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SECURITY-RELATED-INFORMATION—Withhold under 10 CFR 2.390 This Document contains Security-Related Information. When this page is separated from the document, it is Decontrolled. Millstone Power Station Unit 3 Safety Analysis Report Chapter 1: Introduction and General Description of Plant CONTAINS SECURITY RELATED INFORMATION. PLEASE HANDLE PROPERLY

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  • SECURITY-RELATED-INFORMATION—Withhold under 10 CFR 2.390

    This Document contains Security-Related Information. When this page is separated from the document, it is Decontrolled.

    Millstone Power Station Unit 3 Safety Analysis Report

    Chapter 1: Introduction and General Description of Plant

    CONTAINS SECURITY RELATED INFORMATION.

    PLEASE HANDLE PROPERLY

    WJD1Cross-Out

    WJD1Cross-Out

    WJD1Cross-Out

  • Revision 33—06/30/20 MPS-3 FSAR 1-i

    CHAPTER 1—INTRODUCTION AND GENERAL DESCRIPTION OF PLANT

    Table of Contents

    Section Title Page

    1.1 INTRODUCTION ...................................................................................... 1.1-1

    1.2 GENERAL PLANT DESCRIPTION......................................................... 1.2-1

    1.2.1 General........................................................................................................ 1.2-11.2.2 Site .............................................................................................................. 1.2-11.2.3 Structures .................................................................................................... 1.2-11.2.4 Nuclear Steam Supply System.................................................................... 1.2-21.2.5 Instrumentation and Control Systems......................................................... 1.2-41.2.6 Radioactive Waste Systems ........................................................................ 1.2-41.2.7 Fuel Handling ............................................................................................. 1.2-51.2.8 Turbine Generator and Auxiliaries ............................................................. 1.2-51.2.9 Electrical Systems....................................................................................... 1.2-61.2.10 Engineered Safety Features ........................................................................ 1.2-61.2.11 Cooling Water and Other Auxiliary Systems ............................................. 1.2-91.2.12 Reference for Section 1.2.......................................................................... 1.2-10

    1.3 COMPARISON TABLES .......................................................................... 1.3-1

    1.3.1 Comparison with Similar Facility Designs ................................................. 1.3-11.3.1.1 Comparison of Nuclear Steam Supply System........................................... 1.3-11.3.1.2 Comparison of Engineered Safety Features................................................ 1.3-11.3.1.3 Comparison of Containment Concepts ....................................................... 1.3-11.3.1.4 Comparison of Instrumentation Systems.................................................... 1.3-21.3.1.5 Comparison of Electrical Systems.............................................................. 1.3-21.3.1.6 Comparison of Radioactive Waste Systems ............................................... 1.3-21.3.1.7 Comparison of Other Reactor Plant Systems ............................................. 1.3-21.3.2 Comparison of Final and Preliminary Designs........................................... 1.3-2

    1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS...................... 1.4-1

    1.4.1 Licensee's Subsidiaries ............................................................................... 1.4-11.4.2 Architect-Engineer...................................................................................... 1.4-1

  • Revision 33—06/30/20 MPS-3 FSAR 1-ii

    CHAPTER 1—INTRODUCTION AND GENERAL DESCRIPTION OF PLANTTable of Contents (Continued)

    Section Title Page

    1.4.3 Nuclear Steam Supply System Manufacturer ............................................. 1.4-11.4.4 Turbine Generator Manufacturer ................................................................ 1.4-1

    1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION ........................................................................................ 1.5-1

    1.6 GENERAL REFERENCES (HISTORICAL) ............................................ 1.6-1

    1.7 DRAWINGS AND OTHER DETAILED INFORMATION ..................... 1.7-1

    1.7.1 Electrical, Instrumentation, and Control Drawings .................................... 1.7-11.7.2 Piping and Instrumentation Diagrams ........................................................ 1.7-11.7.3 Loop and Systems Diagrams ...................................................................... 1.7-11.7.4 Other Detailed Information (Special Reports and Programs)..................... 1.7-1

    1.8 CONFORMANCE TO NRC REGULATORY GUIDES .......................... 1.8-1

    1.8N NSSS CONFORMANCE TO NRC REGULATORY GUIDES............. 1.8N-1

    1.9 STANDARD REVIEW PLAN DOCUMENTATION OF DIFFERENCES .......................................................................................... 1.9-1

    1.10 TMI ACTION ITEMS .............................................................................. 1.10-1

    1.11 MATERIAL INCORPORATED BY REFERENCE ............................... 1.11-1

  • Revision 33—06/30/20 MPS-3 FSAR 1-iii

    CHAPTER 1—INTRODUCTION AND GENERAL DESCRIPTION OF PLANT

    List of Tables

    Number Title

    1.3-1 Design Comparison

    1.3-2 Comparison of Engineered Safety Features

    1.3-3 Comparison of Containment Concepts

    1.3-4 Comparison of Containment Atmosphere Pressure Sensor Parameters

    1.3-5 Comparison of Reactor Coolant Pump Bus Protection

    1.3-6 Comparison of Engineered Safety Feature Actuation Signals

    1.3-7 Comparison of Emergency Generator And Steam Generator Auxiliary Feedwater Pump Start Signals

    1.3-8 Comparison of Process And Effluent Radiation Monitoring Systems

    1.3-9 Comparison of Area Radiation Monitoring Systems

    1.3-10 Comparison of Airborne Radiation Monitoring Systems

    1.3-11 Comparison of Electrical System Parameters

    1.3-12 Comparison of Radioactive Liquid Waste Systems

    1.3-13 Comparison of Radioactive Gaseous Waste Systems

    1.3-14 Comparison of Radioactive Solid Waste Systems

    1.3-15 Comparison of Other Reactor Plant Systems

    1.3-16 Comparison of Final And Preliminary Information

    1.6-1 Topical Reports as General References (Historical)

    1.7-1 Electrical, Instrumentation, And Control Reference Documentation

    1.7-2 Piping And Instrumentation Diagrams

    1.7-3 Omitted

    1.7-4 Special Reports And Programs

    1.8-1 NRC Regulatory Guides

    1.8N-1 NRC Regulatory Guides

    1.9-1 Summary of Differences From SRP

    1.9-2 SRP Differences And Justifications

    1.10-1 TMI Action Items

  • Revision 33—06/30/20 MPS-3 FSAR 1-iv

    NOTE: REFER TO THE CONTROLLED PLANT DRAWING FOR THE LATEST REVISION.

    CHAPTER 1—INTRODUCTION AND GENERAL DESCRIPTION OF PLANT

    List of Figures

    Number Title

    1.2–1 Not Used

    1.2–2 Plot Plan

    1.2–3 (Sheets 1-3) Piping & Instrumentation Diagram Legend

  • Revision 33—06/30/20 MPS-3 FSAR 1.1-1

    CHAPTER 1 – INTRODUCTION AND GENERAL DESCRIPTION OF PLANT

    This Final Safety Analysis Report (FSAR) has been prepared with the guidance of RegulatoryGuide 1.70, Revision 3, Standard Format and Content of Safety Analysis Reports for NuclearPower Plants, LWR Edition, dated November 1978. The report is intended to be responsive to theguide, to existing regulations, and to NUREG-75/087, Standard Review Plan for the Review ofSafety Analysis Reports for Nuclear Power Plants, LWR Edition.

    1.1 INTRODUCTION

    This report was submitted in support of an application by the companies listed in the GeneralInformation Section of the application (the Applicants) for a Class 103 permit for a facilityoperating license to operate a nuclear power plant, designated as Millstone Nuclear PowerStation - Unit 3 (Millstone 3). This plant is located on a site in the town of Waterford, NewLondon County, Connecticut, on the north shore of Long Island Sound.

