ML19309C547
| ML19309C547 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 05/01/1967 |
| From: | JERSEY CENTRAL POWER & LIGHT CO., METROPOLITAN EDISON CO. |
| To: | |
| References | |
| NUDOCS 8004080744 | |
| Download: ML19309C547 (9) | |
Text
-. . ___ - - .-. ._
l l
- O '
~
\
O 4
4 t.
t I
\
O o o g, o o, 799 0001 220
TABLE OF CONTENTS Section P_ age 10 STEAM AND POWER CONVERSION SYSTEM 10-1 10.1 DESIGN BASES 10-1 10.1.1 OPERATING AND PERFORMANCE REQUIREMENTS 10-1 10.1.2 ELECTRICAL SYSTEM CHARACTERISTICS 10 -1 10 .1.3 FUNCTIONAL LIMITATIONS 10-1 10.1.k SECONDARY FUNCTIONS 10-1 10.2 SYSTEM DESIGN AND OPERATION 10-2 10.2.1 SCHEMATIC FLCW DIAGRAM 10-2 10.2.2 CODE AND STANDARDS 10-2 10 .2.3 DESIGN FEATURES 10-3 10.2.h SHIELDING 10-3 O 10.2 5 CORRCSION PROTECTION 10 -3 10 .2.6 IMPURITIES CONTROL 10-3 10 .2.7 RADI0 ACTIVITY 10-3 10.3 SYSTEM ANALYSIS 10-3 10.3.1 TRIPS, AUTOMATIC CONTROL ACTIONS, AND ALARMS 10-3 10.3.2 TRANSIENT CONDITIONS 10 h 10.3.3 MALFUNCTIONS 10-h
! 10.3.h OVERPRESSURE PROTECTION 10-5 10.3 5 INTERACTIONS 10-5 10.3.6 OPERATIONAL LIMITS 10- 5 10 k TE TS AND INSPECTIONS 10-5 0 .
10-1
>' LIST OF FIGURES O Figure No. Title steam and Power Consersion SY2t*5 l
O O '
{
0001zi2 10-11 t '
.v'
10 STEM 4 AND PCVER CCN7ERSICU SYS"'E4
( 10.1 DESIGN 3ASES 10.1.1 OPERATING AND PE3FCP.V.ANCE REQUIRE 4ENTS The steam and ;over conversion systa= vill be designed to convert heat energy frem the reactor coolast to electrical energy. Two steam gen-erators vill be utilized with a closed feedvater system condensing the steam and returning the heated feedvater to the steam generators. Design of the entire system vill be based on the maximum expected energy frem the nuclear steam supply system.
Upon loss of full lead, the system vill dissipate all the energy existent or produced in the reacter coolant system through steam relief to the condenser and the atmosphere. The unit vill be designed to maintain rtation auxiliary load without a reactor trip on loss of full lead. The steam by-pass to the condenser and atmospheric relief valves will be utilized as necessary to achieve this lead reduction.
10.1.2 ELECTRICAL SYSTE4 CHARACTERISTICS The station vill be designed for load following operatien. The maximum rate of change of load is noted in 10.1.1 and 10.1.3.
10.1.3 FUNCTIONAL LD4ITATICUS
( The rate of change of reactor power vill be limited to valves consistent with the characteristics of the reactor coolant system and its control systems.
These li=itations in the reacter ecolant system vill be reflected as functional li=itations in the steam and power conversion systems. The nuclear steam supply system vill follow lead changes under autcmatic control as follows:
Increasing power transients between 20 and 90 per cent power are limited !
to ra=p changes of 10 per cent per minute and step increases of 10 per cent.
Power increases above 90 per cent are limited to 5 per cent per minute.
Oecreasing power transients between 100 and 20 per cent power are limited i to ramp changes of 10 per cent per =inute and step decreases of 10 per cent.
The turbine generator has limitations on ramp and step changes which can further limit the above below 60% load.
The steam safety valves vill be si:ed to relieve 100 per cent steam flev.
10.1.h SECONDARY FUNCTICUS The steam and power conversion system vill provide steam for driving the l tvc 60 per cent capacity feedvater pumps. Steam vill also be used for the -
emergency feedvater pumps when required.
l 3e ,
10-1 (Fevised 1-6-68) 00i2231 1
10.2 SYSTE4 DESIG:I A'ID CPEP.ATION 10.2.1 SCHE 4ATIC FLOW DIAGRAM The steem and power conversien syste= is shown in Figure 10-1. S e cicsed cycle feedvater heaters will be half-si:e units (two parallel strings).
