat is still transferred to secondary coolant in the steam generators. Flow in the RCS is maintained by the reactor coolant pumps or by natural circulation, The heat transfer path x to the ultimate heat sink can be established by using the secondary steam relief system to vent main steam to atmosphere when the power conversion and circulating water systems are not available. If reactor core heat removal by this alternate path is not adequate, the RCS pressure will increase and a heat balance will be established in the RCS by venting steam or reactor coolant to the quench tank through the pressurizer relief valves. There are two simple spring loaded safety valves on the pressurizer. Following a large LOCA, reactor core heat is dumped to the containment as reactor coolant and ECCS makeup water s containment can act as a heat sink; however, pills from the break. For a short period, the the containment cooling systems must operate in order to complete a heat transfer path to the ultimate heat sink. 3.1.4 Sntem Success Criteria The RCS success criteria can be described in terms of LOCA and transient mitigation, as follows: An unmitigatible LOCA is not initiated. If a mitigatible LOCA is initiated, then LOCA mitigating systems are successful. If a transient is initiated, then either: RCS integrity is maintained and transient mitigating systems are successful, or RCS integr4y is not maintained, leading to a LOCA like condition (i.e. stuck open safety or relief valve, reactor coolant pump seal failure), rnd LOCA mitigating systems are successful. OV S 12/88

Waterford 3 3.1,5 Comoonent Information A. RCS

1. Volume: 10,300 ft3 (without pressurizer)

2. Nonnal operating pressure: 2250 psig

11. Pressurizet

1. Volume: unknown C. Reactor Coolant Pumps (4)

1. Rated flow 99,0(X.) gpm @ 310 ft. head (134 psid)

2. Type: Vertical Centrifugal D. Safety Valves (2)

1. Set pressure: unknown

2. Relief capacity: unknown E. Steam Gererators (2)

1. Type: Venical shell and U Tube F. Pressurizer lleaters

1. Capacity: Unknown 3.1,6 Suonort Systems and Interfnees A. Motive Power l. The reactor coolant pumps are supplied from Non Class lE switchgear.

2. The pressurizer heaters are Class 1E AC loads that can be supplied from the standby diesel generators as describea in Section 3.6.

11. Reactor Coolant Pump Seal Injection Water System The chemical and volume control system supplies seal v

.a cool the rea:!or coolant pump shaft seals and to maintain a controlled imcakage of seal watec into the RCS. Loss of seal water flow may result in RCS leakage through the pump shaft seals which will resemble a small LOCA. L O V 9 12/88

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s ~ 3 l Table 3.1-1. Waterford 3 Reactor Coolant System Data Summary for Selected Components l} COf.1POf1EtJT ID C O F.t P. LOCATIOfA POWER SOURCE VO LTA G E POWER SOURCE E P.1 E R G. TYPE HCS-1501 B flV HC L OC ATIO tl I.OAD GRP._ flCS-1502B MOV HC MCC-3831 -S 480 4KVSWGHMB AC/H RCS-1503A HV HC ~ llCS-1504 A f.10V HC MCC-3A31-S 480 4KVSWGHMA AC/A HCS-1516AB tJV HC HCS-2501 AB rJV HC HCS-HV HV HC C 4 G }! 1 i

_.. ~ _ _ _. _ _ _ _ _ _ _ Waterford 3 3.2 EMERGENCY FEEDWATER SYSTEM (EFS) AND SECONDARY STEAM RELIEF SYSTEM (SSRS) 3.2.1 Svctem Function The EFS provides an independent means of supplying feedwater to the steam generators in addition to the main feedwater system. The EFS is intended to provide a sufficient supply of feedwater to permit the plant to operate at hot standby after a transient - or small break LOCA for eight hours followed by an orderly plant cooldown to the point where the shutdown cooling system may be initiated. The Secondary Steam Relief System (SSRS) provides a steam vent path from the steam generators to the atmosphere, thereby - completing the heat transfer path to an ultimate heat sink when the main steam and power conversion systems are not available. The EFS and SSRS constitute an open loop fluid system that provides for heat transfer Nm the RCS following transients and small break

LOCAs, 3.2.2 Svstem Definition The EFS consists of two half capacity motor driven pumps, one full capacity

-steam turbine driven pump, associated piping, controls and instrumentation. All pumps can supply both steam generators The primary source of auxiliary feedwater is the condensate storage pool (CSF), The secondary or backup source of auxiliary feedwater is the Auxiliary Component Cooling Water System (see Section 3.8). The EFS pumps discharge into a distribution header to permit any, pump to supply feedwater to either steam generator. From the distribution header waar is carried by two pipelines, one to feedwaterline A and the other to feedwater line B, Each pipeline contains four isolation valves, arranged as two parallel paths each containing two valves. The valves are pneumatically-operated and fallin the'open position on loss of power, The turbine driven pump can be supplied with steam from either steam generator. The SSRS consists of six safety-valves-and one pneumatically operated atmospheric dump valve on each of two main steam lines, Simplified drawings of the EFS and the SSRS are shown in Figures 3.2-1 and 3,2 2, A summary of data on selected EFS components is presented in Table 3.2-1, i 3,2,3 Svstem Oneration During normal operation the EFS is in standby, The system is actuated b Emergency Feedwater Actuation Signal (EFAS) under one of the following conditions:y an (a) low steam generator (SG) level coincident with no low pressure trip present for that SG, or (b) low SG level coincident with a preset differential pressure present between the two SGs, with the higher pressure associated with the SG to be fed. The EFAS causes all EFS 4 pumps to e, determines which SG is intact and opens the EFS valves to that SG, and - pre.wnts a high level condition by closing the EFS valves when w ater level is reestablished

r. cove the low level trip serpoint. Steam generator levelis maintained automatically after c

initiation of the EFS. Manual control of the EFS pumps and valves is also possible from ~i the control rcom and from the auxiliary control panel. The EFS is shutdoivn manually. 'The turbine driven pump or both motor driven pumps together are designed to L provide 700 gpm flow to the steam generators (Ref,1, Sec.10.4.9.2).- In order to remove decay heat 440 gpm must be provided to the steam generators upon loss of normal i feedwater (Ref. 2). Steam for the EFS :aroine driven pump is supplied from either or [ -both steam generatorsitaken upstream of the' main steam isolation, valves; Each supply line I contains a turbine steam supply valve (TSSV) which is pneumatically operated, fail o3en. The turbine is a single stage, noncondensating, horizontal split casing unit, designec for startup from a cold condition, and will operate with steam generator pressuren from 1135 to i 50 psig. The turbine discharges to atmosphere. 14 12/88 F T w v + m-ne a.rv4 r-+-r r ys. - w a we.+ g "a w fe e r+ b t-te s Af / v v v fm -rrtee r a weie e e ar + meno-it r -er e 1er a-e e g 1p wr e rs=*

Waterford 3 The only dedicated source of water for the EFS pumps is the Condensate Storage Pool (CSP)_ inside the Reactor Auxiliary Building, with a capacity of 195,000 gallons. There are two separt.te connections to the pool, each sized to provide sufficient Dow to all three J umps. As a backup, the Auxiliary Component Cooling Water (ACCW) pumps can deliver water from the two 180,000 gallon wet cooling tower basins to the two EFS pump = Gun lines. This alignment is performed manually. 3.2.4 System Success Criterin For the decay heat removal function to be successful, both the EFS and the SSRS must operate successfully. The EFS success criteria are the following: - Makeup to any one steam generator provides adequate decay heat removr.1 from the Reactor Coolant System. In order to remove decay heat 440 gpm must be provided to the steam genetwors (Ref. 2). Either the turbine driven pump or both motor driven pumps can provide adequate Dow. The condensate storage tank or the ACCW system is an adequate source of water for the EFS pumps. 3.2.5 ('omnonent information A. Motor-driven EFS pumps A, B (N

1. Rated now: 350 gpm @ 2673 ft. head

,t]-

2. Rated capacity: 50%

3. Type: Horizontal centrifugal -

B. Turbine-driven EFS pump AB

1. Rated now: 700 gpm @ 2673 ft. head

2. Rated capacity: 100%

3. Type: Horizontalcentrifugal C. Condensate Storage Pool

1. Capacity: 195,000 gallons -

3.2.6 Suonort Sntems and Interfacis A. Control Signals - - 3

1. Automatie The EFS pumps are automatically actuated upon_ receipt of an Emergency Feedwater Actuation Signal (EFAS) under the following -

conditions: Low SG level coincident with no low pressure trip for that SG Low SG level coincident with a preset differential pressure present between the two SGs =

2. Remote manual The EFS can be operated from the control room (

auxiliary control -

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3. ' Manual'~

The EFS can be manually aligned to the alternate water source, the wet cooling tower basins. B. Motice Power

1. The motor driven EFS pumps and motor operated valves are Class'lE loads that can be supplied from the standby diesel generators as described in Section 3.6._

2. The turbine driven pump is supplied with steam from the main steam lines of either steam generator upstream of the main steam line isolation-valves. The power and controls for the valves associated with this-pump receive power from the Class lE DC system.

C, Other

1. The Auxiliary Component Cooling Water (ACCW) S stem is' an alternate water source for the EFS pumps (see Section 3.8).L __

2. Lubrication, cooling, and ventilation are provided locally for the EFS.

pumps.

3. Systems for EFS pump room cooling have not been identified.

3.2.7 Section 3.2 References

1. Waterford SES Unit No. 3 Final Safety Analysis Report Louisiana Power &

Light Company, New Orleans, Louisiana, December,1986.-

2. "Waterford Steam Electric Station. Unit':3-Auxiliary Feedwater System..

Reliability Study Evaluation," NUREG/CR-2219, September,1981. l l. l 16 12/88-- i ., - a. c..,,-,,_,.. .-,,-....L.m..;.. A

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Table 3.2-1. Waterford 3 Emergency Feedwater System Data Summary for Selected Components COf.1POf 3EfJ T ID C o r.1 P. LOCATIOf4 POWER SOURCE VO LT A G E POWER SOURCE E fA E R G. TYPE LOC ATIOfJ LOAD GRP. El-W-416 MOV IDPMHM UNKNOWTJ e.KVSWGRMAB AC/AB E F-W-CSP TATJK CSP EF W-PA MDP MDPMRMA BUS-3A3 S 4160 4KVSWGRMA AC/A El W-PAB IDP IDPMRM Et W-PB MDP MDPMRMB BUS-3B3-S 4160 4KVSWGHMB AC/B MS-609A NV MSIMENW l MS 610B NV MSTMENE SG-1 SG ITC SG-2. SG liC G t [ 4 OC