    Millstone 3 uses a pressurized water type nuclear steam supply system (NSSS) furnished byWestinghouse Electric Corporation (WNES) and a turbine-generator furnished by the GeneralElectric Company (GE). The remainder of the unit, including a subatmospheric reactorcontainment, was designed and constructed by the Applicants, with the assistance of theirrepresentative, Northeast Utilities Service Company (NUSCo.), and their architect-engineer,Stone & Webster Engineering Corporation (SWEC).

    The core was originally designed for a warranted power output of 3,411 MWt, which was theoriginal license application rating. This output, combined with the reactor coolant pump heatoutput of 14 MWt, gave an NSSS warranted output of 3,425 MWt.

    The core has been re-analyzed for a power output of 3,650 MWt which, when combined with therevised reactor coolant pump output of 16 MWt, gives a 100% NSSS power output of 3,666 MWt.

    All steam and power conversion equipment, including the turbine-generator, has the capability togenerate a maximum calculated gross output of approximately 1,296 MWe. When the NSSS isoperating at its warranted output of 3,666 MWt, the net electrical output is approximately 1,245MWe.

    The project schedule was based on a fuel loading date of November 1, 1985, and an anticipatedcommercial operation date of May 1, 1986. The Low Power License (5 percent) was issued by theNRC November 25, 1985, the Full Power License was issued January 31, 1986, and the Unitbecame commercially operational April 23, 1986.

    In 2001, Millstone Units 1, 2 and 3 operating licenses were transferred from Northeast NuclearEnergy Company to Dominion Nuclear Connecticut, Inc. (DNC).

    DNC is an indirect wholly-owned subsidiary of Dominion Energy, which is in turn owned byDominion Resources, Inc. (DRI). Virginia Power, which is the licensed owner and operator of theNorth Anna and Surry nuclear stations, is also a subsidiary of DRI.

  • Revision 33—06/30/20 MPS-3 FSAR 1.1-2

    The transmission and distribution assets on the site will continue to be owned by ConnecticutLight and Power (CL&P) and will be operated under an Interconnection Agreement betweenCL&P and DNC.

    The FSAR will retain references to Northeast Utilities and Northeast Nuclear Energy Companydocuments/activities when they are used in a historic context and are required to support the plantlicensing bases.

    Upon license transfer, all records and design documents necessary for operation, maintenance,and decommissioning were transferred to DNC. Some of these drawings are included (orreferenced) in this FSAR. These drawings often have title blocks (or drawing numbers) which listNortheast Nuclear Energy Company or Northeast Utilities Service Company (et. al). In general,no changes to these title blocks will be made at this time. Based on this general note, thesedrawings shall be read as if the title blocks list Dominion Nuclear Connecticut, Inc.

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-1

    1.2 GENERAL PLANT DESCRIPTION

    This section includes a summary description of the principal characteristics of the site and aconcise description of Millstone 3.

    1.2.1 GENERAL

    Millstone 3 incorporates a four loop closed cycle pressurized water type nuclear steam supplysystem (NSSS); a turbine generator and electrical systems; engineered safety features; radioactivewaste systems; fuel handling systems; structures and other on site facilities; instrumentation andcontrol systems; and the necessary auxiliaries required for a complete and operable nuclear powerstation. The site plan (Figure 2.1.4) and the plot plan (Figure 1.2–2) show the generalarrangement of the unit.

    Piping and instrumentation diagrams are included throughout this document with the appropriatesystem descriptions. Symbols and abbreviations used in the diagrams are illustrated onFigure 1.2–3.

    With respect to the numbers, graphs, and drawings included within this report, the normaltolerance permitted by good engineering practice is intended. Where operating parameters areunusually important, such items have been included in the technical specifications.

    1.2.2 SITE

    The site, approximately 500 acres in area, is on the north shore of Long Island Sound and on theeast side of Niantic Bay. It is located in the Town of Waterford, Connecticut, about 3.2 miles west-southwest of New London and about 40 miles southeast of Hartford. The surrounding area isprimarily residential with some commercial and industrial uses.

    Millstone 1 and 2 are also located on the site. Millstone 1 is a permanently defueled boiling waterreactor. Millstone 2 uses a two-loop pressurized water reactor supplied by CombustionEngineering, Inc., with a rated thermal power level of 2,700 MW; the architect-engineer wasBechtel Corporation. Section 2.1 contains a more detailed description of the site and surroundingareas.

    1.2.3 STRUCTURES

    Millstone 3 major structures are the containment structure, auxiliary building, fuel building(including decontamination facilities), waste disposal building, engineered safety featuresbuilding, main steam valve building, turbine building, service building, control building, technicalsupport center, emergency generator enclosure, containment enclosure building, warehouse 5(including the condensate polishing waste treatment facility), auxiliary boiler enclosure, andcirculating and service water pumphouse. Section 3.8.4.1 describes the general arrangement ofthese structures.

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-2

    The reactor is operated inside a reinforced concrete containment structure maintained at asubatmospheric pressure between 10.6 and 14.0 psia. The containment concept is similar to thoseof Surry Power Stations 1 and 2, North Anna Power Stations 1 and 2, and Beaver Valley PowerStation 1. Following the loss-of-coolant accident (LOCA), described in Section 15.6.5, thecontainment remains above atmospheric pressure.

    The containment structure is housed within the containment enclosure building, which along withstructures adjacent to the containment, forms the boundary of the supplementary leak collectionand release system (SLCRS). The SLCRS establishes a subatmospheric pressure in thecontainment enclosure building and contiguous structures. See Section 6.2.3 for a furtherdescription.

    The seismic criteria used in the design of the structures and equipment for Millstone 3 aredescribed in Section 3.7.

    1.2.4 NUCLEAR STEAM SUPPLY SYSTEM

    The nuclear steam supply system (NSSS) consists of a Westinghouse pressurized water-typereactor and four closed reactor coolant loops connected in parallel to the reactor vessel. Each loopcontains a reactor coolant pump and a steam generator, two loop isolation valves, an isolationbypass valve, and a bypass line. The NSSS also contains an electrically heated pressurizer andauxiliary systems.

    High pressure water circulates through the reactor core to remove heat generated by the nuclearchain reaction. The heated water exits from the reactor vessel and passes via the coolant looppiping to the steam generators. Here, it releases heat to the feedwater to generate steam for theturbine generator. The cycle is completed when the water is pumped back to the reactor vessel.The entire coolant system is composed of leaktight components to ensure that all fluids areconfined to the system.

    The reactor core is of the multi-region type. All fuel reactor assemblies are mechanicallyidentical, although the fuel enrichment is not the same in all assemblies. These assembliesincorporate the rod cluster control concept in canless 17 x 17 fuel rod assemblies using a springclip grid to provide support for the fuel rods. The reactor moderator has a negative temperaturecoefficient of reactivity at full power at all times throughout core life.

    In the typical initial core loading, three fuel enrichments are used. Fuel assemblies with thehighest enrichments are placed in the reactor core outer region, and the two groups of lowerenrichment fuel assemblies are arranged in a selected pattern in the central region. In subsequentrefuelings, one-third of the fuel is discharged from the central region and fresh fuel is loaded intothe outer region of the reactor core. The remaining fuel is arranged in the central two-thirds of thereactor core in such a manner as to achieve optimum power distribution.

    Rod cluster control assemblies are used for reactor control and consist of clusters of cylindricalabsorber rods. The absorber rods move within guide tubes in certain fuel assemblies. Above thereactor core, each cluster of absorber rods is attached to a spider connector and drive shaft, which

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-3

    is raised and lowered by a drive mechanism mounted on the reactor vessel head. Downwardmovement of the rod cluster control after trip is by gravity.

    The reactor coolant pumps are vertical, single-stage, centrifugal pumps of the shaft-seal type.

    The steam generators are Westinghouse Model F vertical U-tube units which contain Inconeltubes. The Model F steam generator includes features such as improved tube support plate designand high circulation ratio which are designed to minimize most forms of corrosion, sludgebuildup, and chemical attack. Integral moisture separation equipment reduces the moisture ofsteam to one-quarter percent or less.

