ML080290234

Radioactive Waste Management System and Effluent Control System Description from Vogtle Electric Generating Plant, Final Safety Analysis Report, Revision 13, Burke County, Georgia

ML080290234
Person / Time
Site:	Vogtle
Issue date:	01/28/2008
From:	Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML080290234 (54)

Text

VEGP-FSAR-1 boron, in the form of burnable poison rods, is employed in the first core to establish the desired initial reactivity.

'The fuel rods consist of slightly enriched uranium dioxide cylindrical pellets contained in slightly cold-worked, Zircaloy-4 tubing which is plugged and seal welded at the ends to encapsulate the fuel. All fuel rods are pressurized with helium during fabrication to reduce stresses and strains and to increase fatigue life.

Additional reactivity control is provided by control rod assemblies which consist of a group of individual absorber rods fastened at the top end to a common hub or spider assembly. The control rod drive mechanisms for the control rod assemblies are of the magnetic latch type.

The latches are controlled by three magnetic coils. They are so designed that upon a loss of power to the coils, the control rod assembly is released and falls by gravity to shut down the reactor.

The components of the reactor internals are divided into three structures consisting of the lower core support structure (including the entire core barrel and neutron shield pad assembly), the upper core support structure, and the incore instrumentation support structure. The reactor internals'support the core, maintain fuel alignment, limit fuel assembly movement, maintain alignment between fuel assemblies and control rod drive mechanisms, direct coolant flow past the fuel elements and to the pressure vessel head, provide gamma and neutron shielding, and (provide guides for the incore instrumentation.

Instrumentation is provided in and out of the core to monitor the nuclear, thermal-hydraulic, and mechanical performance of the reactor and to provide inputs to automatic control functions.

The reactor core design together with corrective actions of the reactor control, protection, and emergency core cooling systems ensure that attained peak local power densities do not:

• Lead to fuel damage during normal operation or faults of moderate frequency.

" Cause failure of more than a small fraction of fuel rods due to infrequent fault.

• 'Prevent acceptable heat transfer during transients associated with limiting faults.

1.2.3.2 Reactor Coolant System The RCS is arranged as four closed loops connected in parallel to the reactor vessel. Each loop consists of one 29-in. inside diameter (ID) outlet pipe (hot leg), one steam generator, and one 27.5-in. ID inlet pipe (cold leg), with one reactor coolant pump in each cold leg. The piping between the steam generator and the reactor coolant pump suction has an inside diameter of 31 in. to reduce pressure drop and improve flow conditions to the pump suction. An electrically heated pressurizer is connected to one of the loops. A safety injection line is connected to each of the four cold legs;- The RCS operates at a nominal pressure of 2235 psig.

The reactor coolant enters the reactor vessel through four inlet nozzles, turns and flows downward between the reactor vessel shell and the core support barrel, and enters the lower plenum through the flow skirt. The coolant then turns and flows upward through the core barrel lower supportstructure, through the core support plate flow holes, and continues parallel to the axis of the fuel assemblies to remove the heat generated within the fuel. The coolant continues its upward flow through the upper guide structure, then turns and leaves the reactor vessel through the four outlet nozzles and the hot leg pipes, which lead to the steam generators..Thb coolant flows through the tube side of the four steam generators, where heat is transferred to the secondary system! Reactor coolant pumps return the reactor coolant to the reactor vessel.

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VEGP-FSAR-1 The pressure in the RCS is controlled by regulating the temperature of the coolant in'the pressurizer, where steam and water are held in thermal equilibrium. Steam is formed by the pressurizer heaters or condensed by the pressurizer spray to reduce pressure variations caused by expansion and contraction of the reactor coolant due to system temperature changes. The pressurizer limits pressure variations during plant load transients and keeps system pressure within design limits during abnormal conditions.

1.2.4 STEAM AND POWER CONVERSION SYSTEM The turbine-generator is furnished by the General Electric Company. The gross generator output at turbine guaranteed rating is 1,156,622 kW output at 1800 rpm, using a tandem compound 6-stage flow machine with 38-in. last-stage buckets. The throttle steam conditions are 940 psia, 1191.4 Btu/Ib, with one stage of reheat. The exhaust pressure is 3.5-in. Hg abs; the makeup is 0.0 percent. Extraction steam is used for normal feedwater heating and for steam generator feed pump turbine operation.

General features of the generator include a 1,350,000-kVA output at 1800 rpm, four poles direct connected, 3-phase, 60-Hz, 25,000-V conductor cooled synchronous generator rated at 0.90 power factor, 0.5 short circuit ratio at maximum hydrogen pressure of 75 psig.

The auxiliary feedwater system contains two motor-driven pumps and one turbine-driven pump.

This system is designed to provide emergency heat removal capacity.

1.2.5 CONTAINMENT The containment completely encloses the reactor and reactor coolant system. It is a vertical, right-cylindrical, prestressed, post-tensioned concrete structure with a dome and flat base with a depressed center for a reactor cavity and instrumentation tunnel. The interior is lined with carbon steel plate for leaktightness. Approximate dimensions of the containment are as follows: inside diameter, 140 ft; inside height, 228 ft; vertical wall thickness, 3 ft 9 in.; dome thickness, 3 ft 9 in.; foundation thickness, 10 ft 6 in., with a minimum thickness of the concrete basemat of 8 ft 3 in.; and the minimum thickness of the concrete instrumentation cavity of 8 ft.

Inside the containment, the reactor and other nuclear steam supply system components are shielded with concrete. A vent stack is attached to the outside of the containment and extends a short distance above the top of the containment dome. Access to portions of the containment during power operation is permissible.

The containment, along with the safety features, is designed to withstand the internal pressure and coincident temperature resulting from the energy release of the high energy line break accident. The containment design internal pressure is based upon the design basis loss-of-coolant accident, and the internal temperature is based upon design basis main steam line break.

1.2.6 SAFETY FEATURES The safety features limit the potential radiation exposure to the public and to plant personnel following an accidental release of radioactive fission products from the reactor system, particularly as the result of a loss-of-coolant accident (LOCA). These safety features function to localize, control, mitigate, and terminate such accidents, ensuring that 10 CFR 100 guidelines are not exceeded. The safety features include the following systems:

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VEGP-FSAR-1

• Emergency core cooling system (ECCS).

" Containment spray system.

• Containment cooling system.

" Penetration room filtration systems.

• Hydrogen recombiners.

1.2.6.1 Emergency Core Cooling System The ECCS injects borated water into the reactor coolant system following a LOCA. This provides cooling to limit core damage, metal-water reactions, and fission product release and ensures adequate shutdown margin regardless of temperature. The ECCS also provides continuous long term, post-accident cooling of the core by recirculating borated water between the containment sump and the reactor core.

1.2.6.2 Containment Spray System The containment spray system is composed of two redundant, full-capacity trains which are designed to reduce the post-accident containment building iodine concentrations so that offsite doses are less than 10 CFR 100 guidelines.

The containment spray system supplies borated water during injection and borated water mixed with trisodium phosphate during recirculation to the containment atmosphere. The spray system in combination with four of the eight containment air coolers (operating at reduced speed) is sized to provide adequate cooling with either or both of the two containment spray pumps in service. These pumps take suction from the refueling water storage tank. When the RWST empty alarm is received, suction of'the containment spray pumps is aligned to pump water from the containment sump directly into the containment during the recirculation mode of operation.

1.2.6.3 Containment Cooling System The containment cooling system consists of two independent, redundant, full-capacity trains containing the equipment necessary for safe shutdown of the plant following an accident. The system is designed to reduce the post-accident containment pressure to 50 percent or less of the peak containment pressure within 24 h or less following the accident.

1.2.6.4 Penetration Room Filtration Systems The penetration room filtration systems for each unit collect and process potential airborne contamination due to leakage from process components during the recirculation mode of ECCS operation. This filtration limits the environmental activity levels following an accident.

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VEGP-FSAR-1 1.2.6.5 Hydrogen Recombiners Fully redundant electrical hydrogen recombiners inside the containment reduce the percentage of hydrogen in the post- accident containment atmosphere to below combustible levels.

1.2.7 UNIT CONTROL The reactor is controlled by control rod movement and regulation of the boric acid concentration in the reactor coolant. During steady-state operation, the reactor control system maintains a programmed average reactor coolant temperature that rises in proportion to the load.

The solid state protection logic system automatically initiates appropriate action whenever the parameters monitored by this system reach preestablished setpoints. This system acts to trip the reactor, actuate emergency core cooling, close containment isolation valves, and .initiate the operation of other safety feature systems.

1.2.8 PLANT ELECTRICAL POWER The two main turbine-generators are each rated at 1350 MVA, 0.90 power factor, 25,000 V; they are 3-phase, 60-Hz, 1800 rpm hydrogen- and water-cooled units. The power from these units is delivered to the Georgia Power Company 230-kV and 500-kV transmission lines.

Termination points of these lines are described in section 8.2.

Each unit has three separate sources of power for its auxiliaries. The three sources of power and associated electrical equipment ensure the functioning of both units without undue risk to the health and safety of the public and provide reliable power sources for startup, normal operation, safe shutdown, and emergency situations.

The three sources for each unit are:

A. The main turbine-generator supplies normal auxiliary loads during plant operation.

B. The two reserve auxiliary transformers supply the two safety feature buses from the 230-kv switchyard. The standby auxiliary transformer (SAT) may supply either of the two safety feature buses from Plant Wilson.

C. The two standby diesel generators provide emergency power to two safety feature buses. Upon loss of all offsite power, either diesel generator and its associated bus has the capacity to power the equipment required to safely shutdown the reactor and mitigate the consequences of the design bases accidents.

Plant batteries ensure a constant supply of power to vital instruments and controls.

Plant power is distributed through buses at 13,800 V, 4160 V, and 480 V, and 120 V ac. The safety-related dc loads in each unit are powered from four 125-V dc buses.

1.2.9 PLANT INSTRUMENTATION AND CONTROL SYSTEM To avoid undue risk to the health and safety of the public, instrumentation and controls monitor and maintain neutron flux, primary coolant pressure, temperature, and control rod positions within prescribed operating ranges.

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VEGP-FSAR-1 The regulating, process, and containment instrumentation measure temperatures, pressures, flows, and levels in the reactor coolant system, steam systems, containment, and auxiliary systems. Process variables required on a continuous basis for startup, operation, and shutdown of the unit are indicated, recorded, and controlled from the control room. The quality and types of process instrumentation provided ensure safe and orderly operation of all systems and processes over the full operating range of the plant.

Startup and shutdown of the reactor and adjustment of reactor power in response to turbine load demand are provided by the reactor control system. The reactor is controlled by control rod motion for startup, shutdown, and load-follow transients; it is also controlled by a soluble neutron absorber (boron, injected as boric acid into the primary coolant) which is inserted during cold shutdown and refueling, partially removed during reactor startup, and adjusted in concentration during core lifetime to compensate for such effects as fuel consumption and accumulation of fission products which reduce the levels of desirable nuclear reactions. The cdntrol system permits each unit to accept step load increases or decreases of 10 percent and ramp load increases or decreases of 5 percent/min over the load range from 15 percent to, but not exceeding, 100-percent power under normal operating conditions, subject to xenon limitations.

Under normal conditions both the reactor and the turbine-generator are controlled from the control room by Nuclear Regulatory Commission-licensed personnel.

1.2.10 AUXILIARY SYSTEMS Nuclear auxiliary systems perform the following functions:

• Supply reactor coolant system (RCS) water requirements.

" Purify reactor coolant water.

" Introduce chemicals for corrosion inhibition.

" Introduce and remove chemicals for reactivity control.

• Cool system components.

" Remove residual heat during a portion of the reactor cooling period and when the reactor is shut down.

• Cool the spent fuel pool water.

• Permit sampling of reactor coolant water.

• Provide for safety injection.

" Vent and drain the RCS and the auxiliary systems.

• Provide containment ventilation and cooling.

" Process liquid and gaseous wastes and dispose of solid wastes.

These functions are performed by the systems discussed below.

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VEGP-FSAR-1 1.2.10.1 Chemical and Volume Control System (CVCS)

The CVCS performs the following functions:

• Reactivity control.

" Regulation of reactor coolant inventory.

" Reactor coolant purification.

• Chemical additions for corrosion control.

" Seal water injection to reactor coolant pump seals.

The purity level in the RCS is controlled by continuous purification of a bypass stream of reactor coolant. Water removed from the RCS is cooled in the regenerative heat exchanger. From there, the coolant flows to a letdown heat exchanger and through a demineralizer where corrosion and fission products are removed. The coolant then passes through a filter and is sprayed into the volume control tank.

The CVCS automatically adjusts the amount of reactor coolant to compensate for changes in specific volume due to coolant temperature changes and reactor coolant pump shaft seal leakage in order to maintain a constant level in the pressurizer.

1.2.10.2 Residual Heat Removal (RHR) System The RHR system is used to reduce the temperature of the reactor coolant at a controlled rate from 3500F to 140°F and to maintain the proper reactor coolant temperature during refueling.

The RHR pumps are used to circulate the reactor coolant through two RHR heat exchangers, returning it to the RCS through the low-pressure injection header.

1.2.10.3 Auxiliary Feedwater (AFW) System The AFW system provides feedwater to the steam generators for removal of reactor core decay heat following a loss of main feedwater. The AFW system is also used to cool down the reactor to the temperature and pressure conditions required for initiation of the RHR system.

1.2.10.4 Component Cooling Water (CCW) System The CCW system consists of two independent trains of pumps and heat exchangers to remove heat from the various auxiliary systems handling the reactor coolant. Corrosion-inhibited demineralized water is circulated by the system through the spent fuel pool heat exchangers, the residual heat exchangers, and the RHR pump seal coolers.

The CCW system provides an intermediate barrier between the RCS and the nuclear service cooling water (NSCW) system described in paragraph 1.2.10.8.

