ML20008D784

Chapter 10 to Midland 1 & 2 PSAR, Steam & Power Conversion Sys. Includes Revisions 1-36

ML20008D784
Person / Time
Site:	Midland
Issue date:	01/13/1969
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
References
NUDOCS 8007300691
Download: ML20008D784 (10)

Text

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i TABLE OF C0!; TENTS Section

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Face 10 STFE AND. g,EF C_0NVEFSION_SYSTDi 10-1 10.1 D_ESIGN BASES 10-1 10.1.1 C'ERATING AND PEFF0?!'ANCE RECUIPDfE :TS 10-1 10.1.2 ELECTPICAL SYSTD' CEAPACTEFISTICS 10-1 10.1.3 FUNCTICNAL LIMITATIONS 10-1 10.1.h SECCNDARY FUNCTICKS 10-1 1

10.2 SYSTD! DESIGN AND OPERATION 10-2 10.2.1 SCHD!ATIC FLOW DIAGRAM 10-2 10.2.2 CODES AND STMTARDS 10-2 10.2.3 DESIGN FEATUEES 10-3 10.2.h SHIELDING 10- 3 l

10.2.5 CORROSION FROTECT.mN 10- 3 10.2.6 IMPURITIES CONTROL 10- 3 i

j 10.2.7 RADI0 ACTIVITY 10- 3 10 3 SYSTD' ANALYSIS _

10-3 S

10.3.1 TRIPS, AUTOMATIC COIiTRO~ \\CTIONS, AND ALARMS 10-3 10.3.2 TRANSIENT CONDITIONS 10 h 10.3.3 MALFUNCTIONS 10- 5 10.3.h OVEFFRESSURE PFCTECTION 10-5 l

10.3.5 INTERACTIONS 10-5 l

l 10.h TEETS AND INSPECTIONS 10-5 i

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200'2300 r1 THIS DOCUMENT CONTAINS 10-1 P00R QUAUTY PAGES I

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I Figure No.

Title 10-l Piping & Instr =entation DiaPra: - Main Stea:

and Turbine Steam - Unit 2 25 10-2 Piping & Instrumentatien Diagra: - Feedwater &

Condensate Systems, Sheet 1 - Unit 2 10-2a Piping & Instru=entation Diagram - Feedwater &

Condensate Systems, Sheet 2 - Unit 2 j

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i 10-11 Amendment No. 25 2/74

10 STEAM AND PC'4ER CONVERSION SYSTE4 10.1 DESIGN RASE 10.1.1 CPGATING A'ID PERFOPl4A ICE RECUIRE4E'ITS The steam and po'..e conversion system for each unit vill be designed to convert heat energy from the reactor coolant to electrical energy.

Two steam generators vill be installed with a closed heater feedvater system utilizing extraction steam and returning the heated feedvater to the steam generators. Design of the entire system will be based on the maximum expected energy (2560 L't) from the nuclear steam supply system.

Upon loss of full load, the system vill dissipate all the energy existent or produced in the reactor coolant system through steam relief to the condenser and the atmosphere. The unit vill be designed to =aintain plant auxiliary load without a reactor trip on loss of full load. The steam by-pass to the condenser and atmospheric relief valves will be utilized as necessary to achieve this load reduction.

10.1.2 ELECTRICAL SYSTE4 CHARACTERISTICS The plant vill be designed for load-following operation. The =aximum rate of change of load is noted in 10.1.1 and 10.1.3 10.1.3 FUNCTIONAL LIMITATIONS The rate of change of reactor power vill be limited to values consistent with the characteristics of the reactor ecolant system and its control systems. These limitations in the reactor coolant system vill be reflected s

as functional limitations in the steam and power conversion syste=s.

The nuclear steam supply system vill follow load changes under automatic centrol as follows:

Increasing power transients between 20 and 90 per cent power are li=ited to ramp changes of 10 per cent per minute and step increases of 10 per cent. Power increases from 15 to 20 per cent and above 90 per cent are limited to 5 per cent per minuto.

Decreasing power transients between 100 and 15 per cent power are limited to ramp changes of 10 per cent per minute and step decreases of 10 per cent.

Under normal operating conditions and for loads belov 50 per cent, the turbine generator has limitations on ramp and step changes which limit the rate of load change to values less than those listed above.

