hinkley c environmental permit application

8/13/2019 Hinkley C Environmental Permit Application

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RADIOACTIVE SUBSTANCES REGULATION SUBMISSION HINKLEY POINT C

CHAPTER 1 BACKGROUND INFORMATION AND LOCATION

CHAPTER 1.0

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CONTENTS CHAPTER 1 BACKGROUND INFORMATION ANDLOCATION

SUB-CHAPTER 1.1 LOCATION OF HINKLEY POINT C POWER STATIONAND ITS ENVIRONMENT................................................................................ 3

1. LOCATION OF HINKLEY POINT C ................................................................... 3

1.1. LOCAL DEMOGRAPHIC......................................................................................... 5

2. ENVIRONMENT AROUND HINKLEY POINT C................................................. 6

APPENDIX 1 HINKLEY POINT C INTERNATIONAL STATUTORYDESIGNATIONS...................................................................................................... 7

APPENDIX 2 HINKLEY POINT C NATIONAL STATUTORYDESIGNATIONS...................................................................................................... 8

SUB-CHAPTER 1.2 GENERAL DESCRIPTION OF THE STATION............ 9

1. GENERAL OVERVIEW OF THE UK EPR.......................................................... 9

1.1. DEVELOPMENT OF THE UK EPR ......................................................................... 9

1.2. GENERAL PRINCIPLES OF THE UK EPR ............................................................ 11

2. STRUCTURES WITHIN THE UK EPR UNITS.................................................... 12

2.1. LAYOUT OF THE UK EPR UNITS AT HINKLEY POINT C.................................... 12

2.2. UNIT POSITIONING AT HINKLEY POINT C .......................................................... 12

2.3. GROUPING OF UK EPR STRUCTURES ............................................................... 13

2.4. LIST OF MAIN STRUCTURES WITHIN AN UK EPR UNIT.................................... 13

2.5. SHARED AND NON-SHARED MAIN STRUCTURES AT HINKLEY POINT C...... 14

3. MAIN STRUCTURES AT HINKLEY POINT C RELEVANT TO THE RSRENVIRONMENTAL PERMIT .............................................................................. 15

3.1. NUCLEAR ISLAND AND EXTENSIONS ................................................................ 15

3.2. CONVENTIONAL ISLAND ...................................................................................... 19

3.3. BALANCE OF PLANT............................................................................................. 20

3.4. BUILDINGS RELATED TO SPENT FUEL AND ILW STORAGE........................... 21


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CHAPTER 1.0


3.5. ANCILLARY BUILDINGS/AREAS.......................................................................... 22

4. MAIN PLANTS, SYSTEMS AND PROCESSES HAVING A BEARING ONRADIOACTIVE WASTE...................................................................................... 23

4.1. GENERAL OVERVIEW OF RADIOACTIVE WASTE ............................................. 23

4.2. MAIN SYSTEMS...................................................................................................... 25

APPENDIX 1 UNIT POSITIONING AT HINKLEY POINT C.................................... 43

SUB-CHAPTER 1.3 REFERENCES............................................................. 45


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SUB-CHAPTER 1.1


SUB-CHAPTER 1.1 LOCATION OF HINKLEY POINT C POWERSTATION AND ITS ENVIRONMENT

1. LOCATION OF HINKLEY POINT C

Hinkley Point is located on the west Somerset coast, approximately 25 km east of Minehead and12 km north-west of Bridgwater (see Figures 1 and 2). The site is bounded to the north by theBristol Channel (Bridgwater Bay) and to the west by land in agricultural production. The nearestresidential areas to the site are the hamlets of Shurton, Burton and Stolford, adjacent to thesouthern boundary, approximately 300 m to the east and approximately 11 km to the west of thesite respectively [1]. The permanent nuclear power station development will cover approximately67 hectares.

Immediately to the east, the land is occupied by two nuclear power stations, Hinkley Point A andHinkley Point B, which form the existing Hinkley Point Power Station Complex (see Figure 3).Hinkley Point A operated between 1965 and 2000 and is currently undergoing decommissioning bythe Nuclear Decommissioning Authority (NDA). Hinkley Point B, owned by EDF Energy, hasoperated since 1976 and is scheduled to continue generating electricity until at least 2016.

The Hinkley Point C Development Site has been nominated as strategically suitable in the revisedNational Policy Statement for Nuclear Power Generation (EN-6) (the revised Nuclear NPS) [2].The site benefits from its proximity to the existing road infrastructure and access to cooling water,and it is predominantly outside designated sites of ecological importance. These factors alsocontributed to the inclusion of the site in the revised Nuclear NPS as being suitable for the earlydeployment of new nuclear power. The revised Nuclear NPS does not in itself confer consent fornew nuclear development at Hinkley Point.

The Hinkley Point C nuclear power station development itself would comprise two UK EPR units.The expected net electrical output of each UK EPR unit will be approximately 1,630 megawatts(MW) giving a total site capacity of 3,260 MW. This is sufficient to power approximately 5 millionhomes or 6 % of the UK national requirement, making a significant contribution to the generation oflow-carbon electricity.


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SUB-CHAPTER 1.1


Hinkley Point

Devon

Cornwall

Dorset

Somerset

Hinkley Point

Devon

Cornwall

Dorset

Somerset

Hinkley Point

Devon

Cornwall

Dorset

Somerset

Figure 1 Hinkley Point site location


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SUB-CHAPTER 1.1


Figure 2 Main towns in the vicinity of Hinkley Point C site

1.1. LOCAL DEMOGRAPHIC

The three immediate districts of Sedgemoor, West Somerset and Taunton Deane (see Figure 2)have approximate population sizes of 112,000, 35,400 and 108,200 respectively, and a combinedpopulation of approximately 256,000 according to the mid-year 2007 estimates reported by theOffice for National Statistics, 2008 [1].

Sedgemoor and Taunton Deane are of a similar population size with a population density inkeeping with the South West trend. In contrast, West Somerset is more rural in nature, exhibiting alower population number and a significantly lower population density than local, regional or nationalaverages [1].

The three wards closest to the Hinkley Point C site (Cannington & Quantocks, Quantock Vale andWest Quantocks) have a relatively small population (10,403 persons) displaying an averagepopulation density of 0.56 persons per hectare (PPH). The highest levels of population density are

typically displayed in urban centres of Taunton, Bridgwater, Minehead and Burnham [1].


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SUB-CHAPTER 1.1


Figure 3 Hinkley Point Power Station Complex [3]

2. ENVIRONMENT AROUND HINKLEY POINT C

A number of international and national environmental designations lie in close proximity to the sitehowever, the majority of the site is undesignated.

A wide range of environmental baseline studies have been undertaken to determine theenvironmental context of the Hinkley Point C site and surrounding area. The Hinkley Point C sitearea comprises mixed lowland farmland with hedgerows and occasional trees of variable qualityand small woodland copses. Much of the area is subject to agricultural land management practicesand there is little semi natural habitat present. The contiguity of the proposed site with the existingcomplex reduces the use of agricultural land [3].

