Text

Proposed Tech Specs Re Steam Generator Level Reactor Trip Mod
	ML20154A147
Person / Time
Site:	Callaway
Issue date:	08/30/1988
From:	; UNION ELECTRIC CO.
To:	;
Shared Package
ML19297G891	List: ML20154A112; ML20154A129; ML20154A138; ML20154A147; ML20154A160;
References
	ULNRC-1822, NUDOCS 8809120090
	Download: ML20154A147 (77)
	v • d • e

..

.. 5 t

Attcchment -4 ULNRC-18 22 TECllNICAL SPECIFICATION CIIANGES STEAM GENERATOR LEVEL _ REACTOR TRIP _ MODIFICATION Yabic 2.2-1 page 3-5 Incert A Table 3.3-1 pages 3/4 3-3, 6, 6a Ir.ser ts B, C, D Table 3.3-2 page 3/4'3-8 Insert E Table 4.3-1 page 3/4 3-10 Insert F Table 3.3-3 pages 3/4 3-17, 18, 21 Inserts G, H, I Table 3.3-4 page 3/4 3-25 Inserts J, K Table 3.3-5 pages 3/4 3-31, 32a Table 4.3-2 page 3/4 3-36 Insert L Bases page B 2-7

Insert M GG09120090 scosso PDR ADOCK 05000483 P PDC ,

e TABLE 2.2-1 (Continued) h REACTOR TRIP SYSTEM' INSTRUMENTATION TRIP SETPOINTS C

g TOTAL SENSOR ERROR

< tur4Cf10NAt UNIT ALLOWANCE (TA) Z Q TRIP SETPOINT ALLOWABLE VALUE

[ 13. Sim R.a.eter Uster 23.5 21.10 2.0 123. 5% ef .-. . - 122. 0% of .-. . -

Z i a.;T La-La fggy f 727^^ ' ^' t,- - n t ? ?~; ' ni t ~ ^ -- t a ;:n 1;r-r

14. Undervoltage - Reactor 7.7 1.33 0 11GS84 Volts A.C 110356 Volts A.C.

Ccolant Pumps

.$. Undertrequency - Reactor 3.3 0 0 137.2 Hz 157.1 H:

Coolant Pumps

16. L.st,ine irip

4. 1o., Fluid 011 Pressure N.A. N.A. N.A. 1598.94 psig 1539.42 psig e ,. b. Turbine Stop Valve N.A. N.A. N.A. 11% open >1% open u- Closure -

17. Safety Injectiun input N.A. N.A. N.A. N.A. M.A.

from ESF .

d 2

fra

<~

O 2'

e ,4 e

L _- . _- .

INSERT A CN TAE E 2.i-1 TOIAL SENSOR ALIB4A)CE ETSOR

,JU.NQllCNAL 1: Int (TA) Z (S) TRLP SETM!g g,LOWABLE VAIL 5

13. Ftaan Cteerator Water I m l-Low :cw

a. Vesse; Delta-T Egalv11ent i10%iTP TasselDestaT(Power 1) 6.0 2.3.8 2.0 IVesselDeltaT $VesselDeltaT Eq'21 valent to 10% FAphalect to 14.0%

MP UP CoirAcent with Steam Generator Water Level 20.2 17 58 2.0 220.2%ofNarrev 218.4%ofNarrow It/. Lov (Mverse Containment Range Instrucent Span Range Instruent Environe:nt) Span and Containrent Pressure - 3.3 0.71 2.0 11.5psig 52.3psig Environn ntal Allevance RMifict OR Stean Generater Water Level 14.8 12.18 2.0 214.8%ofNarrev 213.0 % d Narrow low-Icv (E) tral Containent Rar,e lastrtrent RangeInstrurent Envirentent) Sran Span With a fire Delay, (t) $232 seconds 1240secor.ds

b. 10% FTP < Vessel Onita-T Iq11valenti20%RTP Vess*1 Delta T (Pcvar-2) 6.0 2.34 2.0 $VesselCaltaT ! Vessel Nlta T Squivalent to 20 % Fq11 valent to 24.0 %

RTP RTP Cotacident with SteamGenerderWaterI,evel 20.2 17.M J.0 220.2%cfNtrrev ! 18.4 % of Narrov ,

low Icv (Mverse Containtant Range Instrurs t RangeIns'.rurent D:virer. rent) Spc Span Ard Centainr+nt Pressure- 3.3 0.71 2,0 11.5psig i2.3psig E.wirontental Allevance WMifter OR Stein Centra'wr Water Level 14.R 12.1% 2.0 214.8 % of Warrew 213.0%ofNarrow lev-[tv (nitral Centainrent FangeInstrurent RangeInstrerent Environrent) Stan Spin With a Tir.e Dalay, (t) $122secovis ! 130 samnds

f INSERT A ON TABLE 2.2-1 (Cont.)

TOTAL SENTR ALIDAKE ERROR (TA) Z (S) TRIP SETPOINT ALi& ABLE VALUE l _

FORTIONAL UNIT

c. Vessel Delta-T Eq11 valent > 10% RTP l

Coincident with Steaa Generator Water Level 20.2 17.58 2.0 220.2%ofNarrev 218.4%ofNarrev f

Range Instrurent Range Instrurent Low-tov (Adverse Containt.ent Enytronrnt) Spin Span And Containrent Pressure - 3.3 0.71 2.0 11.5pulg i2.3psig ;,

Environrenta.' Allevance Modifier OR SteasGeneratorWaterLevel 14.8 12.18 2.0 214.8%ofNarrev 2 13.0 % of krrev Range instrurent Fange Instrurent Low-Lev % real Containrent Span Span E:r<1tontent) l l

. . - . - . - = - . _ _ . . . . . - _ . - _ - - _ _ _ _ - _ -

TABLE 3.3-1 (Continued) o

)~ REACTOR TRIP SYSTEM INSTRUMENTATION 5 MINIMUM SE

-' TOTAL NO. CitANNELS CilANNELS APPLICABLE FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE H00ES ACTION E

11. 3 2 2 1 6#

1 Pressurtzer Water tevel-liigh l e

12. Reactor Coolant flow-Low

a. Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1 6# l any oper- each oper-ating loop ating loop

b. Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1 6# l below P-8) two oper- each oper-ating loops ating loop t 13. ', t _

_ .m . e te. '.Je te .- 4/31 . g;.. 2/31.;;. g... 2/; L.. g... ~ 1, 2 O'1) I E ,- } - -

^

[

L a l L " Lo- fyggg f ....., ..-.

'f. . ,..-.

!: g^

~

P -9**r

14. Undervoltage-Reactor Coolant 4-2/ bus 2-1/ bus 3 1 Pumps 6#(1) l

15. Underfrequency-Reactor Coolant Pumps 4-2/ bus 2-1/ bus 3 1 6#

16. Turbine Trip Low fluid Oil Pressure 2 6# j

{

a.

b. Turbine Stop Valve Closure 3

4 2

4 1 1

1 11#

E 2 17. Safety Injection Input 2 1 2 1, 2 9 a from ESF E

s e

4

MINIML3 TOTAL NO. CHANNELS CHANNELS FUNCTIONAL' UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

13. Steam Generator Vater Level-w .;ow

a. Steam Generator Vater Leve.1- 4/stm. gen. 2/stm. gen. in 3/stm. gen. each 1,2 6 # (1), 7 Iow-Low (Adverse Containment any operating ooerating stm.

Environment) stm. gen. gen.

b. Steam Generator Vater Level- 4/stm. gen. 2/stm. gen. in 3/stm. gen. each 1,2 7, 13 # (1)

Iow-Low (Normal Containment any operating operating stm.

Environment) stm. gen. gen.

c. Vessel Delta-T 4 2 3 1,2 11 # (1) h (Power-1, Po;ter-2) y e

d. Containment Pressure - 4 2 3 1,2 11 # (1) 08 i Environmental Allowance @

Modifier g l

l N e

t:1

?

Y I

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.

ACTION 5 - a. With the nudar of OPERABLE channels one less than the Minimum Channels OPERABLE requirertent, restore the in-operable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor trip braakers, suspend all cperations involving positive reactivity changes and verify Valves BG-V178 and BG-V601 are closed and secured in position within the next hour,

b. With no channels OPERABLE, open the Reactor Trip Breakers, suspend all operations involving positive reactivity changes and verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter, and verify valves BG-V178 and BG-V601 are closed and secured in position within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and verified to be closed and secured in position every 14 days.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and l

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months l for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 - hkt:d. TMTE#7 C l ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 10 - With the numcer of OPERABLE channels one less than the Minimum Channels 0PERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor trip breakers within the next hour.

ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inocerable enannels are placed in the tripped conoition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l CALLAWAY UNIT 1 3/4 3-5 Amend nent No. U

r INSERT C ON TABLE 3.3-1 ACTION 7 - With an inoperable delay timer in the Trip Time Delay ,

circuitry, STARTUP and/or POWER OPERATION may proceed provided that the Vessel Delta-T (Power-1, Power-2) channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

. . - . . . . . . . . . . . . . . . . . ...s .. . . . . . . . . .

l l

TABLE 3.3-1 (Continued)

J ACTION STATEHENTS (Continued) I 1

ACTION 12 - With one of the diverse trip features (Uncervoltage or Shunt I Trip Attach:r.ent) icoperable, restore it- to OPERABLi statt.s within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the affected br. raker inoperable and apply ACTION 9. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time ;

required for performing maintenance to restore the breaker t'o l

OPERABLE status.

A CTI4N /3 - % NSEA7~ O ,

I I

1 4

I

.I i

n CALLAWAY - UNIT 1 1/.4 3 64 Amencment No. 19 1

\ <

1

.. . ._ _ . ,r.

.;.... -, q . 7,,

.. y .

,7

. 4 . . . .,. j ,_ . _ _

c d

y: ,

m INSERT D ON TABLE 3.3-1 I

4

. ACTION 13- With the number of OPERABLE channels less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that the Containment

.. Pressure-Environmental Allowance Modifier channels in 5' '

the affected protection sets are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , l

i I

I L

i i

1

~

s d

I i

1,,,

i 3

i 6

1 i

i e

l 1~

- - . - . - = . , _ , . - . . . . , .

TABLE 3.3-2'(Continued) 9 r- REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES .

E a E b FUNCTIONAL UNIT RESPONSE TIME

]

E 12. Reactor Coolant Flow-Low "a

- a. Single Loop (Above P-8) -

i 1.0 secoert

b. Two Loops (Above P-7 and below P-8) i 1.0 second .

13. C';= 'ai. 22: 22: * .;1 ' u Lu ' :.: u; - 2 ZNSEXT E

14. Undervoltage-Reactor Coolant Pumps i 1.5 seconds

15. Underfrequency-Reactor Coolant Piamps 5 0.6 second

16. Turbine Trip 1 a. Low Fluid Oil Pressure M.A. -

.y b. Turbine Stop Valve Closure -

N.A.

se *

17. Safety Injection Imput from ESF M.A.

18. Reactor Trip Systen Interlocks N.A.

19. Reacter Trip Breakers N.A.

20. Automatic Trip and Interlock Logic N.A.

fT1

<~

O 2:

. e-.

. e

.4

%.w &

I INSERT E ON TABLE 3.3-2 FUNCTIONAL UNIT _ RESPONSE TIME :

I 13. Steam Generator Water Level-Low-Low I ,

a. Steam Generator Water Level-Low-Low 5 2.0 seconds (1) i j (Adverse. Containment Environment) l Steam Generator Water Level-Low-Low 5 2.0 seconds (1) j b.

l (Normal Containment Environment) 4

c. Vessel Delta-T $ 6.0 seconds (1)

(Power-1, Power-2) i e

d. Containment Pressure - 5 2.0 seconds (1) 3 Environmental Allowance Modifier [

i 1

j (1) Does not include Trip Time Delays. Response times !

noted above include the transmitters, 7300 process l l '

protection cabinets, solid state protection cabinets, '

! and actuation devices only. This reflects the 4 response times necessary for THERMAL POWER An excess l

of 20% RATED THERMAL POWER.

< E j l l I

! r t

i

! i

1 1

I i l l

4 i r

i l J i i l i t

TABLE 4.3-1 (Continued) h REACTOR 1 RIP SYSTEN INSTRUNENTATION SURVEILLANCE REQUIRENENTS C

ff TRIP ACIDATING N00ES FOR ANALOG

CilANNEL DEVICE WillCH E CHANNEL CllANNEL OPERATIONAL OPERATIONAL ACTUATICN SURVEILLANCE y FUNCTIONA1 UNIT CllECK CALIBRATION TEST IFST LOGIC TEST 15 REQUIRED

13. 1 L.-. 6.- Lie .- L .. ; 5 2 Q(14,l' ) X.A. %.A. 1, 2 ZNSEXT F

14. Umlervoltage - Reactor Coolant N.A. R N.A. Q(14,15) N.A. 1 l Pumps

15. Underfrequency - Reactor N.A. R N.A. Q(14) N.A. 1 Coolant Pumps o 16. Turbine Trip

4. Low fluid Oil Pressure N.A. R N.A. S/U(1, 10) N.A. 1

b. Turbine Stop Valwe M.A. R N.A. S/U(1, 10) N.A. 1

Closure s II. Safety Injection Input from W.A. N.A. N.A. R# N.A. 1, 2 ESE -

l

18. Reactor I.-ip System Interlocks

a. Intermediate Range Neutron flux, P-6 N.A. R(4) R N.A. N.A. 2##

i l b. Power Range Neutron i

g IIux, P-8 N.A. R(4) R N.A. N.A. 1

% c. Power Ram.;e Neutron 9 fIux, P-9 N=A. R(4) R N.A. N.A. 1 e

E N

)

-t----g-we e -w- ,vv-w- 7v v w w -ww w wy w--*- - wv m -w e mww - - - - - - - - - - 1-- - - .wr-----' w-- -----==w 7 T-w -%- w -r-- - - - - - - - - , -

= - . .-

TPIP MODES FOR AN! DOG ACT. '. TING VHICH CHANNEL DEVICE SURVEILIANCE CHANNEL CHANNEL OPERATIONAL OPERATIONAL AC"IVATION IS FIXTIONAL INIT CHECK CALIBRATIO_N _"IT.ST TEST IDGIC TEST REQUIRED

13. Steam Generator Water Level-Lcas-Low l l

a. Steas Generator Vater S R Q (14,25) N.A. N.A. 1,2 l Level-Low-Im ( Adverse i Contain=ent Environment)

b. Steas Generator Watur S R Q (14,15) N.A. N.A. 1,2 E Ievel-Im-Im (Normal $

Containment Environment) N m

> c Vessel L*. elta-T S R Q (14,t.5) N.A. N.A. 1,2 o I (Pomer-1, fewer-2) a t >

d. Cont.ninoent Pressure- S R Q (14,15) N.A. N.A. 1,2 E m

Environmental Allo.cance v Ndifier w b

l

.- ,a n ,

~'

( )

TA8LE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SY9 EM IX51RUMENTATION n

.? MINIMUM . ,

q CHANNELS APPLICA3LE f

TOTAL NO.

Of CHANNELS CHANNELS TO TRIP OPERABLE MODES ACTION .'

FUNCTIONAL _UN_IT E 'i . Feco-ater isolation & Turtaine Trip .-

2 1, 2 J'

4. Automatic actuation 2 1 togic and Actuation Ralay (55PS) 7/sta. gen. 3/sta. gen. 1, 2 19*

ts. Steam Generator 4/sta. gen.

Wster Level- in any oper- in each of4P ating sta gen. ating sta.

High-Higt gen. ,

c. Safety injection Sae Ites 1. above for all Safety -Injection initiating (ue2tions --

w and requirements,

)

y 6. Anthary feeduater

a. Manual Initiation 3(1/ pump) 1/ pump 1/ pump 1. 2. 3 24 Automatic Actuatios's Logic 2 l 2 .1, 2, 3 21 ts.

and Actuettw Relays ($$PS) - --

c. Autoutic Acta.ation Logic ,

and Actuation Relays 2 1 2 1.2.3 21 (80P E5FAS)

ar try J

d. Steam Generate Water < .

Level- Low-Law %

_rNTEfr G 2 n.-

g n . . - -

. . . . . .. :/>=. m ..z :/; =. s . 3/:e. j . :., 2. : n-

= =; # z. m. -

Sn,'M W;Y 5 4 N

-gen:- 15. m .. .

.- , . _ , _ _ _ -.,,v, y-,m- -.>--y -,p . , - - - - . - - . , . . - - , , ,,y ,,,, ,e. m-- .--,.m9 - - , - -

y-,, , , , - , ,

MINIMUM

~TTTAL NO. CHANNELS CHANNELS FLNCTIONAL UNIT OF CHANNEL _S TO TRIP OPERABLE _ M7 DSS ACTION 6.d. Steam "ienerator Water Level-Iow-Low

1) Start Motor-Driven Pumps a) Stear. Generator Water Level- 4/stm. gen. 2/stm. gen. in 3/stm. gen. cach 1,2,3 19*,27(a)

Low-Im (Adverse Centainment any op-rating opersting stm.

Environment) stm. gen. gen.

b) Steam Cenerator Vater Level- 4/stm. gen. 2/stm. gen. in 3/stm. gen. each 1,2,3 27(a),27(b)*

Low-Low (Normal Containicent any operating operating stm.

Environment) stm. gen. gen. E un c) Vesse' Irelts.-T 4 2 3 1,2,3 27 (c)*

J, Power-1, Power-2) o o

d) Containment Pressure- 4 2 .* 1,2,3 27 (c)*

Environmental Allowance $

Modifier E rn

?