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VEGP-FSAR-1 1.2.10.5 Auxiliary Component Cooling Water (ACCW) System The ACCW system consists of pumps and heat exchangers to remove heat from various auxiliary systems handling reactor coolant. Corrosion-inhibited demineralized water is circulated by the system through the letdown heat exchanger, the reactor coolant pump coolers, sample heat exchangers, waste gas compressors, and other nonsafety-related heat loads.

The ACCW system provides an intermediate barrier between the RCS and the NSCW system described in paragraph 1.2.10.8.

1.2.10.6 Fuel Handling and Storage System The reactor is refueled with equipment designed to handle spent fuel underwater from the time it leaves the reactor vessel until it is placed in a cask for shipment offsite.' Transfer of spent fuel underwater enables the use of an optically transparent radiation shield and provides a reliable source of coolant for removal of residual heat.

The fuel handling system also provides for the safe handling of rod cluster control assemblies under all foreseeable conditions and for the required assembly, disassembly, and storage of reactor internals. This system includes a manipulator crane located inside the containment above the refueling pool, fuel transfer carriage, upending devices, fuel transfer tube, spent fuel cask bridge crane in the spent fuel pool area, and various devices used for handling the reactor vessel head and internals.

The new fuel storage area is shared by both units and is sized to accommodate storage of 162 fuel assemblies and control rods. The new fuel assemblies are stored in racks in parallel rows having a center-to-center distance of approximately 21 in. to preclude criticality.

Together, the two stainless steel-lined, reinforced concrete spent fuel pools provide storage capacity for 3574 fuel assemblies. Spent fuel assemblies are stored in vertical racks spaced to preclude criticality with no credit taken for the borated pool water. See drawings 1X6AN1OB-66 and AX6AN1OA-6 for the layout of the pools. The layout of the pools is also shown in figures 9.1.2-3 and 9.1.2-5.

Purification and redundant cooling equipment is provided for each spent fuel pool. This equipment may also be used for cleanup of refueling water after each fuel change in the reactor.

1.2.10.7 Sampling Systems Three sampling systems are provided: nuclear sampling system - liquid, nuclear sampling system - gaseous, and turbine plant sampling system. These systems are used for determining both chemical and radiochemical conditions of the various fluids used in the plant.

1.2.10.8 Cooling.Water Systems The turbine-generator condenser is cooled by the circulating water system, which rejects heat to a cooling tower.

The cooling water requirements for various nuclear components, CCW system, ACCW system, and diesel generators are supplied by pumps taking suction from the NSCW tower basins.

Water makeup to the storage basins is supplied by the normal plant makeup wells or the 1.2-15 REV 13 4/06

VEGP-FSAR-1 Savannah River. In addition, a standby nuclear service makeup well can supply makeup flow to the NSCW system as a backup source of water.

1.2.10.9 Plant Ventilation Systems Separate ventilation systems are provided for the containment, penetration rooms, auxiliary building, fuel handling building, control room, control building, turbine building, and emergency diesel generator building. In addition, a purge system, mini- purge system, post-loss-of-coolant accident purge system, and containment preaccess filtration system are provided for the containment.

The auxiliary building, fuel handling building, and control building penetration rooms are ventilated by the penetration room filtration systems, which include filters for control of any leakage from process components during the recirculation mode of emergency core cooling system operation.

1.2.10.10 Plant Fire Protection System The major fire protection system contains both diesel- and electric-driven fire pumps which supply the various hydrants, hose stations, sprinklers, and deluge systems. Hydrants and hose stations are manually operated; the sprinkler and deluge systems are a combination of automatic and manually actuated systems. Supplementary to these facilities, chemical fire-extinguishing equipment is provided to accommodate special requirements for various classes of hazards. Noncombustible and fire-resistant materials are selected for use wherever practical throughout the facility, particularly in critical portions of the plant such as the containment, control room, and components of the safety features system.

1.2.10.11 Compressed Air Systems One reciprocating and two rotary air compressors, with separate aftercoolers and separators, discharge compressed air to two separate headers. These headers provide a continuous supply of filtered, dried, oil-free, compressed air for pneumatic instrument operation and control of pneumatic actuations. The system also provides service air at outlets throughout the plant.

An additional reciprocating compressor train can be aligned to either unit.

1.2.10.12 Radioactive Waste Disposal System The waste disposal system provides controlled handling and disposal of liquid, gaseous, and solid wastes. The waste processing system provides all equipment necessary for controlled treatment and preparation for retention or disposal of all liquid, gaseous, and solid wastes produced as a result of reactor operation.

The liquid waste processing system collects, processes, and recycles reactor grade water; removes or concentrates radioactive constituents; and processes them until suitable for release or shipment offsite. Liquid wastes are sampled and activity levels verified and recorded prior to release. Processed liquid effluent from the RCS will have been subjected to the CVCS purification ion exchanger and the components of the waste processing system and will be within the limits established by the Offsite Dose Calculation Manual.

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VEGP-FSAR-1 The gaseous waste processing system functions to remove fission product gases from the reactor coolant and to contain these gases during normal plant operation. Waste gases are collected in the vent header. These gases are withdrawn from the vent header by one of two compressors and discharged to a waste gas decay tank. The tank contents will be released to the environment in accordance with the program requirements of Technical Specifications, and releases will be within the limits set forth in the Offsite Dose Calculation Manual. Seven waste gas decay tanks and two shared waste gas decay shutdown tanks are provided. Gaseous wastes are discharged through an absolute particle filter to the vent stack.

Solid wastes are stored in suitable containers for eventual disposal.

1.2.11 SHARED FACILITIES AND EQUIPMENT An integrated, twin-unit station enables certain components, systems, and facilities to be designed and arranged so that they are common to both units without impairing the safety or reliability of either unit.

Separate and similar systems and equipment are provided for each unit except as noted in paragraphs 1.2.2.1 and 1.2.2.2.

1.2.12 PRINCIPAL DESIGN CRITERIA The VEGP is designed to comply with the intent of the General Design Criteria for Nuclear Power Plants contained in Appendix A to 10 CFR 50. The details of compliance to the general design criteria are provided in section 3.1.

The principal design criteria are presented in two ways--power generation function or safety function--and grouped according to system. Although the distinctions between power generation or safety functions are not always clear and occasionally overlap, the functional classification facilitates safety analyses, while the grouping by system facilitates the understanding of both the system function and design.

1.2.12.1 General Design Criteria 1.2.12.1.1 Power Generation Design Criteria A. The plant is designed to produce steam for direct use in a turbine-generator unit.

B. Heat removal systems are provided with sufficient capacity and operational adequacy to remove heat generated in the reactor core for the full range of normal operational conditions and abnormal operational transients.

C. Backup heat removal systems are provided to remove decay heat generated in the core under circumstances wherein the normally operational heat removal systems become inoperative. The capacity of such systems is adequate to prevent fuel cladding damage.

D. The fuel cladding, in conjunction with other plant systems, is designed to retain integrity through the range of normal operational conditions and abnormal operational transients.

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VEGP-FSAR-1 E. The fuel cladding accommodates, without loss of integrity, the pressures generated by fission gases released from fuel material throughout the design life of the fuel.

F. Control equipment is provided to allow the reactor to respond automatically to minor load changes, major load changes, and abnormal operational transients.

G. Reactor power level is manually controllable.

H. Control of the reactor is possible from a single location.

I. Reactor controls and related indicators and alarms are arranged to allow the operator to rapidly assess the condition of the reactor system and locate system malfunctions.

J. Interlocks, or other automatic equipment, are provided as backup to procedural controls to avoid conditions requiring the functioning of nuclear safety systems or engineered safety features (ESF).

1.2.12.1.2 Safety Design Criteria A. The plant design conforms to applicable regulations as discussed in sections 1.9 and 3.1.

B. The plant is designed, fabricated, erected, and operated in such a way that the release of radioactive materials to the environment does not exceed the limits and guideline values of applicable government regulations pertaining to the release of radioactive materials for normal operations and for abnormal transients and accidents.

C. The reactor core is designed so its nuclear characteristics do not contribute to a divergent power transient.

D. The reactor is designed so that there is no tendency for divergent oscillation of any operating characteristic, considering the interaction of the reactor with other appropriate plant systems.

E. Gaseous, liquid, and solid waste disposal facilities are designed so that the discharge of radioactive effluents and offsite shipment of radioactive materials can be made in accordance with applicable regulations.

F. The design provides means by which plant operators are alerted when limits on the release of radioactive material are approached.

G. Sufficient indications are provided to allow determination that the reactor is operating within the envelope of conditions considered by plant safety analysis.

H. Radiation shielding is provided and access control patterns are established to allow a properly trained operating staff to control radiation doses within the limits of applicable regulations in any mode of normal plant operations.

1. Those portions of the nuclear steam supply system (NSSS) that form part of the reactor coolant pressure boundary (RCPB) are designed to retain integrity as a radioactive material containing barrier following abnormal operational transients and accidents.

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VEGP-FSAR-1 J. Nuclear safety systems and ESF function to ensure that no damage to the RCPB results from internal pressures caused by abnormal operational transients and accidents.

K. Where positive, precise action is immediately required in response to abnormal operational transients and accidents, such action is automatic and requires no decision or manipulation of controls by plant operations personnel.

L. Essential safety actions are provided by equipment of sufficient redundance and independence so that no single failure of active components can prevent the required actions. For systems or components to which Institute of Electrical and Electronics Engineers (IEEE) 279-1971, Criteria for Protection Systems for Nuclear Power Generating Stations, applies, single failures of both active and passive electrical components are considered in recognition of the higher anticipated failure rates of passive electrical components relative to passive mechanical components.

M. Provisions are made for control of active components of nuclear safety systems and ESF from the control room.

N. Nuclear safety systems and ESF are designed to permit demonstration of their functional performance requirements.

0. The design of nuclear safety systems and ESF includes allowances for natural environmental disturbances such as earthquakes, floods, and storms at the station site.

P. Standby electrical power sources have sufficient capacity to power all nuclear safety systems and ESF requiring electrical power.

Q. Standby electrical power sources are provided to allow prompt reactor shutdown and removal of decay heat under circumstances where normal auxiliary power is not available.

R. A containment is provided which completely encloses the reactor system.

S. The containment is designed to allow periodic integrity and leaktightness testing.

T. The containment, in conjunction with other ESF, limits to less than the prescribed acceptable limits-the radiological effects of accidents resulting in the release of radioactive material to the containment volume.

U. Provisions are made for removing energy from the containment as necessary to maintain the integrity of the containment system following accidents that release energy to the containment.

V. Piping that penetrates the containment and could serve as a path for the uncontrolled release of radioactive material to the environs is automatically isolated whenever such uncontrolled radioactive material release is threatened.

Such isolation is effected in time to limit radiological effects to less than the specified acceptable limits.

W. Emergency core cooling systems (ECCS) are provided to limit fuel cladding temperature to less than the limits established by 10 CFR 50.46 in the event of a loss-of-coolant accident (LOCA).

X. The ECCS provides for continuity of core cooling over the complete range of postulated break sizes in RCPB.

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VEGP-FSAR-1 Y. Actuation of the ECCS occurs automatically when required, regardless of the availability of offsite power supplies and the normal generating system of the station.

Z. The control room is shielded against radiation so that continued occupancy under accident conditions is possible.

AA. In the event that the control room becomes uninhabitable, it is possible to bring the reactor from power range operation to cold shutdown conditions by utilizing the shutdown panels and other equipment available outside the control room.

BB. Backup reactor shutdown capability is provided independent of normal reactivity control provisions. This backup system has the capability to shut down the reactor from any normal operating condition and subsequently to maintain the shutdown condition.

CC. The fuel handling and storage facility is designed to prevent inadvertent criticality and to maintain shielding and cooling of spent fuel.

1.2.12.2 System Criteria The principal design criteria for particular systems are discussed below.

1.2.12.2.1 Nuclear System Criteria A. The fuel cladding is designed to retain integrity as a radioactive material barrier throughout the design power range. The fuel cladding is designed to accommodate, without loss of integrity, the pressures generated by the fission gases released from the fuel material throughout the design life of the fuel.

B. The fuel cladding, in conjunction with other plant systems, is designed to retain integrity throughout any abnormal operational transient.

C. Those portions of the nuclear system that form part of the RCPB are designed to retain integrity as a radioactive material barrier during normal operation and following abnormal operational transients and accidents.

D. Heat removal systems are provided in sufficient capacity and operational adequacy to remove heat generated in the reactor core for the full range of normal operational transients. The capacity of these systems is adequate to prevent fuel cladding damage.

E. Heat removal systems are provided to remove decay heat generated in the core under circumstances wherein the normal operational heat removal systems become inoperative. The capacity of these systems is adequate to prevent fuel cladding damage. The reactor is capable of being shut down automatically in sufficient time to permit decay heat removal systems to become effective following loss of normal heat removal systems.

F. The reactor core and reactivity control system is designed so that control rod action is capable of bringing the core to subcriticality and maintaining it subcritical even with the rod of highest reactivity worth fully withdrawn and unavailable for insertion into the core.

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VEGP-FSAR-1 G. The reactor core is designed so that its nuclear characteristics do not contribute to a divergent power transient.

H. The nuclear system is designed so there is no tendency for divergent oscillation of any operating characteristic, considering the interaction of the nuclear system with other appropriate plant systems.

1.2.12.2.2 Power Conversion Systems Criteria Components of the power conversion systems are designed to produce electrical power from the steam coming from the steam generator, condense the steam into water, and return the water to the steam generator as heated feedwater.

1.2.12.2.3 Electrical Power System Criteria Sufficient normal and standby auxiliary sources of electrical power are provided to facilitate prompt shutdown and continued maintenance of the plant in a safe condition under all credible circumstances. The power sources are adequate to accomplish all required essential safety actions under postulated design bases accident conditions.