    All of the pressure containing and heat transfer surfaces in contact with reactor water are stainlesssteel clad or stainless steel except the steam generator tubes and fuel tubes, which are Inconel andZircaloy, respectively. Reactor core internals, including control rod drive shafts, are primarilystainless steel.

    There are two double-disc, motor-operated, loop isolation valves in each loop, one locatedbetween the reactor vessel and the steam generator and the other between the reactor vessel andthe reactor coolant pump of each of the four loops. The isolation bypass valves, also double-disc,motor-operated valves, are located in a bypass line connecting the two loop isolation valves ineach loop.

    An electrically heated pressurizer connected to one reactor coolant loop maintains reactor coolantsystem pressure during normal operation, limits pressure variations during plant load transients,and keeps system pressure within design limits during abnormal conditions. In addition, itprovides indication of and maintains reactor coolant system water inventory.

    The auxiliary systems, provided as part of the NSSS, charge the reactor coolant system and addmakeup water, purify reactor coolant water, provide chemicals for corrosion inhibition andreactivity control, remove decay heat when the reactor is shut down, and provide for emergencysafety injection.

    Other auxiliary systems supporting the NSSS but not part of the NSSS provide the following:

    1. System components cooling

    2. Fuel pool cooling

    3. Reactor coolant water and other auxiliary system fluid sampling

    4. Venting and draining the reactor coolant system and other auxiliary systems

    5. Emergency containment depressurization spray and combustible gas control

    6. Maintaining the containment atmosphere pressure at sub-atmospheric levels

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-4

    7. Collecting, processing, and disposing of liquid and gaseous wastes

    8. Preparation of solid wastes for disposal

    9. Process, store, and supply reactor coolant system boric acid

    10. Component ventilation

    11. Instrument and valve operator air

    1.2.5 INSTRUMENTATION AND CONTROL SYSTEMS

    The instrumentation and control for the reactor protection system, engineered safety featuresactuation system, and other safety related systems meet the requirements of IEEE 279-1971,“Criteria for Protection System for Nuclear Power Generating System.” In addition, otherapplicable criteria are met as described in Sections 3.1 and 7.1.2.

    The nonsafety related instrumentation and controls accomplish reliable control and allowmonitoring of the plant status without degradation of safety related instrumentation. Section 7.7describes the design details.

    The reactor is controlled by a coordinated combination of chemical shim, mechanical controlrods, and temperature coefficients of reactivity. The control system allows the unit to accept stepload changes of 10 percent and ramp load changes of 5 percent per minute over the load range of15 percent to 100 percent power under nominal operating conditions subject to xenon limitations.

    Control of the reactor and the turbine generator is accomplished from the control room, whichcontains all instrumentation and control equipment required for startup, operation, and shutdown,including normal and accident conditions. The turbine generator controls are designed for manualoperation; the operator selects the load setpoint and loading rate. The NSSS automatically followsthe turbine generator, on decreasing power, from loads of 100 to 15 percent power. The operatortakes manual action to match the NSSS to the turbine generator load, for load increases between15% and 100% power. If, during rapid turbine generator loading (5 percent per minute), theresponse of the control rods and chemical shim is not adequate to supply the needed reactivity, thereactor coolant temperature automatically drops to supply more reactivity. If a reactor coolant lowoperating temperature is reached, turbine generator loading is stopped automatically.

    1.2.6 RADIOACTIVE WASTE SYSTEMS

    Radioactive wastes are collected, processed, and disposed of in a safe manner complying withappropriate regulations, in particular, NRC Regulations 10 CFR 20, 10 CFR 50 Appendix I, 10CFR 61, 10 CFR 71, 49 CFR 171-178, 10 CFR 100, and General Design Criteria 60 and 64(Sections 3.1.2.60 and 3.1.2.64). There are three interrelated radioactive waste treatment systems:radioactive liquid waste, radioactive gaseous waste, and radioactive solid waste. Chapter 11describes these systems.

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-5

    The radioactive liquid waste system (LWS) collects, classifies, and processes all radioactive wasteliquids generated during plant operation and refueling, either for recycle within the plant or fordischarge off site. The process operations available to treat the liquid wastes are filtration anddemineralization. The process descriptions and flow diagrams illustrate the number and sequenceof processing steps to be applied to each type of liquid waste (Section 11.2).

    Gaseous wastes, consisting of hydrogen streams and air streams containing various levels ofradioactivity, are treated before release to the environment. Through the use of degasification andpurification of reactor coolant letdown, the consequences of any reactor coolant leakage areminimized. This degasification and purification process produces hydrogen waste gas streams,which are passed through charcoal decay beds to provide adequate holdup time for the decay ofnoble gases and the removal of iodines. The decay beds are followed by high efficiencyparticulate air filters to ensure particulate removal. Aerated waste gas streams, produced by otherphases of unit operation, are released to the environment via the Millstone stack. A process flowdiagram, illustrating the processing steps for gaseous waste, appears in Section 11.3.

    The radioactive solid waste system provides holdup, packaging, and storage facilities for theeventual off site shipment and ultimate disposal of solid radioactive waste material. Availableprocess operations are: solidification of liquid wastes, holdup for decay, sluicing and dewateringof resins, encapsulation of miscellaneous solid wastes, and compacting of compressibles.Provisions for shielding during the processing and shipment of solid wastes are included in thedesign of the radioactive solid waste system. A process flow diagram illustrates the processingand handling sequences for solid wastes generated by the plant (Section 11.4).

    1.2.7 FUEL HANDLING

    The reactor is refueled by equipment designed to handle spent fuel under water from the time thespent fuel leaves the reactor vessel until the spent fuel is placed in a cask for shipment from thesite. Underwater transfer of spent fuel provides an optically transparent radiation shield as well asa reliable source of coolant for the removal of decay heat produced by the spent fuel. New fuel istransferred to the fuel pool using the new fuel handling crane and is loaded into the reactor usingthe same equipment that handles the spent fuel. (Section 9.1.4)

    1.2.8 TURBINE GENERATOR AND AUXILIARIES

    The turbine is a tandem-compound, six-flow, 1,800 rpm unit with 43 inch last stage blades. Twocombination moisture separator-reheaters remove moisture and superheat the steam between thehigh and low pressure turbines. The turbine generator is discussed, in detail, in Section 10.2.

    The turbine generator plant and associated steam and power conversion systems are capable of a40 percent load rejection without producing a reactor trip. This is accomplished by dumpingsteam into the condenser through the turbine bypass system which reduces the transient to withinthe NSSS transient response capability.

    The turbine control system is an electrohydraulic control (EHC) system capable of remote manualor automatic control of acceleration and loading of the unit at preset rates, and holding speed and

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-6

    load at a preset level. The EHC provides a normal overspeed protection system and an emergencyoverspeed protection system to limit turbine overspeed.

    A single-pass deaerating surface condenser installed in three sections, two 100 percent designcapacity steam jet air ejector units, three 50 percent design capacity condensate pumps, threesteam generator feedwater pumps (two turbine-driven and one motor-driven), two 50 percentdesign capacity motor-driven and one 100 percent design capacity turbine-driven steam generatorauxiliary feedwater pumps, three trains of feedwater heaters, each having six stages, and a fullflow condensate demineralizer polishing system are provided. Any combination of two steamgenerator feedwater pumps is adequate to support 100% power operation. Condenser circulatingwater is provided by six circulating water pumps. The turbine plant component cooling systemprovides cooling water for lubricating oil coolers, generator hydrogen coolers, and other turbineplant auxiliary heat loads.

    1.2.9 ELECTRICAL SYSTEMS

    The electric power system includes the electrical equipment and connections required to generateand deliver electric power to the 345 kV system. This system also includes station serviceelectrical equipment to provide electric power to support station auxiliaries during normaloperation, startup, shutdown, and accident conditions.