Y w

r 3

P L._ _ __ __ _ _ _ .

l

~

l

" taste 3.3 '.s (Continued) y

' -fMGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUM NTATiON

<9 MINIMUM r- QUWIN[L5 CilANNELS LPPL1 CABLE 10!AL NO.

JC ST OlAINIELS 10 TRIP OPERABLE t D K_ 5 _

ACTION 43, IONCIT.ONAL INil_i_

6. Auxiliaryfeedwater(Continued)

E, d. Stease Generator Water Level-Low-Low (Continued) ;p 0/2%. F .. 2h M. -E... Jf53. p . i. 2. 3

[ ?) S'ri Edh

'" T 2.~NJ'f f T H ??l

, _ . -.El_

??lW

25. per- -22. r

e. Safety injection See Itua 1 ateve for all Safety injection initiating functions Start Motor-Driven Pumps and reqcirements.

2 1 2 1. 2. 3 22 w f. Loss-of-Offsite s'ower-1 Start Turbine-Driven Pump 8##

2-(1/ pump 3 1, 2 19

". g. Trip of all Main 4-(2/ pump)**

feedwater Pumps e in.same ,

os separation)

Steri Motor-Driven Pisaps 2 2 1. 2. 3 15*

li. Anellf ary feedwater 1

Pump Sustion Pressure-tow (Transfer to ESW) .

a

'l 7. Autcoatic Switchover to

/y Containment scop 2 1, 2, 3. 4 14 l

a. Automatic Actuation Logic 2 1 '

l S -

and Actuatton Relays (55PS) l ,

4 2 3 I , 2. 3, t, 16

? b. RWST Level - Low-tow Coincident %dith Safety

'J injection See Itan 1 above for Safety Injectica lattiatta$ fucctions and requirements.

' .. i l~.

e e

w _,

g' I

MINI $1M TOTAL NO. CHANNEI.S CHAnILS FUNCTIONAL UNIT OF CHAWILS TO TRIP OPERABLE MODES ACTION 6.d. Steam Generator Vater Level-im-Im

2) Start Turbine-Driven Pump a) Steam Generator Water Level- 4/stm. gen. 1/stm. gen. In 3/stm. gen. each 1,2,3 19*,27(a)

Low-Im ( Adverse Containment any operating operating stm.

Enviroesent) stm. gen. gen.

b) Steno Generator Water Level- 4/sta. gen. 2/sta. gen. in 3/stm. gen. each 1,2,3 27(a),27(b)*

Low-Im (Ncrual Containwnt any operating operating stm.

Environ:nent) stm. gen. gen. g c) Vessel Delta-T 4 2 3 1,2,3 27(c)* g (Power-1, Power-2) x o

d) Cantainment Pressure- 4 2 3 1,2,3 27(c)* v.

Environmental Allowance y Modifier p t'1 Y

Y w

f . .

. . , .1 RENfgygg ]

I FABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continted)

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTIC9 20 - With less than the Mi'nimum Channels OPERA 8LC, u thin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the asscetated permissive annunciator window ('s) that tha interlock is in its required state for the existing plant ccndition, or apply Specification 3.0.3.

ACTION 21 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least. HOT STANOBY '

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUT 00WN within the following G hours; h'owever, one channel may be bypassed for up to 2 heurs for surveillance testing per Specification 4.3.2.1 provided the * '.

other channel is OPERABLi. .

ACTION 22 - With the number of 6;ERABLE channels one less than the To' 't Ncaber of channels, restore the inoperable channel to OP N ,$LE status witt!n 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at laast HOT STANDBY withirt 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTD0WN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - With the numbcr of OPERAtt.E channels one less than the Total 1

.i Number of Channels, restore the inoperable chancel to CPE?ABLL i status within A8 hours or declare the associated valve inoperabla and take the ACTION required by Specifice.tfon 3.7.1.5.

, ACTION 24 - With the number of OPERABLE.channele one less than the Minimum Channels OPERABLE requirement, decir e the affected auxiliary feedwater pump inoperable and take tue ACTION required by Specification 3.7.1.2.

ACTION 25 - With the number of OPERA 8LE channels one less than the Minimum Channels OPERABLE requirement, declare the affected diesel generator and off-site power source inoperable and take the ACTION re@ ired by Specification 3.8.1.1.

' i ACTION 26 - With the num, Jar Uf OPERABLE channa13 one less than the Mintuun t Channels OPER/0LE requirement, ts. tore the ir. operable channel ta p OPERABLE statuc withir, 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or initiate and maintein opera- l tion of the Con'.rol Room Emergency ventilation System.

AC110N 27 - With the number tf CPERAaLE chamels one less than th Minimum '

Channels OPERABLE requirement, be in at least HOT ! TAC 3Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one chienel may De bypassed for ';p to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other chat.nel is OPERABLE. 1 Z/WGPT Z CALLAWAY - UNIT 1 3/4 3-21

(

l 1

'I s

INSERT I ON TABLE 3.3-3 ;

i 4- ACTION 27(a) - With an inoperable delay timer in the Trip Time [

Dolay circuitry, STARTUP and/or POWER OPERATION ;

may proceed previded that the Vessel Delta-T (Power-1, Power-2) channels are placed in the ~!

tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . !

ACTION 27(b) - With the number of OPERABLE channels less than the 4

Total Number of Channels, STARTUP and/or FOWER -

' OPERATION may proceed provided that the [

Containment Pressure-Environmantal Allowance Modifier channels in the affected protection sets are placed in the tripped condition within 6 :

hours, t I. ACTION 27(c) - With the number of OP5RABLS channels less than the l Total Number of Channels, operation may continue -

provided the inoperable channels are placed in the .,

1 tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

] !

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..r-. - . _ - - . , , . ~ - - - - - - - . . - - , _ _ . - . , _ _ _ - _ . - _ . _ _ - - , _ _ _ ___ _ - , - _ . . , . . . , , _ _ . . _ -

,-~., .\

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( ,

TA8tE 3.3-4 (Continued) o A ENGINEERED SAFETY FEATbRES ACTUATION SYSTEM INSTRUMDJTATION TRIP $ETPOINTS, C.-

>= '

SENSOR 7 RIP ALLOWA8LE TOTAL FUNCTIONAL UNIT ALLOWANCE (TA) ERPOR (5) SETPOINT VALUE i Z_

d

5. Fee 6%ater Isolation (Coat'nu2d) .

b. Steam Generator Water -

Level-High-High 5.0 2.18 2.0 1 78% of $ 79.8% of

. narrow ra Se narrw range instrument fastrument span. spen i

c. Safety Injection See Ites 1. above for all Safety Injection Trip Setpoints and Allouable Values.

6. Auxiliary Fe% ater o,

1 a. !'anual Ini*.f ation M. A. N.A. E.A. N.A. M.A.

,, b. Automatic Actuation Logic and Actuation . .

Re1ays (55PS) N.A. H.A. k.A. N.A. N.A.

c. Aut m tic 1.ctuation .

1 Logic auf Actuation Relays (80P ESFAst N.A. N.A. N.A. N.A. N.A.

d. Steam Generator Vater .-

Level-Lw-Lc2 .

i 1) mn =e.- . ; .;..

Em 2M-- - 21ae ~2. 0 > 23 5% ;f : 22.0% af

=.__ : ;: .-aerrw-reen.--- :o ,

m. .

,_o.-... .

3gg7 3 . -+ .

m ,

cn g Mt=n T='_% arrvee-u; -- - 23.5 21.1e - 2.0 ; 22.5% 25 12 E er o

-=r:= cn;_ n n = ,;::;- Z .,

-insecumeat- --4ntit_n c.i i:

MMU N, . -sPaa-- -teen- m

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- ii INSittJ0147ASLE3.3-4 TOTAL SENSOR ALLOWANCE ERROR FETIONAL UNIT ,_ (TA) Z (S) TRIP SENIKf ALLOWABLE VALUS

6. l. Stear.Generatcr Water Level low-Icv

1) Start Ibtor Driven Futps

a. Vessel belts T Equivalent i1C%RTP Vessel Delta T (Power-1) 6.0 2.38 2.0 $VesselCeltaT iYesselDelta-T Equivalentto10% Fgivalent to 14.0%

UP FP Coin h ent with Steas Generator Water Level 20.2 11.58 2.0 220.2%afNarrev 218.4%ofNarrev '

tev-!.ov (AAerse C,;ntaint.ast Range Inrtre+nt Span RangeInstrument Envirenrett) Spn aM Containrent Pressure - 1.3 0.71 2.0 < l.5 reig i 2.3 pig Environrental Allevance M ifier OR Steas Generate: Water Level 14.8 12.18 2,0 214.8%ofNarrov 213.0%ofNarrev lev-lev Obtral Containrent RangeInstrueent RangeInstrutent Enviro w nt) Span Span With a !he Delay, :t) i232teceni !240 seconds

b. 10% RTP < Vessel Delta T Fquivalenti20%RTP Yessel Del'a-T iPeve.-2) 6.0 2.38 2.0 iVerre! Delta-T $VesselDeltaT Fm ivalent to 20 % F4 fvalent to 24.0 %

RTP RTP i

Coincident with Steas Generster Water Level 20.2 17 'A 2.0 ?20.2%ofNarrov 218.4%ofNarrov lov-!cv (Adverse Containment Range Instr m at RangeInstrtrent Environment) Span Spn t

AM l Contastrent Pressure- 3.3 0.71 2.0 i 1.5 pig i2.3psig j E. viro. rental Allevance

!bilt.et e

+

l OR l

Steas Gen.rator Water Level 14.8 12.18 2.0 114.8%ofXariov 213.0%of'arter low-Icv Obtral Costar. rent Range in3trurant Ran;e Instrtscat l E x etent) Sp's Spn With a fire Delay, (t) i 122 secfds i 130 seconds t

g --e , .--s---,-r- . , - - - - - - - - - - -

s INSERT J CM 7AllE 3.3-4 (Cont.)