1.2.12.2.4 Radwaste System Criteria A. The gaseous and liquid radwaste systems are designed to minimize the release of radioactive effluents from the station to the environs. Such releases as may be necessary during normal operations are limited to values that meet the requirements of applicable regulations.

B. The solid radwaste disposal systems are designed so that in plant processing and offsite shipments are in accordance with applicable regulations.

C. The system design provides means by which station operations personnel are alerted whenever specified limits on the release of radioactive material are approached.

1.2.12.2.5 Auxiliary Systems Criteria A. Fuel handling and storage facilities are designed to prevent criticality and to maintain adequate shielding and cooling for spent fuel. Provisions are made for maintaining the cleanliness of. spent fuel cooling and shielding water.

B. Other auxiliary systems or portions of these systems, such as service water, cooling water, fire protection, heating and ventilating, communications; and lighting, are designed to function during normal and/or accident conditions.

C. Auxiliary systems which are not required to effect safe shutdown of the reactor or maintain it in a safe condition are designed so that a failure of these systems does not prevent the essential auxiliary systems from performing their design functions.

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VEGP-FSAR- 11 11.2.1.3 Equipment Design The LWPS equipment design parameters are provided in table 11.2.1-2.

The seismic design classification and safety classification for the LWPS components and structures are listed in table 3.2.2-1. Safety class designations are also indicated on the LWPS piping and instrumentation diagram, drawings 1X4DB124, 1X4DB125, 1X4DB126, 1X4DB127, AX4DB124-2, AX4DB124-3, "AX4DB124-4, and AX4DB124-5.

11.2.1.4 Reference

1. U.S. Nuclear Regulatory Commission, "Calculation of Releases from Pressurized Water Reactors," NUREG-0017, April 1976.

11.2.2 SYSTEM DESCRIPTIONS The liquid waste processing system (LWPS) collects and processes potentially radioactive wastes for recycling or release to the environment. Provisions are made to sample and analyze fluids before discharge. Based-onthe-laboratory-analysiS-theer eitl-erretained-f6r further-p~rocessing, or rel~aýR-s-n-dbulr cont"ro l-d'-c-ondititons-th ugh-the-cooing-wate-r-syste-m,-

which-dilutes-the-discharge-flowt A permanent record of liquid releases is provided by analyses of- k5nvolume s of effluent.

The radioactive liquid discharged from the reactor coolant system (RCS) is processed by the radwaste processing facility systems and may be discharged or recycled.

The LWPS is arranged to recycle reactor grade water ifdesired. This is implemented by the segregation of equipment drains and waste streams to prevent intermixing of liquid wastes.

The LWPS can be divided into the following subsystems:

A. Reactor Coolant Drain Tank (RCDT) Subsystem This portion of the LWPS collects nonaerated, reactor grade effluent from sources inside the containment.

B. Drain Channel A This portion of the LWPS collects aerated, reactor grade effluent that can be recycled.

C. Drain Channel B This portion of the LWPS processes all effluent that is not suitable for recycling.

D. Radwaste Processing Facility Demineralizers The radwaste processing facility demineralizer systems consist of portable demineralizers installed in subterranean enclosures inside the radwaste processing facility. The radwaste processing facility is described in paragraph 11.4.2.4. The radwaste processing facility demineralizers can be aligned to process any of the three waste drain streams.

E. The radwaste processing facility filtration system consists of a portable, vendor supplied system located within a shielded area inside the radwaste processing facility. The filtration system associated tanks, pumps, accumulator, piping, valves, and controls located within a shielded area inside the radwaste 11.2-4 REV 13 4/06

VEGP-FSAR-1 1 processing facility. The peripheral equipment is located adjacent to the filter assembly. The filter system can be aligned to process any of the three waste drain streams. Details of this equipment are shown on drawing AX4DB124-1.

In addition, the LWPS provides capability for handling and storage of spent ion exchange resins.

The LWPS does not include provisions for processing secondary system wastes. Secondary system effluent is handled by the steam generator blowdown processing system (SGBPS), as described in subsection 10.4.8, and by the turbine building drain system. Estimated releases from these systems are discussed in subsection 11.2.3. The LWPS design, which segregates primary and secondary wastes, minimizes the amount of water that must be processed by discharging low activity wastes directly, where permissible, with no treatment.

Instrumentation and controls necessary for the operation of the LWPS are located on a control board in the auxiliary building. Any alarm on this control board (except for the waste processing holdup control panel) is relayed to the main control board in the control room.

The LWPS piping and instrumentation diagrams are shown in drawings 1X4DB124, 1X4DB125, 1X4DB126, 1X4DB127, AX4DB124-1, AX4DB124-2, AX4DB124-3, AX4DB124-4, and AX4DB124-5 and process flow diagram for the LWPS is shown on figure 11.2.2-1. Table 11.2.1-1 lists the assumptions regarding flows and activity levels that were used in preparation of table 11.2.1-3, which gives nuclide concentrations for key locations within the LWPS as shown on figure 11.2.2-1. The process flow data is calculated using the data in table 11.2.1-1, the flow paths indicated on figure 11.2.2-1, realistic primary coolant activity levels from section 11.1, and decontamination factors as given in reference 1 of subsection 11.2.1.

11.2.2.1 Reactor Coolant Drain Tank Subsystem Recyclable reactor grade effluents enter this subsystem from valve leakoffs, reactor coolant pump No. 2 seal leakoffs, reactor vessel flange leakoff, and other deaerated, tritiated water sources inside the containment. Connections are provided for draining the RCS loops and the safety injection system (SIS) accumulators and for cooling the pressurizer relief tank. In addition, refueling canal drains can be routed to the refueling water storage tank using the RCDT pumps.

The RCDT contents are continuously recirculated through the RCDT heat exchanger to maintain the desired temperature. Level is prevented from varying significantly by a control valve which automatically opens a path from the recirculation line to the BRS when normal tank level is exceeded. The RCDT is also connected to the gaseous waste processing system (GWPS) vent header. Hydrogen gas bottles connected to the RCDT ensure a hydrogen blanket. Maintaining a constant level minimizes the amount of gas sent to the GWPS and minimizes the amount of hydrogen used. Provisions for sampling the gas are provided.

Details of the RCDT subsystem are shown on drawing 1X4DB127. A separate RCDT subsystem is provided for each of the two units.

11.2.2.2' Drain Channel A Subsystem Aereated, tritiated liquid enters drain channel A through lines connected to the waste holdup tank. Sources of this aerated liquid are as follows:

A. Accumulator drainage (via RCDT pump suction).

11.2-5 REV 13 4/06

VEGP-FSAR-1 1 B. Sample room sink drains (excess primary sample volume only).

C. Ion exchanger, filter, pump, and other equipment drains.

The containment sump or auxiliary building sump may be directed to the waste holdup tank or the floor drain tank for processing as necessary.

The collected aerated drainage is pumped or flows to the waste holdup tank prior to processing through the radwaste processing facility filtration system and/or the radwaste processing facility demineralizers before reuse or discharge. Details of this equipment are shown on drawings AX4DB124-2, AX4DB124-3, AX4DB124-4, and AX4DB124-5.

The basic composition of the liquid collected in the waste holdup tank is boric acid and water with some -radioactivity.

A separate drain channel A subsystem is provided for each of the two units. Details are shown on drawings 1X4DB124 and 1X4DB127. Table 11.2.1-1 lists the estimated flows entering the waste holdup tank.

11.2.2.3 Drain Channel B Subsystem Drain channel B is provided to collect and process nonreactor grade liquid wastes. These include:

• Wastes from floor drains.

• Equipment drains containing nonreactor grade water.

" Laundry and hot shower drains.

" Other nonreactor grade sources.

Drain channel B is comprised of three drain subchannels, each associated with one of the following tanks.

A. Laundry and Hot Shower Tank The laundry and hot shower tank is provided to collect and process waste effluents from the plant laundry and personnel decontamination showers and hand sinks.

Laundry and hot shower drains normally need no treatment for removal of radioactivity. This water is transferred to a waste monitor tank through the laundry and hot shower tank filter for eventual discharge. If sample analysis indicates that decontamination is necessary, the water can be directed through the Unit 1 or Unit 2 waste monitor tank demineralizer or the radwaste processing facility for cleanup.

The laundry and hot shower tank and filter are shared by the two units. Details of this portion of the LWPS are shown on drawing 1X4DB126. Table 11.2.1-1 lists estimated flows entering the laundry and hot shower tank.

B. Floor Drain Tank Water may enter the floor drain tank from system leaks inside the containment through the containment sump, from system leaks in the auxiliary building through auxiliary building sumps and the floor drains, and floor drains in the 11.2-6 REV 13 4/06

VEGP-FSAR-1 1 radwaste facilities. Sources of water to the containment sump and auxiliary building sumps and floor drains are the following:

1. Fan cooler leaks.

2. Secondary side steam and feedwater leaks.

3. Primary side process leaks.

4. Decontamination water.

The containment sump or auxiliary building sumps may be directed to the waste holdup tank.

Another source of water to the floor drain tank is the chemical laboratory drains.

Excess nonreactor grade samples that are not chemically contaminated and laboratory equipment rinse water are drained to the floor drain tank.

The contents of the floor drain tank are processed through the radwaste processing facility demineralizers and/or the radwaste processing facility filtration system and then pumped to a waste monitor tank for ultimate discharge.

If the activity in the floor drain tank liquid is such that the discharge limits cannot be met without cleanup, the liquid can be processed by the waste monitor tank demineralizer, the radwaste processing facility demineralizers, or the radwaste processing facility filtration system.

A separate floor drain tank and associated equipment are provided for each of the two units. Details of this portion of the LWPS are shown on drawing 1X4DB126. Table 11.2.1-1 lists the estimated flows entering the floor drain tank.

C. Chemical Drain Tank Laboratory samples which contain reagent chemicals (and possibly tritiated liquid) are discarded through a sample room sink which drains to the chemical drain tank. Chemical drains requiring radwaste processing are sent to the solid waste management system or may be processed through the radwaste processing facility demineralizers and/or the radwaste processing facility filtration system.

The chemical drain tank and associated equipment are shared by Units 1 and 2.

Details of this portion of the LWPS are shown on drawing 1X4DB125. Table 11.2.1-1 lists the estimated flow directed to the chemical drain tank.

Annyliq uids-released-to-the-environment-byt he-L-W PS-a-re-first-directed-to-a-waste-mnriitortank?

fBtef.e releasi i dihgs--a ng-the-contents-of-a-waste-monitor-tankl,_-_asample r~e-l o~g ed ,-a n d,_-I f.te-a---ti~it-lv eli-iti _a ct--'*tbel _is-tak:eWf67an-a rris-ee-ank-~r 0-*-

Ds Tihe releeased-to-the-dischargecan-lThe discharge valve is interlocked with a process radiation monitor-and-lo-sesautomatically when the radioactivity concentration in the liquid discharge exceeds a preset limit. The radiation element is located upstream of the discharge valve at a distance sufficient to close the valve before passing the fluid that activated the detector trip signal. The isolation valve also blocks-flow if sufficient dilution water is not available. The radiation monitor is described in section 11.5. A permanent record of the radioactive releases is provided by a sample analysis of the known volumes of waste effluent released. Liquid waste discharge flow and volume are also recorded.

If the monitor tank contents are not acceptable for discharge, the fluid can beheld for a time to allow activity to decay to acceptable levels, or it can be further processed by the waste monitor 11.2-7 REV 13 4/06

VEGP-FSAR-1 1 tank demineralizer, the radwaste processing facility filtration system, or radwaste processing facility demineralizers.

11.2.2.4 Spent Resin Handling Subsystem This subsystem collects, handles, and processes spent resins from the primary fluid systems prior to their disposal.

Spent resin from the primary system demineralizers is transported to and stored in the spent resin storage tank prior to being drummed. The spent resin sluice portion of the LWPS consists of a spent resin sluice filter, spent resin sluice pump, and the spent resin storage tank. The resin sluice water, after being directed to an ion exchange vessel by the sluice pump, returns to the spent resin storage tank for reuse.

Thus, sluicing of spent resin from primary plant demineralizers is accomplished without generating a large volume of liquid waste.

Reactor makeup water storage tank system pressure may also be used as a motive force for sluicing demineralizers to the spent resin storage tank.

Resin from the SGBPS demineralizers is handled in a similar manner to that described for the primary system demineralizers. The SGBPS resin handling is discussed in subsection 10.4.8.

The primary system resins and the SGBPS resins are segregated during all phases of handling so that no cross-contamination occurs.

Resin slurry from both spent resin storage tanks is sent to the radwaste processing facility by pressurizing the tank with nitrogen.

A separate resin handling subsystem is provided for each of the two units. Details of this portion of the LWPS are shown on drawing 1X4DB125.

11.2.2.5 Liquids From Sources Other Than the Liquid Waste Processing System 11.2.2.5.1 Steam Generator Blowdown Processing System Blowdown from the steam generators of each unit is cooled, filtered, and demineralized.

Normally it is then returned to the condensers for reuse as condensate makeup, but it may be discharged to the environment. The SGBPS is described in subsection 10.4.8.

11.2.2.5.2 Turbine Building Drain System The function of the turbine building drain system is:

A. To collect the floor drains and sampling wastes in the turbine building and other miscellaneous drains.

B. To treat these wastes, if necessary, to meet the requirements of the State of Georgia Environmental Protection Agency (EPA) regulations and Nuclear Regulatory Commission regulations prior to discharge to the Savannah River.

11.2-8 REV 13 4/06

VEGP-FSAR-1 1 All the wastes generated in the turbine building including drains, leakages, and the sampling wastes are collected in the sumps in the turbine building. The sump pump discharge, combining with the auxiliary building clean water sump discharge, auxiliary feedwater pumphouse drain, maintenance building drain, and the treated turbine building drain, normally passes through a radiation monitor before entering into an oil water separator to meet the EPA oil discharge limit. If the radioactivity level of this combined waste stream exceeds the setpoint of the radiation monitor, a signal is sent to stop the flow to the nonradioactive oil water separator. This stream is then sent to one of the turbine building drain tanks before processing.