Important conservation sites in the vicinity of Hinkley Point C are:

Severn Estuary Special Protection Area (SPA), Special Area of Conservation (SAC) andRamsar site.

Bridgwater Bay Site of Special Scientific Interest (SSSI).

Exmoor and Quantock Oakwood candidate SAC.

Quantock SSSI.

Blue Anchor to Lilstock Coast SSSI.

Ge-mare Farm Fields SSSI.

Berrow Dunes SSSI.

Much of the area listed above is also a National Nature Reserve (NNR) and Exmoor is an Area ofOutstanding Natural Beauty (AONB). See Appendix 1 and Appendix 2 for the conservation areas

of international and national importance in the vicinity of Hinkley Point C.


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Figure1TypicallayoutofasingleEPRunit


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SUB-CHAPTER 1.2


1.2. GENERAL PRINCIPLES OF THE UK EPR

At the centre of the UK EPR is the reactor core capable of producing a thermal output of4500 MWth from a controlled fission reaction contained within a thick-walled steel pressure vessel.

The thermal power is transferred into steam which operates a turbo generator with a net electricaloutput of 1,630 MW. The operation of the UK EPR, as a PWR is based on a primary system, asecondary system and a cooling system.

The primary system is a closed water-filled pressurised system installed in a leak tight concreteenclosure, the reactor building. It comprises a reactor, namely a steel vessel containing thenuclear fuel (reactor core) and four cooling loops, each containing a reactor coolant pump and asteam generator. The heat produced by the nuclear reaction inside the reactor vessel is extractedwith pressurised water which circulates in the primary system. The heated water then passesthrough the steam generators. Here the heat is transferred to the water of the secondary systemwhich flows between the steam generators tubes [1].

The secondary system is a closed system which is independent of the primary system. It supplies

steam to the turbo generator set located in the turbine hall. Water in this system evaporates in thesteam generators heated by the primary system water. The steam drives a turbine coupled to thegenerator which produces electrical energy. After leaving the turbine, the steam is cooled andreturned to its liquid state in the condenser and then returned to the steam generator. Theefficiency of the UK EPR turbine generator set is planned to be greater than that of existing PWRplants.

The cooling system is independent of the primary and secondary systems. It cools the condenserby circulating sea water. This system is an open system at Hinkley Point C. An open system refersto circulating water which is directly drawn from and discharged into the sea. The Hinkley Point Ccondensers will be directly cooled by seawater from the Bristol Channel.

See Figure 2 below for the electricity generating process of a PWR.

Figure 2: Schematic Layout of the Electricity Generating Process of a PWR [1]

Electricity from the generator is stepped-up to high voltage (400 kV) via transformers before being

exported on EDF Energy overhead lines to the National Grid substation which connects thegeneration output to the national grid transmission system [2].


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SUB-CHAPTER 1.2


The nuclear power station at Hinkley Point C is designed for 60 years of operation and makes moreefficient use of fuel than current PWR designs, thus reducing the quantities of spent fuel for a givenenergy produced. Operational radioactive waste from an UK EPR unit would arise in solid, liquid

and gaseous form, which are summarised in Section 4. Systems and plants would be designedand operated using Best Available Techniques (BAT) to minimise liquid and gaseous dischargesand reduce any environmental impact to a practicable minimum.

2. STRUCTURES WITHIN THE UK EPR UNITS

Structures of an UK EPR unit are characterised as standard or site specific. The standard UK EPRunit structures are generic structures standardised within the GDA. Site specific structures will takeaccount of Hinkley Point site constraints. As two UK EPR units are to be built at Hinkley Point C,some structures are shared between the two units without any compromise to the safety,environmental and construction criteria. The layout of the site is based on achieving an efficientlayout minimising the distances between buildings within the safety separation criteria andminimising the impact on the environment.

2.1. LAYOUT OF THE UK EPR UNITS AT HINKLEY POINT C

The layout and design of Hinkley Point C has taken into consideration a number of options andconstraints including:

nuclear and conventional safety and security measures;

environmental risk and radiological protection;

adequate spacing between the Reactor Buildings and Turbine Halls to facilitateconstruction and operation;

provision of an open circuit main cooling system;

on-site spent fuel storage and Intermediate Level Waste (ILW) storage for the two UKEPR units;

energy transmission infrastructure from the Energy Platform to the National Grid 400 kVsubstation; and

an Operational Service Centre to be located between the two units.

2.2. UNIT POSITIONING AT HINKLEY POINT C

The first UK EPR unit to be built at Hinkley Point C is referred to as Unit 1 and the second as Unit2. The respective positioning of Units 1 and 2 , with unit 1 to the east, has been developed basedupon the rationale of simplification of the construction sequence, allowing construction of commonfacilities required to support both units being built with Unit 1 first. The layouts have been adjustedto correspond with the construction sequence drawings. In the second phase of the works, theconstruction traffic from Unit 2 construction across Unit 1 operational area will be minimised.

All common facilities required for plant operation are linked with the construction of Unit 1, e.g.Effluent Treatment Building, Hot Laundry, Hot Workshops, etc. This will allow Unit 1 to operate andmeet all safety and licensing criteria independently of Unit 2 completion.

Appendix 1 illustrates how the units are positioned at Hinkley Point C.


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SUB-CHAPTER 1.2


2.3. GROUPING OF UK EPR STRUCTURES

The UK EPR structures are grouped into the following main elements:

Nuclear Island and extensions. Conventional Island.

Balance of Plant other industrial buildings.

Buildings related to spent fuel and ILW storage.

Ancillary buildings/areas.

2.4. LIST OF MAIN STRUCTURES WITHIN AN UK EPR UNIT

Figure 1 above shows the typical main UK EPR structures. The main structures within a single UKEPR unit at Hinkley Point C are listed below. However, as there are to be two UK EPR units atHinkley Point C some of these structures are shared between the two units (see detailed list inTable 1).

Reactor Building.

Four Safeguard Buildings.

Fuel Building.

Nuclear Auxiliary Building.

Access Building.

Diesel Buildings.

Effluent Treatment Building, which is shared between the two units.

Turbine Hall.

Conventional Island Electrical Building.

Energy Platform.

Cooling Water Structures comprising of the Intake Tunnel, Forebay and Pumping Station.

Outfall Structures comprising of the Outfall Buildings and Outfall Tunnel (the OutfallTunnel is shared between the two units).

Attenuation Pond, which collects and processes the sites waste water, and is sharedbetween the two units.

Gas Storage and Chemical Products Storage, which are shared between the two units.

Operational Service Centre, which is shared between the two units.

