Text

Proposed Tech Specs Re RTD Bypass Elimination
	ML20034A105
Person / Time
Site:	Callaway
Issue date:	04/12/1990
From:	; UNION ELECTRIC CO.
To:	;
Shared Package
ML19302D976	List: ML20034A101; ML20034A103; ML20034A104; ML20034A105;
References
	NUDOCS 9004200105
	Download: ML20034A105 (35)
	v • d • e

.

F A.;

a i

ULNRC-2196 9

i

i..

b ATTACHMENT.4 TECHNICAL SPECIFICATION CHANGES' FOR

'RTD BYPASS ELIMINATION I

Table 2,2-1 Pages 2-4, 2-5,.2-5(a),

2-7, 2-9, 2-10 _

Bases B 2-5 Table 4.3-1 Pages 3/4 3-9,-3/4.3-12al

-Table"3.3 Pages.5/4.3-25(a),.

3/4 3-25(b),-3/4 3-25(d),

3/4 3-25(e)

1. i'l i '

b-'

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g IC i

.r 7r,,,

l:fl *;

Q w

e

TABLE 2.2-1 REACTOR TRIP SYSTEM INSTR!jMENTATION TRIP SETPOINTS h

TOTAL SENSOR ERROR

{

FUNCTIONAL UNIT ALLOWANCE (TA)

Z_

151 TRIP SETPOINT ALLOWA8tE VAttE ZE 1.

Manual Reactor Trip N.A.

N.A.

2.

Power Range, Neutron Flux E

a.

High Setpoint

7. 5 4.56 0

1109% of RTP*

<112.3% of RTP*

]

b.

Low Setpoint 8.3 4.56 0

125% of RTP*

128.3% of RTP*

3.

Power Range, Neutron Flux, 2.4 0.5 0

14% of RTP* with

<6.3% of RTP* with a time constant a time constant High Positive Rate 1 seconds 2

1 seconds 2

1 3% of RTP* with 6

4.

Power Range, Neutron Flux, 2.4 0.5 0

14% of RTP* with a time constant a time constant High Negative Rate 1 seconds 2

1 seconds 2

5.

Intermediate Range, 17.0 8.41 0

<25% of RTP*

<35.3% of RTP*

Neutron Flux 7

1 5

1 6 x 10 ces 6.

Source Range, Neutron Flux 17.0 10.01 0 1105 cps 7.

Overtemperature aT

9. 3

6.47 1.83 See Note 1 See Note 2

]

+1.24***

/.10

/. 65~

8.

Overpower AT 5.7 4-9tr -he-See Note 3 See Note 4 l

i 9.

Pressurizer Pressure-Low 5.0 2.21 2.0 11885 psig

>1874 psig

10. Pressurizer Pressure-High 7.5 4.%

1.0 12385 psig 12400 psig

11. Pressurizer Water Level-8.0 2.18 2.0

~<92% of instrument

<93.8% of instrument

=

span span

{

High

12. Reactor Coolant flow-tow

2. 5 1.38 0.6 190% of loop 188.8% of loop l

a minimum measured minimum measured 5

flow **

~

g

RTP = RATED THE7 % POWER

- Minimum Measurea Flow = 95.660 gpa

- - Two Allowances (*emperature ar-d pressure, respectively) 4 e

w -

+

ri.~

w

-er--

r

--a

em TABLE 2.2-1 (Continued) y REACTOR TRIP SYSTEM INSTRUNENTATION TRIP SETPOINTS r-V E

SENSOR 5

TOTAL ERROR i

FUNCTIONAL UNIT ALLOWANCE (TA)

Z (5)

TRIP SETPOINT ALLOWABLE VALUE Ci'i

13. Steam Generator h ter i

Level Low-Low

.2.12

/M a.

Vessel aT Equivalent 6.0 38-

-3 4 -

< Vessel aT

< Vessel AT

< 101 RTP fquivalent to Equivalent to Vessel'ai (Power 1) 10% RTP 92 RTP

/3.1%

Coincident with Steam Generator hter 20.2 17.58 2.0

> 20.2% of krrow

> 18.4% of Narrow Level Low-tow (Adverse Range Instrument Range Instrument i

~

J, Containment Environment)

Span Span and Containment Pressure -

2.8 0.71 2.0 1 1.5 psig i 2.0 psig Environmental Allowance Modifier F

OR 2

Steam Generator hter 14.8 12.18 2.0

> 14.8% of b rrow

> 13.0% of k rrow 3

tevelLow-Low (Normal Range Instrument liange Instrument Containment Environment)

Span Span

^

~

With a Time Delay, (t) 1 232 seconds 1 240 seconds u

1-- u- _

C t

TA8tE 2.2-1 (Continced) h REACTOR TRIP SYSTEM INSTRUNENTATION TRIP SETPOINTS E

StM50R TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA)

Z (5)

TRIP SETPOINT ALLOWARLE VALUE E4

13. Steam Generator Wter Level Low-Low (Continued) p.12

/M b.

10% RTP < Vessel aT 6.0 39-

-2:9-

< Vessel AT

< Vessel t,T Equivalent < 20% RTP Equivalent to Equivalent to

~,

Vessel AT (Power 2) 20% RTP 44s@5-RTP i

Coincident with 33.4%

Steam Generator Water 20.2 17.58 2.0

> 20.2% of Narrow

> 18.4% of Narrow m

I,,

Level tow-tow (Adverse Range Instroent b nge Instrument

{

Containment Enviroment)

Span Span and Containment Pressure-2.8 0.71

2. 0

< 1.5 psig

< 2.0 psig Environmental Allowance Modifier OR I

3 Steam Generator Water 14.8 12.18

2. 0

> 14.8% of Narrow

> 13.0% of k rrow tevel tow-tow (Nomal -

Range Instroent h oge Instrument Containment Environment)

Span Span g

With a Time Delay, (t)

< 122 seconds

< 130 seconds

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E CALLAWAY - UNIT 1 2-7

/cendment No /yJ 28

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E Amenoment No. /n 25 2-9 CALLAWAY - UNIT 1 1

l 4

8

4 e

TABLE 2.2-1 (Continued)

IA81E 100IAT10105 (Continued)

NOIE 3: (Continued)

Ks 0.0065/*F for T > I" and Ks = 0 for T e

=

T 1 ";

T Average Temperature. *f;

~

=

T" Indicated T, at RATED THEIUt41. POWER (Calibration temperature for AT l

=

Instrumentation, 1 588.4*F);

5 Laplace transfons operator, s 3; and

=

f(al) 2 0 for all al.