The amount of waste delivered to the turbine building drain tanks is kept minimal by promptly locating the specific contaminated (radioactive) stream(s) and pumping the remaining (nonradioactive) streams via their normal route. The turbine building drain system and associated components are discussed in detail in subsection 9.3.3.

11.2.2.6 Equipment Description Principal design parameters for the LWPS equipment are given in table 11.2.1-2. All parts or components in contact with borated water are fabricated from or clad with austenitic stainless steel. Pumps are provided With vent and drain connections.

Since this system performs no function related to the safe shutdown of the plant, many components of the system are classified as nonnuclear safety. Component safety classes, seismic design, and principal codes are shown in table 3.2.2-1.

11.2.2.6.1 Pumps Pumps in the LWPS have been standardized wherever possible. Where operation is not critical and surge capacity is available, a single pump has been provided. Spare pumps can be kept onsite in case any pump should fail. Quick replacement is possible because:

" The pumps are flanged, not welded.

• The system has surge capacity.

" Adequate vent, flush, and drain capabilities are provided.

• The pumps are standardized.

Three types of standard pumps are required, as described below.

Canned rotor pumps are used wherever possible to minimize fluid leakage and to minimize the release of entrained radioactive gases in the leaking fluid to the atmosphere.

Canned rotor pumps with similar head-flow characteristics are used for the following applications:

" Spent resin sluice pumps.

" RCDT pumps.

Another canned rotor pump design is used for the following applications:

• Waste evaporator feed pumps.

11.2-9 REV 13 4/06

VEGP-FSAR-1 1

" Waste evaporator condensate tank pumps.

• Chemical drain tank pump.

• Waste monitor tank pumps.

Mechanical seal pumps are also used in some applications because these pumps, have an open impeller, which will not be damaged by large particles in the water. Mechanical seal pumps with similar head-flow characteristics are used for the following applications:

" Floor drain tank pump.

" Laundry and hot shower tank pump.

Globe valves are installed in pump discharge lines where necessary to prevent pump runout.

Pump miniflow lines have locked-in-position globe valves to ensure that the minimum pump flow requirements are met.

A. RCDT Pump The design basis for this pump is that, in its function of RCS drain, the coolant level reaches the midplane of the reactor vessel nozzles within an 8-h period.

Two pumps are furnished because of the relative inaccessibility of the containment during plant operation. Both pumps are operated to meet the draining time requirement. One pump provides sufficient flow for normal operation of the RCDT portion of the LWPS. The liquid is sent to the recycle holdup tanks.

B. Waste Evaporator Feed Pump This pump supplies feed to the radwaste processing facility for processing from the waste holdup tank, and it can be used to transfer waste holdup tank contents to the floor drain tank, if desired.

C. Waste Evaporator Condensate Pump The waste evaporator condensate tank pump is used to transfer the contents of the waste evaporator condensate tank.

D. Chemical Drain Tank Pump This pump may be used to transfer the contents of the chemical drain tank.

E. Spent Resin Sluice Pump One pump is provided to sluice resins from primary side demineralizers to the spent resin storage tank. Its delivery flow is based on the velocity required to sluice resin in a 3-in. pipe.

F. Laundry and Hot Shower Tank Pump This pump is used to transfer the water from the laundry and hot shower tank to a waste monitor tank.

G. Floor Drain Tank Pump This pump is used to transfer water from the floor drain tank to the radwaste processing facility. From the radwaste processing facility, processed waste is transferred to the waste monitor tank.

11.2-10 REV 13 4/06

VEGP-FSAR-1 1 H. Waste Monitor Tank Pumps Two pumps are provided for each unit. One pump is used for each monitor tank to discharge water from the LWPS or for recycling if further processing is required.

The pump may also be used for circulating the water in the waste monitor tank to obtain uniform tank contents, and therefore a representative sample, before discharge. These pumps can be throttled to achieve the desired discharge rate.

Auxiliary Waste Monitor Tank Pumps Two pumps are provided. They are installed in Unit 2 but serve both units. One pump is used for each auxiliary waste monitor tank to discharge water from LWPS or for recycling if further processing is required. A mixer may be used for circulating the water in the auxiliary waste monitor tank to obtain uniform tank contents, thereby assuring a representative sample is acquired prior to discharge of the tank contents. The pumps can be throttled to achieve the desired discharge rate.

11.2.2.6.2 Tanks A. Reactor Coolant Drain Tank One tank is provided for each unit. The purpose of the RCDT is to collect leakoff-type drains inside the containment at a central collection point for further disposition through a single penetration via the RCDT pumps. The tank provides surge volume and net positive suction head (NPSH) to the pumps.

Only water which can be directed to the boron recycle holdup tanks enters the RCDT. The water is compatible with reactor coolant and does not contain dissolved air during normal plant operation, by engineering design.

A constant level is maintained in the tank to minimize the amount of gas sent to the GWPS and also to minimize the amount of hydrogen cover gas required.

The level is maintained by one continuously running pump and by a control valve in the discharge line. This valve operates on a signal from a level controller to limit the flow out of the system. The remainder of the flow is recirculated to the tank.

Continuous flow is maintained through the heat exchanger in order to prevent loss of pump NPSH resulting from a sudden inflow of hot liquid into the RCDT.

B. Waste Holdup Tank One atmospheric pressure tank is provided for each unit to collect:

1. Equipment drains.

2. Valve and pump seal leakoffs (outside the containment).

3. Boron recycle holdup tank overflows.

4. Other water from tritiated, aerated sources.

The tank size is adequate to accommodate 11 days of expected influent during normal operation.

C. Waste Evaporator Condensate Tank 11.2-11 REV 13 4/06

VEGP-FSAR-1 1 One tank with a diaphragm to exclude air is provided for each unit to collect water from processing systems.

D. Chemical Drain Tank One tank is provided to collect chemically contaminated, tritiated water from the laboratories. This tank is shared by the two units and has sufficient capacity to accept a month's laboratory waste during normal operation of both units.

E. Spent Resin Storage Tank The purpose of the spent resin storage tank is to-provide a collection point for spent resin and to allow for decay of short-lived radionuclides before disposal.

The tank also serves as a head tank for the spent resin sluice pump.

One vertical, cylindrical tank with sufficient capacity to handle the spent resin storage needs is provided. A vertical, cylindrical tank is used because the symmetrical bottom facilitates the removal of resin. The tank is designed so that sufficient pressure can be applied in the gas space of the tank to move the resin slurry to the radwaste processing facility.

The spent resin storage tank and associated equipment, which can contain radioactive material, are shielded to limit the dose to personnel.

The level indicating system in the spent resin storage tank shows only total level and not the amount of resin and water separately. However, since the resin volumes flushed from demineralizers and the resin volumes transferred to the radwaste processing facility are known, the resin level in the tank is also known.

F. Laundry and Hot Shower Tank One atmospheric pressure tank is provided to collect laundry and liot shower drains for the two units. The tank size is sufficient to furnish a 10-day surge capacity for the two units during normal operation of both units and a 2-day surge capacity during refueling of a single unit.

G. Floor Drain Tank One atmospheric pressure tank is used to collect floor drains from the controlled areas of each unit's primary system. The tank provides sufficient surge capacity for the floor drains within the collection area and, in connection with the waste holdup tank, provides surge capacity for abnormal primary system leaks. The tank size is adequate to accommodate 3.5 days of expected influent during normal operation or 1.8 days of expected influent during shutdown operation.

H. Waste Monitor Tanks Two atmospheric pressure waste monitor tanks are provided for each unit to monitor liquid discharged from the plant site. Each tank is sized to hold a volume large enough that sampling requirements are minimized, thereby minimizing laboratory effluent.

Two additional atmospheric pressure tanks have been provided to augment the plant capacity to handle large surges of water or to accommodate conditions in which release of the processed water is not feasible. These 20,000 gallon tanks are installed on level D of the Unit 2 auxiliary building. They are shared by both units, with one tank normally aligned to each unit.

11.2-12 REV 13 4/06

VEGP-FSAR-1 1 11.2.2.6.3 Reactor Coolant Drain Tank Heat Exchanger This heat exchanger is located in the discharge line of the RCDT pumps and is in constant service as part of the RCDT recirculation path. Continuous auxiliary component cooling water flow is maintained to the heat exchanger to accommodate, without operator action, sudden flow of hot liquid to the RCDT. The heat exchanger can also be used to cool the contents of the pressurizer relief tank in the RCS.

The heat exchanger is sized for several modes of operation:

A. It can maintainthe RCDT liquid below 170 0 F, assuming a 10-gal/min input of 600°F reactor coolant.

B. It can cool the contents of the pressurizer relief tank from 200OF to 120OF in less than 8 h.

C. It can maintain the contents of the RCDT at less than 170 0 F, assuming a 25-gal/min input from the excess letdown heat exchanger (chemical and volume control system).

One RCDT heat exchanger is provided per unit.

11.2.2.6.4 Demineralizers

.As part of a program of continuous pressurized water reactor operating plant followup, Westinghouse has obtained operational data on demineralizer decontamination factors for selected isotopes. The measured range of decontamination factors for these isotopes is given in table 11.2.2-1.

These values were observed across mixed bed demineralizers containing cation resin in the lithium-7form and anion resin in the borated form. The minimum values in table 11.2.2-1 were generally observed just before resin flushing and recharging; during the operating life of the demineralizer, decontamination factors were consistently closer to the maximum values.

Although specific operating decontamination factors have not yet been measured for other isotopes, their behavior in a mixed bed demineralizer may be inferred from this data.

The process decontamination factor used for the demineralizers in the analysis of system performance is taken from reference 1, subsection 11.2.1. These decontamination factors are given 'in table 11.2.2-1.

A. Waste Monitor Tank Demineralizer One mixed bed demineralizer is provided upstream of the waste monitor tanks to remove, if desired, trace ionic contaminants. The laundry and hot shower tank contents can also be processed through the demineralizer if such processing is necessary.

B. Radwaste Processing Facility Demineralizers The radwaste processing facility houses a series of demineralizers which can be operated in various configurations. The type and loadings of resins or other filter media utilized in these vessels can be changed as necessary to optimize the performance of the system.

11.2-13 REV 13 4/06

VEGP-FSAR-1 1 11.2.2.6.5 Filters The following filters are provided in the LWPS:

0 Laundry and hot shower tank filter.

• Floor drain tank filter.

• Spent resin sluice filter.

e Waste evaporator condensate filter.

• Waste monitor tank filter.

The laundry and hot shower tank filter element is normally removed since installation of the filtration system in the radwaste processing facility.

11.2.2.6.6 Strainers Basket-type strainers of mesh construction are provided to prevent clogging of filters and lines downstream because of large particles being sluiced through the lines during liquid transfer operations.

The following strainers are provided in the LWPS:

0 Laundry and hot shower tank strainer.

0 Floor drain tank strainer. (This strainer may be removed to enhance system operability.)

11.2.2.7 Instrumentation Design The system instrumentation is shown on the LWPS drawings 1X4DB124, 1X4DB125, 1X4DB126, 1X4DB127, AX4DB124-2, AX4DB124-3, and AX4DB124-4.

Instrumentation readout is located mainly on the waste processing system panel in the auxiliary building. Some instruments are read at the equipment location.

All alarms are shown separately on the waste processing system panel and are further relayed to one common waste processing system annunciator on the main control board in the control room. The waste processing holdup control panel does not relay signals to the control room annunciator.

All pumps are protected against loss of suction pressure by a control setpoint on the level instrumentation for the respective vessels feeding the pumps. In addition, the RCDT pumps and the spent resin sluice pump are interlocked with flowrate instrumentation to stop the pumps when the delivery flows reach minimum setpoints. The RCDT pumps have a keyswitch allowing the bypass of the flowrate instrumentation control logic. During certain intermittent outage flowpaths, flowrates less than those recommended by the pump vendor may be established.

Administrative controls require continuous monitoring of pump performance during such flowpaths to ensure the pumps' availability.

11.2-14 REV 13 4/06

VEGP-FSAR-1 1 Pressure indicators are provided to give local indication of pressure drops across demineralizers, filters, and strainers.

All releases to the environment are monitored for radioactivity. This instrumentation is described in section 11.5.

Each tank is provided with level indication instrumentation that actuates an alarm on high liquid level in thejtank, thus warning of potential tank overflow.

11.2.2.8 Operating Procedures The LWPS is manually operated except for some functions of the RCDT circuit. The system.

includes adequate control equipment to protect components and adequate instrumentation and alarm functions to provide operator information to ensure proper system operation.

Operation of the LWPS is essentially the same during all phases of normal and defined off-normal reactor plant operation; the only differences are in the load on the system. The term "normal operation," as used here, means all phases of plant operation except operation under emergency or accident conditions. The LWPS is not regarded as an engineered safety features system.

11.2.2.8.1 Reactor Coolant Drain Tank Subsystem Operation A. Reactor Coolant Drain Tank Recirculation Reactor coolant is continuously circulated through the RCDT heat exchanger to maintain _<170 0 F in the event of a hot reactor coolant leak. Level is maintained by a control valve which automatically opens a path from the recirculation line to the recycle holdup tanks. Normal operation of this mode is automatic and requires no operator action. The system can be put into the manual mode, if desired.

Leakage into the RCDT can be estimated by putting the system in the manual mode, stopping the pump, and monitoring the level change. A venting system is provided to prevent wide pressure variations in the RCDT. A hydrogen blanket is automatically maintained between 2 and 6 psig. Hydrogen is supplied from bottles which must be replaced when the pressure drops to -100 psig.

During all other operations, the recirculation mode is stopped and the RCDT is isolated.

