ML16256A485
| ML16256A485 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/25/2016 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16256A115 | List:
|
| References | |
| W3F1-2016-0053 | |
| Download: ML16256A485 (19) | |
Text
WSES-FSAR-UNIT-3 10.3-1 Revision 14 (12/05)10.3 MAIN STEAM SUPPLY SYSTEM10.3.1 DESIGN BASES The Main Steam Supply System is designed to convey steam generated in the two steam generators, through the containment vessel in two separate lines, to the high pressure turbine and to other auxiliary equipment for power generation. It supplies steam to the high pressure turbine and to the moisture separator reheaters during normal plant operation, to the turbine gland seals during low load, and to the steam generator feedwater pump turbines during low loads or whenever low pressure steam is not sufficient. During normal conditions of operation, the steam generator feedwater pump turbines receive steam extracted from the moisture separator-reheater "B" outlet. During all conditions stated above, exhaust steam from the steam generator feedwater pump turbines flow to the main condenser via two 66
in. exhaust ducts. (DRN 03-2157, R13; 03-2064, R14)The Main Steam Supply System is designed to remove the heat generated in the Nuclear Steam Supply System (NSSS) during plant startup, hot standby, hot shutdown and normal cooldown, and to permit load reductions of up to full load. This last function is accomplished by means of the Steam Bypass System (SBS), in conjunction with Emergency Feedwater System (EFS) and/or main steam safety valves. The SBS is discussed in Subsection 10.4.4 and the EFS in Subsection 10.4.9. If a large rapid reduction in power demand occurs, the SBS bypasses steam to the condenser to prevent tripping of the reactor with the exception that there is a probability that the reactor may trip at power levels between 50% and 70% at certain times in core life (a trip is more probable at 70% power at Beginning of Cycle). In case the condenser is not available as a heat sink, e.g., high condenser back pressure caused by loss of
circulating water, the turbine bypass valves are blocked closed and steam is exhausted to the atmosphere through the atmospheric dump valves for decay heat removal. In addition, the Atmospheric Dump Valve (ADV) is also credited with safety related function of providing decay heat removal during a small break LOCA event. (Refer to Section 6.3) If the condenser is not available on large load reductions, the main steam safety relief valves will open. The design capacities of the safety valves are shown in Table 10.3-1. The total capacity of the safety valves is sufficient to pass 100 percent of the steam flow generated at rated load. The lowest setpoint of the safety valves on the main steam line from each steam generator is equal to the steam generator secondary side design pressure of 1100 psia minus the pressure drop between the steam generator and the safety valves, at full discharge condition.
When the safety valve with the highest setpoint is discharging at three percent accumulation, pressure does not exceed 1150 psia which is 110 percent of steam generator design pressure minus full lift and popping pressure tolerance, in accordance with ASME Code,Section III, Class 2 requirements. (DRN 03-2157, R13; 03-2064, R14)(DRN 00-1730) The main steam isolation valves (MSIV) are provided to isolate the steam generators from the remaining portions of the secondary system in the event of a loss of coolant accident or a main steam line break.
Detailed analyses of such accidents are provided in Chapter 15. Following the unlikely event of a main steam line rupture, the main steam isolation valves will close upon receipt of a main steam isolation signal (MSIS). The MSIVs are energized to close in a maximum of seven seconds. The MSIV hydraulic-
pneumatic actuators are provided with heaters and shields to ensure proper actuator operation during
periods of low ambient temperature or icing. (DRN 00-1730)
Pipe rupture criteria is discussed in Section 3.6.
WSES-FSAR-UNIT-3 10.3-2 Revision 307 (07/13)
The operators for MSIV are furnished with redundant hydraulic fluid dump valves powered by diverse power, to ensure that no single electric al failure will prevent isolation valv e closure. The trip circuitry for the main steam isolation valves is discussed in Se ction 7.3. The control and power circuits for the redundant equipment have been designed in accordance with the separation criteria as described in Section 8.3.