There are also additional Hinkley Point C site specific structures which are not listed above, e.g.the interim storage facilities for spent fuel and ILW, Radioactive Waste Treatment Building of Unit 2(for the transfer of radioactive waste from Unit 2) and the Hot Laundry. The standard, site specificand shared structures at Hinkley Point C are shown in Table 1 below and are described inSection 3.


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SUB-CHAPTER 1.2


2.5. SHARED AND NON-SHARED MAIN STRUCTURES AT HINKLEY POINT C

Main Structures

UK EPR

StandardStructures

HPC Site

SpecificStructures

SharedFacilities

Nuclear Island and Extensions

Reactor Building

Four Safeguard Buildings

Fuel Building

Nuclear Auxiliary Building Radioactive Waste Treatment Building of Unit 2(transfer of radioactive waste from Unit 2 to Effluent TreatmentBuilding)

Access Building

Diesel Buildings

Effluent Treatment Building(for radioactive waste treatment of Units 1 and 2)

Discharge Tanks (KER [LRMDS], TER [ExLWDS], SEK[SiteLWDS]) *

Hot Laundry

Hot Workshop, Hot Warehouse and Facilities forDecontamination

Conventional Island

Turbine Hall

Conventional Island Electrical Building

Energy Platform

Balance of Plant

Pumping Station

Intake TunnelForebay

Outfall Buildings

Outfall Tunnel

Attenuation Pond

Demineralisation Station

Fire-Fighting Water Building

Gas Storage and Chemical Products Storage

Buildings related to spent fuel and ILW storage

Interim Storage Facility for Spent Fuel

Interim Storage Facility for Intermediate Level Waste (ILW)

Ancillary Buildings/Areas

Operational Service CentreThe Radioactive Source Storage

Transit Area for Very Low Level Waste (VLLW) and Low LevelWaste (LLW)

* Liquid Radwaste Monitoring and Discharge System (KER [LRMDS])Additional Liquid Waste Discharge System (TER [ExLWDS)Site Liquid Waste Discharge System (SEK [SiteLWDS])

Table 1 Relevant Main Standard and Site Specific Structures


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SUB-CHAPTER 1.2


3. MAIN STRUCTURES AT HINKLEY POINT C RELEVANT TO THE RSRENVIRONMENTAL PERMIT

This section details the relevant main structures on the Hinkley Point C site, necessary for thegeneral understanding of the UK EPR and those which have a bearing on radioactive waste.Therefore, some of the standard UK EPR buildings listed in Table 1 are not explained further. Therelevance of the structures to the RSR permit and the connections to systems relevant to the RSRis explained in this section, where appropriate.

The main systems, which are necessary for the general understanding of the UK EPR and thosewhich have a bearing on radioactive waste, are identified in this section under the applicable mainstructures. These main systems are explained further in Section 4 with their relevance to the RSRpermit.

3.1. NUCLEAR ISLAND AND EXTENSIONS

The design of the Nuclear Island is fixed via the GDA process currently being undertaken by theHSE and the Environment Agency. The Nuclear Islands at Hinkley Point C are the same as thatpresented in the GDA process delivering high standards of safety, security and environmentalprotection.

Each of the two Nuclear Islands will comprise of a Reactor Building, four Safeguard Buildings and aFuel Building which share the same foundation raft. The design of the Reactor Building, FuelBuilding and Safeguards Buildings are identical for the two Nuclear Islands. This independenceprovides safety, constructability and operability advantages.

Other structures within the Nuclear Island and Extensions grouping include:

Nuclear Auxiliary Building, Access Building and Diesel Buildings all one per unit;

Effluent Treatment Building, Discharge Tanks, Hot Laundry, Hot Workshop, HotWarehouse and Facilities for Decontamination all shared between the two units, and

Radioactive Waste Treatment Building of Unit 2 specific to Unit 2.

The following sub-sections describe the relevant structures within the Nuclear Island andExtensions grouping.

3.1.1. The Reactor Building

The Reactor Building is in the centre of the Nuclear Island and houses the core and the maincomponents of the Nuclear Steam Supply System (NSSS). The Reactor Building is cylindrical inshape. The containment is of a double enclosure type with a pre-stressed concrete innerenclosure and a reinforced concrete outer enclosure separated by an inter-space called the inter-containment annulus. The internal surface of the interior containment is covered by a metallic leaktight skin.

The Reactor Building contains the main components of the NSSS which houses the reactor. Otherplants systems within the Reactor Building are:

the In-Containment Refuelling Water Storage Tank (IRWST), which is the ReactorBuilding pool water storage reservoir;

the Chemical and Volume Control System (RCV [CVCS]); and

the Steam Generator Blowdown System (APG [SGBS]).

The Reactor Building is a standard EPR unit structure and is specific to each UK EPR unit.


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3.1.2. The four Safeguard Buildings

The four Safeguard Buildings, also referred to as divisions, are similar in shape. Safety systemsare generally designed with quadruple redundancy, therefore each safety train (containing

safeguard and electrical equipment) is located in a separate Safeguard Building.

Each division contains a mechanical section dedicated to the safeguard systems. The third train ofthe Fuel Pool Cooling (and Purification) System (PTR [FPC(P)S]) is located in one of the fourdivisions.

The Safeguard Buildings are standard EPR unit structures and are specific to each UK EPR unit.

3.1.3. The Fuel Building

The main function of the Fuel Building is to house the fuel storage pool for fresh fuel, associatedfuel handling equipment and initial storage of spent fuel. The Fuel Building contains the followingmain plants and systems:

the fresh fuel and at-reactor spent fuel pools, and two trains of the main PTR [FPC(P)S];

the Extra Boration System (RBS [EBS]);

part of the Chemical and Volume Control System (RCV [CVCS]); and

the ventilation systems with appropriate filtration units in the event of air escaping in anaccident.

The Fuel Building is a standard EPR unit structure and is specific to each UK EPR unit.

3.1.4. The Nuclear Auxiliary Building

The Nuclear Auxiliary Building is built on an independent foundation raft next to the Fuel Building.The Nuclear Auxiliary Building houses the nuclear operation systems and the maintenance areas.

The main systems installed in the Nuclear Auxiliary Building are the following:

The Coolant Storage and Treatment System (TEP [CSTS]) for treatment of primaryeffluents.

The Fuel Pool Purification System (PTR [FPPS]).

The Gaseous Waste Processing System (TEG [GWPS]).

Part of the Steam Generator Blowdown System (APG [SGBS]).

The operational ventilation and chilled water systems of the Nuclear Auxiliary Building.

The Reactor Boron Water Make-up System (REA [RBWMS]).

Part of the Nuclear Island Sampling System.

The Nuclear Auxiliary Building also contains laboratories. All air discharged by ventilatingradiologically-controlled areas in the Nuclear Island buildings is channelled to the Nuclear AuxiliaryBuilding where it is collected and checked before being discharged to atmosphere via the stack.There is a Nuclear Auxiliary Building associated with each unit with a single stack.