    The major component in the system is the turbine-driven main generator. The electric poweroutput from this generator is stepped up in a transformer bank and delivered to the 345 kVswitchyard for distribution to the utility grid.

    The station service equipment consists of switchgear, load centers, motor control centers, ac vitaland nonvital buses, and battery systems. The normal source of station service power is providedby the main generator through normal station service transformers. Startup and shutdown stationservice power is provided by a preferred off site source from the 345 kV switchyard through themain and normal station service transformers with the generator breaker open, or by thealternative off site source from the 345 kV switchyard through the reserve station servicetransformers. In the event of an accident with loss of both normal and off site sources, an on siteemergency power system, consisting of two redundant diesel engine-driven generators, providespower to the emergency 4,160V buses within 11 seconds after receiving a start signal. Thesediesel engine-driven generators are sized to provide required power to all safety relatedequipment.

    1.2.10 ENGINEERED SAFETY FEATURES

    Engineered safety features (ESF) are provided to mitigate the consequences of postulatedaccidents including a loss-of-coolant accident (LOCA) resulting from large and small pipe breaks.The ESF systems provided for Millstone 3 have sufficient redundancy and independence ofcomponents and power sources so that, under the conditions of the postulated accident, the

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-7

    systems maintain the integrity of the containment structure and accomplish the following evenwhen operating with a postulated single active failure:

    1. Prevent radiation release to the outside environment from exceeding the limit specified in 10 CFR 50.67.

    2. Provide core cooling to prevent excessive metal-water reaction, to limit the core thermal transient, and to maintain the core in a coolable geometry.

    Millstone 3 is independent of Millstone 1 and 2 with respect to ESF. The systems provided forMillstone 3 are summarized below.

    Containment Structure

    The steel lined reinforced concrete containment structure provides a barrier against the escape offission products. It is designed to operate at approximately atmospheric pressure and canwithstand the pressures and temperatures resulting from a spectrum of LOCAs and secondarysystem breaks. The containments response following the accident is similar to other atmosphericPWRs. The structure and all penetrations, including access openings, are of proven design(Section 6.2.1).

    Emergency Core Cooling System

    The emergency core cooling system (ECCS) provides borated water to cool the reactor corefollowing a major LOCA. This is accomplished by the automatic injection of water from thesafety injection accumulators into the reactor coolant loops and by the automatic pumping of aportion of the refueling water storage tank contents into the loops via the charging pumps, thesafety injection pumps, and the residual heat removal pumps. After the injection mode ofemergency core cooling, long term core cooling is maintained by recirculating the water from thecontainment structure sump by the containment recirculation pumps, through the containmentrecirculation coolers, and into the reactor coolant loops directly and via the charging and safetyinjection pumps (Section 6.3).

    Containment Heat Removal System

    The containment heat removal system consists of the quench spray and the containmentrecirculation systems. Following the postulated DBA, the containment pressure is reduced byemploying both systems.

    The quench spray system sprays borated water from the refueling water storage tank (RWST).

    The recirculation spray system draws suction from the containment sump, the content of whichconsists of the primary or secondary system effluent and the quench spray.

    The sump water pH is controlled to be above 7.0 to improve effectiveness of fission productsremoval (Section 6.5.2), and for materials compatibility (Section 6.1.1).

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-8

    The pH is controlled by the dissolution of trisodium phosphate crystals (stored in baskets) in thecontainment sump water.

    Supplementary Leak Collection and Release System

    Following a postulated accident, particulate and gaseous radioactive material is ducted from thecontainment enclosure structure and the buildings contiguous to the containment structure to thesupplementary leak collection and release system (SLCRS), where it is filtered and discharged tothe atmosphere through an elevated stack rather than through a ground-level vent. SLCRS is notcredited for a postulated fuel handling accident.

    Containment Isolation System

    The containment isolation system isolates piping lines which penetrate the containment boundaryso that, in the event of a LOCA, radioactivity is not released to the environment through theselines.

    The lines are either isolated passively (check valves or locked closed manual valves) or isolatedautomatically by receipt of a safety injection signal (SIS), a containment isolation (phase A andB) signal, or a steamline isolation (SLI) signal (Section 6.2.4).

    Engineered Safety Features Actuation System

    The engineered safety features actuation system (ESFAS) monitors selected parameters anddetermines whether predetermined safety limits have been exceeded. If they have been exceeded,the ESFAS initiates action to mitigate the abnormal occurrence (Chapter 7).

    Habitability Systems

    The Millstone 3 control room envelope is equipped with an intake isolation system designed toprotect the plant operators from the presence of hazardous substances outside the control roomenvelope.

    Control room envelope makeup air is supplied via redundant air filtration trains designed to meetthe requirements of Regulatory Guide 1.52 (Section 6.4).

    Inservice Inspection

    All ASME Section III, Code Class 1, 2, and 3 systems and components which require inserviceinspection and testing are designed, fabricated, and erected to meet the inspection requirements ofASME Section XI (except where specific written relief has been granted by the Commissionpursuant to 10 CFR 50.55a). The inservice inspection program includes baseline preserviceexamination and periodic inservice inspection and testing to ensure the operability and integrityof all systems classified Class 1, 2, and 3 pursuant to 10 CFR 50.55a (Sections 5.2.4 and 6.6).

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-9

    1.2.11 COOLING WATER AND OTHER AUXILIARY SYSTEMS

    Cooling water and other auxiliary systems provided in Millstone 3 are outlined below. Theirdesign criteria and details are described in Chapters 9, 10, and 11.

    1. The chemical and volume control system performs the following functions:

    a. Fills the reactor coolant system.

    b. Provides a source of high pressure water for pressurizing the reactor coolant system when cold.

    c. Maintains the water level in the pressurizer.

    d. Reduces the concentration of corrosion and fission products in the reactor coolant.

    e. Adjusts the boric acid concentration of the reactor coolant for chemical shim control.

    f. Provides high pressure seal water for the reactor coolant pump seals.

    2. The boron recovery system concentrates and stores borated radioactive water from reactor coolant letdown (chemical and volume control system) processed through the gaseous waste system. Processing by an evaporator, ion exchanger, filters, and demineralizers in the boron recovery system is capable of producing primary-grade water and concentrated boric acid solution for station reuse or disposal.

    3. Radioactive fluid degasification, liquid concentration, and waste solidification for disposal are provided by the radioactive gaseous waste, radioactive liquid waste, and radioactive solid waste systems.

    4. The service water system provides cooling water for heat removal from the reactor plant auxiliary systems during all modes of operation and from the turbine plant auxiliary systems during normal operation.

    5. The reactor plant component cooling water system, an intermediate cooling system, transfers heat from systems containing reactor coolant or other radioactive or potentially radioactive liquids to the service water system, and provides a source of safety grade cooling water to systems which have this requirement.

    6. The turbine plant component cooling system, also an intermediate cooling system, transfers heat from various turbine plant equipment to the service water system.

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-10

    7. The fuel pool cooling and purification system removes residual heat from spent fuel stored in the spent fuel pool and purifies the water in the refueling cavity and spent fuel pool.

    8. The reactor plant vent and drain systems collect potentially radioactive fluids and gases from various plant systems and transfer these fluids and gases to the boron recovery system or to the appropriate waste disposal system.

    9. Individual ventilation systems are provided for the containment and other structures. The containment ventilation system recirculates and cools containment air. The ventilation and air-conditioning system servicing the main control room provides uninterrupted service, even under accident conditions.

    10. The circulating water system removes heat resulting from the operation of the turbine generator and main condensers. The service water system provides cooling water from the ultimate heat sink for systems and components which require an ensured supply of cooling water under all conditions.

    11. The domestic water system receives water from the Town of Waterford, Conn., public water system and distributes it throughout the unit for power plant system makeup and potable water needs.

    12. The compressed air systems consist of the service air system, instrument air system, and containment air system. Dryers are provided in the instrument air system and the containment instrument air system.