Deaeration vill be accc=plished in the condenser hotvell. A bypass of 15 per cent o' "" 'oad main steam flow to the condenser vill be provided.
Two of the three one-half capacity condensate pu=p? and condensate booster pu=ps vill be in nor=al use. Each of two feedvater pumps vill be 60 per cent capacity.
There vill be a total of ten =inutes condensate stcrase at full lead in the condenser hetvells. Se eccdensate storage tank together with the condenser hotvell vill provide a =in1=u= of 365,000 gallens of condensate stcrage.
l There vill also be two, turbine driven. emergency feedvater r. umps which take suction directly fren the hotvell cr condensate storare tank and nu. p to the stem renersters. Stesn for the turbine drive vill ec=e from the main sten:
line and exhaust to atmosehere.
l "'he main steam lines and the feedvater lines vill be the only lines of the stes= and power conversion system which penetrate the Reacter Building.
l These lines can be isolated by the steam generator stop valves and the feedvater line valving. Sach of the lines leaving the main steam line before the main stop valves has valves to cc=plete the isolation of a steam generator. These lines are:
- a. Steam bypass.
- b. Supply to feed pu=p turbines.
- c. Supply to emergency feed pu=p "rbine.
The arrange =ent of the valving and parallel piping shown sche =atically in Figure 10-1 prevents blevdown of both steam generators frc= a single leak in the system.
10.2.2 CODES A:O STA:CAROS The turbine-generator equipment will confor= to the applicable ASA, ASME, and I N standards.
The design, =aterials, and details of construction of the feedvater heaters vill be in accordance with both the ASME Code,Section VIII, Unfired Pressure i
1 Vassels and the Standards of Feedvater Heater Manufacturers Association, Inc.
1 i
The condenser equipment vill be in accordance with the Standards for Steam Surface Condensers as published by the Heat Exchange Institute.
The ta=ks associated with the stes= and power conversien system vill be in accordance with the ASME Code,Section VIII.
O 10-2 (Pevised 1-8-oS)
10 .2 3 EESIGN FEATL" DES
/
The condenser air removal off-gas will be continuously monitored with an ' alar =
to indicate high radiation levels. The air removal off-gas vill be released thrc, ugh the station vent.
An oil fired auxiliary steam generator of adequate capacity and pressure vill be provided. This boiler vill be used only during start-up to provide steam for sealing the turbines and for driving the feedwater pump turbines. During shut-downs , it will provide steam as required for =aintenance procedures requi ing decontamination. "
10 . 2. h SHIELDING No radiation shielding vill be required for the components of the steam and power conversion system. Continuous access to the ca::ponents of this system vill be possible during nomal conditiens.
10 .2.5 CORROSION FROTECTION Hydrazone vill be added to the feedvater for oxygen control, and ammonia vill be used to maintain the pH at the optimum value for the materials of construct for the system. No other additives are contemplated.
10.2.6 IMPURIT!'S CONTROL Impurities in the steam and power conversion system vill be controlled by a polishing demineralizer sized for at least one-half flev. The makeup water to the steam and power conversion system vill be treated by a separate demin-eralizer.
10 .2*.7 RADI0 ACTIVITY Under normal operating conditions , there vill be no radioactive contaminants present in the steam and power conversion system. It is possible for this system to beccme conta::inated 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 SYSTEM ANALYSIS 10 . 3.1 TRIPS, AUTOMATIC CONTROL ACTIONS, AND ALARMS Trips , autcmatic control actions , and alarms vill be initiated by deviations of system variables within the steam and power conversion system. In the case of automatic corrective action in the steam and ppver conversion system, i appropriate corrective action vill be taken to protect the reactor coolant i syste=. The more significant =alfunctions or faults which cause trips ,
autcmatic actions , or alams in the steam and power conversion system are: i
- a. Turbine Trips l
- 1. Generator / electrical faults.
im qq<,
,, 10-3 0001725'
~
L _
- 3. Thrust bearing wear.
- h. Loss of both feedvater pu=ps.
l 5 Turbine overspeed.
- 6. Reactor trip.
- b. Autcmatic Control Actions
- 1. Feedvater flow lagging feedvater demand results in a reduction in pcVer demand.