AffAL, SI E R ALILVANCE ERRR ENCL [CoAI, UNif .

(TA) 2 (S) TilPSE1T0thi &_!I_kA!L3lA!,E c) Yestel Delta-T Fq2ivalent > 20% RTP Cefnetaentvit.h

$ teas Generator Water Leuil 20,2 17.58 2.0 220.2%ofNattrv ! 18.4 % of Narow lev-Icv (Mverse Contaireent RangaInstrument RangeInstrutent Envirentant) SP:, Span And ContainantPressure- 3.3 0.71 2.0 $1,5psig 1i.3psig ,

n~irenmu tal Allevance ,

!bdifier OR Steam Generat'.' Water !.evel 11.8 12.18 2.0 214.8%ofNarrov 213,0%ofWarrow low-tav Obraai Containtant R nge Instrurent langeInstrument Ewirentett) Span Spa P

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IEIRT K 0] TABLF $.3-4 TOTA!, SENSOR

\

ALifWANCE EFROR

.. TalCTLONAL_l' NIT (TU Z (S) fl!P_ SUM SLOWABLE VALliE 6.d. Steam Generator Water Level lev-Icv

2) Start Turbine Oriven Purp

a. Yessel Delta T Eq2ivalent

,10% RTP Vessel Delta T (Pover 1) 6.0 2.33 2.0 1 Venel Delta T 3VesselDeltaT Fq1halent to 10% Eq2ivalent to 14.0%

RTP RTP Coirdicent with l

Stean Ge.ncrator Water Level 25.2 17.53 2.0 120.2IcfNarrev 318.4%ofKarrow Range Instrutent Sp n Rangeinstrument tov tev ( b erne Centainrent Span Environrent) and Containrent fressure - 3.3 0.71 2.0 1 1.5 p ig i 2.3 pig Envirottental Allevance N ifier OR Stear Generator Water Level 14.8 12.18 2.0 114.8%ofNarrov 213.0%ofKarrow Range Instrurent RangeInstrument lev-tev (Norsal Containeent Enviro. ment) Spn Spa I

i With a Tira Delay, (t) !232 seconds 1240 seconds j b. 10% RTP < Vessel Delta-T E721 valent f 20% RTP Vessel Delta T (Fever-2) 6.0 2.M 2.0 $VesselDelta-T !VesselDelta-T Iqalvalent to N % Lpivalent to 24.0 %

MP MP Coincident with Ster

9 nerater Water Level 20.2 17.58 2.0 220.2%efNarrev ! 18.4 % of Narrev RangeInstrerent FaNe Instrument Icv-tev (herse Containrent Spa Spn Envirenrent)

And 3.3 0.71 2.0 51.5 pig ! 2.3 p ig containrent fressu e -

Enviro rental Allevance M lfier OR 14.8 12.18 2.0 214.8%ofKarrev 313,0 % of Narrev Steas Generator Water Level h qe Instrerent Range instrurent lev Icv (Nortal Containrent Spn Spn Envirenrent)

With a fire Delt), (t) $ 122 seceds i 130 recends l

INSTRf K OW TA3!Z 3.3 4 (Coat.)

TCffAL St#SOR ALIAA)CE ERROR GlC{l_0NALCHlf (fA) I (S) 1RILK((0)lg j ALIDAPLE VALUE c) Vessel Delta-f Egi1 valent > 20% RTP Coinciden,with t

Steas 0*nerator Water Level 20.2 17.54 2.0 120,2%ofNarrow 118.4%ofNarrow lev-Low ( Aterse Contairrcnt RangeInstruzent Range Instrurent Environrent) Sian Spa And Contattr*ntfressure- 3.3 0.71 2.0 $ 1.5 pig j2.3psig Environpental Allevance M iffer OR Stean Generator Water level 14.8 12.18 2.0 214.8%cfNarrev 213.0%ofKarrov La-Icv (Xortal Cchtainsent Rangalestrurent Range Instrument ;

Environmant) Spa Spn f

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9 TABLF. 3.3-S (Continued)

I ENGINEERED SAFETY flATURES RESPbNSE TIMES

_I_NITIA11NGSIGNALANDfUNCTION RESPONSE TIME IN SECONDS

5. Cortainment Pressure-Hich-3

^

a. Containment Spray 1 32(1)/20(2) ,

b. Phase "B" Isolation i 31.5

6. Containment Pressure-Hich-2 Steam f,ine Isolation 1 2(5)

7. Steam Line Pressure-Negative Rate-High Steam Line Isolation i 2(5) {

8. Steam Generator Water Level-Hich-High

, a. Feedwater Isolation i 2(5)

b. Turbine Trip i 2.5

9. Sieam Generaper Water level-Low-tow

a. Start MotWDFiven Auxiliary '

Feedwater Pumps 160(T)

b. Start Turbine-Oriven Auxiliary feedwater Pump 160 ( f)

10. _ Loss-of-Offsite Power Start Turbine-Oriven Auxiliary Feeckster Pump N.A.

11. Trip of All Main Feedwater Pumps Start Motor-Driven Auxiliary ;

Feedwater Pumps N.A. !

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I CALLAWAY - UNIT 1 3/4 3-31 Amend. tent No. 18 I-

4 4

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$ ) TABLE NOTATIONS (Continued)

! (7) Olesel generator starting and sequence loc 11ng delays included. Sequen-

j. tial transfer of charging pump suction from the VCT to the RWST (RWST valves omen, then VCT ulves close) is not included. Response i time assumes only opening of RWST valves.

(f) boet mi include Trif Ti"* b*l^ff A*'f'"'* YI**! "'l'A *A*V*

3 inekde He fransmi/hvn 7200 j*<ocore po/r<+ron ea ttn.}s solid l sh}e fes /sel,fon c alise /9 os) n e}u,};on oferices e*, /y .1~4ft en f/s e/.e // r rotfonte /Im os n e e rtsery Ar ~rHermAt. hwcx l in e x c ast o S 36 % XA TEA 7WffmAL /%ct.

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! CALLAb'AY - UNIT 1 3/4 3-32a Amendment No.22 i

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.. N.. ..

TABLE 4.3-2 (Continued)

. n ..

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

. ,~, .

c SURVEILLANCE REQUIREMENTS l E*

eli T2IP ,

g A1ALOG ACTUATING MODES y

~ CHANNEL DEVICE MASTER SLAVE FOR %dHICH Y. . CHAltiEL CHANNEL OPERATIONi.L OFF. RATIONAL ACTUATION RELAY RELAY SURVEILLANCE

" FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST tc31C TEST TEST TEST IS REQUIRE 0 s

6. Auxiliary feedsater (Continued)

c. Automatic Actuation Logic .

~

and Actuation Relays (80P ESFAS) N. A. M.A. M.A. K. A. M(1)(2) N.A. N.A. 1, 2, 3

-3. S t x C . ,. . b r '.'. R r S- ;; %.A. X.A. %.A. X.A. 1, 2, 3 ,

-L. .; Lu L= _T/VSE47* /

e. ' Safety Injection- See Item 1. above for all Safety Injection Surveillance Requirements.

{

w f. Loss-of-Offsite Power N.A. A N.A. M N.A. N.A. N.A. 1, 2, 3

g. Trip of All Main M.A. M.A. M.A R

.N.A. N.A. N.A. 1, 2 8

. Fee &ater Pumps

h. Auxiliary Techater 5 Jt M M.A. N. A. M. A. M.A. 1, 2, 3 Pump Suction Pressure , .

Low .