The steam safety valves vill be sized to relieve 100 per cent steam flow.

10.1.h SECONDARY FUIiCTIOUS The steam and power conversion system vill provide steam for driving the two c0 per cent capacity feedvater pu=ps.

Steam vill also be used.for one 720 gal. e=ergency feedvater pump when recuired.

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The steam and pcver conversion is shcvn in Figure 10-1.

The closed cycle feedvater heaters vill be half-sice units (tvc parallel strings).

"eneration vill be acec=nlished in the ecndenser hetvell. A bypass of 15 per cent of full lead main steam fice to the ecndenser vill be provided.

Tvc cf the three One-half capacity condensate pumps and cendensate becster n.u=:s will be in normal use.

Each cf two feedvater.cu=-s vill be eC per cent P

capacity.

The ecndensate sur. r. l~J systen tcrether with the ecndenser hotvell vill previde a minimum of 200,003 gallens of condensate stcraze.

There vill be tvc (2) e=ergency feedvater pu=ps, each capable of delivering 1

720 gp: frc= condensate stcrage against the full steam pressure in the steam generators; cne vill be driven by a non-cendensing steam turbine, the Other vill be driven by an electric =cter.

These pu=ps will provide redundant means for emergency supply of feedvater to the steam generatcrs over the cceplete range of pressures until suitable ceaditiens are attained for trans-fer of the heat re=cval function to the decay heat syste=.

The =ctor driven pu=p vill be povered by the en-site diesel generators. Steam for the turbine drive vill ccte frc= the main steam line and exhaust to the condenser or at=csphere.

The main steam lines and the feedvater lines will be the only lines of the stea= an1 power conversien syste= vhich penetrate the Feactor Suilding.

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These lines can be isclated by the turbine step and governing valves and

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the feedvater line valving. Each of the branch lines leaving the main stea:

line before the main s:cp valves has valves to ec=plete the isolatien of a stea= generater. These lines supply a header vnich serves the fcileving:

a.

Stea= bypass, b.

Supply to the main feed pu=p turbines during periods of low load on the rain unit.

c.

Supply to emergency feed pump turbine, d.

Supply to the reheater cells.

The arrangement of the valving and parallel piping (shavn schematically in Figure 10-1) prevents blevdevn of bcth steam generaters frc= a single leak in the system.

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The turbine-generater equipment vill cenfer to the applicable USASI, ASME, and IEEE standards.

Tha design, materials, and details of ccnstructicn of the feedvater heaters vill be in accordance with both the ASME Code, Secticn VIII, "Unfired Pressure Vessels, and the " Standards of Feedvater Heater Manufacturers Asscciaticn, Inc."

The condenser equipment vill be in accordance with the Standards for Steam

[N Surface Ccndensers as tublished by the Heat Exchange Institute.

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The tanks associated with the steam and power conversion system vill be in accordance with the ASME Code,Section VIII.

10.2.3 DESIGN FEATURES The condenser air removal off-gas vill be continuously monitored and alarmed to indicate high radiation levels. The air removal off-gas will be released through the plant vent.

An auxiliary steam supply vill be avsilable frc= Units 1 or 2, and adequate capacity and pressure vill be provided. This supply vill be used during start-up to provide steam for sealing the turbines and for driving the feed-vater pu=p turbines. During shut-downs, it will provide steam as required.

10.2.h SHIELDING No radiation shielding vill be required for the components of the steam and power conversion system. Continuous access to the components of this system vill be possible during normal conditions.

10.2.5 CORROSION PROTECTION Hydrazine vill be added to the feedwater for oxygen control, and a=menia vill be used to =aintain the pH at the optimum value for the materials of construction for the system. No other additives are contemplated.

10.2.6 IMPURITIES CONTROL I= purities in the condensate of the stes and power conversion system vill be controlled by a polishing demineralizer. The makeup water to the steam and power conversion system vill be treated by a separate demineralizer.

10.2.7 RADI0 ACTIVITY Under normal operating conditions, there vill be no radioactive conta=inants present in the steam and power conversion system.

It is possible for this system to become contaminated only through steam generator tube leaks.

In this event, monitoring of the steam generator shell side sample points and the air removal off-gas will detect any contamination.