The Nuclear Auxiliary Building is a standard EPR unit structure and is specific to each UK EPRunit.

3.1.5. The Access Building

The main function of the Access Building on each UK EPR unit is to control and enable access tothe Nuclear Island, specifically access to the controlled area via an underground gallery and ahigher level access bridge. The building will contain a room for maintaining and decontaminating

minor equipment, together with a number of operational and technical rooms [2].

The Access Building is a standard EPR unit structure and is specific to each UK EPR unit.


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SUB-CHAPTER 1.2


3.1.6. The Diesel Buildings

There two Diesel Buildings for each UK EPR unit which each house two emergency diesel

generator sets and one Station Black Out diesel generator set for plant cooling. The DieselBuildings are constructed from reinforced concrete, and are built on an independent foundation raft.The two buildings are geographically separated to provide protection from external hazards withself-contained and therefore separate fuel supplies.

Each Diesel Building houses two main diesel generator sets each of which supplies a safety trainwithin a division of the Safeguard Buildings, as well as an emergency back-up unit. The tworedundant generators and the emergency generator with their auxiliaries are protected againstinternal hazards by a separating wall.

The Diesel Buildings are standard EPR unit structures and are specific to each UK EPR unit.

3.1.7. The Effluent Treatment BuildingThe Effluent Treatment Building is used for the collection, storage, treatment and disposal of liquidand solid radioactive waste. The Effluent Treatment Building adjoins the Nuclear Auxiliary Buildingof Unit 1.

The Effluent Treatment Building is made of reinforced concrete and is subdivided into main twosections:

a solid waste conditioning and storage section; and

a liquid effluent treatment section.

The Effluent Treatment Building is a standard EPR unit structure and is shared between the twoUK EPR units.

3.1.7.1. Solid Waste Conditioning and Storage Section

The Solid Waste Conditioning and Storage Section is made up of two main areas:

an area acting as a reception room for mobile equipment for resin treatment. It includes alevel used for the control and maintenance of the overhead crane and the baler used forpackaging low-activity waste; and

an area providing sufficient room and access to process, package, monitor and transferthe wastes associated with treatment by the Solid Waste Treatment System (TES[SWTS]).

3.1.7.2. Liquid Effluent Treatment Section

The Liquid Effluent Treatment Section consists of an area that houses mainly the Liquid WasteProcessing System (TEU [LWPS]) facility (for head storage, processing) and the TES [SWTS]facility (for resin storage, concentrates, bay for encapsulating filters). The TEU [LWPS] treatmentsystem (non-recycled liquid waste treatment system) is located in the Effluent Treatment Building,and has a treatment capacity for two units. This area also houses a plant for producing concreteand storing aggregates and the Effluent Treatment Building control room.

3.1.8. Radioactive Waste Treatment Building of Unit 2

The Effluent Treatment Building at Hinkley Point C is shared between the two units and is adjoinedto Unit 1. Therefore, the solid radioactive wastes (LLW and ILW) generated in Unit 2 will be pre-

conditioned in a dedicated building adjoining the Nuclear Auxiliary Building of Unit 2 before transferby road to shared Effluent Treatment Building for treatment and conditioning. This dedicatedbuilding is referred to as the Radioactive Waste Treatment Building of Unit 2.


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SUB-CHAPTER 1.2


Liquid radioactive wastes including active ion exchange resins (from demineralisers in the RCV[CVCS], PTR [FPC(P)S] and sometimes TEP [CSTS]) generated in Unit 2 are transferred directlyto the shared Effluent Treatment Building via underground galleries. Low activity ion exchange

resins generated in Unit 2 are those from the demineralisers of the APG [SGBS], and sometimesfrom the TEP [CSTS] if monitoring shows activity is low.

The two main functions of the Radioactive Waste Building of Unit 2 are:

pre-conditioning of filters (used on RCV [CVCS], PTR [FPC(P)S], TEP [CSTS] of Unit 2) inconcrete drums (type C1 or C4), closed with a temporary biological plug; and

preparation and transfer to the shared Effluent Treatment Building adjoined to Unit 1, ofthe waste packaged in concrete drums (filters) or suitable transfer containers (low activityion exchange resins).

The ventilation of Radioactive Waste Treatment Building of Unit 2 is performed by a specificventilation system in the building which is linked to the Unit 2 Nuclear Auxiliary Building Ventilation

System. Liquid radioactive effluent generated in the Radioactive Waste Treatment Building of Unit2 is collected by the RPE [NVDS] and is transferred directly to the Effluent Treatment Building viaunderground galleries, for treatment by the TEU [LWPS].

The Radioactive Waste Treatment Building of Unit 2 is a site structure specific to Unit 2 only.

3.1.9. The Discharge Tanks

The discharge tanks of the Liquid Radwaste Monitoring and Discharge System (KER [LRMDS]),Additional Liquid Waste Discharge System (TER [ExLWDS]) and Site Liquid Waste DischargeSystem (SEK [SiteLWDS]), adjoin the Effluent Treatment Building. Their pumps are located underand adjacent to the Hot Laundry.

The site discharge tanks for effluent storage prior to discharge comprise of the following:

KER [LRMDS] (system for collection, monitoring and discharge of effluent from theNuclear Island).

TER [ExLWDS] (system for additional storage capacity, if required, and for return ofeffluent from the KER [LRMDS] and SEK [SiteLWDS] back to the TEU [LWPS], ifretreatment is required).

SEK [SiteLWDS] (system for monitoring and discharge of effluent from the secondarycircuit. The Conventional Island Liquid Waste Discharge System (SEK [CILWDS]) collectsand treats effluent from the Turbine Hall before sending to the SEK [SiteLWDS]).

The contents of the KER [LRMDS], TER [ExLWDS] and SEK [SiteLWDS] tanks (also called the T,

S and Ex Tanks, respectively) may be transferred to the TEU [LWPS] for retreatment via the TER[ExLWDS] if required.

Liquid effluents from Unit 2 are routed via underground galleries to the Effluent Treatment Building,or directly to the relevant discharge tank.

These discharge tanks are site specific structures sufficiently sized for the site and are sharedbetween the two UK EPR units and associated facilities. More information on the size andconstruction of the discharge tanks is presented in Chapter 7.

3.1.10. The Hot Laundry

The main function of the Hot Laundry building is to launder radioactive contaminated work clothing

such as overalls and overshoes, for reuse. Non-contaminated work clothing is not laundered in theHot Laundry. Common practice in the UK is for radioactive contaminated work clothing to belaundered off-site. This facility provides Hinkley Point C with the ability to be self sufficient should it


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SUB-CHAPTER 1.2


choose. The Hot Laundry building is adjacent to the Effluent Treatment Building. The Hot Laundrywill discharge effluents to the KER [LRMDS].

The Hot Laundry is a site specific structure sufficiently sized for the site and is shared between the

two UK EPR units.

