ML16256A124

Revision 309 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant, Section 1.2

ML16256A124
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Site:	Waterford
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WSES-FSAR-UNIT-3 1.2-1 Revision 14 (12/05) 1.2 GENERAL PLANT DESCRIPTION1.2.1 PRINCIPAL SITE CHARACTERISTICS1.2.1.1 Location and Population The Waterford 3 site is located on the west (right descending) bank of the Mississippi River near Taft, Louisiana in the northwest portion of St. Charles Parish. About three miles westward is the eastern boundary of St. John the Baptist Parish. The coordinates for the reactor are 290 59' 42" north latitude

and 900 28'16" west longitude. The UTM coordinates are 3320744 meters north, and 743963 meters

east.Kenner, the nearest population center is 13 miles east of the site. Approximately 25 miles east-southeast of the site is the city of New Orleans, and approximately 50 miles north-northwest is the city of Baton Rouge. The exclusion radius is taken as 915 meters, and the low population zone is a two mile radius. 1.2.1.2 Geography and HydrologyThe site is located on the right descending bank of the Mississippi River near Taft, Louisiana. It consists of over 3,000 acres of flat land extending from the Mississippi River to the St. Charles Drainage Canal.

The site includes about 7500 feet of river frontage. About 3,000 feet back from State Road 18, which runs adjacent to the levee, the Missouri Pacific Railway crosses the width of the property. The plant area is raised to a final grade of +17.5 ft.MSL around the Nuclear Plant Island Structure, and +14.5 ft. MSL

around the Turbine Building. Flood protection in the vicinity of the site includes levees, bypass channels, and channel stabilization that can effectively confine flood flows except for very severe floods. Structures housing safety-related

equipment are flood protected to elevation +30 ft.MSL. 1.2.1.3 Meteorology(DRN 03-2054, R14)The climate of southeastern Louisiana is classified as humid subtropical and is characterized by mild, humid winters and hot, humid summers. Daily maximum summer temperatures are generally around 95F while winter temperatures normally lie between 41 and 69F. The region's rainy season extends from mid-December to mid-March. Measurable precipitation occurs on about one-third of the days during this period. Snowfall amounts are very light with the snow usually melting as it falls. (DRN 03-2054, R14)Thunderstorms with damaging winds and hail are relatively infrequent. A few of the more severe thunderstorms however, will generate tornadoes. The probability of a tornado striking the site is

discussed in Section 2.3. During the period 1871-1977, 55 tropical storms and hurricanes passed within 100 nautical miles of the site.

WSES-FSAR-UNIT-3 1.2-2 Revision 307 (07/13)

Wind direction varies widely at the site with an average speed of about nine mph. Calms occur approximately 12 percent of the time. The average wind speed during inversion conditions is about three mph. Stability at the site is Pasquill type E,F,or G, 56 percent of the time.

1.2.1.4 Geology and Seismology The site has a uniform stratigraphy i.e., no salt domes or possibility of local faulting, no possible surface expression of known or hypothetical faults. The st ructures are conservatively designed and built with respect to geological considerations. The site ground accelerations for the Safe Shutdown Earthquake (SSE) and Operating Basis Earthquake (O BE) are 0.10g and 0.05g, respectively.

1.2.1.5 Nearby Industry and Commerce The area adjacent to the site is moderately industria lized. Both banks of the Mississippi River near the site are lined with industrial facilitie s, primarily chemical plants. The Agrico Chemicals Co. is adjacent to and downstream of the Waterford 3 site. Next to Agrico Chemicals Co. is the Occidental Chemical Corporation and farther downstream is the Union Ca rbide Company. Two Shell Oil Company plants, a chemical plant and a refinery, are located on the oppos ite bank from Waterford 3, approximately 1.5 miles downstream. The Mississippi River is used ext ensively for commercial traffic and municipal, and industrial water use.

Site and plot plans are provided in Figures 1.2-1 and 1.2-2.

For further information see Chapter 2.

