revision 33—06/30/20 mps-3 fsar 1-i chapter 1—introduction and general description of plant...

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Millstone Power Station Unit 3 Safety Analysis Report

Chapter 1: Introduction and General Description of Plant

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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


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.


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.


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.


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.


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


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


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.


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


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


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).


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).


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.


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


FIGURE 1.2–1 NOT USED


Withhold under 10 CFR 2.390 (d) (1)


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.


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.


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.


TA

BL

E1.

3-1

DE

SIG

N C

OM

PAR

ISO

N

Para

met

er o

r Fe

atur

e

Mill

ston

e 3

FSA

R

Cha

pter

/Se

ctio

nM

illst

one

3C

oman

che

Peak

W. B

. McG

uire

Tro

jan

Rea

ctor

Cor

e H

eat O

utpu

t (M

Wt)

4, 5

, 15.

03,

411

3,41

13,

411

3,41

1

Min

imum

DN

BR

for D

esig

n Tr

ansi

ents

4.1,

4.4

, 15.

0>

1.30

> 1.

30>

1.30

> 1.

30

Tota

l The

rmal

Flo

w R

ate

(10

lb/h

r)4.

1, 4

.4, 5

.114

0.8

140.

314

0.3

132.

7

Rea

ctor

Coo

lant

Tem

pera

ture

s (°F

)4.

1, 4

.4

Cor

e O

utle

t62

0.6

620.

862

0.8

619.

5

Ves

sel O

utle

t61

7.2

618.

261

8.2

616.

8

Cor

e A

vera

ge59

0.5

589.

458

9.4

585.

9

Ves

sel A

vera

ge58

7.1

588.

258

8.2

584.

7

Cor

e In

let

557.

055

8.1

558.

155

2.5

Ves

sel I

nlet

557.

055

8.1

558.

155

2.5

Ave

rage

Lin

ear P

ower

(kW

/ft)

4.1,

4.4

5.44

5.44

5.44

5.44

Peak

Lin

ear P

ower

for N

orm

al O

pera

tion

(kW

/ft)

4.1,

4.4

12.6

12.6

12.6

13.6

Hea

t Flu

x H

ot C

hann

el F

acto

r, F Q

4.1,

4.4

, 15.

02.

322.

322.

322.

50

Fuel

Ass

embl

y A

rray

4.1,

4.3

17 x

17

17 x

17

17 x

17

17 x

17

Num

ber o

f Fue

l Ass

embl

ies

4.1,

4.3

193

193

193

193

Ura

nium

Dio

xide

Rod

s Per

Ass

embl

y4.

1, 4

.326

426

426

426

4

Fuel

Wei

ght a

s Ura

nium

Dio

xide

(lb)

4.1,

4.3

222,

739

222,

739

222,

739

222,

739


Num

ber o

f Grid

s Per

Ass

embl

y4.

1, 4

.38-

Type

R8-

Type

R8-

Type

R8-

Type

R

Rod

Clu

ster

Con

trol A

ssem

blie

s4.

1, 4

.3

Num

ber o

f Ful

l/Par

t Len

gth

61/-

53/-

53/8

53/8

Abs

orbe

r Mat

eria

lH

fH

fA

g-In

-Cd/

B4C

*A

g-In

-Cd

Cla

d M

ater

ial

SS *

*SS

SSSS

Cla

d Th

ickn

ess (

inch

es)

0.01

850.

0185

0.01

850.

0185

Equi

vale

nt C

ore

Dia

met

er (i

nche

s4.

1, 4

.313

2.7

132.

713

2.7

132.

7

Act

ive

Fuel

Len

gth

(inch

es)

4.1,

4.3

144

143.

714

3.7

143.

7

Fuel

Enr

ichm

ent (

Wei

ght P

erce

nt)

4.1,

4.3

Uni

t 1

Uni

t 2

Reg

ion

12.

401.

601.

402.

102.

10

Reg

ion

22.

902.

402.

102.

602.

60

Reg

ion

33.

403.

102.

903.

103.