    13. The fire protection system furnishes the capacity to extinguish any probable fires which might occur at Millstone 3. The system includes a water system, a CO2 system, a halon system, and portable fire extinguishers.

    14. The reactor and turbine plant sampling system have the capability for sampling all normal process systems and principal components listed in Tables 9.3–1 and 9.3–2 for laboratory analysis.

    15. The Auxiliary Steam System is designed to supply steam for building heating and freeze protection for outdoor water storage tanks and to carry condensate from various heating and processing equipment associated with both Unit 2 and Unit 3 during normal plant operations. The system is nonnuclear safety (NNS).

    1.2.12 REFERENCE FOR SECTION 1.2

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-11

    FIGURE 1.2–1 NOT USED

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-12

    Withhold under 10 CFR 2.390 (d) (1)

  • Revision 33—06/30/20 MPS-3 FSAR 1.2-13

    FIGURE 1.2–3 (SHEETS 1-3) PIPING & INSTRUMENTATION DIAGRAM LEGEND

    The figure indicated above represents an engineering controlled drawing that is Incorporated byReference in the MPS-3 FSAR. Refer to the List of Effective Figures for the related drawingnumber and the controlled plant drawing for the latest revision.

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-1

    1.3 COMPARISON TABLES

    1.3.1 COMPARISON WITH SIMILAR FACILITY DESIGNS

    Principal features of the design of Millstone 3 at the time of application for an operating licensewere similar to those that were evaluated and approved by the NRC staff for other reactors underconstruction, operation, or review. Comparison of notable similarities and differences to NorthAnna 1 and 2, Surry 1 and 2, Comanche Peak 1 and 2, W. B. McGuire 1 and 2, Maine Yankee, andTrojan was provided in a series of comparison tables in this section. This section is retained forhistorical purposes.

    The design of this facility was based on proven technology attained during the development,design, construction, and operation of pressurized water reactors of similar or identical types. Thedata, performance characteristics, and other information represented a standard design that wasengineered for the particular requirements of the utility system and site characteristics.

    1.3.1.1 Comparison of Nuclear Steam Supply System

    A design comparison of major parameters or features of Millstone 3 with similar plants waspresented in Table 1.3-1. The following plants were used in the comparison:

    1. Comanche Peak Units 1 and 2, Docket Number 55-445, -446

    2. W.B. McGuire Units 1 and 2, Docket Number 50-369, -370

    3. Trojan, Docket Number 50-344

    1.3.1.2 Comparison of Engineered Safety Features

    Table 1.3-2 compared the design data for the Millstone 3 engineered safety features (ESF)systems with similar systems in Trojan (for NSSS scope of supply - ECCS), and North AnnaPower Station Units 1 and 2 (for balance of plant). The ESF systems compared were theemergency core cooling, containment depressurization, hydrogen recombiner, and supplementaryleak collection and release systems.

    These units were chosen for comparison because Millstone 3 systems were similar in design.Trojan and North Anna 1 and 2 obtained operating licenses and are currently in commercialoperation.

    1.3.1.3 Comparison of Containment Concepts

    Table 1.3-3 summarized the design and operating parameters described in Section 6.2.1 for theMillstone 3 containment concept. The table provided a comparison with similar data forsubatmospheric containments from the FSAR for North Anna 1 and 2, and the FSAR for Surry 1and 2. These references were selected because the units used the Stone & Webster subatmosphericcontainment design. Surry 1 and 2 and North Anna 1 and 2 are in commercial operation.

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-2

    1.3.1.4 Comparison of Instrumentation Systems

    Tables 1.3-4 through 1.3-10 compared Millstone 3 instrumentation with similar instrumentation inNorth Anna 1 and 2. These units were chosen for the comparison because they haveinstrumentation similar in design to that of Millstone 3, they have obtained operating licenses, andare currently in commercial operation.

    1.3.1.5 Comparison of Electrical Systems

    Table 1.3-11 compared the Millstone 3 electrical system parameters with similar systems ofMillstone 2 and Maine Yankee Atomic Power Station. The electrical systems compared were the345 kV transmission, ac power, ac vital bus, 125 volt DC, and emergency power systems. Theseunits were chosen for the comparison because they have electrical systems similar in design toMillstone 3. They have obtained operating licenses, and they are currently in commercialoperation.

    1.3.1.6 Comparison of Radioactive Waste Systems

    Tables 1.3-12, 1.3-13, and 1.3-14 compared the radioactive waste systems features for Millstone 3with similar systems in North Anna 1 and 2 and Surry 1 and 2. These units were chosen for thecomparison, because they had radioactive waste systems similar in design to Millstone 3, haveobtained operating licenses, and are currently in commercial operation.

    1.3.1.7 Comparison of Other Reactor Plant Systems

    Table 1.3-15 summarized the final design and operating parameters for the major reactor plantsystems. This table compared the Millstone 3 data with systems data in similar nuclear powerplants (North Anna 1 and 2).

    1.3.2 COMPARISON OF FINAL AND PRELIMINARY DESIGNS

    Table 1.3-16 detailed the significant design changes that were made since the submittal of thePSAR, through the issuance of the operating license.

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-3

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  • Revision 33—06/30/20 MPS-3 FSAR 1.3-4

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  • Revision 33—06/30/20 MPS-3 FSAR 1.3-5

    Num

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  • Revision 33—06/30/20 MPS-3 FSAR 1.3-6

    Hea

    tup

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  • Revision 33—06/30/20 MPS-3 FSAR 1.3-7

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  • Revision 33—06/30/20 MPS-3 FSAR 1.3-8

    TABLE 1.3-2 COMPARISON OF ENGINEERED SAFETY FEATURES

    Emergency Core Cooling System (Section 6.3) Millstone 3 Trojan

    Charging Pump (used for high pressure safety injection)

    Number 3 2

    Design capacity each (gpm) 150 150

    Design total developed head (feet) 5,800 5,800

    Safety Injection Pump (used for intermediate pressure safety injection)

    Number 2 2

    Design capacity each (gpm) 425 425

    Design total developed head (feet) 2,500 2,500

    Residual Heat Removal pump (used for low pressure safety injection)

    Number 2 2

    Design capacity each (gpm) 4,000 3,000

    Design total developed head (feet) 350 375

    Safety Injection Accumulator

    Number 4 4

    Total volume each (ft3) 1,350 1,350

    Water volume (ft3, minimum) 950 870

    Operating pressure (psig, minimum) 600 600

    Containment Depressurization Systems (Section 6.2.2)

    Millstone 3 North Anna 1 and 2

    Quench Spray Pump

    Number 2 2

    Design capacity each (gpm) 4,000 2,000

    Design total developed head (feet) 291 265

    Containment Recirculation Pump

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-9

    Number 4 outside containment

    2 out / 2 in a

    Design capacity each (gpm) 3,950 3,700/3,300

    Design total developed head (feet) 342 287/269

    Millstone 3 North Anna 1 and 2

    Containment Recirculation Cooler

    Number 4 4

    UA per cooler (Btu/hr-°F) 3.865 x 106 3.79 x 106

    Recirculation flow (gpm) 3,950 3,500

    Service water flow (gpm) 6,500 4,500

    Refueling Water Storage Tank

    Volume (gal) 1,206,556 480,000

    Temperature (°F, maximum) 75 50

    Hydrogen Recombiner System (Section 6.2.5)

    Number 2 2

    Flow rate (scfm, each) 50 50

    Supplementary Leak Collection and Release System (Section 6.2.3)

    Number of filter trains 2 None

    Flow rate (scfm, each) 9,700 None

    a. Out - outside containment In- inside containment

    TABLE 1.3-2 COMPARISON OF ENGINEERED SAFETY FEATURES (CONTINUED)

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-10

    TABLE 1.3-3 COMPARISON OF CONTAINMENT CONCEPTS(Section 6.2.1)