1.2.2 CONCISE PLANT DESCRIPTION 1.2.2.1 Reactor and Reactor Coolant System 1.2.2.1.1 Reactor (DRN 03-2054, R14)

The pressurized water reactor was designed for an init ial core thermal power output of 3390 megawatts.

The design core thermal power output is incr eased to 3716 megawatts starting at Cycle 14. (DRN 03-2054, R14)

(DRN 06-1058, R15; EC-30663, R307)

The reactor core is fueled with uranium dioxide pellets enclosed in zircaloy or ZirloTM1 tubes pressurized with helium and fitted with welded end plugs. The tubes are fabricated into assemblies in which end

fittings prevent axial motion and spacer grids prevent lateral motion of the tubes. The control element assemblies (CEAS) consist of Ni-Cr-Fe alloy clad bor on carbide absorber rods, guided by tubes in the fuel assembly. The core consists of 217 f uel assemblies with multiple U-235 enrichment. (DRN 06-1058, R15; EC-30663, R307)

Fuel rod clad is designed to maintain cladding integrity throughout fuel life. Fission gas release within the rods and other factors affecting design life are considered for the maximum expected exposure.

(EC-30663, R307) 1 Zirlo, Optimized Zirlo, and Low Tin Zirlo ar e trademarks or registered trademarks of Westinghouse Electric Company LLC, its affiliates and/or its subsid iaries in the United States of America and may be registered in other countries throughout the world.

All rights reserved. Unaut horized use is strictly prohibited. Other names may be tradem arks of their respective owners. (EC-30663, R307)

WSES-FSAR-UNIT-3 1.2-3Revision 307 (07/13) The reactor and control systems are designed so that any xenon transients will be adequately damped.

The CEAs are capable of holding the core subcritical at hot zero power conditions with margin following a trip even with the most reactive CEA stuck in the fully withdrawn position.

The combined response of the fuel temperature coe fficient, the moderator temperature coefficient, the moderator void coefficient and the moderator pressure coefficient to an increase in reactor thermal power is a decrease in reactivity.

In addition, the reactor power transient remains bounded and damped in response to any expected changes in any operating variable.

The reactor, in conjunction with its protective systems is designed to safely accommodate the anticipated operational occurrences.

See Chapter 4 for further information.

1.2.2.1.2 Reactor Coolant System

The Reactor Coolant System (RCS) is arranged as tw o closed loops connected in parallel to the reactor vessel. Each loop consists of one 42 in. ID outle t (hot) pipe, one steam generator, two 30 in. ID inlet (cold) pipes and two pumps. An el ectrically heated pressurizer is connected to one of the loops and a safety injection line is connected to each of the four inlet legs. The RCS operates at a nominal pressure of 2,250 psia.

(EC-1020, R307)

The reactor vessel is fabricated fr om SA-533, Grade B steel, clad with stainless steel. The replacement reactor vessel closure head is fabricated from SA-508, Grade 3, Class 1 material. The design of the vessel and its internals is such that for reactor operation at design power and an 80 percent capacity factor, the vessel fluence greater than one Mev at the vessel wall will not exceed 3.68 x 10 19 n/cm 2 over the 40-year design life of the vessel. (EC-1020, R307)

(DRN 03-2054, R14)

The two steam generators are vertical shell and U-t ube units. The steam generated in the shell side of the steam generator flows upward through moisture separ ators which reduce its moisture content to less than 0.25 percent. All RCS internal surfaces are eit her stainless steel or Ni-Cr-Fe alloy in order to maintain reactor coolant purity. (DRN 03-2054, R14)

The reactor coolant is circulated by four electric-motor-driven, single-suction centrifugal pumps. The pump shafts are sealed by mechanical seals. The seal performance is monitored by pressure and temperature sensing devices in the seal system.

The RCS is designed and constructed to maintain its integrity throughout the plant life. Appropriate means of test and inspection are provided.

See Chapter 5 for further information.