=

NOIE 4:

The channel's maximum Trip Setpoint shall not exceed its computed Trip'Setpoint by asore than

?

-h-3t of AT span.

~

5 3.0%

a t.

x E.

hu e

_.e_.p._._._._a_

,_m-

w LIMITING SAFETY SYSTEM SETTINGS EASES Intemediate and Source Ranee, Neutron Flux The Intermediate and Source Range, Neutron Flux trips provide core protec-tion during reactor startup to mitigste the consecuences of an uncontrolled rod These cluster control asse-bly bank withdrawal frcm a suberitical condition.

trips provide redundant protection to tne Low Setpoint trip of the Pcwer Range, The Source Range channels will initiate a P.eactor trip j

Neutron Flux cnannels.

at about 105 counts cer second unless manually blocked when P 6 becomes active.

The Intemediate Ran;e channels will initiate a Reactor trip at a current level equivalent to aporoxicately 25% of PATED THER$L POWER unless manually blocked

[

when P-10 becomes active.

Overtemeerature AT The Overtemperature AT trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and exihi power distribu-tion, provided that the transient is slow with respect to piping transit delays from the core to the temperature detectors (ht i ;,zt:,, and pressure is The within the range between the Pressurizer High and Low Pressure trips.

(1) coolant temperature to correct for Setpoint is automatically varied with:

temperature induced changes in density and heat capacity of water and includes dynamic compensation for piping delays from the core to the loop temperature l

With detectors, (2) pressurizer pressure, and (3) axial power distribution.

normal axial power distribution, this Reactor trip limit is always below the core Safety Limit as shown in Figure 2.1-1.

If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the Reactor trip is automatically reduced according to the notations in Table 2.2-1.

Delta-To, as used in the Overtemperature and Overpower AT trips, represents' This nomalizes each the 100% RTP value as measured by the plant for each loop.

loop's AT trips to the actual operating conditions existing at the time of measurement, thus forcing the trip to reflect the equivalent full power condi-tions as assumed in the accident analyses.

These differences in vessel AT can arise due to several factors, the most prevalent being measured RCS loop flow;.

greater than Minimum Measured Flows and slightly asyrnetric power distributions While RCS loop flows are not expected to change with cycle between quadrants.

life, radial power redistribution between quadrants may occur, resulting in Accurate determination of the small changes in loop specific vessel AT values.

loop specific vessel AT value should be made when performing the Incore/Excere quarterly recalibration and under steady state conditions (i.e., power distribu-tions not affected by Xe or other transient conditions).

Overpower AT The Overpower AT trip provides assurance of fuel integrity (e.g., no fuel pellet melting and less than 1% cladding strain) under all possible overpower conditions, limits the required range for Overtemperature AT trip, and provides l

CALLAWAY - UNIT 1 B 2-5 Amendment No. 28 N

..;. - ~..- - -. w _ _. -......

.. --. w x

.., w w

.~..~:--x

,_:,. aw,

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R-TABLE 4.3-1 C

REACIOR TRIP SYSTEM INSTRISENTAT10N SURVEILLANCE EqulREBENTS r-i G

f 1 RIP i

ANALOG AciWTING MDOES EOR CNAleIEL DEVICE

%dHICN i

E CilANKEL CHAleIEL OPERATIONAL OPERATICIIAL ACTUATION SURVEltlAIICE U

FUNCTIONAL UNIT CHECK CAtlBRATION TEST TEST 10GIC TEST IS REQUIRED 1.

Manual Reactor Trip N.A.

N.A.

.-, N.A.

R(16)

N.A.

1,2,3*,4*,5*l t

2.

Power Range, Neutron Flux a.

High Setpoint S

D(2,4),

Q(14)

N.A.

1, 2 M(3,4),

~

Q(4,6),

R(4,5) i s

b.

Low Setpoint S

R(4)

S/U(1)

N.A.

18##, 2 I

R 3..

Power Range, Neutron Flex, M.A.

R(4)

Q(14)

N.A.

M.A.

1, 2 liigh Positive Rate '

i Y

4.

Power Rmige, Neutron Flux, M.A.

R(4)

Q(14)

N.A.

M.A.

1, 2 j

High flegative Rate a

8 5.

Intermediate Range, S

R(4,5)

S/U(1)

N.A.

1###, 2 1

Neutron Flux t

i 6.

Source Range, Neutron Flux 5

R(4,5,12)

S/U(1),Q(9,14)

N.A.

2##, 3, 4, 5 I

7.

Overtemperature AT S

RM Q(14)

N.A.

1, 2 9

H.

Overpower AT S

R Q(14)

N.A.

1, 2

]

g 9.

Pressurizer Pressure-Low 5

R Q(14)

N.A.

1 l

l o

l 10.

Pressurizer Pressure-High 5

R Q(14)

N.A.

1, 2 j

t O

ji

11. Prer,surizer Water Level-High 5

R Q(14)

N.A.

I U

12.

Reactor Coolant flow-Low S

R Q(14)

N.A.

I l

t s

i

)

1 TABLE 4.31 (Continued) l TABLE NOTATIONS (10) Setpoint verification is not required.

e (11) Following maintenance or adjustment of the Reactor trip breakers, the f

TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verifi-6 cation of tr.e Undervoltage and Shunt trips.

(12) At least once per 18 months during shutdown, verify that on a simulated Boron Dilution Doubling test signal the nonnal CYC5 discharge valves will close and the centrifugal charging pumps suction valves from the RWST i

will open within 30 seconds.

(13) ""*?:!:1 CAI:F'JIT. : tail ital.:: tra PJ" typ;; 1;;;; 'h: r:tc. - he/ ele /.

i (14) Each channel shall be tested at least every g2 days on a STAGGERED TEST BASIS.

(15) The surveillance frequency and/or MODES specified for these channels in i

Table 4.3 2 are more restrictive and, therefore, applicable.

(16) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERASILITY of the Undervoltage and Shunt Trip circuits for the Manual Reactor Trip function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit.

(17) Local manual shunt trip prior to placing breaker in service.

l (18) Automatic Undervoltage Trip.

I i

t l

I CALLAWAY - UNIT 1 3/4 3-12a

/cenament No. U,,28,34 5

A

n n

TABLE 3.3-4 (Continued) n ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRtRIENTATION TRIP SETPOINTS 5

SENSOR h-TOTM.

ERROR TRIP ALLOWABLE 7

FUNCTIONAL UNIT ALLOWANCE (TA)

Z (5)

SETPOINT VALUE 6.