    Millstone 3North Anna

    1 and 2Surry

    1 and 2

    Type Subatmospheric Subatmospheric Subatmospheric

    ID (feet) 140 126 126

    Overall height (feet) 200 191 173

    Free volume (ft3) 2.3 x 106 1.825 x 106 1.73 x 106

    Maximum design pressure (psig) 45 45 45

    Design temperature (°F) 280 280 280

    Calculated peak pressure psig) 38.49 44.1 a

    a. Based on Tagami condensing heat transfer coefficient

    44.98 b

    b. Based on Uchida condensing heat transfer coefficient

    Reactor Coolant System:

    Liquid volume (including pressurizer) (ft3)

    11,695 9,874 9,874

    Temperature (mass average) (°F) 583.5 586.8 574.5

    Concrete Thickness:

    Vertical wall 4 feet 6 inches 4 feet 6 inches 4 feet 6 inches

    Dome 2 feet 6 inches 2 feet 6 inches 2feet 6 inches

    Containment structure leak rate (%/day)

    0.30 (0-24 hrs) 0.1 0.1

    0.15 (24-720 hrs) 0.0 0.0

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-11

    TABLE 1.3-4 COMPARISON OF CONTAINMENT ATMOSPHERE PRESSURE SENSOR PARAMETERSA

    a. The numbers stated for components or system performance do not represent the maximum/minimum acceptable or required values to support system operation. Setpoints are stated in the Technical Specifications.

    Pressure Sensors Millstone 3North Anna

    1 and 2

    Containment Atmosphere High Pressure Transmitter (Millstone 3, High-1)

    Number of channels 3 3

    Logic matrix 2/3 2/3

    Approximate setpoint (psia) 19.7 15.0

    Containment Atmosphere Intermediate High-High Pressure Transmitter (Millstone 3; High-2)

    Number of channels 3 3

    Logic matrixÅ 2/3 2/3

    Approximate setpoint (psia) 19.7 20

    Containment Atmosphere High-High Pressure Transmitter (Millstone 3; High-3)

    Number of channels 4 4

    Logic matrix 2/4 2/4

    Approximate setpoint (psia) 24.7 25.0

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-12

    TABLE 1.3-5 COMPARISON OF REACTOR COOLANT PUMP BUS PROTECTION A

    a. The numbers stated for components or system performance do not represent the maximum/minimum acceptable or required valves to support system operation. Settings are stated in the Technical Specifications.

    Millstone 3 North Anna 1 and 2

    Undervoltage Reactor Coolant Pumps Buses

    Number of channels N/A 3

    Logic matrix N/A 2/3

    Approximate Setting (V) N/A 70% of 4,160 (2,912)

    Underfrequency Reactor Coolant Pumps Buses

    Number of channels N/A 3

    Logic matrix N/A 2/3

    Approximate Setting (Hz) N/A 54-59

    Reactor Coolant Pump Shaft Low-Low Speed

    Number of channels 4 N/A

    Logic matrix 2/4 N/A

    Approximate Setting (rpm) (later) N/A

    Reactor Coolant Pump Shaft Low Speed

    Number of channels N/A N/A

    Logic matrix N/A N/A

    Approximate Setting (rpm) N/A N/A

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-13

    TABLE 1.3-6 COMPARISON OF ENGINEERED SAFETY FEATURE ACTUATION SIGNALS

    Signal Actuation Millstone 3 North Anna 1 and 2

    Safety Injection Signal (SIS)

    Low pressurizer pressure coincident with low pressurizer level

    No No

    Low pressurizer pressure Yes Yes

    High main steam line differential pressure No Yes

    Low steam line pressure Yes No

    High main steam flow coincident with low main steam pressure or low temperature average

    No Yes

    High containment atmosphere pressure Yes Yes

    Manual initiation Yes Yes

    Containment Isolation Phase A (CIA) Signal

    Safety injection signal (SIS) Yes Yes

    Manual initiation Yes Yes

    Containment Isolation Phase B (CIB) Signal or Containment Depressurization Actuation (CDA) Signal

    High-High containment atmosphere pressure (Millstone High-3)

    Yes Yes

    Manual initiation Yes Yes

    Steam Line Isolation Signal

    High main steam flow coincident with low steam pressure or low main reactor coolant temperature average

    No Yes

    High-High containment pressure No No

    Intermediate High-High containment atmosphere pressure (Millstone; High-2)

    Yes Yes

    High steam pressure rate Yes No

    Low steamline pressure Yes No

    Manual initiation Yes Yes

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-14

    NOTE:

    The numbers stated for components or system performance do not represent the maximum/minimum acceptable or required values to support system operation.

    TABLE 1.3-7 COMPARISON OF EMERGENCY GENERATOR AND STEAM GENERATOR AUXILIARY FEEDWATER PUMP START SIGNALS

    Component Millstone 3 North Anna 1 and 2 Emergency generator auto start signals

    Emergency bus under-voltage Emergency bus under-voltage

    Safety injection signal (SIS) SIS

    Steam generator auxiliary feedwater pump (motor-driven)

    All steam generator feedwater pumps tripped

    2/4 - lo-lo level trip any steam generator (1/4 matrix) coincident with reactor coolant loop cold leg stop valve open

    2/3 - lo-lo level trip any steam generator (2/3 matrix) coincident with reactor coolant loop hot leg stop valve open or reactor coolant loop cold leg stop valve open

    Sequenced safeguards signal Undervoltage reserve station service power

    SIS SIS

    Steam generator auxiliary feedwater pump (turbine- driven) auto start signals

    2/3 - undervoltage on station service bus

    2/4 - steam generators lo-lo level (2/4 matrix) coincident with reactor coolant loop cold leg stop valve open

    2/3 - steam generator lo-lo level trip (2/3 matrix) coincident with reactor coolant loop hot leg stop valve open or reactor coolant loop cold leg stop valve open

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-15

    TABLE 1.3-8 COMPARISON OF PROCESS AND EFFLUENT RADIATION MONITORING SYSTEMS

    MonitorNumber of Locations

    Millstone 3 North Anna 1 and 2

    Aerated vent particulate 0 1

    Aerated vent gas 0 1

    Ventilation vent particulate 0 1

    Ventilation vent gas 1 1

    Ventilation vent high range (particulate and gas) 1 0

    Hydrogenated vent 1 N/A

    Supplementary leak collection 1 0

    Condenser air ejector 1 1

    Containment recirculation cooler service water outlet 2 4

    Component cooling heat exchanger service water discharge

    0 1

    Liquid waste 1 1

    Steam generator blowdown sample 1 3

    Auxiliary condensate 1 0

    Turbine building floor drains 1 0

    Reactor plant component cooling water subsystem 1 1

    Reactor Coolant Letdown: Gross activity 0 2

    Reactor Coolant Letdown: Specific fission product activity

    0 0

    Circulating water discharge 0 1

    Liquid waste evaporator 0 1

    Service water discharge 0 1

    Service water reservoir 0 1

    Control building inlet 2 0

    Regenerant evaporator (removed from service) 1 0

    Waste neutralizing sump 1 0

    Steam line monitors 5 0

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-16

    TABLE 1.3-9 COMPARISON OF AREA RADIATION MONITORING SYSTEMS

    Monitor

    Number of Locations

    Millstone 3 North Anna 1 and 2Containment structure low range 4 1

    Containment structure high range 4 1

    Manipulator crane 1 1

    Incore instrumentation transfer area 1 1

    Decontamination area 1 1

    New fuel storage area 1 1

    Spent fuel pool pit bridge and hoist 1 1

    Auxiliary building control area 0 1

    Sample room 1 1

    Control room 1 1

    Laboratory (Service building) 1 1

    Auxiliary building general area 8 0

    Equipment decontamination area (Service Building) 1 0

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-17

    TABLE 1.3-10 COMPARISON OF AIRBORNE RADIATION MONITORING SYSTEMS

    Number of LocationsMonitor Millstone 3 North Anna 1 and 2

    Auxiliary building lower levels particulate 2 0

    Auxiliary building lower levels gas 2 0

    Auxiliary building upper levels particulate 3 0

    Auxiliary building upper levels gas 3 0

    Charging pumps cubicles particulate 1 0

    Charging pumps cubicles gas 1 0

    Fuel building particulate 1 0

    Fuel building gas 1 0

    ESF building particulate 1 0

    ESF building gas 1 0

    Waste building particulate 1 0

    Waste building gas 1 0

    Control room particulate 1 0

    Control room gas 1 0

    Containment structure particulate 1 1

    Containment structure gas 1 1

    Ventilation vent sample particulate a

    a. The ventilation vent sample particulate and gas monitors have the capability to take a sample from any one of eight different areas, some of which are equivalent to areas being monitored by separate Millstone 3 monitors.