WSES-FSAR-UNIT-3 1.2-4 Revision 304 (06/10) 1.2.2.2 Engineered Safety Features (DRN 04-1619, R14)

The plant design incorporates redundant engineered safety features (ESF). These systems, along with the containment, insure that the offsite radiological consequences following any postulated loss-of-coolant accident (LOCA) up to and including a double-ended break of the largest reactor coolant pipe will not exceed the guidelines of 10CFR50.67. The systems also insure that the guidelines of 10CFR50, Appendix K, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Power Reactors",

are satisfied, based upon analytical methods, assumptions and procedures accepted by the NRC. The

ESF include: (a) independent redundant systems (Containment Cooling System and Containment Spray System) to remove heat from and reduce the pressure in the containment in order to maintain

containment integrity, (b) a Safety Injection System to limit fuel and cladding damage to an amount which will not interfere with adequate emergency core cooling and to limit metal-water reactions to negligible

amounts, (c) a Containment Isolation System to minimize post-LOCA radiological effects offsite, (d) a Combustible Gas Control System to maintain safe post-LOCA hydrogen concentration within the

containment (e) Habitability Systems to insure control room habitability following a LOCA, and (f) a Shield Building Ventilation System to limit annulus pressure, and to control and filter releases post-LOCA. (DRN 04-1619, R14)

See Chapter 6 for further information.

1.2.2.3 Instrumentation and Controls

1.2.2.3.1 Controls (EC-15702, R304)

The Reactor Control System is used for startup and shutdown of the reactor and for adjustment of the reactor power in response to turbine load demand. The Nuclear Steam Supply System (NSSS) is capable of following a ramp change from 15 percent to 100 percent power at a rate of up to five percent per

minute and at greater rates over smaller load change increments up to a step change of 10 percent.

During a maneuver, compensation must be provided for the changes in reactivity associated with both changes in power level (power defect) and changes in transient xenon level which result from the change in power level. The average temperature control program provides a reference temperature which is a function of power. This temperature is compared with the existing average reactor coolant temperature. If the temperature is different, core reactivity is adjusted until the difference is within the prescribed control band. Regulation of the average reactor coolant temperature in accordance with this program maintains the secondary steam pressure within operating limits and matches reactor power to load demand. The

mechanisms by which the necessary reactivity compensation is provided are CEA position, boron

concentration and primary coolant temperature. (EC-15702, R304)

The reactor is controlled by a combination of CEAs and dissolved boric acid in the reactor coolant. Boric acid is used for reactivity changes associated with large but gradual changes in average coolant

temperature, xenon concentration and fuel burnup.

WSES-FSAR-UNIT-31.2-5Additions of boric acid also provide an increased shutdown margin during the initial fuel loading andsubsequent refuelings. The boric acid solution is prepared and stored at a temperature sufficiently high to prevent precipitation.CEA movement provides changes in reactivity for shutdown or power changes. The CEAs are actuated bycontrol element drive mechanisms mounted on the reactor vessel head. The control element drive mechanisms are designed to permit rapid insertion of the CEAs into the reactor core by gravity. CEA motion can be initiated manually or automatically.The Core Operating Limit Supervisory System (COLSS) functions to monitor selected parameters, toprovide an on-line calculation of margin to a Limiting Condition for Operation (LCO), and to actuate an alarm when a LCO is reached.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 orcondensed by the pressurizer spray to reduce variations caused by expansion and contraction of the reactor coolant due to system temperature changes.Overpressure protection is provided by safety valves connected to the pressurizer and designed inaccordance with ASME Code,Section III. The discharge from the pressurizer safety valves is releasedunder water in the quench tank, where it is condensed and cooled. Overpressure protection for the tank is provided by a rupture disc which relieves to containment.1.2.2.3.2InstrumentationThe nuclear instrumentation includes out-of-core and in-core flux detectors. Eight independent channelsof out-of-core nuclear instrumentation monitor the fission process. Two channels are used to monitor the reactor from startup through full power; four channels are used to monitor the reactor from routine startupneutron flux levels to 200 percent power and are used to initiate a reactor shutdown in the event of high linear or logarithmic power; and two are used in the automatic control system to regulate the reactor inresponse to turbine demand. The in-core monitors provide information on neutron flux distribution.The reactor parameters are maintained within acceptable limits by the inherent negative feedbackcharacteristics of the reactor, by the CEAS, by boric acid dissolved in the moderator, and by the operatingprocedures. In addition, in order to preclude unsafe conditions for plant equipment or personnel, the RPS is provided. The RPS consists of sensors, calculators, logic and other equipment necessary to monitor selected Nuclear Steam Supply System (NSSS) conditions and to effect reliable and rapid reactor shut-down (reactor trip) if any or a combination of the monitored conditions approach specified safety systemsettings. The systems functions are to protect the core fuel design limits and reactor coolant pressure boundary for anticipated operational occurrences and also to provide assistance in limiting conditions forcertain accidents. Four measurement channels with electrical and physical separation are provided for each parameter used in the direction generation of trip signals, with the exception of control elementassembly (CEA) position. A two out of four coincidence of like trip signals is required to generate areactor trip signal. The use of four channels allows bypassing of one channel for maintenance while maintaining a two out of three channel trip. The reactor trip signal deenergizes the control element drive mechanism (CEDM) coils, allowing all CEAs to drop into the core.