10

Num

ber o

f Coo

lant

Loo

ps5

44

44

Tota

l Ste

am F

low

(10

lb/h

r)5.

115

.05

15.1

415

.14

15.0

7

Rea

ctor

Ves

sel

5.3

Insi

de D

iam

eter

(inc

hes)

173

173

173

173

Inle

t Noz

zle

Insi

de D

iam

eter

(inc

hes)

27.5

27.5

27-1

/227

.5

Out

let N

ozzl

e In

side

Dia

met

er (i

nche

s)29

2929

29

TABL

E1.

3-1

DES

IGN

CO

MPA

RIS

ON

(CO

NTI

NU

ED)

Para

met

er o

r Fe

atur

e

Mill

ston

e 3

FSA

R

Cha

pter

/Se

ctio

nM

illst

one

3C

oman

che

Peak

W. B

. McG

uire

Tro

jan


Num

ber o

f Rea

ctor

Clo

sure

Hea

d St

uds

5454

5454

Rea

ctor

Coo

lant

Pum

ps5.

4.1

Hor

sepo

wer

7,00

07,

000

7,00

06,

000

Cap

acity

(gpm

)10

0,40

099

,000

99,0

0088

,500

Hea

d (f

eet)

289

288

288

277

Stea

m G

ener

ator

s5.

4.2

Mod

elF

DD

51

Hea

t Tra

nsfe

r Are

a (f

t2)

55,0

0048

,300

48,0

0051

,500

Num

ber o

f U-T

ubes

5,62

64,

578

4,67

43,

388

Res

idua

l Hea

t Rem

oval

5.4.

7

Initi

atio

n Pr

essu

re (p

sig)

425

425

425

400

Initi

atio

n/C

ompl

etio

n Te

mpe

ratu

re (°

F)35

0/12

035

0/14

035

0/14

035

0/14

0

Com

pone

nt C

oolin

g W

ater

Des

ign

Tem

pera

ture

(°

F)95

105

9595

Coo

ldow

n Ti

me

Afte

r Ini

tiatio

n (h

r)20

1616

16

Hea

t Exc

hang

er R

emov

al C

apac

ity (1

0 B

tu/h

r)35

.27

39.1

34.1

534

.2

Pres

suriz

er5.

4.10

TABL

E1.

3-1

DES

IGN

CO

MPA

RIS

ON

(CO

NTI

NU

ED)

Para

met

er o

r Fe

atur

e

Mill

ston

e 3

FSA

R

Cha

pter

/Se

ctio

nM

illst

one

3C

oman

che

Peak

W. B

. McG

uire

Tro

jan


Hea

tup

Rat

e U

sing

Hea

ters

(°F/

hr)

5555

5555

Inte

rnal

Vol

ume

(ft3

)1,

800

1,80

01,

800

1,80

0

Pres

suriz

er S

afet

y V

alve

s5.

4.13

Num

ber

33

33

Max

imum

Rel

ievi

ng C

apac

ity (l

b/hr

)42

0,00

042

0,00

042

0,00

042

0,00

0

Acc

umul

ator

s6.

3

Num

ber

44

44

Ope

ratin

g Pr

essu

re, M

inim

um (p

sig)

600

600

600

600

Min

imum

Ope

ratin

g W

ater

Vol

ume

Each

(ft3

)95

095

095

087

0

Cen

trifu

gal C

harg

ing

Pum

ps6.

3

Num

ber

32

22

Des

ign

Flow

(gpm

)15

015

015

015

0

Des

ign

Hea

d (f

eet)

5,80

05,

800

5,80

05,

800

Safe

ty In

ject

ion

Pum

ps6.

3

Num

ber

22

22

Des

ign

Flow

(gpm

)42

542

542

542

5

Des

ign

Hea

d (f

eet)

2,68

02,

680

2,50

02,

500

TABL

E1.