- 2. Lov feedvater temperature results in a reduction in pcuer demand.
- 3. High level in steam generator results in a reduction in feedvater flow,
- b. Lcv level in steam generator results in an increase in feedvater flev.
- c. Principal Alarms l 1. Lev pressure at feedvater pump suction.
- 2. Lov vacuum in condenser.
3 Lov vater level in condenser hoc.all.
l h. High water level in condenser hotwell.
l 5 High water level in steam generator.
l
- 6. Lov vater level in steam generator.
7 High pressure in steam generator.
- 8. Lov pressure in steam generator.
9 Lev feedvater temperature.
10 .3.2 TRANSIEllT CONDITIONS l The analysis of the effects of loss of full load on the reactor coolant l
system in discussed in 14.1.2.8. Analysis of the effects or partial less of load en the reactor coolant system is discussed in 7.2.3.h.
10 .3.3 MALFUNCTIONS The effects of inadvertent steam relief or steam bypass are covered by the analysis of the steam line failure given in ik.1.2 9 The effects of an inadvertent rapid throttle valve closure are covered by the loss of PLll load discussion in 14.1.2.8.
9 '
4 t
10 . 3. h OVERPRE3SURE PROTECTION Pressure relief is required at the system design pressure of 1050 psig, and the first safety valve bank vill be set to relieve at this pressure.
The design pressure is based on the operating pressure of 925 psia plus a 10 per cent allowance for transients and a h per cent allowance for blevdown. Additional safety valve banks vill be set at pressures up to 110k psig, as allowed by tne ASME Code.
The pressure relief capacity will be s2ch that the energy generated at the reactor high power level trip setting can be dissipated through this system.
10 .3.5 INTERACTIONS Following a turbine trip, the control system vill reduce reactor power output i= mediately. The safety valves vill relieve excess steam until the output is reduced to the point at which the steam bypass to the cendenser can handle all the steem generated.
In the event of failure of a single feedvater pump, there vill be an autcmatic runback of the power demand. The one feedvater ptmp remaining .
in service vill carry approximately 60 per cent of full load feedvater l flow. If both feedvater pumps fail, the turbine vill be tripped, and 1 the emergency feedvater pump started. If reactor coolant system condi- I tions reach trip limits, the reactor vill trip.
On failure of a condensate pump or condensate bocster pump the spare I condensate pump or condensate booster pump will be autcmatically started.
10.3.6 OPERATIONAL LIMITS The air renoval off-gas will be monitored for radioactivity, and safe operating limits vill be established for the station.
- 10. k TESTS AND INSPECTIONS As is essential in successful operation of any modern pcver station, frequent functional operational checks vill be made on vital valves , cent,rol systems ,
and protective equi;nent.
l O 0001 n7 10-5
N
.w
(~" 2. 2 . ~-
- ~
-lI ll l
l r -
5 !- !
Ii n- w L* :
_-r a! : '
Is !l
- i
': .ji -. b
.p S. ,
d,r 7r L,'=b.
II I r
lljj ;-
- ' 9. . . :
- i:
-t- .
( gi * !!i I.!'i -
.-s fa 2,= sli'i; _'
( ,.I
'_m
~, .Jili! , 1, p'l esie y!
, li.
p:
~
n-i
.r r, id.:.i.l
. : g.
i
/
iii-i c
!jl ; lN 8i NI I
- ! 3 i
a __ ! 1s, ,
to pd 't .i
. =Lw-=
\' 51 ey
- p.
r_
ilt-w v, e, ,
3 ,
l j j
, i
-i.p!
s
. , i.
Ii .!:
p -
-i I ' l_. ,,
i: i-
- l y;briri'n.4
. a. -y 11 -
i.: > ii l! *!! . . -
.-l u l
. i si i i t t -j i
.i 4e4 F1, tt t;- , ,
l '
d 6} le ij=l l!' !I c:..
i u , ::
i --- - l
'L
. i{
, ;l-li sig
- igg 5q,: E t >
E =
'1 li'
-),
% ! H:
'll ii 2 T)
-l oi ;
e -
=
0001 <,
\
C ,,
l r f: ' . ti5 l
i i..;'g=;;. - t Jl, f } .t' t j s 'l?3
-a i( t . - cr - -
I - ;:; ,
,; ,i i
a y