3.1.11. The Hot Workshop, Hot Warehouse and Facilities for Decontamination

The Hot Workshop, Hot Warehouse and Facilities for Decontamination are encompassed in asingle structure adjacent to the Hot Laundry.

The Hot Workshop is designed to perform machining of radioactive contaminated components ortools. The Hot Workshop may generate liquid effluents, which will be stored underneath the HotLaundry and sent to the TEU [LWPS] for treatment prior to discharge off site.

The Hot Warehouse is designed to store radioactive contaminated tools.

The Facilities for Decontamination is designed to reduce or suppress radioactive contamination oftools, components or wastes. Decontamination of equipment enables reuse of tools andminimisation of the volume of material requiring disposal. Therefore, these facilities enable permitconditions to be achieved.

These structures are site specific sufficiently sized for the site and are shared between the two UKEPR units.

3.2. CONVENTIONAL ISLAND

3.2.1. The Turbine Hall

The location of the Turbine Hall in relation to the Nuclear Island is set by requirements for routingthe Main Steam Supply System pipework and inter-unit tunnels and the need to leave sufficientspace for the air intakes of the Nuclear Island.

The Turbine Hall houses the turbo-generator set, the moisture separator/reheaters, the condenserand the feedwater plant, and the associated support systems.

The Turbine Hall is a standard EPR unit structure and is specific to each UK EPR unit.

3.2.2. The Energy Platform

The Energy Platform is located adjacent to the Turbine Hall and houses the following plant items:

a main transformer; step-down transformers;

a switchroom; and

an auxiliary transformer platform.

Electricity generated from the turbo-generator is stepped up to 400 kV via the main generatortransformer and then this power is exported to the National Grid 400 kV substation via overheadlines and towers.

Auxiliary transformers are utilised to provide lower voltages within Hinkley Point C for poweringequipment.

The Energy Platform is a standard EPR unit structure and is specific to each UK EPR unit.


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3.2.3. The Conventional Island Electrical Building

The Conventional Island Electrical Building houses all the unclassified electrical equipment servingthe Conventional Island and the other unit structures apart from the Nuclear Island. The

Conventional Island Electrical Building is adjacent to the Turbine Hall.

The Conventional Island Electrical Building houses the normal and secured electrical distributionpanels, which supply the Conventional Island systems, together with the instrumentation andcontrol system which manages and monitors these systems.

The Conventional Island Electrical Building is a standard EPR unit structure and is specific to eachUK EPR unit.

3.3. BALANCE OF PLANT

3.3.1. Cooling Water Structures

The cooling water structures comprises the Intake Tunnel, Forebay and Pumping Station.

3.3.1.1. Intake Tunnel

The UK EPR units at Hinkley Point C will be directly cooled by seawater from Bristol Channel viaIntake Tunnels. There is a single Intake Tunnel for each UK EPR unit. The Intake Tunnel isconnected to the Forebay. The location of the intake heads are approximately 3.3 km northwesterly off-shore and the internal diameter of the Intake Tunnel is approximately 6 m.

The Intake Tunnel is a site specific structure and is specific to each UK EPR unit.

3.3.1.2. The Forebay

The water feed to the buildings is via the Forebay which is a semi-circular basin located adjacent tothe Pumping Station. Seawater is transferred to the Forebay via the Intake Tunnel.

The Forebay is a site specific structure and is specific to each UK EPR unit.

3.3.1.3. The Pumping Station

The Pumping Station is adjacent to the Forebay, and contains equipment supplying cooling waterfor:

the Nuclear and Conventional Islands auxiliaries; and

the secondary (condenser) cooling system.

It is a solid structure designed to resist earthquakes.

The Pumping Station is a standard EPR unit structure and is specific to each UK EPR unit.

3.3.2. Outfall Structures

The outfall structures comprise of the Outfall Buildings and Outfall Tunnel.

3.3.2.1. The Outfall Buildings

The Outfall Buildings are located near the Pumping Station, and consist of the Filtering DebrisRecovery Pit (pre-discharge section) and the Outfall Pond (discharge pond).

The Filtering Debris Recovery Pit, which is located between the Pumping Station and the OutfallPond, is designed to receive marine debris discharged from the Pumping Station. A skip with a


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SUB-CHAPTER 1.2


perforated base is used to collect the marine debris, which are then removed by lorry. The water istransferred to the Outfall Pond and then discharged to the sea via the Outfall Tunnel.

The Outfall Pond is a circular concrete structure connected to the common Outfall Tunnel via an

underground outfall gallery.

The outfall galleries of both Outfall Ponds (Unit 1 and Unit 2) meet at a connecting structure thatconnects to the single common Outfall Tunnel.

The Outfall Buildings are site specific structures and are specific to each UK EPR unit.

3.3.2.2. Outfall Tunnel

The common Outfall Tunnel shared between the two UK EPR units at Hinkley Point C is a maindischarge outlet for radioactive liquid waste. The location of the discharge point is approximately2 km off-shore. The internal diameter of the Outfall Tunnel is approximately 7 m.

The Outfall Tunnel is a site specific structure and is shared between the UK EPR units.

3.3.3. Attenuation Pond

The Attenuation Pond, which collects and processes the sites waste water (from SEO-EP andSEH networks), contains a confinement (retention) tank, the SEH (collection of oils andhydrocarbon effluents) sedimentation (settling) tank and an oil filter (separator). The waterprocessed in the Attenuation Pond is transferred to the Forebay.

The Attenuation Pond is a site specific structure and is shared between the two UK EPR units.

3.4. BUILDINGS RELATED TO SPENT FUEL AND ILW STORAGE

3.4.1. Interim Storage Facility for Spent Fuel

The Interim Storage Facility for Spent Fuel provides safe and secure underwater storage of spentfuel once it leaves the spent fuel pool of the Fuel Building, from both UK EPR units, after a periodof cooling. The spent fuel will remain here until disposal at the national Geological Disposal Facility.The Interim Storage Facility for Spent Fuel consists of a pool, or pools, housed in a seismicallyqualified building. Spent fuel assemblies are placed in storage racks, located at the bottom of thepool(s), which are designed to be resistant to movement. Whilst in storage, water cooling andclean-up systems remove the heat generated by the spent fuel assemblies and maintain waterquality. Throughout the operational life of these facilities an inspection and monitoring regime willbe implemented to ensure that fuel is safely stored. The pools are lined with welded stainless steelplates and have leak detection and collection systems to ensure that there is no unplanned release

of radioactivity to the environment.

The discharges of the Interim Storage Facility for Spent Fuel will be covered by the RSR permiteven though the final disposal of the fuel is not. Detailed design of the building is not complete butabatement equipment is likely to be required and similar to that of the PTR [FPC(P)S], noting thatthe initial cooling period in the Fuel Building spent fuel pool will result in much of the short livedactivity decaying and the heat production of the stored fuel being lower. The Interim StorageFacility for Spent Fuel will discharge gaseous effluents via its own dedicated stack, it is proposedthat this is a minor discharge outlet during the operational period. Liquid effluents are planned tobe discharged via the KER [LRMDS].