The Main Steam Supply System is also designed to provide an assured source of steam to operate the emergency feedwater pump turbine. The Emergency Feedwater System (EFS) operates in conjunction with the Main Steam Supply for decay heat removal.
EFS maintains the water level in steam generators and main steam regulates the rate of heat removal.
The main steam isolation signal (MSIS) is a part of the Engineered Safety Features Actuation System (ESFAS) and is described in Section 7.3. The ESFAS/MSIS conformance to safety criteria is described in Sections 7.1 and 7.3.
The design of the main steam line penetration a ssemblies is discussed in Subsection 3.8.2.
The main steam safety valves and main steam isol ation valves are designed to operate during a tornado, hurricane or offsite explosion. Environmental des ign bases and qualifications are discussed in Section 3.11. (DRN 00-786, R11-A)
The main steam piping (including flow elements, safety relief valves, at mospheric dump valves, and isolation valves for steam to the emergency feedwat er pump turbine) up to and including the main steam isolation valves outside the containment are safety-related and are designed to meet seismic Category I and ASME Section III Code Class 2 requirements (1971, up to and including Winter 1972 addenda). The
portion of the MSIV hydraulic act uator system required for valve closure is designed to ASME Class 2 requirements and the portions not required for closure are designed to ANSI B31.1 requirements, except that the isolation valve on the thermal relief valv e is not allowed per ANSI B31.1. However, adequate administrative controls are provided to insure that the relief valve set pressure is not exceeded, thus insuring equipment and personnel safety. Piping from ups tream of the isolation valves to the emergency feedwater pump turbine stop valve is designed to meet seismic Category I and ASME Section III Code Class 3 requirements (1971, up to and including Wi nter 1972 addenda). The remainder of the piping downstream of the isolation valves is classified as nonsafety-related piping and is designed to meet the requirements of ANSI B31.1 (1973). In addition, the main steam piping located downstream of the isolation valves to the end of Reactor Auxiliary Bu ilding (column line G) is designed to meet seismic Category I requirements.
(EC-41355, R307)Seismic Category I accumulators, sized for a minimum of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> operation, are provided for the
atmospheric dump valves, and associated EFS valves. Ten hours is consistent with the natural circulation cooldown analysis described in Section 9.3.
6.3.3. The valves can also be manually operated if required. Procedures are established for operating manual handwheel overrides or lining up backup air
supplies for continued safety function after the 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> mission time of the safety related Nitrogen Accumulator. Main steam isolation va lves operators are hydraulic-pneumantic. (EC-41355, R307)
All valves, except the main steam isolation valves , are fabricated and tested, such that in the closed position steam leakage in either direction past the va lve seats is not to exc eed the limits stated in MSS-SP-61 (1961). The main steam safety valves are test ed prior to installation to ensure that seat leakage through each valve does not exceed 65 lbs/
hr when tested on steam at 900 psig. (DRN 00-786, R11-A)
WSES-FSAR-UNIT-310.3-3Revision 11-A (02/02)
Other codes and standards used for designs and fabrications of components are AWS, IEEE, NEMA and OSHA.10.