B. Pressurizer Relief Tank Cooling The pressurizer relief tank may be cooled by a feed- and-bleed method, by spraying cold makeup water and pumping the water to the recycle holdup tanks with an RCDT pump through the RCDT heat exchanger. This is a rapid cooldown and can be used even if the heat exchanger is out of service.

However, to minimize the addition of water to the system when a rapid cooldown is not necessary, the pressurizer relief tank may be cooled from 200OF to 120OF in less than 8 h by using the RCDT heat exchanger and one pump in a recirculation mode without adding makeup water.

C. Loop Draining 11.2-15 REV 13 4/06

VEGP-FSAR-1 1 Four RCS loops may'be drained simultaneously to the midpoint of the reactor vessel nozzles in less than 8 h when both RCDT pumps are running. The loops are vented to 100 psig, then a spectacle flange is positioned to the pumps' suction. The water may be sent to the recycle holdup tanks, refueling water storage tank, waste holdup tank, or the spent fuel pool. Since the RCDT heat exchanger is not needed for cooling, it may be bypassed or used in parallel with the bypass.

D. Refueling Canal Draining and Cleanup Refueling canal water is transferred, using the RCDT pumps, to the refueling water storage tank (draining), to the canal via the spent fuel pool cooling system (cleanup), or to the waste holdup tank (disposal).

Since the RCDT heat exchanger is not needed for cooling, it may be bypassed or used in parallel with the bypass.

E. Accumulator Draining This mode is available for accumulator maintenance. After the accumulator is vented to 90 psig, the spool piece is connected to the RCDT pump suction for transfer of accumulator water to the reactor water storage tank or recycle holdup tank.

F. Excess Letdown Header During normal plant heatup operations, excess letdown to the RCDT will permit faster heatup rate. Excess letdown flow is directed from the RCDT to the recycle holdup tanks.

11.2.2.8.2 Drain Channel A Subsystem Operation Water is accumulated in the waste holdup tank until sufficient quantity exists to warrant starting the processing systems for a batch process.

If it is not desired to recycle the water in the waste holdup tank and analysis indicates that decontamination is not necessary, the water may be sent to the floor drain tank for eventual discharge.

TLhe-w~aste-hiold u p-ta nk-conte nts-ma~y.be-processe~d-b.y-th e-ad~waste-p rocessing-facilitT}-filtr-tib n system-and/or-the-a ig-facility-deniiff-e-alizerst 11.2.2.8.3 Drain Channel B Subsystem Operation Drain channel B of the LWPS consists of the laundry and hot shower system, the floor drain tank system, and the chemical drain tank system.

Laundry and hot shower water enters the laundry and hot shower tank for holdup; it is sampled, filtered, and transferred to the monitor tank for discharge, or processed through the radwaste processing facility filtration system or the radwaste processing facility demineralizer. If demineralization is required, the resin must be replaced with clean resin thereafter.

The floor drain tank contents are recirculated, and then samples are taken and analyzed. If the floor drain tank is overloaded or the water is recyclable, the water can be transferred to the waste holdup tank.

11.2-16 REV 13 4/06

VEGP-FSAR-1 1 Water leaving this system to the discharge canal is monitored for radiation. This radiation monitor is described in section 11.5. If the radiation monitor closes the discharge valve, it must be cleared before the valve can be reopened. The monitor element can be cleared by flushing it with demineralized water from the temporary connection back to the waste monitor tank.

During refueling, the load on this portion of the LWPS is increased, but there is no change in operation.

Spent samples with high chemical concentrations are held up in the chemical drain tank, then sampled. The contents are drained to the auxiliary building sumps or the radioactive drain sumps.

11.2.2.8.4 Spent Resin Handling Subsystem A. Resin Fluffing The demineralizer is valved out of service, and the flow path is aligned from the spent resin sluice pump (or the reactor makeup water system header) through the process line of the demineralizer, through theJohnson screen at the top of the demineralizer, and back to the spent resin storage tank. The resin bed is backflushed for about 10 min to loosen it for sluicing. This operation may also be used to recover pressure drop caused by bed fouling by backwashing particulates from the top layer of the resin into the spent resin storage tank.

Such a recovery is useful when the resin is not ionically depleted.

B. Resin Sluicing The sluice pump is shut off after fluffing. The valves in the backflush circuit are closed, the sluice line to the bed screen is opened, and the sluice pump is started. The resin flows to the spent resin storage tank, initially at a slow rate; it continues for about 10 min until sluicing is completed. Finally, the pump is stopped, and the sluice inlet and outlet valves are closed. If the pump suction line screen in the tank becomes resin plugged at any time, it can be cleared with a blast of nitrogen.

C. Resin Fill After sluicing is completed, fresh resin must be added. The path to the drain header from the demineralizer is opened to allow overflow. The resin fill line is opened and resin added. After fresh resin is added, the fill line valve is closed and the flow path is realigned for normal demineralizer operation.

D. Resin Disposal The resin in the spent resin storage tank is loosened before disposal by sending pressurized nitrogen or sluice water through the six sparging nozzles in the tank.

The valves in the resin transfer line are opened to direct the spent resin to the radwaste processing facility.

The tank is then pressurized with nitrogen to force the resin up through the resin transfer line to the disposal area. A single nozzle in the spent resin storage tank is provided to allow local fluidization with sluice water at the opening of the discharge pipe. During resin transfer, this nozzle is used to ease the flow of the resin slurry. After resin transfer is complete, the tank is vented to the plant vent and returned to atmospheric pressure. The resin transfer line is then backflushed to the spent resin storage tank to clear it of resin.

11.2-17 REV 13 4/06

VEGP-FSAR-1 1 Since a certain amount of resin remains in the tank after a disposal operation, it may hinder the backflush operation. Therefore, the fluidizing nozzle is again used to facilitate the backwash operation.

11.2.3 RADIOACTIVE RELEASES 11.2.3.1 Criteria for Discharge, Recycle, or Further Treatment of Liquid Waste Processed liquids are recycled for reuse within the plant whenever possible, provided that the following criteria are satisfied:

0 The plant water inventory requires makeup.

0 The water to be reused satisfies system water quality requirements.

• Tritium buildup is less thanplant operating limits.

Processed liquids are discharged under the following conditions:

" The processed water does not satisfy plant operating requirements for water quality and tritium buildup.

" The effluent concentrations are within the limits specified by the Offsite Dose Calculation Manual.

• The discharge does not cause the limits of 10 CFR 50, Appendix I, to be exceeded.

Processed liquids are recycled within their respective treatment systems for additional processing when system water quality requirements are not satisfied and reuse within the plant is desirable, or when discharge of the processed liquid is planned but the discharge would result in exceeding limits in the Offsite Dose Calculation Manual.

11.2.3.2 Estimated Releases The equipment utilized during liquid waste processing is at the discretion of the operator; therefore, the calculated releases conservatively do not address all possible treatment processes but only the expected process. Liquid releases from VEGP are calculated using the PWR-GALE computer code~ 1 ) and parameters listed in'table 11.1-8, which are discussed in more detail below. Releases calculated assuming operation with expected levels of fuel cladding defects of 0.12 percent are presented in table 11.2.3-1. Primary and secondary coolant activity levels are given in section 11.1 for the realistic case. In agreement with reference 1, the-total releases include an adjustment factor of 0.15 Ci/year, using the same isotopic distribution as the calculated release, to account for anticipated operational occurrences.

The tables list the calculated annual release from each of the process paths discussed below as well as, the total annual release. A comparison of annual average effluent concentrations with Appendix B, Table II, column 2 values of 10 CFR 20.1 -20.601 is provided in table 11.2.3-2 for operation with expected fuel leakage.

11.2-18 REV 13 4/06

VEGP-FSAR-1 1 The releases are calculated for one unit, assuming that both units are operating. This is done to reflect the impact of the second unit's operation on the operation of systems and components shared between the two units. To obtain the combined releases of the two units, simply double the values listed in table 11.2.3-1.

A survey has been performed of liquid discharges from different Westinghouse pressurized water reactor plants, with results presented in table 11.2.3-3. The data includes radionuclides released on an unidentified basis and are all within the permissible concentration for release of liquid containing an unidentified radionuclide mixture. The data in table 11.2.3-4 clearly indicate that actual releases are highly dependent upon the actual operation of the plant and can vary significantly from year to year for a given plant as well as from plant to plant.

11.2.3.2.1 Boron Recycle System (BRS)

Primary coolant is withdrawn from the reactor coolant system (RCS) and processed through the chemical and volume control system (CVCS). A side stream of 1700 gal/day of the letdown stream is assumed to be diverted to the BRS as shim bleed. The shim bleed is combined with a conservatively estimated 300 gal/day of other reactor grade wastes that are collected by the reactor coolant drain tank (equipment drain wastes). Since the BRS is shared by both units, the total process flow is 4000 gal/day. The equipment drains and shim bleed flows have an activity level equivalent to primary coolant activity (PCA).

The combined shim bleed and equipment drain wastes streams are routed to one of the recycle holdup tanks. The contents of the recycle holdup tank are then processed through the radwaste processing facility filtration system and the radwaste processing facility demineralizers. The water is either pumped to the reactor makeup water storage tank for reuse in the plant or to a waste monitor tank for monitoring and discharge. The BRS has sufficient capacity to allow total reuse of the combined shim bleed and equipment drain wastes.

Radioactive decay during collection in the recycle holdup tanks is calculated using a collection time of 22.4 days. This value is based upon filling one of the recycle holdup tanks to 80 percent of capacity using the combined shim bleedand reactor coolant drain tank flows. Radioactive decay during processing and discharge is calculated using a process time of 0.31 days. This value is based upon processing the combined shim bleed and reactor coolant drain tank flows at the design flowrate of the recycle evaporator.

The decontamination factors used in calculating radionuclide removal for iodine, cesium, rubidium, and other nuclides, are determined by applying the methodology and parameters of reference 1 to the processing capabilities of the BRS and CVCS as shown in figure 11.2.3-1.

No credit is taken for the recycle evaporation condensate demineralizer since its main function is to remove boron carryover.

11.2.3.2.2 Liquid Waste Processing System (LWPS)

A. Clean Wastes (Drain Channel A - Miscellaneous Wastes)

Clean wastes are collected in the waste holdup tank for processing. Based on sample analysis, the water in the monitor tank would either be discharged or processed further by recirculation through the waste monitor tank demineralizer until sample analysis indicated that it was acceptable for discharge. The flow to the waste holdup tank is 713 gal/day at 0.051 times PCA. The LWPS has sufficient capacity to allow total reuse of the processed clean wastes. However, 11.2-19 REV 13 4/06

VEGP-FSAR-1.1 in the release calculations a discharge fraction of 1.0 is used as specified by reference 1.

Radioactive decay during collection in the waste holdup tank is calculated using a collection time of 5.6 days. This value is based upon filling the waste holdup tank to 40 percent of capacity. Radioactive decay during processing and discharge is calculated using a process time of 0.028 days. This value is based upon processing 40 percent of the waste holdup tank capacity at the design flowrate of the waste evaporator (no longer in system) and the time required to pump this volume of water out of the monitor tank at the maximum pumping rate.

The decontamination factors used in calculating radionuclide removal are based upon demineralization as shown in figure 11.2.3-1.

B. Dirty Wastes (Drain Channel B - Miscellaneous Wastes)

Dirty wastes are collected in the floor drain tank. A sample is analyzed to determine whether the water can be discharged without processing. If cleanup is required,'the liquid is processed by the radwaste processing facility filtration system and/or the radwaste processing facility demineralizer and the effluent directed to a waste monitor tank. Based on sample analysis, the monitor tank contents are either discharged or processed further by recirculation through the -

monitor tank demineralizer until sample analysis indicates that the water is acceptable for discharge. The flow to the floor drain tank is 2047 gal/day at 0.02 times PCA. Since all of the di'rty wastes are normally discharged, a discharge fraction of 1.0 is used in the release calculations.

Radioactive decay during collection in the floor drain tank is calculated using a collection time of 1.43 days. This value is based upon filling the floor drain tank to 40 percent of capacity. Radioactive decay during processing is calculated using process time of 0.03 days. This value is based upon processing 40 percent of the floor drain tank capacity at the design flowrate of the waste evaporator (no longer in service) and the time required to pump this volume of water out of the monitor tank at the maximum pumping rate.

The decontamination factors used in calculating radionuclide removal are based upon the decontamination factors given in reference 1 for demineralizers as shown in figure 11.2.3-1.

C. Detergent Wastes (Laundry and Hot Shower Tank)

Detergent wastes are normally released without treatment. The releases through this path are assumed to be the same as listed in reference 1, table 2-20.

11.2.3.2.3 Steam Generator Blowdown Processing System (SGBPS)

Blowdown from the steam generators is normally processed by the two generator blowdown demineralizers (in series) and recycled back to the main condenser. If discharge of blowdown is desired, the demineralizers can be bypassed. A valve in the discharge line automatically stops discharge on a high radioactivity signal. In the event of a primary to secondary side leak, the demineralizers would be in use. For the release calculation, a 100 lb/day primary to secondary side leakage is assumed. Also, a design basis total blowdown rate of 180,096 lb/h is assumed with 100 percent of the flow being discharged.

11.2-20 REV 13 4/06

VEGP-FSAR-1 1 No credit is taken for radioactive decay of the isotopes in the blowdown stream since the SGBPS design utilizes a through-flow process with no significant decay.

The decontamination factors used in calculating radionuclide removal are shown in figure 11.2.3-1. Thesevalues are based upon the decontamination factors given in reference 1 for two steam generator blowdown mixed bed demineralizers (in series).

11.2.3.2.4 Turbine Building Floor Drains The processing of the low level radioactive water in the turbine building dirty drain tank is manually initiated by the operator based on the predetermined water level in the tank. This processing system, located in the auxiliary building, consists of an oil water separator, an activated charcoal filter, two demineralizers in series, and a discharge filter. The treated water is returned to the clean drain tank in the turbine building. After monitoring it is combined with other waste streams for disposal.