A number of alternative methods of long-term spent fuel storage are now available to commercialnuclear power plant operators, namely wet storage in ponds or dry storage in a variety of

configurations (casks, vaults or canisters). Any of these mature methods could in principle beemployed to provide additional long-term spent fuel storage capacity at UK EPRs, including thoseat Hinkley Point C. All of the methods have been used successfully internationally, all are capable


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SUB-CHAPTER 1.2


of meeting the high safety and environmental standards that would be required for their use in theUK, and each has its own advantages and disadvantages. There is, therefore, no obviouslypreferred method for the long-term storage of spent fuel at UK EPRs in general, or those at HinkleyPoint C specifically.

Selecting a long-spent method of storing spent fuel at Hinkley Point C has, therefore, been acomplex matter, which has demanded that EDF balance a number of inter-related and sometimescompeting needs and desires. In order to examine the relative advantages and disadvantages ofthe different methods, and to help in making a decision on the method that should be employed atHinkley Point C, EDF undertook a Multi-Attribute Decision Analysis (MADA). The MADA assessedthe four available alternative long-term spent fuel storage methods of wet storage in ponds, drystorage in casks, dry storage in vaults and dry storage in canisters. The performance of the fouralternative options against nineteen attributes was scored, the attributes were weighted and theresults calculated and analysed.

The results of the MADA suggest that on balance, the preferred choice of long-term spent fuelstorage method at Hinkley Point C should be wet storage in ponds. Dry storage would be an

acceptable alternative to wet storage, and would offer some advantages, but on balance these areoutweighed by the advantages offered by pond storage at Hinkley Point C.

The Interim Storage Facility for Spent Fuel is a site specific structure with sufficient capacity toaccommodate spent fuel arisings from both UK EPR units.

3.4.2. Interim Storage Facility for Intermediate Level Waste

ILW generated during the operational phase will be placed in an Interim Storage Facility for ILWwhich will be designed to be in operation for at least 100 years. ILW generated during the 60 yearsof UK EPR operation, primarily from the TES [SWTS] in the Effluent Treatment Building, will beconditioned and packaged in the Effluent Treatment Building before transfer to the Interim StorageFacility for ILW. The Interim Storage Facility for ILW will provide interim storage for all ILW pending

removal to a final national Geological Disposal Facility.

The discharges from the Interim Storage Facility for ILW will be covered by the RSR environmentalpermit even though the final disposal of the ILW is not. Gaseous radioactive emissions will besufficiently small that it is proposed this is considered as a minor discharge outlet. Active liquiddischarges are not anticipated. Design of the building is not complete but abatement equipment isnot likely to be required for operational discharges.

The facility is to be designed and constructed as a stand-alone unit due to continued operation forup to 40 years after the shutdown of the nuclear power plant units.

The Interim Storage Facility for ILW is a site specific structure with sufficient capacity toaccommodate waste arisings from both UK EPR units.

3.5. ANCILLARY BUILDINGS/AREAS

3.5.1. The Operational Service Centre

The Operational Service Centre is a multi-purpose building that serves both units. Itaccommodates access areas to the Nuclear Island, storage areas, various workshops,laboratories, part of the decontamination facilities for operators and workers, site Restaurant duringoperation phase, offices and associated support and welfare facilities.

The Operational Service Centre is a site specific structure and is shared between the two UK EPRunits.


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SUB-CHAPTER 1.2


3.5.2. The Radioactive Source Storage

A facility that will be used to store low activity sealed radioactive sources used for the calibration ofmetering equipment and Non Destructive Testing equipment of metallic elements. The radioactive

source storage is located near the Demineralisation Station.

The Radioactive Source Storage is a site specific structure and is shared between the two UK EPRunits.

3.5.3. The transit area for Very Low Level Waste (VLLW) and Low Level Waste(LLW)

The transit area is for the temporary storage of packaged VLLW and LLW prior to transport off theHinkley Point C site for further treatment or final disposal. These wastes are conditioned by theTES [SWTS] in the Effluent Treatment Building.

This is a site specific area and is shared between the two UK EPR units.

4. MAIN PLANTS, SYSTEMS AND PROCESSES HAVING A BEARING ONRADIOACTIVE WASTE

This Submission does not include the disposal of spent fuel and ILW but the current strategy formanaging these wastes is outlined within Sub-chapter 2.1 based on NNB GenCos IntegratedWaste Management Policy and Principles. The key elements of the management strategy of wasteare:

implementation of the waste hierarchy to minimise waste arisings from all activities thatwill, or have the potential to, give rise to radioactive waste, with priority given to thosetechniques that eliminate or reduce the generation of radioactive waste and then identifyand quantity wastes that are unavoidably generated; and

application of environmental optimisation, through use of BAT.

A summary of the "Environment Case", as described in the Environment Agency guidance [2], ispresented in Chapter 7. It demonstrates that the practice of generating electricity from the UK EPRat Hinkley Point C is considered to be optimised at this stage of the project and that the BAT isbeing applied. It is recognised that the demonstration of environmental optimisation is acontinuous process, which will evolve and grow in parallel with the design, construction, operationand eventual decommissioning of the nuclear power station at Hinkley Point C.

An overview of the operational radioactive waste is summarised below.

4.1. GENERAL OVERVIEW OF RADIOACTIVE WASTE

Radioactive waste is produced by activities associated either directly or indirectly with operatingand maintaining the reactor, and ultimately, from decommissioning the plant. In particular,operating an UK EPR generates radioactive waste in the water of the primary reactor coolantcircuit. As a result of all stages of its operation, during start-up, operation at power and shutdownfor refuelling, it produces:

liquid radioactive discharges;

gaseous radioactive discharges; and

solid radioactive waste (some of which are secondary wastes generated as a result ofremoving activity from liquid and gaseous effluents).

These radioactive materials are in the form of fission products in the fuel and also arise fromactivation of the primary reactor circuit components and the liquid coolant. Once in the coolant,they are transferred around various parts of the primary reactor coolant circuit and can also passinto the various reactor support systems in liquid and gaseous form. Systems and plants are


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SUB-CHAPTER 1.2


operated in a manner so as to minimise the environmental impacts of discharges and alldischarges are monitored and recorded to demonstrate this.

For all these types of waste, the effluent management process may be broken down into the main

steps:

Collection.

Processing (i.e. monitoring, treatment, segregation, characterisation and assessment).

Storage.

Disposal.