    1 1

    Ventilation vent sample gas 1 1

    Leak collection area gas 1 0

    Leak collection area particulate 1 0

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-18

    TA

    BLE

    1.3-

    11C

    OM

    PAR

    ISO

    N O

    F EL

    ECTR

    ICA

    L SY

    STEM

    PA

    RA

    MET

    ERS

    Syst

    ems a

    nd C

    ompo

    nent

    s

    Mill

    ston

    e 3

    Mill

    ston

    e 2

    M

    aine

    Yan

    kee

    TRA

    NSM

    ISSI

    ON

    SY

    STEM

    (Sec

    tion

    8.2)

    Tran

    smis

    sion

    Lin

    es to

    Circ

    uits

    4 at

    345

    kV

    3 at

    345

    kV

    2 at

    345

    kV

    (Tot

    al fo

    r 3 U

    nits

    )(T

    otal

    for 2

    Uni

    ts)

    2 at

    115

    kV

    AC

    PO

    WER

    SY

    STEM

    S (S

    ectio

    n8.

    3.1)

    Mai

    n tra

    nsfo

    rmer

    2 at

    630

    MV

    A1

    at 9

    45 M

    VA

    2 at

    430

    MV

    A

    Nor

    mal

    stat

    ion

    serv

    ice

    trans

    form

    er1

    at 5

    0 M

    VA

    (6.9

    kV

    )1

    at 4

    5 M

    VA

    1 at

    30

    MV

    A

    1 at

    40

    MV

    A (4

    .16

    kV)

    1 at

    20

    MV

    A

    Res

    erve

    stat

    ion

    serv

    ice

    trans

    form

    er1

    at 5

    0 M

    VA

    (6.9

    kV

    )1

    at 4

    5 M

    VA

    1 at

    30

    MV

    A

    1 at

    45

    MV

    A (4

    .16

    kV)

    1 at

    20

    MV

    A

    AC

    VIT

    AL

    BU

    S SY

    STEM

    (Sec

    tion

    8.3.

    1)

    Dis

    tribu

    tion

    Cab

    inet

    s6

    44

    Inve

    rters

    4 at

    25

    kVA

    4

    at 1

    5 kV

    A4

    at 1

    0 kV

    A

    1 at

    30

    kVA

    1 at

    60

    kVA

    125-

    V D

    C S

    YST

    EM (S

    ectio

    n8.

    3.2)

    Uni

    t bat

    terie

    s (12

    5V)

    2 at

    165

    0 A

    h

    2 at

    750

    Ah

    2 at

    230

    0 A

    h

    2 at

    255

    0 A

    h1

    at 1

    200

    Ah

    2 at

    180

    0 A

    h

    4 at

    200

    am

    p6

    at 4

    00 a

    mp

    4 at

    250

    am

    p

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-19

    2 at

    50

    amp

    3 at

    200

    am

    p (in

    stal

    led

    spar

    es)

    EMER

    GEN

    CY

    PO

    WER

    SY

    STEM

    (Sec

    tion

    8.3.

    1)

    Emer

    genc

    y ge

    nera

    tor (

    cont

    inuo

    us ra

    ting)

    2 at

    498

    6 kW

    2 at

    275

    0 kW

    2 at

    250

    0 kW

    Emer

    genc

    y 4.

    16 k

    V B

    uses

    2 at

    200

    0/30

    00 a

    mp

    2 at

    200

    0 am

    p2

    at 1

    200

    amp

    TA

    BL

    E1.

    3-11

    CO

    MPA

    RIS

    ON

    OF

    EL

    EC

    TR

    ICA

    L S

    YST

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    PA

    RA

    ME

    TE

    RS

    (CO

    NT

    INU

    ED

    )

    Syst

    ems a

    nd C

    ompo

    nent

    s

    Mill

    ston

    e 3

    Mill

    ston

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    M

    aine

    Yan

    kee

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-20

    TABL

    E1.

    3-12

    CO

    MPA

    RIS

    ON

    OF

    RA

    DIO

    AC

    TIV

    E LI

    QU

    ID W

    AST

    E SY

    STEM

    S

    Mill

    ston

    e 3

    Nor

    th A

    nna

    1 &

    2Su

    rry

    1 an

    d 2

    Type

    of P

    roce

    ssin

    g

    Evap

    orat

    ion

    Yes

    Yes

    Yes

    Dem

    iner

    aliz

    atio

    nY

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    Filtr

    atio

    nY

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    tmen

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    adio

    activ

    e W

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    h A

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    apor

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    n an

    d/or

    dem

    iner

    aliz

    atio

    n an

    d fil

    tratio

    n, if

    requ

    ired

    Sam

    eSa

    me

    Low

    Act

    ivity

    Was

    tes I

    nclu

    ding

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    onta

    min

    ated

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    wer

    Dra

    ins

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    atio

    n (e

    vapo

    ratio

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    d su

    bseq

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    ratio

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    ptio

    nal)

    Sam

    eSa

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    Reg

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    ant C

    hem

    ical

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    teFi

    ltrat

    ion

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    quire

    dN

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    m G

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    nk w

    here

    st

    eam

    is d

    raw

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    f to

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    t hea

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    and

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    wn

    to m

    ain

    cond

    ense

    r fo

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    ent b

    y th

    e co

    nden

    sate

    de

    min

    eral

    izer

    s

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    wdo

    wn

    is c

    oole

    d an

    d se

    nt

    to c

    larif

    ier f

    or fl

    occu

    latio

    n,

    sedi

    men

    tatio

    n, a

    nd fi

    ltrat

    ion.

    Th

    e se

    dim

    ent i

    s sen

    t to

    the

    solid

    was

    te d

    ispo

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    and

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    uid

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    mon

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    atin

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    rge

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    wdo

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    d an

    d th

    en e

    ither

    rele

    ased

    or

    dem

    iner

    aliz

    ed a

    nd fi

    ltere

    d an

    d re

    cycl

    ed to

    the

    mai

    n co

    nden

    ser

    Equi

    pmen

    t

    Hig

    h Le

    vel W

    aste

    Dra

    in T

    anks

    Num

    ber

    22

    2

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-21

    Cap

    acity

    (gal

    /eac

    h)26

    ,000

    *5,

    000

    2,39

    0

    Low

    Lev

    el W

    aste

    Dra

    in T

    anks

    22

    2

    Cap

    acity

    (gal

    /ea)

    4,00

    0 *

    5,00

    02,

    874

    Reg

    ener

    ant E

    vapo

    rato

    r Fee

    d Ta

    nks

    (rem

    oved

    from

    serv

    ice)

    N/A

    N/A

    Num

    ber

    2

    Cap

    acity

    (gal

    /eac

    h)13

    ,500

    Con

    tam

    inat

    ed S

    how

    er D

    rain

    Tan

    k

    Num

    ber

    02

    2

    Cap

    acity

    (gal

    /eac

    h)1,

    400

    (incl

    udin

    g La

    undr

    y)1,

    230

    (incl

    udin

    g La

    undr

    y)

    Was

    te T

    est T

    ank

    Num

    ber

    22

    2

    Cap

    acity

    (gal

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    ,000

    1,50

    054

    8

    Reg

    ener

    ant C

    hem

    ical

    Eva

    pora

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    (rem

    oved

    from

    serv

    ice)

    N/A

    N/A

    Num

    ber

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    Tray

    s, nu

    mbe

    r8

    Cap

    acity

    (gal

    /eac

    h)35

    Was

    te E

    vapo

    rato

    rTAB

    LE1.