3.2 DESCRIPTION
The Main Steam Supply System is shown schematically in Figure 10.2-4. The major components are two 40 in. main steam lines, one coming from each of the two steam generators and each provided with a flow
element, six main steam safety relief valves, one main steam isolation valve, and one atmospheric dump valve. The steam supply lines to the emergency feedwater pump turbine are taken from each main steam
line upstream of the main steam isolation valve.Plant startup is effected by means of the Condensate System operating in conjunction with the SBS. At low power levels, main steam is supplied to the steam generator feedwater pump turbines and the TurbineGland Seal System. At higher power levels, the steam supply to the steam generator feedwater pump turbines is transferred from main steam to the outlets of the moisture separator-reheater "B".The main steam lines carry the total steam flow from the steam generators. At maximum flow, a pressure drop of about 40 psi will not be exceeded. Each line is anchored to the flued head of the containment penetration and is routed to provide sufficient flexibility for movement due to thermal expansion of the steam generators and piping. At the turbine, each of the two main steam lines terminate into a common header which feeds the four admission inlets to the turbine. The high pressure turbine inlet has four automatic turbine stop valves and four governing-control valves. Branch connections on the main steam lines between theMSIV's and the turbine stop valves are provided to supply the moisture separator-reheaters, the Turbine
Gland Seal System and waste and boric acid concentrators as indicated in Table 10.3-5.(DRN 00-1730;00-786)
The main steam isolation valves are vertical gates designed with cylinder operators and are capable ofstopping steam flow in both directions against maximum expected differential pressure. Pressurized nitrogen is stored in the upper portion of the cylinder and hydraulic fluid in the lower portion. As an isolation valve, it is designed for tight shut-off and fast closing. The MSIV closure time, a maximum of seven
seconds, is controlled by the flow resistance through the redundant dump valves on the actuator, nitrogen pressure, and differential pressure across the valve discs. The seating velocity is not sufficient to cause significant loading of the disk. The energy required to close the valve is contained in the form of compressed nitrogen. This acts in the same manner as a mechanical spring with the added advantage of being able to monitor spring integrity, energy, and thus functionality. No energy exterior to the actuator is required to effect valve closure. The nitrogen is not consumed or vented from the actuator at any time. During normal plant operation, the main steam isolation valves are placed in remote-auto control. Each dump valve has two integral solenoids which are both simultaneously energized to close the MSIV. Redundant MSIS are provided to the dump valves of each MSIV from integral independent vital ac power supplies.(DRN 00-1730)
Either signal is adequate to cause a rapid closure of the MSIV by opening the respective dump valve andreleasing the hydraulic fluid. Main steam isolation valve configuration is shown in Figure 10.3-1.(DRN 02-90)
The spring loaded, dual outlet safety relief valves are all installed on the main lines upstream of the mainsteam isolation valves. The arrangement is such that a valve with lower setpoint is installed upstream of ahighersetpoint valve. The valves are a direct-acting, spring-loaded, double outlet design with an open yoke.
The design parameters are given in Table 10.3-1.(DRN 00-786; 02-90)
WSES-FSAR-UNIT-3 10.3-4 Revision 14 (12/05
)(DRN 00-786, R11-A; 02-90, R11-A) (DRN 00-786, R11-A; 02-90, R11-A)The arrangement of the two power operated atmospheric dump valves, provided in the main steam lines upstream of the main steam isolation valves, permits controlled release of steam for Reactor Coolant System cooling when the main steam isolation valves are closed. Isolation valves installed in two redundant main steam branch lines to the emergency feedwater pump turbine are normally closed. Safety Class 1E, 125V dc power from the A/B bus is supplied to the motor operated isolation valves. Piping downstream of these isolation valves to the emergency feedwater pump turbine is electrically heat traced (approximately twenty feet of pipe in the pipe chase is not heated). The purpose of the heat trace is to prevent standing water and to minimize the condensate load during start-up
of the turbine. 10.3.3 EVALUATION (DRN 03-2064, R14) Heat dissipation requirements during plant startup, hot shutdown, and cooldown are normally met by bypassing steam to the condenser via the turbine bypass system described in Subsection 10.3.1 and 10.4.4. If the bypass system is not available, the atmospheric dump valves are adequately sized (each valve is sized for five percent of the total throttle flow) to remove decay heat during plant cooldowns. In addition, the Atmospheric Dump Valve (ADV) is also credited with safety related function of providing decay heat removal during a small break LOCA event. (Refer to Section 6.3) The 60 percent capacity (of total throttle flow) SBS permits full load rejection, to house load, without reactor trip and without lifting of main steam safety valves. Failure of the SBS to function during turbine-reactor power mismatch will result in a reactor trip, causing the main steam pressure to rise. However, the main steam safety valves, which are adequately sized to permit load rejection from full power, will open and prevent pressure rise above
110 percent of the maximum allowable pressure for the steam generator. (DRN 03-2064, R14)
All safety-related components in the Main Steam Supply System are designed to perform their intended function in the normal and accident temperature, pressure, humidity, chemical, and radiation environment to which they will be subjected. Environmental design bases and qualifications are discussed in Section
3.11.The main steam isolation valves cannot be tested during normal operation without causing severe system transients. Therefore, they are provided with an exercise mode which allows the valves to be cycled from full open to 90 percent open and back to full open during power operation. This ensures that the valve stems are free to move in the event a rapid closure is required. Full-scale testing of the actuation system will be accomplished during scheduled plant shutdown periods. Redundant dump valves, controlling the hydraulic fluid for each MSIV, are provided so that the MSIV can remain operable with the failure of any one dump valve. Each dump valve is powered from a redundant dc power supply and has two integral solenoids both of which must be energized to open to drain hydraulic fluid from the lower portion of the
MSIV cylinder.