Waterford 3 3.3 EMERGENCY CORE COOLING SYSTEM (ECCS) !p V; 3.3.1 Svstem Function The ECCS, or Safety injection System (SIS), is an integrated set of subsystems that perform emergency coolant injection and recirculation functions to maintain reactor core coolar.t inventory and adequate decay heat removal following a LOCA. The coolant injection function is performed during a relatively short term period after LOCA initiation, followed by realignment to a recirculation mode of operation to maintain long term, post-LOCA core cooling. Heat from the reactor core is transferred to the containment. The heat transfer path to the ultimate heat sink is completed by the containment heat removal systems. 3.3.2 Svetem Definition The emergency coolant injection (ECI) function is perfomied by the following ECCS subsystems: Safety Injection Tanks (SITS) High Pressure Safety Injection (HPSI) system Low Pressure Safety Injection (LPSI) system There are four safety injection tanks, one attached to each cold leg, that discharge their contents when RCS pressure drops below the tank pressure. The HPSI system consists of three moto. driven pumps that deliver water to two injection headers. The headers direct flow to the four cold legs. The HPSI pumps can also inject into the hot legs. The LPSI system consists of two motor driven pumps that deliver water to the four cold legs. The LPSI pumps also provide the shutdown cooling function. The Refueling (3 Water Storage Pool (RWSP) is the water source for the HPSI and LPSI pumps. i'" ) Simplified drawings of the HPSI system are shown in Figures 3.3-1 and 3.3 2. The LPSI system is shown in Figures 3.3-3 and 3.3 4. 3.3.3 Svstem Ooerntion During normal operation, the ECCS is in standby. HPSI pumps A and AB are normally aligned to injection header A while HPSI pump B is normally aligned to injection header B. The ECCS automatically goes into operation upon indication that a significant breach in the RCS boundary has occurred. The injection mode of operation is initiated upon a Safety injection Actuation Signal (SIAS). A SIAS is produced upon any two coincident lc / pressurizer pressure or two coincident high containment pressure signals, or produced manually from the control room. - An SIAS starts the HPSI and LPSI pumps, opens their cold leg isolation valves, and sends an open signal to the SIT isolation valves, even though they are already open when the plant i,s at operating pressure. The SITS constitute a passive injection system, discharging their contents automatically when RCS pressure drops below the tank pressure. Adequate borated water is supphed in the four tanks to rapidly cover the core, with the contents of one tank assumed to be lost through the break. During injection the HPSI and LPSI pumps take suction on the RWSP and deliver borated water to the four cold legs. The HPSI pumps are designed for small breaks when the RCS is still at high pressure, while the LPSI pumps are designed to respond to large breaks. When RWSP inventory is down to 10% the recirculation phase begins. The t LPSI pumps are secured and the HPSI pumps are realigned to take suction from the SIS sump. For long-term recirculation the HPSI pumps are aligned for simultaneous hot and cold leg injection. When shutdown cooling entry conditions are met the LPSI pumps are aligned to take suction from the hot legs through the shutdown cooling line, discharge m [Q through the shutdown cooline heat exchangers, and return flow to the RCS through the \\ 20 12/88

Waterford 3 cold leg injection lines, lieat is transferred in the shutdown cooling heat exchangers to the g Component Cooling Water system. 3.3.4 Svstem Success Crlferia LOCA injection requires both the emer;ency coolant injection and emergency coolant recirculation functions to be accompFshec. The ECl success criteria for a small LOCA in the reactor coolant pump discharge is the following (Ref,1, Section 6.3.3.3.1): a j 3 of 4 safety injection tanks provide makeup as RCS pressure drops below tank pressure, and One high pressure safety injection pump deliver 75% ofits rated now to the RCS, and One low pressure safety injection pump deliver 50% of its rated flow to the RCS, and One charging pump deliver 50% ofits rated flow to the RCS The ECl success criteria for a small LOCA in the RCS hot leg is the following (Ref.1, Section 6.3.3.3.1): i 4 of 4 safety injection tanks provide makeup as RCS pressure drops below tank pressure, and One high pressure safety injection pump deliver 100% of its rated flow to the RCS, and One low pressure safety injection pump deliver 100% of its rated Gow to the RCS, and One charging pump deliver 100% of its rated now to the RCS \\ The ECl success criteria for a large LOCA in the reactor coolant pump discharge is the following (Ref.1, Section 6.3.3.2.1): 3 of 4 safety injection tanks provide makeup as RCS pressure drops below tank pressure, and Two high pressure safety injection pumps deliver 75% of their rated flow to the RCS, and One low pressure safety injection pump deliver 50% of its rated flow to the RCS, and The ECI success critena for a large LOCA in other areas is the following (Ref,1, Section 6.3.3.2.1 ): 4 of 4 safety injection tanks provide makeup as RCS pressure drops below tank pressure, and Two high pressure safety injection pumps deliver 100% of their rated flow to the RCS, and One low pressure safety injection pump deliver 100% of its rated flow to the RCS, and If the ECl success criteria is met, then the following large LOCA ECR success criteria will apply (Ref.1, Section 6.3.2): At least one high pressure safety injection purup is realigned for recirculation and takes a suction on the containment sump and injects into the RCS cold legs. , ( 21 12/88

Waterford 3 C ( 3,3,5 Comoonent Information A. High Pressure Safety injection pumps A, B, AB

1. Rated flow: 380 gpm @ 2830 ft head (1227 psid)

2. Rated capacity: 100 %

3. Type: multistage, horizontal, centrifugal B. Low Pressure Safety injection pumps A, B

1. Rated flow: 4050 gpm @ 342 ft. head (148 psid)

2. Rated capacity: 1(4 %

3. Type: Single stage, vertical, centrifugal C. Safety lajection Tanks (4)

1. Volume: 2250 ft3

2. Normal operating pressure: 610 psig D. Refueling Water Storage Pool

1. Capacity: 600,000 gallons 3.3.6 Suncort Systems and Interfaces A. Control Signals

1. Automatic The ECCS subsystems are automatically actuated by a safety injection n

actuation signal (SIAS). Conditions initiating an SIAS trip are: i V

a. Low pressurizer pressure

b. High contamment pressure

c. Manualactuation The SIAS automatically initiates the following actions:

starts the HPSI and LPSI pumps aligns the pumps for injecuon aligns the pump suction to the RWSP sends open signal to SIT isolation valves Switchover to the recirculation mode occurs automatically on low level in the RWSP. Remote manual An SIAS signal can be initiated by remote manual means from the main control room or from the auxiliary control panel. ECCS operation can be initiated by remote manual means. B. Motive Power

1. All ECCS motor driven pumps and motor operated valves are Class lE AC loads that can be supplied from the standby diesel' generators as described in Section 3.6.

OO 22 12/58

Waterford 3 'N C. Odier l. The HPSI pumps, LPSI pumps, and shutdown cooling heat exchangers are cooled by the Component Cooling Water System (see Section 3.7).

2. Lubrication is provided locally for the ECCS pumps and motors.

3. Systems for ECCS pump room cooling have not been identified.

3.3.7 Section 3.3. References

1. Waterford SES Unit No. 3 FS AR, Louisiana Power and Light Company, New i

Orleans, Louisiana, December,1986. I 4 l l l i i i I 4 4 i l l t i i l \\ i i 4

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s m Table 3.3-1. Waterford 3 Emergency Core Cooling System Data Summary for Selected Components COfAPOf1ENT ID C O fA P. L O C A TIOf1 POWER SOURCE VOLTAGE POWER SOURCE E fA E R G. TYPE LOC ATION LOAD GRP. SI-103A fiV VOEBA SI-103A flV VOEUA SI-104B flV VOEBB SI-154082 MOV 35 pef 4WG MCC-3B311 -S 480 4KVSWGRMB AC/B SI-1542A3 MOV 35PENWG MCC-3A311 -S 480 4KVSWGRMA AC/A SI-1544B4 MOV 35PENWG PACC-3B311 -S 480 41'VSWGRMB AC/B SI-1545B1 MOV 35PENWG FACC-38311-S 480 4KVSWGHMB AC/B SI-1546A2 MOV 35PENWG MCC-3A311-S 480 41;VSWGHMA AC/A Si-1547B3 MOV 35 pef 4WG MCC-3B311 -S 480 4KVSWGHMB AC/B SI-1548A4 MOV 35PENWG MCC-3A311 S 480 4KVSWGHMA AC/A SI-1550A1 MOV 35PENWG MCC-3 A311-S 480 4KVSWGHMA AC/A St-PA MDP SAFEGDA BUS-3A3-S 4160 4KVSWGHMA AC/A StPAB MDP SAFEGOA BUS-3AB3-S 4160 4KVSWGHMAB AC/AB SI-PB MDP SAFEGDB BUS-383-S 4160 4KVSWGHMB AC/B SI-RWSP TANK HWSP U 30

Waterford 3 l 3,4 Cll ARGING SYSTD1 \\ 3.4.1 System Function I The charging system is part of the Chemical and Volume Control System (CY CS). The CVCS is responsible for maintaining the proper water inventory in the l l Reactor Coolant System and maintaining water purity and the proper concentration of neutron absorbing and corrosbn inhibiting chemicals in the reactor coolant. The makeup function of the CVCS is required to maintain the plant in an extended hot shutdown condition following a transient. The ECCS (see.Section 3.3) provides makeup after a LOCA. t 3.4.2 Svstem Definition The CVCS consists of several subsystems that perform the functions of maintaining RCS inventory, chemistry and urity control, and reactivity control. The charging system consists of three positive dis lacement charging pumps that take suction from the volume control tank and inject into the RCS. The boric acid makeup system, consisting of two pumps, two storage tanks, and a boric acid batching tank, controls changes in reactor coolant boron concentration. Purification is accomplished by directing letdown flow from one cold leg through a series of heat exchangers, filters, and ion exchangers. Simnlified drawings of the CVCS, focusing on the charging portior, of the system. are shown in Figures 3.41 and 3.4-2. The boric acid makeup portion of the CVCS is shown in Figures 3.4 3 and 3.4-4. A summary of data on selected CVCS system components is presented in Table 3.4 1. 3.4.3 System Ooerntion During normal operation. including hot standby and power generation when the l RCS is at nonnal operating pressure and temperature, one charging pum is in operation with suction on the volume control tank (VCT). Letdown flow from co d leg 2B passes l through the tube side of the regenerative heat exchanger for an initial temperature reduction. The pressure is then reduced by a letdown control valve to the letdown heat exchanger operating pressure. Flow is then directed through the various filters and ion exchangers in l the purification system before being sprayed into the VCT where it is returned to the RCS by the charging pumps. Reactor coolant pump bleedoffis also directed to the VCT. The charging flow passes through the shell side of the regenerative heat exchanger for recovery of heat from the letdown flow before being returned to the RCS. Charging flow is split into two charging lines, to cold legs l A and 2A, and to auxiliary pressunzer spray. Concentrated boric acid solution, prepared in the boric acid batching tank,is stored in the two boric acid makeup tanks. Two boric acid pumps supply boric acid to the volume control tank or directly to the charging pu,mps suction. A gravit feed line directly from the borie acid tanks to the charging pumps is also provided. The oric acid makeup i system operates in four modes: (a) dilute, in which demineralized water from the primary water system is introduced into the VCT; (b) borate, in which boric acid is introduced; (c) manual blend, in which the flow rates of primary water and boric acid can be set to a desired concentration; (d) and automatic, in which a preset blended concentration is automatically introduced into the VCT upon demand from the VCT level controller. 3.4.4 Svstem Success Criterin The following success criterion is assumed for CVCS makeup (Ref.1, Section (m\\ 1 of 3 positive displacement charging pumps is required for adequate post-transient makeup to the RCS. 29 12/88

l= Waterford 3-2 2 of 2 boric acid tanks are required as a source of water for the charging pumps,

_ p supplied by either the associated boric acid pump or the gravity feed line.

L . An adequate injection path from the charging pump to the RCS,- s 3.4.5 Comnonent Informntion l L A. Charging pumps A, B, AB l

1. Rated capacity: 44 gpm

2. Normal discharge pressure: 2324 psig 3 Type: Positive displacement -

B. Boric acid pumps A,B : 1, - Rated capacity: 143 gpm @ 231 ft. head (100 psid)

2. Type: Horizontalcentrifugal C. Boric acid makeup tanks A B.

1. Volume: 11,800 gal.

D. -Volume control tank

1. Volume:: 4780 gal.

i 3.4,6 Suncort Systems and Interfaces - A,- Control Signalg

1. ' Remote manual The charging pumps, boric acid pumps, and associated motor operated' valves can be actuated by remote means from the control room and from the auxiliary control panel, B. Motive Power 1

The positive displacement charging pumps, boric acid pumps, and motor operated valves of the CVCS are Class IE AC loads that can be supplied i from the standby diesel generators as described in Section 3.6,- C, Other -1 Cooling _ water and lubrication for the charging and boric acid pumps are assumed to be provided locally,

2. Pump room cooling systems have not been identified; 3.4.7-Section 3.4 Rererences l. Waterford SES Unit No. 3 FSAR,~ Louisiana Power & Lighi Compan'y, New Orleans, Louisiana, December,1986.