Auxiliary Feedwater (Continued)

d. Steam Generator Water

~

Level Low-Low (Continued)

1) Start Motcr-Driven Pumps 2.1)

/.45

a. Vessel AT Equivalent 6.0

-2de-

-2:t -

< Vessel AT

< Vessel aT

< 101 RTP Equivalent to Equivalent to

. t' Tessel'AT (Power-1) 10% RTP 44 RTP

/3'. 9'/o Y

Coincident with 37 Steam Generator Water 20.2 17.58 2.0

> 20.2% of Marrow

> 18.4% of Narrow Level Low-Low (Adverse liange Instrument Range Instrument Containment Environment)

Span Span and Containment Pressure -

2.8 0.71

2. 0 1 1.5 psig i 2.0 psig 1

Environmental Allowance

{

Modifier 3

8" i'.

E Steam Generator Water 14.8 12.18 2.0-

> 14.8% of Narrow

> 13.0% of Narrow Level Low-Low (Nomal Range Instrument lange Instrument O

Containment Environment)

Span Span With a Time _ Delay. (t) 1 232 seconds 1 240 seconds

-^ c x-

,c

p O

r TABLE 3.3-4 (Continued) g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMEMTATION TRIP SETPOINTS r-g-

SENSOR TOTAL ERROR TRIP ALLOWABLE FUNCTIONAL UNIT ALLOWANCE (TA)

Z (5)

SETPOINT VALUE 6.

Auxiliary Feedwater (Continued)

d. Steam Generator Water Level Low-Low (Continued)

1) Start Motor-Driven Pumps (Continued) 2.12

/.4 f

b. 101 RTP < Vessel AT 6.0 1 -2:9-

< Vessel aT

< Vessel ar u

Equivalent < 20% RTP Equivalent to' Equivalent to y

Vessel AT (Fower-2) 20% RTP

-24:M-RU 1

y 3T,1%

DE Coincident with 9

Steam Generator Water 20.2 17.58 2.0

> 20.2% of Marrow

> 18.4% of Narrow Level Low-tow (Adverse Kange Instrument Range Instrumect Containment Environment).

Span Span and l

[

Containment Pressure-2.8 0.71

2. ti 1

1 5 psig 2

1 0 psig Environmental Allowance

=

k Modifier a

5 Steam Generator Water 14.8 12.18 2.0

> 14.8% of Marrow

> 13.0% of Narrow Level Low-Low (Normal Range Instrument Kange instrument Containment Environment)

Span Span With a Time Delay, (t) 1 122 seconds

< 130 seconds

-g-m

^

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUE NTATION TRIP SETPOINTS nN t->

SENSOR E

TOTAL ERROR TRIP ALLOWABLE f

FUNCTIONAL UNIT ALLOWANCE'(TA)

Z (5)

SETP0lMT

_VALUE 6.

Auxiliary Feedwater (Continued)

d. Stem Generator Water Level Low-Low (Continued) i

2) StartoTurbine-Driven Pump 2.72

/. iS

a. Vessel aT Equivalent 6.0

-&38

-he-

< Vessel AT

< 101 RTP-Equivalent to Equivalent to g

Vessel AT (Power-1) 10% RTP M.G% RTP

/3.9%

.y Cotricident with m

21 Steam Generator Water 20.2-17.58 --

2.0

> 20.2% of Narrow

> 18.4% of ~ Narrow S

Level Low-Low (Adverse _

- Kange Instrument fange Instrument ContainmentEnvironment)

Span Span i

and-Containment Pressure -

2.8 0.71 2.0 g

Environmental Allowance

-< 1,5 psig.

-< 2.0 psig Modifier

s k

OR E

2 Steam Generator Water 14.8 12.18 2.0

>-14.8% of Narrow

> 13.0% of Marrow

?

Level Low-Low (Normal Range Instrument fange Instrument g

Containment Environment)

Span Span With a Time Delay, (t)

< 232 seconds

< 240 seconds a

w_.

. _. _. m 4_ a a. w

_. m

~

N

^

TABLE 3.3-4'(Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 3

SENSOR S

TOTAL ERROR TRIP ALLOWABt.E 7

FliMCTIONAL UNIT ALLOWANCE (TAl Z

(S)

SETPOINT VALUE E

6.

Ausliary Feedwater (Continued)

-s

d. Stt:an Generator Water Level Low-tow (Continued) 4

2) Start-Turbine-Driven Pump (Continued) 2.~n f.iS b.10% RTP < Vessel AT 6.0

-ih M

< Vessel AT

< Vessel aT i

Equivalent -< 20% RTP Equivalent to Equivalent to w1 Vessel AT (Power-2) 20% RTP J1.0!-RTP u4 Coincident with 23.1'4 y

Steam Generator Water 20.2 17.58 2.0

> 20.2% of Marrow

> 18.4% of Narrow Level Low-Low (Adverse Kange Instrument Range Instrument ContainmentEnvironment)

Span Span And g

Containment Pressure -

2.8 0.71 2.0 1 1.5 psig

< 2.0 psig m

Environmental Allowance I"

Modifier OR

?

Steam Generator Water

-14.8 12.18 2.0

> 14.8% of Narrow

> 13.0% of Narrow level Low-Low (Normal Range Instrument

'fange Instrument

="

Containment Environment)

Span Span With a Time Delay. (t) i 122 seconds

< 130 seconds

~.

~

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a

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I 6

4 ATTACHMENT ]

2

?

DRAFT'FSAR REVISIONS t

J FOR

-1 RTD' BYPASS-ELIMINATION-

.d q

s L

Table 3.11(B) 1 Sheets;41,J42, 431

.r

+

Table.3.11(B) Sheet'3-7 Figure 5.1-1 Slieet :11 d

Figure ~5.1-2 and Notes 1

(Sheets 1,-2)-

i Pages 5.4-24 through 5.4.

t

'i Insert A Insert B-s o,

. Pages 7.~2-13, 7.2-14,' 7.2-34,-7.'2.:

r

\\i.

f 3

' t' Thg r

t i

3

'7 i

's I

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-J CALLAWAT - SF TABLE 3.11(B)-3 (Sheet (1)

(4)

SEUIDN CATEGORT C

L M

H.

H 0

0 S

E COMPOENT LOCATION SPEC.

O L

C L

L NORM ACCIDENT ENYlROMENT NUMBER DESCRIFIION ROOM NUMBER NUMBER T

D A

B B

EN7 T F

R H

SF R.