WSES-FSAR-UNIT-31.2-6Four independent core protection calculators (CPCS) are provided, one in each protection channel. Calculation of departure from nucleate boiling ratio (DNBR) and local power density is performed in each CPC, utilizing the input signals described below. The DNBR and local power density so calculated are compared with trip set-points for initiation of a low DNBR trip and the high local power density trip.Two independent CEA calculators are provided as part of the CPC System to calculate individual CEAdeviations from the position of the other CEAs in their subgroup.Each CPC receives the following inputs: core inlet and outlet temperature, pressurizer pressure, reactorcoolant pump speed, excore nuclear instrumentation flux power (each subchannel from the safetychannel), selected CEA position, and CEA subgroup deviation from the CEA calculators. Input signals are conditioned and processed.Additional temperature, pressure, flow and liquid level monitoring is provided, as required, to keep theoperating personnel informed of plant conditions, and to provide information from which plant processescan be evaluated and/or regulated.The plant gaseous and liquid effluents are monitored for radioactivity. Activity levels are displayed and off-normal values are annunciated. Area monitoring stations are provided to measure radioactivity at selected locations in the plant.See Chapter 7 for further information.

1.2.2.4Electric PowerWaterford 3 generates power at a nominal 25 kV. This is transformed up to 230 kV and enters the 230 kVswitchyard through two overhead tie lines. Two start-up transformers, each supplied from one of the two overhead tie lines provide power for start-up, shutdown, reserve full load operation and preferredemergency shutdown service to the 6.9 kV and 4.16 kV auxiliary system buses. While the unit is in normal operation, these buses are normally supplied by two auxiliary transformers connected to the maingenerator 25 kV bus.Redundant sources of offsite power are provided by seven separate transmission lines connected to the230 kV switchyard. Any one of these lines together with either of the tie lines and its start-up transformeris capable of supplying the total emergency power requirements to ensure that no single failure of any active component can prevent a safe and orderly shutdown.Redundant sources of onsite power are provided by two diesel generators, either of which is capable ofsupplying sufficient engineered safety features (ESF) loads to ensure safe shutdown and maintenance in a safe condition in the event of complete loss of offsite power.The ESF redundant systems have been electrically and physically designed and segregated so that asingle electrical fault or a single credible event will not cause loss of power to both sets of redundant essential electrical components.See Chapter 8 for further information.

WSES-FSAR-UNIT-3 1.2-7 Revision 306 (05/12) 1.2.2.5 Steam and Po wer Conversion System The Steam and Power Conversion System removes heat energy from the reactor coolant in two U-tube steam generators, and converts the steam into electrical energy by means of a turbine-generator. The

unusable heat in the steam cycle is transferred to t he main condenser for rejection by the Circulating Water System. The resulting condensate is then deaerated, heated through feedwater heaters and returned to the steam generators as feedwater.

The main turbine is a Westinghouse Electric Co rporation 1800 rpm, tandem-compound, six flow exhaust unit with 40 in. last stage blades. Moisture separators and reheaters dry and superheat the steam between the high and low pressure elements of the turbine.