10.3 SYSTR4 ANALYSIS 10.3.1 TRIPS, AUTOMATIC CONTROL ACTIONS, AND ALARMS Trips, auto =atic control actions, and alar =s vill be initiated by deviations of system variables within the steam and power snversion system. In the case of autcmatic corrective action in the steam ard power conversion system, appropriate corrective sction vill be taken to protect the reactor coolant system. The more significant =alfunctions or faults which cause trips, automatic actions, or alarms in the steam and power conversion system are:

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10-3

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1 Valving in the feed-water system is provided to per=it bypassing the closed feed-water heaters in each train. Feec-vat.er regulator valves are provided en the supply lines to each stes. generator. Feed-water regulation is described 3

in Cection 7 1

Chemicals are added to the feel-vater headers downstrea= cf the condensate i

pu=ps for oxygen scavenging and pH control.

4 A condensate storage tank is prcvided for each unit. A condensate transfer pump is provided per tank to supply ecndensate =akeup to the various systems.

Autc=atic controls for =akeup to and reject frc= the condensers, =aintaining the condenser hot well levels, are provided.

The total flow of process returns, described previously, includes an allowance i

j for normal pri=ary and secondary syste= icsses in addition to replacement of the total process steam delivery.

l 10.2 5 CIRCUIATIIIG WATER SYSTEM Cooling water is stored in a cooling pond. The pond is enclosed by a dike.

Overflow spillways control the =axi=um pond elevation, and low-level gates provide for periodic blevdown discharge to the Tittabavassee River. Cooling pond makeup water is taken frc= the river during at least nine =enths of the year. The pond is sized to allow for all water losses frc= the pond, without makeup, during the three-=onth period when river flew is lov.

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Circulating water for the condensers is taken fro = the cooling pond.

Four vertical, vet pit circulating water pu=ps, two for each unit are installed 2

3ddacent to the screen vells frc= vhich they take suction. The circulation water piping is arranged in fcur parallel lines with one pu=p discharging through one line to one of the water boxes on the condensers. A chlorinat-ing facility is provided for algae and slime control.

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Two pumps on the north dike, adjacent to the river, provide for cooling pond makeup.

10 3 DESIGII EVAIUATIO!T f

All parts of this system are designed and fabricated in accordance with appli-

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cable codes. The ec=penents are similar to those which have experienced service in cperating power plants. Adequate protective devices and controls are provided to assure reliable and safe operation.

10 3 1 TRIPS AITD AUTCMATIC COITIROL ACTICIIS 25lIrips and autc=atic control actions are described in Sections 7.1.2.2.3 and 7.4 i

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10 3.3 MAlFUNC* IONS i

j The effects of inadvertent steam relief or steam bypass are covered by the analysis of the stea= line failure given in ik.l.2.9 ne effects of an

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inadvertent rapid throttle valve elesure are covered by the less of full i

load discussion in ik.1.2.8.

10.3.h OVIFFFISSL'RI ?? OTIC ION Pressure relief is required at the syste= design pressure of 1050 psig, and the first safety valve tank vill be set to relieve at this pressure.

The design pressure is based on the cperating pressure of 925 psia plus a 10 per cent allowance for transients and a k per cent allevance for blevdevn. Additional safety valve banks vill be set at pressures up to 1

1102.5 psig, as allowed by the AS'E Ccde.

T The pressure relief capacity will be such that the energy generated at the

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reactor high power level trip setting can be dissipated through this syste=.

10.3.5 INTERACTICNS Following a turbine trip, the centrol syste= vil] reduce reactor power output i==ediately.

The safety valves vill relieve exer ss stea= until the output is reduced to the point at which the steam bypass to the condenser can handle all the stes: generated.

In the event of failure of a single feedvate. pu=p, there vill be an i

autc=atic runback of the power de=and.

The one feedvater pu=p re=aining in service vill carry approxi=ately 60 per cent of full lead feedvater j

flow.

If both feedvater pu=ps fail, the turbine vill be tripped, and the e=ergency feedvater pu=p started. If reactor coolant syste= condi-i tions reach trip li=its, the reactor vill trip.

On failure of a condensate pu=p or condensate bcoster pu=p, the spare i

condensate pu=p or condensate bcoster pu=p vill be autc=atically started.

i 10.h TESTS AND INSPECTIONS l

As is essential in successful operation of any =cdern power plant, frequent functional operational checks vill be =ade en vital valves, control syste=s, s

and protective equip =ent.

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