A l ..j 4 i 30 -12/88 5

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% h M cJm I m.,, -.nA ; 4,,u...,. 1,,, A. 1 - viou. 4 i = T_._ x . iou - ..nA.. BAu PA 'd i E +D "JJE l ,'m. c-3. A r.s A 1 NOTE Ati ARE AS AFE AS$1%TC BASED tm PutNT t AYOff OfWWINr4 I Figure 3.4-4. Waterford 3 Boric Acid Makeup System Showing Component Locations

(m ym k v Table 3.4-1. Waterford 3 Charging System Data Summary for Selected Components I COMPOilEtiT n t LOCA TIOT3 POWER SOURCE VOLTAGE POWER SOURCE EMEPG. LOC A TIOTI LOAD GRP. BAM-PA !!AIKi1MA MCG-3A313 3 480 4KVSWGiliAA ACIA , BAf.1-PB BAIKilMB MCG-3 A3:2-S 480 4KVSWGHMA AC/A BATA-l KA Im. BATKHMA BAM-IKB I Afj[~ BAIKHMB CVC-106A FAOV UAIKitMA FACC-3B312-S 480 4KVSWGHMit AC/B CVC-107B fAOV BAIKilMB MCC-38311-S 480 4KVSWGHMB AC/B ~ CVC-112AB MOV 35HAB fACC-3A311-S 480 4KVSWGHMA AC/A CVC-PA MDP Ci1PMHMA BUS-3A3-S 4160 4KVSWGHMA AC/A CVC-PAB FADP CHPMHMAB BUS-3AB3-S 4160 4KVSWGHMAB AC/AB CV"-PB FADP CHPMHMB GUS-383-S 4160 4KVSWGHMB ACIB d J 4 i T'

Wat:rford 3 3.5 INSTRUMENTATION AND CONTROL (1 & C) SYSTEMS i 3.5,1 System Function The instrumentation and control systems consist of the Reactor Protective l System (RPS), the Engineered Safety Features Actuation System (ESFAS), and systems for the display of phant information to the operators. The RPS and the Engineered Safety Features Actuation System monitor the reactor plant, and alert the operator to take corrective action before specined limits are exceeded. The RPS will initiate an automatic reactor trip (scram) to rapidly shutdown the reactor when plant conditions exceed one or more specined limits. The Engineered Safety Features Actuation System will automatically actuate selected safety systems based on the specific limits or combmations of limits that are exceeded. A remote shutdown capability is provide to ensure that the reactor can be placed in a safe condition in the event that the main control room must be evacuated. 3.5,2 System Definition ~ The RPS includes sensor and transmitter units, logic units, and output trip relays that generate a reactor trip signal. The reactor trip signal deenergizes the control element drive mechanisms, allowing all control element assemblies (CEAs) to drop into the core. The Engineered Safety Features Actuation System includes independent sensor and transmitter units, logic units and relays that interface with the control circuits for the many different sets of components that can be actuated by this system. Operator instmmentation display systems consist of display panels in the control room and at the auxiliary control panel that are powered by the 120 t AC electric power system (see Section 3.6). 3,5.3 Svstem Ooerotion j A. RPS The RPS has four redundant input instrument channels for each sense parameter. A two-out of four coincidence of like trip signals n required to generate a reactor trip signal. The fourth instrument channelis provided as an installed spare and allows bypassing one channel while maintaining a two-cut-of-three system. Manual reactor trip is also provided. i l The fo!!owing conditions result in rer.ctor trip: I High linear power level High logarithmic powerlevel High local power density Low departure from nucleate boiling High pressurizer pressure Low pressurizer pressure l Low steam generator water level Low steam generator pres.sure l High containment pressure High steam generator water level Low ructor coolant flow Turbine trip Loss ofload Manual B. ESFAS p) The ESFAS alm utilizes a two-out of-four coincidence of like initiating trip g signah from four independent measurement channels, with two output actuation v M 12/88 r n- .s 1

t Waterford 3 1 i q trains. The ESFAS logic is similar to that of the RPS. The ESFAS generates I the following actuation signals: Safety injection Actuation Signal (SIAS) Containme. t Isolation Actuation Si,nal(CIAS) j t Containment Spray Actuation Signal (CSAS) Main Steam Isolation Signal (MSIS) Emergency Feedwater Actuation Signal (EFAS) Recirculation Actuation Signal (RAS) The actuation systems provide an actuation signal to each individual component in the required engineered safety features system. An individual component usually receives an actuation signal from only one output train. Components powered from the AB load group (see Section 3.6) receive an actuation signal from both output trains. C. Remote Shutdown Selected controls and instrumentation for safe shutdown of the reactor are provided at the auxiliary contol panel, located in area ACPL at elevation plus 21 feet of the Reactor Auxiliary Building. The transfer of control from the main control board to the auxiliary control panel is done manually by means of transfer switches mounted on auxiliary,anelslocatedin area RELAYRM on elevation plus 35 feet of the Reactor Auxi iary Building. An alarm is initiated in the main control room whenever any one of the transfer switches is operated ( Ref. 1). 3.S.4 Svstem Success Criteria d A. RPS The RPS uses hindrance logic (normal = 1, tri; - 0) in both the input and output logic. Therefore, a channe! will be in a trip state when input signals are lost, when control power is lost, or when the channel is temporarily removed from service for testing or maintenance (i.e. the channel has a fail safe failure mode). A reactor scram will occur upon loss of control power to the RPS. A reactor scram usually is implemented by the scram circuit breakers which must open in response to a scram signal. Typically, there are two series scram circuit breakers in the pcwer path to the scram rods. In this case, one of two circuit breakers must oper Details of the scram system for Waterford 3 have not been determined. B. ESFAS A single component usu lly receives a signal from only one ESFAS output i train ESFAS Trains A and B must be available in order to automatically actuate their respective components. ESFAS typically uses hindrance input logic (normal = 1, trip = 0) and transmission output logic (normal = 0, trip = 1). In this case, an input channel will be in a trip state when input signals are lost, when control power is lost, or when the channel is temporarily removed from service for testing or maintenance (i.e. the channel has a fail-safe failure mode). Control power is needed for the ESFAS output channels to send an actuation signal. Note that there may be some ESFAS actuation subsystems that utilize hindrance output logic. For these subsystems, loss of control power will cause p) system or component actuation, as is the case with the RPS. Details of the v ESFAS system for Waterford 3 have not been detemiined. %/ 37 12/88

Waterford 3 C Mantially initiated Protective Actions i\\ When reasonatje time is available..ertain protective actions may be performed manet.lly by plant personnel. The control room operators are capable of operating individual components using normal control circuitry, or operating groups of components by manually tripping the RPS or an ESFAS subsystem. The control room optrators also may send qualified persons into the operate components locally or from some other remote control location (plan i.e., the remote shutdown panel or a motor control center). To make these judgments, data on key plant parameters must be available to the operators. 3.5.5 Sunnort Systems and Interfaces A. Control Power

1. RPS The RPS input instrument channels are powered from separate 120 VAC uninterruptible power supply buses (see Section 3.6). It is assumed that the RPS output logic trains are powered from separate 125 VDC distribution panels.

2. Engineered Safety Features Actuation System The input instrument channels are powered from 120 VAC UPS buses, it is assumed that the A aad B output logic trains are powered from separate 125 VDC distribution panels.

3. Operator Instrumentation O

Operator instrumentation displays are powered from the 120 VAC vital l instrument buses. I 3.5.6 Section M References

1. Waterford 3 Final Safety Analysis Report, Section 7.4.1.5.

l l l I 38 12/88 ~

Waterford 3 3.6 ELECTRIC POWER SYSTEM 3.6.1 System Funel,gn The electne power system supplies power to various equipment ar.d systems needed for normal operation and/or response to accidents. The onsite Class lE electric power system supports the operation of safety class systems and instnimentation needed to establish and maintain a safe shstdown plant condition following an accident, when the nonnal electric power sources are not avmlable. 3.6.2 System Definition The onsite Class lE electric power system consists of three AC load groups. Diesel generator 3A is connected to 4160 VAd bus 3A3 S, and diesel generator 3B is connected to 4160 VAC bus 3B3 S. A third 4160 VAC bus,3AB3 S, can receive power from either bus 3A3 S or 3B3 S. but not from both simultaneously This hus supplies power to eqil' ment which is standby to equipment on the other buses. There are three 480 VAC power centers, bus 3A31-S which is connected to 4160 bus 3A3 S through transformer 3A31-S, bus 3B31 S which is connected to 4160 bus 3B3 S through transfonner 3B31 S, and bus 3AB31 S which can receive pown either power center 3A31 S or 31431 S, but not from both simultaneously Various motor control centers receive their power from the 480 VAC buses. The 480 VAC system also includes buses 3A32 and 3832 that supply power to the pressurizer heaters. The 125 VDC system is designed to provide a source of reliable continuous power for control and instrumentation and other loads. The 125 VDC system consists of three 60 cell batteries, each with its own battery chargers, load center, and distribution panels. The batteries, designated 3A S,3B S, and 3AB S are connected to load center buses 3A.DC S,3B DC S, and 3AB DC S, respectively. Each battery is provided with two battery chargers, which are supplied from 480 VAC motor control centers. The 120 voll uninterruptible (vital) AC system provides power to the Plant Protection S control and,vstem (RPS and ESFAS) instrumentation channels and to other safety related mstrumentation. There are four 120 VAC power distribution panels for the four Plant Protection System measurement channels and two panels for safety related control and instrumentation. Simplified one line diagrams of the 4160 VAC and 480 VAC electric power system are shown in Figures 3.61 and 3.6 2. The 125 VDC and 120 VAC 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 3.6-1, A partial listing of electric sources and loads is presenled in 1a 31e 3.6 2. l 3.6,3 System Ooernflort l Dunng normal operation, the Class 1E electric power system is supplied from the switchyard through two unit auxiliary transfonners. The emergency sources of AC power are the diesel generators. The transfer from the preferred power source to the diesel generators : accomplished automatically by opening the nonnal source circuit breakers and then rectargizing the Class lE portion of the e.ectric power system from the diesel generators. The DC power systera normally is supplied through the battery chargers, with the batteries " floating" on he system, maintaining a full charge. Upon loss of AC power, the entire DC load draws from the batteries. The batteries are sized to provide the maximum simultaneous combination of steady state and peak loads for a period of approximately I hour (Ref.1, Sec. 8.3.2.1.1). The 120 VAC consists of rectifier / inverters and distribution panels. Each O invener ls nonnally supplied through its rectifier from a 480 VAC MCC. Should this-supply fail the invener is automatically supplied from a 125 VDC bus. 39 '2/88

Waterford 3 ((" 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 grou 3s". Load group AC/A contains components powered either directly or indirectly from 4: 60 bus 3A3 S. Load group AC/B contains components powered either directly or indirectly by bus 3B3-S. Load grou) AC/AB contains components powered by 4160 VAC bus 3 AB3 S,480 VAC bus 3A331 S, or associated MCCs. Components receiving DC power are assigned to load groups DC/A, DC/B, or DC/AB, based on the battery power source. 3.6,4 System Success Crlierla 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 entena are defined as follows, without taking credit for cross ties that may exist between independent load groups: Each Class lE DC load group is supplied inidally from its respective battery (also needed for diesel starting) Each Class lE AC load group is isolated from the non Class IE system and is supplied from its respective emergency power source (i.e. diesel generator) Power distribution paths to essential loads are intact Power to the battery chargers is restored before the batteries are exhausted 1 3.6.5 Coff1Donent Informutlon A. Standby diesel generators 3A,3B

1. Maximum continuous rating: 4400 kW O

2. Rated voltage:4160 VAC

3. Manufacturer: Unknown B. Batteries 3A S,3D S,3AB S

1. Rated voltage: 125 VDC

'!. Cells: 60

3. Type: Lead acid 3.6.6 Suonort Systems and interfaces A. Control Signals 1, Automatic 2

The standby diesel generators are automatically started based on: Undervoltage on the nomial tus, loss of offsite power (LOSPW) Safety injection actuanon signal (SlAS)

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

B. DieselGenerator Auxiliary Systems

1. Diesel Cooling WaterSystem

) Heat from both diesel generators is transferred from a jacket water system to the Component Cooling Water System (see Section 3.7).