4.1.1. Liquid radioactive waste

Liquid radioactive discharges are produced mainly from effluents associated with systems forcollecting and treating the primary circuit water. Other sources of effluents include the fuel poolpurification system and washings from plant decontamination. Effluent treatment facilities includeaccumulation, hold up and monitoring tanks, filters, evaporation, degassing and demineraliser ionexchange resin beds. Facilities to sample and monitor effluents before they are released areprovided. Discharge to the sea is combined with water from the cooling system.

Chapters 2, 4, 7 and 9 of this Submission describe how liquid radioactive waste is generated,treated, assessed and managed prior to disposal.

4.1.2. Gaseous radioactive waste

The main source of gaseous radioactive emissions is from degassing the water in the primarycircuit. This is directed to the TEG [GWPS] where waste gas is dried then passed through a line ofthree activated carbon delay beds to allow noble gases and isotopes of iodine to decay. Afterprimary filtration, the waste gas is further filtered through High Efficiency Particulate Air (HEPA)

filters, (and iodine traps if necessary) sampled and monitored prior to discharge.

Gaseous activity will also be present in the main Nuclear Island buildings (i.e. Reactor Building,Nuclear Auxiliary Building, Effluent Treatment Building, etc.), which are serviced by the Heating,Ventilation and Air Conditioning (HVAC) systems. The effluents from ventilation are passedthrough HEPA filtration systems and, if necessary, iodine traps before being discharged. Allgaseous effluents are collected for discharge through a common stack on each unit (the NuclearAuxiliary Building stack). There is provision for sampling and monitoring gaseous effluents atvarious points in the treatment systems as well as at the unit stack.

Chapters 2, 3, 7 and 9 of this Submission describe how gaseous radioactive waste is generated,treated, assessed and managed prior to disposal.

4.1.3. Solid radioactive waste

Solid radioactive waste includes spent ion exchange resins; spent filter media; worn-out plantcomponents and parts; contaminated protective clothing and tools; rags and tissues and waste oil.In addition, there are also some solid wastes which are secondary wastes generated as a result ofabatement of liquid and gaseous waste transfer of activity to solid form for concentration andcontaining, consistent with UK Government policy. Solid wastes are collected in the Solid WasteConditioning and Storage Section of the Effluent Treatment Building where appropriateconditioning is carried out so that they can be treated and disposed of off-site or for interim storageon site depending on the types of waste.


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SUB-CHAPTER 1.2


The disposal routes of solid waste arisings will depend on the radioactivity level:

Very Low Level Waste (VLLW) appropriately authorised sites.

Low Level Waste (LLW) transfer to authorised sites for recycling, incineration or for high

force compaction or direct disposal to the national Low Level Waste Repository (LLWR). Intermediate Level Waste (ILW) and higher activity wastes National Geological Disposal

Facility (GDF).

LLW and VLLW will be sent off-site promptly after it has been generated; typically the equivalent ofseveral lorry loads per year will be despatched. ILW will be kept onsite for interim storage in theInterim Storage Facility for ILW designed to accommodate the nuclear power stations lifetimearisings and capable of lasting for at least 100 years, pending despatch to a national GDF.

Chapters 2, 6 and 7 of this RSR Submission describe how solid radioactive waste is generated,managed and temporarily stored on site prior to disposal. In addition, Chapter 6 details theestimated volume of packaged solid radioactive waste produced annually at Hinkley Point C basedof estimates presented in the GDA process, and solid waste disposal routes. The relevant main

plants and systems which have a bearing on radioactive waste generation, treatment, assessment,disposal and interim storage are listed in the Table 2 below.

4.2. MAIN SYSTEMS

The main plant, systems and processes having a bearing on radioactive waste generation,treatment, assessment, disposal and interim storage are summarised in Table 2. The table alsodetails the main location of the systems, the relevance of the systems to the RSR permit, anddescribes how these systems relate to each other and are connected.

4.2.1. Main Primary Systems

Figure 3 shows the main routes by which liquid, gaseous and solid radioactive wastes areprocessed and transferred between the main primary systems of the UK EPR.

4.2.2. Main Secondary Systems

Figure 4 shows the main routes by which liquid, gaseous and solid radioactive wastes areprocessed and transferred between the main secondary systems of the UK EPR.

4.2.3. Building Ventilation Systems

A summary of the building ventilation systems is provided in Table 3 below, with the relevance tothe RSR permit and connections to other systems. Further explanation of the building ventilationsystems is provided in Sub-chapter 2.3.

4.2.4. Fuel Management Systems

The fuel is the direct source of activity, either from release of fission products or indirectly throughactivation of corrosion products. The NSSS is composed of a core, which contains 241 fuelassemblies. A fuel assembly is in a 17 x 17 square array comprising 265 fuel rods. The fuel is inthe form of UO2pellets. The pellets are enclosed in a zirconium alloy tube to form fuel rods. Whilstit would be possible to use Mixed Oxide (MOX) pellets in the UK EPR there are currently no plansto use MOX fuel at Hinkley Point C.

Fuel cladding minimising the release of fission products and reducing the number of fuel failures isvery important. Furthermore the ability to detect and manage fuel failures is important to limit therelease of activity into the primary coolant. The efficient use of fuel to minimise the amount of

radioactive waste produced per MWe produced is also an important consideration


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SUB-CHAPTER 1.2


The fuel is used in the reactor and after use, stored for up to 10 years in the Fuel Building spentfuel pool before transfer to the Interim Storage Facility for Spent Fuel.

Figure 5 shows the main systems related to the management of spent fuel and how they relate toeach other.


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ESUBSTANCESREGULATION

SUBMISSIONHINKLEYPOINT

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CHAPTER1BACKGROUNDINFORMATIONANDLOCATION

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Figure3Mainprimarysystems

Fuel

ReactorCoolant

System

GaseousWaste

Processing

System

LiquidWaste

Processing

System

SolidWaste

TreatmentSystem

Chemicaland

VolumeControl

System

NABVentilation

System

ReactorBoron

WaterMakeup

System

Recyclable

effluents

Non-recyclable

effluents

NABs

tack

LiquidRa

dwaste

Monitorin

gand

Discharge

System

SpentFuel

Sto

rageinFuel

Building

Spent

fuel

Offsited

isposal

InterimStorage

FacilityforILW

CoolantStorage

andTreatment

System

Purgegas

Liquid

Condensate

FuelPoolCooling/

Purification

System

NuclearIsland

SamplingSystem

AdditionalLiquid

WasteDis

charge

Syste

m

PlantRadiation

MonitoringSystem

Storage

Treatment

Generation

Disposal

Gas

Solid

Liquid

Key

Monitoring

and

assessment

Monitoring

andDisposal

Interimstorage

Facilityfor

SpentFuel

SecondarySystem

In-Containment

RefuellingWater

StorageTank

FuelBuilding

VentilationSystem

Mixed

Notes:

1.ThemainsystemsandconnectionsrelevanttotheRSRsubmissionareindicatedabove.This

diagramisasimplificationanddoesnotattempttoidentifyalloftheconnectionsbetweensystems

and

nordoesitreplacethemoredetailedengineerin

gdiagrams.