11.2.3.3 Release Points The natural draft cooling towers are not radioactive release points. However, the following information regarding location is offered.

Blowdown from both cooling towers and flow from the waste water retention basin is collected in a common blowdown sump and is discharged to the river via the waste water effluent pipe. The radioactive release line discharges into the waste water effluent pipe at a point downstream of the blowdown sump and is then discharged into the Savannah River downstream of the river intake structure.

11.2.3.4 Dilution Factors At 100-percent capacity factor and design basis conditions for cooling tower operation, blowdown from the cooling tower to the blowdown sump is approximately 5000 gal/min per unit.

Furthermore, 10,000gal/min per unit river water can be provided to the sump through a dilution flow transfer line takeoff on the river water makeup line to the natural draft cooling towers.

Thus, a total of 15,000 gal/min per unit dilution flow is available during the liquid radwaste discharge operation. Minimum dilution flow is as specified in the release permit which is prepared in accordance with the ODCM.

There will be some additional dilution following discharge due to the effect of the near field mixing zone in the Savannah River. For 15,000 gal/min (33.4 ft3/s) effluent discharge into the Savannah River with 5800 ft3/s minimum flow, the VEGP thermal plume analysis utilizes a dilution factor of 10 for summer discharge conditions and 20 for winter conditions.(2)

For conservatism, the lower dilution factor of 10 was chosen for the LADTAP II analysis.

11.2.3.5 Estimated Doses Release of radioactive effluents to the Savannah River during normal plant operation and anticipated operational occurrences will result in a minimal radiological exposure to individuals as noted in table 11.2.3-4. The estimated annual average doses to the maximum exposed individual were calculated using the LADTAP II computer code.(3) 11.2-21 REV 13 4/06

VEGP-FSAR-1 1 The location of maximum exposure is in that area of the river allowing for initial near field dilution of the discharge with essentially zero travel time. Since crop irrigation from the Savannah River has not been observed in the vicinity of the plant site, this pathway has not been considered in the evaluation of doses. The anticipated dose due to drinking water could be considered insignificant because the nearest location of potable use of river water is in Beaufort County, South Carolina, approximately 103 river miles downstream of the plant site.

However, for conservatism, this pathway was evaluated assuming the maximum exposed individual obtains drinking water in the immediate area of the discharge plume. Shoreline use in the vicinity of the plant is very limited, with essentially no fishing from the bank, swimming, or sunbathing, and, consequently, is expected to be an insignificant pathway in comparison with the pathway of aquatic foods. Nevertheless, for purposes of conservatism, this pathway has been included in the evaluation of doses for the maximum exposed individual.

Furthermore, a single dilution factor (10.0) for the initial near field dilution of the discharge with a travel time of zero was used for the pathway's consideration. In lieu of site specific data, the pathway usage factors and shorewidth factor (0.2) outlined in Regulatory Guide 1.109, Revision 1, October 1977, were utilized in this evaluation. As noted in table 11.2.3-4, based on the criteria as outlined above, the maximum exposed individual annual doses from the discharge of radioactive materials in liquid effluent from each of the VEGP units meet the guideline of Appendix 1,10 CFR 50, and Docket RM-50-2, Annex to Appendix I.

11.2.3.6 References

1. U.S. Nuclear RegulatoryCommission, "Calculation of Releases from Pressurized Water Reactors," PWR-GALE Computer Code, NUREG-0017, April 1976.

2. Georgia Power Company, "Waste Water Effluenit Discharge Structure Thermal Plume Analysis," Vogtle Electric Generating Plant Units 1 and 2, Revised March 1981.

3. U.S. Nuclear Regulatory Commission, "Calculation of Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents," LADTAP II Computer Code, NUREG/CR-1276, March 1980.

11.2-22 REV 13 4/06

VEGP-FSAR-11 11.3.2 SYSTEM DESCRIPTION This section describes the design, operating features, and performance of the gaseous waste processing system (GWPS) and other plant gaseous waste management systems with respect to the collection and control of radioactive gases. Detailed.

descriptions of the plant ventilation systems and condenser vacuum system are presented in sections 9.4 and 10.4, respectively.

The GWPS is provided with two main process loops. Each processes gaseous wastes from one of the two plant units.

Interconnections are provided to allow either process loop to process waste gas from either or both units.

All equipment in the GWPS is controlled from the waste processing panel. The GWPS consists mainly of two closed loops comprised of a waste gas compressor, a catalytic hydrogen recombiner, and seven waste gas decay tanks (GDTs) to accumulate the fission product gases. All pipes containing radioactive gases are shielded as necessary, and no piping is run through normally occupied areas.

Each main process loop also includes a GDT drain pump, six gas traps, and a waste gas drain filter. All of the equipment is located in the auxiliary building.

The piping and instrumentation diagram for the system is shown in drawings 1X4DB128 and 1X4DB129. This diagram indicates safety classes for all components and piping.

The GWPS reduces the fission gas concentration in the reactor coolant system (RCS), which in turn reduces the escape of fission gases from the RCS during maintenance or through equipment leakage.

Tprimar-yvsour ce of radioac.ti-ve---gas-to-_Dh- GWPS-i-s-t-he-volume t-o l--t-ak--(*-T-)-pu-rge/. Smaller quantities-of-7ýdT*diothfive gas are received-via the vent connections from the reactor coolant drain tank (RCDT), the pressurizer relief tank, and the recycle holdup tanks.

Although the GWPS functions to contain radioactive gases, at no time do the radioactive gases constitute more than a small fraction of the gases stored in the GDTs.

REV 5 9/95 11.3.2-1 REV 4 4/94

VEGP-FSAR-11 Since hydrogen is continuously removed in the hydrogen recombiner, this gas does not build up in the GWPS. The largest contributor to the nonradioactive gas accumulation is helium generated by a B10 (n,x)Li 7 reaction in the reactor core. The second largest contributors are the impurities in the bulk hydrogen and oxygen supplies.

The expected accumulation rate is 575 sf 3 /year per unit (1150 sf 3 /year total), assuming the following:

• Two-unit operation.

• A 0.7-sf 3 /min hydrogen purge for the VCT of each unit.

• An 80-percent plant load factor for each unit.

• 99.95-percent pure hydrogen.

• 99.5-percent pure oxygen.

At this rate of accumulation and assuming zero leakage from the GWPS, the 14 GDTs have sufficient combined capacity to hold all the gaseous wastes produced during 4 years of plant operations without any releases to the environment. This assumes that the waste gas holdup tanks are operated with an initial charge of 5 psig of nitrogen and the pressure in the tanks is allowed to accumulate to 100 psig.

Operation of the system is such that fission gases from one unit are distributed throughout seven normal operation GDTs.

Separation of the gaseous inventory into several tanks ensures that the allowable site boundary dose will not be exceeded in the event any one of the .GDTs ruptures. Radiological consequences of such a postulated rupture are discussed in chapter 15.

The GWPS also provides sufficient capacity to hold indefinitely the gases generated during reactor shutdown. Nitrogen gas from previous shutdowns is contained in one of the shutdown GDTs.

This is used to strip hydrogen from the RCS during subsequent shutdowns. The second shutdown tank is normally at low pressure and is used to accept relief valve discharges from the normal operation GDTs, the hydrogen recombiners, and the waste gas compressors.

Table 11.3.2-1, based on the RCS activities given in table 11.1-2, shows the maximum fission product inventory in the 11.3.2-2 REV 4 4/94

VEGP-FSAR-11 GWPS over the 40-year plant life. Table 11.3.2-2, based on the RCS activities given in table 11.1-7, shows the expected fission product inventory in the GWPS over the 40-year life assuming no releases from the system.

Figures 11.3-.2-1 and 11.3.2-2 are based on the RCS activities given inr tables 11.1-2 and 11.1-7, respectively; the figures show that the quantity of fission gas activity accumulated after 40 continuous years of operation is about twice the activity accumulated after 30 days of operation. Most of the accumulated activity arises from short-lived isotopes reaching equilibrium in 1 month or less.

The difference between the 30-day and 40-year accumulations is predominantly krypton-85. This accumulation of krypton-85 is not a hazard to the plant operator because:

A. Krypton-85 is principally a beta emitter, for which the tanks themselves provide adequate shielding.

B. The activity of the system's inventory is distributed among seven normal operation GDTs, minimizing inventory in any single tank.

The removal of fission gas from the reactor coolant by the GWPS during normal operation reduces the plant activity levels caused by a leakage of reactor coolant. Operation of the GWPS allows the collection of virtually all the krypton-85 released to the reactor coolant and can reduce the fission product gas inventory in the RCS, as shown in table 11.3.2-3. Table 11.3.2-3 is based on the RCS activities given in table 11.1-2. Provisions are made to collect any gases from the RCDT and gases from the recycle holdup tanks.

Process flow diagrams are shown in figures 11.3.2-3 and 11.3.2-4. Table 11.3.2-4 gives process parameters for key locations in the GWPS for the normal operating mode with the normal operation GDTs at low pressure (less than 25 psig). This operating mode is used early in plant life and is shown in figure 11.3.2-3. Table I1.3.2-6 gives process parameters for key locations in the system for the normal operating mode at the end of plant life, when the waste GDTs are at high pressure.

This operating mode, shown in figure 11.3.2-4, is used from the time the normal operation GDT pressure reaches 25 psig until the end of plant life.

Table 11.3.2-5 gives the process parameters for key locations in the GWPS based on a 90-day holdup of the waste gases.

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VEGP-FSAR-11 11.3.2.1 Component Design The gaseous waste processing equipment design parameters are given in table 11.3.2-7. Since the GWPS performs no function related to the safe shutdown of the plant, some components are classified as nonnuclear safety. Component safety classes and the corresponding code and code class are shown in section 3.2.

11.3.2.1.1 Waste Gas Compressor Packages Two waste gas compressor packages are provided to circulate gases around each GWPS system loop. One is normally in use and the other on a standby basis.

The compressor packages are water-sealed centrifugal displacement machines which are skid mounted in a self-contained package. The waste gas compressor packages are primarily constructed of carbon steel. Mechanical seals are provided to minimize seal water leakage.

11.3.2.1.2 Catalytic Hydrogen Recombiner Packages Three catalytic hydrogen recombiners are provided for the two units. One recombiner per. unit is used in each main process loop to remove hydrogen from the hydrogen-nitrogen fission gas mixtures by oxidation to water vapor, which is removed by condensation. The third recombiner is available on a standby basis. The units are self-contained and are designed for continuous operation.

11.3.2.1.3 Waste Gas Decay Tanks The tanks are vertical cylindrical type constructed of carbon steel. There are a total of 16 waste decay tanks. Seven are used by each unit during-normal operation; the remaining two are shared between the two units and are used for shutdown and startup.

11.3.2.1.4 Gas Decay Tank Drain Pump The waste GDTs may contain water from condensation from the process gas or from maintenance operations. This pump is used to drain water from the waste GDTs when there is insufficient pressure in the GWPS to transfer the fluid. Two canned motor pumps are provided, one for each set of seven normal operation GDTs.

11.3.2-4

VEGP-FSAR-11 11.3.2.1.5 Waste Gas Drain Filter Two waste gas drain filters are provided, one to filter the drain water from each of the two process loops.

11.3.2.1.6 Waste Gas Traps The gas traps serve to prevent undissolved gases from leaving the GWPS via the liquid drains. For each of the two process loops there are four gas traps - one in the compressors drain line, one in the recombiner drain line, and two mounted in the waste GDT drain line. There are also gas traps on each low point of the gaseous portion of the system to avoid condensate accumulation in the piping that may block the flow path.

11.3.2.1.7 Valves and Piping Each valve in the hydrogen recombiner packages is designed to meet the temperature, pressure, and code requirements for the specific application in which it is used. The recombiner circuits contain manual valves provided with a metal diaphragm to prevent stem leakage and control valves provided with gaseous leakoffs returned to the GWPS. Other parts of the GWPS use elastomer diaphragm valves and control valves with bellows seals. Relief valves have soft seats and operate at pressures which are normally less than two-thirds of the relief valve set pressure. The relief valves of the major components discharge to one of the shutdown GDTs. This allows the discharge to be monitored before being released. It also provides a means of containing and detecting seal leakage across the relief valves.

All piping from the waste GDTs, up to and including the isolation valves, is designed to Seismic Category 1 requirements to preclude any accidental release of gas to the environment.

11.3.2.2 Instrumentation and Control Design The GWPS instrumentation is shown on the piping and instrumentation diagram, drawings 1X4DB128 and 1X4DB129.

The instrumentation readout is located mainly on the waste processing system (WPS) panel, while some instruments are read locally.

All alarms are shown separately on the WPS panel and further relayed to one common WPS annunciator on the main control board.

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VEGP-FSAR-11 Where suitable, instrument lines are provided with diaphragm seals to prevent fission gas leakage through the instrument.

11.3.2.2.1 Waste Gas Compressor Package Instrumentation and Control Figure 11.3.2-5 shows the location of the instruments on the waste gas compressor package.

The compressors are interlocked with the seal, water inventory in the moisture separators; they trip off on either high or low moisture separator level.

During normal operation the proper seal water inventory is maintained automatically.

11.3.2.2.2 Hydrogen Recombiner Package Instrumentation and Control The catalytic hydrogen recombiner packages are designed for automatic operation with a minimum of operator attention.

Figure 11.3.2-6 shows the location of the instruments on the hydrogen recombiner. A multipoint temperature recorder monitors temperatures at several locations in the packages. Process gas flowrate is measured by an orifice located upstream of the hydrogen recombiner preheater. Local pressure gauges indicate the hydrogen recombiner process inlet pressure and the oxygen supply pressure.