2. Diesel Starting System Bach diesel has an air starting system.

40 12/88

Waterford3 (A

3. Diesel Fuel Oil Transfer and Storage System j

A " day tank" supplies shon-tenn tap?roximately 2 hours) fuel needs of each v diesel, Each day tank can be replen shed from a separate diesel oil storage tank during engine operation. 1 Diesel Lubrication System Each diesel generato'r has its own lubrication system,

5. Diesel Room Ventilation System This system consists of e'xhaust 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-tenn operation of the diesel generatot, 3,6,7 Section 3.6 References

1. Waterford SES Unit No. 3 Final Safet,v Analysis Repon, Louisiana Power &

Light Company, New Orleans, Louistana, December,1986. O V 4l 12/88

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[ r m-r s [ I i wn ,.a w wn n e.a-em ma u...... x a.:, ww.,< ). Figure 3.6-2. Waterford 3 4160 and 480 VAC Electric Power System Showing Component Locations i i i 4 -

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• ge vac amo vec o.s ac

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• 2S VDC Desimm>Tm PA*JF [ 3A s PAfd t saft A 25 voc Desrat autm PaNFt 30, y

? 4 ~ t 4 ~ y n 120 VAC NiCI E AR e25 W OtSmiHIJTm rd5TMasF N7A fiORS Pa'E S 3aN E ,20 WAC edt3Ctf AR UPS BUS 3hEA $ ~ WES TM 9sF NT A TM t.P$ BLG 3tfB $ II II 120 VAC NUCl e A.* NSTRunaENT af SON I tM bAC NUctf AR l INSfft.M asTATm UPS 811$ 3asC S OPS Bus Sato S ,__6________.s________,

o n

o o u o ,m.Ac .AC o UPS 3A $ ,,,, Ac, , W 3As (pg 3g g, n_ u 2 2 i 2 l s s s = R e e z a 'ovacga;ag,'aa' l imvAcv,ra a,s3As ,,,,v.C vr,At ous,s ._.__...m. Figure 3.6-3. Waterford 3125 VDC and 120 VAC Electric Power System i

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= = e g M e e 2 W = I 170 VAC vtTAL BJS 3A S 120V MT m 3A01 120 VAC Vf7At aus yet S t........_.___....... - - -..... _ _ _ _ _ _ _...,4 fd.)T{, iIn $ GdAV,#1I $5 PIE Of ful Tin ( C Af.il[ eRJJTNG BE TVut i N ROr sh $ Figure 3.6-4. Waterford 3125 VDC and 120 VAC Electric Power System Showing Component Locations

m n p i Table 3.6-1. Waterford 3 Electric Power System Data Summary f for Selected Components [ i 1 COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. [ a' TYPE LOCATION LOAD GHP. I 3A I T-3A-S - BA I I - BATTRMA 125 DC/A l f BA I I-38-S BAII BAIIRMB. 125 DCB BC-3A1-S BC-4KVSWGR7f,A MCC-3A311-S 125 4KVSWGRMA DC/A f BC-3A2-S BC 4KVSWGRMA MCC-3A312-S 125 4KVSWGRMA DCA } 5 -381-S BC 4KVSWGRMB MCC-38311-S - 125 4KVSWGRMB DGB BC-382-S BC 4KVSWGhMB MCC-38312-S 125 4KVSWGRMB DC/B BUS-3A-3 BUS-4KVSWGRMA MCC-3A313-S 120 4KVSWGRMA AC/A BUS-3A-DC-S BUS 4KVSWGRMA BATI-3A-S 125 BAIIRMA DC/A BUS-3A-DC-S BUS: 4KVSWGRMA BC-3A1 -S 125 4KVSWGRMA DC/A 4 i BUS-3A-DC-S BUS 4..VSWGRMA BC-3A2-S 125 4KVSWGEWA DOA f BUS-3A-S BUS 4KVSWGRMA MCC-3A312-S 120 4KVSWGRMA AC/A { BUS-3A-S - BUS 4KVSWGRMA BUS-3A-DC-S ~ 120 4KVSWGRMA AC/A BUS-3A3-S BUS 4KVSWGRMA DG-3A 4160 DGA AC/A BUS-3A31-S BUS 4KVSWGRMA T RAN-3A31-S 480 4KVSWGRMA AC/A - BUS-3A32 BUS UNK-3A32 - TRAN-3A32 480 UNK-3A32 AC/A I BUS-3AB3-S BUS 4KVSWGRMAB BUS-3A3-S 4160 4KVSWGRMA AC/AB j BUS-3AB3-S BUS 4KVSWGRMAB BUS-383-S 4160 4KVSWGRMB AC/AB l' BUS-38-DC-S BUS 4KVSWGRMB - BATT-38-S, 125 BATTRMB DC/B j i-BUS-38-DC-S BUS 4KVSWGRMB BC-381-S 125 4KVSWGRMB DC/B j BUS-3B-DC-S BUS 4KVSWGRMB BC-382-S 125 4KVSWGRMB DC/B i BUS-38-S - BUS. 4KVSWGRMB MCC-38312-S 120 4KVSWGRMB AC/B I ? BUS-38-S 5 BUS 4KVSWGRMB MCC-38313-S 120 4KVSWGRMB AC/B f BUS-38 S BUS 4KVSWGRMB - BUS-38-DC-S 120 4KVSWGRMB AC/B BUS-383-S

BUS 4KVSWGRMB DG-3B 4160 DGB AC/B l

BUS-3831-S BUS 4KVSWGRMB IRAN-3831-S 480 4KVSWGRMB AC/B 1 BUS-3832 jBUS UNK-3B32 IRAN-3832 480 UNK-3832 AC/B j CB-3A-1 4CB-4KVSWGRMA AC/AB CB-3A-14 CB 4KVSWGRMA ACIA i 1 _ i

Table.3.6-1. Waterford 3 Electric Power SySten Data Summary for Selected Components (Continued) } i COMFOf3Ef4T ID COMP. LOCATIOtt POWER SOURCE VOLT A GE POWER SOURCE EMERG. TYPE LOCATIOt1 LOAD GRP. I CB-3AB-2 CB 4KVSWGFifAAB AC'AB l CB-3AB 6 CB 4KVSWGHfAAB AC'AB I CB-381 CB 4KVSWGU.18 AC/AB I CB-3B-15 CB 4KVSWGUAB ACB DG-3A DG DGA 4160 AGIA l DG-38 DG DGB 4160 AO13 MCC-3A311-S MCG 4KVSWGRMA BUS-3A31 -S 480 4KVSWGUAA AC/A MCC-3A312-S MCC 4KVSWGHMA GUS-3A31-S 480 4KVSWGGJA ACIA MCC-3A313-S MCC 4KVSWGRMA BUS-3A31-S 480 4KVSWGRMA AC/A MCC-38311-S MCC 4KVSWGHMB

BUS-3B31 -S 480 4KVSWGiMB

' ACB _ i MCC-3B312-S MCC 4KVSWGUAB BUS-3B31-S 480 4KVSWGUAB AGU '3 MCC-3B313-S MCC 4KVSWGRMB BUS-3B31-S 480 4KVSWGRMB AC13 TRAN-3A31-S IRAN 4KVSWGRMA l BUS-3A3-S 480 4KVSWGiMA AC/A { IRAN-3A32 TRAN UNK-3A32 BUS-3A3-5 480 4KVSWGRMA AC/A ( T RAN-3831-S TRAN 4KVSWGRMB BUS-383--S 480 4KVSWGRMB AC/B i TRAN-3832 MAN UNK-3832 BUS-383-S 480 4KVSWGRMB AC/B t I i t U z t

TADLE 3 0 2. PARTIAL LISTINO OF ELECTRICAL SOURCES AND LOADS AT WATERFORD 3 POM 4 VO;.T AGE E Mt.RG POWER SOURCE LOAD LOAD COMP COMPONENT SO A E LOAD GRD LOCATION SYSTEM COMPONENT ID TYPE LOCATION bAM4A S ist DC. A BATTRMA EP BUS 3A-DC S BUS 4 KVsWGRMA tMT4ed i t. t dub BATTRMB EP BUS-30 DC S BUS 46VSWGRM8 r s3A1 b 'a DC. A 4KVSWGRMA EP= BUS 4A DC S BUS 4 KV5WGRN% f PCOAs S 12S DC> A 4KVSWGRMA EP BUS 3A DC S BUS 4KVSWGRMA 6Cashb iit DC'B 4KYSWGRMB EP BUS 3B DC S BUS 48VSWGRMB R362 S 125 DC,8 4KVSWGRMB EP BUS 4B DC S BUS 4NYSWGRMB_ bus 3A DC-S 120 AC. A 4NV$WGRMA EP BU S-3A.S BUS 4KVSWGRMA bvS-3AJ b 4160 ACiA 4KVSWGRMA AC4 W ACCW PA MDP 4PENWG BU54A3 L 4ito A C<A dNv6WGRMA CCW CCW PA MDP CCWRMA t: u d.>A k b 4160 AC A 4%VSWGRMA CVCS CVCPA MDP CHPMRMA bh 4A&d 41 @ AC/A 4KV6WGRMA ECCS StPA MDP SAFEGDA L,5 3AJ b 4160 AC<A 4KYSWGAMA EFS EFW PA MDP MDPMRMA bvS4A3 S 4160 ACrAb 46V5WGRMA EP BUS-3AB3 S BUS 4KYS WGRMAB bud 3A) b 480 ACeA 4NVSWGRMA EP TRAN 3A31 S TRAN 4 KVSWGRMA s BV6 3A3 b 460 AC= A 4KV6WGRMA EP TRAN 3A32 TRAN UNN 3A32 bud 4A31 b db0 AC, A 4KV5WGAMA EP MCC4A311.S ACC 4KV5WORfAA bus 3A315 460 AC,A 4NVSWGRMA EP MCC4A312 S MCC 4AVSWGRMA bu6 3A31 d 460 ACIA 4KV6WGRMA EP MCC-3A313 S MCC 4 NVSWGRMA l EUS JAB 3 6 4160 AC-Ab 4KVSWGRMAB CCW CCW PAB MDP CCI AMAB bu5 3AB3 S 4160 AC AB ANV5WGRMAB CVCS CVC PAB MDP CHPMRMAB bud-3Ae3 5 4160 AC/AB 4 K VSWGRMAB ECCS StPAB MDP SAFEGDA EUS-3B*DC d 120 ACiB 4KVSWGRMB EP BUS 30 S BUS 4KVSWGhMB BUS 363 S 4160 AC B 4KVSWGRMB ACCW ACCW PB MDP 4PENWG BUS-aiti5 4160 A C:6 4AVSWGRMB CCW CCW PB MDP GCWRMB BUS 393 S 4160 AC B 4KvSWGRMB CVCS CVC PB MDP CHPMRMB bub 4b3 5 4160 AC,8 4KVSWGRMB ECCS StPB MDP SAFEGDB BVS 3B3-5 4160 AC B 4KVSWGRMB EFC EFW PB MDP MDPMRMB DU5463 S 4160 AC/AB 4NVSWGRMB EP BUS-3 AB3-S BUS 4KVSWGRMAB BU5463 6 480 AC-B 4KV5WGRMB EP TRAN 3B31 S TRAN 4KVSWGRMB BU54B3 5 4E0 AC B 4%VSWGRMB EP TRAN 3B32 TRAN UN% 3832 UU54bJ15 4eo AC:B 46V5WGRMB EP MCC 38311 S MCC 48VSWGRMB .;g 12/88