7. Automatic Switchover to '

Containment Susp

a. Autocatic Actuation N.A. N.A. N.A. N. A. M(1) M(1) Q(3) 1, 2, 3, 4 Logic and Actuation -

Relays (SSPS) -

b. RWST Level - Low-Low 5 R H N.A. . -

N. A. N. A. N.A. 1,2,3,4%

Coincident With . ,

4 4

Safety Injection ' See Item 1. above for all Safety Injection Survel11ance Requirements. -

, CO

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8. Loss of Power ,. O

a. 4 kV Undervoltage- N.A. R N.A. M N.A. N.A. M.A. 1, 2, 3, 4 %

Loss of Voltage

~

b. 4 kV Undervoltage- N.A. R -

N. A. . M N.A. N. A. N.k. 1, 2, 3, 4" Grid Degraded Voltage ,

, L. -

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"IRIP ANAIDG KRKITU 'f1FS RR OWN1 DNIm MASIER SULW. EIIQI ORW1 ORWL G D KTI N AL Q ULTTI W AL ACnKTIN REIAY REIAY SW"EIIl#E PJCDWAL thTT CEII CALIBRKrim *IIST 'IIST LDGIC "IIET , 'IEST 'IIST IS REIUDIED

6. Artillary Twinner

d. Stass Grwrator U:grer Irvel-Inw-Im S R M N.A. KA. KA. KA. 1,2,3

1) Stuan Grerator Vater Iml-Inw-Im (Ah Q11tairswrc huiruumsc)

S R M K A. K A. N.A. N.A. 1,2,3

2) Stssun Grrrator Vater Irvel-Im-Im (.*ormal Cmtairmerc y huirursrt) v>

S R M N.A. K A. N.A. KA. 1,2,3 h

3) Vessel Delta-T (Ibws-1, Itwr-2) e o

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4) Ccutaimsst 1%ssure - S R M N.A. N.A. K A. N.A. 1,2,3 y Dwuussertal A11cuance p

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REVISlay 3 LIMlf1NG 5AFETY SYSTEN SETTING $

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Steam Generator Water Level The $ team Generator Water Level Low-Low trip protects the reactor frva loss of heat sink in the event of a sustained steam /feedwater flow misaatcp resul4ing frca 19ss of normal feedwater a 'h; : pee 4fted-6e4pe4at F=Mn ggg g

-eRann !cssteering c My; of- th; Stttery r;.:Jer ;yet= 4 Undervoltaoe and Underfrequency - Reactor Coolant Puno Susses The Undervoltage and Underfrequency Reactor Coolant Pues tus trips provide core protection against ONs as a result of cowletc loss of forced coolant flow. The specified Setpoints assure a Reactor trip signal is generatedTime delays a before tne Low Flow Trip 5etpoint is reached.

the Underfrequency and Undervoltage trips to prevent spurious Reactor For undervoltage, the delaytrips is froe momentary electrical power transients.

set su that the time rsquired for a signal to reach the Reactor trip brer.kers following the simultaneous trip of two orFor mure reactor coolantthe underfrequency, pumpdelaybus circuit is set breakers shall not exceed 1.2 beconds.

50 that the time required for a signal to reach the Reactor trip breakers af ter the Underfrequency Trip 5etpoint is reached shall not exceed 0.3 Jacond.

On decreasing power the Undervoltage and Underfrequency Reactor Coolant Pump Bus trips are autocatically blocked 7y P-7 (a power level of approximately 10%

of RATED THERMAL POWER with a turaine impulse chamber pressure at approminately 10% of full power equivalent); a< J on increasing power, reinstated automatically by p-7.

Turbine Trip A Turbine trip initiates a Reactor trip. On decreasing power the Reactor trip from the Tureine trip is automatically blocked by P-9 (a power level of approaimately $C% of RATED THERMAL POVER); and on increasing power, reinstated automatically by P-9.

Safety injeetten Input from ESF If a Reactor trip has not already been generated by the Reactor Trip System instrwentation, the E5F autcoatic actuation logic channelsThe willESF initiate a Reactor tr Q upon any signal which initiates a $afety Injection.

instrumentation channels which initiate a $4fety injection signal are shown in table 3.3 3.

~\

8 2*7 CALLAWA1

UNIf 1 g )

(

INSERT M or a feedwater system pipe break, inside or outside of containment. This function also provides input to the steam generator levcl control system, therefore, the actuation logic must be able to withstand both an input failure to the control system (which may then require the protective function actuation) ,

and a single failure in the remaining channels providing the protection function actuation. This results in a 2/6 actuation logic. With the transmitters (d/p cells) located inside t containment and thus possibly experiencing adverse environmental conditions (due to a feedline break), the Environmental Allowance Mcdifier (EAM) was devised. The EAM function (Containment '

Pressure with a setpoint of 31.5 psig) senses th3 presence of adverse containment conditions (elevated pressure) and enables the Steam Generator Water Level - Low-Low trip setpoint (Adverst) which reflects the increased transmitter uncertainties due to this environment. The EAM allous the use of a lower Steam Generator Water Level - Low-Low trip setpoint (Normal) when these conditions are not present, thus allowing more margin to trip for normal operating conditions. The Trip Time Delay (TTD) creates ,

additional operational margin when the plant needs it most, during early escalaticn to power, by allowing the operator time F to recover level when the primary cido load is sufficiently small to allow such action. The TTD is based on the continuous ,

monitoririg of primary side power through the uae of Vessel t De2ta-T. Two time delays are possible, based on the primary side power level, the magnitude of the trip delay decreasing with !

increasing power. In the event that the EAM or TTD functions do i not meet the minimum channels operable requirements, it is acceptable to place the inoperable channels in the Tripped '

Condition and continue operation. Placing the inoperable channels in this mode will result in the enabling of the Stean Generator Water Level - Low-Low (Adverse) function, for the EAM, i or in the removal of the trip delay, for the TTD. In the event !

that the Steam Generator Water Levul - Low-Low (Normal) function i does not meet the minimum channels operabin requirement, it is !

neceptable to place the associated EAM channels in the Tripped Condition and continue operation. Performing this action will result in the enabling of the Steam Generator Water Level -

Low-Low (Adverse) function which has a more conservative (higher level) trip setpoint. At this time it would also be acceptable to place the inoperable Steam Generator Water Level - Low-Low channels in the Bypassed Condition to prevent an inadvertent Reactor Trip or ESFAS actuation.

l l

l At.tachmen t ' - 5 l

UMIRC-1822 ll l

l SIGNIFICANT !!AZARDS EVALUATION i

dTEAM. GENERATOR LEVEL _REACTO_R TRIP MODIFI, CATION l

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i SIGNIFICANT HAZARDS EVALUATION CALLAWAY STEAM GENERATOR LOW-LOW LEVE_L REACTOR TRIP MODIFICATION I. Ir}troduction This evaluation supports Union Electric Company's license

amendment request to modify the Callaway Plant steas generator low-low level reactor trip circuitry. The :

changes will include the addition of an Environmental Allowance Modifier (EAM) and Trip Time Delay (TTD) circuitry. The design of these circuits has been developed by the Westinghouse owners Group as a means to reduce the frequency of unnecesrary feedwater-related reactor trips, sne EAM and TTD conceptual designs are documented in WCAP-ll325-P-A and WCAP-11342-P-A, which were approved by the Nuclear Regulatory Commission in January, 1988, t

Technical specification changes being made in conjunction !

with this change include revised steam generator low-low level trip setpoints and allowable values for reactor trip and auxiliary feedwater initiation, new trip setpoints and allowable values for the EAM/TTD circuitry, and new operability, trip time delay, and surveillance requirements.

In support of the requested amendment Union Electric has reviewed the impact of the modifications to steam generator level circuitry on the analysis described in the Callaway Final Safety Analysis Report (FSAR) and the Callaway Uprating which was approved by the Nuclear Regulatory Commission in Amendment 35, dated March 30, 1988, to Callaway 2:a:ility Operating License NPF-30. On the basis of the results of this review Union Electric han concluded that the changes do not involve a significant hazard, the following are summaries for each change and the conclusions reached.

II. EnyitonmeJLta_1 Allowe,nce JodiUer The design of the Environmental Allowance Modifier (EAM) selects a setpoint for the steam generator low-low level trip which includes an environmental uncertainty associated with the applicable plant environmental conditions. In the event that an onset of an adverse containmant environment is sensed by the EAM circuitry via containment pressure, a higher steam generator low-low level trip setpoint is automatically selected to account for larger environmental uncertainties associated with the adverse environmental conditions due to a feedwater line rupture inside containment. Since a lower setpoint is used by the EAM circuitry during normal operation, improved operating margin (larger steam generator level operating band) with respect to feedwater l

inventory control can be realized. These features act to reduce feedwater-related tripo especially during plant startup and load change maneuvers.

a) This change does not involve a significant incroace in the probability or consequences of an accident previously evaluated. No changes are involved in accident initiators which would change the probability of an accident. The consequences of previously analyzed accidents remain unchanged because the new setpoints and allovable values for the steam generator low-low level trip, vessel Delta-T, and containment pressure bistables have been determined using the methodology in WCAP-11342-P-A, which has been approved by NRC.

a b) This change doer not create the possibility of a new or different kind of accident from any accident previously evaluated. The design assures that the "

appropriate environmental allowance is included in setpoints for events requiring protective action during which an adverse environment exists, c) This chance does not involve a significant reduction in a margin of safety. This is based on the fact that the analysis and setpoints associated with the incorporation of EAN have been performed and esta-blished using the models and methodologies from WCAP-11342-P-A, which has been approved by NRC.