All ASME Code Class 2 and 3 main steam piping is furnished with removable insulation to allow inservice inspection of the welds.
Seismic and safety classifications and the analysis of postulated high energy line failure are presented in Section 3.2 and 3.6, respectively.
WSES-FSAR-UNIT-3 10.3-5 Revision 307 (07/13) 10.3.4 INSPECTION AND TESTING REQUIREMENTS
Inspection and testing, including hydrostatic tests and leakage tests, are performed for all valves at the manufacturers' shops in accordance with applicabl e codes. The Main Steam Supply System is hydrostatically tested in the field after in stallation in accordance with applicable codes.
The components are given preoperational and functional tests to ensure that they will perform in accordance with design. The closure times of the main steam isolation valves are determined during the preoperational test of the Main Steam Supply System. This is accomplished by measuring the elapsed time from the generation of a main steam isolation signal until the valve is closed. This test will be
repeated during the life of the unit. Preoperational testing is further discussed in Chapter 14.
During normal operation, the opening and closing of t he redundant solenoid valves for the MSIV can be performed for testing purposes.
10.3.5 WATER CHEMISTRY
10.3.5.1 Chemistry Control Basis
Steam generator secondary side water c hemistry control is accomplished by:
a) a close control of feedwater purity to limit the amount of impurities which can be introduced into the steam generator, b) a continuous blowdown of the steam generator to reduce the concentrating effects of the steam generator, and
c) chemical addition to establish and maintain an environment which minimizes system corrosion.
(EC-8465; R307)During normal plant operations, a continuous blowdow n of approximately 150 gpm per steam generator is maintained. Under abnormal operating conditions this rate may be increased to 405.7 gpm per steam generator. The actual blowdown rate will be determined by steam generator operating water chemistry
requirements. The blowdown can be proce ssed through or bypassed around the Blowdown Demineralizer System and returned to the condenser, or discharged to the Circulating Water System or
the Waterford 1 and 2 Waste Processing Facility. Ho wever, radioactivity will not be released to the Waterford 1 and 2 Waste Processing Facility.