TABLE 3 6 2, PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT WATERFORD 3 (CONTINUED) b POM R VoilAGE EMERS POWER SOURCE LOAD LOAD COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION GuS 3b31 S 460 AC B 4%V6WGRMB EP MCC-3B312-S MCC 4KVSWGRMB buk3631 b 460 AC4 4KVSWGRMB EP MCC 3B313-S MCC 46VSWGRMB OG 3A 4153 AC;A DGA EP BUS 3A3 S BUS 4 KVSWGRMA DG 3B 41 % AC B DGB EP BUS-3B3-S BUS 4KVSWGRMB MCC-3A31 b 490 ' ACsA 4KVSWGRMA RCS RCS-1504 A MOV RC MC C-3 A311 6 460 AC/A eNVSWGRMA CVCS CVC 112AB MOV 35RAB MCC-3A311 S 4b0 AC/A 4NVSWGRMA ECCS SI1542A3 MOV 35PENWG MCC 3A3116 460 ACIA 4KVSWGAMA ECCS Si 154 2A3 MOV 35PENWG MCC-3A311 S 460 AC/A ANVbWGRMA ECCS SI 1546A2 MOV 35PENWG MGG-3A3M 5 450 AC'A 4NYSWGRMA ECCS SI 1546A2 VOV 35PENWG b%C4A3)1 s 4D A C< A 4NVSWGRMA ECCS SI 1548A4 MOV 35FENWG MCC 3A311 S 460 AC A ANVSWGRMA ECCS SI 1548A4 MOV 35PENWG MCC4A311 S 460 AC/A ANVSWGRMA ECCS Stt$50A1 MOV 35PENWG MCC-3A3M S 4B0 AC;A 46VSWGRMA ECCS SI1550A1 MOV 35PENWG MCC-3A311-S 125 DC, A 4NVSWGRMA EP BC-3Al S BC 4KVSWGRMA MCCOA312 S 400 AC/A 4NVSWGRMA CVCS BAM PB MDP BATKRMS MCCOA312-S 125 DC. A 4NVSWGRMA EP BC 3A2 S DC 4 NVSWGRN% MCC 3A312 6 120 AC/A 46VSWGRMA EP BUS 3A S BUS 4KVSWGRMA MCC-3A313 S 460 ACeA 4NVSWGRMA CVCS BAM-PA MDP BAT KRMA MCC 3A313-5 120 AC/A 4KVSWGRMA EP BUS-3A 3 BUS 4KVSWGRMA V 'C4A315 S 460 ACzA DRYCTA ACCW ACCW CTA FAN WETCTA MCCOA315-d 450 . AcaA DRYCTA CCW CCW CTA FAN DRYCTA MCC-3A3156 480 AC A DRYCTA CCW CCW CTA FAN DRYCTA MCC 3A315 S 460 AC/A DRYCTA CCW CCW CTA FAN DRYCTA MCC 3b316 483 AC.B-4NVSWGRMS RCS RCS-1502B MOV RC MCC4B311 S 460 A C, B ANVSWGRMS CVCS CVC 107B MOV BAlKRMB MCC 363116 4B0 AC/B 48VSWGRMB ECCS Si 154082 MOV 35PENWG McCOB3115 460 AC/B 4KVSWGRMB ECCS SI 1544B4 MOV 35PENWG M;C4B311 6 4B0 AC/B 4KVSWGRMB ECCS Sb1545B1 MOV 35PENWG MCC 3B311 S 460 AC/B 4KVSWGRMB ECCS Sb154783-MOV 35PE N WG h MCC-3BJ11 d 125 DC/B 4KVSWGRMB EP BC-3B1 S BC 4NVSWGRMS -49= 12/88

TABLE 3.6 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT WATERFORD 3 (CONTINUED) l POAEh VO lAGE E t/E RG POWER SOURCE LOAD LOAD COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT 10 TYPE LOCATION MCC-3b312 6 460 AC B 4AVSWGRMB CVCS CVC 106A MOV BATERiAA MCC 3b312-S 1:5 DC 8 46VSWGRMB EP BC 382 5 BC 45fSWGRMB MCC-36312 d 120 AC/B 4Kv5WGRMB EP BUS 38-S BUS 46VSWGRMB MJ.C 3B313 S 120 AC B 4KVSWGRMB EP BUS 3B S BUS 4KVSWGRMB McCQB315 S 400 AC/B DRYCTB ACCW ACCW CTO FAN WETCTB MCC-Sb315 6 4eo ace 8 DRYCTB CCW CCW CTD FAN DRYCTB MCC 383tb b 480 AC/B DRYCTB CCW CCW CTB FAN DRYCTB l'1CC363156 460 AC,8 DRYCTB CCW CCW CTS FAN DRYCTB TRAN 3A3t-S 4L0 ACsA 4Av5WGRMA EP BUS 3A31 S BUS 4KVSWGRh% TRAN 3A32 460 AC<A UNK 3A32 EP BUS 3A32 BUS UNN-3A32 1hAN Sc2315 460 AC S 4NvsWGRMB EP BUS 3B31 S BUS 4KVSWG4MB IRAN 3B32 460 AC 6 UN A 3B32 EP BUS 3B32 DVS UNK 3832 UNNNO A N AC/AB 4KVSWGRMA8 EFS EFW 416 MOV TDPMRM i n 50 12/M

Waterford 3 r-3.7 COMPONENT COOLING WATER SYSTEM (CCWS) (( 3.7.1 System Function The CCWS serves to remove heat from the rem :or auxiliaries and to transfer it to the cooling towers for rejection to the atmosphere. TM CCWS ensures continuous operation or safe shutdown of the plant under all modes of operation. 3.7.2 System DefinitioD The CCWS is a closed loop cooling water system that uses demineralized water buffered with a corrosion inhibitor to cool various components throughout the plant. The system includes three 100% capacity pumps, two heat exchangers. two dry cooling towers, one surge tank, and one chemical addition tank. The three CCW pumps supply a common header. The header distributes water into two pipelines, one to dry cooling tower A and CCW heat exchanger A, the other to dry cooling tower B and CCW heat exchanger B. Downstream of the heat exchangers the Dows are split to serve the various safety and non safety loads. Simplified drawings of the CCWS are shown in Figures 3.71 and 3.7 2. A summary of data on selected CCWS components is presented in Table 3.71, 3,7.3 System Goeration Dunng normal, shutdown, or refueling operating conditions, two CCW pumps are operating, supplying coohng water into common headers serving safety and non safety equipment. Upon receipt of a SIAS, the two redundant safety loops are automatically isolated from each other and the non safety loop is isolated from the safety loops. The outlet valve on the "A" shutdown heat exchanger remains closed but the outlet valve on the "B" shutdown heat exchanger goes full open automatically. Following isolation, separate f CCWS loops are fonned, each providing 100% of the heat removal capability necessary to ( shutdown the reactor. Each essential CCWS loop supplies one diesel generator, one essential services water chiller, two containment fan coolers, one liPSI pump (A or B), one LPSI pump, one containment spray pump, and one shutdown cooling hat exchanger. Loop A also serves the Post Accident Sampling System. The standby IIPSI pump AB is supplied from either CCWS loop A or B based on the loop assignment of the AD pum? in the liPSI system, in each loop heat can be removed by either the CCW acat exchanger or the dry cooling tower. In the heat exchanger, heat is transferred to the Auxiliary Component Cooling Water System (see Section 3.8). The CCW surge tank is connected to the suction side of the pumps, and accommodates fluid expansion and contraction in the system. The chemical feed tank pemtits manual on line addition of proper corrosion inhibitor. 3.7,4 Svstem Success Criteria Success criteria is given on a per loop basis. A given component must be cooled by its respective CCWS loop. The success criteria for each loop are (Ref.1): 1 CCW pump must operate in the respective loop either the CCW heat exchanger or the dry cooling tower must be available as a-heat sink piping and valves must provide an adequate path for the coolant. 3.7.5 Comoonent information = (p. A. Component Cooling Water pumps A, B, AB

1. Rated flow: 6800 gpm @ 145 ft head (63 psid) f V

2, Rated capacity: 100% 51 12/88 w v ~m-

Waterford 3 p

3. Type: Horizontal centrifugal U

lt Component Cooling Water heat exchangers A, B

1. Design duty: 40 x 106 Btu /hr (nonnal) 58.1 x 106 Btu /hr (accident)

2. Type: llorizontal, straight tube 3.7.6 Suonort Systems and Interfaces A. Control Signals

1. Automatic A SIAS sends a start signal to the CCWS pumps and closes appropriate valves to isolate the two CCWS loops.

2. Remote manual The CCWS can t,c operated from the control room or the auxiliary control panel.

13. Motive Power

1. The motor driven CCWS pumps are Class IE loads that can be supplied from the standby diesel generators as described in Section 3.6.

C. Other

1. Lubrication, cooling, and ventilation are assumed to be provided locally for the CCWS pumps, b

3.7.7 Section 3.7 References

1. Waterford SES Unit No. 3 Final Safety Analysis Report, Louisiana Power &

Light Company, New Orleans, Louisiana, December,1986, a v 52 12/88

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• y 12/88

CCWS SURGE TANK n %s -f f l ?A TO LOOP A RETURN LINE F (PAGE 2) > TO LOOP B RETURN LINE (PAGE 2) ED Figure 3.7-1. Waterford 3 Component Cooling Wate System (page 3 of 3)

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O O O r l 91 R A B l CCWS SURGE TANK O i 1 R k_. l t j l 69RAB l l a I i l I 46RAB l TO LOOP A i l RETURN LINE + (PAGE 2) + TO LOOP B RETURN LINE { (PAGE 2) I l PPCHASE = 4 i Figure 3.7-2. Waterford 3 Component Cooling Water System Showing Component Locations (page 3 of 3) i

~ e ~ \\s Table 3.7-1. Waterford 3 Component Cooling Water System Data Summary for ScicCled Components COtJPOtJEt3T ID COf1P. LOCATIOri POWER SOURCE VOLTAGE POWER SOURCE E f5 E R G. TYPE L OC ATIOtt TOAD G E CCV/ CIA CI DilVGIA CCV/ CI A f ATJ DHYCIA FACG-3A315-S 480 . OliVC TA ACIA ~ CCV/CIB CI DFlYCIB CCV/ CIB i AfJ DHYCIB TACC-38315-S 460 DilYCIB ' AC/B CCV/ IlXA i 1/. CCV/11XA CCV/IlXB IfX CCVirIXB CCV/PA FADP GCV/ICAA BUS-3A3 S 4I60 4KVSV/GFifAA AC/A CCV/-PAB FADP GCV/HfAAB BUS-3AB3-S 4160 4KVSV/GH?AAB AC/AB CCY/-PB fADP CCY/f@AB BUS-3B3-S 4160 4KVSV/GICAB ACtB G . m z h l L-__ .n-. .e. - -....