III. Tyrip_ Time _D_e 1 ay once the les-low water level trip setpoint (either the

! norme.1 environment setpoint or the adverse environment i setpoint) is reached, the Trip Time Delay (TTD) acto to

, delay reactor trip, main feedwater isolation, and i auxiliary feedwater system actuation to allow timo for operator corrective action or for natural etabilization of shrink / swell water level transients. The TTD is designed for low power or startup operations. The TTD design may be generally described as a eystem of pro-determined programmed trip delay times that are based upon the prevailing power level at the time a low-lov

! level trip setpoint is reached.

The Callaway TTD design is based on two unique power level interlocks at 10% and 20% of Rated Thermal Power (3565 MWt) for implementation of the TTD logic. These power level interlocks are well within the power level i range defined by the NRC in the WCAP-11325-P-A SER for i plant-specific applications. Consistent with the WCAP-11325-P-A methodology, appropriate trip time delaya i

have been established to preserve existing safety analysis limits. No time delays are utilized for power levels

greater than 20% of R.ked Thermal Power, i

a) This change does not involve a significant increase in the probability or consequences of an accident previously evaluated. No changes are involved in accident initiators which would change the probability ,

of an accident. The consequen:es of previously a analyzed accidents remain unchanged because the time ,

delays associated with the TTD modification and "

supporting transient analyses utilise the methodology in WCAP-11325-P-A, which has been approved b'/ NRC.

v b) This change does not croato the possibility of a new or different kind of accident from any accident

) previously evalunted. The design assures that a Condi*, ion II event, as defined in ANSI-N18.2-1973, does not lead to a Condition III or IV event.

c) This change does not involve a significant reduction in a margin of safety. This is based on the fact

that the analysis and time delayn ansociated with the incorporation of TTD have been performed and esta-

" blished using the models and methodologies from WCAP-113 2 5- P - A , which has been approved by NRC.

IV. S_ummat:y K

Baned on tho above discussions, the amendment request does not involvn a significant increase in the probability F or conoequencen of an accident previously evaluated; does not cre6te the ponnibility of a new or different kind of accident from any accident previously evaluated; and does m not involve a reduction in the required margin of cafety.

Based on the foregoing, the requested amendment does not L present a significant hazard, a

K E

1 Attcchment -6 ,.

ULNRC-1022 i

t DRAFT FSAR CIIAPTER 7 CHANGES 1 .1TEAM G_ENERATOR LEVEL REACTOR TRIP MODIFIC ATION h

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CALLAWAY - SP 7.2 REACTOR TRIP SYSTEM 7.

2.1 DESCRIPTION

7.2.1.1 System Description The reactor trip system (RTS) automatically keeps the reactor l o;perating within a safe region by shutting down the reactor i whenever the limits of the region are approached. The safe i

< operating region is defined by several considerations, such as l' nechanical/ hydraulic limitations on equipment and heat transfer phenomena. Therefore, the reactor trip system keeps surveil-lance en process variables which are directly related to '

equipment mechanical limitations, such as pressure, and pres-surizer water level (to prevent water discharge through safety :

valves and uncovering heaters), and also on variables which directly affect the heat transfer capability of the reactor :

(e.g., flow and reactor coolant temperatures). Still other :'

parameters utilized in the reactor trip system are calculated from various process variables. Whenever a direct process or :

ceilculated variable exceeds a satpoint,ethe reactor will be dy,a8 ;

D* shut down in order to protect against either damage to fuel ese wn i cladding or loss of system integrity, which could lead to the expired i release of radioactive fission products into the containment ;

The following systems make up the reactor trip system (see t % ;

l Ref. 1, 2, and 3 for additional background information). -

a. Process instrumentation and control system j

b. Nuclear instrumentation system

c. Solid state logic protection system

d. Reactor trip switchgear l

e. Manual actuation circuit i The reactor trip system consists of sensors that monitor various i plant parameters and are connected with analog circuitry, con-i sisting of two to four redundant channels, and digital circuitry, l consisting of two redundant logic trains, that receives inputs from the analog channels to complets the logic necessary to l automatically open the reactor trip breakers, I

i Each of two logic trains, A and B, is capable of opening a separate and independent reactor trip breaker, RTA and RTB, respectively. The two trip breakers in series connect three-j phase ac power from the rod drive motor generator sets to the

! rod drive power cabinets, as shown in Figure 7.2-1 (Sheet 2).

During plant power operation, a de undervoltage coil on each l reactor trip breaker holds a trip plunger out against its spring, allowing the power to be available at the rod control 4

i Rev. OL-0 f 7.2-1 6/86 i

CALLAWAY - SP the reactor if the power level is above P-7.

The coincidence logic and interlocks are given ,

in Table 7.2-1.

e. Steam generator low-low water level trip The specific trip function generated is low-low steam generator water level trip.

This trip protects the reactor from loss of heat sink. Tais trip is actuated on two out of four low-low water level signals occurring in any steam generator. Coscri A FeV. The lugic is shown on Figure 7.2-1 (Sheet 7),

f. Reactor trip on a turbine trip (anticipatory)

The reactor trip on a turbine trip is actuated by two-out-of-three logic from emergency trip fluid pressure signals or bv all closed signals from the turbine steam stop valves. A turbine trip causes a direct reactor trip above P-9. The reactor trip on turbine trip provides additional protection and con-servatism beyond that required for the health and safety of the public. This trip is included as part of good engineering practice and prudent design.

The turbine provides anticipatory trips to the reactor protection system from contacts which change position when the turbine stop valves close or when the turbine emergency trip fluid pressure goes below its setpoint.

Components specified for use as sensurs for input signals to the reactor protection system for "emer-gency trip oil pressure low" and "turbine stop valves close" will conform to the requirements of IEEE 279-1971 and be environmentally qualified. However, seismic criteria are not included in qualification regarding mounting and location for that portion of the trip system located within nonseismic category I structures.

Evaluations indicate that the functional performance of the protection system would not be degraded by credible electrical faults such as opens and shorts in the circuits associated with reactor trip or the generation of the P-7 interlock. The contacts of redundant sensors on the steam stop valves and the trip fluid pressure system are connected through the grounded side of tne ac supply circuits in the solid state protection system. A ground fault would, there-fore, produce no fault current. Loss of signal caused by open circuits would produce either a partial or full Rev. OL-0 7.2-10 6/86

1 CALLAWAY - SP hot le9 coolant stream, contains five inlet orifices distributed along its length. In this way, a total of 15 locations in the hot leg stream are sampled, providing a representative coolant temperature measurement. The 2-inch-diameter pipe leading to the resistance temperature detectors manifold provides mixing of the samples to give representative temperature measurement.

Care hac been taken to distribute the flow evenly among the five orifices of each probe by effectively restricting the flow through the orifices. This has been done by designing a smaller overall orifice flow area than that of the common flow channel within the probe. This arrangement has 'lso a been applied to the flow transition from the three probe flow channels to the pipe leading to the temperature element manifold.

The total flow area of these channels has, therefore, been designed to be less than that of the 2-inch pipe connecting the probes to the manifold.

The cold leg reactor coolant flow is well mixed by the reactor coolant pump, thereby eliminating any cold leg temperature spatial dependence. Therefore, the cold leg sample is taken directly from a 2-inch pipe tap off the cold leg downstream of the pump.

7.2.1.1.5 Pressurizer Water Level Reference Leg Arrangement The design of the pressurizer water level instrumentation employs the usual tank level arrangement, using differential pressure between an upper and a lower tap on a column of water. A reference leg connected to the upper tap is kept full of water by condensation of steam at the top of the leg.

7.2.1.1.6 Analog System The analog system consists of two instrumentation systems - the process instrumentation system and the nuclear instrumentation system.

Process instrumentation includes those devices (and their interconnection into systems) which measure temperature, pressure, fluid flow, fluid level as in tanks or vessels, and occasionally physiochemical parameters, such as fluid con-ductivity or chemical concentration. Process instrumentation specifically excludes nuclear and radiation measurements. The process instrumentation includen the process measuring devices, power supplies, indicators, recorders, alarm actuating devices, timers, controllers, signal conditioning devices, etc., which are 73v necessary for day-to-day operation of the NSSS, as well as for monitoring the plant and providing initiation of plant pro-tective functions.