(EC-8465; R307)
Secondary water chemistry is based on the zero solids treatment method. This method employs the use of volatile additives to maintain system pH and to scavenge dissolved oxygen present in the feedwater. (DRN 00-873, R11-A)
A neutralizing amine is added to establish and maintain alkaline conditions in the feed train. Although the amines are volatile and will not concentrate in t he steam generator, they will reach an equilibrium level which will establish an alkaline condition in the steam generator. Volatile chemicals are also added to scavenge dissolved oxygen present in the condensate and feedwater and to promote the formation of a protective oxide layer on metal surfaces by k eeping these layers in a reduced chemical state. (DRN 00-873, R11-A)
WSES-FSAR-UNIT-3 10.3-6 Revision 309 (06/16)
Both chemistry limits for the steam generator (secondar y side) and Feedwater System water are given in Tables 10.3-2 and 10.3-3. (DRN 00-873, R11-A, LBDCR 12-003, R309)
(DRN 00-873, R11-A, LBDCR 12-003, R309) 10.3.5.2 Corrosion C ontrol Effectiveness Alkaline conditions in the feed train and the st eam generator reduce general corrosion at elevated temperatures and decrease the release of soluble corrosion products from metal surfaces. These conditions promote the formation of a protective me tal oxide film and thus reduce the corrosion products released into the steam generator. (DRN 00-873, R11-A)
Chemical oxygen scavengers also promotes the formati on of a metal oxide film by the reduction of ferric oxide to magnetite. Magnetite prov ides an adhesive, protective layer on carbon steel surfaces. Ferric oxide may also be loosened from the metal surfaces and be transported by the feedwater. Chemical oxygen scavengers also promotes the formation of protective metal oxide layers on copper surfaces.
The removal of oxygen from the secondary water is also essential in reducing corrosion. Oxygen dissolved in water causes corrosion that can result in pitting of ferrous metals, particularly carbon steel.
Oxygen is removed from the steam cycle condensat e in the main condenser deaerating section.
Additional oxygen protection is obtained by chemical injection of chemical oxygen scavengers into the condensate stream. Maintaining a residual level of chemical oxygen scavengers in the feedwater ensures that any dissolved oxygen not removed by the main condenser is scavenged before it can enter the steam generator. (DRN 00-873, R11-A)
The presence of free hydroxide (OH) can cause rapid caustic stress corrosion if it is allowed to concentrate in a local area. Free hydroxide is avoided by maintaining proper pH control, and by minimizing impurity ingress into the steam generator.
Boric acid addition to the secondary cycle may be perfo rmed to mitigate the buildup of alkaline conditions in the steam generator crevices. T he presence of boric acid acts to dilute the hydroxide concentration and lower the crevice pH. The overall effect of boric acid addition is in the reduction of the rate of IGA/SCC. Additions will be monitored so that the specifications of Tables 10.3-2 and 10.3-3 are not exceeded.
WSES-FSAR-UNIT-310.3-7Revision 9 (12/97)Zero solids treatment is a control technique whereby both soluble and insoluble solids are excluded fromthe steam generator. This is accomplished by maintaining strict surveillance over the possible sources of feed train contamination (e.g., main condenser cooling water leakage, air inleakage and subsequent corrosion product generation). Solids are also excluded by injecting only volatile chemicals to establish conditions which reduce corrosion and, therefore, reduce the transport of corrosion products into the steam generator.In addition to minimizing the sources of contaminants entering the steam generator, continuous blowdown,described in Subsection 10.4.8, is employed to minimize their concentration. With the low solid levels which result from employing the above procedures, the accumulation of scale and deposits on steam generator heat transfer surfaces and internals is limited. Scale and deposit formations can alter the thermal hydraulic performance in local regions to such an extent that they create a mechanism which allows impurities to concentrate to high levels, and thus could possibly cause corrosion. Therefore, bylimiting the ingress of solids into the steam generator, the effect of this type of corrosion is reduced.Because they are volatile, the chemical additives will not concentrate in the steam generator, and do notrepresent chemical impurities which can themselves cause corrosion.10.3.5.3Chemistry Control Effects on Iodine PartitioningSystem design and operating practices are directed towards the goal of corrosion protection which at thesame time provides an excellent environment for the suppression of iodine emissions in steam.