Waterford 3 i p 3.8 A U N !!.lA R Y COS1PONENT C O OI,1NG WATER SYSTES1 l ( ACCWS) 3,8.1 Snk.gn Function Ihe ACCWS removes heat, when required, from the CCW heat exchangers dunng normal operation, normal shutdown, and accident conditions. The ACCWS is required to operate whenever the heat rejection capacity of the CCWS (via the dry cooling tow ers) is exceeded, or whenever the ambient conditions prevent the CCWS from rejecting its required heat load. The ACCWS also serves as a backup water source for the Emergency Feedwa':r System, delivering water from the wet cooling tower basins to the EFS pumps. 3,8,2 Svstem Definition Ihe ACCWS is a closed loop cooling water system. It is divided into two 1009 capacity,indep:ndent loops. Each loop includes one pump and an evaporative wet type mechanical draft cooline tower. Each tower has a basin which is capable of storing outticient w ater to brinJ. the plant to safe shutdown under all accident conditions. Simplified Crawings of the ACCWS are shown in Figures 3.81 and 3.8 2. A summary of data on selteted AACWS components is presented in Table 3.81 3.S.3 System Oneration The ACCWS is required to operate whenever the heat rejection capacity of the CCWS is exceeded (l.OCA conditions), or whenever the ambient conditions prevent the CCWS from rejecting its required heat load. The ACCWS is periodically started and monitored by the computer for performance, capabilite, and availability of its components, ACCWS water is pumped through the shell side of the CCW he t exchangers to n [ the wet cooling towers. The ACCW pumps can also deliver water from the basins to the EFS pumps, connecting with the supply from the Condensate Storage Pool. 3.8.4 Sutem Success Criterin Success entena is give, on a per loop basis. Each CCW heat exchanger must be cooled by its respective ACCWS loop. The success criteria for each loop are: the ACCW pump in the loop must operate l the wet cooling tower in the loop must be available as a heat sink piping and valves must provide an adequate coolant flow path 3.8.5 Comoonent Information A. Auxiliary Component Cooling Water pumps A,B

1. Rated flow: 6500 gptn @ 145 ft head (63 psid)

2. Rated capacity: 1009h

3. Type: Honzontal centrifugal B. Wet cooling tower basins A,B

1. Capacity: 180.000 gal.

3.8.6 Sucoort Systems and Interfaces A. Control Sirnals

1. Autor.... ;c

' /9 The ACCWS pumps are automatically started by a SIAS. ll O 60

2/gg

Waterford 3 i l 2, Remote Manual l The ACCWS pumps can be operated from the control room or the auxiliary l control panel, i l

13. Motive Power

1. The motor driven ACCWS pumps are Class IE loads that can be supplied l

from the standby diesel generators as described in Section 3.6. C, C 'er

1. Lubrication, cooling, and ventilation are assumed to be provided locally for the ACCWS pumps.

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• y-1; 4

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3 ~ ' ~~ Table 3.8-1. Waterford 3 Auxiiiary Component Cooling Water System Data Sttmmary for Selected Components 1 I COMPOtJEf1T ' ID COMP. LOC A T1074 POWER SOURCE VOLTAGE POWER SOURCE E tt E R G. TYPE LOCATIOff LOAD GRP. ' ACCW-CI A GI WLICIA ACCW CI A I ATJ WEICIA FACC-3 A315-S 480 DilVCIA AGIA ACCW-CIB CI WE TCID ACCWCIO ~ f ATJ WE!GIU FACC-38315-S 480 1DHiCIB ACIB e AGCW-PA TADP 4PLfJWG BUS-3A3-5 4160 4KVSWGHfAA AC/A ACCW-PG TJDP j 4PETJWG BUS-383 S 4160 4PjVGWGRfAB AC/B ~ p i i e l l 9J l 3 =. _ _ _ _ _ _ _ -.

Waterford 3

4. PLANT INFORMATION 4.1 SITE AND BU," DING

SUMMARY

The Waterfoni 3 ate is located in southeastern leuisiana on the wen benk of the Mississippi River nec t. e town of Taft. The site is in the northwest }rartion of St. Charles Farish, about three n Des ucst of the eastern boundhry of St. John the liaptist Parish. The nearest population center is Kenner,13 miles east ot the site. New Orleans is approximately 25 miles east so theast of the site end Baton Rouge is approximately 50 miles nonh nonhwest. In additioi m the Unit 3 nuclear plant the Waterford site contains two coal fired units, designatei nitt ' and 2. Figure 41 (from Ref.1) shows a general view of de e vhi'e Figure 4 a,how> a simplified plot plan. 1 1 7 buildit p contains the RCS and portions of the EFS, ECG and CVCS. Fig sows twn.ccrion views of the reactor building. + 'Itw reactor auilhtry building, located south of the reactor building, contah4, A maior engir. cered safety features components. Components of the EFS, ECCS, CTS. CCWS. and electric power system are located in the reae.or auxiliary building, The n.6 control rcom, cabM spreading room, relay room, and auxiliary control panel are also located in the reactor auxilu, building. Figure 4 4 shows three section views of the reactor auxiliary buDdingd. The fuc\\ han ag hundih is located north of the react; building and contains the spent fuel pW Figure 4-1 show r wo section views of the fuel andling building. i The turbine builmag is b ated south of the reactor auxiliary building and contains components of the poner : wersion system. Figure 4 6 shows two scetion ( viev s of the turbine Nilding. 4.2 FACILITY LAYOUT DRAWINGS l Figures 4 7 through 4-13 show sin:plified layout drawings for Waterford 3 l reactor, auxiliary, and fuel handling buildings. The turbine and service building, l maintenance shop, and technical wpport building are not shown on these drawings. Major rooms, stairways, elevatort anu doorways are shown in the simplified layout drawings, however, many inter 9 M have been 'omitted far clarity. Labels printed in uppercase i correspond to the hanon corm. limed ir' Table 41 and used in the component data listings and system drawings in Sectis J. Roma additionallabels tue included for infonnation and are printed in lowercase type. A \\isting of components b lo~tior presented in Table 4 2. Components included in rable 4 2 are those found 117 e 'vstem data tables ita Section 3, therefore this table is only a panial listing of the compownd ~ nd equipment that are located in a particular room or arca ct the plant. 4,3 SECTfDN 4 REFERENCES

1. 1leddleson, F.A., " Design Data and Si $ ty Features of Commercial Nuclear Pour Plants.", ORNL-NSIC 55, Volun 1, Oak Ridge National Laboratory, Nuclear Safety Infomudon Center, Decen her 1973, 1

J 65 12/88 m

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c___ - - - - x. se 1 ( NORTH O ^ UQ 2. C~ Fuel Handling BWiding G E ORYCTA DRYCT8 Ceo' g Aeactor Cootmq i+*** Buildmg T***' A,ea Area b[N WETCT A WETCTB RC 35PENWG PPCHASE nee Dc4 Cease w { Po Chase Fue at EL t3-l sosvueen b 1 SAFECOG votal a c + cu c.u,. o wyW SDHXS SDHXA O O O SAFECOA voteA b chevaua ch'unuas CM*unus uopunua h i i 35RAB I*111N U oc OO i

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c O O sr o o nU. \\e) . w u,. u,u. Bow Aea C ~.,.1.T.~. 0 0 00 c Hoiduo Tanu Figure 4-7. Waterford 3 Reactor, Reactor Auxiliary, and Fuel Handling Buildings, Elevation -35'0" 77 12/88

Access Ladoer pyp) o s> cme ><as> as><!a>< H4V Eowipment Room NORTH 3 h. n o v g Re,,, g Sbnt Fuei S a ei pumuse O Releng O Tunnes mesen a_ ! I DRYCTA DRYCTS Coe ; h U x:: C,=ooling WETCTA Steam Steam O WETCTB Generator Generator i 2 G 4 s ACCW pomoA ACCW Pump B \\. w U D U DOTKAMAT . 00fueW. PPCHASE O Y O s O* ..,o_.. o C2 X XT><T>G oe o u 9 g g / FrTxRu l i h ::=d l u,o C u.or - - -o j AABeC0RR C06d8 9-W,pg nu u S;';. 6 ,l .co, .Y. CSP RWSP og a o s ,e,. n O glp o'o O o G v ..,,,.. g 6 o u nIn .m... 2 C C a. O O 9 n n 7' U V w. C C Re c.., C C C Snoo () Radiccnem,etry '*U g Wa to Conantrators i me. T.,o Figure 4 8. Waterford 3 Reactor and Reactor Auxiliary Buildings, Elevation -4'0", and Fuel Handling Building, Elevation 1'0" 78 12/8S

Aasse La&tse (typ) f I f _g NORTH ' P tt em 'l k s o Wh I 0 e b h ) C 'Jsp. i, l . Fwel -- I h Pool: mv i i DRYCTA

DRYCTB i

Cocht 0 Towem Coolmg - Tomm g RoofE:21t* h EL309' lowo of[,),,, a$or WETCTB' WETCTA c. I 2 G""" 1 1 0 Coco nat.o^ RC M4V p Hot Room '!::;' 0 M'i O b CCWHXA CCWCCAR e y j g i C C O CCWHXB ccwou4 ccepmas ccwous d ~" 1 o 8 4KYSWORMB -C DCA 000 V E O, Q g B ATTRMB Q C C O B ATTR M AB gg R A B 21 C ORR CM Q BATTRMA h 3g -4 [0 Q C A+ v j uwn,. z.J 46tV SWC R M A 0 0 0 <>L 0 I I I umt. O Ci >O c a Figure 4-9. Waterford 3 Reactor, Reactor Auxiliary, and Fuel Handling Buildings, Elevation 21'0" 79 12/88 1 4 ..m.--

NORTH d l ~ D .ss.e - Pool r-- h / G a or Go a or I lO cg i RC 1 4 g j 4-P PCH A S E o xe "o s gg O. b C e Y O 2 j Catre Screading Anom E i 1 y O CSR o Peo-a av Figure 4-10. Waterford 3 Reactor, Reactor Auxiliary, and Fuel Handling Buildings, Elevation 35'0" SO 12/88

Aateos Laoase (typ) 5:<is><3hmAw r...,, d E N )U ): II'EPL 2;:: t)g . Top of.. Q-- Stent.. Aee Fuel rv.i p Vault Pool : UU /.. 9 3 Sta am Stoem

Generato, Ganerator E

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l l l l / NORTH d Fuer Handhe0 Bding l l l i I Reador Bui; ding RC l l WCROOF m Root Et set" G W= t ) 60AA9 DOAEX M89 ' DCBEIRMet o a < l o Reactor AusAary BAerx: Rool El 600' l S O Figure 4-12. Waterford 3 Reactor, Reactor Auxiliary, and Fuel Handling Buildings, Elevation 69'0" S2 12/88

f I NORTH d Fvel MaWeg B#tdmg, l Roof El 91V' Reactor Buddeg .RC I O Root l EL001' I M. I k O l [ CCWSuge r Taat 3 4 9tRAS ^p Racf Ror) E!. 95 8' EL951' i i 1 s Figure 4-13. Waterford 3 Reactor, Reactor Auxiliary, and l Fuel Handling Buildings, Elevation 91'0" S3 12/88 ~ _...

l Table 41. Definition of Waterford 3 Building and-O Location Codes Codes Descrintions 1, 21PENWG - Penetration Area, located on the 21' elevation of the Reactor Building-2. 35PENWG Piping Penetration Wing, located on the 35' elevation of the - Reactor Building 3. 4KVSWGRMA 4KV Switchgear Room A, located on the 21' elevation of the Auxiliary Building 4, 4KVSWGRMAB 4KV Switchgear Room AB, located on the 21' elevation of the Auxiliary Building 5. 4KYSWGRMB 4KY Switchgear Room B, located on the 21' elevation'of the Auxiliary Building 6. 4PENWG Piping Penetration Wing, located on the 4' elevation of the Reactor Building 7. ACPL Auxiliary Control Panel, located on the 21' elevation of the Auxiliary Building \\ 8. BATTRMA Battery Room A, located on the 21' elevation of the Auxiliary Building 9. BATTRMB Battery Room B, located on the 21' elevation of the Auxiliary Building 10 CCWCORR - Component Cooling Water Corridor, located on the 21' elevation of the Auxiliary Building,

11. CCWHXA Component Cooling Water Heat Exchanger Room A, located -

on the 21' elevation of the Auxiliary Building 12.' CCWHXB Component Cooling Water Heat Exchanger Room.B. located on the 21' elevation of the Auxiliary Building 13, CCWMKPMRM CCW Makeup Pump Room,-located on the 35' elevation of the Auxiliary Building 14.CCWRMA Component Cooling Water Room.A, located on the 21' elevation of the Auxiliary Building _

15. CCWRMAB Component Cooling Water Room 'AB, located on the 21'f elevation of the Auxiliary Building

16. CCWRMB Camponent Cooling Water. Room B, located on the 21'

's elevation of the Auxiliary Building g; 12/88- { 1

O Table 41. Definition of Waterford 3 Building and Q Location Codes (Continued) Codes Descriotions

17. CR Control Room, located on the 46' elevation of the Auxiliary Building 1S. CSP Condensate Storage Pool of the Auxiliary Building