The primary function of nuclear instrumentation is to protect the reactor by monitoring the neutron flux and generating appropriate trips and alarms for various phases of reactor Rev. OL-0 7.2-14 6/86 1

CALLAWAY - SP I i

7.2.1.2 Design Bases Information i i

The information given below presents the design bases information requested by Section 3 of IEEE Standard 279-1971. Functional '

i diagrams are presented in Figure 7.2-1.

l 7.2.1.2.1 Generating Station Conditions l

The following are the generating station conditions requiring !

reactor trip. [

a. DNBR approaching 1.30.

b. Linear power density (kilowatts per foot) approaching !

rated value for Condition !! events (see Chapter 4.0 i for fuel design limits), j

c. Reactor coolant system overpressure creating stresses [

approaching the limits specified in Chapter 5.0. l 7.2.1.2.2 Generating Station Variables

{

r The following are the variables required to be monitored in order !

to provide reactor trips (see Table 7.2-1). l Neutron flux '

b. Reactor coolant temperature

c. Reactor coolant system pressure (pressuriser pressure)

d. Pressurizer water level

e. Reactor coolant flow

f. Reactor coolant pump operational status (voltage and frequency) 9 Steam generator water level (ReGencnce 5)

U

h. Turbine-generator operational status (trip fluid pres-pure and stop valve position) 7.2.1.2.3 Spatially Dependent Variables The only spatially dependent variable is the reactor coolant temperature. See Section 7.3.8.1.2 for a discussion of this spatial dependence.

7.2.1.2.4 Limit.s. Mtrgins, and Setpoints The parameter values that will require reactor trip are given in Chapter 15.0 and the Callaway Technical Specific &tions. The Rev. OL-0 7.2-17 6/86

-.-----.-_...-_-_A

CALLAWAY - SP 7.2.1.2.6 Minimum Performance Requirements

a. Reactor trip system response times Typical time delays in generating the reactor trip signal are tabulated in Table 7.2-3. See Section 7.1.2.6.2 for a discussion of periodic rer.ponse time verification capabilities,

b. Reactor trip accuracies Reactor trip accuracies are tabulated in Table 7.2-3.

An additional discussion on accuracy is found in Section 7.3.2.1.2.7.

c. Protection system re.nges Typical protection system ranges are tabulated in Tuale 7.2-3. Range selection for the instrumentation covers the expected ranas of the process variable being monitored during povar operation. Limiting setpoints are at least 5 percent from the end of the instrument span.

7.2.1.3 Final Systems Drawings Functional block diagranis, electrical elementaries, and other drawings required to assure electrical separai'.on and perform a safety review are provided in the Safety-Related Drawing Package (refer to Section 1.7).

7.2.2 ANALYSES 7.2.2.1 , Failure Mode and Effects An, alp es An analysis of the reactor trip system has been perfonted.

Results of this study and a fault tree analysis are presented in Reference 4.

7.2.2.2 Evalyation o'? Design Limits While most setpoints used in the reactor protection system are.

I fixed, there are variable setpoints, most qqsAbly the over- ,

temperature AT and overpower AT setpoints.* All setpoints in 3N55 4 D the reactor trip system have been selected on the basis of tst engineering design or safety studies. The capability of the reactor trip system to prevent loss of integrity of the fuel cladding and/or reactor coolant system pressure boundary during Condition II and III transsents is demonstraued in Chapter 15.0. Accident analyses are carried out using those Letpoints determined from results of the engineering design studies. Setpoznt limits are presented in the Callaway Technical Specifications. A discussion of the intent for each of the various reactor trips and the accident analyses Rev. OL-0 7.2-19 6/86 i

CALLAWAY - SP ,

i. Capability for Ornsor checks The operational availability of euch systsm input sensor during reactor nperatien is Lecomy!ished by cross check.ing betweer. channels that bear s known relationship to each ether and that hava r63douts available. Channel chseks are discussed in Chcpter 16.0.

j. Capability for testing The reactor trip system is capable of Deing tested during power operation. Where onl system are tested at any one time,ytha parts of thesequence testing provides the necessary overlsp between the parts to ensure complete system operation. Tho testing capa-bilities are in conformance with Regulatory Guide 1.22, as discussed in Section 7.1.1.5.2.

The protection system is designed to permit periodiq testing of the analog :hannel portion of the reactor trip system during reactor power operation without initiating a protective action, unless a trip condition actually exists. This is because cf the coincidenc2 logic rewired for teactor trip. Thesa tests may be performed at any plant power from cold shutdown to full power. Befere starting any of these tests with the plant at pows:, all redundant reactor trip channels associated with ti.e function to be tested,must h1 in the normal (untripped) mode in order to avoid spurious trips. Sotpoints are referenced in the precauti m=,

limitations, and setpoints portion of the plant technical manual.

Analog ffannel Tests Analog channel testing is performed at the analog instrumentation rack ret by individually introducing dummy input signals into the instrumentation channels and observing the tripping of the appropriate output bistables. Process analog output to the logic circuitry is in utztpted during individual channel test byG4 3est ~I e, swit hW hich, when throwr..Adeenergizes the associatea logic . 7 puts,and inserts outpytt Interruption of2,up3bista praying, ble output to thelamp in the bistable logic circuitry for any cau,se (test, maintenance pur-try' poses, or removed from service) will cause that portion of the logic to be actuated (partial trip), accompanied by a partial trip alarm and caannel status light actu-ation in the control soom. Each 5annel contains those switchet, test points, etc. necessary to test the channel. See References 1 AQW 2yfor additional back-ground information. And 5

%sv.

Rev. OL-C 7.2-25 6/86

_ - - _ _.__________________________________________D

i

^

CALLAWAY - SP

o. Multiple setpoints g %g For monitoring tautron flux,4 multiple setpoints are used. When a more restrictive trip setting becomes AEV, necessary to provide adequate protection for a parti- 1 cular mode of operation or set of operating conditions, the protective system circuits are designed to provide positive means or administrative control to ensure that the more rcstrictive trip setpoint is used. The devices used to prevent improper use of less restrictive trip settings are considered part of the protective system and are designed in accordance with the criteria of this section.

p. Completion of protective action The protection system is so designed that, once initiated, a protective action goes to completion.

Return to normal operation requires action by the operator,

q. Manual initiation Switches are provided on the control board for manual initiation of protective action. Failure in the automatic system does not prevent the manual actuation '

of the protective functicns. Manual actuation relies on the operation of a minimum of equipment.

r. Access The design provides for administrative control of access to all setpoint adjustments, module calibration adjustments, and test points.

s. Identification of protective actions Protective channel identification is discussed in Section 7.1.2.3. Indication is discussed in item t below,

t. Information readout The protective system provides the operator with complete information pertinent to system status and Eafety. All transmitted signals (flow, pressure, temperature, etc.) which can cause a reactor trip will be either indicated or recorded for every channel, including all neutron flux power range currents (top detector, bottom detector, algebraic difference, and average of bottom and top detector currents).

Rev. OL-0 7.2-33 6/86

CALLAWAY - SP to the automatic high pressurizer pressure reactor trip ac-tuating at a presrure sufficiently below the safety valve setpoint.

For control failures which tend to emptv the pressurizer, two-out-of-four logic for safety injection action on low pressure ensures that the protection system can withstand an independent failure in another channel. In addition, ample time and alarms exist to alert the operator of the need for appropriate action.

7.2.2.3.5 Steam Generator Water Level The basic function of the reactor protection circuits associated with low-low steam generator water level is to preserve the steam generator heat sink for removal of long tekm residual heat. Should a complete loss of feedwater occur, the reactor would be tripped on low-low steam generator water level. In addition, redundant auxiliary feedwater pumps are provided to supply feedwater to maintain residual heat removal capability after trip. This reactor trip acts before the steam generators are dry. This reduces the required capacity, increases the time interval before auxiliary feedwater pumps are required, and minimizes the thermal transient on the reactor coolant system and steam generators.

Therefore, a lowalow steam generator water level reactor trip circuit is provided for each steam generator to ensure that sufficient initial thermal capacity is available in the steam generator at the start of the transient.e Two-out-of-four ][nsert D low-low steam generator water level trip logic ensures a Rtv. reactor trip, if needed, even with an independent failure in another channel used for control and when degraded by an additional second postulated random failure.

A spurious low signal for the feedwater flow enannel being used for control would cause an increase in feedwater flow.

The mismatch between steam flow and feedwater flow produced by the spurious signal would actuate alcrms to alert the operator of the situation in time for manual correction (see Figure 7.2-1, sheets 13, 14). If the condition continues, a two-out-of-four high-high steam generator water level signal in any loop, independent of the in.dicated feedwater flow, will cause feedwater isolation and trip the turbine. The turbine trip will result in a subsequent reactor trip if power is above the P-9 setpoint. The high-high steam generator water J.evel trip is an equipment protective trip treventing excessive moisture carryover which could damage th= .urbine blading.

In addition, the three-element feedvater controller incorporates reset action on the level error signal, such that with expected controller settings a rapid increase or decrease in the flow signal would cause only a small change in level before the controller would compensate for the level error. A slow Rev. OL-0 7.2-37 6/86 1

CALLAWAY - SP 7.

2.4 REFERENCES

1. Reid, J. B., "Process Instrumentation for Westinghouse Nuclear Steam Supply Systems (4 Loop Plant Using WCID 7300 Series Process Instrumentation)," WCAP-7913; Jatriary 1973. (Additional background information only.)