Secondary water chemistry will suppress the formation of volatile species of iodine in the steam generators and convert volatile iodine that may be carried over via primary to secondary leakage to nonvolatile iodine compounds. As demonstrated in CE Topical Reports entitled "Iodine Decontamination Factors During PWR Steam Generation and Steam Venting" (References 1, 2 and 3), iodine carryover in the steam generators is a function of moisture separator performance.This report supports CE's position on iodine decontamination factors in CE designed and fabricated steamgenerating equipment. As a direct result of this work, steam generator iodine decontamination factors should not be lower than a value of 400 for design basis studies or less than 1000 for normal operation studies.10.3.5.4Secondary Water Chemistry Monitoring ProgramProcedures to implement an effective Secondary Water Chemistry Monitoring Program will be utilized atthe Waterford-3 Nuclear Plant. The main objective of the program is to maintain the integrity of the steam generator components and materials. Included in the program are the following:a)A sampling schedule for the critical secondary water chemistry parameters.b)Control specifications (points) for the critical secondary water chemistryparameters are established and results from sample analyses are compared to these specifications to determine if corrective action is necessary.
WSES-FSAR-UNIT-3 10.3-8 Revision 305 (11/11) c) Control point parameters will be analyzed in accordance with the procedure series CE-3-XXX.
d) Process sampling points are as follows:
- 1) Steam Generator Blowdown
- 2) Steam Generator Outlet
- 3) Condenser Hotwells
- 4) Condensate Pump Outlet
- 5) Feedwater Pump Inlet
- 6) Moisture Separator Shell Drain Tanks
- 7) High Pressure Heater Outlet
Figure 10.3-2 is a simplified schematic that demons trates the location of these process sampling points. e) Analytical data will be recorded and managed in accordance with approved
procedures.
f) Corrective actions for off-normal control point chemistry conditions are covered in the Operations Off-Normal procedures. The specific action taken will depend on
the particular off-normal parameter, the magnit ude of deviation and the cause of the condition.
Chemistry Technicians provide the fi rst line of review for data they generate. The Laboratory Supervisor and/ or C hemistry Engineer reviews all data and plots trends of analyses. The C hemistry Superintendent reviews data and trends randomly to determine if the requirements for collection and evaluating data are being met. This should eliminate necessity for most emergency action.
However, if an emergency occurs, such as a condenser leak, corrective action and responsibilit ies of all personnel are delineated in the abnormal operating procedures.
10.3.6 STEAM AND FEEDWATER SYSTEM MATERIALS
10.3.6.1 Fracture Toughness
Fracture toughness criteria as stated in the ASME Code Section III, Article NC-2300 and ND-2300, are fully complied with for Code Class 2 and 3 components.
10.3.6.2 Materials Selection and Fabrication
Materials used for Class 2 and 3 components of st eam and feedwater systems are primarily carbon steels listed in Appendix I to Section III of the ASME Code. Where austenitic stainless steel components are utilized, delta ferrite is controlled in accordance with Regulatory Guide 1.31, R3, "Control of Ferrite Content in Stainless Steel Weld Metal", RG 1.36 "N onmetallic Thermal Insulation for Austenitic Stainless Steel", is complied with.
For cleaning and handling of all ESF components, a ll recommendations of Regulatory Guide 1.37 "Quality Assurance Requirements for Cleaning of Fluid Systems and Associ ated Components of Water-Cooled Nuclear Power Plants" (March, 1973) and AN SI N45.2.1-73 "Cleaning of Fluid Systems and Associated Components for Nuclear Po wer Plants" are complied with. (EC-29980, R305)
With the exception of possible pi ping replacement with A335 P-11 or P-22, or SA335 P-11 or P-22, there is no low alloy steel utilized for any Class 2 or 3 component. Since Reg. Guide 1.50 "Control of Preheat Temperature for Welding of Low-Alloy Steel" only applie s to P Nos. 3, 4, and 5a, it is not applicable. (EC-29980, R305)
WSES-FSAR-UNIT-310.3-9Revision 10 (10/99)With the exception of Valve MS-407, there is no non-carbon steel utilized for any Class 2 or 3 component.Therefore, Regulatory Guide 1.71 "Welder Qualifications for Areas of Limited Accessibility" is not applicable except for this case where access exceeds the RG requirements. SECTION 10.3:REFERENCES1.J. A. Martucci, Iodine Decontamination Factors During PWR Steam Generation andSteam Venting, Topical Report CENPD-67, Revision 1, Nuclear Power Department, Combustion Engineering, November 1974.2.R.E. Mayer and E.R. D'Amaddio, Iodine Decontamination Factors During PWR SteamGeneration and Steam Venting, Topical Report CENPD-67, Revision 1, Addendum 1, Nuclear Power Department, Combustion Engineering, November 1974.3.Iodine Decontamination Factors During PWR Steam Generation and Steam Venting,Topical Report CENPD-67, Revision 1, Addendum 2, Nuclear Power Systems, Combustion Engineering, August 1975.
