ML20154H551

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Proposed Tech Specs,Revising First Stage Turbine Pressure Setpoints Based on Test Data
ML20154H551
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 05/20/1988
From:
CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20154H547 List:
References
NUDOCS 8805250393
Download: ML20154H551 (5)
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Text

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.i g t LIMITING SAFETY SYSTEM SETTINGS BASES.

REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS (Continued)

8. Dr well Pressure-Hich High pressure in the drywell could indicate a break in the primary pressure boundary systems. The reactor is tripped in order to minimize the possibility of fuel damage and reduce the amount of energy being added to the coolant and to the primary containment. The trip setting was selected as low as possible without causing spurious trips.
9. Scram Discharge Volume Water Level-Hich

.. The scram discharge volunie rece'ives the water displaced by the motion of the control rod drive pistons during a reactor scram. Should this volume fill up to a point where there is insufficient volume to accept the displaced water

at pressures below 65 psig, control rod insertion would bo hindered. The reac-tor is therefore tripped when the water level has reached a point high enough.

to indicate that it is indeed filling ep, but the volume is still great enougn to accommodate the water from the movement of tM rods at pressures below 65 psig when they are tripped. The trip setpoint for each scram discharge volume is equivalent to a contained volume of approximately 24 gallons of water. J

(' m 10. Turbina Stop Valve-Closure

. The turbine stop valve closure trip anticipates the pressure, neutron flux, and heat flux increases that would result from closure of the stop valves. With a trip setting of 5% of valve closure free full open, the resultant increase in heat flux is such that adequate thermal sargins are maintained during the worst case transient. As indicated in Table 3.3.1-1, this function is automatically bypassed below the turbine first stage pressude value equivalent to thermal power less than 40% of RATED THERMA POWER.

eedwater The automatic bypass setpoint s3temperature dependent due to the subcooling changes that affect the turbine first stage pressure reactor power relation- l' ship. For RATED THERMAL POWER operation with feedwater temperature greater f than or equal to 420*F, an allowable ::t;:St :f 125 a*' ef ::-t ! v:!ve ti valueo]sig 218 p

  • pom turbine first stage pressure is provided for the bypass function. This e

' setpoint is also applicable to operation at less than RATED THERMAL NWER with as defined the correspondigly lower feedwater temperature. The allowable ::';:StJs Q t0 122. , 19cf%, - " " " "' ^^ ^- ' ; @;; f t ^^^a * = hine h t I in Tabl 3.3.1-1)ebetween._,_ g:::re forand 370*F RATED 420*F; THERMAE POWER 370*F and 320*F, operation and 320*F withrespectively.

and 250*F, a feedwater temperatu Similarly, the reduced setpoint is applicable to operation at less than RATED THERMAL POWER with the correspondingly lower feedwater temperature.

11. Turbine Control Valve Fast Closure, Trip 011 Pressure-Low

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The turbine control valve fast closure trip anticipate's the pressure, neutron flux, and heat flux increase that could result from fast closure of the PERRY - UNIT 1 B 2-9 ,

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LIMITING SAFETY SYSTEM SETTING

@Y BASES REACTOR. PROTECTION SYSTEM INSTRUMENTATION SETPOINTS (Continued) turbine control valves daa to load ejection with or without coincident failure of the turbine bypass valves. The Reactor Protection System initiates a trip when fast closure of the control valves is initiated by the fast acting sole-noid valves and in less than 20 mil 71 seconds after the start of control valve fast closure. This is n.hieved by the action of the fast acting solenoid valves in rapidly reducing hydraulic trip oil pressure at the main turbine control valve actuator disc dump valves. This loss of pressure is sensed by pressure switches whose contacts form the one-out-of-two twice logic input to the Reactor Protection System.. This trip setting, a slower closure time, and a different valve characteristic from that of the turbine stop valve, combine to produce transients which are very similar to that for the stop valve. Relevant tran-sient analyses are discussed in Section 15.2.2 of the Final Safety Analysis Report. A". with the Turbine Stop Valve-Closure, this function is also bypassed below 40% of RATED THERMAL POWER. The basis for the etpoint is identical to that described for the Turbine Stop Valve-Closure. nd rediIctifiiTof the ypassy setpoint due to reduced

12. Reactor Mode Switch Shutdown Position feedwater temperatures The reactor mode switch Shutdown position provides additional manual reactor trip capability.
13. Manual Scram The Manual Scram provides manual reactor trip capability. . The manual scram function is composed of four push button switches in a one-out-of-two i taken twice logic. '

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TAfsLE 3.3.1-1 (Continued) t REACTOR PROTECTION SYSTEM INSTRUMENTATION  !

l TABLE NOTATIONS ,

1 (a) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system i is monitoring that parameter.