2.TheNuclearVentandDrainSystemisnotex

plicitlyindicatedabovebutisresponsibleforthetra

nsfer

ofliquidandgaseouseffluentsbetweenthesys

tems.

ILW

LLW


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Figure4Main

secondarysystems

SecondarySystem

SolidWaste

TreatmentSystem

SteamGenerator

BlowdownSystem

NABVentilation

System

NABstack

LiquidRadwaste

Monitoringand

DischargeSystem

Offsitedisposal

Condenser

Vacuum

OtherTurbinehall

efflue

nts

SiteLiquidWaste

DischargeSystem

Recyclable

effluents

Non-recyclable

effluents

NuclearIsland

SamplingSystem

AdditionalLiquid

WasteDischarge

System

PlantRadiation

MonitoringSystem

GaseousWaste

Processing

System

CoolantStorage

andTreatment

System

Samples

Storage

Treatment

Generation

Disposal

Gas

Solid

Liquid

Mixed

Key

Monitoring

and

assessment

Monitorin

g

andDisposal

Conventional

IslandLiqW

aste

DischargeSy

stem

Optional


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Figure5Fuelm

anagementsystems


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MainSystems

UKEPR

acronym

EDF

Coding

System

DescriptionofMainFunctions

RelevancetoRSRpermit

M

ainConnectionsandInteractionswith

otherSystems

Locationof

System

Thereare3tanksinthe

KER[L

RMDS]thatservicebothUK

EPRunits.

ofmon

itoring.

TheKE

R[LRMDS]isidentifiedasa

maind

ischargeoutletforliquideffluents

intheRSRpermitsubmission.

Liq

uidWasteDischargeSystem

(TE

R[ExLWDS])foradditionalstorage/decay

capacityandthereturntotheTEU[LWPS]of

outofspecificationeffluents.

AdditionalLiquid

Waste

Discharge

System

ExLWDS

TER

TheAd

ditionalLiquidWaste

Discha

rgeSystem(TER[ExLWDS])

isnotn

ormallyusedandkeptin

reservetoprovideadditionalstorage

capacityshoulditberequired.The

TER[E

xLWDS]tanks(STanks)are

alsous

edtodiverteffluentsfromthe

LiquidRadwasteMonitoringand

Discha

rgeSystem(KER[LRMDS])

andSiteLiquidWasteDischarge

System

(SEK[SiteLWDS])backto

theLiq

uidWasteProcessing

System

(TEU[LWPS])should

retreatmentberequired.

Thereare3tanksinthe

TER[E

xLWDS]thatservicebothUK

EPRunits.

Thissy

stemprovidesbackupcapacity

totheKER[LRMDS]tanks(TTanks)

andSE

K[SiteLWDS]tanks(ExTanks).

Italsoprovidesroutebywhichoutof

specificationeffluentscanbereturned

totheTEU[LWPS]forre-treatment.

TheTE

R[ExLWDS]isidentifiedasa

maind

ischargeoutletforliquideffluents

intheRSRpermitsubmission.

Thissystemisconnectedtothe

KE

R[LRMDS],FuelPoolCooling(and

Purification)System(PTR[FPC(P)S]),

TEU[LWPS],SteamGeneratorBlowdown

System(APG[SGBS])andSiteLiquidWaste

Dis

chargeSystemSEK[SiteLWDS].

ThereisareturnlinetotheTEU[LWPS]fo

r

treatingoutofspecificationeffluents.This

sys

temcan,subjecttosamplingcriteriabe

ing

me

tandoperationalcontrols,dischargevia

the

OutfallBuildingsthroughtheoutfall

tun

nel.

KER-TER-SEK

Tanks


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MainSystems

UKEPR

acronym

EDF

Coding

System

DescriptionofMainFunctions

RelevancetoRSRpermit

M

ainConnectionsandInteractionswith

otherSystems

Locationof

System

wastes

thatissubjecttomeeting

stringe

ntcriteria,areapprovedfor

dischargeviatheOutfallBuildings

throughtheoutfalltunnel.

Collectionof

Oilsand

Hydrocarbon

Effluents

(including

storage)

-

SEH

TheSE

Hcollectsrainwaterwitha

greaterlikelihoodofbeing

contam

inatedwithoiland

hydroc

arbonsfrom:

theo

n-sitecarandHGVparks

and

helipad;

theo

ilstorageareas;

thet

ransformerareas;and

theb

uildingswithpotentialoil

flows(TurbineHalls,diesels,etc.)

TheSE

Hsystemisconnectedtothe

AttenuationPondwhichisdefinedasa

minordischargeoutletforliquid

effluen

ts.

TheSEHsendswatertotheAttenuation

PondpriortotransfertotheForebay.

Sitewide

SiteDrainage

System

-

SEO

TheSE

O-EPsystemissubdivided

intotwoseparatenetworks:

SEO

-EP(Roof/Road);and

SEO

-EU/EV.

SEO-E

P(Roof)networkcollects

rainwaterfromroofs.

SEO-E

P(Roads)networkcollects

rainwaterfromroads.

TheSE

O-EU/EVnetworkcollects

foulwa

terfromthesitebuildings.

TheSE

Osystemisconnectedtothe

AttenuationPondwhichisdefinedasa

minordischargeoutletforliquid

effluen

ts.

TheSEO-EP(Roof/Road)networksends

watertotheAttenuationPondpriortotransfer

totheForebay.

TheSEO-EU/EVsystemsendsfoulwaterto

the

SewageTreatmentPlant.

Sitewide

Table2Mainsystemswhichhaveabearingonradioactivewaste


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SUB-CHAPTER 1.3 REFERENCES

SUB-CHAPTER 1.1 LOCATION OF HINKLEY POINT C POWER STATIONAND ITS ENVIRONMENT

[1] EDF Energy, Hinkley Point C Proposed Nuclear Development, Pre-ApplicationConsultation Stage 2, Consultation on Preferred Proposals, Health Impact Appraisal,August 2010

[2] Department of Energy and Climate Change, Revised National Policy Statement forNuclear Generation [EN-6], Version for Approval, June 2011

[3] EDF Energy, Hinkley Point C Proposed Nuclear Development, Pre-Application

Consultation Stage 2, Consultation on Preferred Proposals, Masterplan: Main Site andBuildings, August 2010

SUB-CHAPTER 1.2 GENERAL DESCRIPTION OF THE STATION

[1] EDF Energy, Hinkley Point C Proposed Nuclear Development, Pre-ApplicationConsultation Stage 2, Consultation on Preferred Proposals, Masterplan: Main Site andBuildings, August 2010

[2] EDF / AREVA NP, GDA PCER Sub chapter 1.2 General description of the unitUKEPR-0003-012 Issue 01


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