2. Lipchak, J. B., "Nuclear Instrumentation System," WCAP-8255, January 1974. (Additional background information only.)

3. Katz, D. N., "Solid State Logic Protection System Description," WCAP-7488-L (Proprietary), J&nuary, 1971 and WCAP-7672 (Non-Proprietary), June it71. (Additional background information only.)

4. Gangloff, W. C. and Loftus, W. D., "An Evaluation of Solid State Logic Reactor Protection in Anticipated Transients," WCAP-7706-L (Proprietary) and WCAP-7706 (Non-Proprietary), July 2.971.

5 [Entert E 8 64.

Rev. OL-0 7.2-39 6/86 a

CALLAWAY - SP TABLE 7.2-1 (Sheet 2)

Coincidence Protection Reactor Trip Logic Interlocks Comments

9. Pressurizer high pressure 2/4 No interlocks -

10. Pressurizer high water 2/2 Interlocked with Blocked below P-7 level P-7

11. Lou reactor coolant 2/3 in a0y Interlocked with Low flow in one loop will cause flow loop P-7 and F-6 a reactor trip when above P-8, and a low flow in two loops will cause a reactor trip when above P-7; blocked below P-7 1/4 Interlocked Blocked below P-8 with P-8

12. Reactor coolant pump 1/2 in both Interlocked Low voltage on all busses undervoltage busses with P-7 permitted bulow P-7

) 13. Reactor coolant pump 1/2 in both Interlocked Underfrequency on one j underfrequency busses with P-7 motor in both busses will trip all reactor coolant pump breakers and cause l'

reactor trip; reactor trip blocked below P-7 I

14. Low-low steam gener- 2/4 in any No interlocks JEnsect F -

ator water level loop IEV.

15. Safety injection coincident Interlocked with See Section 7.3 for with actua- P-11. (If reactor engir.eered safety features tion of coolant is less actuation conditions safety than 2000 psig, P-ll injection allows manual block)

Rev. OL-0 6/86

~

I x, w' ~'. -

CM CAWAY - SP I

TABLE 7.2-3 (Sleet 2)

Typical Trip Typical Time Reictor Tr'ap Signal Typical Range Accuracy Response (sec)*

10. Pressurizer high water Entire cylintarical 1 2.3% of full range 1.2 level portion of pressurizer Ap between trps at design (distance betweta taps) temperature and pressure

11. Low reactor coolant flow 0 to 120% of rated flow t 2 5% of full flow within 0.3 raage of 70 to 1002'. of full flow

12. Rermr coolant pump 0 to 100% rated voltage i 1% 0.7 unoervoltage

~

13. Reactor coolant pump 50 to 65 Hz i 0.1 Hz 0.3 underiregaency fe, As Se rance S.

^ ' * ^ ' " "

Ses se erence S

14. Low-low st ar generator 16 feet apprcximately -t .;

wat:r level from nominal full load ;: - - :: - g ef 4^0 W

) water level W ortt

15. 7.arbine trip - - 0.3 1

W overall allowable response time for each reactor trip channel is given in Table 3.3-2 of the kallaway Technical 5,et cifications. The channel response time value is the elapsed time from when the pu ameter being sen%d by the j

ch.annei reaches the safety set point until the undervoltage trip coil in the reactar trip breaker ir. de-energized.

j The additional time until the rods are free to fall into the cote is 0.3 second, or hss, for the breaker mechanism.

4 J

I 1

~

Rev. OL-0 6/86

CALLAWAY - SP l

i AFAS-M is generated en the occurrence of any one of i the following events-

1. Trip of both main feidwater pumps (Manual b)c:k of ,

the main feed pump trip signals is provided at the 1 main control board, and is indicated on the ESEAS status panel. This block permits startup and shutdown of the plant without automatic start of the AFPs, while allowing the AFPs to remain available to respond to a demand from any other sov.rce . )

2. 2 out of 4 low-low level signals iny o steam generator (c.t send * *c 7'ote d'l6 5Snc Rev. :

3. Manual AFAS-M initiation The turbine-driven pump is started on the occurrence of either of the following signals:

1. Manual start

2. Auxiliary feedwater actuation (AFAS-T)

AFAS-T is generated on the occurrence of any one of the following events: ,

1. Loss-of-offsite- ower

2. Low-low level 84 any two steam generators (at scud Moh.

proirc % a s p+cm) 7EV. 3. Manual AFAS-T initiation The steam generator sample line containment isolation valves and the steam generator blowdown isolation valves are all automatically closed on the occurrence of a safety-injection signal, a loss-of-offsite-power signal, or an AFAS. The signal which causes this closure is roset automatically upon reset of the AFAS.

b. Logic See Figure 7.3-1,

c. Bypass There is no device level override on this system.

Rev. OL-0 7.3-20 6/86 i

~

INSERTS FOR CHAPTER 7 0F FSAR INSE9T A The Environmental Allowance Modifier (EAM) circuitry in the low-low l level channel proviies for two level setpoints corresponding to an adverse and a norc i containment enviror. ment. The trip actuation signal may then % delayed by the Trip Time Delay (TTD) timers depending on the plant power level at the tims that the low-low level signal is sensed. A detailed description of the EAM/TTD design basis and functional implementation is provided in Reference 5.

INSERT B Additionally, for steam generator low-low level reactor trip, the Environmental Allowance Modifier (EAM) circuitry allows for two set)oints, one for a norm:1 containment environment and another ena)1ed when an adverse environment is detected. Also, the Trip Time :'

Ditlay (TTD) allows possible time delays dependent on power levels.

INSERT C places any applicable Environmental Allowance Modifier (EAM) and/or Trip Time Delay (TTD) functions into a conservative state.

INSERT D i Of the two available low low level setpoints, one corresponding to an :

adverse and 9ne, a normal containment environment, the Environmental Allowance Modifice (EAM) enables the appropriate setpoint. This trip is actuated on two-out-of-four low-low water level signals occurring in any steam generator after the expiration of any enabled Trip Time Delay (TTD) system timers (see Section 7.2.1.1.2 and Reference 5).

INSERT E Leach, C. E., Gongaware, B. L., Tuley, C. R., Erin, L. E., Miranda, S., "Implementation of Steam Generator Low-Low Level Reactor Trip Time Delay and Environmental Allowance Modifier in the Callaway i Plant," WCAP 11883 (Proprietary) and WCAP-ll884 (Non-Proprietary),

j August, 1988.

INSERT F l

Two level setpoints corresponding to normal and adverse i j environments. Also trip may be delayed depending on plant power

, level (Referenco 5).

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'" mir."- APERTUIG CARD - ] AISO Ava}hbfe @ A%.M .4 ' l7' '.' . 't.?.'.. i..t.'2..: n' C*'*%'.*;1.". ' ;*'hi? . '".* Y',' '?.ir,7!' ' , '::::,u::':=:::::'::,*' . ~';;'* 8809120090 - Nh nwlot.o 6/86 s CALLAWAY PLANY ' FIGURE 7.21 FUNCTIONAL DIAGRAMS (ST GENER R TRIP SIGNALS, @f[ "gd 0" (SHEET 7) ' . M 1 ~ _ _ PROTECTION SET I PROTECTION SET II ,,,,,m, m oo m ..ru t m 4,'pk , , , , _ , .. _ ,7 . 1. tm 4,'pk ~,2 - ,a, w m m- ~x ,a, w w 4 - - - , , ..b , a a n a n a a n n a , 0, 6, 6, L M $ M r . 5' sr h' r '( 'r# r g' s/ sf ,sf EAM Logic EAM Logic swvvv y s- sfs,ws,s, ., , TTD Logic TTD Logic @w464646464cH868cH464&M .1. d . .b a = SG NO,i S0 NO.2 g SG NO.3 i @*%k $ b M _ .W RE Acto 2 T2tP (ca HEET 1) PROTECTION SET III PROTECTION SET IV I[ 'D 8 % STE.M ODO.fGt w.fDI LL'W2, I WT1. CDd0 NT 3 Mda M NT - .a. u, m a ' Em , ,, m y a a a . s sz st sg sz y sz h sz sr 0- 0, Yn 6,Yg 6, Vn L ' s( s., r s s' s/ ,f a / $f s , / EAM Logic EAM Logic I i S,Ispi,'hggt/ 'f N/ 1'9FinFi/ TTD Logic TTD Logic l Fi & &l } " SI h - l @k&h@ @ APERTURE ' g,' 4 - u ..es cent.t o nt .. ire w n: CARD 8 N - horal cons 41reent Ovirownt k so tio.4 SP1 L*" "' s g Mign power Aho AM(h g -:-A @ A CALLAWAY PLANT R FIGURE 721 'q, ,, ' FUNCTIONAL Of AGriAMS pgggy,j8dgpg (STE AM GENERATOR GTAarup uc cics TRIP SIGN ALS. ogainy conmw o r cicws su e st r (S H E E T$ o-tu o 8809120090 - 9.7 , ,}}

ML20154A147

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ML20154A147

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