(b) Unless adequate shutdown reargin has been demonstrated per Specifica- l tion 3.1.1 and the "one-rod-out" Refuel position interlock has been i demonstrated OPERABLE por Specification 3.9.1, the shorting links shall .

be removed from the RPS circuitry prior to and during the time any control I rod is withdrawn.*

(c) An APRM channel is inoperable if there are less than 2 LPRH inputs per i level or less than 14 LPRM inputs to an APRM channel. 1 (d) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

(e) This function shall be automatically bypassed when the reactor mode switch l is not in the Run position. l

(#) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required.

(g) With any control rod withdrawn. Not applicable to control rods removed I per Specification 3.9.10.1 or 3.9.10.2.

(h) This function is automatically bypassed when turbine first stage pressure is less than the value of turbine first stage pressure carresponding to 40%** of RATED THERMAL POWER.

  • Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
    • The initial setpoint--shall bc < 25.'% cf the celibrated : pan en-increasing turMne first-stage-pressure fir-AT ( cc 3/4.2.2 for-def4ni-t4onW'-Ft

<-H%-for-09-F<-AT < 50 F; < 18%-fee-60'- F < aT-4--100'-r-end-4-16%-for IOO*-F<-6F- +-900-F- The alTowable voitte-shall bi1-26-9%, 5 Y2.5%,110.5%,

e Q- s-6r6 QNespectively, I Reolace with insert 1.

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PERRY - UNIT 1 3/4 3-5

-- . 1 l

  • j Insart 1
    • The Turbine First Stage Pressure Bypass Setpoints and corresponding ,

Allovable Values are adjusted based on Feedvater temperatures (see 3/4.2.2 for definition of ZiT). The Setpoints and Allowable Values for various diTs are as follows:

T( F1 Setpoint (psig) Allovable Value (psig) 0 T < 212 < 218 0<adiT < 50

~

7 190 i 196 50 < tit < 100

~

i 168 I 174 100 < ZiT < 170 7 146 3152 I

TABLE 3.3.4.2-1 ,-

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION 4

c: MINIMUM 25

-" OPERABLECHANNE(j)

TRIP FUNCTION PER TRIP SYSTEM

1. Turbine Stop Valve - Closure 2(D)
2. Turbine Control Valve - Fast Closure 2(b)

(a)A trip system may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance (a provided that the other trip system is OPERABLE.

3 (b)This function is automatically bypassed when turbine first stage pressure is less than the value of turbine first stage pressure corresponding to 40%* of RATED THERMAL POWER.

t.o

  • The 4-fti:1 ::tpcint :hcli bc < 25.1% cf th: calibrated pen n "ner 9:ing turbine '# ret st:ge pressure fer AT (see

< AT < 100'F-r.nd 15% 3/4.2.2 fer 100" fer T<

definitien)

AT < 170^= 0"F.T, IIuwoLie The . velue shelT be <21% -fer 200" T<<AT 0%, < 50" T, < 10% fer 50" i 22.5%,

519.5%, end i 10.5% respect-iw4y-

  • The Turbine First Stage Pressure Bypass Setpoints and corresponding ,

Allovable Values are adjusted based on Feedvater temperatures (see 3/4.2.2 for definition of fit). The Setpoints and Allowable V&luas for various [iTs j are as follows:

T( Fl Setpoint (psig) Allovable Value (psig) 0- < 212 < 218 0 < a[ tit < 50 7 190 7 196 50 < /iT < 100 i 168 7 174

, 100 < ZiT f 170 3146 3152 i

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