The oxygen concentration. is monitored and controlled to ensure that a flammable hydrogen-oxygen mixture does not occur. The GWPS is provided with two analyzers to monitor oxygen concentrations. One is between the oxygen supply and the hydrogen recombiner package, and one is downstream of the hydrogen recombiner. When the hydrogen concentration is above the lower flammability limit of 4 percent, the minimum concentration of oxygen necessary for deflagration is 5 percent.. The control function assigned to these analyzers is to automatically terminate the oxygen supply before reaching GWPS oxygen concentrations favorable for hydrogen flammability. Each hydrogen recombiner package also includes two hydrogen analyzers. One monitors the process stream entering the hydrogen recombiner, and one monitors the discharge stream.

The controls and alarms incorporated to maintain the gas composition outside the range of flammable and explosive mixtures are described below.

11.3.2-6 REV 5 9/95

VEGP-FSAR-11 A. The maximum concentration of hydrogen that the hydrogen recombiner can process in a single pass is 6-percent hydrogen by volume.

B. If the hydrogen recombiner feed concentration exceeds 6-percent hydrogen by volume, a high-hydrogen alarm sounds to warn that all hydrogen entering the hydrogen recombiner is not reacted. This alarm will be followed by a second alarm indicating high hydrogen in the hydrogen recombiner discharge. These alarms warn of a possible hydrogen accumulation in the GWPS.

C. If the hydrogen concentration in the hydrogen recombiner feed reaches 9 percent by volume, a high-high hydrogen alarm sounds; the oxygen feed is terminated; and the VCT hydrogen purge flow is terminated. These controls limit the possible accumulation of hydrogen in the system to 3 percent by volume.

D. If the oxygen concentration in the hydrogen recombiner feed reaches 3 percent by volume, an alarm sounds and oxygen feed flow is limited so that no further Afncrease in flow is possible. This control maintains the system oxygen concentration at 3 percent or less, which is below the flammable limit for hydrogen-oxygen mixtures.

E. If hydrogen in the hydrogen recombiner discharge exceeds 1.5 percent by volume, an alarm sounds. This alarm warns of high hydrogen feed, possible reactor malfunction, or loss of oxygen feed.

F. If oxygen in the hydrogen recombiner discharge exceeds 15 ppm, a high alarm sounds. If it exceeds 60 ppm, a high-high alarm sounds and oxygen feed is terminated.

This control prevents any accumulation of oxygen in the system in case of reactor malfunction.

G. On low flow through the hydrogen recombiner, oxygen feed is terminated. This control prevents an accumulation of oxygen following system malfunction.

H. On high discharge temperature from the cooler-condenser (downstream from the catalytic reactor) oxygen feed is terminated. This protects against loss of cooling water flow in the cooler-condenser.

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VEGP-FSAR-11 I. On high temperature indication by any one of six thermocouples in the catalyst bed, the oxygen feed is terminated, and the VCT hydrogen purge flow is terminated.

J. On high temperature indication at the recombiner catalytic reactor discharge, oxygen feed to the recombiner is terminated.

11.3.2.2.3 Volume Control Tank Purge Flow Control Each VCT purge line into the GWPS is equipped with a trip valve, a pressure-reducing valve and a hand-operated flow control valve. This arrangement will maintain a constant purge flow as selected by the operator.

Pressure fluctuations caused-by changes in the VCT water level are absorbed by the pressure-regiulating valve, which maintains a constant downstream pressure. This provides a constant head loss across the hand-operated control valve. Design flow is 0.7 sf 3 /min hydrogen, with a range of 0.3 sf 3 /min to 1.2 sf 3 /min. When mixed with the 40 sf 3 /min nitrogen stream, the maximum hydrogen content (both units operating) in the recombiner feed is 6.0 volume percent.

The purge line trip valve closes as a result of:

A. A low-pressure signal from the VCT pressure instrumentation. This prevents depressurization of the VCT if the hydrogen supply is lost.

B. A low-pressure signal from the gas compressor suction line. Thissignal also stops the gas compressor.

C. Closure of the oxygen supply valve to the hydrogen recombiner.- The purge line trip valve is closed only if the oxygen supply valves for both the normally operating recombiner and the standby recombiner are closed.

11.3.2.3 System Operation 11.3.2.3.1 Startup Operation The GWPS is initially purged with nitrogen to remove all air.

During startup operation, one waste gas compressor, one hydrogen recombiner, and one shutdown GDT are in service in the process loop serving that plant unit. The reactor is at cold REV 9 5/00 11.3.2-8 REV 5 9/95

VEGP-FSAR-11 shutdown and the VCT contains nitrogen in the gas space. Reactor coolant contains neither hydrogen nor fission gases, but it may be saturated with air. While one unit is being started up, the VCT purge for the other unit is unaffected since each unit is served by a separate process loop of the GWPS.

When the reactor startup procedure requires that a hydrogen blanket be established in the VCT gas space, fresh hydrogen is charged into the VCT. The hydrogen-nitrogen mixture vented from the VCT enters the GWPS circulating nitrogen stream at the waste gas compressor suction. Nitrogen added to the GWPS accumulates in the shutdown GDT, causing the tank's pressure to rise.

Initially, the VCT vent gas will be very lean in hydrogen, and almost all the gas entering the GWPS will accumulate in the shutdown GDT. As the operation continues, however, the vent gas hydrogen content will gradually increase until it is almost totally hydrogen at t'he point when all of the nitrogen has been removed from the reactor coolant. At that time, hydrogen gas is passing through the VCT and mixing with the circulating nitrogen stream to give a mixture of hydrogen in nitrogen at the hydrogen recombiner inlet. A sufficient amount of oxygen is added in the hydrogen recombiner to react with the hydrogen to yield a discharge stream with a low residual concentration of hydrogen in nitrogen. After the water vapor is condensed and removed, the gas flow is directed to a shutdown GDT and from there to the waste gas compressor and back to the hydrogen recombiner.

When the reactor coolant hydrogen concentration is within operating specifications, the shutdown GDT is isolated, and flow is routed to one of the normal operation GDTs provided for normal power service. Gas accumulated in the shutdown GDT will be retained for use during operations to strip hydrogen from the reactor coolant when a plant unit is shut down.

11.3.2.3.2 Normal Operations During normal power operation, nitrogen gas with entrained fission gases is continuously circulated around each GWPS process loop by one of the two waste gas compressors in the loop. Fresh hydrogen gas is charged to the VCT, where it is mixed with fission gases which have been stripped from the reactor coolant into the VCT gas space. The contaminated hydrogen gas is continuously vented from the VCT into the circulating nitrogen stream to transport the fission gases into the GWPS. The resulting mixture of nitrogen-hydrogen fission gas is pumped by the waste gas compressor to the hydrogen 11.3.2-9

VEGP-FSAR-11 recombiner, where enough oxygen is added to reduce the hydrogen to a low residual concentration by oxidation to water vapor on a catalytic surface. After the water vapor is removed, the resulting gas stream is circulated to a normal operation GDT and back to the waste gas compressor suction to complete the circuit.

Each normal operation GDT is capable of being isolated, and only one tank is valved into operation in each process loop at any time. This minimizes the amount of radioactive gases that could be released as a consequence of any single failure, such as the rupture of any single tank or connected piping. A normal operation GDT is valved into the GWPS recirculation loop until the pressure or curie content of the inservice GDT reaches a value determined by approved plant procedure(s), after which it is isolated and another tank is placed in service. This process is illustrated in figure 11.3.2-3 for GDT pressure

• 20 psig and as illustrated in figure 11.3.2-4 when .GDT pressure will exceed 20 psig. By alternating the use of these tanks, the accumulated activity from one unit is distributed among all seven normal operation GDTs in the process loop.

With continued plant operation, pressure in the normal operation will gradually increase as nonremovable gases accumulate in the system. The initial system equipment lineup, as described above, will be from the waste gas compressor to the hydrogen recombiner and, then to the normal operation GDT. As the normal operation GDT'pressure builds up, compensation must be made by periodic adjustment of the hydrogen recombiner backpressure control valve. When the normal operation GDT pressure reaches approximately 20 psig, the backpressure control valve will be fully open, so that no more adjustment can be made. At this time, the appropriate bypass lines are opened to line up the equipment for flow from the waste gas, compressor to the normal operation GDTs and then to the hydrogen recombiner, as shown in figure 11.3.2-4. The hydrogen recombiner backpressure control valve is reset as required for the new arrangement, and the normal operation GDT pressure indicators are switched to read high range. This arrangement is suitable for operation up to 100 psig. Note that this high-pressure mode of operation will also normally be utilized during shutdown/startup operations.

11.3.2.3.3 Shutdown and Degassing of the Reactor Coolant System Plant shutdown operations are essentially startup operations in reverse sequence. The VCT hydrogen blanket is maintained until after the reactor is shut down and reactor coolant fission gas concentrations have been reduced to desired level. During this REV 6 4/97 11.3.2-10 REV 5 9/95

VEGP-FSAR-11 operation hydrogen purge flow may be increased to speed up reactor coolant degassing. At this time, the VCT hydrogen purge is stopped for the plant unit being shut down. The normal operation GDT in service for that unit is then valved out and a nitrogen purge from a shutdown GDT to the VCT is begun for the unit being shut down. This shutdown GDT is placed in the GWPS process loop at the waste gas compressor discharge so that the gas mixture from the VCT vents to the waste gas compressor suction, passes through the shutdown GDT and to the hydrogen recombiner, where hydrogen is removed, and remaining gases are returned to the waste gas compressor suction. The nitrogen purge continues until reactor coolant hydrogen concentration reaches the required level or chemical degassing may be used by the operator to reduce RCS hydrogen concentrations during cold shutdown operations. Degassing is then complete, and the RCS may be opened for maintenance or refueling. At this point the shutdown GDT may be isolated.

During the first plant cold shutdown, fresh nitrogen is charged to the VCT to strip hydrogen from the reactor coolant. The resulting accumulation of nitrogen in the shutdown GDT is accommodated by allowing the tank pressure to increase. During subsequent shutdowns, however, there is no additional accumulation since the gas from the first shutdown will be reused.

11.3.2.3.,4 System Drains During operation, water may accumulate in the waste gas compressor moisture separator, in the hydrogen recombiner phase separator, and in the GDTs. Normally, the waste gas compressor and hydrogen recombiner drains will discharge to the VCT under motive head provided by internal component pressure. During maintenance, the. drains-are directed either to the recycle holdup tanks (if the drains contain dissolved fission gases) or to the waste holdup tank through the drain header (if the drains contain no fission gases). A gas trap is provided in the drain lines from the waste gas compressors and hydrogen recombiners to prevent undissolved gases from leaving the GWPS.

All drains from the waste GDTs are manually operated. Depending on the internal tank pressure on the drain routing, the waste GDT drain pump is used or bypassed. As necessary, the tank is drained by pumping the accumulated condensate to the VCT.

However, during tank maintenance, waste GDT drains are routed to the recycle holdup tank because the volume of water in a waste GDT may be large enough to cause a noticeable dilution of reactor coolant boron concentration. Gas traps are provided in the waste GDT drain line to prevent the discharge of gases into other parts of the plant. All drains from the GWPS are filtered before entering either the VCT or the recycle holdup tank.

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VEGP-FSAR-11 11.3.2.3.5 Atmospheric Releases Although the GWPS is designed to accommodate continuous operation without atmospheric releases, the system design permits controlled discharge of gas from the system. Before a tank is emptied to the atmosphere via the plant vent, a gas sample must be analyzed to determine and record the activity to be removed. While the contents of a tank are being released to the atmosphere, a trip valve in the discharge line will close automatically if a high activity level is detected in the plant vent effluent.

11.3.2-12

VEGP-FSAR-ll 11.4 SOLID WASTE MANAGEMENT SYSTEM The solid waste management system is designed to collect, process, and package all solid radioactive wastes generated as a result of normal plant operation, including anticipated operational occurrences. The packaged waste is stored until it is shipped offsite to a licensed volume reduction facility or burial site. This system does not normally handle large waste materials such as activated core components.

11.4.1 DESIGN BASES The solid waste management system is designed to meet the following objectives:

A. Provide packaging capability for spent radioactive resins from the liquid waste processing and steam generator blowdown systems.

B. Provide a means to package crud from backflushable filters.

C. Provide a means to package combustible dry solid wastes, such as paper, rags, and contaminated clothing.

D. Provide a means to transfer the spent filter cartridges from filter vessels to shielded disposal containers in a manner which minimizes radiation exposure to operating personnel and the spread of contamination.

E. Provide a means for compacting and packaging miscellaneous dry radioactive materials, such as paper, rags, and contaminated clothing.

F. Provide temporary onsite storage of packaged wastes in the event of delay or disruption of offsite shipping schedules.

G. Package radioactive solid wastes for offsite shipment and disposal in accordance with applicable Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regulations, including 49 Code of Federal Regulations (CFR) 170-178 and 10 CFR 71.

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VEGP-FSAR-11 The solid waste management system is designed and constructed in accordance with Regulatory Guide 1.143, as described in section 1.9, to meet the requirements of General Design Criterion (GDC) 60 of 10 CFR 50, Appendix A. The seismic design classification of the alternate radwaste, radwaste processing facility, and radwaste transfer bui.ldingsis-provoided in section 3.2. jTh-e radwaste-proces.ing faci ltio.t-- proai.de* t ollow useof op6rtabie

_ssems,(Aemineral, rs frtion system de e~rin7iying.,-sol~iditicatioAlied by contractors for handling solid wastes from plant operations duringallplant cond-i-tions-(-paragraph 11.4.2.A). D__-y=c.tive~wase_(.DAW.)

f.ce-i-l-i-t--i-es-a-re-pprovided toprocess anfd stforeDAW (paragraph 11.4.2.5).