WSES-FSAR-UNIT-3TABLE 10.3-1Revision 9 (12/97)MAIN STEAM SUPPLY SYSTEMMAIN STEAM LINE SAFETY VALVESNumber of main steam lines2Number of valves per main steam line6 Total number of safety valves12Design Data for Valves in Each Main Steam LineValve No.Set PressureFlowLine #1Line #2(psig)(pounds/hr/valve)2MS-R613A2MS-R619B10701,426,9772MS-R614A2MS-R620B10851,446,718 2MS-R615A2MS-R621B11001,466,459 2MS-R616A2MS-R622B11151,486,200 2MS-R617A2MS-R623B11251,499,360 2MS-R618A2MS-R624B11351,512,521
__________Total Rated Flow (for each line)8,838,235 WSES-FSAR-UNIT-3 TABLE 10.3-2 Revision 11-B (06/02)STEAM GENERATOR BLOWDOWN CHEMISTRY LIMITSNormal SteamingNormalAbnormalVariableSpecifications (1)LimitspH 8.5 - 10.20Cation Conductivity (3) 1.0µmhos/cm1.0 - 4.0
µmhos/cm Sodium5 ppb5 - 50 ppbChloride10 ppb10 - 50 ppbSulfate10 ppb10 - 50 ppbBoric Acid< 10 ppm>
10 ppmWet LayupNormalVariableSpecificationspH9.8 - 10.5Hydrazine 75 - 500 ppm(DRN 01-1210)Carbohydrazide100 - 700 ppmDimethylamine (2)
Ammonia (2)(DRN 01-1210)Ethanolamine(2)Morpholine(2)
Boric Acid< 1 ppm Nitrogen (overpressure)Positive overpressure Sulfates<1.0 ppm Chloride<1.0 ppm Note:(1)Normal specifications are those which should be maintained by continuous steam generatorblowdown during proper operation of secondary systems.(2)As required to maintain pH within specified limits.
(3)When Ethanolamine or Morpholine is used to maintain pH, the Cation Conductivityspecification and limit do not apply due to the production of organic acids.
WSES-FSAR-UNIT-3 TABLE 10.3-3 Revision 10 (10/99)FEEDWATER OPERATING CHEMISTRY LIMITSNormal (1)VariableSpecificationsCation Conductivity (4) 0.2µmhos/cmDissolved Oxygen 5 ppbHydrazine (5)Ethanolamine (2)Morpholine (2)
Boric Acid (3)Sodium 0.15 ppbTotal Copper 1 ppbTotal Iron 5 ppbpH8.8 - 10.20 Note:(1)Normal specifications are those which should be maintained during properoperation of secondary systems.(2)As required to maintain pH within specified limits.(3)As required to inhibit and/or mitigate intergranular attack and provide adequate buffering action(based on present industry experience).(4)When Ethanolamine or Morpholine is used to maintain pH, Cation Conductivityspecification does not apply due to the production of organic acids.(5)Greater than 8 times the condensate dissolved oxygen value OR 20 ppb, which ever is higher.
WSES-FSAR-UNIT-3 Table 10.3-4 has been deleted.