The main condenser is a single-pass, three shell, single pressure type with divided water boxes. The tubes in each shell are oriented transverse to the turbine shaft. Cooling water for the condenser is

provided by the Circulating Water Sy stem from the Mississippi River.

Other components of the Steam and Power Conversion Sy stem are the main steam supply piping, Steam Bypass System, three motor driven condensate pumps, thr ee strings of five stage low-pressure feedwater heaters, two turbine driven feedwater pumps, three st rings of one stage high pressure feedwater heaters, the Steam Generator Blowdown Syst em, and Emergency Feedwater System.

The Emergency Feedwater System (EFS) supplies condensate to the steam generators following the loss

of normal feedwater. The EFS also provides water to the unaffected steam generator following a postulated main steam or feedwater line break.

In case of a turbine trip, the Steam Bypass Syst em passes steam directly to the condenser thereby dissipating the stored energy in the reactor coolant and nuclear fuel. There are also the spring loaded main steam safety valves which discharge to the at mosphere, providing overpressure protection for the Main Steam System.

See Chapter 10 for additional information.

1.2.2.6 Fuel Storage and Handling

New fuel assemblies are normally stored in vertical racks of the spent fuel Pool. (EC-16212, R304; EC-14275, R306)

Irradiated fuel assemblies are stored in the spent fuel pool or at the Independent Spent Fuel Storage Installation (ISFSI). The stainless steel lined, rein forced concrete spent fuel pool provides storage for up to 1849 assemblies. Adequate spacing in the spent f uel storage pool precludes cr iticality; the supporting analysis takes no credit for the boron in the pool water. (EC-16212, R304)

The ISFSI, shown on Figure 1.2-1, c onsists of a concrete pad with s pace for 72 natural convection air-cooled HI-STORM shielded dry casks, each capable of storing 32 spent fuel assemblies in a welded multipurpose container. The ISFSI is located in the plant protected area. (EC-14275, R306)

New fuel can also be stored in a separate dry fuel st orage vault. That vault has vertical rack space for 80 assemblies. New fuel assembly spacing and vault construction prec ludes criticality.

Cooling and purification equipment is provided for the spent fuel pool cooling water.

WSES-FSAR-UNIT-31.2-8Revision 11-A (02/02)(DRN 01-758)

The Fuel Handling System provides for the safe handling of fuel assemblies and control element assemblies(CEAS) and for the required assembly, disassembly and storage of reactor internals. This system includes a refueling machine located inside the containment above the refueling pool, the fuel handling crane, fuel

handling tools, the fuel transfer carriage, the upending machine, CEA change mechanism, new fuel elevator, fuel inspection stand, the fuel transfer tube, a fuel handling machine in the spent fuel storage room, and

various devices used for handling and storing the reactor vessel head and internals.(DRN 01-758)

See Section 9.1 for further information.

1.2.2.7 Cooling Water and Other Auxiliary Systems 1.2.2.7.1 Circulating Water System The Circulating Water System provides a heat sink with sufficient capacity to remove the heat rejected inthe main condenser and Turbine Building Closed Cooling Water System during normal operation. River

water is pumped from the intake structure to the tube side of the main condensers and turbine building

closed cooling water heat exchangers by the circulating water pumps. Water from the condensers and the

heat exchangers is discharged through a system to a discharge structure which discharges into the river

downstream of the intake structure.

See Subsection 10.4.5 for further information.

1.2.2.7.2 Component Cooling Water SystemsThe Component Cooling Water System (CCWS) is the ultimate heat sink for the plant. It is designed toremove heat from the reactor coolant and the auxiliary systems during normal operation, shutdown, oremergency shutdown following a Loss of Coolant Accident (LOCA). In the CCWS, cooling water is pumped through the dry cooling towers and the tube side of the component cooling heat exchangers, through the

components being cooled, and back to the pumps.