19. CSR Cable Spreading Room, located on the -35' elevation of the Auxiliary Building

20. DG A Diesel Generator Room A, located on the 21' elevation of the Auxiliary Building

21. DGAEXRh146 Diesel Generator A Exhaust Room, located on the 46' elevation of the Auxiliary Building

22. DGAEXRh!69 Diesel Generator A Exhaust Room, located on the 69' elevation of the Auxiliary Building

23. DGB Diesel Generator Room B, located on the 69' elevation of the Auxiliary Building A)

24. DGBENRN146 Diesel Generator B Exhaust Room, located on the 46' (V

elevation of the Auxiliary Building 25 DGBEXRh169 Diesel Generator B Exhaust Room, located on the 69' of the Auxiliary Building

26. DOTKRhlA Diesel Oil Tank Room A, located on the 46' elevation of the Auxiliary Building

27. DOTKRhtB Diesel Oil Tank Room B located on the 46' elevation of the Auxiliary Building

28. DRYCTA Dry Cooling Tower A, adjacent Reactor Containment -

northwest

29. DRYCTB Dry Cooling Tower 8, adjacent Reactor Containment -

northeast

30. EDSUhlPRN1 ED Sump Room, located on the -35' elevation of the Auxiliary Building

31. ELPENWG Electrical Penetration Wing, located on the -35' elevation of the Reactor Building

32. EQDNTKRhl Equipment Drain Tank Room, located on the -35' elevation of V]

[ the Auxiliary Building 85 12/88

Tablo 41, Definition of Waterford 3 Building and O Location Codes (Continued) Codes Descriotions

33. FFTKRM Filter Flush Tank Room, located on the 4' elevation of the Auxiliary Building

34. MDPMRMA EFW Motor Driven Pump Room A, located on the -35' elevation of the Auxiliary Building

35. MDPMRMB EFW Motor Driven Pump Room B, located on the 35' elevation of the Auxiliary Building

36. MSTMENE Main Steam Enclosure, located on the 46' elevation of the Reactor Building east

37. MSTMENW Main Steam Enclosure, located on the 46' elevation of the Reactor Building - west

38. PPCHASE Pipe Chase between Reactor Building and Auxiliary Building

- 13' elevation to 46' elevation

39. RAB21 CORR Auxiliary Building Corridor, located on the 21' elevation

+ (m

40. RAB40 CORR Auxiliary Building Corridor, located on the -4' elevation 41.RC Reactor Containment

42. RELAYRM Relay Room, located on the -35' elevation of the Auxiliary Building

43. RWSP Refueling Water Storage Pool, located in the Auxiliary Building

44. SAFEGDA Safeguards Room A, located on the -35' elevation of the Auxiliary Building

45. SAFEDGB Safeguards Room B, located on the -35' elevation of the Auxiliary Building

46. SDilXA Shutdown Heat Exchanger Room A, located on the -35' elevation of the Auxiliary Building i

47. SDHXB Shutdown Heat Exchanger Room B, located on the 35' elevation of the Auxiliary Building

48. TDPMRM EFW Turbine Driven Pump Room, located on the 35' elevation of the Auxiliary Building

',/] 49.TSPFPL Spent Fuel Pool Operacing Floor, located on the 46' elevation V of the Fuel Building 86 12/88

[ ( Table 41. Definition of Waterford 3 Building and Location Codes (Continued) h Descrintions

50. VOEBA Valve Operating Enclosure Bay A, located on the -15' elevation of the Auxiliary Building

$1.VOEBB Valve Operating Enclosure Bay B located on the -15' elevation of the Auxiliary Building 52 WETCTA Wet Cooling Tower A, adjacent Reactor Containment - southwest 53 WETCFB Wet Cooling Tower B, adjacent Reactor Containment - southeast

54. WGROOF Wing Area Roof, located on the 69' elevation of the Reactor Building OV

<~ 87 12/88 i

TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION WATERFORD 3 k LOCATION SYSTEM COMPONENT ID COMP i TYPE 35PENWG ECCS Si 1550A1 MOV 35PENWG ECCS Si154501 MOV 35PENWG ECCS S4 1550Al - MOV 35 PEN WG ECCS Si1546A2 MOV 35PENWG ECCS SI 1542A3 MOV-I5PENWO -- ECCS Si1548A4-MOV 35PENWG ECCS Si154082 MOV 35PENWG ECCS S4 154783-MOV 35PENWG ECCS SI-154484 MOV 35PENWG ECCS Si 1546A2 MOV-35PENWG - ECCS Si1542A3 MOV-35PENWG ECCS St-1546A4 - MOV 35RAB CVCS CVC 112AB MOV 4KVSWGRMA EP BUS 3A3 S BUS 4KVSWGRMA EP. CB-3A 14 - CB 4KVSWGRMA EP BUS-3A DC-S BUS. I 46VSWGRMA EP BUS-3A DC-S - BUS 4KVSWGRMA EP BUS-3A DC-S bus ~4KVSWGRMA EP CB-3A 1 CB-4KvSWGRMA - EP BUS 3A31 S BUS dnVSWGRMA-EP TRAN 3A31 S. TRAN. l 46VSWGRMA EP MCC-3A311 S MCC - 4KVSWuRMA EP MCC-3A312 S MCC 4KVSWGRMA EP MCC-3A313-S. MCC i 46VSWGRMA EP BUS 3A 3 - BUS 4KvSWGRMA EP BUS 3A 3 BUS 4KVSWGRMA EP BUS 3A S BUS; 4KvSWGRMA EP BC3AlS_ EC, 4KvSWGRMA EP BC 3A2-S BC l 46VSWGRMAB EP-BUS 3AB3-S BUS 4 k i gg-12/88 i e w 7 7 p yevp- +-+w_g y g-p w--y+= 9 9-w ,etm _,ppwe--g ,9 gy g=9

TABLE 4 2. PARTIAL LISTING OF' COMPONENTS BY LOCATION. WATERFORD 3- (CONTINUED) l I LOCATION SYSTEM COMPONENT 10 COMP l TYPE 4Av5WGAMAB EP CB4AB 2 CB i l 4KVSWGRMAB EP CB-3AB 6 CB f 4Kv6WGRMAB EP BUS 3AB3-S BUS. 4Wv6WORMB, E P. BUS 4838 BUS l i l 4KvsWGRMB EP C B-3815 CB l 4KVSWGRMB EP BUS 38-DC-S, BUS 4KvsWGRMB EP BUS-3D DC S BUS 48vsWGRMB EP BUS 4B-DC-S BUS '~ 46VSWGRMB EP CB381 CB 4NVSWGRMB EP BUS-3831 S BUS 4KVSWGRMB EP TRAN4B31 S TRAN 4Kv6WGRMB EP MCC 38311-S MCC 4KvSWGAMB EP. MCC-3B312-S, l

MCC, i

4KvSWGRMB EP. MCC 30313-S MCC 4NvsWGRMB EP BUS 3B-S BUS-4KVSWGRMB - EP BUS 4B-S BUS 4KvSWGRMB - EP. BUS 38-S BUS: 4Kv5WGAMB EP BC-381 S BC dnvsWGAMB. EP BC-382 S. BC -. 4PENWG ACCW ACCW PA MDP [- 4PENWG ACCW-ACCW PB MOP l_ BATKRMA CVCS-BAM TKA TANK BATKRMA. OvCS C VC-106A Mov : f BAT KRMA CVCS BAM PA MOP j. 6AT KRMB CVCS BAM-TKB. TANK SA T fsRMB CVCS CVC 1078 MOV BATKRMB CVCS. DAM-PB MOP _ i BATTRMA-EP BATT 3A S BATT a BATTRMS-EP B A TT48-S. BATT 4 CCWMAA ACCW-CCW HXA HA V V j g9 .12/88 E + ~ w ~w '~n'

TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION WATERFORD 3 (CONTINUED) /q \\ \\ l LOCATION SYSTEM COMPONENT ID COMP TYPE CCWHJA CCW CCW HXA HX CCWHAA CCW CCW.HXA HX CCW M AA CCW CCW-hXA HX CCWMAB ACCW CCW-HXB HX CCWMAB CCW CCW HX8 HX CCWHXB CCW CCW-HAB HX CCWMAB CCW CCW HXB HX CCWnMA CCW CCW PA MOP GCWRN%B CCW CCW PAB MDP CCWRMB CCW CCW PB MDP CHPMRMA CVCS CVC-PA MDP CHPMAVAB CvCS CVC PAB MDP CHPMAMB CVCS C VC-P B MDP CSP EFS EFW CSP TANK ( DCA EP DG-3A OG DGa EP OG-38 OG DAYCTA CCW CCW<,TA CT DRvCIA CCW CCW CTA FAN ORYCTA CCW CCW CTA GT DRYCTA CCW CCW CTA FAN DRYCTA CCW CCW CTA CT ORYCIA CCW CCWCiA FAN ORYCIB CCW CCW CTB CT DRYCTB CCW CCW CiB FAN DRYCIB CCW CCW CTB CT ORYCTB CCW CCW CTB FAN ORYCT8 CCW CCW CTB CT DAYCTB CCW CCW CTB FAN MDPMRMA EFS EFW PA MDP (g MDPMHMS EF5 EFW PB MDP \\) ~. 90 12/88

TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY L OCATION WATERFORD 3 (CONTINUED) LJ LOCATION SYSTEM COMPONENT 10 COMP TYPE AbTMENE EFS MS@.08 NV i MS TMEN W EFS MS-609A NV RC ECCS RCS-RV RV RC ECCS RCS RV RV RC ECCS RCS-RV RV~ ~ fr EFS SG-1 SG RC EFS SG-2 E RC RCS ACS RV RV RC RCS RCS 1516AB NV A0 RCS RCS 2501 AB NV RC RCS RCS-15028 MOV ~~ RC RCS RCS 1504A MOV RC RCS RCS 1501B HV 740 RCS RCS 1503A HV ~ RnSP ECCS SI RWSP TANN' ~ RWSP ECCS SI-RWSP TANK RWSP ECCS SI RWSP TANK SAFEGDA ECCS SIPA MDP SAAEGDA ECCS StPAB MOP l i SAFEGDB ECCS St-PB MDP 1 TOPMRM EFS EFW.PAB , TOP TDPMAM EFS EFW 416 MOV l i UNN 3 A32 EP UUS 3A32 BUS UNK 3A32 EP TRAN 3A32 TFAN l UN A-3 632 EP BUS 3832 BUS l U N K-3 632 EP TRAN 3832 1RAN VOEBA ECCS SI803A HV voEUA ECCS SI-103A HV. VOEB6 ECCS Si1046 HV T WETCIA ACCW ACCW C TA CT 'u) i ; 1 l I 91 12/88

o T ABL E 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION WATERFORD 3 (CON 704UED) LOCATION SYSTEM COMPC/ ANT 10 COMP TYi'E, WEICT I /.CCW CCW C TA FAN WETCIB ACCW A.'CCW(. C CT WElGib ACCW ACCWCTB FAN f, 5 V 1 k { 91 12/88 l

,,.. MRM *i Waterford 3 e 5. IllllLIOGRAPilY FOR WATERFORD 3 POWER STAT'ON 1. Waterford SES Unit No. 3 Final Safety Analysis Report, Louisiana Power and Light Company, New Orleans, Louisiana, De'cembe'r,1986.