3-1

DES

IGN

CO

MPA

RIS

ON

(CO

NTI

NU

ED)

Para

met

er o

r Fe

atur

e

Mill

ston

e 3

FSA

R

Cha

pter

/Se

ctio

nM

illst

one

3C

oman

che

Peak

W. B

. McG

uire

Tro

jan


NO

TE:

*Th

e A

g-In

-Cd

on U

nit 1

, B4C

on

Uni

t 2**

SS =

Sta

inle

ss st

eel

***

The

inst

rum

enta

tion

and

cont

rol s

yste

ms d

iscu

ssed

in C

hapt

er7

for M

illst

one

3 ar

e fu

nctio

nally

sim

ilar t

o th

ose

syst

ems

impl

emen

ted

in C

oman

che

Peak

, W. B

. McG

uire

, and

Tro

jan.

Res

idua

l Hea

t Rem

oval

Pum

p5.

4.7,

6.3

Num

ber

22

22

Des

ign

Flow

(gpm

)4,

000

3,80

03,

000

3,00

0

Des

ign

Hea

d (f

eet)

350

350

375

375

Inst

rum

enta

tion

and

Con

trols

7**

***

***

***

*

Che

mic

al a

nd V

olum

e C

ontro

l9.

3.4

Tota

l Sea

l Wat

er S

uppl

y Fl

ow R

ate,

Nom

inal

(g

pm)

3232

3232

Tota

l Sea

l Wat

er R

etur

n Fl

ow R

ate,

Nom

inal

(g

pm)

1212

1212

Letd

own

Flow

, Nor

mal

/Max

imum

(gpm

)75

/120

75/1

2075

/120

75/1

20

Cha

rgin

g Fl

ow, N

orm

al/M

axim

um (g

pm)

55/1

0055

/100

55/1

0055

/100

TABL

E1.

3-1

DES

IGN

CO

MPA

RIS

ON

(CO

NTI

NU

ED)

Para

met

er o

r Fe

atur

e

Mill

ston

e 3

FSA

R

Cha

pter

/Se

ctio

nM

illst

one

3C

oman

che

Peak

W. B

. McG

uire

Tro

jan


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


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


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)


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


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)


Logic matrixÅ 2/3 2/3

Approximate setpoint (psia) 19.7 20

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


Logic matrix 2/4 2/4

Approximate setpoint (psia) 24.7 25.0


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.


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


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


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

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

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



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


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

MonitorNumber of Locations


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


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


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


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


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

EM

PA

RA

ME

TE

RS

(CO

NT

INU

ED

)

Syst

ems a

nd C

ompo

nent

s

Mill

ston

e 3

Mill

ston

e 2

M

aine

Yan

kee


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

esY

esY

es

Filtr

atio

nY

esY

esY

es

Trea

tmen

t of R

adio

activ

e W

aste

s

Hig

h A

ctiv

ity W

aste

sEv

apor

atio

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

C

onta

min

ated

Sho

wer

Dra

ins

Filtr

atio

n (e

vapo

ratio

n an

d su

bseq

uent

ope

ratio

ns a

re o

ptio

nal)

Sam

eSa

me

Reg

ener

ant C

hem

ical

Was

teFi

ltrat

ion

if re

quire

dN

one

Non

e

Stea

m G

ener

ator

Blo

wdo

wn

Blo

wdo

wn

pipe

d to

flas

h ta

nk w

here

st

eam

is d

raw

n of

f to

4th

poin

t hea

ter

and

liqui

d is

dra

wn

to m

ain

cond

ense

r fo

r tre

atm

ent b

y th

e co

nden

sate

de

min

eral

izer

s

Blo

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

sal s

yste

m

and

the

liqui

d di

scha

rged

th

roug

h th

e liq

uid

was

te

mon

itor t

o th

e ci

rcul

atin

g di

scha

rge

tunn

el.