The solid waste management system design parameters are based on the radionuclide concentrations and volumes consistent with operating experience for similar reactor designs and with the source terms of section 11.1.

he-e eil-dwefstte-ma-nagemesnt-system--*+/-;bo Ients-arey re-l-ea'sedIt-ihr-ddgh the oýadV-a *t e=p-5*sn-g f-a~c-i]t y-ve nt-t-he latmcfs45here-as4p5rt of the"I0 CFR So; AppendikIk nalysis=-j T~he _sol-idw_--s-te -managment-s ystem--s-des-gned-to--cZlet-7 t- 3ý-t

[smation =Yotd"ndi:at:ro-,ead o-l-id-i-f y7-pack}ageý-, r_. tcý pl ah£i operati on or, maintenance persnnel as low as , sreas~onab.uy_ailfievaJe £!ý+/-ý in acco-dance wi.t h-GDDC 0 CFR 50,,ppendix A*WandýRegu-latory Gu*8T8-n-- ý6 -- o orde uu@f rt-t-oT- ] Thatiain pe rsonne-l--expo suros--*re s--o-w'----

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l 1 -~~qi~emets. m* C Ss- --t*the_'p roc(ýss 6r I pfmm nt--an d-7,

-Acce!E s 'o :l d =w a Ef6,-ý- Eoria g e -a-r-e a s-1-s -c Jen-ttre-1-eýd-to i-nimrze-personne47 expos--reb7y-sil---tabl "bartiers such a's locked doorfsor-gat-es--orj7 control cardst--See paragrap-H-27.3.1.2and sect-onnd25)- -The socrr-waste management system has been designed to conform with the design criteria of NRC Branch Technical Position ETSB 11-3.

11.4.1.1 Safety Design Bases The solid waste management system performs no function related to the safe shutdown of the plant, and its failure does not adversely affect any safety-related system or component; therefore, the solid waste management system has no safety design basis.

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VEGP-FSAR-11 11.4.1.2 Power Generation Design Bases The solid waste management system is designed to minimize the volume of solidified wastes and provide temporary onsite storage for the packaged wastes. 'The system is designed for a 40-year service life, maximum reliability, minimum maintenance, and minimum exposure to operating and maintenance personnel. The system is designed to have sufficient capacity based on normal waste generation rates to ensure that maintenance or repair of the solid waste management system equipment does not impact power generation.

.. \vegpfsar\Chapll\11-4-1 11.4.1-3 REV 2 3/92

VEGP-FSAR-11 11.4.2 SYSTEM DESCRIPTION 11.4.2.1 General Description The solid waste management system consists of the following which are shown in drawings AX4DBI05-1, AX4DBI05-2, AX4DBI05-5, lX4DBI48, IX4DB148-1, IX4DB148-2, lX4DBI48-3, IX4DB148-4, AX4DBI48-5, AX4DBI48-6, AX4DBI48-7, lX4DBI48-8, IX4DB148-9, lX4DBl48-10, IX4DB148-11, lX4DBI48-12, and IX4DB148-13.

• Resin transfer.

• Backflushable filter system.

• Crud transfer.

The activity of the influents to the solid waste management system is dependent on the activities of various fluid systems, such as the boron recycle system, liquid waste processing system, chemical and volume control system, spent fuel pool cooling and cleanup system, steam generator blowdown system, and condensate polishing demineralizer system. Reactor coolant system activities and the decontamination factors for the systems given above also determine the influent activities to the solid waste management system.

Table 11.4.2-1 lists the parameters used in calculation of the estimated activity fed to the solid waste management system.

Table 11.4.2-2 lists the estimated expected activities of wastes to be processed on an annual basis, their physical form and source, and their isotopic makeup and curie content. Table 11.4.2-3 provides the same information based on the maximum expected activities of the input wastes. The estimated annual quantities of radwaste input to the solid waste management system and the estimated quantities of radwaste to be shipped offsite are presented in table 11.4.2-4. The estimated expected curie and isotopic content of wastes to be shipped offsite for each waste category is presented in table 11.4.2-5. Table 11.4.2-6 presents the same'information based on expected maximum activities.,

Section 11.1 provides the bases for determination of liquid source terms which are used to calculate the solid waste source terms. The data presented in tables 11.4.2-2, 11.4.2-3, 11.4.2-5, and 11.4.2-6 are conservatively based on section 11.1 and the following additional information:

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VEGP-FSAR-11 A. As a basis for the shipped-from-site activities given in tables 11.4.2-5 and 11.4.2-6, 30 days of decay prior to shipping is assumed. The major contributors to the activity levels in the system are radionuclides having long half-lives; therefore, further onsite decay of radionuclides provides limited benefit.

B. The miscellaneous dry and compacted waste volume is based on reference 1.

C. Shipping volumes from the cartridge filter handling system are based on packaging (per 55-gal drum):

1. One spent filter cartridge.

2. The drum is prelined with cement with an integral cavity to accept a filter.

Section 11.1 provides the bases for the quantity of primary and secondary resins. Section 11.2 provides the basis for the quantity of chemical drain wastes, while reference 1 provides the basis for the remaining quantities presented in table 11.4.2-4.

11.4.2.2 Component Description Codes and'standards applicable to the solid waste management system are listed in table 3.2.2-1. The solid waste management system is housed within buildings designed to meet the seismic requirements of Regulatory Guide (RG) 1.143. Conformance with RG 1.143 is to the extent specified in section 1.9.

11.4.2.3 System Operation 11.4.2.3.1 Resin Transfer System The resin transfer system provides the capability for remote transfer of spent radioactive resin from the auxiliary building to the radwaste processing facility.

11.4.2.3.2 Backflushable Filter System The backflushable filter system provides the means to remove and deliver radioactive crud from certain process streams to the crud transfer system. The system consists of the filters summarized in table 11.4.2-7, a backflushable filter crud tank, and a centrifugal pump. Each backflushable filter is operated REV 11 5/03 REV 8 10/98 REV 4 4/94 11.4.2-2 REV 2 3/92

VEGP-FSAR-11 in a similar manner. A sufficient buildup of crud on the filter signals an annunciator and the operator then initiates the automatic filter backflush sequence (Unit 1 only). The operator can manually carry out the backflush sequence if it is desired.

The backflush sequence isolates the filter, opens a line to the backflushable crud tank, and introduces approximately 8 ft3 of high-pressure (350 psig) nitrogen from a nitrogen accumulator through the filter. The nitrogen accumulator is supplied by the auxiliary gas system. The crud removed from-the filters collects in the backflushable crud tank. After each backflush operation the lines and tank are water flushed. The contents of the backflushable crud tank may be slurried to the radwaste processing facility at operator discretion or upon high tank level annunciation.

11.4.2.3.3 Filter Handling System The filter handling system is a semiremote system which provides the capability to remove spent radioactive cartridge filters from their filter housings and place them in drums with external shielding or use of a transfer cask for transport to the radwaste processing facility. The techniques used in the filter handling system included the consideration of the following:

• Operator exposure.

• Time and manpower requirements.

• Potential for the spread of contamination.

• Potential for mechanical difficulties.

Logistics for filter handling.

The semiremote system, as the name implies, requires the operator to be in the proximity of the filters; however, operator exposure is minimized by distance and shielding.

The filter handling system consists of a working plug, a bell-shaped shielded transfer cask, a mobile cask-to-drum transfer station, and drum capper. The working plug is designed to fit in a hatch above the filter housing and has provisions for viewing the top of the filter housing and penetrations to allow long handled tools to be used for the removal of the filter housing top. The bell-shaped shielded transfer cask is used to retract the spent filter cartridge from its housing and transport it to the filter transfer station where the filter is placed in a shielded drum and capped. The filters in the shielded drums are transported to the radwaste processing facility for packaging.

The filters may also be transported using the transfer cask directly to the radwaste processing facility for packaging.

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VEGP-FSAR-11 11.4.2.4 Portable Radwaste System VEGP will utilize vendor-supplied portable radwaste equipment to provide for disposal of spent resins, radioactive cartridge filters, backflushable filter crud, and chemical wastes via dewatering or solidification. Details of this equipment are shown on drawings AX4DBl24-2, AX4DBI24-3, and AX4DBI24-4. In addition, a portable demineralizer system and a filtration system are available as alternate means of processing the contents of the waste holdup tank, chemical drain tank, floor drain tank, and boron recycle holdup tank. Details of this equipment are shown on drawings AX4DBI24-2, AX4DBI24-3, AX4DBI24-4, and AX4DBI24-5.

These systems are housed in the radwaste processing facility which is shown on drawing AX4DE357.

Isolation valves are provided to allow processing of waste streams at the radwaste processing facility. The valves are manually and remotely operated to achieve the desired configuration. Delivery of waste streams to the radwaste processing facility is controlled from local panels near the waste stream source. Flanged connections are provided at the radwaste processing facility to interface with the vendor-supplied systems. Major components for portable radwaste systems typically include process liners, process skids, and control panels. A separate radwaste processing facility control room and dressout area is provided to facilitate system operation.

Radioactive condensate polishing demineralizer resins, backflushable filter crud, and spent resins from the liquid waste processing system and the steam generator blowdown system will be dewatered. The dewatering system supplied by vendor allows the water to be-removed from the spent resins in the shipping containers. A vendor-supplied container vent is provided for the shipping containers thereby minimizing leakage into the building. A vent line to a monitored HVAC exhaust duct in the radwaste processing facility is provided. In addition, demineralizer resins from the portable demineralizers (as discussed in section 11.2) can be sluiced to the container fill skid for dewatering and disposal.

An NRC approved process control program (PCP) will be required of the vendor and appropriately referenced in the VEGP PCP prior to any actual operation. If the burial site does not accept dewatered resins or the waste form criteria cannot be met, VEGP will have the ability to solidify resins utilizing a portable solidification system. Cartridge filters will be loaded into liners for shipment offsite.

Solidification/dewatered liners will normally be shipped after filling and proper cure time, provided the proper shielding is available, without exceeding DOT radiation limits. If REV 11 5/03 REV 6 4/97 REV 5 9/95 11.4.2-4 REV 2 3/92

VEGP-FSAR-11 49 CFR 173 dose limitations cannot be met with the available shielding, the liners are stored ard allowed to decay until the appropriate shielding is available. Onsite storage for decay of short-lived radionuclides is accomplished both prior to solidification in holdup tanks and in appropriate onsite storage areas.

Short-term storage of solid radwaste for the purpose of activity reduction by radioactive decay is provided by shielded environmental containers located on a concrete pad adjacent to the southeast corner of the abandoned radwaste solidification building. High-integrity containers, containing the solid radwaste, are inserted into the shielded environmental containers which are right circular cylinders of reinforced concrete of sufficient thickness to provide appropriate shielding and normal environmental protection.

11.4.2.5 Dry Active Waste Facilities Low level dry wastes are collected in drums, plastic bags, and other methods as approved by the health physics department, at appropriate locations throughout the plant, as dictated by the volume of these wastes generated during operation or maintenance.

Large components and equipment which have been activated during reactor operation and which are not amenable to solidification, compaction, or volume reduction are handled either by qualified plant personnel or by outside contractors specializing in radioactive materials handling and are packaged in boxes or shipping casks of appropriate size.

Two buildings have been designed for handling dry active wastes (DAW) from plant operations:

A. The DAW processing building was designed to be used for sorting and compacting DAW. This building-may also be used to store radioactively contaminated outage material and other radioactively contaminated items as needed.

B. The DAW storage building is used to store DAW. This building may also be used to store radioactively contaminated .outage material and other radioactively contaminated items as needed.

11.4.2.5.1 Dry Active Waste Processing Building uAWota-gee equipment--- and-other--ra'di-oa-c-t-i-*iiv -- contýa minated7 "i----n

'j--_- - asr- (deto thai tot-hep -° c-t-*-iners or( contained-in some manner which will prevent any leakage of radioactive material during conditions incident to REV 9 5/00 REV 6 4/97 11.4.2-5 REV 2 3/92

VEGP-FSAR- 11 normal transportation; The radioactive material is packaged such that contamination on the outer container/containment surface is below administrative limits. The transport path remains within the owner-controlled area.

The DAW processing building has separate areas for incoming radwaste containers, sorting and compaction of radioactive waste, handling of nonradioactive dry waste, and storage of empty containers. The DAW is sorted to separate usable material, radioactive waste, and nonradioactive waste. Radioactive waste is compacted into packaging that will comply with the criteria of 10 CFR part 71 to minimize the need for repackaging for shipment.

A sorting table and dry waste compactor are provided. The sorting table and trash compactor have designs that direct any airborne dusts created by the sorting or compaction operation through an exhaust fan and filter and then to the building ventilation system.

T-Fi -i--Z----i-n-g-h-a-s--ockab-l-e-door-s-a.nd-is-enc-l-osed-by-a-f-ence-wi-t-h.

• 1-07.* k-a15 l _-*gates- - e p urp S

• f*-t-*- =*f e-n-*e,ýf -t o-pre *eln-t-- ,/

czErtypatr-'svri y-bu-ild-i-ng~s ecu-rity--_ý The building is provided with automatic wet-pipe sprinkler systems designed for an Ordinary Group II Hazard. Ionization and photoelectric smoke detectors are provided. Smoke detectors actuation or sprinkler head water flow initiates local audible/visual alarms external to the building. A fire hose station with portable extinguisher is provided. The waste container materials used do not support combustion.

11.4.2.5.2 Dry Active Waste Storage Building DAW--ou-t-age-equi-pment--nd-7ohern radi-a-tve--arial--aretransported to the storage facility in packaging that will comply with the criteria of 10 CFR Part 71 or in containers that will prevent leakage of any radioactive material incident to normal transportation. The waste-i.sstored, in the interior of the building. L:]k-a-l-e--deor-s-and---a-fence-with aock abcl--are e-p-rov-i-de d.

The building is provided with automatic wet-pipe sprinkler system and smoke detectors. Fire alarms external to the building are provided. The waste container materials used do not support combustion.

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VEGP-FSAR-11 REFERENCES

1. "A Waste Inventory Report for Reactor and Fuel-Fabrication Facility Wastes," ONWI-20, NUS-3314, March 1979.

11.4.2-7 REV 2 3/92