2. "Waterford Steam E't etric Station Unit 3 Auxiliary Feedwater System ReliabDity Stady Evaluation,' NUREG,CR 2219, Septemaer,1981.

i \\ i i9 1 9 12/88 i 1

Waterford 3 ,O APPENDIX A DEFINITION OF SYMil0LS USED IN Tile SYSTEM AND LAYOUT DRAWINGS A 1. SYSTEM DRAWINGS A 1.1 Fluid System Drawings The simplined system drawings are accurate repiesentations of the major f' *w 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 dhmeter cf the connecting major flow path. There usually are two versions of each fluid system drawing;he drawing conventions a simplified system drawing, and a comparable drawing showing component locations. T 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 sides of the vessel. llorizontal lines always dominate and break venicallines. O V Component symbols used in the fluid system drawings are defined in Figure A-1. Most valve and pump symbols are designed to allow the reader to distinguish among similar components based on their support systeta requirements (i.e., electric power for a motor or solenoid, steam to drive n 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 perfonn an overpressure protection function. No 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 benveen centrifugal and positive displacement pumps and between types of pump drives (i.e., motor, turbine, or engine). Locations are identined in terms of plant location codes defined in Section 4 of this Sourcebook. Location is indicated by shaded " zones" that are not intended to represent the actual room geometry. Locations of discrete components represent the actual physical location of - the component. Piping locations b: tween discrete components represent the plant areas through which the pi underground pipe runs). ping passes (i.e. including pipe tunnels and Component locations that are not known are inf.cated by placing the ' O components in an unshaded (white) zone. (v) The primary flow pain in the system is highlighted (i.e., bold white line)in the 5 cation version of the Guid system drawings. 94 12/88

Waterford 3 A 1.? Electrical System Drawings O The electric power system drawings focus on the Class IE portions of the plant's electric lower system. Separate drawines are provided for the AC and DC portions of the Class Ib system. There often are two versions of each electrical system drawing;he a simplified system drawing, and a comparable drawing showing component locations. T drawing conventions used in the electncal system drawings Ue the following: Flow generally is top to bottom In the AC cower drawings, the interface with the switchyard and/or offsite prid is ..vn at the top of the drawing. In the DC power drawings, the batteries and the interface with the AC power system are shown at the top of the drawing. Vertical lines dominate and break horizontal lines. Component symbols used in the electrical system d*awings are defined in Figure A 2. locations are identified m terms of plant location codes defined in Section 4 of this Sourcebook, locations are indicated by shaded " zones" that are not intended to represent the actual room geometry. locations of discrete components represent the actual physical location of the component. The electrical connections (i.e., cable runs) between discrete components, as shown on the electrical system drawings, DO NOT represent the actual ca 'le 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 A2.1 Site Drawings A general view of eac' ren tor site and vicinity is presented along with a simplified site plan showing the arrangemen.? tha major buildings, tanks, and other features of the site. The general view of the reactor s.:e is obtained frot". 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, l.abels 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 Drawings Simplified building layout drawings are developed for the portions of the plant that contain components and systems that are described in fieulon 3 of this Sourcebook. l Generally, the following buildings are included: reactor building, auriliary building, fuel building, diesel building, and the intake structure or pumphouse. Layout drawings l generally are not developed for other buildings. Symbols used in the simplified layout drawings are defined in Figure A-3. Major. O however, many interior walls have been omitted for clarity.- The building layout drawings, rooms, stairways, elevators, and doorways are shown in the simplified layout drawings os 12/88 ~

Waterfctd 3 l are approrimately to scale, should not be used to estimate room size or distances. A. built scah draw,np for should be consulted his purpose. Lare; s printed in uppercase bolded also correspond to the location codes defined in Section J and used in the component data listings and system drawings in Section 3. Some additio.al labels are included for infomiation and are pnnted in lowercase type. A 3, Al'PENI)lX A REFERENCES 1. lieddleson, F.A., " Design Data and Safety Features of Commercial Nuclear Power Plants.", ORNL NSIC 55, Volumes 1 to 4, Oak Ridge National Laturatory, Nuclear Safety Infom1ation Center, December 1973 (Vol.1), January 1472 (Yol. 2), April 1974 (Vol. 3), and March 1975 (Vol. 4) i J !O N O 96 12/88 4 - i e .y., .--w- ..-_..-_--.r. --m, -.vr

---

w..

r

_.... -. ~ _ -... - - - - -. ~... -.., - -... ~. -. -. _ -. _ - - -,~... - ~.-.. -..,. _.. - ~...- ~ -.. ~ l (OPEN CLC Of VALVE RCV (OPEN CLOSED) ~ ~ ~ o MOTOR.0PER ATED VALVE. MOV MOTOR OPEPATED (O P E N 'C L O $ E D) 3 WAY valve MOV (CLOSED PJRT MAY VARY) Y 80LEN0lD 0Pf R ATED VALVE * $0V $0LEN0lD.0 8tR ATJD (OP E N'C LO S E D) 3 WAY VALVE * $0V (CLOSED PC'4 T MAY.'ARY) i HYOR AULIC VALVE. HV HYDR AVLIO NON RETURN ~ ~ ~ (O P E N 'C L O S E D) 9 4 YALVE, HCV (C $tNiCLOSED) J , PNEUMATIC VALVE e NV PNEUM ATIC NONMIETURN (CPIN:CLO6ED) VALVE, NCV (OPL N!CLOSi D) CHECK VI.;,VE

• CV S AFETY VALVE
• SV (CLOSED)-

4 W Ch J@ POWER OPER ATED RELi[F V ALVE, POWER OPERATEP RtLiiF V ALVE, k SOLENolD PILOT TYPE + PORY J PNEUMATICALL) ofeERI.TE D. DORV l (CLCsED, OR DUAL. FUNCTION SAFETY / RELIEF YALVE

• SRV (CLOSED)

CENTRIFVO AL CENTRIFUG AL. MOTOR.0 RIVEN PUMP. MDP TURBINE. DRIVEN PUMP

• TDP

\\ / I 1 POSITIVE DISPL ACE MEN T MOTOR.ORIVEN PUMP. MDP POSITIVE DISPLACEMENT - = TURBINE. DRIVEN PUMP = TDP I L / I K Figure A-1, Key To Symbols in Fluid System Drawings-97; 12/88 a.

- ~... a. -. -

/ f s c PWR swr MAIN CONDENSER

• COND i

t Rt ACTOR y($$(L. py y 2 n ~h Hf AT EXCHANG[R HE MECHANIC AL OR AFT COOLING TOWER f-A j NO UNIT ACO k Ott ATER 0 ST AM HE AT d C ACH ANGf R (i t. f tEDW AT[H HE ATE R, OR AIN COOLtR, ETC.) HK o n, I 08 I TANK TK gaagg SPR AY NO2RES. SN O I 1 Ruptunt o-sw. no FILTER FLT ~ l [ ORIFICE CR \\ l i l l l E Figure A.' Key To Symbols in Fluid System Drawings (Continued) j f 98 12/88

f i J I i f A C. DitStt otNtH AToR, Do Z m ATTtRy. D ATT oH A C. TURea.E ctNERAfoH. To j l on CIRCUIT eHE Aktn. co C E (CDEN:ClottD) O... g oR 15... O INTE RLoCr t o CIRCulf DRE AktR$. CD SWITCH = SW on O oR oTHER TYPE of R NSFilt SWITCH. ATS DISCONNECT oEVICE OR I I MANUAL TRANSFtH SWITCH. MTS f SWITCHGE AR DVS. BUS ! 'HUS W) ] l otoR CoNTFlot CENTER. MCC M' oR NY Yt TRANSFORMER + TRAN UR Dhi!RIDUTICN P ANtl. PNL f i I I D Af f t H) CH ARGE R (PC CTIFitlO. BC m T I i \\ lV 1 1 REL Av Con ACTS ~ en T T (octN Ctosto) rust.rs I g tLtCTRic MoroR. MTR McTon otNERAfoR Mo (n\\ V Figure A-2. Key To Symbols in Electrical System Drawings l 99 12/88 l l

O '? ST AIRS g SPIRAL 0. Down TAmCASE (* .u ELEVATOR D Down O".- HATCH OR OPEN AREA GRATING DECK (NO FLOOR) --O - PERSONNEL DOOR

• EQUIPMENT DOOR RAILROAD TRACKS FENCE LINE O

TANKlWATER AREA 7 . Figure A-3. Key To Symbols in Facility Lay _out Drawings - gg) 12/88

i ) v j Waterford 3 APPENDIN B j DEFINITION OF TERMS USED IN Tilh DATA TAllLES Terms appearing in the data tables in Sections 3 and 4 of this Sourcebook are defined as follows: SYSTEM (also LOAD SYSTEM) All components associated with a particular system description in the Sourcebook have the same system code in the data base. System codes used in this Sourcetook are the following: 3 i Chk Dennition RCS Reactor Coolant System EFS Emergency Feedwater System ECCS Emergency Core Cooling System CVCS Charging System - 1&C Instrumentation and Control System EP Electric Power System CCW Com;mnent Cooling Water System - - ACCW Auxi;iary Component Cooling Water System COM PONENT ID (also LOA D COMPONENT ID) The component identification (ID) code in a data table matches the component ID that appears in the corresponding system drawing. The component ID generally begins with a system prefaca followed by a component number. The system preface is not necessarily the same as the system code described above. For g component ids, the sysam preface corresponds to what the plant calls tre 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 appnring 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 t COMPONENT TYPE -(COMP TYPE)- Refer to Table B 1 for a list of component type codes. POWER SOURCE - The component ID of the power source is' listed in this field (see COMPONENT ID, above). In this data base, a " power source" for a particular component (i.e. a load or a distribution component) is the next higher electrical distribution or generatingu 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 load of a-power source is entered in this field. The downstream (output) voltage of a transformer, ~ inverter, or hattery charger is used. . EMERGENCY LO AD GROUP (EMERG LOAD GROUP) RAC and DC load groups (or electrical divisions) are defined as appropriate to the plant.. Generally, AC load groups are - identified as AC/A, AC/B,'etc. The emergency load group for a third-of a kind load (i.e. a " swing" load) that can be powered from ei_ther of two AC load groups would be identified as' AC/AB. DC load group follows similar naming conventions. 101 12/88 : L 4 er9ewm-- FrW e-Wu-e- 'er

• 'py--31-~wyg y

V m-4 9----wt-7 r*-e-d.rrw g *2s * -g a gpgmee rpeegy 5-t w>e p uev + rr yd e-.=MrT!?rav+F---yg ey y --1p 9gw4 g Py-'* gs,.e,.%tc-t-W-ml6 'um-We t-M t vp;9,ggept g*+g * $4 g-- W-Yr m ' y

D TAllLE 111. COhtPONENT TYPE CODES CO %1PO N f'NT COMP TYPE VALVES: Motor-operated valve hiOV Pneumatic (air operated) valve NV or AOV liydraulie valve llV Solenoid operated valve SOV hianual valve XV Check valve CV Pneumatic non return valve NCY liydraulic non retum valve HCV Safety valve SV Dual function safety / relief valve SRV Power operated relief valve PORY (pneumatie or solenoid operated) PUh1PS: hiotor-driven pump (centrifugal or PD) hiDP Turbine-driven pump (centrifugal of PD) TDP Diesel driven pump (centrifugal of PD) DDP OTilER FLUID SYSTEh1 COh1PONENTS: Reactor vessel RV d Steam generator (U tube or once-through) SG licat exchanger (water to water liX, HX or water to air !!X) Cooline tower CT Tant ' TANK or TK Sump SUh1P Rupture disk RD Oritice ORIF Filter or strainer FLT Spray nozzle SN lleaters (i.e. pressurizer heaters) llTR VENTILATION SYSTEh! COMPONENTS: Fan (motor-driven, any type) FAN Air cooling unit (air to water IIX, usually ACU or FCU including a fan) Condensing (air conditioning) unit COND EMERGENCY POWER SOURCES: Diesel generator DG Gas turbine generator GT Battery BATT O g 10.3 12/88

TAllLE 11-1. CO.511'ONENT TYPI' CODES (Continued) COS1PONENT CON 1P TYPE ELECTRIC PCWER DISTRIBUTION EQUIPh1ENT: Bus or switchycar BUS 510 tor control center h1CC Distribution panel or cabinet PNL or CAB Transformer TRAN or XFAIR Battery charger (rectifier) BC or RECT Inverter INV Uninterruptible pow er supply (a unit that nia) UPS ineNde battery, battery charger, and inverter) h10 or generator h10 Circuit breaker CII Switch SW Autornatic transfer switch ATS 51anual transfer switch h1TS I i ( 103 12/88}}