Blo

wdo

wn

is c

oole

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


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

/eac

h)24

,000

1,50

054

8

Reg

ener

ant C

hem

ical

Eva

pora

tor

(rem

oved

from

serv

ice)

N/A

N/A

Num

ber

1

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

STEM

S (C

ON

TIN

UED

)

Mill

ston

e 3

Nor

th A

nna

1 &

2Su

rry

1 an

d 2


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

yste

ms p

erfo

rman

ce

do n

ot re

pres

ent t

he m

axim

um/m

inim

um a

ccep

tabl

e or

requ

ired

valu

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)

One

was

te e

vapo

rato

r di

still

ate

polis

hing

, tw

o cl

arifi

er d

emin

eral

izer

s

One

was

te e

vapo

rato

r di

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

ound

fibe

rW

ound

cot

ton

fiber

Wou

nd sy

nthe

tic fi

ber

TA

BLE

1.3-

12C

OM

PAR

ISO

N O

F R

AD

IOA

CTI

VE

LIQ

UID

WA

STE

SYST

EMS

(CO

NTI

NU

ED)

Mill

ston

e 3

Nor

th A

nna

1 &

2Su

rry

1 an

d 2


TA

BLE

1.3-

13C

OM

PAR

ISO

N O

F R

AD

IOA

CT

IVE

GA

SEO

US

WA

STE

SY

STE

MS

Mill

ston

e 3

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

nd re

leas

e th

ru v

ent o

n to

p of

Uni

t 1

cont

ainm

ent

Filtr

atio

n (c

harc

oal a

nd

parti

cula

te fi

lters

) and

re

leas

e to

env

ironm

ent


Equi

pmen

t

Deg

asifi

er

Num

ber

12

1 (c

omm

on to

bot

h un

its)

Cap

acity

(gpm

/ea)

150

240

Proc

ess G

as C

ompr

esso

r

Num

ber

22

2

Cap

acity

(scf

m/e

a)3

1.5

2.5

(Cur

rent

ly a

band

oned

in p

lace

)

Proc

ess G

as C

harc

oal A

bsor

bers

Num

ber

20

0

Cap

acity

- C

harc

oal (

lb/e

a)13

,500

--

Gas

Dec

ay T

anks

Num

ber

02

2

Cap

acity

(ft3

/ea)

-46

243

4

Pres

sure

(psi

g)-

115

- the

insi

de ta

nk11

5

4 - t

he o

utsi

de ta

nk

Gas

Sur

ge T

ank

(Pro

cess

Gas

Rec

eive

r)

Num

ber

11

1

Cap

acity

(ft3

)10

1515

.7

Was

te G

as R

ecom

bine

rs

TAB

LE1.

3-13

CO

MPA

RIS

ON

OF

RA

DIO

AC

TIV

E G

ASE

OU

S W

AST

E S

YST

EM

S (C

ON

TIN

UE

D)

Mill

ston

e 3

Nor

th A

nna

1 an

d 2

Surr

y 1

and

2


Num

ber

01

1

Cap

acity

(scf

m)

1.5

1.31

Pres

sure

(psi

a)14

22

Was

te G

as C

ompr

esso

rs

Num

ber

02

2

Cap

acity

(scf

m/e

a)

01.

51.

5

Pres

sure

(psi

g)15

012

0

Filte

r for

low

act

ivity

aer

ated

act

ivity

ae

rate

d ga

seou

s was

te e

fflu

ents

Non

eA

ctiv

ated

cha

rcoa

l with

H

EPA

afte

r-fil

ter

Act

ivat

ed c

harc

oal w

ith

HEP

A a

fter-

filte

r

TABL

E1.

3-13

CO

MPA

RIS

ON

OF

RA

DIO

AC

TIV

E G

ASE

OU

S W

AST

E S

YST

EM

S (C

ON

TIN

UE

D)

Mill

ston

e 3

Nor

th A

nna

1 an

d 2

Surr

y 1

and

2


TA

BLE

1.3-

14C

OM

PAR

ISO

N O

F R

AD

IOA

CTI

VE

SOLI

D W

AST

E SY

STEM

S

Mill

ston

e 3

Nor

th A

nna

1 an

d 2

Surr

y 1

and

2

Type

of T

reat

men

t

Solid

ifica

tion/

Dew

ater

ing

Yes

Yes

Yes

Dru

mm

ing

Yes

Yes

Yes

Solid

ifica

tion

agen

tC

emen

tU

rea

form

alde

hyde

Cem

ent

Inpu

ts (T

ype)

Tre

ated

Bor

on e

vapo

rato

r bot

tom

sY

esY

esY

es

Was

te e

vapo

rato

r bot

tom

sY

esY

esY

es

Reg

ener

ant e

vapo

rato

r bot

tom

sEv

apor

ator

rem

oved

from

se

rvic

eN

/AN

/A

Filte

rsY

esY

esY

es

Res

ins

Yes

Yes

Yes

Mis

cella

neou

s was

tes (

cont

amin

ated

cl

othi

ng, t

ools

, pap

er p

rodu

cts,

etc.