BB-SBB05A RTD CL loop 1 2000 M 725 B

B D

Tl F3 E6 T2 T2 T2

1 BB-SBB05B RTD CL Loop 2 2000 M 725 B

B D

T1 F3 F6 T2 TZ T2 '

1

-1 BB-SBB05C RTD CL loop 2 2000 M 725 B

B

.D T1 F3 E6 T2 T2 T2 -

BB-SBB05D' RTD CL Ioop 2 2000 M 725 B

B D

T1 F3 F6 T2 T2 T2

1 BB-TBB03 Fressurizer 2000-M 713 I

I B

B D-71 F3 E6 T2 T2 T2

16 BB-T/C-1000[ RV Core Subcooling Monitor Thermocouples (50) 2000 W (ESE-43A)

A A

D Tl F3 F6 T2 T2 T2 11 BB-T/C-IXIX RV Core Subcool. Hon. Tbermoccup. Connectors (50) 2000 W (ESE-43B)

A A

D T1 F3

.F6 T2 T2 T2 11 l

2000 W 0-1034)

A A

'D T1 ' F3 E6 72 T2 T2 15

{'gre Subcool. Mon. TC Splices (50)

BB-7/C-I)DD[

BB-TE-0410Al RCS Hot Leg RTD4tearf-Temp Ele (InstaJ1ed Spare) 2201

-" (Z C) f 1o27 C

.A D

Tl D

E6 T2 T2. T2 8

, A2, A3 Conne etw BB-TE-0410A/VRCS Hot Leg RTD45eetf-Temp Elev(Installed Spare) 2201 2 :=-;) f to27

.C A

D Tl F3 F6 T2 72 T2 BB-TE-04103 RCS Cold Leg RTD4'eerf-Terp Ele (Insta) led Spare) 2201'

" :=-;)J /c37

'C A

D Tl F3 F6 T2 T2' T2 Connector BB-TE-04103 Id Leg RTD4fnetf-Temp EleV(Installed Spare) 2201 W (Z C) J 1827 C

A D

Tl F3 F6 T2 T2 T2 8

BB-TE-0411A1 RCS Hot-Leg RTD b ifold Temp Element Loop 1 2201

" (":51f 1827 I I

.C A

D Tl F3 - F6 T2 12 T2 16.

,A2, A3 Conneche BB-TE-04111F RCS Hot-Leg RTD b;if;1d Temp Element loop 1 V 2201

-" :I 0) f1027 I I

C A

D Tl F3 F6 T2 T2 T2 16 BB-TE-0411B RCS Cold-Leg RID S tifold Temp Element Loop 1 2201 N J1827 I I

C' A

D T1 F3 F6 T2 T2 T2 16 Connecer BB-TE-0411B RCS Cold-Leg RTD inif:STemi Element Loop IV 2201

" 'I C) f /027 I I

C A

D Tl F3 - F6 T2 T2 T2 16 BB-TE-0413A -RCS Bot-Leg Temperature Element (WR) Loop 1

-2201

-W (EE-8)

I I

A A

D Tl ' F3 F6 T2 T2 T2 16 BB-TE-0413A RCS Hot-Leg Temperature Element (E) loop 1 2201 W (E5E-6)

I I-A A

D Ti F3 F6 T2 T2 T2 16 '

BB-TE-04133 RCS Cold Leg Temp Element (E) Icop 1 2201:

W (ESE-6)

I I

A A

D Tl F3 E6 T2 T2 T2 16 BB-TE-0413B k'CS cold Leg Tenp Element-(WR) Loop l 2201 W (E-8)-

I I

A A

D T1-F3 3 F6 T2 T2 72 16-Rev. OL-3 6/89 m -

- _ _ n _,_- _.__._:__--

CALLAWAY - SF IABLE 3.11(B)-3 (Sheet 42)

(4)

SHUIDM CATEGRY C

L M

H H

0 0

S E

COMP 0ENT 10 CATION SPEC.

O L

C L

L NORM ACCIDENT ENVIR0lOIENT NUMBER (A2 A3 DESCRIPTION ROOM FJMBER N'JMBER T

D A

B B

ENT T P

R H

SF R

i BB-TE-0420Al RCS Bot Leg RTD Montf-Temp Ele (Installed Spare) 2201

" t r 5: I /o27 C

A D

T1 D

F6 T2 T2 T2 Y

> ^*r A3 Conneche BB-TE-0420AlvES Hot Leg RTD Meetf-Temp ElebtInstalled Spare) 2201

+4!E@ f /027 C

A D

T1 D

F6 T2 T2 T2 8

BB-TE-0420B ES Cold Leg RID Meetf-Temp Ele (Installed Spare) 2201

-W (G ;; I /o27 C

A D

T1 D

.F6 T2 T2 T2 conneefer BB-TE-0420B RCS Cold Leg RTDileetf-Temp ElevtInstalled spare) 2201

" C 0;- # /c27 C

A D

T1 D

F6

'I2 T2 T2 8

>A2A3 r

BB-TE-0421Af VRCS Hot Leg RID 41entfeM Temp Element Icop 2 2201

-" C 01-# /027 I I

C A

D

.71

-B F6 T2 T2 T2 16 oA%A3 Cennec4er BB-TE-0421Af ES Hot Leg RID MontfeMTemp Element loop 2 V 2201

" 'T 51-J /o21 I I

C A

D T1 D

F6 72 T2 12 16 BB-TE-0421B ES Cold Leg RTD L if;10 Temp Element Loop 2

-2201

-" 'r Sif /027 I I

C A

D T1 D

F6 T2 T2 T2 16 -

Con-sche BB-TE-0421B E S Cold Leg RTD i ni t:0 Temp Element Loop 2 v 2201

" C C V / day I I

C A

D T1 D

F6 T2 T2 T2 16

.BB-TE-0423A ES Bot Leg Temp Element (WR) Icop 2 2201 W (ESE-6)

I I

A-A D

T1 E'

E6 - T2 T2 T2 16 BB-TE-0423A. ES Hot Leg Temp Elesent (WR) loop 2 2201 W (E-8)

I' I

A A

D T1 D

F6 T2 T2 T2 16

'EB-TE-0423B ES Cold Leg Temp Element (WR) Loop 2 2201 W (ESE-6)

I I

A A

D T1 D

E6 T2 - T2 T2 16 2201 W (EE-8)

I I

A A

D T1 D

E6 T2 T2 T2 16 gldLegTempElement(WR) Loop 2 BB-TE-0423B 3B-TE-0430AiVRCS Bot Leg EID48eetf-Temp Ele (InstalJed Smre) 2201 4-fE* f /a27 C

A D

T1 D

E6 T2 T2 T2 8

Aa, A3 Conneehr BB-TE-0430Al#ES Hot Leg RID Meetf-Temp Ele tInstalled Spare) 2201 4 (= 57f /s27 C

A D

T1 D

F6 T2 T2 T2 v

BB-TE-0430B. ES Cold Leg RTD 41eerf-Temp Ele (Installed Spare) 2201

" (= ;)/ /027 C

A

.D T1 D

F6 T2 T2 T2 Conseedor BB-TE-0430B ES Cold Leg RTD4teerf-Temp Ele (Installed Spare) 2201

-W C-3) / /a27 C

A D-Il D

F6 T2 T2 T2 8

v

, A2, A3 BB-TE-0431A1 *ES Hot Leg RID h;Ivid Temp Element loop 3 2p1

-4 ( = -;;I(o2-1 1.