WSES-FSAR-UNIT-3 TABLE 10.3-5 (Sheet 1 of 2)BRANCH CONNECTIONS BETWEEN MSIV'S AND TURBINE STOP VALVESNormalType ofSizeClosureSourceActuationMotiveQualityBranch-OffMax.Valve/ ofTime of ofMechanismor PowerGroupPipingSteam FlowNormalValve ValveActuating ofSource ofofDesignFunction (lbs/hr) Position (in.) (sec.) Signal Valve Valve Valve Code RemarksTwelve (12)500 eachTraps with2 -None - - DANSI(1) Only water (notMain SteamupstreamB31.1steam) is drainedDrain Linesmaintenance to the condenserThru TrapGlobe Valve Stations to/N.O.(2) Motor operatedthe Mainglobe valve bypass-Condensering trap stationsare normally closed.These valves openautomatically on high water level
and close auto-matically on lowwater level.Twenty eight (28)0Globe/N.C.2/1 -NoneHand -DANSIVent/Drain LinesB31.1to AtmosphereSteam Supply40,200Gate/N.O.215NoneMotorA.C.DANSISteam flow forLine toTotalB31.1this source isWaste andcontrolled auto-Boric Acidmatically by theConcentratorsdemand of theconcentrators.Steam Supply26,000Self reg-4 -NoneHand -DANSISelf regulatingto TurbineulatingB31.1control valveGlandsControlmaintains steamValve/N.O.supply to theturbine steamseal systemunder all conditions.Bypass around0Gate/N.C.430NoneMotorA.C.DANSIUsed duringthe aboveB3].lmaintenance ofSteam Glandthe normalSupplycontrol valve.Piping WSES-FSAR-UNIT-3 TABLE 10.3-5 (Sheet 2 of 2) Revision 307 (07/13)
BRANCH CONNECTIONS BETWEEN MSIV'S AND TURBINE STOP VALVES Normal Type of Size Closure Source Actuation Motive Quality Branch-Off Max. Valve/ of Time of of Mechanism or Power Group Piping Steam Flow Normal Valve Valve Actuating of Source of of Design Function (lbs/hr) Position (in.) (sec.) Signal Valve Valve Valve Code Remarks
Six (6) 0 Angle/Fail 10 20 - Diaphragm Air D ANSI Steam Bypass Turbine Close B31.1 System Controls Steam are designed to Bypass to maintained the Main pressure in the Condenser steam lines by modulating steam flow to the con-denser (see FSAR Subsections 10.4.4 and 15.1.1.3). (EC-8465, R307)Four (4) 1,178,152 Globe/N.O. 10 30 - Diaphragm Air D ANSI MS-R drain col- Heating Total B31.1 lector tank level Steam control valves Lines to (air operated, Moisture fail closed) located Separator downstream.
Reheaters (MS-R's) (EC-8465, R307)
Four (4) Included Globe/N.O. 3 5 - Diaphragm Air D ANSI Same as above.
Bypass Steam in above B31.1 Lines to MSR
Purging 0 Globe/N.C. 1 - - Motor AC D ANSI These valves open Lines B31.1 only during startup around the for warm-up purging.
MSR's
Startup 0 Turbine 4 - - Piston Oil D ANSI Used during startup Steam Stop and B31.1 only.
Supply to Control Steam Valve/N.C.
Generator
Feed Pump Turbine
MSR 0 Globe/N.C. 1 - - Hand - D ANSI Used during startup only.
Shutoff B31.1 Valve Leakoff Lines WSES-FSAR-UNIT-3Table 10.3-6Revision 6 (12/92)This Table Intentionally Deleted.
WSES-FSAR-UNIT-3Table 10.3-7Revision 6 (12/92)This Table Intentionally Deleted.
WSES-FSAR-UNIT-3Table 10.3-8Revision 6 (12/92)This Table Intentionally Deleted.
WSES-FSAR-UNIT-3Table 10.3-9Revision 6 (12/92)This Table Intentionally Deleted.