    3-12

    CO

    MPA

    RIS

    ON

    OF

    RA

    DIO

    AC

    TIV

    E LI

    QU

    ID W

    AST

    E SY

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    S (C

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    TIN

    UED

    )

    Mill

    ston

    e 3

    Nor

    th A

    nna

    1 &

    2Su

    rry

    1 an

    d 2

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-22

    NO

    TE:

    *In

    clud

    e co

    nden

    sate

    dem

    iner

    aliz

    er, l

    iqui

    d w

    aste

    syst

    em ta

    nk v

    olum

    es. T

    he n

    umbe

    rs st

    ated

    for c

    ompo

    nent

    s or s

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    ms p

    erfo

    rman

    ce

    do n

    ot re

    pres

    ent t

    he m

    axim

    um/m

    inim

    um a

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    tabl

    e or

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    ired

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    es to

    supp

    ort s

    yste

    m o

    pera

    tion.

    Num

    ber

    11

    1

    Tray

    s, nu

    mbe

    r8

    00

    Cap

    acity

    (gal

    /eac

    h)35

    66

    Dem

    iner

    aliz

    ers

    Num

    ber

    Two

    was

    te e

    vapo

    rato

    rs, o

    ne

    rege

    nera

    nt c

    hem

    ical

    eva

    pora

    tor

    (rem

    oved

    from

    serv

    ice)

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    was

    te e

    vapo

    rato

    r di

    still

    ate

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    hing

    , tw

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    arifi

    er d

    emin

    eral

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    s

    One

    was

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    vapo

    rato

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    still

    ate

    polis

    hing

    Type

    Mix

    ed b

    edM

    ixed

    bed

    Mix

    ed b

    ed

    Cap

    acity

    (ft3

    )35

    17/4

    5 re

    spec

    tivel

    y17

    Efflu

    ent F

    ilter

    s

    Num

    ber

    22

    1

    Cap

    acity

    (gpm

    /eac

    h)50

    5075

    Filte

    r ele

    men

    t typ

    eW

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    fibe

    rW

    ound

    cot

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    nthe

    tic fi

    ber

    TA

    BLE

    1.3-

    12C

    OM

    PAR

    ISO

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    AD

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    STE

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    (CO

    NTI

    NU

    ED)

    Mill

    ston

    e 3

    Nor

    th A

    nna

    1 &

    2Su

    rry

    1 an

    d 2

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-23

    TA

    BLE

    1.3-

    13C

    OM

    PAR

    ISO

    N O

    F R

    AD

    IOA

    CT

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    WA

    STE

    SY

    STE

    MS

    Mill

    ston

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    Nor

    th A

    nna

    1 an

    d 2

    Surr

    y 1

    and

    2

    Type

    of T

    reat

    men

    t

    Deg

    asifi

    catio

    nY

    esO

    ccur

    s in

    boro

    n re

    cove

    ry

    syst

    emO

    ccur

    s in

    boro

    n re

    cove

    ry

    syst

    em

    Dec

    ay o

    f nob

    le g

    ases

    in h

    igh

    activ

    ity g

    as

    stre

    amY

    es

    Yes

    Yes

    Filtr

    atio

    n of

    low

    act

    ivity

    gas

    stre

    ams

    reco

    mbi

    ners

    Gas

    stre

    ams

    Yes

    Yes

    No

    Rec

    ombi

    ners

    Stre

    ams

    Yes

    Yes

    No

    Trea

    tmen

    t of S

    tream

    s

    Con

    tinuo

    us d

    egas

    ifica

    tion

    of re

    acto

    r le

    tdow

    nY

    esY

    esY

    es

    Deg

    asifi

    catio

    n of

    letd

    own

    to b

    oron

    re

    cove

    ry sy

    stem

    Yes

    Yes

    Yes

    Dec

    ay m

    etho

    d fo

    r gas

    es st

    rippe

    d in

    de

    gasi

    fier

    Ads

    orpt

    ion

    on c

    harc

    oal f

    or

    min

    imum

    60-

    day

    xeno

    n de

    cay

    befo

    re re

    cycl

    e or

    re

    leas

    e to

    the

    envi

    ronm

    ent

    Rec

    ombi

    natio

    n of

    hyd

    roge

    n st

    ream

    for r

    educ

    tion

    stor

    age

    in g

    as d

    ecay

    tank

    , the

    n ch

    arco

    al fi

    ltrat

    ion

    befo

    re

    rele

    ase

    to a

    tmos

    pher

    e

    Rec

    ombi

    natio

    n of

    hyd

    roge

    n st

    ream

    for r

    educ

    tion

    stor

    age

    in g

    as d

    ecay

    tank

    s bef

    ore

    rele

    ase

    to th

    e en

    viro

    nmen

    t

    Low

    act

    ivity

    air

    stre

    ams

    (non

    vent

    ilatio

    n st

    ream

    s)R

    elea

    se th

    roug

    h M

    illst

    one

    stac

    kFi

    ltrat

    ion

    (cha

    rcoa

    l and

    H

    EPA

    filte

    rs) a

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    cula

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    lters

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    re

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    env

    ironm

    ent

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-24

    Equi

    pmen

    t

    Deg

    asifi

    er

    Num

    ber

    12

    1 (c

    omm

    on to

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    its)

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    acity

    (gpm

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    150

    240

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    ess G

    as C

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    Num

    ber

    22

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    Cap

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    1.5

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    rent

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    lace

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    Proc

    ess G

    as C

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    oal A

    bsor

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    Num

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    20

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    Cap

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    - C

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    lb/e

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    ,500

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    ay T

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    ber

    02

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    Cap

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    (ft3

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    y 1

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  • Revision 33—06/30/20 MPS-3 FSAR 1.3-25

    Num

    ber

    01

    1

    Cap

    acity

    (scf

    m)

    1.5

    1.31

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    sure

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    ber

    02

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    D)

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    ston

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    th A

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    y 1

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  • Revision 33—06/30/20 MPS-3 FSAR 1.3-26

    TA

    BLE

    1.3-

    14C

    OM

    PAR

    ISO

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    y 1

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    t

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    ifica

    tion/

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    mm

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    Yes

    Yes

    Yes

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    tion

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    tC

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    (gal

    )50

    050

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    Spen

    t res

    in tr

    ansf

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    r:

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-27

    Num

    ber

    11

    1

    Cap

    acity

    (gpm

    )15

    010

    015

    0

    Type

    Wou

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    Num

    ber

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    Cap

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    ft3

    55 g

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    um

    Type

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    solid

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    te is

    50

    ft3 o

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    eate

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    D)

    Mill

    ston

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    th A

    nna

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    d 2

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    y 1

    and

    2

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-28

    TABL

    E1.

    3-15

    CO

    MPA

    RIS

    ON

    OF

    OT

    HER

    REA

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    ems w

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    a 1

    and

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    Num

    ber

    22

    Des

    ign

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    city

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    lers

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    Num

    ber

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    t exc

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    tion

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    nt C

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    ling

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    ps:

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    ber

    34

    Des

    ign

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    city

    (gpm

    )8,

    100

    8,00

    0

    Des

    ign

    tota

    l hea

    d (f

    t)28

    419

    0

  • Revision 33—06/30/20 MPS-3 FSAR 1.3-29

    Rea

    ctor

    Pla

    nt C

    ompo

    nent

    Coo

    ling

    Hea

    t Exc

    hang

    ers:

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    ber

    32

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    y pe

    r uni

    t exc

    hang

    er (B

    tu/h

    r)76

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    00,0

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