I C

A D

T1 D

E6 T2 T2 ' T2 16 A1,A3 Cen~*cter BB-TE-0431A'l# ES Hot Leg RID inifcid Temp Element loop 3 7 2201 W C C J'to27 I I

C A

D T1 D

E6 T2 T2 T2 16 BB-TE-0431B KS Cold Leg RID-ManifeM Temp Element Loop 3 2201-

-" 'C 5),fle27 I I

C A

D T1 D

F6 T2 T2 T2 16 Csnnec4er BB-TE-0431B ' ES Cold Leg RfD

.inld Temp Element loop 3 v, 2201

-" C 0F # te2 7 I I

C A

D T1 D

F6 ' T2 T2 72 16 -

Rev. OL-2 6/88 i

+

q

~

cu,

Qj

\\

h a

q CALLAviAI - SP TABLE 3.11(B)-3 (Sheet 43)

(4)

SEUTDI CATEGORY C

L M

H H

0 0

S E

COMPOEE IOCATION SPEC.

O L

C L

L. )0RM.

ACCIDEE ENVIRONMENT NUMBER DESCRIPTION ROOM NUMBER NUMBER T

D A

B B

EN7 7 P

R H

SP R

BB-TE-0433A RCS Bot Leg Temperature Element ( E) Loop 3 2201 W (E-8)

I I

A A

D.

Il D

E6 T2 T2 T2 16 BB-TE-0433A RCS Hot Leg Temperature Element (WR) Icop 3 2201 W (ESE-6)

I I

A A

D T1 B

F6

.T2 T2 T2 16 BB-TE-0433B RCS Cold Leg Temperature Element (R) Icop 3 2201 W (ESE-6)

I I

A A

D T1

.F3 E6

.T2 T2 T2 16 BB-TE-0433B RCS Cold Leg Temperature Element (WR) Loop 3 2201 W (E-8)

I I

A.

A D

T1 D

E6 T2 T2 T2 16

, A2;M BB-TE-0440AIV RCS Hot Leg RID 48enf-Temp Ele (Installed Spare) 2201

" 23:4) # /c27 C

A

.D T1 D

F6 T2 T2 T2

, A1, A.1 Connec k BB-TE-0440Al' RCS Hot Leg RTD henf-Temp Ele (Installed Spare) 2201

" ::E4) f /027 C

A D.

T1 D

E6 T2 T2 T2 8

V BB-TE-0440B RCS Cold Leg RTD Memf-Temp Ele (Insta Spare) 2201

-" != 5) f /82'7 C

A D

T1 D

F6 T2 T2 Cenn BB-TE-0440B Id Leg RID 48 emf-Temp Ele (Installed Spare) 2201

-W :5 0PI /027 C

A~

'D, T1 D

F6 T2 T2 T2-8 v

2K

" (C Orfle27 I 1.

C A

D n

D E6 T2 T2 T2 16 BB-TE-0441Al'RCS Hot Leg RID 2:iOM Temp Element loop 4kn* w)l.

, A2,M V

2201

-" =-51-f /027 I

.I C

A D

T1 D. F6 T2 T2 T2 16,

BB-TE-0441Al' RCS Hot Leg RID 5: ISM Temp Element Loop 4 BB-TE-0441B ' RCS Cold Leg RTD Jiaeffeld Temp Element loop 1

" CZ-5)f/827 I I

C A

D T1 D

E6 T2 T2 T2 16 BB-TE-0441B ' RCS Cold Leg RID llanafel4 Temp Element Icop 4 Y 2201 Y(Z Cl J/027 I I

C A

-D T1 D

F6 T2 T2 - T2 16 BB-TE-0443A RCS Hot Leg Temperature Element (WR) Icop 4 2201 W (ESE-6)

I I

A A

.D T1 D

.F6 T2 72 T2 16

~ 201-

- W (E-8)

I I

A A

D T1 D

E6 - T2 T2 T2 16 '

2 BB-TE-0443A RCS Hot Leg Temperature Element (WR) Icop 4 BB-TE-04433 RCS Cold Leg Temperature Element (WR) Icop 4 2201 W (ESE-6)

I I

A A

D T1 F3 F6 T2 72 T2 16 BB-TE-0443B ' RCS cold Leg Temperature Element (WR) Icop 4 2201 W (BE-8)

I I

A A

D T1 B

E6 T2 T2 T2_

16 BB-TE-1313 ' RVLIS Head 1spulse Line Temp Element 2000 W (ESE-42A)

A A.

D T1 D'

E6 T2 T2 T2 15 BB-TE-1314 RVLIS Head Impulse Line Temp Element 2000 W (ESE-42A)

A A

D. T1 D

E6 TZ T2 T2 15 BB-TE-1317 RVLIS Scal Impulse Line Temp Element 2000 W (ESE-42A)

A A

D ' T1 B

F6 T2 T2 T2 15 BB-TE-1318 RVLIS Seal' Impulse Line Temp Element 2000 W (ESE-42A)

A A

D T1 D

F6 T2. T2 T2 15 Rev. OL-2 '

6/88-

=

i i

I-CALLAWAY - SP l

f j

TABLE 3.11(B)-7.-(Sheet 3)

,l i '.i

), ?

a

}

SPECIFICATION-DESCRIPTION C

.)

b; 1

M236' Motor-Operated-Butterfly Valves-(1) j M237-1 But'terfly Valves (Limitorque) (OC) l at Butterfly Valves (Limitorque) (IC).

M23.7-2 M237-3 Butterfly Valves =(Bettis)_

}.

M612 Room Coolers M619i3

-Hydrogen Mixing Fans A

M620

-Containment Cooling-Fans M627A Dampers S

M628=

Steam Isolation Valves M630 Feedwat r Isolation Valves S/021 Afarrow

tnfe KCf A7hr

~

W(AE2)

Large Pump Motors

}.