)Y

esY

esY

es

Equi

pmen

t

Spen

t res

in h

old

tank

:

Num

ber

11

1

Cap

acity

(gal

)3,

000

1,80

02,

019

Spen

t res

in d

ewat

erin

g ta

nk:

Num

ber

11

1

Cap

acity

(gal

)50

050

061

9

Spen

t res

in tr

ansf

er p

ump

filte

r:


Num

ber

11

1

Cap

acity

(gpm

)15

010

015

0

Type

Wou

nd fi

ber

Wou

nd fi

ber

Wou

nd fi

ber

Evap

orat

or b

otto

ms t

ank:

Num

ber

11

N/A

Cap

acity

(gal

)3,

150

1,10

0

Ship

ping

con

tain

er (w

ith c

ask)

:

Cap

acity

50 ft

350

ft3

55 g

allo

n dr

um

Type

All

solid

was

te is

50

ft3 o

r gr

eate

r shi

ppin

g co

ntai

ners

All

solid

was

te is

ship

ped

in 5

0 ft3

con

tain

ers e

xcep

t co

mpr

essi

ble w

aste

whi

ch

is in

55

gallo

n dr

ums

All

was

te in

55

gallo

n dr

ums

TA

BL

E1.

3-14

CO

MPA

RIS

ON

OF

RA

DIO

AC

TIV

E S

OL

ID W

AST

E S

YST

EM

S (C

ON

TIN

UE

D)

Mill

ston

e 3

Nor

th A

nna

1 an

d 2

Surr

y 1

and

2


TABL

E1.

3-15

CO

MPA

RIS

ON

OF

OT

HER

REA

CTO

R P

LAN

T SY

STEM

S

O

pera

ting

Para

met

ers

Syst

ems w

ith C

ompo

nent

sM

illst

one

3N

orth

Ann

a 1

and

2

Fuel

Poo

l Coo

ling

and

Purif

icat

ion

Syst

em (S

ectio

n9.

1.3)

Fuel

Poo

l Coo

ling

Pum

ps:

Num

ber

22

Des

ign

capa

city

(gpm

)3,

500

2,75

0

Des

ign

tota

l hea

d (f

t)92

80

Fuel

Poo

l Coo

lers

:

Num

ber

22

Dut

y pe

r hea

t exc

hang

er (B

tu/h

r)27

,700

,000

56,8

00,0

00

Fuel

poo

l coo

ling

flow

(gpm

)3,

500

2,75

0

Com

pone

nt c

oolin

g flo

w (g

pm)

1,80

03,

350

Num

ber o

f cor

es c

oole

d15

-1/2

(304

8 Fu

el A

ssem

blie

s)1-

1/3

Fuel

poo

l tem

pera

ture

, nor

mal

(°F)

150

140

Rea

ctor

Pla

nt C

ompo

nent

Coo

ling

Syst

em

(Sec

tion

9.2.

2.1)

Rea

ctor

Pla

nt C

ompo

nent

Coo

ling

Pum

ps:

Num

ber

34

Des

ign

capa

city

(gpm

)8,

100

8,00

0

Des

ign

tota

l hea

d (f

t)28

419

0


Rea

ctor

Pla

nt C

ompo

nent

Coo

ling

Hea

t Exc

hang

ers:

Num

ber

32

Dut

y pe

r uni

t exc

hang

er (B

tu/h

r)76

,000

,000

52,0

00,0

00

Rea

ctor

pla

nt c

ompo

nent

coo

ling

wat

revision 33—06/30/20 mps-3 fsar 1-i chapter 1—introduction and general description of plant...

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