The Auxiliary Component Cooling System (ACCS) removes heat, if required, from the CCWS via thecomponent cooling heat exchangers during normal operation, shutdown, or post-LOCA. In the ACCS the

cooling water is pumped through the shell side of the component cooling heat exchangers, where it removes

heat from the CCWS, and rejects it to the atmosphere via the wet cooling towers.There are two redundant, independent, full capacity CCWS trains. Each CCWS is provided with an ACCS loop.See Section 9.2 for a discussion of the CCWS.

WSES-FSAR-UNIT-31.2-9Revision 11-A (02/02) 1.2.2.7.3 Chemical and Volume Control System A Chemical and Volume Control System (CVCS) controls the purity and chemistry of the reactor coolant.

Part of the reactor coolant is bypassed through the CVCS, via regenerative and letdown heat exchangers, afilter and ion exchangers before being sprayed into the volume control tank. The charging pumps take suction from this tank and pump the coolant back into the Reactor Coolant System.

See Subsection 9.3.4 for further information.

1.2.2.7.4 Shutdown Cooling System(DRN 01-758)

The Shutdown Cooling System (SDCS) reduces the temperature of the reactor coolant from 350°F to the refueling temperature, removes decay heat during normal shutdown, and removes heat from the Safety

Injection System sump water via the shutdown cooling heat exchangers following a LOCA.(DRN 01-758)

During shutdown cooling, a portion of the reactor coolant, via the shutdown cooling lines and low pressuresafety injection system pumps, is cooled through two shutdown heat exchangers. The control valves and bypass lines are used to control the plant cooldown rate.

See Subsection 9.3.6 for further information.

1.2.2.7.5 Compressed Air System The Compressed Air System is provided to supply properly conditioned compressed air required to operate pneumatic instruments and controls, periodically pressurize containment penetrations for leak detection, operate containment isolation valves and perform normal plant maintenance. it consists of the Instrument Air

System which supplies the various air operated valves, pneumatic instruments and controls and the Station

Air System which supplies various outlets throughout the plant.

Redundancy is provided by multiple compressor units and a cross-connection between the Instrument andStation Air Systems. In case of loss of instrument air, all safety related pneumatically operated devices inthe plant are designed to fail in a position which would allow safe shutdown. Where safety class valves are

required to operate, accumulators are provided.

See Subsection 9.3.1 for further information.

1.2.2.7.6 Demineralized Makeup Water System In the Makeup Water System, river water is first filtered, then demineralized and stored in a condensate storage tank and primary storage tank for use as makeup for the plant processes.

See Subsection 9.2.3 for further information.

WSES-FSAR-UNIT-3 1.2-10 Revision 14 (12/05)1.2.2.8 Radioactive Waste Management SystemsThe Boron Management and Waste Management Systems (BMS and WMS) provide the means for controlled handling, storage and disposal of liquid, gaseous and solid wastes. In addition, the BMS provides the mechanism for reconcentrating and recovering dissolved boron from the liquid effluent for

reuse in the plant. (DRN 00-1053, R11-A;00-803, R11-B,)

Liquid effluent from the RCS first passes through the purification filter in the CVCS. It is then processed in the BMS by successively passing through the holdup tanks, filters, and ion exchangers. These operations remove the radioactive material and concentrate the boric acid for reuse or drumming. All other radioactive liquid wastes are processed in the WMS for release to the environment or drumming.

All liquid wastes are sampled prior to release. The waste release rates are as low as reasonably

achievable and within the guidelines and limits for waste release established by 10CFR20 and 10CFR50, Appendix I.(DRN 00-1053, R11-A;00-803, R11-B)All solid wastes are stored in suitable containers for ultimate offsite disposal in accordance with applicable regulations. Waste gases are either collected in the gas surge header or filtered and released to the atmosphere via the gas collection header, depending on expected activity level. High activity gases are collected in the gas surge header and compressed into gas decay tanks. The waste gas held in the gas decay tanks is released to the plant vent after sampling. The tank contents are released at rates well within the limits

established by 10CFR20 and 10CFR50, Appendix I.

See Chapter 11 for further information.

1.2.2.9 General Arrangement of Major Structures and Equipment(DRN 03-2054, R14)The general arrangement of major structures and equipment is shown in Figures 1.2-3 through 1.2-25. (DRN 03-2054, R14)