0 W(AE3).'

Canned Safety-Related Pump Motors,(1)

W(ESE-01A)-1 Pressure Transmitters (A) (Barton-IC) i W(ESE-01A)-2 Pressure Transmitters'(A) ( Barton-OC )'-

W(ESE-01B)

. Pressure Transmitters (A)-(Veritrak)

W(ESE-010)-1 Pressure Transmitters (A)-(Tobar-IC) a W(ESE-01C)-2 Pressure Transmitters (A) (Tobar-OC)

W(ESE 03A)

D.P. Transmitters-(A) (Barton)

[-

7 W(ESE-03C)

D.P. Transmitters (A) (Tobar)-

W(ESE-04A)

D.P. Transmitters (B) (Barton) j' W(ESE-04D)

D.P. Transmitters (B) (Rosemount) i

' - W(ESE-05)

RTC; (bypass)

.W(ESE-06)

RTDs H(ESE-08)

Excore Neutron Detectors (power range) (1) x-l i; i f Rev. OL-0.

6/86

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&<.t,Jin. l j - mq/y,*.. 4 ~4: 5) G.,h I 3,..e.tv . sic,,ou n.a.<, N. ; 't*"' * '6 REACTOR i

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7. {...... 3 I

I J gpg esLM - J g i .TJC.5...$..... .P j FIGURE s.t.1 j 2 ~ '"'O* REACTOR COOLANT SYSTERI k j ,. g.".a tas-220001(OP3) as snest t y i i ...... 10 0 V 200/OS'- Q l ^ l r 8 TEAM GENERATOR 47 47 47 g, %9 / / / /-l' 48Q46 4/ I / / / i 5f ) 4/ / / / / / y RK C9(Oty(i p iege h Y REACTOR PRES $URIZE R COOLANT PUMP 9 e (b + g

A w,,

SAS Al g ET/ CvCs EMERGENCY \\ LETDOWN REACTOR 5 COOLANT 9 / C RMWS RMW LOOP 1 ] WPS (L) g d ' ' I f "6' RCDT HX /RT[ cop'Lp'M IFOp ^Z = p STE AM GENER ATOR "y' RCDT PUMP 9 >, [9; 9; CONTAINMENT SUMP NOTES THis OLAGR AM l$ A SIMPLIFICATION OF THE SYSTEM INTENDED TO FACILIATE THE UN PROCESS. FOR DETAILS OF THE PIPING, VALVES, INSTRUMENTATION, ETC. REFER TO THE EN00MEER F LOW On AGR AM. REFER TO PROCESS FLOW DIAGRAM TABLES FOR THE CONDITIO [ t i i ) SI APERTURE g CARD ooo223i Also Available On Aperture Card D STE AM GENE R ATOR t'i' 4 t'A'#4 i R9r-Y M 9M9 l N ///// Q 7 7,7 7 7, / 4 / y /TD C,0lD M FOLD J4 == PUMP SIS BIT SIS Bli / /N ! T sis ACCUM 15 24 sls ACCUM 1 g R PS - I NEL ? V 6 33 M' N \\ Sit 81 RHRPMPS $18 BIT 815 BIT AN LOOP 4 CH NG RTgCOLpEG[NI LD, // ./ / / / /> / RTD OTL 'G 1 STE AM GENE R ATOR / / [{$ k @8@ ~~ t',, U P F LLOW NG AGES) ETHE Rev. 000 n9ng gg,, US "3 *"T* / CALLAWAY PLANT FIGURE 5.1-2 REACTOR COOLANT SYSTEM PROCESS FLOW DIAGRAM

j D _D Y N..D!Q_$*~05

^ ' a CALLAWAY - SP NOTES TO FIGURE 5.1-2 Mode A Steady State Full Power Operation Pressure Temperature II} Flow Location Fluid (psig) (F) gpm lb/hr(2 ) Volume p-l 1-Reactor 2,235.0 616.9 110,250 36.7125 coolant 2 Reactor 2,233.1 616.9 110,150 36.6792 coolant 3 Reactor 2,195.9 559.1 98,930 36.6792 y (' coolant 4 Reactor 2,192.4 559.1 99,100 36.7403 4 L coolant i-5 Reactor 2,285.1 559.4 99,000 36.7428 coolant 6 Reactor 2,283.2 559.4 98,900 36.7125 coolant ,(3) ,mm m .m.... .,.vm.. v v., .vu v.vsss ___,_.m O Rcacter 2,000.1 500.0 100 0.0271

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R;;ctcc 2,100.2 007.0 ,1^^ 0.0700 -- 0 0 01.... 10-te-Reactor See Loop #1 Specifications hr coolant 19 Reactor See Loop #1 Specifications 2f coolant (- 28 Reactor See Loop #1 Specifications 3G? coolant 37 Reactor 2,285.1 559.4 1.0 0.0004 coolant 38 Reactor 2,285.1 559.4 1.0 0.0004 coolant 39 Reactor 2,235.0 559.4 2.0 0.0008 coolant %~. Rev. OL-0 I 6/86 CALLAWAY - SP NOTES TO FIGURE 5.1-2 (Sheet 2) 97 E# Pressure Temperature I1) Flow lb/hr(2) . Volume Ltcation Fluid (psig) (F) gpm 720 .i 40 Steam 2,235.0 652.7 1,080 41 Reactor 2,235.0 652.7 coolant 42 Reactor 2,235.0 652.7 2.5 0.0008 .g. Coolant [ 43 Reactor 2,235.0-652.7 2.5 0.0008 coolant gg 44-Steam 2,235.0 652.7 0 0 45 Reactor 2,235.0 (652.7 0 0 Minimize coolant 46 N 3.0 120 0 0 2 J. 47 Reactor 2,235.0 (652.7 0 0 Minimize-2' coolant o 48 N 3.0 120 0 0 2 f,E 49 N-3.0 120 0 0 2 g. 5 0.- N 3.0 120 450 u y-2 j 51 Pres-3.0 120 1,350 }. surizer 1-relief tank W water At ?. 52 Steam /H2 2,235.0 559 0 0 y j 53 Reactor 3.0 120 0 0 coolant

(

} 54 Reactor 50 170 0 0 1 coolant 't, i 4 At the conditions specified. ('1 ). s 6 L; -(2)i -X-10. ? (3)' Location point--refcrc to the threc 1" cernnectionc on the hot leg. q (j). Lec& tion point refers to the 2" connection en the cold leg. };\\ ' ,.) y 1-Rev. OL-0 6/86 f CALLAWAY - SP Class 1 formula of Paragraph NB-3641.l(3) with an allowable (y stress value of 17,550 psi. The pipe wall thickness for the (

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444 5& 4 4 4 WW A & E44 4w w e Signals from the temperature detectors are used to compute the -rea,ctor coolant AT (temperature of the hot leg, T minus the

hot, temperature of the cold leg, Tcold) and an average reactor coolant temperature (Tayg).

The T f r each loop is indi-avg cated on the main control board. 5.4.3.3 Design Evaluation Piping load and stress evaluation for normal operating loads, seismic loads, blowdown loads, and combined normal, blowdown, and seismic loads is discussed in Section 3.9(N). Rev. OL-0 5.4-27 6/86 INSERT A One hot leg and one cold leg temperature reading are provided from each coolant loop to use for protection. Narrow range, thermowell-mounted Resistance Temperature Detectors (RTDs) are provided for each coolant loop. In the hot. legs, sampling scoops are used because the flow is stratified. That is, the fluid temperature is not uniform over a cross section_of the hot leg. One dual element RTD is mounted in a thermowell in each of the three sampling scoops associated with each hot leg. The scoops extend into-the flow stream at locations 120* apart in the cross sectional plane. Each scoop has five' orifices which sample the hot leg flow along the leading edge of the scoop. Outlet ports are provided in'the scoops to direct the sampled fluid pest the sensing element of the RTDs._ One of each of the RTD's dual elements is used while the other is an installed spare. Three -j readings from each hot leg are averaged to provide a hot leg reading for that loop. One dual element RTD is mounted in a thermowell associated with each cold leg. No flow sampling is needed because coolant flow is well mixed by the reactor coolant pumps. One'RTD element is used while the other is an installed spare. The thermowells are pressure boundary parts which completely enclose the RTD. They have-been shop hydrotested to 1.25 times the RCS design pressure. The external design pressure and temperature are the RCS design temperature and pressure. The RTD is not part of the pressure boundary. The scoop, thermowell, and thermowell/ scoop assembly have been analyzed to the ASME Boiler and Pressure Vessel Code,Section III, Class 1. The effects of seismic and flow-induced loads were considered in the design. 5 1 CALLAWAY - SP h b. Blocks of reactor trips at low power Interlock P-7 blocks a reactor trip at low power (below approximately 10 percent of full power) on a low reactor coolant flow in more than one loop, 3 reactor coolant pump.undervoltage, reactor coolant pump underfrequency, pressurizer low pressure or F pressurizer high-water level. See Figure 7.2-1 i (Sheets 5 and 6) for permissive applications. The low power signal is derived from three out of four power range neutron flux signals below.theLsetpoint in coincidence with two out of two turbine impulse i chamber pressure signals below the setpoint (low-plant load). See Figure ~7.2-1 (Sheets 4 and 16) for w-h' i 'the derivation of P-7. s, j The P-8 interlock blocks a reactor trip when the i plant is below approximately 50 percent of full power, on a low reactor coolant flow in any one loop. c]. The block action (absence of the P-8 interlock signal) occurs when three out of four neutron flux power range signals are below the setpoint. Thus, below .( the P-8 setpoint, the reactor has the capability to -f operate with one inactive loop and trip will not ?! occur until two loops are indicating low flow. See i r Figure 7.2-1 (Sheet 4) for derivation of-P-8 and j ( Sheet 5 for applicable logic. s l Interlock P-9 blocks a reactor trip _following a

j turbine trip below 50 percent' power.

See Figure q 7.2-1 (Sheet 16) for the implementation;of the P-9 la interlock and Sheet 4 for the derivation of P-9. ,3d b-7.2.1.1.4 Coolant Temperature Sensor Arrangement j fNSEW 8 ~+ The hot and-ccid leg rcaistance temperaturc detectors arc d 'inscrted into reactor coolant-bypacc loopc. .. bypacc loop ^ from upstrcam of thc stcam generator tc downstrcam cf the l[ steam gener* tor-is-used-for-the-hot-leg-resistance temperaturc F 3 detectors, and a bypass loop ^from dcunstrcam of the reacter E coolant pump to upstream of the pump-is used for t,hc' cold leg ~ j' rcaistance tcapcraturc dctcctors. Octh bypass loops arc

)

inside the cont-ainment. The recictance temperature detector: l arc located in-manifolds and arc dircctly inserted into the j' rcactor coolant bypass 1ccp ficw without therscwells. Thcrac- ?! - wellc are not--used in crder to miiiiminc the-detector -thermal d lag. The bypass =-arrangement' permits replacement cf dcfcctivc l1 tcapcreturc cicments whilc the-plant-is at-hot shutdcun withcet li draining cr deprecsuricing'the reacter coolant locpc. j Three campling probes arc installed in a cross-sectional plane j-of cach hot leg at appronimete-ly 120-d gree intervalc. Each i c2 of th; sampling probes, which extend sever &1 inches into the J. j= Rev. OL-0 ] 7.2-13 6/86 INSERT B One hot leg and one cold leg temperature reading.are provided from each coolant loop to use for protection. Narrow range, thermowell-mounted Resistance Temperature Detectors (RTDs) are provided for each coolant loop. In'the hot lege, sampling scoops are used because the flow is stratified. That-is, the fluid temperature 11s not uniform over a. cross section of the hot leg. One dual element RTD is mounted in a thermowell in each of the three sampling scoops _ associated with each' hot leg. The scoops extend into'the flow stream at locations 120 apart in the cross sectional _ plane. Each scoop has five orifices-which sample the hot leg flow along the leading edge ofLthe scoop. Outlet ports are provided in the scoops to direct-the sampled fluid past the sensing element of the RTDs. One of each of the RTD's dual - elements is used while the other is an instelled spare. Three readings from each hot leg are averaged to provide a hot leg reading for that loop. One dual element RTD is mounted in a thermowell associated with each cold leg. No flow sampling is needed because coolant flow is well mixed by the reactor coolant pumps. As le the case with the hot leg, one element is used while the other is an installed spare. Certain control signals are derived from individual protection channels through isolation cards. The isolation cards are classified as a part of the protection system. The rod control system uses the auctioneered-(high) value of four_ isolated T-AVG l signals. The RTDs are a fast responso design which conform to the applicable IEEE standards and 10 CFR 50.49 requirements. I-f CALLAWAY - SP -het leg ceclent stream, contains five inlet erifices distributed .c -along-its icngth. In this way, a total of 15 locations in the O}l 6 -het-leg strcam-are-eempled, providing a representative ecclant -tempcrature-measurcment. The 2= inch di-ameter pipe lecding tc the recictanoe-temperatur-e-<letectere-mani-fo-1d-previdec mixing -of the sempics to give represcatative temperetura measurement. -HEare has becn-taken to distribute the ficw cvenly among-the ---five cr-ifices of caeh-prob; by cffectively restricting -the -ficw through-the crifices. This has-been done by designing a cm ller evera14-eri-fice flow-area - than t4;at of the ccm.cn flow i -channel within-the probc. -This-arran;;;cnt has hise been - cpplied tc the f4ow-tranesbica frem the three probe flew ch:nnel to-the-pipe Iceding tc the temperature element-manifcid. -The total f4ew-arca of the:c channels-haer-thereferc, 'be n (I #&g --designed-to be less-than-that-ef the 2-inch--pipe connecting the probes--te the-manifeld. The celd leg reactor coolant flow is well mixed by the reaetor i cociant pump, t-hereby-eliminating any ccid -Icg tcapcreturc ( cpatial dependence. Therefere, the ccid leg c:mple-ic taken i dit=ctly Irvm 2-inch pipe t&p off the cold leg downstrcem of a j rhc pump. t j 7.2.1.1.5 Pressurizer Water Level Reference Leg Arrangement The design of the pressurizer water level instrumentation f. ( employs the usual tank level arrangement, using differential (b 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 L' The analog system consists of two instrumentation systems - the process instrumentation system and the nuclear instrumentation system. L Process instrumentation includes those devices (and their j interconnection into systems) which measure temperature, f [! pressure, fluid flow, fluid level as in tanks or vessels, and L occasionally physiochemical parameters, such as fluid con-ductivity or chemical concentration. Process instrumentation specifically excludes nuclear and radiation measurements. The process-instrumentation includes the process measuring devices, power supplies,- indicators, recorders, alarm actuating devices, e controllers, signal conditioning devices,-etc., which are necessary for day-to-day operation of the NSSS, as well as for monitoring the plant and providing initiation of plant pro-tective functions. l. The primary function of nuclear instrumentation is to protect if>y the reactor by monitoring the neutron flux and generating L appropriate trips and alarms for various phases of reactor Rev. OL-0 l 7.2-14 6/86 CALLAWAY - SP i Any reactor trip will actuate'an alarm and an annun-ciator. Such protective actions are indicated and g3 identified down to the channel level. Alarms and annunciators are also used to alert the operator of deviations from normal operating conditions so that he may take appropriate corrective action-to -avoid a reactor trip. Actuation of-any. rod stop or trip of any reactor trip channc1 vill actuate an alarm. u. System repair i ~ The system is designed to facilitate'the recognition, ga r location, replacement, and repair of malfunctioning nie components or modules. Refer-to the discussion in item-j above. 7.2.2.3 Specific' Control and Protection Interactions 7.2.2.3.1 Neutron Flux t Four power range neutron flux channels are provided for overpower z protection. An isolated auctioneered high. signal is derived by auctioneering the four chan'lels for automatic rod control. If any channel fails in such a way as to produce a-low output, that channel'is incapable of proper overpower protection but 6)b will not cause control rod movement because of the: auctioneer. S!I I j Two-out-of-four overpower trip logic will ensure.an' overpower _ a. trip if needed, even with an independent failure in~another channel. j In addition, channel deviation signals in the control system 4 _ will give an alarm if any neutron flux channel deviates significantly from the average of the flux signals. Also, the control system will respond only to rapid changes in indicated neutron flux; slow changes or drifts are compensated'by the temperature control signals. Finally, an overpower signal from any nuclear power range channel will block manual and-autopatic rod withdrawal. The setpoint forLthis rod stop is L below the reactor trip setpoint. 7.2.2.3.2 Coolant Temperature ,j narrow nange C W'" B '#"j" ' The accuracy of theVres11tance temperature -detector (RTD) by; -- Ice; temperature measurements is demonotrated during plant.startup tests by comparing temperatu ce measurements from J/e/e ' ' ' ' ;7 r : 1 :; RTDs with one another as well as with the temperature measurements obtained from theVRTD located:in the ~ hot leg and cold leg piping of each loop. The comparisons are done with the reactor coolant system-in an isothermal condition. The.linearity of'the AT measurements obtained from the hot leg-and cold ' leg typnrr 12:p RTDs as a function of plant power is () also checked during plant startup tests. The absolute value Rev. OL-C 7.2-34 6/86 t ] CALLAWAY - SP of AT versus plant power is not important, per se, as far as reactor protection is concerned. ~ Reactor trip system setpoints are based upon percentages of the indicated AT at nominal full power rather than on-absolute values of AT. This is done to -account for loop differences which are inherent. The percent AT scheme is relative, not absolute, and therefore provides better protective action without the requirement of absolute accuracy. For this reason, the linearity of the.4T signals.as a function of power is of importance. rather than the absolute values of the AT. As part of the plant startup tests,. the 'yr-1::p RTD signals will be compared with the core exit thermocouple signals. Reactor control is based upon signals derived from protection ( system channels after isolation by isolation amplifiers such that no feedback effect can perturb the protection channels. Since control is based on the. average temperature of the loop with the_ highest temperature, the control rods are always moved based upon the most pessimistic temperature measurement with respect to margins.to DNB. A spurious low average temper-ature measurement from any loop temperature control channel will cause no control action. A spurious high average temper-ature measurement will cause rod insertion (safe direction). i Individual 10w ficw clar:0.with-individual ctatus light for cach rcactor coclant-1 cop bypacc ficw arc provided On the : in } centrol board. The clar and ctatuc lightc provide the operater-- ( vith in:Odictc indication-cf a lcw 4-Icw condition in the bypass loops associated wi-th-eny-reseter coolant-loop. 1, 1 Lccel indicatcra arc provided to monitor total flew thrcugh --the---RTB-bypacc manifc1dc - for cach loop. The indicatcrc are Icceted inside the containment but arc acccasible during pcuer i ~ [ --epera tions. Flow will bc lccal-ly monitored; Prior tc rcat-oring temperature channcic tc normal a. service fol-lowing reopening cf hypace loop ctop i valves whenever a bypacc loop Jeas-been cut of cer-v-ice-b. On a periodic-basic c. Eclicwing-any bypase-leep 10w ficw clare-feec abcVe) In affiti__, Shannel deviation signals in-the control system will give an alarm if any temperature channel deviates signi-ficantly from the auctioneered.(highest) value. Automatic rod withdrawal ~ blocks and turbine runback (power demand reduction) will also occur if any two out of the four overtemperature or overpower AT channels indicate an adverse condition. 1 _d + Rev. OL-0 7.2-35 6/86 i,

ML20034A105

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